ML20092P561

Second Interval Inservice Insp Program, Final Rept

ML20092P561
Person / Time
Site:	Peach Bottom
Issue date:	02/29/1984
From:	Alan Anderson SOUTHWEST RESEARCH INSTITUTE
To:
Shared Package
ML20092P558	List: ML20092P557 ML20092P561
References
PROC-840229-01, NUDOCS 8407090097
Download: ML20092P561 (150)

Text

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SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510 6220 Culebra Road San Antonio, Texas 78284 PEACH BOTTOM ATOMIC ' POWER STATION, UNITS 2 AND 3, SECOND INTERVAL INSERVICE INSPECTION PROGRAM FINAL REPORT SwRI Project 7841 l

Prepared for

' O Philadelphia Electric Company 2301 Market Street Philadelphia, Pennsylvania 19101 February 1984 l

Prepared by Approv by kb - .<

Alfred R. Anderson Way'ne T. ch Project Manager Director inspection Engineering Section Department of Engineering Services Quality Assurance Systems and Engineering Division G

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4 PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3, SECOND INTERVAL INSERVICE INSPECTION PROGRAM i

! Table of Contents 7

f. age TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv

1. INrRODuCT10N . ....................... 1-1 l

l 1.1 General ....................... 1-1 1 1.2 Responsibility . . . . . . . . . . . . . . . . . . . . 1-1 <

i 13 Records ....................... 1-2 l 1-2 1.4 Methods of Examination . ...............

i 1 4.1 Visual Examination . . . . . . . . . . . . . . 1-2 4

1.4.2 Surface Examination . . . . . . . . . . . . . 1-2 i 1 4.3 Volumetric Examination . . . . . . . . . . . . 1-3

! 1.5 Classification of Components . . . . . . . . . . . . . 1-3

1.6 Ropair Procedures . .. ............... 1-3 1 1.7 Baseline Examinations . ............... 1-4

2. CLASS 1 PROGRAM ...................... 2-1 1

2.1 Identification of Components . . . . . . . . . . . . . 2-1 j 2.2 Examination Prograa . . ............... 2-1 ,

i 1 2.2.1 Reactor Pressure Vessel . . . . . . . . . . . 2-2 2.2.2 Piping . . . . . . . . . . . . . . . . . . . . 2-5

2.2.3 Pumps .................... 2-7 j 2.2.4 Valves . . .... . . . . . . . . . . . . . . 2-8 i

l 2.3 System Pressure Tests . ............... 2-9

[ 2.4 Requests for Relief from Section XI Requirements . . . 2-10 t

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3. CLASS 2 PROGRAM . . . . . . . . . . . . . . . . . . . . . . . 3-1 i

, 3.1 Identification of Components ... . . . . . . . . . . . 3-1 I

I 3.1.1 . Standby Liquid control System (SLC) ISI-M-358. . 3-1

! 3.1.2 Reactor Core Isolation Cooling System (RCIC) j -ISI-N-359 . .. . . . . . . . . . . . . . . - 3-1 3.1.3 Residual Heat Removal System (RHR) ISI-N-361 . 3-2

! 3.1.4 ' Core Spray cooling System ISI-M-362 . . . . . 3-2 3.1.5 High Pressure Coolant Injection System (HPCI) ISI-M-365 . . . . . . .-. . . . . . . . 3-2 3.1.6 Fuel Pool cooling and Cleanup System ISI-M-363 - 3-2 3 1.7 Control Rod Drive Scram Discharge Volume Piping

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n' (CRD SDVP) ISI-M-356 and ISI-M-357 . . . . . 3-2 N- 3.1.8- Main Steam (MS) ISI-M-303 . - . . . . . . . . . 3-3 J

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P_ age 3.2 ' Examination Prograa . . . . . . . .......... 3-3 3.2.1 Pressure Vessels . . . ............ 3-3 3.2.2 Piping . . . . . . . . . . . . ........ 3-4 3.2.3 Pumps ... .. ............. .. 3-4 3.2.4 Valves . . . . . . .............. 3-5 3.3 Systes Pressure Tests ................ 3-5

4. CLASS 3 PROGRAM ....................... 4-1 4.1 Identification of Components . . . . . . . . . . . . . 4-1 4.1.1 Emergency Service Water System (ESW)

ISI-N-315 .. ............... 4-1 4.1.2 High Pressure Service Water System (HPSW)

ISI-N-315, 361 . . . . . . . . . . . . . . . 4-1 4.1.3 Emergency Cooling System ISI-M-330 . . .... 4-1 4.1.4 Fuel Pool Cooling and Cleanup System ISI-M-363 .... ............. 4-1 4.2 Examination Prograa ...... ...........-

4-2 4.3 System Pressure Tests ................ 4-3 4.4 Request for Relief from Section XI Requirements . . - . 4-3

5. CLASS 1. CLASS 2. AND CLASS 3 COMPONENT SUPPORT PROGRAM .. 5-1 5.1 General ....................... 5-1 5.2 Inservice Inspection Program for Class 1, Class 2, and Class 3 Component Supports . . . . . . . . . . . . . 5-1 5.3 Request for Relief from Section XI Requirements ... 5-1

6. INSERVICE TESTING OF PUNPS, . . . . . . . . . . . . . . . . . 6-1 6.1 General . . . . . . . . . . . . . . . . . . . . . . .- 6-1 6.2 Inservice Testing Program for Class 1, Class 2, and class 3 Pumps . . . '. ...............

6-1 6.3 Requests for Relief from Section XI Requirements . . . 6-1

7. INSERVICE TESTING OF VALVES ................ 7-1 7.1- General . . . . . .'. . . . . . . . . . . . . . . . .- 7-1

, 7.2 Inservice Testing Program for Class 1. Class 2, and Class 3 Valves .'. . . . . . . . . . . .'. . . . 7-1 7.3 Requests for Relief from Section XI Requirements . . . 7-2 APPENDIX A - Inservice Inspection Boundary Drawings

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1 TABLES i Table No. Title g i

j 2.2-1 Inservice Inspection Program - Class 1 Components 2-13 3.2-1 Inservice inspection Program - Class 2 Components 3-7

- 4.2-1 Inservice Inspection Program - Class 3 Components 4-5 l 5.2-1 Inservice Inspection Program - Class 1, Class 2 l and Class 3 Component Supports- 5-2 t

6.2-1 Inservice Testing Program - Class 1, Class 2, and l Class 3 Pumps 6-2 i

1 l 7.2-1 Inservice Testing Program - Class 1, Class 2, and l Class 3 Valves 7-8 l

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(v ) 1. INTRODUCTION 1.1 CENERAL This program defines the second 10 year interval inservice examina-tion (ISI) requirements for Class 1, Class 2, and Class 3 components and inservice testing of pumps and valves for Philadelphia Electric Company's (PEco) Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3. The second 10 year intervals begin on July 5,1984, and December 12, 1984, respectively.

This program has been developed as required by Paragraph 50.55(a) of 10CFR50 following the guidance of the American Society of Fkchanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI " Rules for Inservice Inspection of Nuclear Power Plant Components."

In accordance with 10CFR50, this program is in compliance, where possible, with the applicable requirements of 1980 Edition of Section XI with Addenda through Winter 1981. Although the basic plant design, accomp-lished prior to December 1969, is not totally consistent with examination requirements of later codes, every attempt has been made to obtain maximum compliance. For instances where 100 percent compliance is not feasible, alternative examinations and tests have been proposed which will satisfy the intant of the Code. This program identifies both the areas for which

(~'S compliance can be achieved and areas for which compliance cannot be

( _, ) achieved with proposed alternative methods of assurance of system integrity.

It should be noted that 10CFR50.55a(b), 2(iv) also defines criteria for the selection of Class 2, CateEory C-F, welds. These criteria are as follows:

" Pressure-retaining welds in ASME Code Class 2 piping (applies co Tables IWC-2520 or IWC-2520-1, Category C-F). (A) Appropriate Code Class 2 pipe welds in Residual Heat Removal Systems, Emergency Core Cooling Systems, and Containment Heat Removal Systems, shall be examined. The extent of examination for these systems shall be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, and paragraph IWC-2411 in the 1974 Edition and Addenda through the Summer 1975 Addenda of Section XI of the ASME Code."

These criteria will be applied for these systems during the second 10 year interval.

1.2 RESPON31BILITY As owner of the plants, PECo bears the overall responsibility for the performance of the ISIS. Certain nondestructive examinations will be performed by a qualified examination agency. The results and evaluation

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os the examinations will be reported to PEco for final evaluation and disposition.

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() 1.3 RECORDS Records and doctmentation of all information and inspection results, which provide the basis for evaluation and which facilitate comparison with results from previous and subsequent inspections, will be mm.intained and available for the active life of the plant in accordance with Sec-tion XI, IWA-6000.

1.4 METHODS OF EXAMINATION Examination methods to be used for the ISIS are visual, surface, and volumetric. Personnel performing nondestructive examinations will be qualified with a written procedure prepared in accordance with the American Society for Nondestructive Testing (ASNT), " Recommended Practice SNT-TC-1A, Supplements and Appendices," as applicable for techniques and methods used.

1.4.1 VISUAL EXAMINATION Visual examinations (VT) will be performed in accordance with IWA-2210 which defines four types of VT examinations. These types of VT examinations are summarized as follows:

(1) VT-1 examinations shall be conducted to determine the s

condition of the part, component, or surface examined.

('- The examination shall determine conditions such as cracks, wear, corrosion, erosion, or physical damage on the surfaces of the part or components. This type of examination may be performed by direct or remote methods as defined in IWA-2211.

(2) VT-2 examinations shall be conducted to detect leakage (or abnormal leakage) from pressure retaining compo-nents during system pressure or functional tests.

(3) VT-3 examinations shall be conducted to determine general mechanical and structural conditions of compo-nents and their supports such as the preservice of loose parts, debris or abnormal corrosion products, wear, erosion, corrosion, and the loss of integrity at bolted or welded connections.

(4) VT-4 examinations shall be conducted to determine conditions related to operability of components or devices, such as mechanical and hydraulic anubbers, components supports, pumps, valves, and spring loaded and constant weight hangers.

1.4.2 SURFACE EXAMINATION rx A surface examination is performed to detect the presence of

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) surface cracks or discontinuities. It may be conducted by either magnetic 1-2

O V particle (MT) or liquid penetrant (PT) techniques where the nurface condi-tions, material, and accessibility permit such an examination.

1.4.3 VOLUMETRIC EXAMINATION A volumetric examination is performed to detect the presence of discontinuities throughout the volume of material. Two such volumetric techniques are radiographic (RT) and ultrasonic (UT) examinations.

For volumetric examinations, the major emphasis in this pro-gram is placed on the use of UT methods for the following reasons:

(1) Other work can be conducted in the area where UT examinations are being performed, thus potentially reducing outage time.

(2) In some locations, background radiation levels would preclude RT examination.

(3) Hethods have been developed to permit remote examina-tion with minimum occupancy time in certain areas.

(4) Records have been obtained utilizing UT to indicate pre-operational conditions for comparison with subse-quent examinations.

U 1.5 CLASSIFICATION OF COMPONENTS Components have been classif ted for purposes of inservic.e inspection in accordance with the requirements of 10CFR50.55a, Section XI of the Code, ,

and the guidance contained in Regulatory Guide 1.26.

It must be noted that the classification of components as equivalent to ASME Classes 1, 2, or 3 implies equivalency for purposes of inservice inspection only and does not imply that the components were designed in accordance with ASME requirements. Since most of the basic plant design was accomplished prior to December 1969, codes and standards applicable at that time were used as set forth in PEco's TSAR.

ne component classification is shown in the ISI-M-300 series of fig-ures which are included in Appendix A. We ISI boundary drawings are Pipind and Instrumentation Diagrams (P& ids) marked up to define the inservice inspection boundaries. Certain notes and details not related to inservice inspection have been deleted.

1.6 REPAIR PROCEDURES Repairs to the pressure retaining boundary of ASME Classes 1, 2, or 3 (equivalent) components will be performed in accordance with IWA-4000 by utilizing PECo-approved procedures which comply with the Code applicable to the construction of the component.' A repair program will be developed (o) 1-3

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in accordance with IWA-4130. Repair procedures for quality assured compo-nents will be reviewed by an authorised Code inspector prior to implementa-tion. Repair work in progress will also be subject to surveillance by an l authorised inspector. l l

1.7 BASELINE EXAMINATIONS  !

The construction code referenced in Paragraph IWA-3100(b) is inter- i preted at Peach lottoa to mean the 1968 Edition of ASME Section III. This l approach will maintain the necessary consistency between the baseline exas-inacions and future ISI examinations to meet the intent of ASME Sec-tion XI. Acceptance of this interpretation was requested from the NRC by f correspondence dated February 19, 1980. Approval of this request was [

granted by the Nic in correspondence dated May 2,1983 (J. F. Stols, NRC, to E. G. Bauer, J r. , PECo). The NRC evaluation concluded that it would be impractical to discard the present data bank in favor of establishing a new evaluation criteria, especially where it is based on earlier Sec-  ;

tion III Code requirements.

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l l l \s ,/ 2. CLASS 1 PROGRAM 2.1 IDENTIFICATION OF COMPONENTS The ASME Class 1 (equivalent) components are outlined on ISI-H-331 and further details are shown on the individual system diagrams. The reactor pressure vessel (RPV) and selected components in the following systems are included (1) Main Steam (2) Main Recirculation (3) Control Rod Drive Hydraulic Return (4) Feedwater (5) Residual Heat Removal (6) Reactor Water Cleanup (7) Reactor Core Isolation Cooling (8) Core Spray (9) High Pressure Coolant Injection (10) Standby Liquid Control In those systems, the Class 1 boundary includes the piping within the drywell and extends to the first valve outside containment. This is an acceptable isolation valve per the Code except in the case of the feed-(~s) water supply and reactor water cleanup, where the first valve outsida containment is a simple check valve.

(G l This Class 1 boundary was defined in the initial Inservice Inspection Program, was approved by the regulatory authority based on design prior to Code requirement, and formed the basis upon which the plant was licensed and from which baseline data was taken. Consequently, this boundary remains unchanged in this revised program.

It should be noted that, in accordance with IWB-1220(a), components and piping containing water,1-1/2 inches in diameter and smallac, and components and piping containing steam, 3 inchen in diameter and smaller, have been exempted on the premise that the amount of fluid lost in the event af a rupture can be replenished by the normal makeup systems which are operable f rom onsite emergency power. Portions of the following piping systems that fall into this category are Jet Pump Instrueentation Lines, Standby Liquid Control System, Control Rod Drive Hydraulic System, and Instrumentation Lines. These exempted components and piping will be subject to VT examination per Table IWB-2500-1, Category B-P.

l 2.2 EXAMINATION PROGRAM The examinations planned for the second 10 year interval are dis-cussed below for the RPV and Class 1 piping, pumps, and valves. The exami-nation areas have been separated into categories in accordance with the 1980 Edition of ASME Section XI with Addenda through Winter 1981. The e-'si requirements are discussed below and are susmarized in Table 2.2-1.

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/~N 2.2.1 REACTOR PRESSURE VESSEL Category B-A - Pressure-Retaining Welds in Reactor Vessel Item Bl.10 Shell Welds Due to plant design,100 percent of the weld length cannot be examined. See Request for Relief, Subsection 2.4.1. Mechanized UT will be performed to the extcut practical for Code-required circumferential and longi-tudinal wolds in the RPV beltline regions. Ibnual UT will be applied where feasible. These examinations may be performed at or near the end of the inspection interval.

Item 81.20 Head Wolds Heridional and circumferential seas welds in the bottom head will be considered individually for physical accessibility and radiation levels. The welds on the closure head are accessible for volumetric examination l

when the head is removed for refueling. These exami-nations may be performed at or near the end of the inspection interval.

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) Items 81.30 and B1.40 Shell-to-Flange and Head-to-Flange l

The shell-to-flange weld will be examined ultrasonically from the seal surface. The head-to-flange weld is available for UT and NT examination when the head is removed for refueling.

Category B-D - Primary Nossle-to-Vessel Welds and Nosale Inside Radius Section--Items B3.90 and 53.100 These RPV nozzle welds are accessible for UT examination from the outside surface of the RPV when the surrounding sec-tions of the sacrificial shield and insulation are removed.

Permanent tracks are mounted on the Recirculation Outlet (N1), Recirculation Inlet (N2), Main Steam (N3), Fetdwater (N4), and Core Spray (NS) nossles for mechanised UT exaw-instion of these welds and inside radius sections. Closure head nossles are readily accessible for UT examination when the head is removed for refueling.

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Category B-E - Vessel Penatrations, including Control Rod Drive and Instrumentation Penetrations--

Items B4.11, B4.12, and B4.13 A VT-2 examination will be conducted for evidence of leakage of partial penetration welds in the RPV in accordance with IWA-5240.

Category B-F - Nozzle-to-Safe End Welds--Items B5.10 and B5.20 There is a dissimilar metal weld between the carbon steel nosale forgings and the piping system on some nozzles in the RPV. Access to these dissimilar metal welds for volumotric and surface examinations will be provided for in the same manner as for the nozzle-to-vessel primary welds.

t Category B--G Pressure-Retaining Bolting Greater than I Two Inches in Diameter Item B6.10 Closure Head Nuts The closure head nuts will be removed and available for an augmented volumetric examination in accordance with IWA-2240 requir.ments. An augmented volumetric examina-I

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\_,/ tion will be performed on the thread and thread root areas in lieu of a surfaca examination.

! Item B6.20 Closure Ikad Stude, in Place l <

Closure head studs which are not removed will be sub-jected to a volumetric examination in place.

Item B6.30 Closure Studs, When Removed l

Not all of the closure studs are scheduled to be removed during any one refueling. However, during the course of the interval, all stude which are removed will be subjected to both volumetric and surface examination.

Item B6.40 Threads in Flange Threaded areas in the vessel flange will be subjected to volumetric examination.

Item B6.50 closure Washers and Bushings A VT-1 examination will be conducted to determine the condition of the washers.

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's_/ Category B-G Pressure-Retaining Bciting--Item B7.10 This category applies to bolting two inches and less in diameter. There is no botting smaller than two inches in diameter in the RPV.

Category B-ll - Integral Attachments for Vessels--Ices 88.10 The RPV is supported on an integrally welded skirt below the shell-to-lower head circumferential weld.

Also, accessible areas on the RPV stab 111:er brackets will be examined. These attachments are subject to a volumetric or surface examination, as applicable.

Category B-N Interior of Reactor Vessel--Item B13.10 A VT-3 examination will be performed on accessible areas above and below the Reactor Core in accordance with the Code.

Category B-N Integrally Welded Core Supports, Struc-tures, and Interior Attachments--Items 813.20 and B13.21

[ ) VT-1 and VT-3 examinations will be performed on

\- / accessible areas in accordance with the Code.

Category B-N Removable Core Support Structures--Item 813.22 A VT-3 examination will be performed on the visually l accessible surfaces of the core support structure.

Category B Pressure-Retaining Welds in Control Rod i

llousings--Item 514.10 l

Ten percent of the peripheral Control Rod Drive housings will be examined by volumetric or surface examination, as applicable.

Category B-P - All Pressure-Retaining Components--Itene B15.10 and 815.11 Components exempted from volumetric and surface exami-nation will be visually examined (VT-2) for evidence of leakage during system leakage and/or system hydrostatic tests (1WB-5221, IWB-5222). ,

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(v) 2.2.2 PIPING f Unless exempted under IWB-1220 and thus subjected to a VT examination under Category B-P, pressure piping will be examined in accord- r f

ance with the items as listed below, with the exception of t l (1) Areas within the containment penetrations, l (2) Cast fittings and structures which are not amenable to UT examination and which are in a system which cannot be drained without draining the RPV, and l

(3) Any weld which during the preservice examination (PSI) i was found not suitable for UT examination (and contin- .

uous evaluation indicates that the state-of-the-art I techniques do not allow UT examination) and which can- ,

not be radiographed due to (a) geometry and/or inter-  ;

forence from surrounding structures, or (b) the systes cannot be drained without draining the RPV.  ;

Category B-F - Pressure-Retaining Dissimilar Metal Welds f f The dissia11ar metal welds joining the piping safe ends to I the RPV are included in the examination of the RPV nossle-

! to-safe end welds (Items 35.10 and 55.20). There are other l

O disais11ar metal welds in the system where lines change from carbon steel to stainless steel. These welds will be sub-jected to voltasetric and surf ace examination.

l Ites 53.130 Dissimilar metal butt welds in piping equal to or greater than four inches in disaster will be subjected to surface and valueetric examination.

Ites 35.140 Dissimilar metal welds in piping less than four inches in diameter will be subject to surface examination.

