ML20112H384

Forwards Description of Planned Inservice Insp & Testing Program for Next 40-month Period & Three Sets of Modified Piping & Instrumentation Drawings,Including Applicable Components,Per 760424 Ltr

ML20112H384
Person / Time
Site:	Hatch
Issue date:	08/03/1978
From:	Whitmer C GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8501170117
Download: ML20112H384 (1)

Text

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Chas. F. Whitmer bC()l'h h()WCf

[,[,$.).)'(" August 3, 1978 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PIAT UNIT 1 IN-SERVICE INSPECTION Gentlemen:

Georgia Power Company hereby submits the information requested in your letter dated April 24, 1976, as supplemented by letters dated November 26, 1976, and January 5,1978, concerning in-service ti.spection und testir.; requitants fw .SME Cod,. Class 1, ?, and 3 /muis alent) components at Plant Hatch Unit 1. The enclosed inrormation hol:Wes:

(1) a description of our planned in-service inspection and testng pto-gram for the next 40-month period, and (2) three sets of modified piping ,

and instrumentation drawings which include the applicable components.

Proposed changes to the Technical Specifications which conform to the in-spection and testing program will be submitted by mid-August, 1978.

In accordance with 10CFR50.5Sa(g), the in-uervice inspection cu-;

testing program has been prepared with the intsat to meet, to the degree practical, the requirements of the 1974 Edition of Section XI of the ASME Code, including Addenda through Su=mer, 1975. The program identifies those components we have determined to be subject to ASME Section XI Code requirements and notes those code requirements that have been determined to be impractical. ASME Section XI Code relief is requested pursuant to 10CFR50.55a(g)(6)(1) for those code requirements whose implementation is impractical. The appropriate justification is provided for these ex-ceptions. It should be emphasized that the Unit 2 inspection and testing program, as described in the Unit 2 FSAR, was used as a basis for the preparation of the Unit 1 program.

We wish to call particular attention to the valve testing portien of the program. You will note that code relief is requested for sevcral

- valves to allow leakage testing in the reverse direction based on the requirements of the containment leak rate test program. The containmeat

• leak rate test program referred to is that which is currently being pre-pared in accordance with our letter dated November 16, 1977. The program will be submitted in the near future and will address Type C reverse leakage testing. As a point of clarification, certain plant modifications will need to be made in order to facilitate leak rate testing. Such changes will be 8501170117 780803 PDR ADOCK 05000321 G PDR f

a

., %6 GeorgiaPower A

'( ) Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission August 3,1978 Page 2 identified in the leak rate test program submittal. In order to be consistent with the information that will be contained in that submittal, the valve testing program has been prepared based on the NRC approval and completion of those modifications. Therefore, some discrepancies may exist in the valve testing program as described and actual implementatic until those modifications are approved and completed.

A final note should be made about the inspection and testing prograr.

The next 40-month period begins April 30, 1979. Also, the next refueling outage is tentatively scheduled for Spring,1979, and may overlap the be-ginning of that period. However, the inspection t<ill be conducted under the present 40-month program. The initial in-service examinations and testing under the second 40-month program will be conducted on the fo?.lew-ing inspection. Such action is allowable under the provisions of ASME Section XI and 10CFR50.55a.

Yours very truly, 2 . )

jas. .L tmer WEB /ab Enclosure 1

l sc: Mr. R. A. Thomas George F. Trowbridge, Esquire l

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i EDWIN I. HATCH NUCLEAR PLANT UNIT 1 i

RESPONSE TO l THE PROVISIONS OF L,

10 CFR 50.55a(g)

" INSERVICE INSPECTION PROGRAM" i

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l.0 Introduction . . . . . . . . . . . . . . . . 1-1 4

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1: 2.0 Inservice Inspection for l l Code Class 1 Components. . . . . . . . . . . 2-1 i

j_ 3.0 Inservice Inspection for '

Code Class 2 Components. . . . . . . . . . . 3-1 i .. -

4.0 Inservice Inspection for -I Code Class 3 Components. . . . . . . . . . . 4-1

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5.0 Inservice Testing of Pumps . . . . . . . . . .

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t 6.0 Inservice Testing of Valves. . . . . . . . . .

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1.0 IflTRODUCTI0ft

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V 1.1 General This document describes the new Inservice Inspection Program for Edwin I. Hatch fluclear Plant, Unit tio.1. The original ISI program for Hatch-1 was prepared in accordance with the ASME Boiler and Pressure Vessel Code, ,

1971 Edition, including the Summer 1972 Addenda for Class 1 components.

Class 2 components were limited to the Main Steam and Turbine Steam Bypass Systems. Class 2 components were scheduled for examination in accordance with the Winter 1972 Addenda of Section XI.

The new inservice inspection plan is an upgrading of the program to meet the examination requirements of the 1974 Edition of Section XI, including Addenda through the Summer,1975.

1.2 Effective Date The new ISI plan shall go into effect at the start of the second 40-month period of plant commercial operation. The effective date is April 30, 1979.

1.3 Scope This document is a description of the ISI program for Unit 1 of Plant Hatch.

The programs for Class 1, 2, and 3 component examinations and for pump and valve surveillance testing are included.

1.4 Component Upgrading All plant components have been reviewed to determine the appropriate classifi-cation for inservice inspection. Regulatory Guide 1.26 was used for guidance in determining component classifications.

It must be noted that the classification of components as ASME Class 1, 2, or 3 equivalent for inservice inspection does not imply that the com-ponents were designed in accordance with ASME requirements. The component design codes remain as stated in the. FSAR.

1.5 Subsequent ISI Plan Revisions In accordance with the existing regulations of 10CFR50.55a, the inservice examination program for Class-1, 2, and 3 components will be reviewed near the end of each 40-month interval. At that time the plan will be modified as required to bring it into compliance with the latest f1RC-approved version of Section XI. The inservice testing program for pumps and valves will be similarly reviewed and modified every 20 months.

1.6 Responsibility Georgia Power Company bears the overall responsibility for the performance of the inservice examinations. Certain non-destructive examinations will

- be performed by a qualified examination agency. The results of such examina-C) tions will be reported to Georgia Power Company for final evaluation and disposition.

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1.7 Records g

'-; Records and documentation of all information and inspection results, which provide the basis for evaluation and which facilitate comparison with re-sults from previous and subsequent inspections, will be maintained and available for the active life of the plant in accordance with Section XI, IWA-6000, 1.8 Methods of Examination The method of examination planned for each area is delineated.in subsequent sections . Personnel performing NDT examinations will be trained in accord-ance with the American Society for Nondestructive Testing (ASNT) " Recommended ~

Practice SNT-TC-1 A, Supplements and Appendices", as applicable for technique and method used.

1.8.1 Ul trasonic It is anticipated that most volumetric examinations will be performed ultra-sonically. Examinations will be conducted in accordance with the require-ments of ASME Section XI and Section V as appropriate.

1.8.2 Radiographic Radiographic techniques will be used to supplement UT as required.

f x, 1.8.3 -Liquid Penetrant

\~ l' Dye penetrant examinations will be performed whenever a surface examination is required on non-magnetic piping.

1.8.4 Magnetic Particle

, Magnetic particle tests will usually be used when surface examination of carbon steel components is required. .

1.8.5 Visual

.. _. A visual (VT) examination is employed to. provide a report of the general condi-tion of the part, component, or evidence of leaking.

1.9 - Repair Procedures Repairs to the pressure retaining boundary of ASME Class 1, 2, or 3 (equiva-

' lent) components.will be performed in accordance with IWA-4000 by utilizing Georgia Power Company approved procedures which generally comply with the code applicable to the construction of the component.

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,, 2.0 INSERVICE INSPECTION FOR CODE CLASS 1 COMP 0NENTS Table 1 provides a tabulation of the Class 1 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Summer 1975. These components will be inspected in accordance with the requirements of Subsection IWB to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examina-tion. Where release from the inspection requirements of Subsection IWB is requested, information is provided which identifies the applicable Code requirements, justification for the release requested, and the inspection method to be used as an alternative. Table IWB-2600 items not applicable to the Edwin I. Hatch Nuclear Plant-Unit 1 have also been listed and identified in the interest of completeness. Items applicable to pressurized water reactors only, such as steam generators and pressurizers, have been omitted entirely.

Some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased.

However, these components will be inspected in accordance with the require-ments of Subsection IWB to the extent practicable. The repair procedures of IWB-4000 will be applied to those components constructed to Section III of the ASME Code. For those components not constructed to Section III of the ASME Code, the rules of IWA-4000 will be applied.

2.1 Requests for Relief from ASME Section XI Requirements >

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2.1.1 Reactor Recirculation Pumps 2.1.1.1 Requirement From Which Relief Requested Table IWB-2500, Category B-L-2, and Table IWB-2600, Item B 5-7, require visual examination of the internal pressure boundary surfaces of one pump in each group of pumps of similar function to be performed once per inspection interval.

2.1.1. 2 Justification This requirement, in absence of other required maintenance, would necessitate dismantling a recirculation pump solely to perform a visual inspection of internal surfaces and, as such, represents an unnecessary exposut e to radiation and contamination and an excessive expense. A job of this scope -

also presents an unnecessary risk of an industrial accident due to the cramped quarters and limited visibility resulting from the use of full anti-C protective equipment. We estimate that the dismantling and reassembly of one pump would consume more than 1,000 manhours and would result in a cumula-tive dose'of between 10 and 50 man-rem.

The net result of this major effort would be a visual inspection consuming about 8 manhours. ' The questionable benefit to be obtained from such an

.- m inspection when measured against the cost in man-rem appears to be in con-(~ ) 'flict with the concept of "As Low as Reasonably Achievable". In view of

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, the cost in dollars, potential hazards, and man-rem and in view of the. minimal benefits to be obtained, we conclude that this Code' requirement is impractical.

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2.1.1. 3 Testing in Lieu of Section XI Requirements f )

' The internal surfaces of the recirculation pump casings will be visually inspected whenever these s -faces are accessible as a result of disassembly for other maintenance purp: s or at the end of the ten-year interval when disassembly is undertaken 6 examination of performance of pump casing.

2.1. 2 Hydraulic Shock Suppressors for Class 1 Piping, Pumps, and Valves 2.1. 2.1 Requirement From Which Relief Requested Tadle IWB-2500, Category B-K-2 requires visual exa.nination of all support components and verification of support settings of snubbers and shock ab-sorbers once per inspection interval. Relief is requested from verification of snubber settings.

2.1.2.2 Justification The hydraulic shock suppressors on Class 1 systems are currently subjected to an ongoing inspection and testing program detailed in the plant Technical Specifications. This program is designed to demonstrate continued operational readiness and structural integrity of the shock suppressors.

2.1.2.3 Testing in Lieu of Section XI Requirements Hydraulic shock suppressors will be inspected and tested in accordance with

(]v Technical Specification requirements.

2.1. 3 ASME Class 1 (Equivalent) Valves Exceeding 4-Inches Nominal Pipe Size 2.1.3.1 Requirement From Which Relief Requested Table IWB-2500, Category B-M-2, and Table IWB-2600, Item B-6.7 require visual examination of the internal pressure boundary surfaces of one valve in each group of valves of the same design, manufacturing method, manufacturer, and function to be performed once per inspection interval.

2.1.3.2 Justification Disassembly of these valves solely for visual inspection, in absence of other required maintenance, represents an unnecessary exposure to radiation and contamination and an excessive expense.

Valves on the recirculation loop suction piping would require off-loading the fuel elements and draining the reactor prior to disassembly. Work on recirculation pump discharge valves, equalizing valves, and RHR injection valves would require installation of plugs in the jet pump risers. Pre-paratory work of this scope is considered impractical for the sole purpose of conducting a visual examination. Contamination levels in the valves associated

,m with the recirculation loops are particularly high due to the physical loca-( i tion of these ~ valves at the bottom of the system.

During routine maintenance, visual examinations of valve body internal surfaces are made. Disassembly of other Class 1 valves solely for internal inspection 2-2

is impractical in view of the fact that many of these valves, particularly the containment isolation valves, are disassembled frequently for maintenance

('") of leak-tightness.

2.1.3.3 Alternate to Section XI Requirement Class 1 valves exceeding 4 inches nominal pipe size are subjected to visual inspection of the internal surfaces of the valve body when disassembled for maintenance. The coverage provided by inspections during routine main-tena1ce coupled with periodic leak tests and hydrostatic tests will provide adequate assurance of the structural integrity of the Class 1 valve bodies, while keeping exposure to radiation and contamination as low as reasonably achievable.

2.1.4 Flued Head Penetrations 2.1.4.1 Requirements for Which Relief Requested Table IWB-2500, Category B-J and B-K-1 requires the examination of circum-ferential butt welds and integrally welded pipe supports, that are located with-in flued head containment penetration assemblies.

