Text

Amend 1 to 780803 Inservice Insp Program
	ML19270G442
Person / Time
Site:	Hatch
Issue date:	06/06/1979
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML19270G441	List: ML19270G440; ML19270G442;
References
	PROC-790606, NUDOCS 7906080269
	Download: ML19270G442 (62)
	v • d • e

{{#Wiki_filter:d,, -y EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 RESPONSE TO THE PROVISIONS OF 10 CFR 50.55a(g) " INSERVICE INSPECTION PROGRAM" 2;37 05l 7006080 a69

a, TABLE OF CONTENTS 1.0 Introduc tion................ 1 -1 2.0 Inservice Inspection for Code Class 1 Components........... 2-1 3.0 Inservice Inspection for Code Class 2 Components........... 3-1 4.0 Inservice Inspection for Code Class 3 Components........... 4-1 5.0 Inservice Testing of Pumps......... 5-1 6.0 Inservice Testing of Valves......... 6-1 2J37 052

1.0 INTRODUCTION

1.1 General This document describes the new Inservice Inspection Program for Edwin I. Hatch Nuclear Plant, Unit No.1. The original ISI program for Hatch-l was prepared in accordance with the ASME Boiler and Pressure Vessel Coie, 1971 Edition, including the Summer 1972 Addenda for Class 1 components. Class 2 components were limited to the Main Steam and Turbine Steam Bypass Systems. Class 2 components were scheduled for examination in accordance with the Winter 1972 Addenda of Section XI. The new inservice inspection plan is an upgrading of the program to meet the examination requirements of the 1974 Edition of Section XI, including Addenda through the Summer,1975. 1.2 Effective Date The new ISI plan shall go into effect at the start of the second 40-month.. period of plant commercial operation. The effective date is April 30, 1979. 1.3 Scope This document is a description of the ISI program for Unit 1 of Plant Hatch. The programs for Class 1, 2, and 3 component examinations and for pump and valve surveillance testing are included. 1.4 Component Upgrading All clant components have been reviewed to determine the appropriate classifi-cation for inservice inspectior.. Regulatory Guide 1.26 was used for guidance in determining component classifications. It must be noted that the classification of components as ASME Class 1, 2, or 3 equivalent for inservice inspection does not imply that the com-ponents were designed in accordance with ASME requirements. The component design codes remain as stated in the FSAR. 1.5 Subsequent ISI Plan Revisions In accordance with the existing regulations of 10CFR50.55a, the inservice examination program for Class 1, 2, and 3 components will be reviewed near the end of each 40-month interval. At that time the plan will be modified as required to bring it into compliance with the latest NRC-approved version of Section XI. The inservice testing program for pumps and valves will be similarly reviewed and modified every 20 months. l.6 Res ponsibil i ty Georgia Power Company bears the overall responsibility for the performance of the inservice examinations. Certain non-destructive examinations will be performed by a qualified examination agency. The results of such examina-tions will be reported to Georgia Power Company for final evaluation and dis posi tio n. 777 w 7 053 1-1

1..,7, _ R ec,o rd,s Reco rde, and dor.umentation of all infonnation and inspection results, which provide thr basie, for evaluation and which facilitate comparison with re- ,ults from previous and subsequent inspections, will be maintained and available for the active life of the plant in accordance with Section XI, IWA-6000. 1.8 Methods of Examination The method of examination planned for each area is delineated in subsequent sections. Personnel performing NDT examinations will be trained in accord-ance with the American Society for Nondestructive Testing (ASNT) " Recommended Practice SNT-TC-1 A, Supplements and Appendices", as applicable for technique and method used. 1.8.1, Ul trasonic It is anticipated that most volumetric examinations will be performed ultra-sonically. Examinations will be conducted in accordance with the require-ments of ASME Section XI and Section V as appropriate. 1.8.2 Radiographic Radiographic techniques will be used to supplement UT as required. 1.8.3 Liquid Penetrant Dye penetrant examinations will be performed whenever a surface examination is required on non-magnetic piping. 1.8.4 Maanetic Particle Magnetic particle tests will usually be used when surface examination of carbon steel components is required. 1.8.5 Visual A visual (VT) examination is employed to provide a report of the general condi-tion of the part, component, or evidence of leaking. 1.9 Repair Procedures Repairs to the pressure retaining boundary of ASME Class 1, 2, or 3 (equiva-lent) components will be performed in accordance with IWA-4000 by utilizing Georgia Power Company approved procedures which gei.e.~ ally comply with the code applicable to the construction of the component. 2337 054 1-2

2.0 INSERVICE INSPECTION FOR CODE CLASS 1 COMPONENTS Table 1 provides a tabulation of the Class 1 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer 1975. These components will be inspected in accordance with the requirements of Subsection IWB to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examina-tion. Where release from the inspection requirements of Subsection IWB is requested, information is provided which identifies the applicable Code requirements, justification for the release requested, and the inspection method to be used as an alternative. Table IWB-2600 items not applicable to the Edwin I. Hatch Nuclear Plant-Unit 1 have also been listed and identified in the interest of completeness. Items applicable to pressurized water reactors only, such as steam generators and pressurizers, have beer. omitted entirely. Some components included in this program were not built to the ASME Section III Code because it was not in effect at ;.ne time the component was purchased. However, these components will be inspected in accordance with the require-ments of Subsection IWB to the extent practicable. The repair procedures of IWB-4000 will be applied to those components constructed to Section III of the ASME Code. For those components not constructed to Section III of the ASME Code, the rules of IWA-4000 will be applied. Hydrostatic testing will be conducted in a manner that will satisfy the re-quirements of IWA-5000 and IWB-5000. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of piping (e.g., boundary is check valve), the sections will be tested together at the lower of the specified test pressures. No point in the piping shall be permitted to experience a pressure greater 1 than the specified test pressure. Components that are exempted from volumetric and surface examination by IWB-1220 will be hydrostatically tested per the requirements of IWA-5000 and IWB-5000. 2.1 Requests for Relief from ASME Section XI Requirements 2.1.1 Reactor Recirculation Pumos 2.1.1.1 Requirement From Which Relief Requested Table IWB-2500, Category B-L-2, and Table IWB-2600, Item B5.7, require visual examination of the internal pressure boundary surfaces of one pump in each group of pumps of similar function to be performed once per inspection inter-

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css / 053 2.1.1.2 Justification This requirement, in absence of other required maintenance, would necessitate dismentling a recirculation pump soleiy to perform a visual inspection '.T Ainendment 14/79 24