Ites 55.150 Dissimilar metal socket welds in piping will be subject i to surface examination.

l l Category 5-0 Pressure-Retaining Bolting Greater Than l Two Inches in Diameter--Items 36.150, 56.160, and 36.170 There is no pres.sure-rataining botting greater than two inches in diameter in these piping systems.

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U Category B-G Pressure-Retaining Bolting Two Inches and Less in Diameter--Item B7.50 The bolting in this category will be examined visually (VT-1) either in place under tension, when the connec-tion is disassembled, or when the bolting is removed.

i Category B-J - Pressure-Retaining Welds in Piping Items B9.11 and B9.12 Circumferential and Longitudinal Welds in Piping Four Inches or Larger in Diameter Circumferential and longitudinal welda in pressure-retaining piping and fittings will be subjected to volu-metric and surface examination.

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Item B9.21 Circumferential Welds in Piping Less Than Four Inches in Diameter Circumferential welds in pressure-retaining piping and fittings will be subjected to surface examination.

Item B9.31 Branch Pipe Connection Welds Four Inches and Larger in Diameter i Branch pipe connection welds four inches and larger-in diameter will be subjected to volumetric and surface

. examination.

Item B9.32 Branch Pipe Connection Welds Less Than

.Four Inches in Diameter

, ' Branch pipe connection welds less than four -inches in dismeter will be subjected te surface examination.

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Item B9.40 Socket Welds

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Socket welds will be subjected to surface examination.

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" _T Category'B-K-1 ' Integral- Attachments for Piping--Item B10.10

, 7. x 'A y I Integially. welded ~ attachments'whose base material thick-L l1 , ( , ness is 5/8 inch or greater will be subjected to volu-(' j

• inetric or surface examination as applicable.

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All'jressure-Retaining Compenents-Items

% B15.50 an,d B15.51

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s .; Pressure-retaining, . .. boundaries for p;ipe components

. a. - e. 9*~.. E exempted from volumatric or surfat 3. examination under,

% 'IWB-1220 will be visually-(VT-2)l, examined for evidence

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of leakage during system leakage and/or system hydro-static tests (IWB-5221, IWB-5222). I 2.2.3 PUMPS l

- Category B-G Pressure-Retaining Bolting Greater Than Two Inches in Diameter Item B6.180 Bolts and Studs Bolting greater than two inches in diameter will be examined volumetrically in place under tension, when the connection is disassembled or when the bolting is removed.

d Item B6.190 Flange Surface Flange surfaces will be visually (VT-1) examined when j the connection is disassembled, with particular atten-tion to the annular surface for one inch around each stud hole.

-Item B6.200 Nuts, Bushings, and Washers

] Nuts, bushings, and washers will be visually (VT-1)

, s) examined in place under tension, when the connection is disassembled .or when the bolting is removed.

Category B-G Pressure-Retaining Bolting Two Inches and Less in Diameter--Item B7.60 There is no pressure-retaining bolting two inches or less in diameter in the main recirculation pumps.

Category B-K Integral Attachments for Pumps--Item B10.20 Integrally welded attachments will be subjected to either volumetric or surface examinations.

Category B-L Pressure-Retaining Welds In Pump

• Casings--Item B12.10 There are window welds within.the pressure-retaining areas of the pumps which will be subjected to. surface examination in lieu of ultrasonic examination. See Re- *est for Relief, Subsection 2.4.2.

Category B-L Pump Casings--Item B12.20 i .

i The only pumps in this category subject to examination

['~Ng,,) are those in the Reactor. Recirculation System. An ultrasonic surveillance program will be implemented as 2-7

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N. / the primary alternative examination. See Request for Relief, Subsection 2.4.2. VT-3 examinations will be scheduled and performed when the pumps are disassembled for maintenance reasons.

Category B-P - All Pressure-Retaining Components--Items B15.60 and B15.61 Pressure retaining boundaries for pump components exempted from volumetric or surface examinations under IWB-1220 will be visually (VT-2) examined for evidence of leakage during system leakage and/or system hydro-static tests (IWB-5221, IWB-5222).

2.2.4 VALVES Category B-G Pressure-Retaining Bolting Greater Than Two Inches in Diameter--Item B6.210 Bolts and studs will be examined volumetrically in place under tension, when the connection is disassembled or when the bolting is removed.

Item B6.220 Flange Surface When Connection Disassembled

() Flange surfaces will be visually (VT-1) examined when the connection is disassembled with particular attention to the annular surface for one inch around each stud hole.

Iten B6.230 Nuts, Bushings, and Washers Nuts, bushings, and washers will be visually (VT-1) examined when the connection is disassembled.

Category B-G Pressure-Retaining Bolting, Two Inches and Less in Diameter--Item B7.70 Belts, studs, and nuts two inches and less in diameter will be visually (VT-1) examined in place under tension, when the connection is disassembled or when the bolting is removed. j Category B-K Integral Attachments for Valves--Item B10.30' Integrally welded attachments will be subjected to either volumetric or surface examinations.

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f3 k/m Category B-M Pressure-Retaining Welds in Valve Bodies--

Items B12.30 and B12.40 There are no valves in the system with pressure-retaining welds.

Category B-M Valve Bodies--Item B12.50 For valve bodies excceding four inches nominal pipe size, an augmented UT Surve111nnce Program will be implemented as the primary alternative examination. See Request for Relief, Subsection 2.4.3. The areas subject to VT-3 examination include the internal pressure boundary surfaces. Code-required coverage would include one of each group of valves of the same structural design and t manufacturing method, maaufacturer, and function in the system. Valves in this category will be examined when disassembled for maintenance purposes.

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. Category B-P - All Pressure-Retaining Components--Items B15.70 and B15.71 Valve components exempted from volumetric or surface

~ ~ examination by IWB-1220 will be examined visually (VT-2) for evidence of leakage during the system leakage and/or system hydrostatic tests (IWB-5221, IWB-5222).

2.3 SYSTEM PRESSURE TESTS 2.3.1 SYSTEM LEAKAGE TEST Class I components will be subjected to a system leakage test 1dB-5221 prior to startup following each reactor refueling outage at a test pressure not less than system nominal operating pressure at 100 percent rated reactor power. The tests scheduled to be performed during tha second 10 year interval are shown in Table 2.2-1.

2.3.2 - SYSTEM HYDROSTATIC TEST Class 1 components will be subjected to a system hydrostatic-test at or near the end of the' inspection interval at a test pressure approximately 30 psi below the lowest relief valve . setting but not less than 1.05 times the system nominal operating pressure at 100 percent rated reactor power. At test temperatures above 350*F the test. pressure may be b ' adjusted in accordance with Table IWB-5220-1. The test scheduled to be

- performed during the second 10 year interval is shown .in Table; 2.2-1.

, /"'

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2.4 REQUESTS FOR RELIEF FROM SECTION XI REQUIREMENTS 2.4.1 REQUEST FOR RELIEF 2.4.1.1 Reactor Pressure Vessel Circumferential and longitudinal welds on the reactor pressure vessel.

2 4.1.2 Requirament from Which Relief Requested Table IWB-2500-1, Category B-A requires essentially 100 percent of the shell welds lengtu to be examined.

2.4.1.3 Justification The space between the insulation and the RPV outside su. face, nominally four . inches, has been measured in some areas to be significantly less. The circumferential and longitudinal welds have been examined in accordance with previous Code requirements (i.e., 5 and 10 per-cent weld length). The design of the biological shield precludes 100 per-cent access to the RPV shell welds.

2.4.1.4 Testing in Lieu of Section XI Requirements O'

N-There are various windows in the biological shield which permit limited access to the RPV shell welds. An attempt will be made to obtain the maximum examination weld length for the circumferential and longitudinal welds.

2.4.2 REQUEST FOR RELIEF 2.4.2.1 Components Reactor recirculation pumps, 2AP34 & 2BP34, ASME Class 1 (equivalent).

2.4.2.2 Requirement from Which Relief Requested Table IWB-2500-1, Category B-L-1, requires volumetric examination of pressure-retaining welds in the pump casing of one pump in cach group of pumps of similar function to be performed once per inspec-j tion interval.

j 2.4.2.3 Justification The pump casings are constructed of stainless steel

( casings which, due to their large grain structure, are highly attenuative to high frequency ultrasonic beams. Casting base metal-to-weld metal inter-faces tend to be reflective to ultrasound, producing false echoes which aggravate the attenuation problem. The interface cannot be reliably

[)

\m ,/ .

distinguished.from either lack of fusion or incomplete penetration and-2-10

~

prevents interpretation of signals. Therefore, angle beam longitudinal and shear wave ultrasonic examinations of welds in static cast steel have not proven to be feasible.

2.4.2.4 Testing in Lieu of Section XI Requirements Pressure-retaining welds in the pump casing will be subjected to a surface examination.

. 2.4.2.5 Requirement from Which Relief Requested Table IWB-2500-1, Category B-L-2 requires VT exam-ination of the internal pressure boundary surfaces of one pump in each group

^

of pumps of similar function to be performed once per inspection interval.

3 2.4.2.6 Justification This requirement, in absence of other required l maintenance, would necessitate dismantling a recirculation pump solely to perform a VT inspection of internal surfaces, and as such, represents an unnecessary exposure 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.

The disassembly of this pump constitutes a mainte-l

nance job of major proportions that, due to plant design, involves removing the motor and transporting it outside the containment. ~ Movement of such large heavy components within the drywell with the attendant hazard of

accidental damage to other safety-related' piping and equipment constitutes

! a risk to reactor safety. It is estimated that the dismantling and reas-

sembly of one pump would consume more than 10,000 manhours and in excess

of one month of round-the-clock effort and would result in a cumulative dose of between 100 and 500 man-rem.

i The net result of this majorfeffort would be a VT inspection consuming about eight manhours. The questionable benefit to be i . obtained from such an inspection when measured against the cost in man-rem

' appears to be in conflict with the concept of "As Low as Reasonably 'Achiev-able." In view of the. cost in dollars, potential hazards, and man-rem and in view of the minimal benefits to be obtained, it is concluded that this

- Code requirement is impractical for PBAPS.

2.4.2.7 Testing in Lieu of Section II Requirements The internal surfaces - of the recirculation pump casings will be visually inspected whenever these surfaces are accessible as a result of disassembly for other maintenance purposes. . In the interim,

- annual performance tests will be" conducted to verify pumping capability -

p-t and to indicate the condition'of internal clearances. An ultrasonic surveillance program will be implemented as the primary alternative i- 2-11

O examination. These data, coupled with the hydrostatic tests performed once per inspection interval and the external inspections performed during seal maintenance, will provide adequate assurance of structural integrity.

2.4.3 REQUEST FOR RELIEF 2.4.3.1 Components ASME Class 1 (equivalent) valves exceeding four inches nominal pipe size.

2.4.3.2 Requirement from Which Relief Requested Table IWB-2500-1, Category B-M-2 requires VT exami-nation of the internal pressure boundary surfaces of one valve in each group of valves of the same design, manufacturing method, manufacturer, and func-tion to be pe'rformed once per inspection interval.

2.4.3.3 Justification Valves on the recirculation loop suction piping would require off-loading the fuel elements and draining the reacto; 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. Preparatory work of this scope is considered impractical  !

O for the sole purpose of conducting a VT examination. Contamination levels in the valves associated with the recirculation loops are particularly high due to the physical location of these valves at the bottom of the system.

I During routine maintenance, when valves are dis-assembled, VT-3 examinations are performed on valve body internal surfaces.

Disassembly of other Class 1 valves solely for internal inspection is impractical in view of the fact that most of these valves, particularly the containment isolation valves, are disassembled frequently for maintenance of leak-tightness.

Disassembly of these valves solely for VT inspec-tion, in absence of other required maintenance, would be extremely imprac-

.ical and unjust. The cost of personnel exposure, potential hazards, time and radioactive waste would be excessively high and in direct violation of the concept of "As Low as Reaeonably Achievable."

2.4.3.4 Alternate to Section XI Requirement Class 1 valves exceeding four inches nominal pipe size are subjected to VT inspection of the internal surfaces of the valve bodys when disassembled for maintenance in accordance with an established progyam and documented procedures. However, an ultrasonic surveillance h, . progb am will be implemented as the primary alternative examination. These l datat coupled with periodic leak tests and hydrostatic tests, will provide adeqdate assurance of the structural integrity of the Class 1 valve bodies, l , whilf keeping exposure to radiation and contamination "As Low as Reason-ably Achievable."

2-12 J _ _ _ ____ _ _ ____

2.4.4 REQUEST FOR RELIEF j

{u'}

2.4.4.1 Components i

ASME Class 1 (equivalent) components.

2.4.4.2 Requirement from Which Relief Requested IWB-5222 requires that Class 1 systems and compo- )

nents be subjected to a system hydrostatic test at pressure and tempera- ,

ture as specified in Table IWB-5220-1.

2.4.4.3 Justification Plant Technical Specifications require primary containment integrity to be maintained whenever reactor water temperature is above 212*F when fuel is in the vessel. Primary containment integrity requires the drywell to be intact and all automatic primary containment isolation valves to be operable or deactivated in the isolated position.

During the hydrostatic test, the drywell head must be removed to allow inspection of the reactor vessel head flange area and reactor head spray nozzle. Also, during the hydrostatic test, several primary containment isolation valves are either deactivated in the open position or are bypassed by pipe jumpers to extend the test boundary to include all Class 1 piping. For these reasons, the hydrostatic test cannot be done at tempera-tures above 212*F.

( '

A test temperature of 212*F corresponds to a test pressure of 1082 psig on Table IWB-5220-1. The present setting of the four lowest set relief valves is 1105 !11 psig. It is proposed to conduct the hydrostatic test with all relief valves in place and to raise pressure within 30 psig of the lowest relief valve setting as determined by review of the latest bench test data available on the relief valves in place at the time of the hydrostatic test. Thirty psig is considered a minimal mar-gin to allow for pressure control while recognizing the tolerance of the relief valve settings and the accuracy of the pressure-indicating devices.

The temperature will be maintained below 212*F and above '185'F, which is the minimum vessel temperature allowed by Technical Specifications at 1075 psig reactor pressure.

2.4.4.4 Alternate to Section XI Requirements The only alternative that permits meeting the Code at temperatures less than 212*F is removal of the relief valves. This job is expensive both in dollars and in man-rem and would result in lengthen-ing the refueling outage because such work would be on the critical path to returning the reacter to service. It is concluded that adequate confidence in the structural integrity of the Class 1 systems and components can be gained by the proposed hydrostatic test and that removal of the relief valves to permit testing to a slightly higher pressure is not justified.

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2-13

O O O TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Sheet 1 of 11

-Item .

Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks REACTOR PRESSURE VESSEL Bl.10 B-A Longitudinal and Volumetric 100% of one circumferential May be examined at Circ umferential and one longitudinal belt- or near the end of Shell Weld line weld length. See Sub- each inspection section 2.4.1 for Request in terval.

7. for Relief.

Bl.20 B-A . Meridional and Volumetric 100% of accessible length May be examined at Circumferential of one meridional and cir- or near the end of Head Weld cumferential weld of the each inspection

i. closure head and bottom interval for the head. bottom head.

Bl.30 B-A Shell-to-Flange Volumetric 100% of circumferential At least 50% of the weld j weld. shall be examined by the end of the first inspection period, and the remainder by the end of the third inspection period.

Bl.40 - B-A' Head-to-Flange Volumetric / 100% of circumferential

Surface weld.

B3.90 B-D Primary Nozzle-to- Volumetric 100% of nozzles.

B3.100 B-D Vessel Welds and Nozzle Inside Radius Section .

2 i __ -__ -l

1 O O O i

TABLE 2.2-1

, INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd) ,

Sheet 2 of 11 Item Components & Parts Examination Requirements

.No. . Category To Be Examined Method For 10-Year Interval Remarks i

B4.10 B-E Partial Penetrations ---

Items B4.11 through B4.13 are applicable.

B4.11 B-E Vessel Nozzles Visual (VT-2) 25% of each group of The examinations will comparable size and be performed when the function. RPV is pressurized y prior to operation.

vs .

B4.12 B-E Control Rod Drive Visual (VT-2) 25% of each group of The examinations will Nozzles comparable size and be performed when the function. RPV is pressurized prior to operation.

B4.13 B-E Instrumentation Visual (VT-2) 25% of each group of The examinations will Nozzles comparable size and be performed when the function. RPV is pressurized

. prior to operation.

B5.10 B-F Nozzle-to-Safe End Volumetric All dissimilar metal Welds ' < 4 inches and Surface welds at nozzles.

B5.20 B-F Nozzle-to-Safe End Surface All dissimilar metal Not Applicable.

Welds > 4 inches welds at nozzles.

t i B6.10 B-G-1 Closure Head Nuts Surface 100% of nuts. An augmented volumetric examination will be performed in accordance l with IWA-2240 in placs of the surface examina-t Lion.

s s/ .

TABLE 2.2-1 E INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

Sheet 3 of 11 1

3 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks

.B6.20 B-C-1 Closure Studs, In Volumetric 100% of studs.

Place w B6.30 B-G-1 Closure Studs, When Volumetric 100% of studs.

Removed and Surface I

y B6.40 B-G-1 Threads in Flange Volumetric 100% of threaded holes. 1 inch Annular Area g around threaded hole.

t B6.50 B-G-1 Closure Washers Visual (VT-1) All washers, and bushings

and Bushings upon stud. removal.

B7.10 B-G-2 Pressure-Retaining Visual (VT-1) Not applicable.

Bolting 2 Inches and Less in

Diameter i 2

B8.10 B-H Integrally Welded Volumetric 100% of accessible area of Vessel Supports or Surface the circumference of the i

weld to the vessel.

1 B13.10 B-N-1 Vessel Interior Visual (VT-3) Accessible areas above and To be examined during

. below reactor core. each inspection period.

B13.20 B-N-2 Interior Attach- Visual (VT-1) Accessible attachment To be examined at i ments Within welds. or near the end of Beltline Region the inspection interval.

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O O O TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 00MPONENTS (Cont'd)

Sheet 4 of 11 i

Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks B13.21 B-N-2 Interior Attach- Visual (VT-3) Accessible attachment To be examined at or near

, ments Within welds. the end of the inspection

. Beltline Region interval.

B13.22 B-N-3 Core-Support Visual (VT-3) Accessible surfaces. To be examined at or near Structures the end of the inspection y interval.

C l B14.10 B-0 Control Rod Drive- Volumetric Welds in 10% of the May be examined at or near Housings or Surface peripheral CRD housings. the end of the inspection i interval.

B15.10 B-P Exempted Pressure- Visual (VT-2) All exempted components Examinations to be per-Retaining Components 'during system leakage formed in accordance with Defined by IWB-1220 test. IWB-5221 for each refuel-ing outage.

B15.11 B-P Exempted Pressure- Visual (VT-2) All exempted components Examinations to be per-I Retaining Components during system hydrostatic formed once in accordance Defined by IWB-1220 test. with IWB-5222 at the end of the test inte rval .

E i

4 1

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\ L) J 4 TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

Sheet 5 of 11 i Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks 1

PIPING '

{

i B5.130 B-F Dissimilar Metal Volumetric 100% of the welds.

Weldsf_4 Inches and Surface ,

.rp +

5; B5.140 B-F Dissimila'r !btal Surface 100% of the welds.

Helds s 4 Inches B5.150 B-F Dissimilar Metal Surface 100% of the welds.

'l Socket Welds l' B6.150 B-G-1 Bolts and Studs, Not applicable.

> 2 Inches in i- Diameter in' Place B6.160 B-G-1 Bolts and Studs, ---

Not applicable.

> 2 Inches in

-Diameter when removed. ,

l B6.170 B-G-1 Bolting .

Not applicable.

4 B7.50 B-G-2 Bolting 2 Inches Visual (VT-1) 100% of bolts, studs, and May be examined in place and Less in Diameter nuts. under tension or when

, bolting is removed.

4 4

O O O TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

Sheet 6 of 11 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks B9.ll B-J Circumferential Pipe Volumetric 25% of the circumferential Welds jg4 Inches in and Surface butt welds.

] Diameter y B9.12 B-J Longitudinal Pipe Volumetric Adjoining longitudinal welds G Welds < 4 Inches in and Surface for scheduled circumferen-Diameter tial welds. One pipe-diameter length or 12 inches of each longitudinal weld length required.

B9.21 B-J Circumferential Welds Surface 25% of the circumferential

< 4 Inchen in Diameter butt welds.

B9.22 B-J Longitudinal Pipe ---

Not applicable.

Welds < 4 Inches in Diameter B9.31 B-J Branch Pipe Connec- Volumetric 25% of the branch connection tion Welds 2.4 Inches and Surface joints.

or Larger in Diameter i B9.32 B-J Branch Pipe Connec- Surface 25% of the branch connection 1 tion Welds < 4 Inches joints.

in Diameter 4

"ad>

d-TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

Sheet 7 of 11 1

Item. Components & Parts Examination Requirements i No. . Category To Be Examined Method For 10-Year Interval Remarks i

B9.40 B-J Socket Welds Surface 25% of the socket welds.