2.1.4.2 Justification These welds are inaccessible for examination due to the design of the flued head. All of the twelve circumferential butt welds, except for two 7 located in the RWCU penetration, are carbon steel and not subject to intergranular (V stress corrosion cracking (IGSCC).

Two stainless steel welds that are located in the RWCU penetration were made to replace a Type 304 SS pipe that had undergone IGSCC. They are a flued head with a Type 308L overlay (> 5% ferrite) on the inside surface to a Type 304L solution annealed pipe (< .035% carbon), and a Type 304L pipe-to-pipe weld. These welds were made in accordance with the guidelines of NUREG-0313 to minimize susceptibility to IGSCC.

2.1.4.3 Testing in Lieu of Section XI Requirements A UT baseline was run for each new weld while the weld was accessible dur-ing the repair to ensure a high quality weld.

In accordance with IWB-5221 a system leakage test is to be performed prior to startup following each reactor refueling outage. This is the same type test that detected the crack in the original pipe.

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(.)ISI PROGRAM .V.

]. ASME CODE CLASS'l COMP 0NENTS D

- Table .

Table' IWB-2500

'IWB-2600 . Examination System or Component Method of Code Relief ~

Item No. Category Description Area to be Examined Examination Reauested Bl .1 B-A Reactor Vessel Circumferential and vertical Volumetric No welds in the core belt area Bl.2 B-B Reactor Vessel Circumferential and vertical Volumetric No

., welds in other than core belt area and meridional welds in bottom head torus, bottom head dome, and close head Bl.3 B-C Reactor Vessel Vessel-to-flange and head-to- Volumetric No a flange circumferential welds ,

i Bl .4 B-D Reactor Vessel Primary nozzle-to-vessel welds Volumetric No m and nozzle inside radius

~1 section Bl .5 B-E Reactor Vessel Vessel penetrations: control Visual (IWA- No rod drives instrumentation 5000)

Bl .6 B-F Reactor Vessel Nozzle-to-safe-end welds Covered by IWB- No 2600 Item B4.1

{

Bl.7 B-G-1 Reactor Vessel Closure studs, in place See Note.1 No

. Closure Head ,

< Bl.8 B-G-1 Reactor Vessel Closure studs and nuts re- See Note 1 No I -

, Closure Head moved

)-  ::r

'E Bl.9 B-G-1 Reactor Vessel Ligaments.between threaded Volumetric No f

"i stud holes I +, B1.10 B-G-l' Reactor Vessel Closure washers, bushings- Visual No k- cn Closure Head Bl.11~ B-G-2 Reactor Vessel Bolting less than 2 inches Visual No

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- V ABLE 1 (Cent'd)

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Table Table - .IWB-2500 IWB-2600 . Examination System or Component . .

Method of Code Relief Item No. Category nascription Area to be Examined- Examination Requested B1;12 LB-H . Reactor Vessel Bottom head torus to support' Volumetric -No skirt

' .Bl .13 B-I-l Reactor Vessel Not applicable See Note 2 No

, Closure Head Bl.14 B-I-l Reactor Vessel Vessel cladding Visual. See No Note 3 Bl .15 'B-N-1 Reactor Vessel Vessel interior Visual No Bl .16 -B-N-2 Reactor Vessel Integrally welded core Visual No support structures and in-g terior attachments 0, Bl .N 'B-N-3

Reactor. Vessel Not applicable (applies to Not applicable No

. PWRs only)

Bl.18 ~ B-0 -Control rod drive housings Reactor. . Vessel Volumetric. See No

Note 10

, . . Bl .19. B-P . Reactor. Vessel Exempted components Visual (IWA-5000) No

- B4.1 . B- F .. ' Piping Nozzle-to-safe-end welds Volumetric and No surface

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E B4.2 B-G-1 Piping Pressure boundary bolting Not applicable. No 2~

" greater than and equal to 2 See Note 4.

inches diameter '(in place) e, 184.3 B-G-1  : Pipi ng -- Pressure boundary bolting Not applicable. No-os greater than and equal to 2 See Note 4.

inches diameter (removed) 1B4.4 B-G-1 Piping Pressure boundary bolting Not applicable No greater than and equal to 2 l'

inches-i

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h TABLE 1 -(Conttd)

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u Table Tabl e' IWB-2500..

IWB-2600, Examination System or Component Method of Code Relief Item No. Cateaory Area to be Examined

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Description Examination Requested B4.5 B-J Piping Circumferential and longitud- Volumetric 'Yes.

inal welds See Note 7.

B4.6 B-J Piping Branch connection welds Volumetric No '

greater than 6 inches diameter 6 24.7 B-J Piping Branch connection welds six Surface No inches diameter and smaller i

! B4.8 B-J. Piping Socket welds Not applicable. No See Note 5. .

B4.9 B-K-1 Piping Integrally welded supports Volumetric f

No ry 'B4.10 B-K-2. Piping Support components Visual Yes m

See Note 9.

! B4.ll B-P Piping Exempted components Visual (IWA- No t

t.

5000)

B4.12 B-G-2 Piping Pressure-retaining bolting. Visual No

. . Bolting less than 2 inches diameter l

B5.1. B-G-1 Pumps Pressure-retaining bolts and Volumetric No m,! .

studs greater than and equal

-g .to 2 inches (in place) a w B5.2 B-G-1 Pumps Pressure-retaining bolts and o

Volumetric & No l , studs greater than and equal Surface

, to 2 inches (when removed) l .B5.3 - B-G-1 , Pumps Pressure-retaining bolting Visual No and studs greater than and equal to 2 inches

r ABLE 1 (Cont'd) 1 Table -

Table'- .IWB-2500 IWB-2600 Examination System or. Component Method of Code Relief Item No. ' Category Description Area to be Examined . Examina tion P.eques ted B5.4 B-K-1 ' Pumps- Integrally welded supports Volumetric No B5.5 B-K-2 Pumps Support components Visual .Yes a

See Note 9.

B5.6 B-L-1 . Pumps Casing welds Not applicable. No See Note 6.

j ,B5.7 .B-L-2 Pumps Casings Visual Yes.

See Note 8.

B5.8 B-P Pumps Exempted components Visual (IWA- No 5000) m B5.9 - 'B-G-2 Pumps Pressure-retaining bolting Visual No a less than 2 inches

-l B6.1 -B-G-1 Valves Pressure-retaining bolting Volumetric No

-l greater than and equal to j 2 inches diameter (in place) jf B6.2 B-G-1 Valves Pressure-retaining bolting greater than and equal to Volumetric No 2 inches diameter (removed) j .86.3 B-G-1 -Valves Pressure-retaining bolting Visual No greater than and equal to 2 y, inches diameter 3 g

% B6.4 B-K-1 Valves Integrally welded supports Not Applicable. No j - y See Note 11.

j

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• B6.5 B-K Vaives Support components Visual Yes. .

) See Note 9, I

j B6.6 -B-M-1 Valves Casing welds Not Applicable. No j

See Note 6.

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LE 1 (Cont'd)

Table .

Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Item No. Ca tegory__ Description Area to be Examined Examination Requested B6.7 B-M-2 Valves Casings Visual Yes.

See Note 12 B6.8 B-P Valves Exempted compinents Visual (IWA- No 5000)

B6.9 B-G-2 Valves Pressure-retaining bolting Visual No less than 2 inches p> .

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TABLE 1 N0TES

1. Normally during each refueling outage, the reactor vessel closure studs are left in place; therefore,

- only a volumetric examination will be performed (Table IWB-2600 Item Bl .7). If the studs are removed, both a surface and volumetric examination will be. performed (Table IWB-2600 Item Bl.8).

2. Closure head does not have cladding. Twenty locations on the closure head will be measured to determine the corrosion rate.

3. - Six 6 x 6-inch evenly distributed accessible sections of the vessel shell cladding are to be visually examined.

-4. At present, piping system pressure boundary bolting areater than or equal to two inches does not exist.

If such bolting.is introduced, examinations will be performed in accordance with applicable Code re-quirements.

5. At present, there are no socket welds ~ in ASME Code-affected Class 1 piping systems. If such are intro-duced, applicable ASME Code examinations will be performed.

6. At present, there are no through-wall-casing welds in ASME Class 1 Code-affected pumps or valves. If such are introduced, applicable ASME_ Code examinations will be performed.

/. The arrangements and details of the piping systems and components are such that some examinations (as required by IWB-2600) are limited due to geometric configuration or accessibility. Generally, these limitations exist.at pipe-to-fitting welds, where examination can be fully performed only from the pipe side, the fitting geometry limiting or even precluding examination from the opposite side. Welds having such restrictions will be examined to the extent practical. In instances where the location of pipe -

supports or hangers restricts the access available' for examination of pipe welds (as required'by IWB-2600),

examinations will be performed to the extent practical unless removal of the support is permissible with-out unduly stressing the system.

8. See Request for Relief, paragraph 2.1.1.

9. See Request for Relief, paragraph 2.1.2.

10. Components . referred _to by. this note are exempt from volumetric and surface examinations per IWB-1220(b)(1).

11. There are no integrally welded valve supports.

12. See Request for Relief, paragraph 2.1.3.

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, 3.0 INSERVICE INSPECTION FOR CODE CLASS 2 COMPONENTS (m!

Table z provides a tabulation of the Class 2 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Sumer 1975. These components will be inspected in accordance with the requirements of Subsection IWC to the extent practical.

This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination. Release from the inspection requirements of Subsection IWC is requested where these inspection requirements have been determined to be impractical. Where release is requested, information is provided which identifies the applicable Code requirement, justification for the release request, and the inspection method to be used as an alternative. Table IWC-2600 items not applicable to the Edwin I. Hatch Nuclear Plant-Unit 1 have also been listed and identified in the interest of completeness.

Items applicable to pressurized water reactors only have been omitted entirely for brevity.

Article IWC-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet available for use.

Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any inservice examinations will be made, using the acceptance standards for materials and welds specified in the Code under which the specific component was constructed. Some components

,s' included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased. However,

(>) these components will be inspected in accordance with the requirements of Subsection IWC to the extent practical .

Article IWC-4000, entitled " Repair Procedures," states that the rules of IWB-4000 shall apply. It is considered that the repair procedures outlined in IWA-4000 are appropriate for the components included in this program, and therefore the rules of IWA-4000 will be applied rather than IWB-4000.

The inservice inspection programs described in this section were developed as a result of a design review. Should certain ASME Section XI Code re-quirements be discovered to be impractical, in the course of inspecting the components, due to unforeseen reasons, Georgia Power Company will submit a request for release from the requirements to the NRC at that time.

3.1 Requests for Relief From ASME Section XI Requirements 4

3.1.1 Hydraulic Shock Suppressors 3.1.1.1 Requirement From Which Relief Requested Table IWC-2520, Category C-E-2, requires visual examination of all support components and verification of support settings for springs and snubbers once per inspection interval . Visual examinations and verification of spring settings will be performed. Relief from the verification of snubber q settings is requested.

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3.1.1. 2 Justification

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v The hydraulic shock suppressors on Class 2 systems are currently subjected to an ongoing testing program per plant technical specifications. This program is designed to demonstrate the functional integrity of the shock suppressors.

3.1.1. 3 Testing in Lieu of Section XI Recuirements Hydraulic shock suppressors will be tested in accordance with technical specifications.

3.1.2 HPCI and RCIC Turbine Bolting 3.1. 2.1 Requirement From Which Relief Requested Table IWC-2520, Category C-D, requires examination of pressure-retaining bolting over one inch in diameter.

The closure fasteners for the HPCI pump are studs and cap nuts. The cap nuts completely obscure the studs making an in-place volumetric examination impossibl e. These studs will receive a surface examination when the pump is disassembled for maintenance. The closure studs for the HPCI and RCIC turbine have rounded ends making an in-place volumetric examination im-possible. Relief from inservice examination of these fasteners is requested.

()

e 3.1.2.2 Justification The examination of the obscured stud bolts can be accomplished only by de-tensioning all bolting in sequence. If this is done the pump (or turbine) cover should be lif ted for gasket replacement.

It is anticipated that the pump (and turbine) will require disassembly for

, maintenance at various times. As the pump / turbine is tested monthly per Section XI, Article IWP, the disassembly for the purpose of examining four studs is not practical .

3.1.2.3 Testing in Lieu of Section XI Requirements These studs will receive a surface examination when the turbine is dis-assembled for maintenance.

3.1.3 HPCI and RCIC Valve Bolting 3.1. 3.1 Requirement From Which Relief Requested Table IWC-2520, Category C-D, requires examination of pressure-retaining bolting over one inch in diameter.

The closure studs for the HPCI and RCIC turbine stop and control valves are obscured by cap nuts or have rounded ends making an in-place volumetric (l examination impossible. Relief from inservice examination of these fasteners

"> is requested.

3-2

i 3.1.3.2 Justification

.O See Paragraph 3.1.2.2.

3.1.3.3 Testing in Lieu of Section XI Requirements These bolts will receive a surface examination when the valves are dis-assembled for maintenance.