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 squipment. We estimate that the dismantling and reassembly of one pump would consume more than 1,000 manhours and would result in a cumulative dose of between 10 and 50 man-rem. The net result of this major effort would be a visual inspection const..ning about 8 manhours. The questionable benefit to be obtained from such an in-spection when measured against the cott in man-rem appears to be in conflict ,;i.h the concept of "As Low as Reasonably Achievable". In view of the cost in dollars, potential hazards, and man-rem and in view of the minimal benefits to be obtained, we conclude that this Code requirement is impractical. 2.1.1.3 Testing in Lieu of Sectico XI Requirements The internal surfaces of the recirculation pump casings will be visually in-spected whenever these surfaces are accessible as a result of disassembly for other maintenance purposes or at the end of the ten year interval when dis-assembly is undertaken for examination of performance of pump casing. 2.1.2 Hydraulic Shock Suppressors for Class 1 Piping, Pumps, and Valves 2.1.2.1 Requirement From Which Relief Requested Table IWB-2500, Category B-K-2 requires visual examination of all support com-ponents and verification of support settings of snubbers and shock absorbers once per inspection interval. Relief is requested Trem verification of snubber settings. 2.1.2.2 Justification The hydraulic shock suppressors on Class 1 systems are currently subjected to an ongoing inspection and testing program detailed in the plant Technical Specifications. This program is designed to demonstrate continued operational readiness an't structural integrity of the shock suppressors and exceeds the re-qairements of Table IWB-2500. I 2.1.2.3 Testing in Lieu of Section XI Requirements Hydraulic shock suppressors will be inspected and tested in accordance with Technical Specification requirements. 2.1.3 ASME Class 1 (Equivalent) Valves Exceeding 4-Inches Nominal Pipe Size 2.1.3.1 Requirement From Which Relief Requested Table IWB-2500, Category B-M-2, and Table IWB-2600, Item B6.7 require visual examination of tne internal pressure boundary surfaces of one valve in each group of valves of the same design, manufacturing method, manufacturer, and function to be performed once per inspection interval. 227 056 Amendment 1 4/79 2-2 i

2.1.3.2 Justification Disassembly of these valves solely for visual inspection, in absenr.e of other required maintenance, represents an unnecessary exposure to radiation and con-tamination and an excessive expense. The opening, visual inspection, and closing of these valves would require an expenditure of approximately 2 to 3 man-rempervalvf31 High contamination levels produce airborne activities of 6 to 10 MPC of I which requires the use of in-line or constant-flow respir-I atory equipment. Dose rates from the disassembled valves are typically 0.5 R/hr gamma and greater than 200 R/hr beta. Valves on the recirculation loop suction piping would require off-loading the fuel elements and draining the reactor prior to di:> assembly. Work on recircu-lation pump discharge valves and RHR injection valves would require installation Il of plugs in the jet pump risers. Preparatory work of this scope is considered impractical for the sole purpose of conducting a visual examination. Contamina-tion levels in the valves associated with the recirculation loops are particu-larly high due to the physical location of these valves at the bottom of the system. During routine maintenance, the valve body internal surfaces are visually examined. Many of these valves, particularly the containment isolation valves, are disassembled for maintenance of leak-tightness. Disassembly of other Class 1 valves solely for internal inspection is counter to the "ALARA" guide-lines to keep the occupational dose rates as low as reasonably achievable. 1 In view of the cost in dollars and man-rem, and in view of the minimal benefits obtained, we conclude that this code requirement does not provide sufficient benefits to justify such expenditures. 2.1.3.3 Alternate to Section XI Requirement Class 1 valves exceeding 4 inches nominal pipe size are subjected to visual inspection of the internal surfaces of the valve body when disassembled for maintenance. The coverage provided by inspections during routine maintenance coupled with periodic leak tests and hydrostatic tests will provide adequate assurance of the structural integrity of the Class 1 valve bodies, while keeping exposure to radiation and contamination as low as reasonably achievable. 2.1.4 Flued Head Penetrations 2.1.4.1 Requirements for Which Relief Requested Table IW8-2500, Category B-J and B-K-1 requires the examination of circumfer-ential butt welds and integrally welded pipe supports, that are located within flued head containment penetration assemblies. These welds and their penetra-tion assembly number are listed below. Penetration No. Weld Identification No. X-9A 821-FW-18A-7A X-98 821-FW-188-6A l 2-3

Penetration No. Weld Identification No. X-10 E51-RCIC-4-0UT-20A X-11 E41-HPCI-10-0VT-15A X-12 E11-RHR-20-8-Discharge-13A X-13A E11-RHR-24-A-Return-3A X-138 E11-RHR-24-B-Return-3B 1 X-14 G31-RWCU-6-0VT-158 X-14 G31-RWCU-6-00T-15C X-16A E21-CORE SPRAY-10-A-3A X-16B E21-CORE SPRAY-10-B-4A X-17 E11-RHR-4-HS-6A 2.1.4.2 Justification These welds are inaccessible for examination due to the design of the flued head. All of the twelve circumferential butt welds, except for two located in the RWCU penetration, are carbon steel and not subject to intergranular stress corrosion cracking (IGSCC). Two stainless steel welds that are located in the RWCU penetration were made to replace a Type 304 SS pipe that had undergone IGSCC. They are a flued head with a Type 308L overlay (> 5% ferrite) on the inside surface to a Type 304L solution annealed pipe (<.035% carbon), and a Type 304L pipe-to-pipe weld. These welds were made in accordance with the guidelines of NUREG-0313 to minimize susceptibility to IGSCC. 2.1.4.3 Testing in Lieu of Section XI Reouirements A UT baseline was run for each new weld while the weld was accessible during the repair to ensure a high quality weld. In accordance with IWB-5221 a system leakage test is to be performed prior to startup following each reactor refueling outage. This is the same type test that detected the crack in the original pipe. 2.1.5 Control Rod Drive Housings 2.1.5.1 Requirements for Which Relief Reouested Table IWB-2500, Category B-0 requires examination of the pressure-retaining welds in the peripheral control rod drive housings. Each housing has one upper weld located near the reactor vessel bottom head and one lower weld lo-cated at the housing flange. 2.1.5.2 Justification 1 8ecause of the proximity of the upper weld to the vessel, the dose rate is too high to permit examination of this weld. Dose rates are typically 20 to 30 R/hr and an examination would expend 10-15 man-rem per housi.g. The lower welds are inaccessible for examination because of the location and design of the housings. Physical accessibility by an inspector is extremely limited by the close proximity of the housings to each other and by the sup-2-3a Amendment 1 4/79

port arrangement. Also, the insert and withdraw lines to the CRD are connec-ted at the top of ti. housing flange and prevent access to much of the weld. The combination of these factors prevents these welds from being examined. 2.1.5.3 Testing in Lieu of Section XI Requirements y These welds are located within the hydrostatic test boundary of the Nuclear Steam Supply System. Therefore, they will be tested per IWB-5000. There are no other alternate means of testing available for these welds. E U 059 Amendment 1 4/79 2-3b