I B10.10 B-K-1 Integrally Welded Volumetric 25% of the supports whose ,

Supports or Surface attachment base material 1

is 5/8 inch or thicker.

y B15.50 B-P Exempted Pressure- Visual (VT-2) All exempted components Examination to be per-4 Retaining Components during system leakage formed in accordance o Defined by IWB-1220 test. with IWB-5221 for each

! refueling outage.

B15.51 B-P Exempted Pressure- Visual (VT-2) All exempted components Examination to be per-

', Retaining Components during system hydrostatic formed once in accor-Defined by IWB-1220 test. dance with IWB-5222 at the end of the test I interval.

I i.

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IABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS l' COMPONENTS (Cont'd)

Sheet 8 of 11 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks PUMPS B6.180' B-G-1 Bolts and Studs, Volumetric All bolts and studs. May be examined in place 2 Inches in under tension, when con-Diameter nection is disassembled, or when the bolting is y removed.

E B6.190 B-G-1 Flange Surface for Visual (VT-1) 100% of the surfaces, Examine when diassembled.

Bolting 2 Inches including annular surface Diameter When Connee- 1 inch around each stud 3

tion is disassembled hole.

B6.200 B-G-1 Nuts, Bushings, and Visual (VT-1) All nuts, bushings, and Examine when disassembled.

Washers 2 Inches washers.

In Diameter B7.60' B-G-2 Bolting, 2 Inches in Visual (VT-1) Not applicable.

Diameter or Less B10.20 B-K-1 Integrally Welded Volumetric 25% of the attachment Attachments or Surface welds.

B12.10 B-L-1 Pump Casing Welds Surface One reactor recircula- A surface examination tion pump. will be performed in lieu of a volumetric examination.

See Request for Relief, Subsection 2.4.2.

].

/

TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

Sheet 9 of 11  ;

i Item Components & Parts Examination Requirements  !

-No. Category To Be Examined Method For 10-Year Interval Remarks B12.20 B-L-2 Internal Surfaces Visual (VT-3) One reactor recircula- An augmented UT surveil-of Pump Casings tion pump. lance program will be implemented as the primary examination. See Request for Relief, Subsection 2.4.2.

A VT will be performed when y pump is disassembled for y~ maintenance purposes.

B15.60 B-P Pressure-Retaining Visual (VT-2) All exempted components Examinations to be per-

, Boundary during system leakage formed in accordance with test. IWB-5221 for each refuel- '

, ing outage.

i B15.61 B-P Pressure-Retaining Visual (VT-2) All exempted components Examination to be per-Boundary during system hydrostatic formed in accordance with test. IWB-5222 at the end of '

the test interval.

i l

1 I

O O O TABLE 2.2-1 l INSERVICE INSPECTION PROGRAM CLASS 1 C0kPONENTS (Cont'd)

Sheet 10 of 11 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks VALVES B6.210 B-G-1 Bolts and Studs, Volumetric All bolts and studs.

>2 Inches in Diameter B6.220 B-G-1 Flange Surface for Visual (VT-1) All surfaces and 1 inch n Bolting > 2 Inches annular area around each 4 in Diameter When stud hole-

'2 Connection is Dis-assembled.

B6.230 B-G-1 Nuts, Bushings, uad Visual (VT-1) All nuts, bushings, and Washers washers.

B7.70 B-G-2 Bolting < 2 Inches Visual (VT-1) All bolts, studs, and in Diameter nuts.

- B10.30 B-K-1 Integrally Welded Volumetric 25% of the supports. Attachments whose Attachments or Surface base material is 5/8 inch or greater in thickness.

B12.30 B-M-1 Valve Body Welds --- Not applicable.

e

. _. f

O O O TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd) s Sheet 11 of 11

, Iter. Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks

, B12.50 B-M-2 Internal Surfaces Visual (VT-3) One valve in each An augmented UT surveil-of Valve Bodies on group of valves that lance program will be ,

Valves 4 Inches is of the same con- implemented as the primary

, Nominal Pipe Size struction and similar examination. See Request function. for Relief, Subsection 2.4.3.

4 e

A VT examination will be 3 performed when the valve is disassembled for maintenance purposes.

I B15.70 B-P Pressure-Retaining Visual (VT-2) All exempted components Examinations to be per- ,

Components during system leakage formed in accordance '

. test. witn IWB-5221 for each 4

refueling outage.

B15.71 B-P Pressure-Retaining Visual (VT-2)- All exempted components Examinatien to be per-Components during system hydrostatic formed once in accor-test. dance with IWB-5222 at the end of the test inte rval.

6 k

TABLE 2.2-1 INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS (Cont'd)

System System Leakage Test System Hydrostatic Test Main Steam Normal Operating Pressure 110% Operating Pressure Main Recirculation Normal Operating Pressure 110% Operating Pressure Control Rod Hydro- Normal Operating Pressure 110% Operating Pressure static Return Feedwater Normal Operating Pressure 110% Operating Pressure Residual Water Cleanup Normal Operating Pressure 110% Operating Pressure Reactor Core Normal Operating Pressure 110% Operating Pressure Isolation Cooling Core Spray Normal Operating Pressure 110% Operating Pressure f High Pressure Coolant Normal Operating Pressure 110% Operating Pressure Injection Standby Liquid Control Normal Operating Pressure 110% Operating Pressure I

I i

i O

( 2-25 l r

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

i i

3. ' CLASS 2 PROGRAM p

3.1 IDENTIFICATION OF COMPONENTS The following systems or portions of systems have been classified as ASME Class 2 (equivalent):

1~

4 (1) Standby Liquid Control System e (2) Reactor Core Isolation Cooling System

, (3) Residual Heat Removal System (4) Core Spray Cooling System i (5) High Pressure Coolant Injection System (6) Portion of Fuel Pool Cooling and Cleanup System.

3 (7) CRD Scram Discharge Volume Piping l (8) Main Steam Lines beyond Outboard MSIV  ;

i r 3.1.1 STANDBY LIQUID CONTROL SYSTEM (SLC) ISI-M-358 The SLC system, beyond the check valve just outside primary containment, is classified Class 2 (equivalent) in accordance with Regu-latory Guide 1.26, Section C l.b. , - system is important to safety and 1

, designed for reactor shutdown. Exemption from the ASME Section XI exami-nation requirements of Table IWC-2500-1 is taken as follows:

( Entire Class 2 portion of the oystem is exempt per t IWC-1220(c) - Four-inch nominal pipe size and smaller.

t i 3.1.2 REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ISI-M-359 i

1 The RCIC system, outside the outermost containment isolation a

valves and excluding the turbine and condenser, is classified as Class 2 (equivalent) . While the RCIC system is not specifically covered by any of

! the definitions in Regulatory Guide 1.26, Section C.1, the system is con-

}

sidered important to safety in that its primary design function is to supplement the normal makeup systems during reactor shutdown, particularly

during isolation feca the main condenser. A secondary function of the

RCIC system is to supplement the HPCI system in the event of loss of coolant; however, no credit has been taken for this function in the plant j safety analysis. Exemptions from the ASME Section XI examination require-ments of Table IWC-2500-1 are taken as follows:

(' Some Class 2 portions are exempt per IWC-1220(b) - system is not required to operate above a pressure of 275 psig or l -above a temperature of 200*F. 'Other Class 2 portions areL

{ exempt per IWB-1220(c) - four-inch nominal pipe size and smaller.

1 3.1.3 RESIDUAL HEAT REMOVAL SYSTEM (RHR) ISI-M-361 ,

(/"'s)

' The RHR system, outside the outermost containment isolation -

. valves, is classified as Class 2 (equivalent) in accordance with Regula-

. tory Guide 1.26, - Sections C.l.a and C.1.b portions - of the system are 3-1

_ , _ ..,m, ,_,,,,, - ,--...~_E,-- .,4 .

4 ., ,  %, ,% ~,~. 6 , . . - , ,m. . , , . ..- . - . -

designed for emergency core cooling and portions are designed for residual heat removal. Exemptions from the ASME Section XI (1974 Edition and Addenda through the Summer 1975) examination requirements of Table IWC-2520 are taken as follows:

Component connections, piping, valves, and vessels that are four-inch nominal pip size and smaller are exempt per l IWC-1220(d).

3.1.4 CORE SPRAY COOLING SYSTEN ISI-M-362

?,

The Core Spray System, outside the outermost containment isolation valves, is classified Class 2 (equivalent) in accordance with Regulatory Guide 1.26, Section C.1.a - system is designed for emergency core cooling. Exemptions from the ASME Section XI (1974 Edition and Addenda through the Summer 1975) examination requirements of Table IWC-2520 are taken as follows:

l' Component connections, piping, valves, and vessels that are four-inch nominal pipe size and smaller are exempt per IWC-1220(d).

3.1.5 HIGH PRESSURE COOLANT INJECTION SYSTEM (HPCI) ISI-M-365

, The HPCI system, outside the outerniost containment isolation i valves, and excluding the turbine and condenser, is classified as Class 2 (equivalent) in accordance with Regulatory Guide 1.26, Section C.l.a. -

system is designed for emergency core cooling. Exemptions from the ASME Section XI (1974 Edition and Addenda through the Sunumer 1975) examination requirements of Table IWC-2520 are taken as follows:

Some Class 2 portions of the HPCI system are exempt per IWC-1220(b) - portions of the system are non-ECCS and do not function in normal operation. Other Class 2 portions of the i HPCI system are exempted per IWC-1220(d) - Four-inch nominal l pipe size and smaller.

i l

3.1.6 FUEL POOL COOLING AND CLEANUP SYSTEM ISI-M-363 The-portion of the Fuel Pool Cooling system that ties into the RHR s/ stem is basically a Class 3 system, however that portion which does not function in normal operation and cannot be tested adequately is classified as Class 2 (equivalent) in accorance with Regulatory Guide 1.26, Section C.2.a system is designed for residual heat removal from spent

[ fuel, does not operate during_ normal operation and cannot be tested ade-

[ quately. Exemption from the ASME Section XI examination requirements of l Table IWC-2500-1 is taken as follows:

' The entire Class 2 portion of the Fuel Pool Cooling System is exempt per IWC-1220(b) - system is not required to -operate above a pressure of 275 psig or above a temperature of 200*F.

O m

I l

3-2 l

l

m 3.1.7 CONTROL ROD DRIVE SCRAM DISCHARGE VOLUME PIPING (CRD SDVP)

ISI-M-356 AND ISI-M-357 The CRD SDVP system between the hydraulic control unit and up to and including the scram discharge header, is classified Class 2 (equivalent) in accordance with Regulatory Guide 1.26 Section C.I .b -

system is important to safety and designed for reactor shutdown. Exemp-tions from the ASME Section XI examination requirements of Table IWC-2500-1 3

are taken as follows:

i i Component connections, piping, valves, and vessels that are

j. four-inch nominal pipe size and smaller are exempt per IWC-1220(c) .

3.1.8 MAIN STEAM (MS) ISI-M-303 l The MS lines beyond the outboard MSIV valves, is classified Class 2 (equivalent) in accordance with Regulatory Guide 1.26, Section C.1.6 - system is important to safety and designed for reactor shutdown.

3.2 EXAMINATION PROGRAM i

The examination program for the second 10 year interval is for Class 2 pressure vessels, piping, pumps, and valves shall be completed during successive inspection intervals in accordance with Table IWC-2412-1.

-g The examination of systems or portions of systems will be performed such l

that 100 percent of the required examinations will be performed per inter-val. Specific examination restrictions will be identified as the actual examinations proceed. The areas for examination are discussed in the fol-

?

loving text and summarized in Table 3.2-1.

l 3.2.1 PRESSURE VESSELS i

The only Class 2 pressure vessels in the system that require l nondestructive testing are the residual heat removal (RHR) heat exchangers.

j Category C-A - Pressure-Retaining Welds in Pressure Vessels--Items C1.10, C1.20 and C1.30 This category applies to head and shell and tube sheet-to-i shell welds.which are gross structural discontinuities.

Welds in this category and the adjoining base metal will be volumetrically examined in accordance with the requirements of Section XI.

Category C-B - Pressure-Retaining Nozzle Welds Jn

Vessels--Items C2.10. C2.11, C2.20, C2.21, C2.22, C2.30, C2.31, and C2.32 Nozzles in Class 2 pressure vessels are subject to volumet-i ric examination. These examinations will cover 100 percent of the vessel attachment veld.

3-3

. .. _ _ ._ .__._ _. _...-_ . _ . .___ ._ _._m.

_ _ _ _ _ .._ _.._.___ _- __ _ _ . _ __q l

4 i

, )

l 1

Category C-C - Integrally Welded Attachments--Ites C3.10 ,

i- The RHR heat exchangers are supported by rod hangers. Inte- l grally welded supports on the pressure-retaining boundary with base material 3/4 inch or greater in thickness are

subject to a surface examination.

I

Category C-D - Pressure-Retaining Bolting--Item C4.10 j i .

! The bolting in the RHR heat exchangers is less than two l inches in diameter.

j Category C-H - Pressure-Retaining Components--Items

. C7.10 and C7.20 i

4' Vessel components exempted from volumetric or surface exami-nations under IWC-1220 will be visually (VT-2) examined for j evidence of leakage during system pressure or component func-tional, and/or system hydrostatic tests (IWC-5221, IWC-5222).

~

f 3.2.2 PIPING I

Category C-C - Integrally Welded Attachments for L Piping--Ites C3.20 I

l Welded support attachments whose base material thickness is j 3/4 inch or greater for components in the C-F category will j be subjected to surface examination.

l l Category C-D - Pressure-Retaining Bolting Greater Than >

!- Two Inches in Diameter--Item C4.20 There is no bolting exceeding two-inches in diameter.

, Category C-F - Pressure-Retaining Welds in Piping--Items C5.10 through C5.32 4

) For piping welds less than or equal to 1/2 inch in nominal

vall thickness, a surface examination will be- performed. ,

l For piping welds greater than 1/2 inch in nominal wall i

thickness, a surface and volumetric examination will be per-formed. Branch connections greater than 4 inches in nominal  :

branch pipe size will be subjected to a surface examination.  ;

i

~

! Category C-H - Pressure-Retaining Components--Items C7.30 and C7.40

Components of piping systems exempt from volumetric or surface examination under IWC-1220 will; be visually (VT-2) i examined for evidence of leakage during system pressure or component-functional, and/or' system hydrostatic tests

!-  : (IWC-5221,;IWC-5222).

3 '+

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W-'+ -p 4 e g-p-We -,- y- et -w4 9 w-.+*,-iW*- g y e-Ty,*,y. - py # -g ww-p+-y 4 5 -spi-Uw , t 13

. m . - _ _ _ _ _ _ _ . . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _

1 1

3.2.3 PUMPS I

Category C-C - Integrally Welded Attachments for l 2 Pumps--Ites C3.30

^

Welded support attachments whose base material thickness is 3/4 inch or greater will be subjected to surface examination.

1

Category C-D - Pressure-Retaining Bolting Greater Than l Two Inches in Diameter--Item C4.30 i

. There is no bolting exceeding two inches in diameter.  ;

i

Category C-G - Pressure-Retaining Welds in Pumps--Ites C6.10 {

l r ,

j There are no pump casing welds in these systems. 4 i

.[ Category C-H - Pressure-Retaining Components--Iteau C7.50 and C7.60 Pump components exempted from volumetric or surface examina- .

1. tions under IWC-1220 will be visually (VT-2) examined for  !

i evidence of leakage during system pressure cr component func- [

tional, and/or system hydrostatic test (IWC-5221, IWC-5222). '

]

! 3 2.4 VALVES Category C-C - Integrally Welded Attachments for Valves--Item C3.40 s

Welded support attachments whose base material thickness is j 3/4 inch or greater will be subjected to surface examination.

i Category C-D - Pressure-Retaining Bolting Greater Than

Two Inches in Diameter--Item C4.40 There is no bolting exceeding two inches in diameter.

1 l' Category C-G - Pressure-Retaining Welds in Valves--Ites c6.20

j. There are no valves in these systems which have body welds.

i Category C-H - Pressure-Retaining Components--Items

C7.70 and C7.80 i

Valve components exempted from volumetric or surface examina-i tions under IWC-1220 will be visually (VT-2) examined for evidence of leakage during systes pressure or component func-tional, and/or system hydrostatic test (IWC-5221, IWC-5222).

3-5

d 3.3 SYSTEM PRESSURE TESTS 3.3.1 SYSTEM PRESSURE OR COMPONENT FUNCTIONAL TEST Class 2 components will be subjected to the system pressure

- or component functional test requirements of IWC-5221. The tests scheduled

! to be performed during the second 10 year zaterval are shown in Table 3.2-1.

In accordance with IWC-5221, the operating pressure of the system and/or component functional test is acceptable as the system pres-sure test.

3.3.2 SYSTEM HYDROSTATIC TEST Class 2 components will be subject to system hydrostatic test requirements of IWC-5222. The tests scheduled to be performed during the second 10 year interval are shown in Table 3.2-1.

In accordance with IWC-5222(c), open-ended portions of l

nonclosed systems extending to the first shutoff valve are exempted from the test requirements of IWC-5000 and IWA-5000. Examples of this i

exemption include suction lines from the torus, test lines, and minimum flow recirculation lines which discharge to the torus, containment spray

lines, torus spray lines and turbine exhaust lines to the torus. For these lines, demonstration of an open flow path will be accomplished in lieu of pressure testing.

i

)

3-6

r _ _ ._. _ _ . ._ .. _ _ _ . _._ _ _ _ ___ _ _. _ _ ..__.

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t TABLE 3.2-1 INSERVICE INSPECTION PROGRAM CIASS 2 COMPONENTS Sheet 1 of 6 Ites Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks PRESSURE VESSELS '

C1.10 C-A Shell circumferential welds Volumetric 100% of each weld. Applies to gross structural dis- ,

continuities.  !

C1.20 C-A Head circumferential welds Voltanetric 100% of each weld.

w C1.30 C-A Tbbe sheet-to-shell weld Voltanetric 100% of each weld, b

C2.1G C-B Nozzles in vessels i 1/2-in. - -

Not applicable ,

nominal thickness i C2.11 C-B Nozzle-to-shell Surface 100% of each veld. Manways and hand I holes are excluded.

C2.20 C-B Nozzles in vessels > 1/2-in. Not applicable, moninal thickness ,

C2.21 C-B Nozzle-to-shell (or head) weld Surface and 100% of each weld, Manways and hand l Volumetric holes are excluded. '

C2.22 C-B Nozzle inside radius section Volumetric 100% of each veld. Manways and hand holes are excluded. ,

f t

1 TABLE 3.2-1 INSERVICE INSPECTION PROGRAM CLASS 2 00MPONENTS (CONT'D)

Sheet 2 of 6 e i

Ites Components & Parts Examination Requirements No. Category _ To Be Examined Method For 10-Year Interval Remarks i

, C2.30 C-B Nozzles with Reinforcing plate Not applicable.

! in vessel 7-1/2-Inch Nominal Thickness l

C2.31 C-B Reinforcing plate welds to Surface 100% of each weld. Manways and hand i nozzle-to-vessel h' oles are excluded.  !

Y l C2.31 C-B Nozzle-to-shell (or head) Volumetric / 100% of each veld. Manways and hand i l welds inside vessel accessible / Visual-(VT-2) holes are excluded.

inaccessible  !

t C3.10 C-C' Integrally welded attachments Surface Attachments whose

• base material is l 3/4 in, or greater.

C4.10 C-D Bolts and studs Volumetric Not applicable. l C7.10 C-N Pressure-Retaining Components Visual (VT-2) 100% of pressure- Examinations to be l retaining boundary. performed in accor- .

dance with IWC-5221 [

for cach refueling i outage.  !

. i C7.20 Visual (VT-2) 100% of pressure-C-H Pressure-Retaining Components Examinations to be retaining boundary. performed in accor-Jaace with IWC-5222

- ' at the end of each I test interval.  !

[

t i

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o c O TABLE 3.2-1 k

. / .,

INSERVICE INSPECTION PROGRAM -

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A.

i CLASS D COMPOEENTS,(CONT'D)'

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s p p s '

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' Components & Parts j/'

Item s , # Examination Requir,ements  ;? ,, 3 -

)- *

, No.. Category, ' 'I y jTo Be Examined ",i Method,s ' for IO,-Yead , Interval Remarks /

s _ r. 1"

1. // ,'*

PIPING .

1

/

< - ,5 C3.20. k C-C . Integrally welded attachments 3urface #

100% of the support Attachments whose Attachment welds in base material is the p'ressure-retain- 3/4 in. .or greater.

3x ,

-f ' '

ing boundary.

j' , , ,

e C4.20 C-D Bolts and studs Volumetric Not applicable

• y

\ Bolting' 2 in.