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h -TABLE 2 L

ISI PROGRAM ASME CODE ~ CLASS 2 COMP 0NENTS-l . Table .

l Tabla., IWB-2500-Method of IWB-2600 Examination System or Component .

, Code Relief -

Iten No. Category Description. Area to be Examined Examination Requested C1.1 - C-A Residual Heat Remov- Circumferential butt welds Volumetric No al Heat Exchangers l

Cl.2 :C-B Residual Heat Remov- Nozzle-to-vessel welds Volumetric No al Heat _Exchangers l

l C1.3 C-C Residual Heat Remov- Integrally welded supports Surface No

, al Heat Exchangers l~ .Cl.4 C-D Residual Heat Remov- Pressure-retaining bolting Visual and No al Heat Exchangers either surface or Volumetric w C2.1 C-F Piping Circumferential butt welds Volumetric Yes.

- A - See Note 1.

?

l C2.2 C-F Piping Longitudinal weld joints in Not Applicable. No fittings 5

-C2.2 C-G Piping Longitudinal weld joints in Not Applicable. No fittings l C2.3 C-F Piping Branch pipe-to-pipe weld Volumetric No

! joints C2.3 C-G Piping' Branch pipe-to-pipe weld Volumetric No joints I

% C2.4 C-D Piping Pressure-retaining bolting Visual and No

_. either surface i o or Volumetric

-o,

! W l _ _ _ _ . ._ _ _ _ _ _ _ __ _ - - - -

J' 0 -

TABLE _2(Cont'd)

Table Table IWB-2500 '

~IWB-2600 Examination System or Component Item No. Category Method of Code Relief Description Area to be Examined Examination Requested C2.5 C-E-1 Piping Integrally welded supports Surface No C2.6 C-E-2 Piping Support components Visual Yes.

See Note 2.

C3.1 C-F Pumps Pump casing welds Not Applicable. No See Note 5.

C3.1 .C-G Pumps Pump casing welds Not Applicable. No See Note 5.

C3.2 C-0 Pumps Pressure-retaining bolting Visual and Yes. See either surface Note 3.

or Volumetric s, .C3.3 C-E-1 Pumps Integrally welded supports Surface No C3.4 C-E-2 Pumps Support components Visual Yes.

See Note 2.

.C4.1 .C-F -Valves Valve body welds Not Applicable. No See Note 5.

C4.1 C-G Valves Valve body welds Not Applicable. No See Note 5.

' 2' C4.2 C-D Valves Pressure-retaining bolting E Visual and Yes.

ro either surface See Note 4 or Volumetric C4.3' C-E-1 Valves Integrally welded supports Surface No C4.4 C-E-2 Valves Support components Visual Yes.

See Note 2.

m

/m

..) V J TABLE 2 N0TES

1. The arrangement and details of the Class 2 piping systems and components were designed and fabricated before the examination requirements of Section XI of the Code were formalized, and some examinations (as required by IWC-2600) are limited or not practical due to geometric configuration or accessibility.

Generally, the limitations exist at all fitting-to-fitting welds such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface conditions preclude ultrasonic coupling or access for the required scan length. Welds having such restrictions will be examined to the extent practical .

In instances where the location of pipe supports on hangers restricts the access available for the examina-tion of pipe welds as required by IWC-2600, examinations will be performed to the extent practical unless removal of the support is permissible without unduly stressing the system.

2. See Request for Relief, paragraph 3.1.1.

3. See Request for Relief, paragraph 3.1.2.

4. See Request for Relief, paragraph 3.1.3.

5. At present, there are no through-wall casing welds in ASME Class 2 pumps or valves. If such welds are introduced, applicable ASME Code examinations will be performed.

3-6 Page 3 of 3

4.0 INSERVICE INSPECTION FOR CODE CLASS 3 COMPONENTS This program consists of the examination areas and the visual examinations required to meet IWD-2000.

The structural integrity of the Safety Class 3 components shall be demonstrated at least once every 40 months during periods of normal reactor operation or during system performance testing by verifying via visual inspection that there is no evidence of unanticipated component leakage, structural distress, or corrosion.

The structural integrity of the Safety Class 3 components shall be demonstrated at least once every ten years by performing system pressure tests at the following test pressures:

1. For closed systems, at least 110 percent of the design pressure.

2. For open storage tanks, at least the nominal hydrostatic pressure de-veloped with the tanks filled to design capacity.

3. Open-ended portions of systems may be exempted from pressure testing.

The structural integrity of the Safety Class 3 components shall be demonstrated at least once every 40 months by verifying via visual inspection that the supports and hangers for piping and components over four inches in diameter show no evidence of inadequate support, unintended restraint, or structural distress.

The following provides further clarification concerning the Class 3 inspection program:

1. Article IWD-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet avail-able for use. Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any in-service examinations will be made, using the acceptance standards for materials and welds specified in the Code under which the specific component was constructed.

2. Article IWD-4000, entitled " Repair Procedures," states that the rules of IWB-4000 shall apply. It is considered that the repair procedures outlined in IWB-4000 are inappropriate for the components included in tnis program, and therefore the rules of IWA-4000 will be applied.

3. ' Inspection of vertical, centrifugal river intake pumps, as required by IWD-2410 (b) and (c), is impractical except at the pump discharge nozzl e. Visual inspection of the discharge nozzle will be performed while the pump is operating. Should the pump be pulled for maintenance, the casing will be visually inspected at that time.

4. The designs of the service water systems do not include provision for testing buried piping as required by IWD-2600(b). Visual inspection for O, leakage at ground level is also impossible for portions which are buried.

'd Nonnal system functional testing demonstrates leaktight integrity of all buried or encased piping.

4-1

5. The system pressure testing requirements of IWD-2410 (b) will not be

,- s performed on lines two inches and smaller unless:

i (a) They are connected to larger lines which will be pressure tested.

(b) Isolation valves are not provided so that these smaller lines may be isolated in case of leakage.

All accessible piping two inches and smaller will be visually inspected while under nortnal operating pressure.

6. System pressure testing as required by IWD-2410 (b) is impractical for certain portions of the plant service water system because it operates continuously during all modes of plant operation. This functional operation demonstrates the structural and leaktight integrity of the system. Visual inspection will be performed while the system is under normal operating oressure to verify leaktightness.

I) v

/*

k _,

4-2

i

5.0 INSERVICE TESTING 0F PUMPS The 1974 ASME Section XI Code with Addenda through Summer 1975 requires in-

, service testing of pumps in accordance with section IWP. The inservice testing program for Class 1, 2, and 3 pumps is described in Table 3. Where '

full compliance with the requirements of the Code was not possible, an explanation is provided in the table.

j 5.1 Requests for Relief from ASME Section XI Requirements t 5.1.1 Vertical Centrifugal Pumps

). 5.1.1.1 Requirement From Which Relief Requested i

Article IWP-4310 of Section XI requires the monitoring of all centrifugal puhp bearing temperatures. Relief from this requirement is requested for vertical centrifugal pumps.

5.1.1. 2 Justification Only the upper bearings are accessible. Pump disassembly for bearing inspec-tion is not practical .

[

- 5.1.1.3 Testing in Lieu of Section XI Requirements

The lower bearings will be inspected for wear whenever a pump is pulled for.

mai ntenance. ,

4 i

l.

$' is A.

O r

i 5-1 4 -

,-x-- - _ - _ . - - -_ _ _ - - _ - - . _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - - . - - . - - - - - _ _ - - _ . - - - - - - _ _ _ _ _ - _ _ - - - - - -'

(v~)

. TABLE 3

-INSERVICE TESTING PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 PUMPS ASME Pump Code

_.Identifica tion - Pump Description Test Section XI Code Class Measured Parameters Interval Relief Requested IC41 C0019- Standby liquid control 2 1. Inlet pressure (P$ ) Monthly No. Note 7 1C41.00018 2. Differential pressure Monthly No.

(AP)

3. Flow rate (Q) NA No. Note 4

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually No. Note 3

6. Lubricant level or Observe Mo. No.

pressure lEll C002A~ Residual heat removal .2 1. Inlet pressure (P$ )

l Monthly No.

lEll C0028 2. Differential pressure Monthly No. Note 1 lEll.C002C. (AP) lEll C0020 3. Flow rate (Q) Monthly No. Note 1

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually Yes. Notes 3, 5

6. Lubricant level or Observe Mo. No. Note 6 pressure l

lEll C001A RHR service water 3 1. Inlet pressure (P$ ) Monthly No.

g lEll C0018 2. Differential pressure Monthly No. Note 1 lEll C001C (AP)

S. lEll C001D 3. Flow rate (Q)

Monthly No. Note 1

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually Yes. Notes 3, 5

6. Lubricant level or Observe Mo. No. Note 6 pressure

_._ , _. _._ - -_.._ _ __ .m. - _ . _ _ ~ - . _ . . _ , _ s L

l c -

OL CL -

l- TABLE 3 (Cont'd) l.

!. ASME

Pump Code Identification' Pump Description Test Section XI Code t Class Measured Parameters Interval- Relief Requested l 1E21 C001A Core spray 2 1. Inlet pressure (P j) Monthly No.

l lE21 C001B 2. Differential pressure Monthly No. Note 1 (AP)

3. Flow rate (Q) Monthly No. Note 1

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually Yes. Notes 3,-5

6. Lubricant level or Observe Mo. No. Note 6 pressure lE21 C002A Jockey' pump 2 1. Inlet pressure (Pi)

Monthly No lE21 C002B 2. Differential pressure l V' Monthly No M (AP)

3. Flow rate (Q) NA No. Note 4 i

4. Vibration amplitude Monthly No. Note 3

5. Bearing' temperature Annually No. Note 3

6. Lubricant level or Observe Mo. No e pressure IP41.C001A Plant service water 3 1. Inlet pressure (P4 )

, Monthly No. Note 2 t IP41 C001B 2. Differential pressure Monthly No. Note-1 l2 1P41.C001C (AP) 1P41 C001D 3. Flow rate (Q) Monthly No. Note 1

4. Vibration amplitude Monthly' No. Note 3 i

. 5. Bearing . temperature Annually Yes. Notes 3, 5

6. Lubricant level or 0Merve Mo. No. No te 6 i pressure  :

s

.,mr w y - - -g-,- w -

e- -,,c,e _

m -a

~) ,s)

Qj LJ  %)

TABLE 3 (Cont'd) ll l ASME Pump Code Test Section XI Code-Identification Pump Description Class Measured Parameters Interval Relief Requested lE41 C001 High-pressure coolant 2 1. Inlet pressure (Pg) Monthly No injection

2. Differential pressure Monthly No. Note 1 (AP)

3. Flow rate (Q) Monthly No. Note 1

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually No

6. Lubricant level or Observe Mo. No pressure

7. Pump speed Monthly No

[ lE51 C001A Reactor core isolation 2 1. Inlet pressure (Pj ) Monthly No cooling

2. Differential pressure Monthly No. Note 1 (AP)

3. Flow rate (Q) Monthly No. Note 1

4. Vibration amplitude Monthly No. Note 3

5. Bearing temperature Annually No. Note 3

6. Lubricant level or Observe Mo. No pressure

7. Pump speed Monthly No E

w

m.

\

O O O TABLE 3 l

N0TES l

1. Measurement of both AP and Q is not required by ASME Section XI. One of these quantities may be omitted from the test specified by the surveillance procedures.

2. These pumps are vertical design with no means of direct inlet pressure measurement. In lieu of direct measurement, the wet-pit level will be measured. This can then be converted to pump inlet pressure as:

Inlet pressure (P i) = Wet-pit level (ft) - pump elevation (ft) 2.3066 (ft/ psi)

3. No instrument is installed on the pump. A portable instrument will be used.

4. No flow instrumentation is installed on this pump. A fixed-resistance test circuit will be used in accordance with footnote 1 of Table IWP-3100-1.

5. See Pequest for. Relief, paragraph 5.1.1.

6. Lubricant level is to be observed for the driver thrust bearing only. The main bearings are lubricated by the pump water.

7. No direct means of measuring pump inlet pressure is available. Pump inlet pressure will be calculated from test tank level.

5-5

1

- 6.0 INSERVICE TESTING OF VALVES

.O i- The 1974 ASME Section XI Code with Addenda through Summer 1975 requires in-service testing of valves in accordance with section IWV. The inservice test-t -- -

ing program for Class 1, 2, and 3 valves is described in Table 4. Where full

! compliance with the requirements of the Code was not possible, an explanation is provided in the table.

6.1 Requests for Relief from ASME Section XI Requirements

! 6.1.1 Requirement From Which Relief Requested

, IWV-3410(g) and IWV-3520(c) state that when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup.

i 6.1.2 Justification e

Under such conditions startup shall be permitted as provided in the technical specifications.

P p.