TABLE 1 5I PROGRAM ASME CODL CLASS 1 COMP 0NENTS Table Table IWB-2500 IWB-2600 Examina tion System or Component Method of Code Relief Item No. Ca tego ry__ Description Area to be Examined Examination Recuested Bl.1 B-A Reactor Vessel Circumferential and vertical Volumetric No welds in the core belt area Bl.2 B-B Reactor Vessel Circumferential and vertical Volumetric No welds in other than core belt area and meridional welds in bottom head torus, bottom head dome, and close head B1.3 B-C Reactor Vessel Vessel-to-flange and head-to-Volumetric No flange circumferential welds Bl.4 B-D Reactor Vessel Primary nozzle-to-vessel welds Volumetric No and nozzle inside radius na I, section B1.5 B-E Reactor Vessel Vessel penetrations: control Visual (IWA-No rod drives instrumentation 5000) Bl.6 B-F Reactor Vessel Nozzle-to-safe-end welds Covered by IWB-No 2600 Itsn B4.1 Bl.7 B-G-1 Reactor Vessel Closure studs, in place See Note 1 No Closure Head Bl.8 B-G-1 Reactor Vessel Closure studs and nuts re-See Note 1 No Closure llead moved <y =r ~y 8 Bl.9 B-G-1 Reactor Vessel Ligaments.between threaded Volumetric No c:? stud holes 9, c:3 Bl.10 B-L-1 Reactor Vessel Closure washers, bushings Visual No Closure llead m B1.11 B-G-2 Reactor Vessel Bolting less than 2 inches Visual No

TABLE 1 (Cont'd) Table Table IWB-2500 IW8-2600 Examination System or Component Method of Code Relief Item No. Category Description Area to be Examined Examination Requested B1.12 B-H Reactor Vessel Bottom head torus to support Volumetric No skirt Bl.13 B-I-l Reactor Vessel Not applicable See Note 2 No Closure Head Bl.14 B-I-1 Reactor Vessel Vessel cladding Visual. See No Note 3 Bl.15 B-N-1 Reactor Vessel Vessel interior Visual No Bl.16 B-N-2 Reactor Vessel Integrally welded core Visual No support structures and in-terior attachments n3 E Bl.17 B-N-3 Reactor Vessel Not applicable (applies to Not applicable No PVRs only) 81.18 B-0 Reactor Vessel Control rod drive housings Volumetric. See Yes l1 Note 10 81.19 B-P Reactor Vessel Exempted components Visual (IWA-5000) No 84.1 B-F Piping Nozzle-to-safe-end welds Volumetric and No surface rx)

."J 84.2 B-G-1 Piping Pressure boundary bolting Not applicable.

No SL LN greater than and equal to 2 See Note 4. N' NJ inches diameter (in place) m ] [f3 C B4.3 B-G-1 Piping Pressure boundary bolting Not applicable. No ii greater than and equal to 2 See Note 4. inches diameter (removed) 42 B4.4 B-G-1 Piping Pressure boundary bolting Not applicable No C$ greater than and equal to 2 inches

TABLE 1 (Cont'd) Table Tabl e IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Item No. Ca tego ry__ Description Area to be Examined Examination Eecuested B4.5 B-J Piping Circumferential and longitud-Volumetric Yes. inal welds See Note 7. B4.6 B-J Piping Branch connection welds Volumetric No greater than 6 inches diameter 84.7 B-J Piping Branch connection welds six Surface No inches diameter and smaller B4.8 B-J Piping Socket welds Not applicable. No See Note 5. B4.9 B-K-1 Piping Integrally welded supports Volumetric No ga B4.10 B-K-2 Piping Support components Visual Yes os See Note 9. B4.11 B-P Piping Exempted components Visual (IWA-No 5000) B4.12 0-G-2 Piping Pressure-retaining bolting. Visual No Bolting less than 2 inches diameter P'J B5.1 B-G-1 Pumps Pressure-retaining bolts and Volumetric No 'J studs greater than and equal m ((j to 2 inches (in place) us B5.2 B-G-1 Pumps Pressure-retaining bolts and Volumetric & No c:3 studs greater than and equal Surface cr o (( to 2 inches (when removed) rs] B5.3 B-G-1 Pumps Pressure-retaining bolting Visual No and studs greater than and equal to 2 inches

.LE 1 (Cont'd) Table Tabl e IWB-2500 IUB-2600 Examination System or Component Method of Code Relief Item No. Ca tego ry__ Description Area to be Examined Examination Requested B5.4 B-K-1 Pumps Integrally welded supports Volumetric No B5.5 B-K-2 Pumps Support components Visual Yes See Note 9. B5.6 B-L-1 Pumps Casing welds Not applicable. No See Note 6. 85.7 B-L-2 Pumps Casings Visual Yes. See Note 8. 85.8 B-P Pumps Exempted components Visual (IWA-No 5000) B5.9 B-G-2 Pumps Pressure-retaining bolting Visual No n, 'a less than 2 inches 86.1 B-G-1 Valves Pr essure-retaining bolting Volumetric No greater than and equal to 2 inches diameter (in place) 86.2 B-G-1 Valves Pressure-retaining bolting Volumetric No greater than and equal to 2 inches diameter (removed) B6.3 B-G-1 Valves Pressure-retaining bolting Visual No greater than and equal to 2 inches diameter v,r, rs? [!, j B6.4 B-K-1 Valves Integrally welded supports Not Applicable. No See Note 11. ,, sy O c;) 86.5 B-K-2 Valves Support components Visual Yes. o' c See Note 9. Lsa B6.6 B-M-1 Valves Casing welds Not Applicable. No See Note 6.

TABLE 1 (Cont'd) Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Item No. Ca tego ry_ Description Area to be Examined Examination Requested B6.7 B-M-2 Valves Casings Visual Yes. See Note 12. 86.8 B-P Valves Exempted compinents Visual (IWA-No 5000) B6.9 B-G-2 Valves Pressure-retaining bolting Visual No less than 2 inches ro ra (,a l./ 4 N us n UI k a e' es*