& i

l C5.ll C-F Circumferential welds 1/2-in. Surface ,. See note below. '

i nominal wall thickness ', '

1 j C5.12 C-F Longitudinal welds _1/2-in. ~ Surface See note below.

i nominal wall thickness i

C5.21 C-F- - Circumferential welds 1/2-in. Surface and See note below.

nominal wall thickness Volumetric l 'C5.22 C-F Longitudinal welds 1/2-in. Surface and See note below.

i nominal wall thickness Volumetric i

NOTE: The selection of Class 2 welds will be performed in accordance with the limitations imposed by 10CFR50.55a(b)(2).- Welds for non-ECCS and non-RHR systems are selected based upon the criteria contained

in the footnotes of Category C-F of Table IWC-2500-1. Piping welds in the RHR and ECCS are selected based upon the criteria contained in Category C-F of Table IWC-2520 of the 1974 Edition of Section XI with Addenda through Summer 1975.

i s

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TABLE 3.2-1 i

INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS (CONT'D)

Shee; 4 of 6 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks C5.31 C-F Circumferential pipe branch Surface See note below.

connection welds 4 Inches C5.32 C-F Longitudinal pipe branch Surface See note below.

connection welds 4 Inches y C7.30 C-II Pressure-Retaining Components Visual (VT-2) 100% of pressure- Examination to be g retaining boundary. performed in accordance with IWC-5221 for each refueling outage.

C7.40 C-H Pressure-Retaining Components Visual (VT-2) 100% of pressure- Examination to be retaining boundary. performed in accordance with IWC-5222 at the end of each test interval.

NOTE: The selection of Class 2 welds will be performed in accordance with the limitations imposed by 10CFR50.55a(b)(2). Welds for non-ECCS and non-RHR systems are selected based upon the criteria contained in the footnotes of Category C-F of Table IWC-2500-1. Piping welds in the RIIR and ECCS are selected based upon the criteria contained in Category C-F of Table IWC-2520 of the 1974 Edition of Section XI with Addenda through Summer 1975.

m t _ U TABLE 3.2-1 INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS (CONT'D)

Sheet 5 of 6 i

Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks PUMPS C3.30 C-C Integrally welded attachments Surface Attachments whose base material is y 3/4 in or greater.

L

- C4.30 C-D Bolts and studs Volumetric Not applicable Bolting 4 2 in.

4 C6.10 C-G Pump casing welds Surface Not applicable.

C7.50 C-H Pressure-Retafning Components Visual (VT-2) 100% of pressure- Examination to be retaining boundary. performed in accordance with IWC-5221 for each '

refueling outage.

C7.60 C-II -Pressure-Retaining Components Visual (VT-2) 100% of pressure- Examination to be retaining boundary. performed in accordance with IWC-5222 at the end of each test

, interval.

-s p ,

TABLE 3.2-1 INSERVICE INSPECTION PROCRAM CLASS 2 COMPONENTS (CONT'D)

Sheet 6 of 6 l

Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks VALVES C3.40 C-C Integrally welded attachments Surface 100% of the support Attachments whose attachment welds in base material is the pressure-retain- 3/4 in. or greater.

w ing boundary.

d.

" C4.40 t;-D Bolts and studs Volumetric Not applicable Bolting <,2 in.

C6.20 C-C Valve body welds Surface Not applicable.

, C7.70 C-H Pressure-Retaining Components Visual (VT-2) 100% of pressure- Examination to be retaining boundary. performed in accordance with IWC-5221 for each

refueling outage.

C7.80 C-H Pressure-Retaining components Visual (VT-2) 100% of pressure- Exa~1 nation to be retaining boundary. performed in accordance with IWC-5222 at the end of each test interval.

i

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

TABLE 3.2-1 SYSTEM PRESSURE TESTS CLASS 2 COMPONENTS System Pressure Testl or System Component Functional Test System Hydrostatic Test 2 i Core Spray Cooling Normal Operating Pressure 125% Operating Pressure High Pressure Coolant Injection Normal Operating Pressure 110% Operating Pressure

-Reactor Core Isolation Cooling Normal Operating Pressure 110% Operating Pressure y Standby Liquid Control Normal Operating Pressure 110% Operating Pressure

- Fuel Pool Cooling Normal Operating Pressure 110% Operating Pressure Reactor Heat Removal Normal Operating Pressure 125% Operating Pressure CRD Scram Discharge Volume Piping Normal Operating Pressure 110% Operating Pressure NOTES' i

(1) -System pressure test or component functional test will be performed in accordance with IWC-5221 requirements with inspection per IWA-5000.

(2) System hydrostatic- test will be conducted once at or near the end of each inspection interval in accordance with IWC-5222 requirements.

4

4. CLASS 3 PROGRAM a

.4.1 IDENTIFICATION OF COMPONENTS The following systems or portions of systems have been classified as ASME Class 3 (equivalent):

a. Emergency service water system

b. High pressure service water system i

c. Emergency cooling system

d. Portion of fuel pool cooling and cleanup system i

4.1.1 EMERGENCY SERVICE WATER SYSTEM (ESW) ISI-M-315 4

The ESW system is classified Class 3 (equivalent) in accor-l dance with Regulatory Guide 1.26, Section C.2.b - system is designed for

, functioning of components important to safety including diesels and ECCS pump room unit coolers.

4.1.2 HIGH PRESSURE SERVICE WATER SYSTEM (HPSW) ISI-M-315. 361

{

i The HPSW system is classified Class 3 (equivalent) in accor-dance with Regulatory Guide 1.26, Section C.2.a - system is important to

! safety and designed to supply cooling water for post-accident heat removal t and normal residual heat removal.

4.1.3 EMERGENCY COOLING SYSTEM ISI-M-330 t

j. The Emergency Cooling System is classified Class 3 (equiva-j lent) in accordance with Regulatory Guide 1.26, Sections C.2.a and C.2.b -

! system is important to safety and designed to supply a source of cooling water for residual heat removal and for functioning of other components -

such as diesels. Open-ended portions of the syster will be examined in j accordance with the test requirements of ASME Section XI, IWD-5223(d)

! and (e).

4.1.4 FUEL POOL COOLING AND CLEANUP SYSTEM ISI-M-363 The portion of the Fuel Pool Cooling system that ties -into the RHR system (excluding that part taken as Class 2) is classified Class 3

(equivalent) in accordance with Regulatory Guide 1.26, Section C.2.a - sys-tea is designed for residual heat removal from the spent fuel. This system also provides a source of makeup water for the pool in the event normal l cooling is lost and the pool is allowed to boil. Open-ended portions of the system will be examined in accordance with the test requirements of ASME Section XI, IWD-5223(c) and (d).

O U

4-1

. , - :. _ - - , . , . - - .u , , - - - _

.. . . . . . - . . ~ - -

x L

'4 . 2 . EXAMINATION PROGRAM The pressure-retaining Class 3 components within each system boundary shall be subjected to the inservice system preesure tests and visual examine.tions as specified in Table IWD-2500-1 during the second 10 year interval. The examination program for Class 3 components is shown in Table 4.2-1.

4.2.1 SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION Category D-A Pressure-Retaining Com p nent and Integral Attachments--Items D1.10 through D1.60 Pressure-retaining components subjected to pressure tests per IWA-5000 will be visually (VT-2) examined for evidence of leakage during system inservice and/or system hydrostatic tests (IWD-5221, IWD-5223). Integral Attachments for components exceeding 4-inch nominal pipe size whose structural integrity is relied upon to withstand desgin loads during sytem function will be visually (VT-3)

. examined.

4.2.2 SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL. ATMDSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL Category D-B Pressure-Retaining Components and Integral Attachments--Items D2.10 through D2.60 Pressure-retaining components subjected to pressure tests per IW.'.-5000 will be visually (VT-2) examined for evidence of leakage during system functional and/or system hydro-static tests (IWD-5222, IWD-5223). Integral attachments for components exceeding 4-inch nominal pipe size whose struc-tural integrity is relied upon to withstand design loads during system function will be visually (VT-3) examined.

4.2.3 SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL Category D-C. Pressure-Retaining Components and Integral Attachments--Items D3.10 through D3.60 Pressure-reta'ining components subjected to pressure tests per IWA-5000 will be visually (VT-2) examined for evidence of leakage during system pressure and/or hydrostatic pressure tests (IWD-5221,'IWD-5223). Integral attachments for components exceeding 4-inch nominal pipe' size whose structural integrity is. relied upon to withstand design loads during system function will be visually'(VT-3) examined.

4-2 t

l i

~i i

!( 4.3 SYSTEM PRESSURE TESTS 4.3.1 SYSTEM INSERVICE TEST Class 3 components will be subjected to the system inservice test in accordance with the requirements specified in IWA-5211(c) and con- ~

ducted in accordance with IWD-5221. The test scheduled to be performed during the second 10 year interval is shown in Table 4.2-1.

4.3.2 SYSTEM FUNCTIONAL TEST Class 3 components will be subjected to the system functional j test in accordance with the requirements specified in IWA-5211(b) and con-

] ducted in accordance-with IWD-5222. The operating pressure of the system functional test shall be acceptable as the system test pressure. The tests l scheduled to be performed during the second 10 year interval are shown in j Table 4.2-1.

! 4.3.3 SYSTEM HYDROSTATIC TEST I

! Class 3 components will be subjected to the system hydro-l static test requirements of IWA-5211(d) and conducted in accordance with IWD-5223, as applicable. Open ended portions of a system extending to the

first shutoff valve and buried system components should be exempted from pressure test and from examination where accessibility is restricted. The

, test scheduled to be performed during the second 10 year interval are shown

in Table 4.2-1.

l 4.4- REQUEST FOR RELIEF FROM SECTION XI REQUIREMENTS l

4.4.1 REQUEST FOR RELIEF j 4.4.1.1 Components High Pressure Service Water (HPSW) System, Emer-

gency Service Water (ESW) System, Emergency Cooling System.

4.4.1.1 Requirement from which Relief Requested IWD-5223(a) - System test pressure at least 1.10 times the systas design pressure.

i

4.4.1.3 Justification i

Testing these systems to 110 percent design pres--

sure is beyond the capability of the system pumps aci therefore would require the use of a special hydrostatic test pump. . The available test

, connections on these systems are 3/4 and 1 inch lines and would sharply j limit the inflow capability from the hydrostatic pump, thereby necessitat-

ing leak-tightncss of system 14 , '16 , 20 , .and 24-inch valves to sucert's-fully perform the tests. Such leak-tightness is not otherwise a requi, e-ment for ' systems of thf3 type and considerable maintenance expense.would i

4-3 .

l

! 4 1

, , . . . . . , , . . . . _ . . , , _ . . . , , _ . . , , , _ , _ , . . , . _ . . . . . _ . , . , , . --,_.#.._,..,m., _

N be required to make the valves leak-tight for test purposes only. In addition, testing to 110 percent design pressure would require taking the entire ESW or HPSW system out of service at the same time which would require the cessation of all shutdown cooling. For the above reasons, we conclude that a hydrostatic test to 110 percent design pressure is imprac-i tical for systems of this type.

Testing to 110 percent of operating pressure is practical and could be accomplished using the system pumps and throttling at the cooling tower inlet valves - MO-48-0502 (A, B, C) for the HPSW sys-tem and MO-48-0501 (A, B, C) for the ESW system. Testing in this manner will provide adequate assurance of the structural integrity of these systems.

4.4.1.4 Testing in Lieu of Section XI Requirements The HPSW system, the ESW system, and their respec-tive portions of the Emergency Cooling Systems will be pressure tested to 1.10 times the system operating pressure.

l

[)

v ,

i l l 4-4 )

O' O u u o Table 4.2-1 INSERVICE INSPECTION PROGRAM CLASS 3 COMPONENTS Sheet 1 of 3 Item Components & Parts Examination Requirements No. Category To Be Examined Method For 10-Year Interval Remarks D1.10 D-A Pressure-Retaining Components Visual (VT-2) All Components are sub- Examination to be in support of reactor ject to a system inser- performed in accor-shutdown function vice and/or system dance with IWD-5221 hydrostatic test. for each inspection period and/or per-formed once in accor-dance with IWD-5223 7

at the end of the inspection interval.

D1.20 D-A Integral attachments (i.e., Visual (VT-3) All attachments. To be examined during through supports, restraints, mechani- each inspection period.

D1.60 cal and hydraulic snubbers and shock absorbers)

D 2.10 D-B Pressure-Retaining Components Visual (VT-2) All components are sub- Examination to be per-in support of ECCS, RHR, AC, ject to a component formed in accordance and RRHR functional test and/or with IWD-5222 for each system hydrostatic test. inspection period and/or to be examined once in accordance

^

with IWD-5223 at the end of the inspection interval.

4

O 0 ('\

'\ ,

\ U Table 4.2-1 INSERVICE INSPECTION PROGRAM CLASS 3 COMPONENTS (Cont'd)

Sheet 2 of 3 Item Components & Parts .

Examination Requirements

. No. Category To Be Examined Method For 10-Year Interval Remarks D2.20 D-B Integral attachments (i.e. - Visual (VT-3) All attachments. To be performed dur-through supports, restraints, mechani- ing each inspection D2.60 cal and hydraulic snubbers, period.

and shock absorbers)

D3.10 D-C Pressure-Eetaining Components Visual (VT-2) All components are sulr- Examination to be per-in support of RHR and Spent ject to system inservice formed in accordance f FSP and/or system hydro- with IWD-5221 for each as static test. inspection period and/or to be examined

! once in accordance with IWD-5223 at the end of the inspec-tion interval.

D3.20 D-C Integral Attachments (i.e., - Visual (VT-3) All attachments. To be performed dur-through supports, restraints, mechani- ing each inspection D3.60 cal and hydraulic snubbers, period.

and shock abrorbers)

O .

s O

, TABLE 4.2-1 SYSTEM PRESSURE TESTS CLASS 3 COMPONENTS (Cont'd) l Sheet 3 of 3 .

System Inservice or

_ System System Functional Test System Hydrostatic Test 4

i Emergency Service Water Normal Operating Pressure 110% Operating Pressure High Pressure Service Water Normal Operating Pressure 110% Operating Pressure ,

Emergency Cooling System Normal Operating Pressure 110% Operating Pressure

, Fuel Pool Cooling System Normal Operating Pressure Exempt per IWD-5223(c) & (d)

L NOTES: (1) System Inservice test will be conducted in each one-third inspection interval.where System Hydrostatic Test is not performed. The nominal operating pressure of the System Function test shall be acceptable as the System test pressure (IWD-5222).

(2) System Hydrostatic Test will be conducted once per 10 year inspection interval. [IWA-5211(d)].

i

5. CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORT PROGRAM 5.1 GENERAL The ISI program for component supports has been developed in accor-dance with the requirements of Subsection IWF of the 1980 Edition of Sec-tion XI with Addenda through Winter 1981. Details of the inservice test program for component supports with requests for relief from Section XI requirements are identified in this section.

5.2 INSERVICE INSPECTION PROGRAM FOR CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS ISIS will be performed either during normal system operation or plant outages. The required examinations will be completed in accordance with the inspection schedule established for the components under IWB, IWC, and IWD as shown on Table 5.2-1.

5.3 REQUEST FOR RELIEF FROM SECTION XI REQUIREMENTS 5.3.1 REQUEST FOR RELIEF 5.3.1.1 Components Hydraulic and mechanical shock suppressors for Class 1, Class 2, and Class 3 piping, pumps and valves.

4 l 5.3.1.2 Requirement from Which Relief Requested Table IWF-2500-1, Category F-C, Item F3.50 requires visual examination (VT-4) of all spring type supports, constant load type supports, shock absorbers, and hydraulic and mechanical type

! snubbers once per inspection interval.

5.3.1.3 Justification The hydraulic and mechanical shock suppressors for Class 1, Class 2, and Class 3 systems are currently subjected to an ongoing inspection and testing program detailed in the plant Technical Specifica-tions. This program is designed to demonstrate continued operational readiness and structural integrity of the shock suppressors.

5.3.1.4 Inspection in Lieu of Section XI Requirements

Hydraulic and mechanical shock suppressors will be inspected and tested in accordance with Technical Specification requirements.

O 1

L) 5-1

. . _ _ _ _ . _ _ . _ - . __ _ .~. . . _ -

O ( O TABLE 5.2-1 INSERVICE INSPECTION PROCRAM CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS Sheet 1 of 4 Item Components & Parts Examination Requirements No. Category To be Examined Method For 10-Year Interval Remarks Plate and Shell Type Supports F1.10 F-A Mechanical connections Visual (VT-3) Each inspection Examination boundariet to Pressure-Retaining interva l. established in accordance Components and build- with IWF-1300 and compo-

. ing structure nents selected in accor-

, dance with IWF-2510.

F1.20 F-A Weld connections to Visual (VT-3) Each inspection Examination boundaries building structure interval. established in accordance with IWF-1300 and compo-nents selected in accor-dance with IWF-2510.

F1.30 F-A Weld and mechanical Visual (VT-3) Each inspection Examination boundaries connections at interval. established in accordance intermediate joints with IWF-1300 and compo-in multiconnected nents selected in accor-Integral and non- dance with IWF-2510.

integral supports F1.40 F-A Component displace- Visual (VT-3) Each inspection Examination boundaries ment settings of interval. established in accordance guides and stops, with IWF-1300 and compo-misalignment of nents selected in accor-supports, assembly dance with IWF-2510.

of support items

O O-

. TABLE 5.2-1 INSERVICE INSPECTION PROGRAM

~~'

CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS (Cont'd) ,

Sheet 2 of 4 Item . Components & Parts Examination Requirements No. Category To be Examined Method For 10-Year Interval Remarks Linear Type Supports t F2.10 F-B Mechanical connections Visual (VT-3) Each inspection Examination boundaries to Pressure-Retaining interval. established in accordance Components and build- with IWF-1300 and compo-ing structure nents selected in accor-dance with IWF-2510.

' u

& F2.20 F-B Weld components to Visual (VT-3) Each inspection Examination boundaries building structure interval. established in accordance with IWF-1300 and compo-nents selected in accor-l dance with IWF-2510.

)

F2.30 F-B Weld and mechanical Visual (VT'3) Each inspection Examination boundaries a

connections at interval. established in accordance intermediate joints with IWF-1300 and compo-t in multiconnected nents selected in accor- ,

} -

integral and non- dance with IWF-2510.

integral supports F2.40 F-B Component and dis- Visual (VT-3) Each inspection Examination bouadaries placement settings interval. established in accordance of guides and stops, with IWF-1300 and compo-misilignment of nents selected in accor-i sapports, assembly dance with IWF-2310.

of support items

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

\

TABLE 5.2-1 INSERVICE INSPECTION PROGRAM CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS (Cont'd)

Sheet 3 of 4 .

Item Components & Parts Examination Requirements No. Category To be Examined Method For 10-Year. Interval Remarks 4

Components Standard Supports I

, - F3.10 F-C Mechanical connections Visual-(VT-3) Each inspection Examination boundaries to Pressure-ketaining in terval. established in accordance Components and build- with IWF-1300 and compo-ing structure nents selected in accor-i-

dance with IWF-2510.

[ F3.20 F-C Weld connections to Visual (VT-3) Each inspection Examination boundaries building structure interval. established in accordance 4

I with IWF-1300 and compo- i nents selected in accor-dance with IWF-2510.

. F3.30 F-C Weld and mechanical Visual (VT-3) Each inspection Examination boundaries connections at interval. established in accordance intermediate joints with IWF-1300 and compo-in multiconnected s nents selected in accor-integral and non- dance with IWF-2510.

integral supports F3.40 F-C Component displace- Visual (VT-3) Each inspection Examination boundaries I. ment settings of interval. established in accordance

. guides and stops, with IWF-1300 and compo-misalignment of nents selected in accor-supports, assembly dance with IWF-2510. ,

of support items

?

i

TABLE 5.2-1 INSERVICE INSPECTION PROGRAM CLASS 1, CLASS 2, AND CLASS 3 COMPONENT SUPPORTS (Cont'd)

Sheet 4 of 4 Item Components & Parts Examination Requirements No. Category To be Examined Method For 10-Year Interval Remarks Components Standard Supports (Cont'd)

F3.50 F-C Spring type supports, Visual (VT-4) Each inspection See Request for Relief constant load type interval. Subsection 5.3.1. Exami-supports, shock nation boundaries estab-absorbers, hydraulic lished in accordance with and mechanical type IWF-1300 and components u snubbers selected in accordance

- di with IWF-2510.