I T

5 f  %,

1 i

J r

I" 6-1 .

d e________m. . ____ ._m____._..__________.______________..___m__._.___i____-______m_____.._.___m__ _.m__._____._________ __ _ _ _ .___. _ _ _ _ _ _ _ _ _ _ . . . . __ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _

") t' O V TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN 5"EEY I of ASME CODE CLASS 1.2. AND 3 VALVES OEa  !* ),*I "

t.e sOJIm MTiX a2 Lo. +uw1m  !;C uc, m m coo.

.{5 extacise e.oa o ta mamu gd **"""***So 821-F010A 1 AC 18" Check 3-E H-16062 Feedwater Inboard Containment Isolation 0 Each Refueling Outage Each Refuelin9 Outage -

Yes. Note 2 B21-F0108 1 AC 18* Check 3-D H-16062 Feedwater Inboard Containment Isolation 0 Each Refueling Outage Yes. Note 2 Each Refueling Outage -

B21-F013A 1 C 6* Relief C-6 H-16062 Main Steam Relief -

Note 3 N/A - No. Note 19 B21-F0138 1 C 6" Relief C-6 H-16062 Main Steam Relief -

Note 3 N/A - No. Note 19 l

B21-F013C 1 C 6" Relief F-6 H-16062 Main Steam Relief - Nqte 3 N/A - No. Note 19 B21-F013D 1 C 6" Relief F-6 H-16062 Main Steam Relief -

Note 3 N/A -

No. Note 19 t

i B21-F013E 1 C 6" Relief F-6 H-16062 Main Steam Relief Note 3 l

N/A -

No. Note 19 i

! B21-F013F 1 C 6" Relief F-6 H-16062 Main Steam Relief - Notg_] N/A - No. Note 19 B21-F013G 1 C 6" Relief F-6 H-16062 Main Steam Relief -

Note 3 N/A -

No. Note 19 B21-F013H 1 C 6" Relief G-6 H-16062 Main Steam Relief -

Note 3 N/A - No. Note 19 B21-F013J l C 6" Relief G-6 H-16062 Main Steam Relief -

Note 3 N/A - No. Note 19 B21-F013K 1 C 6" Relief F-6 H-16062 Main Steam Relief -

Note 3 No. Note 19 N/A -

l B21-F013L 1 C 6" Relief F-6 H-16062 Main Steam Relief .

-l Note 3 N/A - No. Note 19 Fenue fee SF93 6-2 a

i -

m

\ (/ Q TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN "" 2

• 24 ASME CODE CLASS 1.2. AND 3 VALVES i

JOUa [l[A c4 4^.I.Um V.I"Y ua%% 'N'a

,, h * *f.'c"Te"d.E!?lo B21-F016 Yes. Note 10 1 C 3" M0 Gate E-8 H-16062 Main Steam Line Drain Inboard Isolation C Cold Shutdown Each Refueling Outage 15 (See Note 8)

B21-F019 1 A 3* M0 Ga te E-9 H-16062 Reactor Sample System Inboard Isolation C Cold Shutdown Each Refueling Outage 15 No. Note 8 B21-F022A 1 A 24" A0 Globe C-7 H-16062 MSIV O Every Three Months Each Refueling Outage 3-5 Yes. Note 11 B21-F0228 1 A 24" A0 Glote E-7 H-16062 MSly 0 Every Three Months Each Refueling Outage 3-5 Yes. No'te 11 B21-F022C 1 A 24* A0 Globe F-7 H-16062 MSIy 0 Every Three Months Each Refueling Outage 3-5 Yes. Note 11 B21-F022D 1 A 24" A0 Globe G-7 H-16062 MSIV 0 Every Three Months Each Refueling Outage 3-5 Yes. Note 11 B21-F028A 1 A 24" A0 Globe C-9 H-16062 MSly 0 Every Three Months Each Refueling Outage 3-5 No B21-F0288 1 A 24" A0 Globe E-9 H-16062 MSly 0 Every Three Months Each Refueling Outage 35 No B21-F028C 1 A 24" A0 Globe F-9 H-16062 MSIV O Every Three Months Each Refueling Outage 3-5 No B21-F0280 1 A 24" A0 Globe G-9 H-16062 MSIy 0 Every Three Months Each Refueling Outage 3-5 No B21-F032A 1 A IS" Check E-2 H-16062 Feedwater Outboard Isolation 0 Each Refueling Outage Each Refueling Outage - Yes, Note 2 B21-F032B 1 A 18" Check D-2 H-16062 Feedwater Outboard Isolation 0 Each Refueling Outage Each Refueling Outage -

Yes. Note 2 B21-F037A 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None -

Yes. Note 5 N/A e sm 6-3 O

( l

' ' ^

I O  : O .O .

I l

l TABLE 4 .

INSERVICE INSPECTION VALVE TEST PLAN SHEET 3 of 24 ASME CODE CLASS 1,2. AND 3 VALVES d'AIda )[$ oe ntJ'.o #if".h sJd ko. eu~ci m

[3 ye

,5l,c,}g,=g,jyl, u

Q exeacise reore a, cause B21-F0378 3 C 6". Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A - Yes. Note 5 B21-F037C- 3 f. 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A - Yes. Note 5 B21-F037D 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge- C None N/A - Yes.' Note 5 B21-F037E 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A - Yes. No(e 5 i

j B21-F037F 3 C 6" Check H-6' H-16062 ' Vacuum Breaker MSRV Discharge C None N/A - Yes. Note 5 B21-FD37G 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A - Yes. Note 5 B21-F037H 3 C 6" Check: H-6 H-16062' VacuumBreakerMSRYbischarge -C None N/A -

Yes m No P 'n B21-F037J 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A -

Yes. Note 5 B21-F037K 3 'C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A -

Yes. Note 5 B21-F037L 3 C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A -

Yes. Note 5 3/4" A0 B31-F019 1 'A Globe D-3 H-16066 Reactor Sample System Inboard Isolation 0 Cold Shutdown Each Refueling Outage 5 No. Note 23 3/4" A0 .-

B31-F020 1 A Globe D-1 H-16066 Reactor Sample System Inboard Isolation 0 Cold Shutdown Each Refueling Outage 5 No. Note 23 B31-F023A 1 B 28" M0 Gate G-3 H-16066 Reactor Recircul'ation . O Cold Shutdown Each Refueling Outage No. Note 25 40 e n. s.ns 6-4

?,

. q./ l UI &

I I

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SHEET OF ASME CODE CLASS 1.2. AND 3 VALVES

• i et R a g' D4 s t EON D*Ce 9 W f TON , ,Ig'F A l t. .

f L T D B31-F0238 1 B 28" M0 Gate H-3 H-16066 Reactor Recirculation 0 Cold Shutdown Each Refueling Outage 40 No. Note 25 B31-F031A 1 B 28" K) Gate G-7 H-16066 Reactor Recirculation 0 Cold Shutdown Each Refueling Outage 40 No. Note 25 B31-F031B 1 B 28" M0 Gate H-7 H-16066 Reactor Recirculation 0 Cold Shutdown Each Refueling Outage 40 No. Note 25 1-1/2" Expl. .

C41-F004A 2 B Shear D-3 H-16061 SLC Explosive Actuated C Note 4 N/A -

No 1-1/2" Exp1, C41-F004B 2 B Shear E-3 H-16061 SLC Explosive Actuated C Note 4 N/A -

No 1-1/2" C41-F006 1 AC Check E-2 H-16061 SLC Outboard Containment Isolation C Once/18 Pbnths Each Refueling Outage - Yes. Note 26 1-1/2" C41-F007 1 AC Check E-2 H-16061 SLC Outboard Containment Isolation C Once/18 Months Each Refueling Outage -

Yes. Note 26 C41-F029A 2 C 1" Relief D-6 H-16061 SLC Pump Discharge Relief Valve C Note 3 N/A -

No. Note 19 C41-F029B 2 C 1" Relief G-6 H-16061 SLC Pump Discharge Relief Valve C Note 3 N/A - No. Note 19 Ell-F003A 2 B 16" M0 Gate D-9 H-16330 RHR Heat Exchanger Shell Side Outlet 0 Every Three Months N/A 82 No Ell-F003B 2 B 16" M0 Gate D-4 H-16329 RHR Heat Exchanger Shell Side Outlet 0 Every Three Months N/A 82 No Ell-F004A 2 A 24" M0 Gate F-10 H-16330 RHR Pump Suction Torus Isolation 0 Every Three Months Each Refueling Outage 125 No i

i E11-F004S 2 A 24" M0 Gate F-3 H-It,329 RHR Pump Suction Torus Isolation 0 Every Three Months Each Refueling Outage 125 No r m s ru 6-5 D .

9

./'Y% .s'M'N .sh, (a )  ; >

i )

</ y,/

TABLE 4 5Hu T 5 or 24 INSERVICE INSPECTION VALVE TEST PLAN ASME CODE CLASS 1.2. AND 3 VALVES 45 s I vestratoucacv U-J.^4L*.

$s v c ,"e cl. oes?.'Ji*nm tit" oDa "ac ' **

hg-9 exsac.se inove tranace 2D ye a*!<'NMaW.Tiin E11-F004C 2 A 24" M0 Gate F-10 H-16330 RHR Pump Suction Torus Isolation 0 Every Three Months Each Refueling Outage 125 No E11-F004D 2 A 24" M0 Gate F-3 H-16329 RHR Pump Suction Torus Isolation 0 Every Three Months Each Refueling Outage 125 No Ell-F006A 2 8 20" M0 Gate F-10 H-16330 RHR Shutdown Cooling Suction C Cold Shutdown N/A 110 No. Note 8 E11-F006B 2 B 20".M0 Gate F-2 H-16329 RHR Shutdown Cooling Suction C Cold Shutdown N/A 110 No. Noth 8 E11-F006C 2 B 2C" M0 Gate. F-10 H-16330 RHR Shutdown Cooling Suction C Cold shutdown N/A 110 No. Note 8 l

E11-F0063 2 B 20" M0 Gate F-2 H-16329 RHR Shutdown Cooling Suction C Cold Shutdown N/A 110 No. Note 8 Ell-F007A 2 A 4" M0 Gate E-7 H-l',330 RHR Pump Minimum Flow Torus Isolation 0 Every Three Months Each Refueling Outage 25 Yes. Note 10 E11-F007B 2 A 4" M0 Gate D-5 H-16329 RHR Pump Minimum Flow Torus Isolation 0 Every Three mnths Each Refueling Outage 25 Yes. Note 10 l

l E11-F008 1 A 20" M0 Gate D-1 H-16329 RHR Shutdown Cooling Outboard Isolation C Cold Shutdown Each Refueling Outage 24 No. Note 8 I

l E11-F009 1 B 20" M0 Gate D-1 H-16329 RHR Shutdown Cooling Suction C Cold Shutdown N/A 24 No. Note 8 E11-F011A 2 A 4" M0 Gate D-3 H-16330 RHR Condensate Discharge to Torus C Every Three mnths Each Refueling Outage 25 Yes. Note 10 Ell-F011B 2 A 4* M0 Gate C-9 H-16329 RHR Condensate Discharge to Torus C Every Three Months Each Refueling Outage 25 Yes. Note 10 E11-F015A 1 A 24" M0 Gate C-8 H-16330 LPCI Outboard Containment, Isolation C Every Three Months Each Refueling Outage 24 No l ..m

! 6-6 l .

i ,,,.

MS

. TABLE 4 I 6 o, 24 INSERVICE INSPECTION VALVE TEST PLAN sm t T ASME CODE CLASS 1,2, AND 3 VALVES OUa : )lI oan"J.U.ca '.".a 1"el' 02 6. ' = "

• 9

,,,,,,,,,,,,,, ,,,,,,, h *E.MeUtWe o ,

Ell-F015B 1 A 24" MD Gate C-4 H-16329 . LPCI Outboard Containment Isolation C Every Three Months Each Refueling Outage 24 No

. E11-F016A 2 A_ 16" MD Globe B-9 H-16330 Containment Spray Outboard Isolation C Every Three Months Each Refueling Outage 10 No Ell-F0168. 2 A l' 6" M0 Globe B-4 H'-16329 Containment Spray Outboard Isolation C Every Three Months Each Refueling Outage 10 No Ell-F017A 1 B 24" MD Globe D-8 H-16330 LPCI O Every Tnree Months N/A 24 No*

Ell-F017B 1 B 24" M0 Globe 0-5 H-16329 LPCI O Every Three Months N/A 24 No Ell-F019 1 C. 4" Check - A-1 H-16329 Head Spray C Note 6 N/A - No Ell-F021A' 2 B 16" MD Gate B-11 H-16330 Containment Spray C Every Three Months N/A 17 No Ell-F021B 2 B 16" M0 Gate B-2 H-16329 Containment Spray' C Every Three Months N/A 17 No Ell-F022 1 B 4" M0 Sate ~ A-1 H-16329 Head Spray C Cold Shutdown N/A 20 No. Note 8 ,

I Ell-F023- 1 A 4" MD Globe 'A-2 H-16329 Head Spray Outboan; Isolation C Cold Shutdcwn Each Refueling Outage 20 No. Note 8 I i Ell-F024A 2 B 16' MD Globe C-7 H-16330 ~ Suppression Pool Cooling C Every Three Months N/A 110 No

. 2 Ell-F024B 2 B 16" M0 Globe C-6 H-16329 Suppression Pool Cooling C Every Three Months N/A 110 No Yes. Note 20 Ell-F025A 2 AC I" Relief l B-8 H-16330 LPCI Injection Containment Isolation C Note 3 Each Refueling Outage -

(SeeNote19) re e sres d

p WW M* ,

(~. p N.) Q s

Y)

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN sHCEi Of ASME CODE CLASS 1.2. AND 3 VALVES Ju'M!n ((,b. ce s?J.U.cm '.T. ,"eT o7 N *vac'*oa 5 N **

.'. .'eMe"Jo'e%

uv pn excacise c. ort s, taanaca ye Yes. Note 20 Ell-F025B 2 AC 1" Relief C-5 H-16329 LPCI Injection-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Contain.