TABLE 1 N0TES 1. Normally during each refueling outage, the reactor vessel closure studs are left in place; therefore, only a voltmetric examination will be performed (Table IWB-2600 Item B1.7). If the studs are removed, both a surface and volumetric examination will be performed (Table IWB-2600 Item Bl.8). 2. Closure head does not have cladding. Twenty locations on the closure head will be measured to determine the corrosion rate. 3. Six 6 x 6-inch evenly distributed accessible sections of the vessel shell cladding are to be visually examined. 4. At present, piping system pressure boundary bolting greater than or equal to two inches does not exist. If such bolting is introduced, examinations will be performed in accordance with applicable Code require-ments. 5. At present, there are no socFet welds in ASME Code-affected Class 1 piping systems. If such are introduced, applicable ASME Code examinations will be performed. m 6. At present, there are no through-wall casing welds in ASME Class 1 Code-affected pumps or valves. If such d3 are introduced, applicable ASME Code examinations will be performed. 7. The arrangements and details of the piping systems and components are such that some examinations (as re-quired by IWB-2600) are limited due to geometric configuration or accessibility. Generally, these limita-tions exist at pipe-to-fitting welds, where examination can be fully performed only from the pipe side, the fitting geometry limiting or even precluding examination from the opposite side. Welds having such restrictions will be examined to the extent practical. However, all welds examined during the pre-service examination were fully code inspectable. Since hangers or other obstructions may have been added after the pre-service exam, examination limitations may be encountered during the performance of the ISI weld exami-I nation. Relief will be requested at the time inaccessibility is discovered as provided by 10CFR50.55a(g). g? 8. See Request for Relief, paragraph 2.1.1. 2" 9. See Request for Relief, paragraph 2.1.2. 2 nm rx] ELEL 10. See Request for Relief, paragraph 2.1.5. l1 c,y 8m u EL 11. There are no integrally welded valve supports. sa s $2 12. See Request for Relief, paragraph 2.1.3. c:]

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3. 0 INSERVICE INSPECTION FOR CODE CLASS 2 COMPONENTS Table 2 provides a tabulation of the Class 2 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer 1975.

These components will be inspected in accordance with the requirements of Subsection IWC to the extent practical. This tabula-tion identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination. Release from the inspection requirements of Subsection IWC is requested where these inspection requirements have been determined to be impractical. Where release is requested, information is provided which identifies the applicable Code re-quirement, justification for the release request, and the inspection method to be used as an alternative. Table IWC-2600 items not applicable to the Edwin I. Hatch Nuclear Plant-Unit 1 have also been listed and identified in the interest of completeness. Items applicable to pressurized water reactors only have been omitted entirely for brevity. Article IWC-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet available for use. Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any inservice examinations will be made, using the acceptance standards for materials and welds specified in the Code under which the specific component was constructed. Some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased. However, these components will be inspected in accordance with the requirements of Subsection IWC to the extent practical. Article IWC-4000, entitled " Repair Procedures," states that the rules of IWB-4000 shall apply. It is considered that the repair procedures outlined in IWA-4000 are appropriate for the components included in this program, and therefore the rales of IWA-4000 will be applied rather than IWB-4000. The inservice inspection programs described in this section were developed as a result of a design review. Should certain ASME Section XI Code requirements be discovered to be impractical, in the course of inspecting the components, due to unforeseen reasons, Georgia Power Company will submit a request for release from the requirements to the NRC at that time. Hydrostatic testing will be conducted in a manner that will satisfy the require-ments of IWA-5000 and IWC-5000. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of piping (e.g., boundary is a check valve), the sections will be tested together at the lower of the specified test pressures. No i point in the piping will be permitted to experience a pressure greater than the specified test pressure. Components exempted from volumetric and surface examination by IWC-1220 will be hydrostatically tested per the requirements of IWA-5000 and IWC-5000. 2B7 Ou6 Amendment 1 W 9 3-1

3.1 Requests 'or Relief From ASME Section XI Requirements 3.1.1 Hydraulic Shock Suppressors 3.1.1.1 Requirement From Which Relief Reauested Table IWC-2520, Category C-E-2, requires visual examination of all support components and verification of support settings for springs and snubbers once per inspection interval. Visual examinations and verification of spring settings will be performed. Relief rrom the verification of snubber settings is requested. 3.1.1.2 Justification The hydraulic shock suppressors on Class 2 systems are currently subjected to an ongoing testing program per plant technical specifications. This program is designed to demonstrate the functional integrity of the shock suppressors and exceeds the requirements of Table IWC-2520. l1 3.1.1.3 Testing in Lieu of Section XI Requirements Hydraulic shock suppressors will be tested in accordance with technical speci-fications. 3.1.2 HPCI and RCIC Turbine Bolting 3.1.2.1 Requirement From Which Relief Requested Table IWC-2520, Category C-0, requires examination of pressure-retaining bolting over one ir.ch in diameter. The closure fasteners for the HPCI pump are studs and cap nuts. The cap nuts completely obscure the studs making an in place volumetric examination impossi-ble. These studs will receive a surface examination when the pump is dis-assembled for maintenance. The closure studs for the HPCI and RCIC turbine have rounded ends making an in place volumetric examination impossible. Relief from inservice examination of these fasteners is requested. 3.1.2.2 Justification The examination of the obscured sted bolts can be accomplished only by de-tensioning all bolting in sequence. If this is done the pump (or turbine) cover should be lifted for gasket replacement. It is anticipated that the pump (and turbine) will require disassembly for main-tenance at various times. As the pump / turbine is testcJ per Section XI, Article IWP, the disassembly for the purpose of examining four studs is not practical. 3.1.2.3 Testing in Lieu of Section XI Requirements These studs will receive a surface examination when the turbine is disassembled for maintenance. 777 csa7 Ou7 Amendment 14/79 3-2

3.1.3 HPCI and RCIC Valve Bolting 3.1. 3.1 Requirement From Which Relief Requested Table IWC-2520, Category C-0, requires examination of pressure-retaining bolting over one inch in diameter. The closure studs for the HPCI and RCIC turbine stop and control valves are obscured by cap nuts or have rounded ends making an in place volumetric examination impossible. Relief from inservice examination of these fasteners is requested. 3.1.3.2 Justification See Paragraph 3.1.2.2. 3.1.3.3 Testing in Lieu of Section XI Requirements These bolts will receive a surface examination when the valves are dis-assembled for maintenance. m,7zaa7 00 3-3

TABLE 2 ISI PROGRAM ASME CODE CLASS 2 COMPONENTS Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Item No. Ca tegory, Description Area to be Examined Exami na tion Requested Cl.1 C-A Residual lleat Remov-Circumferential butt welds Volumetric No al Heat Exchangers C1.2 C-B Residual Heat Remov-Nozzle-to-vessel welds Volumetric No al lleat Exchangers Cl.3 C-C Residual Heat Remov-Integrally welded supports Surface No al Heat Exchangers C1.4 C-D Residual Heat Remov-Pressure-retaining bolting Visual and No al Heat Exchangers either surface or Volumetric C2.1 C-F Piping Circumferential butt welds Volumetric Yes. o, A See Note 1. C2.2 C-F Piping Longitudinal weld joints in Not Applicable. No fittings C2.2 C-G Piping Longitudinal weld joints in Not Applicable. No fittings C2.3 C-F Piping Branch pipe-to-pipe weld Volumetric No joints C2.3 C-G Piping Branch pipe-to-pipe weld Volumetric No rNJ joints 73 La h[j C2.4 C-D Piping Pressure-retaining bol ting Visual and No either surface r Volumetric o c:] C)- s4)