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BOUNDARY DRAWINGS I

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APPENDIX A if

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BOUNDARY DRAWINGS Table of Contents Drawing No. Title ISI-M-303 Emergency Service Water and High Pressure Service Water Pump ISI-M-315 Inservice Inspection Boundaries, Emergency Service Water and High Pressure Service

Water Pumps ISI-M-330 Inservice Inspection Boundary Emergency Cooling System ISI-M-351 Inservice Inspection 3oundaries, Nuclear Boiler ISI-M-354 Inservice Inspection Boundaries, Reactor Water Cleanup Sysem ISI-M-356 Control Rod Drive Hydraulic System ISI-M-357 Inservice Inspection Boundaries, Control Rod Drive Hydraulic System ISI-M-358 Inservice Inspection Bourdaries, Standby

, Liquid Control bystem ISI-M-359 Inservice Inspection Boundaries, Reactor Core Isolation Cooling System ISI-M-361 Inservice Inspection Boundaries, Residual Heat Removal System ISI-M-362 Inservice Inspection Boundaries, Core Spray i

Cooling System IS I-M-363 Inservice Inspection Boundaries, Fuel Pool Cooling and Cleanup ISI-M-365 Inservice Inspection Boundaries, High Pressure Coolant Injection System

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6. INSERVICE TESTING OF PUMPS 6.1 GENERAL The inservice testing program for Class 1, Class 2, and Class 3 pumps has been developed in accordance with requirements of Subsection IWP of the 1980 Edition of Section XI with Addenda through Winter 1981.

Details of the inservice testing program for pumps with requests for relief from Section XI requirements are identified in this section. 6.2 INSERVICE TESTING PROGRAM FOR CLASS 1, CLASS 2, and CLASS 3 PUMPS The inservice testing program for Class 1, Class 2, and Class 3 pumps is detailed in Table 6.2-1. Table 6.2-1 identifies the pumps to be

tested, pump equivalent ASME Code class, parameters to be measured based

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Inservice testing of pumps is performed at the test frequency speci-fied in Table 6.2-1. Consistent with the treatment of surveillance tests

in the Technical Specifications, these testing intervals may be adjusted plus or minus 25 percent. In cases where the elapsed interval has exceeded

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 .p).

t g vice water system (not a safety-related system). During loss of offsite power, cooling water to safety-related heat exchangers is supplied by the 6-1

O O TABLE 6.2-1 ' INSERVICE TESTING PROGRAM ! CLASS 1, CLASS 2, AND CLASS 3 PUMPS Equivalent Frequency of Measurement Frequency of Pump ASME Code of Test Parameters Operability Pump 1.D. No. P&lD Class N P1 P g Tb V L/P Check Relief Request RHR (4) 2/3(A.B.C.D)P35 M-361 2 NR Q Q Q NA Q Q Q_ (6.3)2,3,7,8 HPCI (1) 2/3/0P(33,38) M-366 2 Q Q- Q Q Y Q Q Q (6.3)3 RCIC (1) 2/3/0P36 M-360 2 Q Q Q Q NA Q Q Q (6.3)2,3 Core spray (4) 2/3(A,B,C,D)P37 M-362 2 NR Q Q Q NA Q Q Q (6.3)2,3 Standby liquid .2/3(A,B,)P40 M-358 2 NR Q Q Q NA Q Q Q (6.3)2,3,4,8 control (2) Emergency service O(A,5)P57 M-315 3 NR Q Q NA NA Q Q Q (6.3)2,3,5,6 3 water (2)- 1

                       -N                                                                     High pressure'               2/3(A,B,C,D)P42 M-315       3         NR . Q . Q      Q   NA        Q      Q       Q       (6.3)2,3,5,7,8 Service water (4)

(RHR service water) Emergency cooling 00P186 M-330 3 NR A A NA NA A A AF (6.3)1,2,3,5,6,8 water (1) l Emergency service 0(A,5)P163 M-330 3 NR A A NA NA A A At (6.3)1,2,3,6,8 i water booster (2) Diesel 011 O(A.B.C.D)P60 M-323 3 NR Q Q Q NA QQ Q (6.3)2,3 Transfer (4) 4- +These pumps are common to both units and are tested once per operating cycle for each unit. The resultant test frequency is approntmately once per 9 months. 1' KEY: N = Rotative speed L/P = Lubricant level or pressure to be observed ! Pi = Inlet pressure NA = Not available P = Differential pressure NR = Not required 4 Q1 - Flow rate . M = Monthly Tb = Bearing temperature Q = Quarterly V = Vibration A = Once per operating cycle Y = Yearly

1 emergency service water pumps. Testing of the emergency cooling water pump and the emergency service water booster pumps requires manually iso- '

lating'the emergency service water system from the service water system and operating several manual valves to establish a proper flow path to and from the emergency cooling tower. These operations can result in the tem-porary loss of cooling to safety-related heat exchangers, and thereby jeopardize safety-related equipment and reactor operations and safety.

Additionally, these pumps, due to their back-up function for a very unlikely event, are operated only during surveillance testing, once per cycle, in t accordance with plant Technical Specifications, and therefore pump hydrau-lic or mechanical changes will not be significant between tests. 6.3.1.4 Testing in Lieu of Section XI Requirements These pumps are tested for operability in accord- , , ance with plant Technical Specifications at least once each operating cycle for each unit. Inservice test quantities are measured during these . tests. Since the eargency cooling water pump and emergency service water booster pumps are common to both units, these pumps are tested approximately every 9 months. i 6.3.2 REQUEST FOR RELIEF 6.3.2.1 Components () RHR pumps, RCIC pump, core spray pumps, standby liquid control pumps, emergency service water pumps, high pressure service water. pumps, emergency cooling water pump, emergency service water booster pumps, and diesel oil transfer pumps.

,                      6.3.2.2    Requirement from Which Relief Requested Bearing temperatures on these pumps shall be measured in accordance with Subarticle IWP-4300.

6.3.2.3 Justification Of the pumps in question, several are centrifugal pumps and have no bearings outside the main flow path and measurement is not required. All the pumps in question either have bearings in main flow for lubrication or have anti-friction bearings lubricated by static oil baths. ' Measurement of the bulk temperature of an oil bath is not indica-tive of bearing condition. Temperature measurements of the bearings themselves are not meaningful. Our discussions with bearing manufactur-i ers, pump builders, and maintenance people confirmed that the temperature rise of an anti-friction bearing prior to failure occurs over a period of  ! seconds or minutes. Measuring the temperature of anti-friction tearings cannot be justified since gradual temperature change is not an early , warning measurement. ) l . 6-3 1

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l 6.3 . 2. 4 Testing in Lieu of the Section XI Requirements Proper operation is verified by the other inservice test quantities which are measured. Condition of the pump bearings is determined by visual inspection when the pump is sufficiently disassembled during maintenance. 6.3.3 REQUEST FOR RELIEF 6.3.3.1 Components All pumps. 6.3.3.2 Requirement from Which Relief is Requested e Requirements of Article IWP-6000 to provide records and plans for inservice testing of pumps. 6.3.3.3 Justification i Existing plant surveillance test procedures docu-ment most of the test conditions and parameters identified in the Subsec-tion IWP. 6.3.3.4 Alternate to Section XI Requirements Surveillance tests were reviewed and revised to incorporate the necessary documentation to meet Section XI requirements for pump testing. Surveillance tests results are retained at the plant site and are available for audit by the enforcement authority. 6.3.4 REQUEST FOR RELIEF 6.3.4.1 Components Standby liquid control pumps. 6.3.4.2 Requirement from Which Relief Requested Pressure measurement to be in accordance with requirements of Subarticle IWP-4200. 6.3.4.3- Justification Plant design does not incorporate direct pump 1 inlet pressure indication.. l i 6.3.4.4 Alternate in Lieu of Section XI Requirements Liquid level in the standby liquid control tank is

  - ["~

(, monitored during quarterly inservice testing. Pump suction pressure is j ! assumed to be the difference in elevation between the pump suction line { connection and the tank liquid elevation. i- 6-4 L

l l l 6.3.5 REQUEST FOR RELIEF l i 6.3.5.1 Components l Emergency service water pumps, high pressure ' service water pumps, and emergency cooling water pump. 6.3.5.2 Requirement from Which Relief Requested Pressure measurements to be in accordance with requirements of Subarticle IWP-4200. i 6.3.5.3 Justification Plant design does not incorporate direct pump inlet pressure indication. These pumps are of a vertical design with each pump suction casing submerged in a wet pit. 6.3.5.4 Alternate in Lieu of Section XI Requirements The water level in each wet pit is monitored dur-ing inservice testing of the respective pump. Pump inlet pressure is cal-culated by utilizing available station instrumentation to determine the appropriate wet pit level and calculating the available suction head at r s the pump inlet. 1

    '.)              6.3. 6 4

REQUEST FOR RELIEF

6. 3 . 6.1 Components Emergency service water pumps, emergency service water booster pumps, and emergency cooling water pump.

6.3. 6. 2 Requirement from Which Relief Requested Inservice test quantities shall include flow rate

measurement in accordance with Subarticle IWP-4600.

6.3.6.3 Justification Plant design does not include flow rate measure-cent instrumentation for these pumps. 6.3. 6.4 Testing in Lieu of Section XI Requirements Pumps will be inservice tested at pump shutoff head conditions in accordance with plant Technical Specifications.

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l 7-~ 6.3 . 7 REQUEST FOR RELIEF 6.3.7.1 Components 4 RHR pumps and high pressure service water pumps. 6.3.7.2 Requirement from Which Relief Requested Pump parameters to be compared with reference values in accordance with Subarticle IWP-3200. 6.3.7.3 Justification Reference values are defined in the Code as one or more fixed sets of values as measured or observed when the equipment is known to be operating acceptably. The flow resistance of the RHRS and high pressure service water system changes due to fouling of the system, and variations in the mode of operaton to satisfy plant conditions. It is, therefore, technically impossible to assign a fixed reference value to the parameters of pump flow and differential pressure, since these values j are inversely proportional to each other. 6.3.7.4 Testing in Lieu of Section XI Requirements f- Pump flow and differential pressures are compared ( with a reference head capacity curve as an alternative method of performing the evaluation. 6.3.8 REQUEST FOR RELIEF

6. 3 . 8.1 Components RHR pumps, standby liquid control pumps, high pressure service water pumps, emergency cooling water pump, and' emergency service water booster pumps.

6.3.8.2 Requirement from Which Relief Requested Measure and evaluate pump differential pressures in accordance with Subarticle IWP-4200. 6.3 . 8.3 Justification , The suction pressure is a function of river level, torus level, tank level, or upstream system pressure for these pumps. Pro-cedural controls are utilized to maintain a constant test suction pressure, or the level variations have an insignificant affect on differential pres-sure. It is therefore possible to accurately monitor pump performance trends by measuring only the discharge. pressure. ga 6-6

s 6.3.8.4 Testing in Lieu of Section XI Requirements l, The RHR, standby liquid control, high pressure service water, emergency cooling water, and emergency service water booster pump discharge pressures are measured and evaluated in lieu of their dif-ferential pressures when the variation in suction pressure is less than , one percent of the pumps differential pressure. l l f 3 4 ( 3 I 6-7

[ 7. INSERVICE TESTING OF VALVES 7.1 General The inservice testing program for Class 1, Class 2 and Class 3 "alves has been developed in accordance with the requirements of Sub-section IWV of the 1980 Edition of Section XI with Addenda through Winter 1981. Details of the inservice testing program for valves with requests for relief from Section XI requirements are identified in the section. 1 7.2 INSERVICE TESTING PROGRAM FOR CLASS 1. CLASS 2. AND CLASS 3 VALVES The inservice testing program for Class 1, Class 2, and Class 3 i- valves is detailed in Table 7.2-1. Table 7.2-1 identifies the valves to be tested, ASME Section XI category, test frequency, and type of test. Categories of valves subject to the rules of this subsection are defined as:

1. Category A - valves for which seat leakage is limited to a j specific maximum amount in the closed position for fulfillment i of their function.

4 (' i

2. Category B - valves for which seat leakage in the closed posi-tion is inconsequential for fulfillment of their function.

3. Category C - valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves).

l

4. Category D - valves which are actuated by an energy source

capable of only one operation, such as rupture discs or explosive-actuated valves.

i Inservice tests on valves will be performed with the test frequen- !~ cies specified in Table 7.2-1. Consistent with the treatment of surveil-i lance tes,ts-in the Technical Specifications, these test frequencies may be adjusted plus or minus 25 percent. In cases where the elapsed interval

             'has exceeded 100 percent of the specified interval the next test interval shall commence at the end of the original specified interval.
                      ; Valve exercising tests may be cancelled at the discretion of the Shift Superintendent-or his alternate when in his judgement the test could place the plant in an unsafe condition. Examples of this situation include certain valves inside containment where a test failure could negate the safety function of a system, and situations where a component is inoper-able and testing of the redundant component may cause an undesirable transient.

N i 7-1.

i

                  'A I                  Table 7.2-1 specifies the type of leak rate test required for the Category A valves. The leak rate test will meet the criteria of 10CFR50,                                   !

Appendix J, Type C leak rate testing (J) or meet the criteria for pressure  ; isolation (PI). . Pressure isolation criteria may be met by leak rate test-ing an alternate check valve or remotely operated valve in series with the pressure isolation valve, as designated in Table 7.2-1. 7.3 REQUESTS FOR RELIEF FROM SECTION XI REQUIREMENTS 7.3.1 REQUEST FOR RELIEF 7.3.1.1 ccaponents Category A valves identified in Table 7.2-1. 7.3.1.2 Requirement from Which Relief Requested ! Valve leak rate testing shall be performed in accordance~with Subsubarticle IWV-3420 of Section XI. 7.3.1.3 ' Justification , l Leak rate testing is already being conducted on Category A valves that perform a containment isolation function in accor-dance with the plant Technical Specifications, which conform as far as [~ ' practicable to the Criteria of Appendix J to 10CFR50. The NRC has reviewed and approved the existing containment isolation valve leak rate testing program. Category A valves performing a pressure isolation function will meet Section XI requirements, except for those valves requiring specific relief as noted in Table 7.2-1. 7.3.1.4 Testing in Lieu of Section XI Requirements Leak rate testing is performed and documented in accordance with the plant Technical Specification on Category A valves that perform a containmen't isolation function. Cate8ory A valves performing a . pressure isolation function are leak tested in accordance with Section XI, l or in accordance with the instructions of the NRC letter on pressure isola-l tion valves dated February 23, 1980, except for those valves requiring [ i specific relief as noted in Table 7.2-1. 7.3.2 REQUEST FOR RELIEF 7.3.2.1 Components All valves identified in Table 7.2-1 of the i Inservice Testing Program for Class 1, Class 2, and Class 3 valves. 7-2

l () 7.3.2.2 Requirement frou Which Relief Requested Corrective action for inoperable valves require the condition be corrected before unit startup from a cold shutdown condition in accordance with Paragraphs IWV-3417 and IWV-3523. 7.3.2.3 Justification i Constraints on unit startup with an inoperable I valve depend on many factors specific to individual plant design. Limit-ing conditions for operation have been analyzed and are identified within the plant Technical Specifications. 7.3.2.4 Alternate to Section XI Requirements l Inoperable valves will be evaluated within the l constraints of the plant Technical Specifications to determine when an 1 inoperable valve will prevent plant startup from a cold shutdown

condition. The evaluation shall specify when inoperable valves may be

repaired in accordance with plant conditions.

7.3.3 REQUEST FOR RELIEF l 7.3.3.1 Components i 1 Feedwater check valves 7V-6-28 (A, B) and - j VV-6-96 (A, B). 7.3.3.2 Requirement from Which Relief Requested Check valves shall be exercised at least once j every 3 months as provided by IWV-3522. I I 7.3.3.3 Justification . 1 1 ! There is no practical way to test these normally j open valves during reactor operation or cold shutdown in accordance with > Paragraph IWV-3522. Valves VV-6-28 (A, B), and VV-6-96 (A, B) are i normally open'during power operation; and open status is verified by j proper feedwater flow. Their safety function is to close for containment isolation during an accident. Since there is no external operator for the , i valve, the valves caa be closed only by a stoppage of feedwater flow which is impractical during power operation. Since the valves are of welded

construction, and the valve disk pins are totally enclosed, there is no

, practical way of observing the disk motion to verify proper valve opera-i

             - tion during exercising. Therefore, the exercising during cold shutdown is j                of no value. The positive closure and the leak tightness of the valves are verified by Appendix J testing once per operating cycle. Such testing

{ will ensure the safety function of the valves to the extent practical. d 7-3

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     ,j                             7.3.3.4                  Testing in Lieu of Section XI Requirements These valves will be Appendix J 1eak tested once                 l per operating cycle in accordance with the plant Technical Specifications.

7.3.4 - REQUEST FOR RELIEF 7.3.4.1 Components deactor water cleanup return check valve VV-12-62. , 7.3.4.2 sRequirement from Which Relief Requested

                                                          ' Check valves shall be exercised at least once every' 3 months as provi,ded by IWV-3522.

N 7.3!4.3 Justification

                                           \

There is no practical way to test this normally open ch' e ck valve during reactor operation or cold shutdown. Neighboring valves VV-6-28B (feedwater check) and M0-12-68 (reactor water cleanup return) are leak. tested in,accordance with the Technical Specifications to ensure isolation capabillries for this penetration. VV-12-62 is not designated as a containment isolation valve (CIV). Instead, M0-12-68 in O' the same line is designated as a CIV and is Appendix J tested and exercised quarterly as required by the Code. Such testing will adequately ensure the safety function of the associated containment penetration. 7.3.4.4 Testing in Lieu of Section XI Requirements Feedwater check VV-6-28B and reactor water cleanup return valve MD-12-68 are Appendix J leak tested in accordance with.the plan,t Technical Specifications to ensure isolation capabilities for this penetration. s , 7.3.$' , NEQUEST FOR RELIEF 7.3.5.1 Components Small control, solenoid, and check valves within Class *1 exeafd portion of Control Rod Drive Hydraulic System as identified on P&'.; ' 57. s , 7.3.5.2 Requirement from Which Relief Requested 3

5. Class 1 valves shall be categorized in accordance with Article IWV ,2000 and tested in accordance with Article IWV-3000.

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7.3.5.3 Justification These small valves cannot be practically tested to Section XI criteria. They have not been categorized nor included in Table 7.2-1. 7.3.5.4 Testing in Lieu of Section XI Requirements Scram testing of control rods is the only practical method of testing these small valves. Scram testing is performed on all control rods; consequently, all the affected small valves are functionally tested as part of the safety portion of the CRD system, near the end of 0.ach refueling outage. This frequency of testing is acceptable in accor-dance with plant Technical Specifications. 7.3.6 REQUEST FOR RELIEF 7.3.6.1 Components

                                ' Standby Liquid Control System discharge check valves VV-11-16 and VV-ll-17.

7.3.6.2 Requirement from Which Relief Requested Check valves shall be exercised at least once , every 3 months in accordance with IWV-3521. 7.3.6.3 Justification These check valves are normally closed during plant operation, and plant design does not provide a practical method of testing them on a quarterly basis. To establish flow through them, the entire pump discharge piping must be purged of boronated solution, the explosive valves (XV-ll-14 A or B) fired, and considerable manual valve movement must be performed which, during the performance of the testing, + would prevent the system from performing its intended function. 7.3.6.4 Testing in Lieu of Section XI Requirements The functional operability of these valves is confirmed while injecting demineralized water to the reactor pressure vessel once per operating cycle in accordance with plant Technical Specifications. 7.3.7 REQUEST FOR RELIEF l 7.3.7.1- Components RCIC and HPCI pump suction check valves VV-13-40 and VV-23-61. O 7-5

J 7.3.7.2 Requirement from Which Relief Requested Check valves shall be exercised at least once every 3 months in accordance with IWV-3521. , 7.3.7.3 Justification These check valves are in the HPCI and RCIC pump suction lines from the torus. The exercising of these check valves will require operation of RCIC or HPCI pumps, recirculating the lower quality suppression pool water. The lines should be flushed, drained, refilled, t and vented before routine Technical Specification surveillance tests ' (recirculation of condensate storage tank) are performed to avoid contami-1 nation of high quality condensate storage tank water. The process is time consuming and involves some-degree of risk to the plant until the process is completed and the system is ready for service. Therefore, the

;      exercising of the valve is not practical routinely on a quarterly basis during normal plant operation. The exercising during cold shutdown is also not practical because the main steam for the pump turbine is not available then.

7.3.7.4 Testing in Lieu of Section XI Requirements These valves will be exercised by passing flow through them once per operating cycle. 7.3.8 REQUEST FOR RELIEF 7.3.8.1 Components RCIC and HPCI turbine exhaust line vacuum relief

valves VRV-13-139 (A, B, C, D) and VRV-23-140 (A, B, C, D).