E11-F026A 2 A 4" M0 Gate D-3 H-16330 Condensate Discharge to RCIC - Isolation C Every Three Months Each Refueling Outage 25 No Contain.

Ell-F026B 2 A 4" M0 Gate D-ll H-16329 Condensate Discharge to RCIC - Isolation C Every Three Months Each Refueling Outage 25 No E11-F027A 2 A 6" M3 Globe D-3 H-16330 Suppression Pool Spray Inboard Isolation C Every Three Months Each Refueling Outage 11 Yes. Note 13 E11-F027B 2 A 6" M0 Globe D-11 H-16329 Suppression Pool Epray Inboard Isolation C Every Three Months Each Refueling Outage 11 Yes. Note 13 E11-F028A 2 A 16" M0 Globe B-8 H-16330 Suppression Pool Spray Outboard Isolation r. Every Three Months Each Refueling Outage 25 No Ell-F0288 2 A 16" M0 Glcta B-5 H-16329 Suppression Pool Spray Outboard Isolation C Every Three Months Each Refueling Outage 25 No Yes. Note 20 Ell-F029' 2 AC 1" Relief E-2 H-16329 RHR Pump Suction-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Yes. Note 20 E11-F030A 2 AC 1" Relief F-9 H-16330 RHR Pump Suction-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Yes. Note 20 Ell-F030B 2 AC 1" Relief F-4 H-16329 RHR Pump Suction-Contairment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Yes. Note 20 Ell-F030C 2 AC 1" Relief F-Il H-16330 RHR Pump Suction-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Yes. Note 20 E11-F0300 2 AC 1" Relief F-1 H-16329 RHR Pump Suction-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Ell-F046A 2 C 3" Check H-7 H-16330 RHR Minimum Flow Line , C Every(Three Note 7) Months N/A -

No Ferne he S F93 6-8

.!a

, .. . .- - - ,- - - ~. ,- . . _ .

- v l ~

l l

l TABLE 4 lNSERVICE IN."PECTION VALVE TEST PLAN SHEET b OF _.24_ i ASME CODE CLASS 1,2, AND 3 VALVES E* mea c.f '

oan^Mion 'uYr"at Mb ' ac m f un a ve u nma "

Every(Three Note 7) Months H-5 H-16329 N/A No Ell-F046B 2 C- 3" Check RHR Minimum Flow Line C -

Ell-F046C 2 C 3" Check H-11 H-16330 RHR Minimum Flow Line C Every(Three Note 7) Nnths N/A - No

- Every Three Months H-2 No Ell-F046D 2 C- '4" Check H-16329 RHR Minimum Flow Line C (Note 7) N/A -

Ell-F047A 2 B 16" MD Gate E-6 H-16330 RHR Heat Exchanger Shell Side Inlet 0 Every Three m nths N/A 82 No

• i E11-F047B 2 B 16" MD Gate E-7 H-16329 RHR Heat Exchanger Shell Side Inlet 0 Every Three Months N/A 82 No Ell-F048A- 2 B 24" M0 Cate B-8 H-16330 RHR Heat Exchanger Shell Side Bypass 0 Every Three Months N/A 175 No l

Ell-F048B 2 B 24" M0 Gate B-5 H-16329 RHR Heat Exchanger Shell Side Bypass 0 Every Three Months N/A 175 No Ell-F050A 1 C 24" A0 Check D-6 H-16330 LPCI Injection C Cold Shutdown N/A - No. Note 22 E11-F050B 1 C 24" A0 Chect D-7 H-16329 LPCI Injection C Cold Shutdown N/A - No. Note 22  :

Contain.

l Ell-FOSSA 2 AC 4" Relief D-6 H-16330 RHR Heat Exchanger Shell Relief-Isolation C Note 3 Each Refueling Outage -

No. Note 19 l l Contain, j Ell-F052 2 AC 4" Relief D-7 H-16329 RHR Heat Exchanger Shell Relief-Isolation C Note 3 Each Refueling Outage - No. Note 19 24" A0 Ell-F065A 2 B Butterfly E-10 H-16330 RHR Torus Suction Isolation 0 Every Three Months N/A 12 No i- 24" A0 Ell-F065B 2 B Butterfly E-2 H-16329 RHR Torus Suction Isol,ation 0 Every Three Months N/A 12 No

% =.

• m 6-9 tv-l b

. ~. ...

\_,,' v  %)

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SM F T OF ASME CODE CLASS 1,2, AND 3 VALVES eue.c son

.Iv".'is'n vu )[$- os s"c'A# ion 'E.0"eS' olo' Ao.

ghl exancese rore n {3 fffy,y,"af,j%

te.oce 7e 24" A0 (

Ell-F065C 2 B Butterfly E-10 H-16330 RHR Torus Suction Isolation 0 Every Three Months N/A 12 No j

?4" A0 '

E11-F065D 2 B Butterfly E-2 H-16329 RHR Torus Suction Isolation 0 Every Three Months N/A 12 No E11-F078A 2 C 10" Check H-6 H-16330 RHR Heat Exchanger Service Water Intertie C Every Three Months N/A No f I

E11-F0788 2 C 10" Check D-9 H-16329 RHR Heat Exchanger Service Water Intertie C Every Three Months N/A No '

E11-F091A 2 B 6" M0 Globe E-2 H-16330 Steam Line to FHR Heat Exchanger Shutdown C Every Three Months N/A 65 No E11-F091d 2 B 6" M0 Globe E-11 H-16329 Steam Line to RHR Heat Exchanger Shutdown C Every Three Months N/A 65 No Yes. Note 20 Ell-F097 2 AC 3" Relief D-11 H-16329 Steam Supply Relief-Containment Isolation C Note 3 Each Refueling Outage -

(See Note 19)

Containment E11-F103A 2 A 1" M0 Globe E-5 H-16330 RHR Heat Exchanger Vent - Isolation C Every Threa Months Each Refueling Outage 15 Yes. Note 11 Containment E11-F103B 2 A 1" M0 Globe E-8 H-16329 RHR Heat Exchanger Vent - Isolation C Every Three Months Each Refueling Outage 15 Yes. Note 11 '

Ell-F140A 2 B 6" MD G3te E-2 H-16330 Steam Line to RHR Heat Exchanger Shutdown C Every Three Months N/A 35 No Ell-F140B 2 8 6" M0 Gate E-11 H-16329 Steam Line to RHR Heat Exchanger Shutdown C Every Three Months N/A 35 No Ell-F068A 3 B 10" M0 Ball H-6 H-16330 RHR Heat Exchanger Service Water Dischargt C Every(Three Note 7) Months N/A No i Ell-F068B 3 B 10" M0 Ball H-7 H-16329 RHR Heat Exchanger Service Water Discharg C Every(Three Note 7)Months N/A No l e m. > 3 6-10 g We

.y.

m x . _..; - . - _

o OL O a TABLE 4-10 or 24 INSERVICE INSPECTION VALVE TEST PLAN SHEEY

' ASME CODE CLASS 1,2, AND 3 VALVES Ju' Amin c c.I[. wOiUion '%T

= o* h * *c "*

,,,,,,,,,,,, ,,,,,,,, n'aY.E.ie%Mo Ell-F073A 2 B 10" M0 Gate G-4 H-16330 RHR Service Water Intertie C Every Three Months N/A 55 No Ell-F073B 2 B 10" M0 Gate G-9 H-16329 RHR Service Water Intertie C Every Three Months N/A 55 No EEll-F075A !2 B 10" M0 Gate G-4 H-16330 RHR Service Water Intertie C Every Three Months N/A 55 No Ell-FO',5B 2 B 10" MO Gate G-9 H-16329 RHR Service Water Intertie Every Three Months ho C N/A 55

. Ell-F119A 3 B' 18" M0 Gate H-4 H-16330 RHR Service Water Train A & B Cross C Every Three Months N/A 110 No Ell-F1198 3 B 18" M0 Gate H-9 H-16329 RHR Service Water Train A & B Cross C Every Three Months N/A 110 No Ell-F125A 3 C 3/4" Relief H-5 H-16330 RHR Heat Exchanger Water Box C Note 3 N/A - No. Note 19 Ell-F125B 3 C 3/4" Relief H-8 H-16329 RHR Heat Exchanger Water Box C Note 3 N/A - No. Note 19 Ell-F200A 3 8 2" A0 PCV D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A - No i

Ell-F2006 3 B' 2" A0 PCV -

'D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A . No

" Ell-F200C' 3 B 2" A0 PCV - D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A - No Ell-Fr00D 3 8 2* A0 PCV -

D-11004- RHR Service Water Pump Minimum Flow C Note 9 N/A - No 1/2" .

' Ell-t001A 3 B Solenoid - D-11004 RHR Service Water Pump Cooling C Note 9 N/A - No 1

Fe,e No. 9-F93  :

6-11

. t g.. ;

f. ;

. j

- f

~. . -- - - .. , - - - -

/% N'  % -

'\

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN 5"

• O' ASME CODE CLASS 1,2, AND 3 VALVES e7o*0!!n o u

)[$

nas?dJI.o= 'EfieT Ed!.o. e vaci .o=

g-[

exenciss <=ou u u muc.a h

7e

,5l,c,v,yg=4c,qg 1/2" E11-L001B 3 B Solenoid -

D-11004 RHR Service Water Pump Coolin9 C Note 9 N/A - No l 1/2" E11-LOO 1C 3 B Solenoid -

D-11004 RHR Service Water Pump Cooling C Note 9 N/A - No l

l 1/2" Ell-LOOlD 3 B Solenoid -

D-11004 RHR service Water Pump Coolin9. C Note 9 N/A - No Core Spray Pump Torus Suction Outboard ,

E21-F001A 2 A- 20" M0 Gate H-8 H-16331 Isolation 0 Every Three Months Each Refueling Outage 100 No Core Spray Pump Torus Suction Outboard E21-F001B 2 A 20" M0 Cate J-8 H-16331 Isolation 0 Every Three Months Each Refueling Outage 100 No I . . .

l. E21-F004A 1 B 10" M0 Gate E-7 H-16331 - Core Spray Outboard Injection 0 Every Three Months N/A 50 No lL

'E21-F004B 1 B 10" MD Gate B-7 H-16331 Core Spray Outboard Injection 0 Every Three Months N/A 50 No

(-

I E21-F005A- 1 A 10" MD' Gate E-6 H-16331 Core Spray Outboard Containment Isolation C Every Three Months Each Refueling Outage 50 No i- E21-F005B 1 A 10" M0 Gate B-6 H-16331 Core Spray Outboard Containment Isolation C Every Three Months Each Refueling Outage 50 No E21-F006A- -1 C 10" A0 Check D-4 H-16331 Core Spray injection C Cold Shutdown N/A -

No. Note 22

(:

i E21-F006B '1 C 10" A0 Check C-4' H-16331 Core Spray injection C Cold Shutdown N/A -

No. Note 22 I

I E21-F012A 2 C 2" Relief ' D-9 H-16331 Ccre Spray Pump Discharge Relief C Note 3 N/A - No. Note 19 l

E?l-F0128 2 C 2" Rellei B-9 H-16331 Core Spray Pump Discharge Relief C Note 3 N/A -

No. Note 19 e =.