TABLE 2 (Cont'd) Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief I tenLNo. CategorE_ Description Area to be Examined Examina tion Requested C2.5 C-E-1 Piping Integrally welded supports Surface No C2.6 C-E-2 Piping Support components Visual Yes. See Note 2. C3.1 C-f Pumps Pump casing welds Not Applicable. No See Note 5. C3.1 C-G Pumps Pump caring welds Not Applicable. No See Note 5. C3.2 C-D Pumps Pressure-retaining bolting Visual and Yes. See either surface Note 3. or Volumetric C3.3 C-E-1 Pumps Integrally welded supports Surface No C3.4 C-E-2 Pumps Support components Visual Yes. See Note 2. C4.1 .C-F Valves Valve body welds Not Applicable. No See Note 5. C4.1 C-G Valves Valve body welds Not Applicable. No See Note 5. ? C4.2 C-D Valves Pressure-retaining bol ting Visual and Yes. r,a either surface See Note 4. n3 ta or Volumetric O C#4 ] J C4.3 C-E-1 Valves Integrally welded supports Surface No cz) C4.4 C-E-2 Valves Support components Visual Yes. ((,I See Note 2.

TABLE 2 N0TES 1. The arrangement and details of the Class 2 piping systems and components were designed and fabricated be-fore the examination requirements of Section XI of the Code were formalized, and some examinations (as required by IWC-2600) are limited or not practical due to geometric configuration or accessibility. Gen-erally, the limitations exist at all fitting-to-fitting welds such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface conditions preclude ultrasonic coupling or access for the required scan length. Welds having such restrictions will be examined to the extent practical. In instances where the location of pipe supports on hangers restricts the access available for the examina-tion of pipe welds as required by IWC-2600, examinations will be performed to the extent practical unless removal of the support is permissible without unduly stressing the system. The results from Hatch Nuclear Plant-tf it No. 2 show that a full code examination can be performed on 98% of the B-J welds, 81% of the B-K-1 welds (Valves & Piping), and 50% of the B-K-1 welds (Pumps). Similar results are expected for Unit 1. y Relief will be requested at the time any weld is found not to be fully Code inspectable as provided by 92 10CFR50.55a(g). m 2. See Request for Relief, paragraph 3.1.1. 3. See Request for Relief, paragraph 3.1.2. 4. See Request for Relief, paragraph 3.1.3. 5. At present, there are no through-wall casing welds in ASME Class 2 pumps or valves. If such welds are in-troduced, applicable ASME Code examinations will be performed. A O .Na f l '4 Q R w.~J E 'd <o C:) d! 'sJ

4.0 INSERVICE INSPECTION FOR CODE CLASS 3 COMPONENTS This program consists of the examination areas and the visual examinations required to meet IWD-2000. The structural integrity of the Safety Class 3 components shall be demonstrated at least once every 40 months during periods of normal reactor operation or during system performance testing by verifying via visual inspection that Nre is no evidence of unanticipated component leakage, structural o, tress, or corrosion. The structural integrity of the Safety Class 3 components shall be demonstrated at least once every ten years by performing system pressure tests at the following test pressures: 1. For closed systems, at least 110 percent of the design pressure. 2. For open storage tanks, at least the nominal hydrostatic pressure de-veloped with the tanks filled to design capacity. 3. Open-ended portions of systems may be exempted from pressure testing. The structural integrity of the Safety Class 3 components shall be demonstrated at least once every 40 months by verifying via visual inspection that the supports and hangers for piping and components over four inches in diameter show no evidence of inadequate support, unintended restraint, or structural distress. The following provides further clarification concerning the Class 3 inspection program: 1. Article IWD-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet avail-able for use. Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any in-service examinations will be made, using the acceptance standards for materials and welds specified in the Code under which the specific component was constructed. 2. Article IWD-4000, entitled " Repair Procedures," states that the rules of IWB-4000 shall apply. It is considered that the repair procedures outlined in IWB-4000 are inappropriate for the components included in this program, and therefore the rules of IWA-4000 will be applied. 3. Inspection of vertical, centrifugal river intake pumps, as required by IWD-2410 (b) and (c), is impractical except at the pump discharge no zzl e. Visual inspection of the discharge nozzle will be performed while the pump is operating. Should the pump be pulled for maintenance, the casing will be visually inspected at that time. 4. The designs of the service water systems do not include provision for testing buried piping as required by IWD-2600(b). Visual inspection for leakage at ground level is also impossible for portions which are buried. Normal system functional testing demonstrates leaktight integrity of all buried or encased piping 2337 072 4-1

5. The system pressure testing requirements of IWD-2410 (b) wi11 not be per-formed on lines two inches and smaller unless: (a) They are connected to larger lines whicn will be pressure tested. (b) Isolation valves are not provided so that these smaller lines may be isolated in case of leakage. These smaller lines have wall thicknesses in excess of what ASME Section III requires for retaining internal pressure. Using heavier-walled piping in these small lines essentially means they are over-designed for the pressure they are retaining and are not susceptible i to the type leakages found during hydrostatic testing. As an alterna-tive, all accessible piping two inches and smaller will be visually in-spected under normal operating pressure. 6. System pressure testing as required by IWD-2410 (b) is impractical for certain portions of the plant service water system because it operates continuously during all modes of plant operation. This functional oper-ation demonstrates the structural and leaktight integrity of the system. Visual inspection will be performed while the system is under normal operating pressure to verify leaktightness. 7. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of I piping (e.g., boundary is a check valve), the sections will be tested together at the lower of the specified pressures. No point in the piping will be pressurized above the specified test pressure. n ,,7 dsJ/ u/J Amendment 1 4/79 4-2

5.0 INSERVICE TESTING OF PUMPS The 1974 ASME Section XI Code with Addenda through Summer 1975 requires inservice testing of pumps in accordance with section IWP. The inservice testing program for Class 1, 2, and 3 pumps is described in Table 3. Where full compliance with the requirements of the Code was not possible, an explanation is provided in the table. 5.1 Requests for Relief from ASME Section XI Requirements 5.1.1 Vertical Centrifugal Pumps-Service Water and RHR Service Water Pumps l1 5.1.1.1 Requirement from Which Relief Is Requested Article IWP-4310 of Section XI requires the monitoring of all centrifugal pump bearing temperatures. Relief from this requirement is requested for the Service 1 Water and RHR Service Water lower bearings. 5.1.1.2 Justification Only the upper bearings are accessible; the lower bearings are below the sur-ly face of the river. Pump disassembly for bearing inspection is not practical. I 5.1.1. 3 Testing in Lieu of Section XI Requirements The lower bearings will be inspected for wear whenever a pump is pulled for maintenance. 5.1. 2 Vertical Centrifugal Pumps-RHR and Core Spray Pumps 5.1. 2.1 Requirement from Which Relief Is Requested Article IWP-4310 of Section XI requires the monitoring of all centrifugal pump bearing temperatures. Relief from this requirement is requested for the RHR and Core Spray Pump lower. bearings. 5.1.2.2 Justification There are no true lower bearings in these pumps. Only bearing surfaces exist that are cooled and lubricated by the process water. There are no means to measure bearing temperatures. 1 5.1. 2. 3 Testing in Lieu of Section XI Requirements The bearing surfaces will be examined for wear whenever a pump is pullea for maintenance. 5.1. 3 Pump Testing Interval 5.1.3.1 Requirement From Which Relief Requested Article IWP-3400 requires an inservice test to be run on each pump once per month. It is proposed that the pump inservice testing interval be changed to once per three months. Amendment 1 4/79 5-1