7.3.8.2 Requirement from Which Relief Requested i Relief valve setpoints shall be tested in accordance with IWV-3512. 7.3.8.3 Justification These valves are vacuum relief valves on the HPCI and RCIC turbine exhaust line to the torus. The valves are piped in a one out of two twice logic and as such cannot be individually tested without removing the valves. The vacuum relief valves are ordinary check valves and do not contain any spring for setpoint adjustment. They open simply by the differential pressure across their' seats. Therefore, setpoint verification,-required for a normal relief valve in accordance with IWV-3512, does not apply for these valves. ! v.b l l 7-6.

i l

 . \m-)                       7.3.8.4 Testing in Lieu of Section XI Requirements The valves are functional tested as a group by verifying passage of flow, to assure that a vacuum relief flow path exists through the valve arrangement. This test is performed quarterly.

7.3.9 REQUEST FOR RELIEF 7.3.9.1 Components Core Spray discharge header stay-full accumulator level makeup solenoid valves SV-14-4224 and SV-14-4225. RHR discharge headers and head spray header stay-full accumulator level makeup solenoid valves SV-10-4221, SV-10-4222, and SV-10-4223. 7.3.9.2 Requirement from Which Relief Requested Exercising of valves in accordance with the requirements of IWV-3412. 7.3.9.3 Justification These small valves are not testable per Paragraph IWV-3412 or by plant design; however, the valves are functionally checked continuously during plant operation. During normal operation of the C,_,%

      / plant, these valves are being continuously exercised for making up the accumulator level and also during monthly surveillance testing of Core Spray pumps or RHR pumps and quarterly surveillance testing of the asso-ciated level switches. Further, the inoperable status of these valves will result in a low level condition in the accumulators which is annunciated in the control room. Failure of any of these valves does not inhibit the safety function of the affected ECCS.

7.3.9.4 Testing in Lieu of Section XI Requirements Based on these considerations, the valves are considered to be in regular use and therefore need not be additionally exercised, provided the analysis and records of the observations of the valve operation are done in accordance with IWV-3414. 7.3.10 REQUEST FOR RELIEF 7.3.10.1 Components , Core Spray Condensate stay-full line check valves to pump discharge header VV-14-22 (A, B, C, D) and VV-14-23 (A, B, C, D). RHR header stay-full check valves VV-10-51, VV-10-63, VV-10-64, VV-10-73, VV-10-183 (A, B), and VV-10-184 (A, B). i A U 7-7 (

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  'M 7.3.10.2     Requirement from Which Relief Requested Check valves shall be exercised at least once every 3 months in accordance with IWV-3521.

7.3.10.3 Justification These small valves are not testable by plant design; however, the valves are functionally checked continuously during plant operation. During normal operation of the plant, these valves are being continuously exercised to keep tha pump discharge headers full and also during monthly surveillance testing of the pumps. Further, the inoperable status of these valves will result in a low level condition in the core spray stay-full accumulators which is annunciated in the control room. The consequence of failure of any of these small valves does not prevent the safety function of the affected ECCS. 7.3.10.4 Testing in Lieu of Section XI Requirements Based on these considerations, the valves are considered to be in regular use and need not be additionally exercised, provided the analysis and records of the observations of the valve operation are done in accordance with IWV-3414. 7.3.11 REQUEST FOR RELIEF O) (_. 7.3.11.1 Components RHR Head Spray Nozzle check valve VV-10-N214M3. 7.3.11.2 Requirement from Which Relief Requested Check valves shall be exercised at least once every 3 months in accordance with IWV-3521. 7.3.11.3 Justification This check valve is in the shutdown cooling line of the vessel head spray nozzle. Relief is requested from the requirement to exercise this valve quarterly in accordance with Paragraph IWV-3520. The head spray isolation valves, M0-10-32, 33 are automatically isolated by the primary containment isolation system when reactor pressure is above 75 psig. This valve is exercised by passing flow through it during reactor vessel head spray operation to accommodate the approach to the cold shutdown condition. l 7.3.11.4 Testing in Lieu of Section XI Requirements Exercising of the valve during reactor vessel O, head spray operation will be performed once per operating cycle. N~-) 7-8

7 i 7.3.12 REQUEST FOR RELIEF 7.3.12.1 Components l Emergency Service Water header check valves, VV-33-513, VV-33-514, and VV-33-516. 7.3.12.2 Requirement from Which Relief Requested f g Check valves shall be exercised at least once  ; every 3 months in accordance with IWV-3521. 7.3.12.3 Justification These valves provide emergency service water or emergency cooling water to safety-relatcd heat exchangers if the normal cooling water supply (service water) is lost. Functional exercising of these valves is not practical during plant operation when the service a water system is operating. Testing requires manually isolating the -j emergency service water system from the service water system and manual _ U operation of several valves to establish the proper flow paths. These m operations can result in temporary loss of cooling to safety-related heat ;;; exchangers and thereby, jeopardize safety-related equipment and reactor  ; a operation and safety. _

 ?                     7.3.12.4   Testing in Lieu of Section XI Requirements These valves shall be exercised once per operating cycle in accordance with the plant Technical Specifications.       g 7.3.13 REQUEST FOR RELIEF                                            j c                                                                                  .

7.3.13.1 Components  ; I Emergency Service Water Booster Pump discharge

  ;     check valve VV-48-0504 (A, B) and Emergency Cooling Water Pump discharge       -

e check valve VV-48-0-506. 7.3.13.2 Requirement from Which Relief Requested { Check valves shall be exercised at least once t every 3 months in accordance with IWV-3521. = e k 7.3.13.3 Justification 5 Functional exercising of these valves is not s practical during plant operation with the normal plant service water - system in service. These valves provide emergency service water or - emergency cooling water to safety-related heat exchangers if the normal ' cooling water supply (service water) is lost. Functional exercising of these valves is not practical during plant operation when the service

                                                                                       =

K 7-9

1 water system is operating. Exercising of these valves requires operation [S

 \_-) of the Emergency Service Water Booster Pump and Emergency Cooling Water Pump. Testing requires manually isolating the emergency service water system from the service water system and manual operation of several valves to establish the proper flow paths. These operations can result in temporary loss of cooling to safety-related heat exchangers and thereby jeopardize safety-relatad equipment and reactor operation and safety.

7.3.13.4 Testing in Lieu of Section XI Requirements These valves shall be exercised once per operat-ing cycle per unit, approximately every nine months, in accordance with plant Technical Specifications. - 7.3.14 REQUEST FOR RELIEF 7.3.14.1 Components RHR Fuel Pool Cooling check valves VV-19-MK273M3 (2 valves). 7.3.14.2 Requirement from Which Relief Requested Chcek valves shall be exercised at least once 4 every 3 months in accordance with IWV-3521. () 7.3.14.3 Justification These check valves are in the RRR cooling water lines to the spent fuel pool. Normal periodic exercising is not practical due to valve and plant design. This line is used for augmentation of fuel pool cooling by the RHR system when a full core is unloaded. The line is not required for safe shutdown of the plant. Use of the RHR System cross-connection to inject RHR water into the spent fuel pool to exercise these valves would unnecessarily contaminate the spent fuel pool with corrosion products from the carbon steel piping within the RHR System. 7.3.14.4 Testing in-Lieu of Section XI Requirements Exercising of these valves is demonstrated whenever the RHR System is rec,uired to cool the spent fuel pool. 7.3.15 REQUEST FOR RELIEF 7.3.15.1 Components Main Steam vacuum relief valves VRV-307A through H and J, K and L. l l O- - 7-10 l

L () 7.3.15.2 Requirement from Which Relief Requested Relief valve setpoints shall be tested in , accordance with IWV-3512. 7.3.15.3 Justification

These valves are the vacuum relief valves on the tail pipes from main steam relief valves to the torus. The setpoint of these valves cannot be adjusted and is determined by proper installation of a torsion spring between the valve body and disc. Valve maintenance is performed in accordance with a detailed procedure to assure proper valve assembly during maintenance.

i 7.3.15.4 Testing in Lieu of Section XI Reauirements i In lieu of setpoint testing, the valve disc will be manually exercised once per operating cycle.

;                           7.3.16 REQUEST FOR RELIEF 7.3.16.1                               Components l                                                                                Standby Liquid Control System discharge check j                valve VV-ll-16.

7.3.16.2 Requirement from Which Relief Requested i Valve seat leakage tests shall be performed in accordance with IWV-3423.

;                                       7.3.16.3                               Justification

. This check valve is in the standby Liquid Control. ] System injection line to the reactor. There is no test tap between VV-11-16 and XV-11-14 to monitor leakage, and thus it is not practical to perform such leak rate testing. 7.3.16.4 Testing in Lieu of Section XI Requirements Appendix J rate testing is performed on VV-ll-16 l in accordance with plant Technical Specifications. I 7.3.17 REQUEST FOR RELIEF ' 7.3.17.1 Components ECCS pump minimum flow check valves VV-14-66 (A, , B, C, D), Core Spray System VV-10-19 (A, B, C, D), RER System VV-13-29

RCIC System, and VV-23-62 HPCI System.

t 7-11

 ,  s_ /                   7.3.17.2        Requirement from Which Relief Requested Check valves shall be exercised at least once every 3 months in accordance with IWV-3522.

7.3.17.3 Justification These check valves are downstream of the motor operated minimum flow recirculation valves on ECCS pumps. Plant design does not provide a method of proving the passage of flow through these check valves to demonstrate valve operability. 7.3.17.4 Testing in Lieu of Section XI Requirements These valves are exercised during surveillance testing of these systems in accordance with the plant Technical Specifications.

 !-              7.3.18 REQUEST FOR RELIEF 7.3.18.1        Components l

Instrument nitrogen supply check valves VV-51 i (2 valves). 7.3.18.2 Requirement from Which, Relief Requested Check valves shall be exercised at least once every 3 months in accordance with IWV-3521. 7.3.18.3 Justification These check valves are in the nitrogen supply lines to pneumatic valve operators in containment. Plant design does not allow testing of these check valves unless the primary containment is accessible. 7.3.18.4 Testing in Lieu of Section XI Requirements l These valves shall be exercised once per operating cycle during Appendix J leak rate testing. 7.3.19 REQUEST FOR RELIEF 7.3.19.1 Components Containment Atmospheric Control oxygen analyzer , check valve VV-9-( ). l lO 7-12

O 7.3.19.2 REQUEST FOR RELIEF Check valves shall be exercised at least once every 3 months in accordance with IWV-3521. 7.3.19.3 Justification This check valve is normally open during plant operation to allow return flow from the containment oxygen analyzer back to containment. The containment oxygen analyzer is required to ensure that the oxygen concentration in containment does not exceed 4% during reactor operation creating a potentially explosive atmosphere in contain-ment. Since testing would require taking the analyzer out of service for a considerable length of time, such testing is not practical on a quarterly basis. 7.3.19.4 Testing in Lieu of Sectien XI Requirements Once per operating cycle, the ability of this valve to check flow will be confirmed by a satisfactory leak rate test in accordance with plant Technical Specifications and the criteria of Appendix J to 10CFR50. 7.3.20 REQUEST FOR RELIEF O 7.3.20.1 Components Standby Gas Treatment System Butterfly valves A0-0-0470-1, A0-0-0470-2, A0-0-0475-1, A0-0-0475-2, A0-0-0476-1, A0-0-0476-2, A0-0-0469-1, and A0-0-0469-2. 7.3.20.2 Requirement from Which Relief Requested Requirements to verify valve position indicator accuracy in accordance with IWV-3300. 7.3.20.3 Justification Thesevalvesarebutterflyvalvesinthesugply to SBGT system and SBGT system filter isolation valves. Secondary containment isolation valves are tested by leak rate testing or by visually observing damper position via inspection ports -in the ducts. The ducts at the SBGT system filter isolation valves and system supply valves do not have inspection ports to observe damper position. Plant design does not provide-any other practical method of proving valve position for these valves. 7.3.20.4 Testing in Lieu of Section XI Requirements Flow through these valves is verified during O. testing of secondary containment integrity. 7-13

O (j 7.3.21 REQUEST FOR RELIEF 7.3.21.1 Components LPCI cross-tie valve MD-10-20. 7.3.21.2 Requirement from Which Relief Requested Category A and B valves shall be exercised at least once every 3 months in accordance with IVW-3411. 7.3.21.3 Justification This valve cross-connects the two LPCI injection loops. Plant Technical Specifications require this valve to be electri-cally locked in the closed position during reactor power operation. Operability of this valve in the open position has no safety-related function. Opening of the valve defeats the independence and redundancy of the LPCI loops and may result in a potential loss of the complete system l in the event of a single failure in'one loop. This valve is only opened occasionally, when shut down, for convenience, to allow flexibility in the use of equipment to provide shutdown cooling. 7.3.21.4 Testing in Lieu of Section XI Requirements This valve is full stroke exercised once per operating cycle in accordance with plant Technical Specifications. 7.3.22 REQUEST FOR RELIEF 7.3.22.1 Components RHR Suction valves MO-10-17 and M0-10-18, RHR Head Spray valves MO-10-32 and MO-10-33, Feedwater long path recirculation valves M0-6-38 (A, B), RHR Return valves MD-10-25 (A, B), HPCI Steam Supply valves MO-23-15 and 16, Core Spray Pump discharge piping valves MO-14-12 (A, B), RCIC Steam Supply valves M0-13-15 and 16, HPCI pump discharge pumping valve MO-23-19, and RCIC Pump discharge piping valve MO-13-21. 7.3.22.2 Requirement from Which Relief Requested Requirements to perform pressure isolation leak rate testing in accordance with IWV-3423. 7.3.22.3 Justification These motor-operated valves are pressure isolation valves associated with ECCS or primary containment isolation system. Relief is requested from the requirement to perform pressure O., isolation valve leak rate testing. These valves, when closed, prevent

• intersystem LOCA from the reactor coolant system to low pressure piping.

7-14

i 4 5 NUREG-0677: "The Probability of Interaystem LOCA: Impact Due to Leak Testing and Operational Changes" addresses pressure isolation valve l testing, and states that motor-operated valves "do not exhibit the leak rate mode of failure because the valve is under positive control by its

                              ~

motor operator and because position indication is provided. Any small

seat leakage that did occur is not expected to be large enough to cause an intersystem LOCA." The only failure mode of these valves that would result in intersystem LOCA is catastrophic failure of the valve internals.

Pressure isolation valve testing during reactor startup would not assist in determining if such failure would occur. The pressure en the low pressure side of the following valves (MO-10-17, 18, 25 A, B, 32, 33; MO-14-12 A, B) is continuously monitored by pressure switches which annunciate on a high pressure condition. These pressure switches are ! functionally tested annually. Relief valves are also installed on the low pressure side of these isolation valves. These relief valves are tested in accordance with Paragraph IWV-3512. In the letter from the NRC to LWR licensees, 2/3/80, concerning LWR primary coolant system pressure isolation valves, this surveillance is considered an acceptable method of reducing the probability of an intersystem LOCA. i ! 7.3.22.4 Testing in Lieu of Section XI Requirements t l In lieu of pressure isolation valve leak rate testing, each valve will be checked in the closed position during reactor startup and after surveillance testing which operates these valves. i f l O 7.3.23 REQUEST FOR RELIEF 4

  ,                                     7.3.23.1                       Components 4

i Categories A and B valves with electric motor operators. 7.3.23.2 Requirement from Which Relief Requested i l Valve stroke time shall be compared with the l previous test results in accordance with Paragraph IWV-3417.

7.3.23.3 Justification i

Electrically driven motor operator stroke times , do not vary significantly. Excessive valve resistance results in motor overcurrent, and an electrical tripping of the motor operator. Comparing j the evaluation to previous test data would therefore be meaningless. 7.3.23.4 Testina in Lieu of Section XI Requirements An evaluation is performed by comparing the i stroke time on electrically driven valves with the more conservative of j the following two limitst (1) the limiting value of full stroke deter-mined by the Technical Specification; or by some other technical evalua-tion that establishes the criteria for determining the operability status I 5 l oo i j ,7-15

    ,e. e.,,    .+4 m   .---c   .-, --     ,..~-m.        - . , . , - - .      ~-,-.-:.,,---.----,.,-,,,.*,._,,-,,-.-y-c--.-~~-,-..r                      -,--,,.m.-y.-      ,_mw. ,,mu,

i l of the valve, or (2) increase in stroke time of 25 percent or more, from the normal or expected stroke time, with stroke times greater than  ; 10 seconds; or an increase in stroke time 50 percent or more, from the normal or expected stroke time, for valves with stroke times less than or j equal to 10 seconds. 7.3.24 REQUEST FOR RELIEF i 7.3.24.1 conoonents ,

 ,                                                  Power operated valves with a specified limiting j                  stroke time of less than 4 seconds.                                                    i 7.3.24.2 Requirements from Which Relief Requested 4

! When an increase in stroke time of 50 percent or f- more is observed, the test frequency shall be increased to once each month r

- until corrective action is taken, in accordance with Paragraph IW-3417. l 7.3.24.3 Justification l A valve with a specified limiting stroke time of

10 seconds need only have the stroke time measured to the nearest second. '

Measuring 50 percent of the stroke time, of a valve with a specified i

limiting stroke time of less than 4 seconds, would require measuring

!                 fractions of a second which is in contradiction to the scope of testing.

l Additionally, measuring 50 percent or more of a specified limiting stroke  ; ! time of less than 4 seconds would be highly subject to interpretation by i i the operating / testing personnel and would not provide meaningful  ; !- infornation. l i

j. 7.3.24.4 Testina in Lieu of Section XI Requirements s

)_ Valves with a stroke time of less than 4 seconds ( ) will r.ot be stroked on a monthly basis if the specified limiting stroke l 1 time is exceeded by 50 percent or more. Instead, if the specified  ! i limiting stroke time is exceeded, limiting conditions for operation shall ' l be analyzed as identified with the plant Technical Specifications. j i ! 7.3.25 REQUEST FOR RELIEF I [

7.3.25.1 Components Power operated valves with a specified limiting stroke time of less than 2 seconds, such as solenoid operated valves.

i 7.3.25.2 Requirements from Which Relief Requested

Measurement of stroke time in accordance with Paragraph IWV-3413 and corrective action per Paragraph IWV-3417.

7-16

l I  !

4 Q d 7.3.25.3 Justification i Po9er operated valves with a specified limiting }

;                  stroke time of less than 2 seconds by design, cannot be measured to the

. nearest second.

l 7.3.25.4 Testina in Lieu of Section XI Requirements j In lieu of stroke time seasurements, the valve shall be checked for operability and if it fails to operate, limiting i conditions for operation shall be analyzed as identified with the plant , Technical Specifications. . { 7.3.26 COMPONENTS REQUIRING RELIEF [ > j j 7.3.26.1 Components I i All actor-operated valves with remote position  ; indicators. ! 7.3.26.2 Requirement from Which Relief Requested

• 1

!                                                                                           All actor-operated valves with remote position indicators observed in accordance with Subarticle IW-3300.

i 7.3.26.3 Justification , Our present program for the adjustment and verifi-cation of the limit switches on motor-operated valves ensures that the i remote valve indicators accurately reflect valve operations. After mainte-j nance on the valve or its operator, the limit switches are adjusted in accordance with a maintenance procedure and the activity documented in the j { procedure. The valve is stroked to verify proper operation after the adjustments and this fact is documented in our maintenance records. This  ; j program satisfies the intent of Subarticle IW-3300. 7.3.26.4 Testina in Lieu of Section XI Requirements

- The maintenance program described above is per- ,

formed to satisfy the intent of Subarticle IW-3300 on motor-operated i

valves.

7.3.27 REQUEST FOR RELIEF , 1 7.3.27.1 Components J ! Category A valves. l i 1 i l i 1 , 7-17 i r

  -y  ,,     ,-       . - . . - -              -
                                          ,....-,.----..-y,                ,r,.*      ,,%.y    -..,,,-----..-r,-..,             ,        --.m.-.-m.-- - ,_., ----..-.---,- _   .%-    - - - , , - , . ~ - - . ~ , -

    .                      . _ ~ . - . _             __     .     . _ _ . _ _ _ _ _ _ _ _ _             __ _ _ -             _ . _ . _    _.   . _ _ .

1 7.3.27.2 Requirement from Which Relief Requested

;                                                 Method for determining valve seat leakage in accordance with Subsubarticle IWV-3420.

7.3.27.3 Justification The methods described do not permit leak rate testing during reactor startup or power operation, or present a possible personnel safety hazard in the event a telltale drain is opened for leak rate testing. 7.3.27.4 Testing in Lieu of Section XI Requirements In addition to the methods described in Subsub-article IWV-3420, the following method may be used to verify leak-tightness. One or more normally closed valves on the line shall be closed and the leakage rate determined by measuring and evaluating the rate of pressure i increase in an isolated section of the line adjacent to the pressure isolation valves. These methods may apply the requirements of the NRC generic letter on leak rate testing pressure isolation valves dated February 23, 1980. I i 7.3.28 REQUEST FOR RELIEF 7.3.28.1 Components i All Class 1, Class 2, and Class 3 valves } requiring testing per Subsection IWV. 7.3.28.2 Requirement from Which Relief is Requested j

Requirements of Article IWV-6000 to provide special tests and records management for inservice testing of valves.