• m l

6-12 s *

.?k'

. . .. ~. ~ ~ - .

l 3

/ ,

/

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN *><tci 3 _ or 24 ASME CODE CLASS 1,2, ANO 3 VALVES i

. E =

. BE M O uv cy OnbCNtPf M h it DwG O. P WC T m  ! smancesa peon n

,Sg gp

,T s C

E O g- annaca fe Core Spray Test Bypass Containment L E21-F015A - 2 A 10" M0 Globe D-8 H-16331 Isolation C Every Three Months Each Refueling Outage 54 Yes. Note 11 Core Spray Test Bypass Containmert E21-F015B 2 A 10" M0 Globe C-8 H-16331 ' Isola tion C Every Three Months Each Refueling Outage 54 Yes. Note 11

~

20" A0 E21-F010A 2 B Butterfly - J-6 H-16331 Core Spray Pump Torus Suction 0 Every Three Months N/A 22 No 20" A0 E21-F019B' 2 B Butterfly K-6 H-16331 Core Spray Pump Torus Suction 0 Every Three Months N/A 22 No*

E21-F031A 2 B 3" MD Gate F-9 ~ H-16331 Core Spray Pump Hintme. Flow 0 Every Three Months N/A 20 No E21-F031B 2 B 3" M0 Gate. F-10 H-16331 Core Spray Pump Minimum Flow 0 Every Three Months N/A 20 No Core Spray Test Line - Containment E21-F036A 2 AC 3" Check- E-9 H-16331 Isolation C N/A N/A -

Yes. Note 21 Core Spray Te=t Line - Containment E21-F036B 2 AC 3" Check' E-10 h-16331 Isolation C N/A N/A -

Yes. Note 21 1-1/2" Stop E21-F044A Each Refueling Outage Yes . Note 16 2 AC Check F-5 H-16331 ~ Core Spray Jockey Pump Torus isolation 0 N/A -

1-1/2" Stop E21-F044B 2 AC Check F-4 H-16331 Core Spray Jockey Pump Torus Isolation 0 N/A Each Refueling Outage -

Yes. Note 16 E41-F001 2 8 10" M0 Gate E-12 ~ H-16332 HPCI Steam Supply Shutoff C Every Three Months N/A 50 No l E41-F002. 1 A 10" MD Gate C-2 H-16332 HPCI Steam Supply Inboard Isolation 0 Every Three Months Each Refueling Outage 50 Yes. Note 10 l

l E41-F003 1 A 10" M0 Gate C-4 H-16332 HPCI Steam Supply Outboard Isolation 0 Every Three Mar.ths Each Refueling Outage 50 No e =..m-6-13

, N

9 I

L

. _a. . . . . .

.,u_

~

.h_ f~~

U r

i b C)' .,

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SHEET or M l

ASME CODE Cl. ASS 1,2, ANO 3 VALVES u"O!!n ' ((j[ oes"cWI.o= 'nTle'S' olOo. r unc t.o= g c

,5f,c,jpg"jo,qb E41-F004 '2 B 16" M0 Gate D-9 H-16332 HPCI Pump Suction from Condensate Storage O Every Three Months N/A 60 ho E41-F006 2 B 14" MD Gate E-5 H-16332 HPCI Pump Inboard Discharge C Cold Shutdown N/A 50 No. Note 8 l

E41-F007 B 14" M0 Gate HPCI Pump Outboard Discharge Every Three Months 50 No 2 E-6 H-16332 O N/A

! . Every Three Months E41-F008 2 B 10" M0 Globe D-7 H-16332 HPCI Pump Test Bypass C (Note 7) N/A - No ,

HPCI Pump Redundant Shutoff to Condensate Every Three Months E41-F011 2 B 10" M0 Gate C-7 H-16332 Storace C (Note 7) N/A . No l

Ever/ Three Months E41-F012 2 A 4" M0 Ga te F-7 H-16332 HPCI Pump Minimum Flow Inboard Isolation C (Note 7) N/A - No

'I 12" Stop E41-F021 e AC Check G-3 H-16332 HPCI Turbine Exhaust-Inboard Isolation 0 N/A Each Refueling Outage . Yes. Note 16 2" Stop E41-F022 2 AC Check G-4 H-16332 HPCI Turbine Exhaust Drain-Torus Isg.lation 0 N/A Each Refueling Outage - Yes. Note 16 l 2" A0 l

E41-F035 2 B PCV G-8 H-16333 HPCI Turbine Lube Oil Cooling C Note 9 N/A - No E41-F040 2 AC 2" Check G-5 H-16332 HPCI Turbine Exhaust Drain-Torus Isolation C Every(Three Note 7)Months Each Refueling 0:tage . - No

'E41-F041' 2 B 16" M0 Gate D-8 H-16332 HPCI Pump Suction Shutoff C Every Three Months N/A 60 No E41-F042 2 A 16" M0 Gate J-5 H-16332 HPCI Pump Suction Torus Outboard Isolation C Every Three Months Each Refueling Outage 60 No l . Every Three Months E41-F046 2 AC 4" Check F-8 H-16332 HPCI Pump Minimum Flow Outboard Isolation C (Note 17) Each Refueling Outage - No rom u . e m 6-14 F t

t'

, s,, .

IO

g a

.L) rd - ,

TABLE 4

-INSERVICE INSFECTION VALVE TEST PLAN 5"LLT O' ASME CODE CLASS 1,2, AND 3 VALVES

'E 'a ca[a - oalcUfeon 'd?,"e7 Ja' l,o, , u c ,,,, ,g sc . . -

ves,,arouancy

..., <.. _ , y m.m.wm y

Every Threr Months E41-F049 2 AC 20" Check- G-4 H-16332 HPCI Turbine Exhaust Outboard Isolation C (Note 7) Each Refueling Outage - No 16" A0 E41-F051 2 A' Butterfly J-4 H-16332 HPCI Pump Suction Torus Inboard Isolation 0 Every Three Months Each Refueling Outage 16 Yes. Note 14 E41-F059 2 B. 2" M0 Globe F-8 H-16333 HPCI Turbine Lube Oil Cooling C Every Three Months N/A 17 No HPCI Vacuum Relief Outboard Torus E41-F104 2 A 2" M0 Gate G-3 H-16332 Isolation 0 Every Three Months Each Refueling Outage 15 No-HPCI Vacuum Relief Inboard Torus

E41-F111 2 A 2" M0 Gate G-2 H-16332 Isolation 0 Every Three Months Each Refueling Outage 15 Yes. Note 10 10" Stop E51-F001 2 C Check G-5 H-16334 RCIC Turbine Exhaust to Torus Isolation 0 N/A N/A -

Yes. Note 16 2" Stop RCIC Vacuum Pump Discharge to Torus E51-F002 2 AC Check G-6 H-16334 Isolation 0 N/A Each Refueling Outage -

Yes. Note 16 6" A0 -

E51-F003 2 A Butterfly J-6' H-16334 RCIC Pump Suction Torus Isolation 0 Every Three Months Fach Refueling Outage 5 Yes. Note 14 E51-F007 -1 A 4" M0 Gate C-5 H-16334 RCIC Steam Supply Inboard Isolation 0 Every Three Months Each Refueling Outage 20 Yes. Note 10 E51-F008 1 A 4" M0 Gate C-6 H-16334 RCIC Steam Supply Outboard Isolation 0 Every Three Mont'es Each Refueling Outage 20 No E51-F013 2 B 4" M0 Gate E-6 H-16334 RCIC Feedwater Injection C Every Three Months 20 No N/A Every Three Months E51-F019 2 A 2' M0 Globe F-7 H-16334 RCIC Pump Minimum Flow-Torus Isolatten C (Note 7) Each Refueling Outage -

Yes. Note 13 Every Three Months .

E51-F021 2 AC 2" Check F-8 H-16334 RCIC Pump Minimum Flow. Torus Isolation C (Note 7) Each Refueling Outage -

No e =.

• m 6-15 4

Ib

O Q/

b.

AJ

[v )

t.

I' l

TABLE 4 15 o, 24 INSERVICE INSPECTION VALVE TEST PLAN SHELT ASME CODE CLASS 1,2, AND 3 VALVES l

d'AMn c,I[,' talcYM.m 'Ei e s' aYtTakiaU<Eo o?a%o. '

• co" f ,,,,,,,,,,,,,, ,,,,,,,

RCIC Vacuum Pump Discharge-Torus Every Three Months E51-F028 2 2" Check G-7 H-16334 Isolation Each Refueling Outage -

No

( AC C (Note 7) l f E51-F031 2 A 6" M0 Gate ~J-6 H-16334 RCIC Pump Suction-Torus Isolation 0 Every Three Months Each Refueling Outage 35 No ,

l Every Three Months E51-F040 2 AC 10" Check G-5 H-16334 RCIC Turbine Exhaust-Torus Isolation C (Note 7) Each Refueling Outage - No 1-1/2" M0 E51-F104 2 A Gate G-5 H-16334 RCIC Vacuum Breaker-Torus Isolation 0 Every Three Months Each Refueling Outage 15 No "

l-1/2" MD E51-F105 2 A Gate G-5 H-16334 RCIC Vacuum Breaker-Torus Isolation 0 Every Three Months Each Refueling Outage 15 Yes. Note 10 Gil-F003l 2 A 3" A0 Gate 'B-3 H-16176 Drywell Floor Drains-Containment Isolation 0 Every Three %nths Each Refueling Outage 20 No Gil-F004 2 A 3" A0 Gate B-3 H-16176 Drywell Floor Drains-Containment Isolation 0 Every Three % nths Each Refueling Outage 20 No Containment Gil-F019' 2 A 3" A0 Gate E-3 H-16176 Drywell Equipment Drains - Isolation 0 Every Three Months Fach Refueling Outage 15 No Containment Gil-F020 2 A 3" A0 Gate E-4 H-16176 Drywell Equipment Drains - Isolation 0 Every Three N nths Each Refueling Outage 15 No G31-F001 1 A 6" M0 Gate B-2 H-16188 RWCU Pump Suction-Inboard Isolation 0 Cold Shutdown Each Refueling Outage 30 No. Note 23 G31-F004 1 -A 6" M0 Gate B-3 H-16188 RWCU Pump Suction-Outboard Isolation 0 Cold Shutdown Each Refueling Outage 30 No. Note 23 8" Manual .

G41-F001A 3 B Butterfly . D-9 H-16002 FPCCU Discharge from Skinsner Surge Tank 0 Every Three Months N/A - No 8" Manual G41-F001B 3 8 Butterfly D-9 H-16002 FPCCU Discharge from Skinsner Surge Tank 0 Every Three Months -

No N/A Form No 9 793 6-16 l

l- ,,,.

.?*

1 ym ;

'f \

f

(/ U TABLE 4 16 24 INSERVICE INSPECTION VALVE TEST PLAN SHEET OF ASME CODE CLASS 1,2, AND 3 VALVES 2v"4L'a c[jl ocs"c W fion 'Mr"S' . c2 ko. *u"C"o" 9

.. h s'b'E U"E'<STEo 6" Manual G41-F002A- 3 B Butterfly ' F-2 H-16002 FPCCU Pump Suction 0 Every Three Months N/A - No 6" Manual G41-F0028 3 B Butterfly H-2 H-16002 FPCCU Pump Suction 0 Every Three Months N/A - No 6" Manual G41-F019A 3 B Gate D-9 H-16002 FPCCU Inlet From RHR C Every Three Months N/A - No 6" Hanual. -

G41-F019B 3 B Gate D-9 H-16002 FPCCU Inlet fmm RHR C Every Three Months N/A -

No 6" Manual G41-F020A 3 B Gate D-ll H-16002 FPCCU Return to RHR C Every Three Months N/A -

No 6" Manual G41-F020B 3 B Gate D-ll H-16002 FPCCU Return to RHR C Every Three Months N/A -

No 2" Manual P21-F353 - 2 AE Gate 'F-7 H-16015 Demineralizer Water-Containment Isolation LC N/A Fach Refueling Outage -

No 2" Manual P21-F406 2 AE Ga te F-b H-16015 Demineralizer Water-Containment Isolation LC N/A Each Refuelino Outaae -

No 1" A0 P33-F002 2 A Control B-4 H-16276 H2 &02 Analyzer Containment Isolation 0 Every Three Months Each Refuelina Outaae 5 No 1" A0 P33-F003 2 A Contml D-4 H-16276 H2 & 02 Analyzer Containment Isolation 0 Every Three Months Each Refuelino Outage 5 No 1" A0 733-F004 2 A Contml - E-4 H-16276 -H2 & 02 Analyzer Containment Isolation 0 Every Three Months Each Refuelino Outaae 5 No 1" A0 P33-F006 2 A Control G-4 H-16276 Hp & Op Analyzer Containment Isolation 0 Every Three Months Each Refuelina Outaae 5 No 1" A0 P33-F007 2 .A Control H-4 H-16276 Hp & 02 Analyzer Containment Isolation 0 Every Three Months r =.

• m Each Refuelina Outaae 5 No 6-17 v.

.D

h '"% ~

k,l) - .U . J(

V l

i

[' TABLE 4

(~ INSERVICE INSPECTION VALVE TEST PLAN SHEET OF ASME CODE CLASS 1,2, AND 3 VALVES 1 sac - -

I TEST Faaourscv I-r J8AEa b g' c.",'$-

oas"$iUsom 'uTv"e's" oIcf ko. e uscreon gg exaacasa p. ora n Q ,5,l,c,pp;,"dffo,$ o tenace 7e 1" A0 P33-F010 2 A' Control 8-5 H-16276 Hs & 02 Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 No.

l 1" A0 P33-F011 2 A Control D-5 H-16276 H2 &02 Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 No 1" A0 P33-F012 2 A Control H2 & 02 Analyzer Containment Isolation Every Three Months Each Refueling Outage 5 ' No 1" A0 P33-F014. 2 A. Control . G-5 H-16276 H2 & 02 Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 No '

1 " AO .