5.1.3.2 Justification The intent of the pump testing program is to assure an increased level of plant safety by verifying the operational readiness of each pump. An optimized testing program would assure pump operability and have the least impact on the degradation of the pump and its associated equipment over its service lifetime. Excessive testing downtime jeopardizes pump availability for performance of its safety-related function, causes component wear, and does not increase the level of plant safety. The Section XI Subgroup for Inservice Testing of pumps and valves has con-1 ducted an extensive investigation and analysis of test optimization. Two papers written by W. E. Vesely, Probabilistic Branch, USNRC, provided a basis for changing from a one-month interval to a three-month test interval. As a result, this proposed revision to the Section XI Code has been initiated to change the pump interval to nominally every three months. Since it has been shown by the NRC and the Section XI Subgroup that the three-month pump testing interval provides the plant with an increased level of safety, it is proposed that the Plant Hatch - Unit No. 1 pump testing in-terval be changed to every three months. m,,, Js3/ 075 Amendment 1 4/79 5-la

J s TABLE 3 INSERVICE TESTING PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 PUMPS ASME Pump Code Test Section XI Code Identification Pump Description Class Measured Parameters Interval Relief Requested 1C41 C00tA Standby liquid control 2 1. Inlet pressure (P ) Monthly No. Note 7 l1 j 1C41 C0'alB 2. Differential pressure Monthly No. (AP) 3. Flow rate (Q) NA No. Note 4 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually No. Note 3 6. Lubricant level or Observe Mo. No. pressure 1E11 C002A Residual heat removal 2 1. Inlet pressure (P ) Monthly No. j IEll C002B 2. Differential pressure Monthly No. Note 1 (AP) lEll C002C 3. Flow rate (Q) Monthly No. Note 1 lEll C002D 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually Yes. Notes 3,8 l1 6. Lubricant level or Observe Mo. No. Note 6 pressure lEll C001A RHR service water 3 1. Inletpressure(P) Monthly No. Note 2 l1 9 y k lEll C001B 2. Differential pressure Monthly No. Note 1 ra 5 1 Ell C001C ta (AP) 3. Flow rate (Q) Monthly No. Note 1 ^ [ lEll C0010 4. Vibration amplitude Monthly No. Note 3 c3 R N 5. Bearing temperature Annually Yes. Notes 3, 5 E 6. Lubricant level or Observe Mo. No. Note 6 pressure

TABLE 3 (Cont'd) ASME Pump Code Test Section XI Code Identification Pump Description Class Measured Parameters Interval Relief Regested lE21 C001A Core spray 2 1. Inlet pressure (P ) Monthly No. lE21 C001B 2. Differential pressure Monthly No. Note 1 (AP) 3. Flow rate (Q) Monthly tio. flote 1 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually Yes. Notes 3,8 [ t 6. Lubricant level or Observe Mo. No. Note 6 pressure lE21 C002A Jockey pump 2 1. Inlet pressure (Pi) Monthly No flote 9 l1 lE21 C002B 2. Differential pressure Monthly No T (AP) 3. Flow rate (Q) NA No. Note 4 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually fio. Note 3 6. Lubricant level or Observe Mo. No pressure IP41 C001A Plant service water 3 1. Inlet pressure (P ) Monthly No. Note 2 j 1P41 C001B 2. Differential pressure Monthly No. Note 1 (A 2 E IP41 C001C N 18 h IP41 Cc01D N 3. Flow rate (Q) Monthly fio. Note 1 N 4. Vibration amplitude Monthly No. tiote 3 {[g 5. Bearing temperature Annually Yes. Notes 3, 5 ] o g ] 6. Lubricant level or Observe Fo. No. Note 6 g pressure

TABLE 3 (Cont'd) ASME Pump Code Test Section XI Code Identification Pump Description Class Measured Parameters Interval Relief Requested lE41 C001 Iligh-pressure coolant 2 1. Inlet pressure (P ) Monthly No j injection 2. Differential pressure Monthly No. Note 1 (AP) 3. Flow rate (Q) Monthly No. Note 1 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually No 6. Lubricant level or Observe Mo. No pressure 7. Pump speed Monthly No )" lE51 C001A Reactor core isolation 2 1. Inlet pressure (P ) Monthly No g cooling 2. Differential pressure Monthly No. Note 1 (AP) 3. Flow rate (Q) Monthly No. Note 1 4. Vibration amplitude Monthly No. Note 3 5. Bearing temperature Annually No. Note 3 6. Lubricant level or Observe Mo. No pressure 7. Pump speed Monthly No 2' ra A w N CD N CO

' TABLE 3 N0TES 1. Measurement of both AP and Q is not required by ASME Section XI. One of these quantities may be omitted from the test specified by the surveillance procedures. 2. These pumps are vertical design with no means of direct inlet pressure measurement. In lieu of direct measurement, the intake level will be measured. This can then be converted to pump inlet pressure as: i Inlet pressure (P ) = .5 R - Intake yvel (fO i 2.3066 (ft/ psi) 3. No instrument is installed on the pump. A portable instrument will be used. 4. No flow instrumentation is installed on this pump. A fixed-resistance test circuit will be used in accordance with footnote 1 of Table IWP-3100-1. 5. See Request for Relief, paragraph 5.1.1. [ 6. Lut;ricant level is to be observed for the driver thrust bearing only. The main bearings are lubri-cated by the pump water. 7. No direct means of measuring pump inlet pressure is available. Pump inlet pressure will be calcula-ted from test tank level. 8. See Request for Relief, paragraph 5.1.2. 1 9. These pumps are normally operating pumps and will not be shut down to measure inlet pressure. E b ra o Q VJ Q L.ed sa b D N e e