I 7.3.28.3 Justification Existing plant surveillance test procedures docu-

;     ment most of the special test conditions and parameters identified in the l      Subsubsection on IWV of Section XI.

7.3.28.4 Alternate to Section XI Requirements i Surveillance tests are reviewed and revised as required to incorporate the necessary documentation to meet Section XI i requirements for valve testing. Surveillance tests are retained at the 4 plant site and are available for audit by the enforcement authority. i 1 O 7-18 p r

            .--,-e.               .v     .. . , , -     ,     -

r , ,m.r - . _ . . _ , ,, _. . . . - . _ _. _ , c

  . __      _ . _ _        .__     _    _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ .                              m.  .          _ . _ _     _   .__m   .

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2. ABE) CLASS 3 VALVES P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES GORY TEST * (FENCY* EXCEPTIONS

• REQUEST No-33-972 Cate 12" Emergency S.W. M-315 (F-2) B F Q (7.3) 2,23,28 A0-33-0-241-A Dia. 6" Emergency S.W. M-315 (D-7) B F Q Common (7.3) 2,24,28 A0-33-0-241-3 (D-7)

A0-33-0-241-C (D-6) A0-33-0-241-D (D-6) , A0-33-334-A Dia. 2* Emergency S.W. M-315 (G-3) 5 F Q (7.3) 2,24,28 A0-33-334-3 (G-3) Y y A0-33-333-A Dia. 1.5" Emergency S.W. M-315 (C-3) B F Q (7.3) 2,24,28 A0-33-333-3 (C-3)  ; A0-33-335-A Dia. 2" Emergency S.W. M-315 (C-7) B F Q (7.3) 2,24,28 , AO-33-335-3 (G-6) AO-33-335-C (C-6) A0-33-335-D (C-6) ., AO-33-335-E s (G-5) A0-33-335-F (C-5) , A0-33-335-C (G-4)

;       AO-33-335-H                                                                                       (C-4) 1       A&-33-336-A      Dia. 1.5"        Emergency S.W.                                 M-315          (C-7)       B        F         Q                    (7.3) 2,24,28 A0-33-336-5                                                                                       (C-6)

A0-33-336-C (G-6) A0-33-336-D (C-6) A0-33-336-E (C-5) A0-33-336-F (C-5) A0-33-336-C (C-4) A0-33-336-H (C-4)

        *See key or the exceptions at the end of this' table.

_f

         \

w TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2 AM CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE -VALVE C00RDI- CATE- 0F FRE- OR RELIEF' VALVE I.D. TYPE SIZE SYSTEM P&ID IMATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST VV-33-515-A Test- 20" Emergency S.W. M-315 (B-7) C M Q (7.3) 2,28 VV-33-515-B able , (3-6)

Check

   . VV-33-516                 Check   12"  Emergency S.W.            M-315                  (F-2)       C             V                  A.                               (7.3) 2,12,28 I
    'VV-33-513                 Check    6"  Emergency S.W.            H-315                  (F-2)       C             V                 A                                 (7.3) 2,12,28 VV-33-514                 Check    6"  Emergency S.W.            M-315                  (F-2)       C             V                 A                                 (7.3) 2,12,28 VV-32-$02-A              Test-    14"  High Pres.                M-315                  (B-4)       C             V                  Q                                (7.3) 2,28 VV-32-502-3               able         Service Utr.                                     (B-3)

VV-32-502-C Check (B-4) t VV-32-502-D (5-2) 1 , MO-34-2374 Cate 4" React. Bldg. CW M-316 (E-9) A F C (7), J (7.3) 1,2,23,

MO-34-2373 (E-6) 7',28

. VV-0-( ) Check 2" Diesel Cil M-323 (u-6) C V Q Common (7.3) 2,28 VV-6-( ) (C-6) VV-0-( ) (F-6) VV-0-( ) (E-6) J MO-44-2201-A Cate 9" Chilled Water M-327 (E-3) A F C (8), J (7.3) 1,2,23, i MO-44-2201-B (D-3) 27,28 I MO-44-2200-A Cate 9" Chilled Water M-327 (D-3) A F C (8), J g.3g1,2,23, MO-44-2200-3 (C-3) ,2 s

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST VV-48-0-506 Test- 18" Emerg. Cooling M-330 (C-3) C V A Common (7.3) 2,13,28 able Check

     .VV-48-0-504-A           Check    16"           Emerg. Cooling              M-330           (E-7)      C   V              A     Common          (7.3) 2,13,28 VV-48-0-504-B                                                                             (D-7) l y     MO-32-486              Cate     24"           High Pres.                  M-330          (D-9)       B   F              Q                     (7.3) 2,23,28 4

H Service Wtr. MO-48-0-498 Cate 20" Emergency S.W. M-330 (D-9) B F Q Common (7.3) 2,23,28 MO-48-804-A Butter- 24" Emerg. Cooling M-330' (C-3) B F Q (7.3) 2,23,28 MO-48-804-B fly (C-2) MO-48-0-841 Cate 18" Emerg. Cooling M-330 (C-3) B F Q Common (7.3) 2,23,28 MO-48-0-501-A Cate 16" Emerg. Cooling M-330 (D-3) B F Q Common (7.3) 2,23,28 MO-48-0-501-B (D-2) NO-48-0-501-C (D-2) MO-48-0-502-A Cate 16" Emerg. Cooling M-330 (E-3) B F Q Common (7.3) 2,23,28 MO-48-0-502-B (E-3) MO-48-0-502-C (E-2) MO-32-803 Cate 12" High Pres. M-330 (E-8) B F Q Emerg Cool. (7.3) 2,23,28 Service Wtr. Cross.

C O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) i P&ID TYPE TEST NOTES

.                             VALVE VALVE                                         C00RDI-           CATE-    0F               FRE-     OR               RELIEF VALVE I.D.              TYPE  SIZE         SYSTEM                P&ID       INATES            CORY  - TEST

• QUENCY* EXCEPTIONS
• REQUEST

. AO-51-2969-A Dia. 1" Inst. Nitrogen M-333 (C-4) A F Q J (7.3) 1,2,24, , 1 AO-51-2969-5 (F-4) 27,28 SV-51-8130-A Cate 1" Inst. Nitrogen M-333 (C-4) A F Q J (7.3) 1,2,25, SV-51-8130-3 (B-4) 27,28

y. VV-51-( ) Check 1" Inst. Nitrogen M-333 (C-4) A/C V A J (7.3) 1,2,18, 4 VV-51-( ) (F-4) 27,28 n

SV-51-8100 Cate 2" Inst. Nitrogen M-333 (D-5) A F Q J (7.3) 1,2,25, 27,28 A0-51-4235 Cate 2" Inst. Nitrogen M-333 (D-5) A F Q J (7.3) 1,2,24, 27,28 I VV-51-( ) Check 1" Back up Inst. M-333 (C-4) A/C V Q J (7.3) 1,2,18, VV-51-( ) Nitrogen (B-4) 27,28 f AO-1-86-A Globe 26" Main Steam M-351 (C-2) A F/P Q (1), J (7.3) 1,2,27, ! A0-1-86-B 28 l AO-1-86-C AO-1-86-D l i l AO-1-80-A Clobe 26" Main Steam M-351 (C-4) A F/P Q (1), J (7.3) 1,2,27, i

AO-1-80-B 28 AO-1-80-C A0-1-80-0 9

1 i

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

                                                              ,-                                                             ~

TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST RV-1-71-A Pres. 6" Main Steam M-351 (C-5) C S 2 (2),(3) (7.3) 2,28 RV-1-71-B Relief B M A RV-1-71-C RV-1-71-D RV-1-71-E RV-1-71-F RV-1-71-C I

RV-1-71-H y RV-1-71-J N RV-1-71-K RV-1-71-L VRV-307-A Vacuum 12" Main Steam M-351 (C-3) C H A (7.3) 2,15,28 VRV-307-5 Relief VRV-307-C VRV-307-D VRV-307-E VRV-307-F VRV-307-C VRV-307-H VRV-307-J VRV-307-K VRV-307-L j ' RV-1-70-A Pres. 6" Main Steam M-351 (C-5) C S 2 (2),(3) (7.3) 2,28 RV-1-70-B Relief B M 2 MO-1-74 Clobe 3" Main Steam M-351 (C-4) A F C (9), J (7.3) 1,2,23, 24,27,28 i i4

O O TABLE 7.2-1 1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AIO CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST j NO-1-77 Clobe 3" Main Steam N-351 (C-3) A F C (9), J (7.3) 1,2,23, 24,27,28 i NO-2-43-A Cate 28" Reactor Recirc. M-351 (C-6) B F C (4) (7.3) 2,23,28 MO-2-43-B NO-2-53-A Cate 28" Reactor Rectre. M-351 (C-5) B F C (4) (7.3) 2,23,28 MO-2-53-B

        ]*
!       y  VV-6-28-A                                          Check                   24"    reedwater          M-351                (F-6)          A/C              F         A                     J               (7.3) 1,2,3, l

VV-6-28-B (E-6) 27,28 VV-6-96-A Check 24" Feedwater M-351 (F-7) A/C F A J (7.3) 1,2,3, VV-6-96-B (E-7) 27,28 NO-6-38-A Cate 10" Feedwater M-351 (F-7) A F A (10),J PI (7.3) 1,2,22, NO-6-38-B (E-7) 23,27,28 .; VV-11-17 Check 15" Standby Liquid M-351 (E-4) A/C V A PI (7.3) 1,2,6, 27,28 VV-11-16 Check 15" Standby Liquid M-351 (E-3) A/C V A J,PI (7.3) 1,2,6, j 16,27,28 A0-1-316 Dia. 0.75" Main Steam M-351 (B-6) A F Q J (7.3) 1,2,24, AO-1-317 (B-8) 27,28 i 't I

s j tI 1:  ! ,l .1 I {  ;- 4 3 3 3 8 , , , FT 2, 2, 2, 2, 2, 5, 5, 5, 8 ES I E 2, 2, 2, 2, 4, 2, 2, 2, 2, O LU 1 1 1 1 2 1 1 1 2 EQ ) ) RE )8 )8 )8 )8 )8 )8 )8 R 32, 32, 32, 32, 3 32, 32, 32, 3 77 77 77 77 7 77 77 77 7 (2 (2 (2 (2 ( (2 (2 (2 ( S N O S I .

-                      E    T                                                                                              )

TRP J J J J J J J . OOE 6 (

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.                           E Y

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( E T E S PFS YOE F F F F F F F

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F M E T T A V R L _ G O A V - D R EY / _ P 3 TR A A A A C A A A B _ 1 AO

             - G S       CC 2  N S                                 -

. I A 7 T L S C - ) ) . . E E IS )) ) ) ) ) )) )0 )1 )) - _ L T D DDE 77 2 3 7 5 66 31 31 22 - B N IRT - - - - - - - - - - - - - - - A E A &0A 55 C C B B DD BB B B EF T C P0N (( ( ( ( ( (( (( (( (( I . CI V 2

._             R E S              1       4         4     4         4    6             6              6                    8 S S          D   5       5         5     5         5    5~            5               5                   5

_. N A I 3 3 3 3 3 3 3 3 3 I L & - - - - - - - - -

.                C          P   M       M         M     M         M    M             M                M                    M             .

_.. 1 .

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.-               S               e         p       p      p        p    v             v                v                  d S               r         u       u      u         u  i             i                i                    i
._               A              i          n       n     n         n    r             r               r                     u L               c         a       a     a         a   D             D                D                     q

_ C M e e e e e i E R l l l l d d d L _. T C C C C o o o S r R R R y _ Y o . . . . b S t t t t t . . . d n c c c c c 1 1 1 a a a a a r r r a e e e e e t t t t _ R R R R R C C C S , E " VE 5 LZ 7 " " " " " "

• AI 6 6 4 4 1 1 'I 6 VS 0 y

E e k VE . e e b c . . . e LP a t t o e a a a t AY i a a l h i i i a VT D C C G C D D D C AR A3 B - D. 5 8 8 2 - - A- - 44 I 90 1 1 6 6 36 22 55 11 34 - - - - 33 33 33 - - E - - 2 2 2 2 - - - - - - 11 V 22 1 1 1 1 33 33 33 11 L - - - - - - - - - - - - - - A OO O O O V VV VV VV VV V AA M N M V CC CC CC XI . yy ii  ;

                                      ]         "             '                  . '        l     -              ii '                , ,

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM

                                                                                                . CLASS 1, CI. ASS 2 AIS CLASS 3 VALVES (Cont'd)

P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID IMATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST l EV-11-39-A Pres. 1" Standby Liquid M-358 (E-6) C S A (7.3) 2,28 RV-11-39-R Relief (J-6) t vv-11-43-A Check 15" Standby Liquid M-358 (F-5) C V Q (7.3) 2,28 VV-11-43-R (J-5)

MO-13-15 Cate 3" RCIC M-359 (C-6) A F Q J. (PI) (7.3) 1,2,22,23, 27,28 Y g MD-13-16 Cate 3" RCIC M-359 .(C-7) A F Q J, (PI) (7.3) 1,2,22,23, 1 27,28 i MO-13-21 Cate 6" RCIC M-359 (E-7) A F Q J. PI (7.3) 1,2,22,23, 27,28 l MO-13-41 Gate 6" RCIC M-359 (L-8) B F Q (7.3) 2,23,28 I MO-4244 Cate 3" RCIC M-359 (H-7) A F Q J (7.3) 1,2,23, 27,28 AO-13-22 Check 6" RCIC M-359 (E-7) A/C M C (5), PI (7.3) 1,2,27,28 VV-13-50 Check 10" RCIC M-359 (J-8) A/C V Q J (7.3) 1,2,27,28 { VV-13-29 Check 2" RCIC M-359 (H-8) C - - (7.3) 2,17,28 VV-13-38 Check 2" RCIC M-359 (J-9) A/C V Q J (7.3) 1,2,27,28 t 1 L i , i'  ; i

r O O

                                                                                                                                      ~

TABLE 7.2-1 INSERVICE TESTING PROGRAM i CLASS 1, CLASS 2. AND CLASS 3 VALVES (Cont'd) . P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIE'7 VALVE I.D. TYPE SIZE SYSTEN P&ID INATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST NO-13-18 Cate 6" RCIC N-359 (D-11) B F Q (7.3) 2,24,27, 28 i

No-13-20 Cote 6" RCIC M-359 (E-8) B F Q (7.3) 2,24,27, 28 1 No-13-39 Cate 6" RCIC H-359 (D-10) A F Q J (7.3) 1,2,23,

 ;                                                                                                                                                                              27,28
        %J i       4 No-13-30                  Clobe              4"    RCIC                 M-359                        (B-8)              B      F       Q                               (7.3) 2,23,28 HO-13-131              Clobe              4"   -RCIC                 M-359                        (E-13)             B      F       Q                               (7.3) 2,23,28

] MO-13-27 Clobe 2" RCIC H-359 (H-8) B F Q (7.3) 2,23,28 AO-13-32 Dia. 1" RCIC N-359 (F-14) B F Q (7.3) 2,24,28 A0-13-34 Dia. 1" RCIC M-359 (J-14) B F Q (7.3) 2,24,28 A0-13-35 Dia. 1" RCIC M-359 (K-14) B F Q (7.3) 2,24,28

!            VRV-13-139-A           Check              2"   .RCIC                 M-359                        (J-6)              C      V       Q                                (7.3) 2,8,28        :

VRV-13-139-B VRV-13-139-C

,            VRV-13-139-D i

t VV-13-40 Check 6" RCIC N-359 (L-9) C V A (7.3) 2,7,28 'T s

O O O TABLE 7.2-1 , INSERVICE TESTINC PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd)

                  .                                                                                            P&ID                       TYPE    TEST        NOTES

, VALVE VALVE C00RDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&lD INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST VV-13-19 Check 6" RCIC M-359 (D-11) C V Q (7.3) 2,28 A0-13-137 Dia. 2" RCIC M-360 (J-9) A F Q J (7.3) 1,2,27,28 1 (4240)

$ A0-13-138 Dia. 2" RCIC M-360 (J-9) A F Q J (7.3) 2,24,29 (4241) Y RV-13-25 Pres. 1.5" RCIC M-360 (C-8) C S T (7.3) 2,28 , j $ Relief RV-13-26 Pres. 1" RCIC M-360 (J-7) C S T (7.3) 2,28 Felief l .A0-13-12 Dia. 1" RCIC M-360 (L-8) B F Q (7.3) 2,24,28 A0-13-13 (L-8) MO-13-132 clobe 2" RCIC M-360 (H-7) B F Q (7.3) 2,23,28 , MO-13-4487 Clobe 3" .RCIC M-360 (E-12) B F Q (7.3) 2,23,28 (*) 4 VV-13-133 Check 2" RCIC M-360 (K-9) C V Q (7.3) 2,28 VV-13-134 (K-11) MO-10-25-A Cate 24" RHR M-361 (C-5) A F Q J, PI (7.3) 1,2,22,23 i

MD-10-25-B (C-9) 27,28 i

4

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2. AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• _QUENCY* EXCEPTIONS
• REQUEST AO-10-46-A Check 24" RHR M-361 (D-5) A/C H C (5),J,PI (7.3) 1,2,27,28 ,

AO-10-46-B (D-9) MO-10-32 Cate 6" RHR M-361 (B-6) A F C (11),J,PI (7.3) 1,2,22,23 27,28 MO-10-33 Cate 6" RHR M-361 (A-5) A F C (11),J,PI (7.3) 1,2,22,23 y 27,28 VV-10-N214M3 Check 6" Rita M-361 (B 7) C V A (7.3) 2,11,28 MO-10-17 Cate 20" RHR M-361 (F-7) A F C (11),J,PI (7.3) 1,2,22,23, 27,28 HO-10-18 Cate 20" RilR M-361 (E-7) A F C (11),J,PI (7.3) 1,2,22,23, 27,28 MO-10-34-A Clobe 18" RHR M-361 (D-3) A F Q J (7.3) 1,2,23, , HO-10-34-8 (D-10) 27,28 l l MD-10-31-A Cate 12" RHR M-361 (B-6) A F Q J (7.3) 1,2,23, 4 MO-10-31-B (B-8) 27,28 MO-10-38-A Clobe 4" RIIR M-361 (D-3) A F Q J (7.3) 1,2,23, MO-10-38-8 - (D-11) 27,28 1 l 1

r

  ~

0; O O TABLE 7.2-1

                                     .~

INSERVICE TESTING PROGRAN CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID IMATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST

        ,  MD-10-15-A    Cate  20"      RER           M-361    (K-6)      R      F       Q                 (7.3) 2,23,28 MD-10-15-3                                          (K-8)

MD-10-15-C (H-6)

    -     'NO-10-15-D                                         (H-8)

MD-10-154-A Angle 24" RHR N-361 (C-4) B F Q (7.3) 2,23,28 MD-10-154-B Clobe (C-9) MD-10-20 Cate 24" M-361 (F-3) (7.3) 2,21,23,28 RER B F A AD-10-163-A Dia. 1" RRR M-361 (E-6) A F Q J (7.3) 1,2,24, AO-10-163-B (E-9) 27,28 MD-10-39-A Cate 18" RHR N-361 (C-3) A F Q J (7.3) 1,2,23, MD-10-39-s (C-11)

• 27,28 MD-10-26-A- Cate 12" RER N-361 (R-5) A F Q J (7.3) 1,2,23, MD-10-26-3 (R-8) 27,28 MD-10-16-A Clobe 3" REE N-361 (J-4) B F Q (7.3) 2,23,28 MD-10-16-5 (J-10)

MD-10-16-C (M-4) MD-10-16-D (H-10) SV-10-4221 Cate 3" RHR M-361 (E-1) B - ' J (7.3) 2,9,28 SV-10-4222 Cate 3" RHR N-361 (F-1) 5 - N (7.3) 2,9,28

O O O TABIX 7.2-1 INSERVICE TESTING PROGRAN CLASS 1. CLASS 2, AIS CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- OF FRE- DE RELIEF VALVs 1.D. TYPE S12s SYSTEu PsID 1 MATES coRY TEST

• QUENCT* EXCEPTIONS
• REQUEST SV-10-4223 Cate 3" RHR M-M1 (F-1) B -

N (7.3) 2,9,28 av-10-35-A Pres. 1- Rua n-361 (C-2) C S T (7.3) 2,28 RV-10-35-R Relief (C-12) Rv-10-44 Fras. 1" RER N-361 (A-5) C S T (7.3) 2,28 Reiser u da ~ RV-10-40 Pres. 1" REE N-361 (M-6) C S T (7.3) 2,28 Relief

   =up-10-174  Gste   18"    Rua           M-361    (E-13)     B     F        Q                   (7.3) 2,23,28 MD-10 -176 Gate   18"    RME           N-361    (E-13)     R     F        Q                   (7.3) 2,23,28 A0-10-175  Dia. 1"    RMR           N-361    (E-13)     B     F        Q                   (7.3) 2,28 RV-10-72-A Pres. 1"   .BME          M-361     (J-9)      C     S        T    -

(7.3) 2,28 RV-10-72-R Relief (K-9)

 - RV-10-72-C                                       (J-5)

RV-10-72-o (K-5)

m TABLE 7.2-1 INSERVICE TESTINC PROGRAM , CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) '

                                                                                                                 ,         P&ID                TYPE    TEST      NOTES VALVE     VALVE                                   COORDI-        CATE-  0F     FRE-       OR              RELIEF                  i VALVE I.D.      TYPE      SIZE             SYSTEM          P&ID   INATES         GORY  TEST

• QUENCY* EXCEPTIONS
• REQUEST i .