P33-F015 2 A- Control H-5 H-16276' H2 & 02 Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 No F41-F035A . 3 B 2" A0 Globe B-9 H-160ll HPCI Pump Room Cooler C Note 18 N/A -

No P41-F035B 3' B 2" A0 Globe C-9 H-16011 HPCI Pump Room Cooler C Note 18 N/A -

No 1

P41-F036A 3 8 3" A0 Globe D-9 H-160ll RHR and CS Pump Room Cooler C Note 18 N/A -

No P41-F036B 3 8 3" A0 Globe D-9 H-160ll RHR and CS Pump Room Cooler C Note 18 N/A -

No 1-1/2" AO-P41-F037A 3 B Globe H-8 H-160il RHR Pump Cooler Note 18 C N/A -

No 1-1/2" A0 i P41-F0378 3 B Globe' E-9 H-160ll RHR Pump Cooler C Note 18 N/A -

No 1-1/2" A0-P41-F037C 3. B Globe ' J-8 H-16011 RHR Pump Cooler t

C Note 18 N/A -

No 1-1/2" A0 P41-F037D 3 8' Globe E-9 H-160ll RHR Pump Cooler . C Note 18 N/A -

No re. n. sm 6-18 i

+3** i 4

. 1 A

~

N, N i /

t.

l TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SHEET O, 24 ASME CODE CLASS 1,2, AND 3 VALVES l

4 -

NU tLR gg . Dig (Mapf Kwe if O h NO. F UNC 7 80N ,sE uu g C,T gp eO L O g2- exencise Nore is u axac.c 7e t

P41-F039A 3 B 3" A0 Globe G-8 H-16011 - RHR Pump Cooler C Note 18 N/A - No l

P41-F039B 3 B 3" A0 Globe G-8 H-16011 RI:R Pump Cooler

{-

C Note 18 N/A - No j I

F41-F040A 3 B 2" A0 Globe H-2 H-16011 RCIC Pump Room Cooler C Note 18 N/A - No P41-F040B 3 8 2" A0 Globe H-3 H-160ll RCIC Pump Room Cooler C Note 18 N/A - No '

P41-F042A 3 B- 3" A0 Globe A-10 H-160ll CRD Pump Room Cooler C Note 18 N/A - No P41-F042B 3 8 3" A0 Globe B-10 H-160ll CRD Pump Room Cooler C Note 18 N/A - No P41-F049 3 B 8" M0 Gate F-6 H-160ll Drywell Air Coolers O Cold Shutdown N/A 55 No. Note 24 Every Three Months P41'-F208A 3 B 3" A0 PCV -

D-11001 Service Water Pressure Regulator C (Note 9) No N/A -

Every Three Months P41-F208B '3 B T A0 PCV -

D-11001 Service Water Pressure Regulator l C (Note 9) N/A - No Every Three Months P41-F208C 3 B 3" A0 PCY - D-11001 Service Water Pressure Regulator C (Note 9) N/A - No Every Three Months P41-F208D 3 B 3" A0 PCV ~.- D-Il001 Service Water Pressure ReQulator ' 'C (Note 9) N/A - No 30" M0 P41-F310A 3 B Butterfly -

D-11001 Turbine Building Supply Shutoff iote 0 Cold Shutdown N/A 27 No. Note 24 30" M0 tote P41-F3108 3 B Butterfly - -

D-11001 Turbine Building Supply Shutoff 0 Cold Shutdown 27 No. Note 24 N/A

.r N. m 6-19 i

, fe

.Y'

j' N

[ k' d -

'O- .

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SHEET OF ASME CODE CLASS 1,2, AND 3 VALVES J8M!n- c)[.. oe5Wiim

'M u eda ' *C h*

Excacise movr a unnace 30" MD .

Note P41-F310C 3 B. Butterfly -

D-11001- Turbine Building Supply Shutoff 0 Cold Shutdown N/A 27 No. Note 24 _

30" M0 Note P41-F310D 3 B Butterfly .

D-11001 Turbine Building Supply Shutoff 0 Cold Shutdown N/A 27 No. Note 24 30" MD Note P41-F312 3 8 Butterfly -

D-11001 Dilution Line to Mixing Box C Every Three Months *N/A 27 ' No 10" MO. Note P41-F380A 3 B ,

Butterfly -

D-11001 Reactor Building Supply Shutoff 0 Cold Shutdown N/A 27 No. Note 24 10" M0 P41-F380B 3 B Batterfly -

D-11001 Reactor Building Supply Shutoff 0 Cold Shutdown N/A No. Note 24 l' Every Three Months P41-LOO 3A 3 B Solenoid -

D-11001 Service Water Pump - Cooling Shutoff C (Note 7) N/A - No 1" Every Three Months P41-LOO 3B. 3 B Solenoid -

D-11001 Service Water Pump - Cooling Shutoff C (Note 7) N/A -

No 1" Every Three Months P41-LOO 3C 3 B Solenoid -

D-11001 Service Water Pump - Cooling Shutoff C (Note 7) N/A - No P41-LOO 3D B l' Every Three Months 3 Solenoid -

D-11001 Service Water Pump - Cooling Shutoff C (Note 7) N/A -

No RBCCW to Recirculatior. Pump Containment P42-F051 2 A 4" M0. Ga te P-9 H-16009 Isolation 0 Cold Shutdown Each Refueling Outage 35 No. Note 24 '

RBCCW to Recirculation Pump Containment

-P42-F052 2 A. 4" N0 Gate E-9 H-16009 Isolation 0 Cold Shutdown Each Refueling Outage 35 No. Note 24 2" Manual P51-F513 2 AE .- Globe - F-3 H-16013 Service Air Containment isolation LC N/A Each Refueling Outage - No 2" Manual P51-F514 2 AE i Globe F-3 H-16013' Service Air Containment Isolation LC Each Refueling Outage N/A -

No e =. ms 6-20 h

M' -

. ,+

r I , -l*  ; ,

.

• 2 2 a

c 2 1 1 .

o

. e e e .

.l&

F O c. t t o o t

o n o o o o o o o o o o N N N N N N N N N n N N N 'N

.o c s s s e

s e e e O Y Y Y T

E E G 5 5 5 5 5 5 7 H s k 5 5 5 5 - - -

e g

eg e

g e

g e

g eg e

g e

g e

g e

g e

g a a a a a a a a a a a t t t t t t t t t t t

. u u u u u u u u u u u O O O O O O O O O O O g g g g g g g g g g g

' n n n n n A A n n n n n n i i i i i / / i i i i i i l

f e

u l

f e

u l

f e

u l

f e

u l

f e

u N N l f

e u

l f

e u

l f

e u

l f

e u

l f

e u

l f

e u

e e e e e e e e e e e R R R R R R R R R R R v h h h h h h h h h h h

- c c c c c c c c c c c c s a a a a a a a a a a a t

u E E E E E E E E E E E o

c a e g

r t a s s s s s t s s s s s s a

v 4 h h h h u h h h h h h 5

t t t t O t t t t t t T

n n n n g

n n n n n n o o o o o 8 8 o o o o o o

" M M M M n 1 1 M M M M M M t i

• e e e e l e e e e e e e e 5 e e e e e t t e e e e e e c r r r r u o o r r r r r r a h h h h f N N h h h h h h L T T T T e T T T T T T

= R E y y y y y y y y y y r r r r h r r r r r r N e e e e c e e e e e e v v v v a v v v v v v A E E E E E E E E E E E LS P E T

S L V i 0 0 0 0 0 C C C C C C C C EA TV n E3 o n n n n n g g i

VD o o o o o t L n n a AN i i i i i

_ t t t t t i i l 4 V A, a a a a a d d o n l l l l l l l n s o n 1 E N 2, o o o o o i i o I i o n 2 L s s s s s u u i t i o n -

B O1 B d a t o 6 O

I I I I I B t i A I S a r l a t i T TS t t t t t r r l a o l a t CA n n n n n o o o o s o l a E L e e e e e t t s b I s o l P m m m m m c c I t I s o S C n n n n n a a u d I s NE i i i i i e e - O r d I I D " t a t a

t a

t a t a R R y p

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r a

d r d

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• CC I

C C C C C r r p k t

u b

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a O I t u

b n

RM c c c c S g g ES i i i i i t t O I t t t

.t t e e s s n n SA a a a a a l l .u u i i g g

' N m m m m m n n r r t t n n I

u u u u u I I o o r r i i e e e e e T T e e t t n n n n n d d n n r r P P P P P e e .& & I I e e B B n n l l l l l l l l l I I l l l l l r r l l l l e e e e e e e e e e e s s w w w w w t t w w w w u u y y y y y l l y y y y r . r r r r r r i i r r r r o n D D D D D F F D D D D T T

._ a 6 6 6 6 6 0 O 0 0 0 0 0 0 8 8 8 2 0 0 0 0 0 0

% 8 2

6 2

6 8

2 6

2 6

2 6

0 6

0]

6 0

6 0

6 0

6 0

6 0

6 0

6 S* 1 1 1 1 1 1 1 . 1 1 1 1 1 1 o - - - - - - - - - - - - -

H H H H H H H .H H H H H H Ts 8 8 8 8 7 1 1 2 4 7 8 7 8 D C C G F .G F F G G Y"v

'a F F C

=

u y v v

. k l l 1 l l l l c f f f l l l l l M o o o o e 0r 0r r 0r

.o 0r o

0r o

0m 0r o

0r 0r 0r Or h Ae t Ae 0e lc At n At n At n At n

C

" t t

t At t At n . At n At n At n At n

e o " o " o "2 C o

"2 C o "2 8u 1B "8

1B a " u 6B

" o 1C

" o 2C

" o 2c

" o 2c

" o 2C 1C 1C I

)' c, 'A A A A C

A B B A A A A A A

!u 2 2 2 2 2 3 3 2 2 2 2 2 2

!u OV 8 2 3 4 5 0 A

1 B

1 3 4 3 4 5 6 0

0 0

0 0

0 0

0 2

0 0

0 0

0 0 0 l i

1 1

l i

l i

m 1 1 M F 0

-0 F

F 0

F 0

F 0

F 6

F 6

F 8

F 8

F 8

8 F

F 8

4 F

8 4

w 7 7 7 7 7 4 4 4 4 4 4 .

P P P P P T T T T T T T T r

4 i 1 + ~ ,i' 4

O Lm;). O u

' TABLE 4 INSERVICE INSPECT 80N VALVE TEST PLAN SHEET OF N ASME CODE CLASS 1,2, AND 3 VALVES Ju"Mla f c.I[. ne s*c^anm 'n"a 1"aT oMo. **c""

,,,,c,ss inore s ""* *

• trance T48-F118A 2 A Solenoid G-5 H-16000 Torus Makeup Inboard Isolation 0 Every Three Months Each Refueling Outage 5 Yes. Note 12 1"

T48-F118B - 2 A Solenoid G-5 H-16000 Torus Makeup Inboard Isolation Every Three Months 0 Each Refueling Outage 5 Yes. Note 12 2" A0 T48-F321 - 2 A Contml J-7 H-16000 Drywell Inerting Outboard Isolation C Every Three Months Each Refueling Outage 5 No 2" A0 T48-F322, 2 A Control J-8. H-16000 Drywell Inerting Inboard Isolation C Every Three Months Each Refueling Outage Yes. Note 12 5

2" A0 T48-F325 2 A Contm1 ' H-7 H-16000 Torus Inerting Outboard Isolation ' Every Three Months C Each Refueling Outage 5 No 2" A0 T48-F327 2 'A Control H-8 H-16000 Torus Inerting Inboard Isolation Every Three Months C Each Refueling Outage 5 Yes. Note 12 18" A0 T48-F307 2 A Butterfly C-9 H-16024 Drywell Purge Inlet-Inboard Isolation C Every Three Months Each Refueling Outage No 5

18" A0 T48-F308 2 A Butterfly C-10 H-16024 Drywell Purge Inlet-Outboard Isolation Every Three Months C Each Refueling Outage 5 No 18" A0 ..

T48-F309 2 A Butterfly - E-10 H-16024 Torus Purge Inlet-Inboard Isolation C Every Three Months Each Refueling Outage Yes. Note 14.

5 20" A0 Note Butterfly T48-F310 2 A F-10 H-16024 Torus Purge Vacuum Breaker Isolation Every Three Months C Each Refueling Outage 27 Yes. Note 14 3" A0 Note T48-F311 2 A' Butterfly F-9 H-16024 Torus Purge Vacuum Breaker Isolation Every Three Months C Each Refueling Outage 27 Yes. Note 14 18' A0 .