6.0 INSERVICE TESTING OF VALVES The 1974 ASME Section XI Code with Addenda through Summer 1975 requires in-service testing of valves in accordance with section IWV. The inservice testing program for Class 1, 2, and 3 valves is described in Table 4. Where full compliance with the requirements of the Code was not possible, an explana-tion is provided in the table. 6.1 Requests for Relief from ASME Section XI Requirements 6.1.1 Requirement from Which Relief Is Requested IWV-3410(g) and IWV-3520(c) state that when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. 6.1.1.1 Justification l1 Under such conditions startup shall be permitted as provided in the technical specifications. 6.1.2 Requirement from Which Relief Is Requested IWV-3410(c) states that if an increase in stroke time of 25% or more from the previous test for valves with stroke times greater than ten seconds or 50% or more for valves with stroke times less than or equal to ten seconds is ob-served, test frequency shall be increased to once each month until corrective action is taken. Relief is requested for valves normally tested during cold shutdown. 6.1.2.1 Justification Valves that are normally tested during cold shutdown or refueling cannot be tested once each month. Stroking these valves during power operation may place the plant in an unsafe condition. 6.1.2.2 Testing in Lieu of Section XI Requirements 1 The test frequency shall be increased to once each cold shutdown, not to exceed once each month. 6.1. 3 Requirement from which Relief is Requested IWV-3420(f) requires a permissible leakage rate for each specific Category A valve. Only valves performing a pressure isolation function, as defined in Table 4, note 38, have Section XI permissible leakages. 6.1. 3.1 Justification The plant design is not compatible with checking permissible leakages for specific valves because of the complex piping and valving arrangement; however, the 10CFR50 Appendix J local leak rate testing program for the centainment isolation valves has an overall limit of 60% La based on off-site dose calcu- ?',37 080 Amendment 1 4/79 6-1

lations. Since 60% La is an overall limit, the possibility exists that the majority of the containment leakage may leak through one highly degraded valve and be within the 60% La limit. Although the uniformity of leakage through the containment penetrations is relatively unimportant, it is not desirable to have the majority of the containment leakage being emitted through one penetration. The engineering judgement of plant management will be used to determine whether a valve is leaking excessively. Valves which leak excessively will be repaired and retested before being placed into service. 6.1. 4 Requirement from which Relief is Requested IWV-3420(g) requires valves with leakage rates to have corrective action applied to them. Only valves performing a pressure-isolation function, as defined in Table 4, note 38, have Section XI corrective action applied to them. 1 6.1. 4.1 Justification Corrective action per IWV-3420(g) cannot be applied to valves exempted from IWV-3420(f). (See request for relief, paragraph 6.1.3) 6.1.4.2 Corrective Action in Lieu of Section XI Reauirements Except for valves performing a pressure-isolation function, corrective action will consist of the repair of valves judged to be leaking enessively. 6.2 Valves to be Tested During Cold Shutdown and Refueling Valve testing will commence as soon as possible into the cold shutdown but no later than 48 hours after the shutdown. Valve testing will continue during the shutdown until complete or until plant startup and return to power. Any testing not completed at one cold shutdown will be performed during subsequent cold shutdowns before the next refueling. During refueling, any valve scheduled for a refueling test will be tested. Also, any valve identified to be tested at cold shutdown that has not been tested during the previous three months will be tested during the refueling. G 7 z.,;7 7 0 8 1 Amendment 1 4/79 6-la

TACLE 4 INSEFWICE INSPECTION VALVE TEST PL AN 5'd 81 ASME CODE CL ASS 1.2. AND 3 VALVES ~/4. olL 4","P.i d ' ;.. = ' " * - g; g;,, 2!! '" U.Te ah l _9 I Note 39 l1 6 21 -I0_10A.. {._1, _A_C. { _18" C hec k 3-E H-16062 feedwater Inboard Containment Isolation 0 Each Refueling Outage Each Refueling Outage Yes. Note 2 I Nte 39 b B21-F0108 . 1 i AC 18" Check 3-D H-16062 Feedwater intoard Containment Isolation 0 Each Refueling Outage Each Refuelin2 utage Yes. Note 2 0 S21-F013A l l ['...C 6" Relief C-6 H-I t>Ob2 Main Steam Relief Note 3 NjA No. Note 19 l 821 - F'll 3B 1 C ' 6" Reitef C-6 H-16062 Main Steam Relief Note 3 N/A No. 6te 19 821 -F 013C 1 C 6" Relief F-6 H-Ib062 Main Steam Re11"f No te j _ __ _ _ h/ A __ _ ____ No. Note 19 B21-F0130 1 C 6" Relief F.6-. H _16062 Main Steam Re_ lief _ __ -.. _ _ _.. _ _ -. _ __N.o..t_e _3- - - --- _ N/A _. [. 9-__ .~_ .-._ _.N. o. te.1_9_ No 8 21-F013E 1 C 6" Relief F-6 H-16062 Main St eam Relief Note 3 N/A No. Note 19 B2hf013F,_,. 1 C y_.,R gl, j t f,__ ..F 9 H-lj,062 Ma.j n_ S te am M j ef _ _ __ __ _ _ __ _ _.. M t t J _ ___ _ _ __ h/A _ ___ ho. tiote.19_ 7 021-F013G 1 0 6" kelief F-6 H.15062 Main Steani Relief Note 3 N/A No. Note 19 B21 - F Ol 3H 1 C 6" Relief G-6

1-16062 Main Steam Relief Note 3 N/A Na, Note 19 B21-F013J l

C 6" Relief G-6 H-16062 Main Steam Relief Note 3 N/A No. 6 te 8' B21 F0138 1 C 6" Relief F-6 H-16062 Main Steam Relief Note 3 N/A N. Note l's 6 t l -F il 3L p C 6* Relief F-6 H-16062 Main Steam Relief Note 3 N/A i - No. Note 19 '~ 6-2 Amendr+rit 14D IN) <.a b4 N CD CO N

4 N Y ~ TABLE 4 2 N INSERVICE INSPECTION VALVE TEST PLAN SH' M O' ASME CODE CLASS 1,2. AND 3 VALVES I f .L*MI (([.,

u. n'.'.!!.oa.