RV-10 .-A P es. , ,' 3 " Rilk M-361 (K-3) C S T , (7.3) 2,28

                                                       -RV   -B    . Relief'                                            (NA)

RV /-C (NA) , , RV -D (NA) RV -A Pres. 2" High Pres. M'361 (J-3) C S T (7.3) 2,28 RV -B Relief . Service Wtr. (NA) RV -C (NA) l'. RV -D (NA) k' ~ VV-10-48-A Check -20" RHR M-361 (K-3) C V Q (7.3) 2,28 VV-10-48-B (K-12)

!                                                       VV-10-48-C                                                          (J-3)

' VV-10-48-D' (J-11) i VV-10-19-A Check' 2" RilR M-361 (K-4) C - - (7.3) 2,17,28 j VV-10-19-B (J-10) VV-10-19-C (H-4)

VV-10-19-D (H-10) i VV-10-51 Check 2" RllR M-361 (F-8) C -

N (7.3) 2,10,28 VV-10-63 Check 2" RilR M-361 (A-8) C - N (7.3) 2,10,28 VV-10-64 Check 2" Ri!R M-361 (A-8) C - N (7.3) 2,10,28 VV-10-73 Check 2" . RiiR M-361 (F-8) C - N (7.3) 2,10,28 i 2

O ' O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, ~1 ASS 2, AND CLASS 3 VALVES (Cont'd) 4 S.. P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- 0F FR'd- OR RELIEF VALVE-I.D. TYPE SIZE SYSTEM P&Ir, INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST 1 r VV-10-183-A Check 2" RilR M-361 (A-7) C -

N (7.3) 2,10,28 VV-10-183-B (A-11) , i VV-10-184-A Check 2" RllR M-361 (A-7) C - N (7.3) 2,10,28 VV-10-184-B (A-11)

                           .VV-10-71-A         Cate   2"        RllR          M-361    (B-3)      B     -

N (7.3) 2,28 w VV-10-71-B (B-11)

                         "   HO-32-89-A        Globe 12"   liigh Pres.        M-261    (NA)       B      F        Q                 (7.3) 2,23,28

HO-32-89-B Service Wtr. (J-14 )

HO-32-89-C (NA) MO-32-89-D (NA) HO-14-12-A- Gate' 12" Core Spray M-362 (D-5) A F Q J. PI (7.3) 1,2,22, H0-14-12-B (B-5) 23,27,28 HO-14-26-A Clobe 10" Core Spr'ay M-362 (B-7) B F Q (7.3) 2,23,28 MO-14-26-B (C-7)

                           'A0-14-13-A         Check 12"   Core Spray         M-362   (D-3)       A/C   M         C    (5), J, PI   (7.3) 1,2,24,
                            .AO-14-13-B                                               (B-3)                                         27,28 A0-14-15-A        Cate   1"   Core Spray         M-362   (D-3)       A      F        Q    J            (7.3) 1,2,24,

, A0-14-15-B (B-3) 27,28 4 4

i C-)h - ~ TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES , VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM- P&ID INATES CORY TEST

• QUENCYA EXCEPTIONS
• REQUEST

                                                                                                                                                                                    \

MO-14-11-A Cate- 12" Core Spray M-362 (D-7) B F Q (7.3) 2,23,28 HO-14-11-B (B-7) MO-14-5-A Globe 3" Core Spray M-362 (E-7) B F Q (7.3) 2,23,28 - MO-14-5-B - (E-9) - HO-14-5-C (E-8) MO-14-5-D (E-11) Y

y. VV-14-66-A Check 3" Core Spray H-362 (E-7) C - -

(7.3) 2,17,28 VV-14-66-B (E-9) VV-14-66-C (E-9) VV-14-66-D (E-10) MO-14-70 Cate 4" Torus Water M-362 ( 11 - 1 0 ) A F Q J (7.3) 1,2,23, MO-14-71' C.U. ( 11 - 1 0 ) 27,28

SV-14-4224 Globe 1" Core Spray H-362 (B-6) B -

N (7.3) 2,9,28 SV-14-4225 Globe 1" Core Spray M-362 (C-6) B - N (7.3) 2,9,28 VV-14-10-A Test- 12" Core Spray M-362 (E-6) C V Q (7.3) 2,28 VV-14-10-B able (E-11) i VV-14-10-C Check (E-8) VV-14-10-D (E-9) I l l

O O O TABLE 7.2-1 INSERVICE TESTINC PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) l P&lD TYPE TEST NOTES VALVE VALVE C00RDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM _P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST VV-14-22-A Check 2" Core Spray M-362 (D-7) C -

N (7.3) 2,10,28 VV-14-22-B (D-10) VV-14-22-C (D-10) VV-14-22-D (D-11) VV-14-23-A Check 2" Core Spray M-362 (D-7) C - N (7.3) 2,10,28 3 VV-14-23-B (D-10) VV-14-23-C (D-10) y w VV-14-23-D (D-11) RV-14-20-A Pres. 2" Core Spray M-362 (D-7) C S T (7.3) 2,28 RV-14-20-B ' Relief (D-11) VV-19-MK237M3 Check 12" Fuel Pool Cool. M-363 (A-11) C V - RHR Cross (7.3) 2,14,28 4 VV-19-MK237M3 Check 12" Fuel Pool Cool. M-363 (A-11) C V - RllR Cross (7.3) 2,14,28 VRV-19-2204-C Vacuum - Fuel Pool Cool. M-363 (B-11) C M Q (7.3) 2,28 VRV-19-2204-D Relief (B-11) MO-23-15 Cate 10" IIPCI M-365 (D-4) A F Q J, PI (7.3) 1,2,22,23, 27,28 i MO-23-16 Cate 10" llPCI M-365 (D-6) A F Q J PI (7.3) 1,2,22,23, 27,28 t i e

O O O

                            ,                                             TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd)

P&ID TYPE TEST NOTES VALVE VALVE C00RDI ' CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST AO-23-18 Check 14" HPCI M-365 (11-5) A/C M C (5), J, PI (7.3) 1,2,27,28 VV-23-65 Check. 20" IIPCI M-365 (J-5) A/C V Q J (7.3) 1,2,27,28 VV-23-56 Check 2" HPCI M-365 (K-5) A/C V Q J (7.3) 1,2,27,28 MO-23-58 Cate 16" IIPCI M-365 (M-7) B F Q (7.3) 2,23,28 w MO-23-19 Gate 14" IIPCI H-365 (11-5) A F Q J, PI (7.3) 1,2,22,23, 27,28 i

h ( MO-23-25 Globe 4" IIPCI M-365 (J-8) B F Q (7.3) 2,23,28 MO-23-31 Cate 4"  !!PCI M-365 0I-8) B F Q (7.3) 2,23,28 ! HO-23-4244A Cate 3" IIPCI M-365 (J-2) A F Q J (7.3) 1,2,23, 27,28 Ho-23-17 Cate 16" IIPCI M-365 (E-11) B F Q (7.3) 2,23,28 MO-23-57 Cate 16" llPCI H-365 (E-11) A F Q J (7.3) 1,2,23, 27,28 MO-23-70 Cate 14" llPCI M-365 (11-6) B F Q (7.3) 2,23,28 MO-23-14 Cate 10" IIPCI M-365 (F-13) B F Q (7.3) 2,23,28 i I

i O O O i TABLE 7.2-1

   .                                                                                                                INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd)

~ P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST MO-23-21 Clobe 10" IIPCI M-365 (E-6) B F Q (7.3) 2,23,28

                                                 -MO-23-24              Cate   4"                IIPCI             M-365         (D-8)          B  F       Q                    (7.3) 2,23,28 A0-23-42        Dia. 1"               IIPCI              M-365         (K-14)         B  F       Q                    (7.3) 2,24,28 1

i j .A0-23-43 Dia. 1" IIPCI M-365 (K-15) B F Q (7.3) 2,24,28 1 Y A0-23-53 ' Dia. 1" HPCI M-365 ( 11- 1 3 ) B F Q (7.3) 2,24,28 d , VRV-23-140-A Check 3" IIPCI M-365 (J-2) C V Q (7.3) 2,8,28 ' ! VRV-23-140-B l VRV-23-140-C VRV-23-140-D VV-23-32 Check 16" HPCI M-365 (E-11) C V Q (7.3) 2,28 VV-23-61 Check 16" HPCI M-365 (M-6) C V A (/.3) 2,7,28 VV-23-22 Check 10" llPCI M-365 (D-6) C V Q (l.3) 2,28 VV-23-62 Check 4" IIPCI M-365 (L-7) C - - (7.3) 2,17,28 l A0-23-4247 Dia. 2" IIPCI M-366 (J-10) A F Q J (7.3) 1,2,24, t 27,28

A0-23-4248 Dia. 2" IIPCI M-366 (J-10) A F Q J (7.3) 1,2,24, 27,28 I

O O O 4 TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST RV-23-34 Pres. 1.5" IIPCI M-366 (C-8) C S T (7.3) 2,28 Relief RV-23-66~ Pres. 1" IIPCI M-366 (K-11) C S T (7.3) 2,28 Relief i

VV-23-130 Check 2" IIPCI M-366 (K-8) C F Q (7.3) 2,28 VV-23-131 Check 3" IIPCI M-366 (K-8) C F Q (7.3) 2,28 A0-23-39 Dia. 1" IIPCI M-366 (L-10) B F Q (7.3) 2,24,28

                                      - A0-23-40                                                    (M-10)
                                        ' A0-23-4807        Cate      1"   IIPCI            M-365   (D-6)         A          F        Q             J        (7.3) 1,2,24, 27,28 VRV-23-4998-A Check    2"    IIPCI            M-366   (D-11)        C          V        Q                      (7.3) 2,28 VRV-23-4998-8                                          (E-11)

PSD-23-7 Rupt. 16" IIPCI M-366 (D-10) D N N Not a testable - Disc design. PSD-23-6 Rupt. 16" IIPCI M-366 (b-10) D N N Not a testable - Disc design. 110-23-4513 Cate 10" IIPCI M-366 (D-12) B F Q (7.3) 2,28 , (*) 4 a

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1 CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST A0-9-2520 Butter- 24" Cont.Atm. Cont. M-367 (E-6) A L B J, Passive (7.3) 1,2,27,28 fly A0-9-2505 Butter- 18" Cont.Atm. Cont. M-367 (E-5) A L B J Passive (7.3) 1,2,27,28 fly.

A0-9-2519 Butter- 6" Cont.Atm. Cont. M-367 (F-6) A L B J, Passive (7.3) 1,2,27,28 y fly e [$ A0-9-2506 Butter- 18" Cont.Atm. Cont. M-367 (C-7) A L B J, Passive (7.3) 1,2,27,28 fly . A0-9-2507 Butter- 18" Cont.Atm. Cont. M-367 (G-7) A L B J, Passive (7.3) 1,2,27,28 fly i A0-9-2511 Butter- 18" Cont.Atm. Cont. M-367 (E-7) A L B J, Passive (7.3) 1,2,27,28 fly A0-9-2512 Butter- 18" Cont.Atm. Cont. M-367 (E-8) A L B J, Passive (7.3) 1,2,27,28 fly A0-9-2502-A Butter- 20" Cont.Atm. Cont. M-367 (D-4) A F Q J (7.3) 1,2,27,28 fly A0-9-2502-B (D-8) A0-9-2521-A Butter- 18" Cont.Atm. Cont. M-367 (E-5) A L B J, Passive (7.3) 1,2,27,28 fly A0-9-2521-B , (E-5) h

                                                                                                    ,O\                                                                   fi
            .                                                                                       \d                                                                    \m /

TABLE 7.2-1 , INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCi* EXCEPTIONS
• REQUEST A0-9-?.523 Dia. 1" Cont.Atm. Cont M-367 (F-6) A F Q J (7.3) 1,2,24,27 28 A0-9-2509 Dia. 1" Cont.Atm. Cont. H-367 (G-7) A F Q J (7.3) 1,2,24,27 28 A0-9-2510 Dia. 1" Cont.Atm. Cont. M ,367 (11-7) A F Q J (7.3) 1,2,24,27 28 74 a

c) A0-9-2514 Dia. 1" Cont.Atm. Cont. H-367 (F-8) A F Q J (7.3) 1,2,24,27 28 A0-9-2513 Dia. 1" Cont.Atm. Cont. H-367 (F-7) A F Q J (7.3) 1,2,24,27 28 VV-9-(. ) Check 1" Cont.Atm. Cont.' M-367 (F-6) A/C V Q J (7.3) 1,2,27,28 l VV-9-( ) Check 1" Cont.Atm. Cont. M-367 (F-6) A/C V Q J (7.3) 1,2,27,28 VV-9-26-A Check 20" Cont.Atm. Cont. M-367 (C-4) A/C H Q J (7.3) 1,2,27,28 VV-9-26-B (C-8) f

^ d U b v , TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 V/LVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST A0-9-2504-A Check -" Cont.Atm. Cont. M-367 (D-7) C H Q (7.3) 2,28 A0-9-2504-B A0-9-2504-C A0-9-2504-D-A0-9-2504-E A0-9-2504-F A0-9-2504-G A0-9-2504-Il y 'A0-9-2504-J d

  " .A0-9-2504-K A0-9-2504-L A0-9-2504-M

{ 'SV-9-2671-A Cate 0.5" Cont.Atm. Cont. M-367 (D-6) A F Q J (7.3) 1,2,25,27, SV-9-2671-B (D-5) 28 SV-9-2671-C (D-5) ., SV a-2671-D ~ (D-5) I SV-9-2671-E (D-5) SV-9-2671-F (D-5) SV-9-2671-G (D-5) SV-9-2978-A Cate 0.5" Cont.Atm. Cont. M-367 (D-5) A F Q J (7.3) 1,2,25,27, SV-9-2978-B (D-5) 28

. SV-9-2978-C                                                                                        (D-5) 2 SV-9-2978-D                                                                                        (D-5)

SV-9-2978-E (D-5) SV-9-2978-F (D-5)

SV-9-2978-C (D-5)

SV-9-2980 Cate 0.5" Cont.Atm. Cont. M-367 (C-6) A F Q J (7.3) 1,2,25,27, 28

O O O TABLE 7.2-1 INSERVICE TESTING PROGRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- OF FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST VV-9-( ) Check 1" Cont.Atm. Cont. M-367 (D-6) A/C V A J (7.3) 1,2,19, 27,28 A0-9-2968 Dia. 1" Cont.Atm. Cont. M-367 (D-7) A F Q J (7.3) 1,2,24, 27,28 A0-20-82 Dia. 2" Rad. Waste M-368 (A-3) A F Q J (7.3) 1,2,24, 27,28

 }[ A0-20-83              Dia. 2"   Rad. Waste         M-368      (A-4)     A    F        Q         J          (7.3) 1,2,24, p                                                                                                               27,28 I

A0-20-94 Dia. 2" Rad. Waste M-368 .(E-3) A F Q J (7.3) 1,2,24, 27,28 AO-20-95 Dia. 2" Rad. Waste M-368 (E-4) A F Q J (7.3) 1,2,24, 27,28 SV-52-4951-A Cate 1" Cont.Atm.Dil. M-372 (C-6) A F Q J (7.3) 1,2,27,28 SV-52-4951-B (C-2) SV-52-4949-A Cate 1" Cont.Atm.Dil. M-372 (F-5) A F Q J (7.3) 1,2,27,28 SV-52-4949-B (F-4) SV-52-4960-A Cate 0.5" Cont.Atm.Dil. M-372 (B-6) A F Q J (7.3) 1,2,27,28 SV-52-4960-3 (C-5) SV-52-4960-C (D-3) SV-52-4960-D (C-2) SV-52-4961-A Cate 0.5" Cont.Atm.Dil. M-372 (B-6) A F Q J (7.3) 1,2,27,28 SV-52-4961-B (H-5) SV-52-4961-C (D-3) SV-52-4961-D (C-2)

O O O TABLE 7.2 INSERVICE TESTING PROCRAM CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd) i P&ID TYPE TEST NOTES VALVE VALVE COORDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES CORY TEST

• QUENCY* EXCEPTIONS
• REQUEST SV-52-4966-A' Cate 0.5" Cont.Atm.Dil. M-372 (B-5) A F Q J (7.3) 1,2,27,28 SV-52-4966-B (B-5)

SV-52-4966-C (A-5) SV-52-4966-D (A-5) VV-52-( ) Check 1" Cont.Atm.Dil. M-372 (C-6) A/C V Q J (7.3) 1,2,27,28

VV-52-(- ) (C-2)

VV-52-( ) (F-5)

                       'yn         VV-52-(-    )                                                       (F-4)

SV-52-8101 Cate 1" Cont.Atm.Dil. M-372 (A-5) A F Q J (7.3) 1,2,25,27, , 28 A0-0-0475-1 Butter- - Standby Cas M-391 (B-5) B F Q Common (7.3) 2,20,28 A0-0-0475-2 fly Treatment (B-4) A0-0-0476-1 Butter- - Standby Cas M-391 (B-5) B F Q Common (7.3) 2,20,28 A0-0-0476-2 fly Treatment (B-4) A0-0-0469-1 Butter- - Standby Cas M-391 (C-6) B F Q Common (7.3) 2,20,28 l A0-0-0469-2 fly Treatment (B-6) A0-0-0470-1 Butter- - Standby Cas M-391 (A-6) B F Q Common (7.3) 2,20,28 A0-0-0470-2 fly Treatment (A-6) A0-0-0452 Bistter- - Standby Cas M-391 (F-8) B F Q Common (7.3) 2,28 ' A0-0-0453 fly Treatment (F-8) A0-0-0457 (E-8) A0-0-0458 (E-8) A0-0-0459 (D-8)

A0-0-0460 (D-8)

! A0-0-0461 (F-5)

  - _ _ - _ _ _         _ - - _ . -- -_ _       __ _ __-.         - - - ..                  . - _ - -      . . .    . . - -  ~        _ _ ,    .-      -                  ._.
                                 )                                                                                                                    G TABLE 7.2-1 INSERVICE TESTING PROGRAM
!                                                                          CLASS 1, CLASS 2, AND CLASS 3 VALVES (Cont'd)

P&ID TYPE TEST NOTES VALVE VALVE C00RDI- CATE- 0F FRE- OR RELIEF VALVE I.D. TYPE SIZE SYSTEM P&ID INATES GORY TEST

• QUENCY* EXCEPTIONS
• REQUEST

) A0-0-0462 Butter- - Standby Cas M-391 (F-5) B F Q Common (7.3) 2,28 A0-0-0463 fly Treatment (E-4) A0-0-0464 (E-4) A0-0-0466 (D-5) A0-0-0467 (D-5) K2Y: A = Once per operating cycle (or during re' fueling outage) yB = Once every 2 years , , 7, Q = Quarterly C = cold shutdown exceeding 48 hr. , f T = Per ASME Table IWV-3510-1 ! 2 = Once every 2 operating cycles N = Not applicable or none P = Partial stroke exercise F = Full cycle exercise, includes stroke timing for power-operated valves M = Hechanical Exercise of check L = Leak rate test E = Explosive Actuator test V = Functional check with flow S = Set point check J = Leak rate tested in accordance with plant Technical Specifications which conforms as far as practical to the criteria of Appendix J to 10CFR50 j PI = Leak rate tested in accordance with Section XI, or in accordance with the requirements of the NRC generic letter on Pressure Isolation Valves dated February 23, 1980 Note on valve identification numbers: Table 7.2-1 can be used for Unic 2 or Unit 3. The valve identification numbers are the same for both units, with the exception of valves with a four-digit identification number. Examples are A0-9-2502-A, l SV-52-8101, and HO-44-2201-A, which are Unit 2 valves. For the Unit 3 valves with four digits, increase the first digit by I one, as compared to the corresponding Unit 2 valves in Table 7.2-1. The Unit 3 valves would be A0-9-3502-A, SV-52-9101, and MO-44-3201-A, respectively, for the above examples. Valves shared between both units are identified as common valves in the i notes, for the applicable valves. t __ _____-__-____}}