T48-F318 2 A Butterfly G-4 H-16024 Torus Purge Outlet-Inboard Isolation C Every Three Months Yes, fate 14 Each Refueling Outage 5 18" A0 T48-F319 2 A Butterfly D-4 H-16024 Drywell Purge Outlet-Inboard Isolation Every Three Months C Each Refueling Outage 5 Yes. fete 14 r . =. m m 6-22 g,.

?m

~s

/

.O A

TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN SHEET OF ASME CODE CLASS 1,2, AND 3 VALVES i

NU BE R ' c3 DE SC R eFI BON NTyg gm F UNC T ION

,yLC ,l'F]E g t% D 18" A0 T48-F320 2 A' Butterfly D-3 H-16024 Drywell Purge Outlet-Outboard Isolation C Every Three Months Each Refueling Outage 5 No 18" A0 T48-F323A 2 C Check H-8 H-1 424 Drywell to Torus Vacuum Breaker C Once Per Month N/A -

No 18" A0 T48-F323B 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Month N/A - No 18" A0 T48-F323C 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per N nth N/A - No~

18" A0 T48-F323D 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per N nth N/A -

No 18" A0 T48-F323E 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Month N/A -

No 18" A0 T48-F323F 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker Jnce Per Month C N/A -

No 18" A0 T48-F323G 2 C Check H-8 H-16024 Drywell to Torus _ Vacuum Breaker C Once Per Month N/A -

No 18" A0 T48-F323H 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per. Month N/A -

No 18" A0 T48-F3231 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Month N/A -

No 18" A0 T48-F323J 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per 2 nth N/A - No 18" A0 T48-F323K 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Month N/A - No 18" A0 T48-F323L' 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Month N/A - No Fe,en No S 793 l

l.

i  ?-

l Iilk l

E _.

[/

\_

%- , [ }

D'j ,

V

, TABLE 4-

, INSERVICE INSPECTION VALVE TEST PLAN SHEET 23 OF 24 '

ASME CODE CLASS 1.2. ANO 3 VALVES JuTla '""'****

cd'i ca s"cW'.on 'Or*e? o.?!.o. 'uacpoa *

,$g;',og=4c,o,g IB" A0 T48-F324 2 A- Butterfly D-10 H-16024 Torus Purge Inlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 No 18" A0 T48-F326 2 A Butterfly G-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 No 20" AO - Reactor Building to Suppression Chamber T48-F328A' 2 AC Check G-10 H-16024 Vacuum Breaker C Every Three Months Each Refueling Outage - No 20" A0 Reactor Building to Suppression Chamber ,

T48-F328B 2 AC Check G-9 H-16024 Vacuum Breaker C Every Three Months Each Refueling Outage -

No 2" AO -

T48-F332A 2 A Control E-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 No 2" A0 T48-F332B 2 A Contml 'F-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Months Each Ref teling Outage 5 No 2" A0 T48-F333A 2 A Control E-4 H-16024 Torus Purge Outlet - Inboard Isolation C Every Three Pbnths Each Refueling Outage 5 No 2" A0 T48-F333B 2 A Control F-4 H-16024 Torus Purge Outlet - Inboard Isolation C F ery Three Months Each Refueling Outage 5 No 2" A0 T48-F334A 2 A- Control. B-3 H-16024 Drywell Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 No 2" A0 .

T48-F334B 2 A Control C-3 H-16024 Drywell Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 No 2" A0 T48-F335A 2 A Control B-4 H-16024 Drywell Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 No 2" A0 T48-F335B 2 A Control C-4 H-16024 Drywell Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 No 2"

T48-F338 2 A Solenoid H-2 H-16024 Bypass - Outboard Isolation Every Three Months C Each Refueling Outage 5 No Ferm Nt SF93 6-24 g . _

. {5

/

, ,-\,

\

K;

! r V) ,

'\ _/ .

TABLE 4 INSERVICE INSPECTIOPiVALVE TEST PLAN SHEET OF ASME CODE CLASS 1,2, AND 3 VALVES

~

-S s e c. o,o, . , , , I us" aE *Eacv 5gs uc.o~ ,,coor Ju^4Ma {j* ct,'.. oelc^aWmN co.A a vEs M Ng C T ION EXERCISE psOTE H EEAMAGE 2*

T48-F339 2 A Solenoid H-3 H-16024 Bypass-Inboard Isolation C Every Three Months Each Refueling Outage 5 No 2"

T48-F340 2 A Solenoid D-4 H-16024 Bypass-Outboard Isolation C Every Three Months Each Refueling Outage 5 No 2"

T48-F341 2 A Solenoid D-4 H-16024 Bypass-Inboard Isolation C Every Three Months Each Refueling Outage 5 No S

Ferm No S793 6-25 A*

'?

k n a o e e i . . r l t e e a C e

a nnv e c s e b v l v i f

iil l

dv a t u

e m r o

ts e

e ep by l lC a i ee h i b t v c gss s t o sv l i wep d e rii t tl l e l e k e p ach e e c sa lh ih ty ci S h rt h k a ev it wt itt ef ce t o e t w r s hi l sxg r c e tr ,ee cr a i en n t ps to

.e c d i i S l . me if io ,f . rht et ev i et n

l) uh

,m rms t

v e l n ebs us pt erv

. pe h v e o . fh gr ra eae woi d mb c l tt i s t er vrt e i e ao t t on no vg eg oft vnr a s to if eo woe H a t

o sl l

T no r e m r wr orv mv n ni y faf e t g ue op H pi

.arre e

ew b ec o

p y

n3 dl H t

t 0gs s

p oer d i

l te s

t i/

pe sa b

.se .tasv 2on 4ro i e eiv y t i c hc 0er 3pc w yu r r ,i a i pn ti 0t 2t e r t r i o nl 2 4 s -

l s i Vta e u mta p b e op 4 e 3en h

l o al )

q ain s a rd mp 3t - t o Ws t mc r

a e r

e r r e

ue se e a

Vr

- a Vac Wr a I en ti o ( the d p sc W f oe 0 s gt a e o ex et ro Ik I

k oeg s nv 1 s ul tn s l 5 a noa h p p re hn a fan sai e sa 3 i r t fe oei trt l iv - s ahe l m o e ol l n

n h V i mtl a u wt yr s g eku l

u t , W b m p o ra st ttn mas fv e I s e

ewa hon r

o g l t o

e vs t n ne nni eet eee d

e oi y v tl o n n tn ee em mml rl "

i t b l fs i c( m mn enu i ut ,

f ya a r a g r e di ei ris qnc i t n d v oae r n u jn et ra iae ees c i r e f i d bw i it ut r qn rmi e l e r d e r uo f e un nd 4 p it i e rvo u s sd ik qo eo ,

s bl u t ean d h t ro er ec r

rcc s

ei hae S aa r

q a kh e n t

n du e eei tth E y e u a lh vt nt E c en r t eyr e o us S eh hhd 6

)  :

n pa c rl a v m o e ht tt ho 2

{v tct L

T e o s a . bl o cd b t e a -

u a ae r e n hnh i B s 0 wee l 6 0 q eA . e1 mmr ure p e r

no oc l e l r hi t

tit hs A e h t s v6 i etn T

N f

r t s0t

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i3 s -

oV uoh cnT a

b e h t

i ta a

i u wss id wes wdt ese ea c nn u

e n1 e lW vt l y rg ee es css aio r en vr ce nen d t h a4e v pI o . l nr aru rd t e3t l x an0 i e pi l p oed ma a ef 2 w v oru a ve ad dd csn t Vr v o ss5 e dd rdo cse a eW _ l ae3 e rd h ra o a t. aet vIk f os o- v n e lt o c- r t i a e rt sdV l e wd o cs css ndl s tfe i t n e W a v oe rg ca aad n idl e iol l ne vdI v e pt t n a t s: e om rn r p

s ni no n nne iot d ai w

e ose pt v r ce r

eaf s o d

e l e at ot ca ii i es k nl d di s s e m l t dte tae o yea n iu ets o b re eu dc ecr s r r bmv a uq vht l . . ob rg ee teu enu t e qe l gn cn l s n ue tr srs tos i s s yre y ir aie o l e l sr si ei s ete

- fih t l vl m yi i v gl s ed tde l i ut e e e l t wl ni ey t r bcrep l rq f yh kgr l a a iw rl e eep a ar ev r pt es bs tr u eef bt cni oit f vro s d ns eiu htq me rp v

l e ut di se c br e tes rt nds a oee r ad cae oo as ir tv ove n e thc o te cr n ve e , hr oe . net aet s t n f se di f h ve to nrs nr cs i l a c ede so st l r c n t a e re ahm y ex snh i i ao f aes ceh eeh vvT t ct r c h e oit he ho vf osi che hT l e s ii o n t l td tt e tt et ar e twf e h coh o sr y e v v t c r u fc nt fm fe i e tt vne l n .

es e

aee rcp q

e oi y i o g ol b

hh tT ii li g a a ais v t lht h l sw l ots s pn r gw l a _ yn ya it vdk ds r e i ae f n ahe ti tc f ba ea eee t nt c tdh i m c il ii o e . ah ete btt os ni r ort t t c. rtn l o ll rt tsl e e nocg s s2 oia i o ip gr e ae l ee o cd g x e e n d bc bp nu pe gtC gt g e scn t er a aa is oru a ea iai t A. sco rn r ns ske skk stk isa e r e e4 inc ew po et po ee pr hn es i ap i aa hey hee hee h tnu h h hic v T Iid T T4 TSa Od On Op Te Tl t Tll Ttl 2

1 2 3 ~4 5 6 7 8 9 0 1 1 1 1

m W '

. ^

I '

b ,

TABLE 4' NOTES .

Page 2

13. 'This globe valve cannot be tested in accordance with the requirements of IWV-3420. However, it will be leak tested in the reverse direction as addressed in the containment leak rate test program for the type C leakage tests.

14. This. butterfly valve cannot be tested in accordance with the requirements of IWV-3420. However, it will be leak tested in the reverse direction as addressed in the containment leak rate test program for the type C leakage tests. The same seating surface is tested when the test pressure is applied from either direction.

15. The operability of this flow-control valve will be verified during equipment tests to ensure it is functioning ' properly. Stroke times are not applicable for this valve.

16. It is not. practical to verify by. positive means the operability of the locked-open stop check valve in

. accordance with the requirements of IWV-3520. However, valve closure will be verified during

.perf ormance of the valve leak rate test.

17. It is not practical to verify by positive means the operability of the normally closed check valve. As an alternative, valve opening will be verified during pump test and closure during the valve leak-rate test.

18. This valve is automatically controlled by the equipment that it services. As an alternative, valve operability will be verified during equipment tests. Stroke times are not applicable to this valve.

19. Tested per the requirements of ASME PTC 25.2-1966.

20. This-pressure relief valve cannot be tested in accordance with the requirements of IWV-3420. However, it will be leak tested in the reverse direction as addressed in the containment leak rate test program for the type C leakage tests.

21 . This containment isolation valve will not be leak tested as addressed in the containment leak rate test program for the type C leakage tests. Therefore, complete closure will r.st be verified.

22. This testable check valve cannot be opened against reactor pressure using the test switch. Therefore, it will be tested during a cold shutdown (not to exceed once/9 months).

23. Closure of this ' valve during power operation would interrupt or trip an essential process system.

Therefore, it will be tested.during a cold shutdown (not to exceed once/3 months).

aw

O -

d i

u p q i i q

u l e . y n b l o d a i n i t a t . a t n) r s .

es e e sh p g v st o n l a

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om e .

w) d u

s 3 os i h

w/ ph d oe gn t

t e . t l c fn no a c. r o im r2 o r r t f ed u3 te d/ sn A. t ae e o4 s wcx dc en m t e

e4 ge n

mo r

d n e i o od eo s lt fe bi i o re t c ot ec ya r co px l c e n e ni x t( e of e p bo i un t nc t rw ro t

ot ae cp s

r ed tt no nn e S i f

o d nu ih ld ul s

ld a(

c ew vo

.n vl l a ac vi kh n

h t

e g

n 8

2 oo at cc 6 wc vu h hT ee i r

na ns c u ig o o h d id et tn tl li d ai ao pw e rr l c m h eu o i e s pd sa sc i o i g

n l b

d da re pn ed a et oi sr t s

ws or oo e oe l u l c pt n

d cc e ge a

od y b.

nb i e l n i tt li l rl as a l a

ul l e mt di ut rs h s

w c . oe e re nt e

vt ib li c sy m a

v ,

el it i t

rl hi

.e i tl e

sr io i sw fb i

k hf ht oa o t e ti r r r ye t fe f', tp s ch oer io e T l n

e r

eo il rf bo i u . ue ar l e

st sr rt s

on oe en po a 4 l e lh o lee. 3 Cm CT Oc B ES BTg . . . .

AOa 4~ 5 6 7 2

TNP 2 ' 2 2 j