' AT*N oU ! o sess e as evaa.cv h "Y' 'Ub None Yes. Note 10 B21-F016 1 A 3" M0 Gate E-8 H-16062 Main Steam Line Drain Intmard Isolation C (Note 53) Each Refueling Outage Note la. None 821-F019 1 A 3" N0 Gate E-9 H-16062 Main Steam Line Drain Outboard Isolation C (Note 53) Each Refueling Outage Yes. Notc 39 821-F022A 1 A 24" A0 Globc C-7 H-16062 MSIV O Every Three Months Each Refueling Outage 3-5 No. Note 39 B21-F0228 1 A 24" A0 Glote E-7 H-16062 MSIY 0 Every Three Ptinths Each Refueling Outage 3-5 No. Note'39 021-F 022C 1 A 24* A0 Glot* F-7 H-16062 MSIy 0 [very three Months Each Refueling Outage 3-5 No. Note 39 L B21-F0220 1 A 24* A0 Glok G-7 H-16062 M51V 0 Every Three Months Each Refueling Outage 3-5 No. Note 39 821-F028A 1 A 24" A0 Glot,c C-9 H-16062 M5tV O Every Three Months Each Refueling Outage 3-5 No. Note 39 821-F0288 1 A 24" A0 Glob. E-9 H-16062 MSIV O Every Three Months Each Refueling Outage 3-5 No. Note 39 821-F028C 1 A 24" A0 Glob. F-9 H-16062 MSIV 0 Ever3 Three Months Each R. fueling Outage 3-5 NJ. Note 39 B21-F0280 1 A 24" A0 Glota G-9 H-16C52 M5ly 0 Every Three M3nths Each Refueling Outage 3-5 No. Note 39 Note 39 821-F032A 1 1 18" Check E-2 H-16062 feedwater Outboard Isolation 0 f ach Refueling Outage Each Refueling Outage Yes. Note 2 Note 39 821-F0328 1 AC 18" Check D-2 H-16062 Feedwater Outboard Isolation 0 Each Refueling Outage Each Refueling Outage Yes. Note 2 B21-F031A 3 C + 6" Check H-6 H-16062 Vacuum Breaker MSRY Discharge C None N/A Yes. Note !, n nt i 4/19 6-3 PJ .a bd N CD Co LN

TABLE 4 INSEMVICE INSPECTION VALVE TEST PLAN 5'"E' - O' ASME CODE CLASS 1.2. AND 3 VALVES --y_. ...h~.....,.., n. L ly g Ep .u.c,...,.,..o.. ,,, m,s .m. ...s m ( i B21-F 037B 3 C 6" C h ec k [H-b H-16062 Vacuum Breaker MSRV Discharge C None N/A Yes. Note 5 B21-F 037C 3 C 6" Check H-6 H-16062 Vacuum Breaker M5RV Discharge C None N/A Yes. Note 5 B21-1037D 3 C 6" Chet6 H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A Yes. Note 5 B21-6037E 3 C 6" Check H-6 H-160b2 Vacuum Breaker MSRV Discharge C None N/A Yes. Note 5 B21-l037F 3 _C_ 6_" C_ hec k _. j H-6 H-16062 Vacuunt "reaker MSRV Discharge C None N/A Ves. Note 5 B 21 -F 037G 3. b_. Check 7.H-6 H-l b. a.62 Vacuum Bre.a.ker.M_SR.V. D.isc.ha.r_ge. _C. _.-- _No.ne _ _ __ _.__ _ _ _N./A.. C Yes. Note 5 1 821 - f 037H 3 C 6" Check l H-6 H-16062 Vacuum Breaker MSRV Discharge C Nant N/A y g3 -_ ggg g, (_ 1 821 - F037J 3 C 6" Chech H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A Ves. Note 5 B21-F037K 3 C 6* Chet h [H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A Ves. Note 5 621 - F 037L 3 C 6" Chec k H-6 H-16062 Vacuum Breaker MSRV Discharge C None N/A Yes. Note 5 Ves. Note 2 b 31-F013A 1 AC 3/4" Check F-3 H-16066 Recirculation Pump Seal Watc* O Each refueling Outage Each Ref uelin3._O_u.t_ age Note 40 Yes. Note 2 B 31-F 0138 1 AC 3/4" Check F-3 H-16066 Recirculation Pump Seal Water 0 fact, afueling Outay_ Each Refuelina Outage NoiL4Q__. Yes. Note 2 I 3 31-F 017A 1 AC 3/4' Check ; F-2 H_-16066 Rr:circulatio_n Pump Seal Water 0 Jach Refa lin3.9uta9L IdCh Fctuelin10utage Yes. Note 2 031-F0178 1 AC 3/4".Chec k F-2 H-16066 Recirculation Pump Seal Water 0 Each Refueling Outage - - -Each Refueling Outage f.y ( 3/4" A0 -- Note 40 -~ B31-f019 1 A Globe D-3 H-16066 Reactor Sample System Inboard Isolation 0 [very three months Each Refueling Outage 5 U Yt es. Note 39 N ~ 6-4 henJment 14/73 O CO h

TABLE 4 4 24 INSERVICE 6NSPECTION VALVE TEST PLAN ASME CODE CLASS 1.2. AND 3 VALVES !n ._ -__ _r~m k z,x,., q'. :.. ,a :.:u ;:.= m :. g-3/4" A0 Bil-F020 1 A Glot,e D-1 H-16066 Reactor Sample System Inboard Isolation 0 Every three months Each Refueling Outage 5 Ves. Nate 39 Ves..ute 52 H31-f031A I B 28" M) Ga t e 1 4-I to66 Reac tor Recircula tion 0 Cold Shutdown N/A 40 No te 25 Ves. Note 52 B 31 - F 03] B 1 B 23" MO Gate H-7 H-l uj66 Reac tor Recircula tion 0 Cold Shutdown N/A 40 Note 25 1-1/2" E pl I C41-F004A 2 0 Shea r D-3 H-1606l SLC Emplosive Actuated C Nute 4 N/A No 1-1/2" Expl C41-FON B 2 0 Shear E-3 H-1606l SLC Explosive Actuated C Note 4 N/A No 1 1/2-Note 39 C41-f006 i AC Check E-2 H '6061 SLC Outboard Containment isolation C Once/ m Pbnths Fach Refueling Outage Yes. Note 2b l-1/2= Note 39 l1 C41-t001 1 AC Chec k t-2 H-16061 SLC Outtoard Containment Isolation C Once/18 Months fech Refueling Outage Yes. Note 26 C4!d O2% _ _ 2 C._ !"_ Relief __ D-6 H_l6061, 5[C_ Pump D scharge Relief Valve C Note 3 N/A No. Note 19 C4I-F029B 2 C 1" Relief G-6 H-16061 5tC Pump Discharge Reitef Valve C Note 3 N/A No. Note 19 l - 1/ 2" . _ _- F 0 3 3A_ _ _ _ E _5_._-16061 i C41 2 C Check H SLC Pump Discharge C Note 7 N/A Yes 1-1/2" C41-I033B 2 C Check G-5 H-16061 SLC Pump Discharge C Note 7 N/A Yes N E lOOOlA __. 2 _8._ 16" N Ga te D-9 H-16330 RHR Heat f xchanjer Shell Side Outlet 0 f very Three Months N/A 82 No LN U f!1-Fp)B _ ? ti 16" M0 Cate D-4 H-16329 RHR fle.st f uthanger Shell $1de Datlet 0 Every Three Months N'A 82 ho N Ell.t004A _ _{ A 24" P0 Ga te F-10 H-16330 RHR Pungsuction Torus isolation 0 Every_Three Months fach Refueling Outa2e 125 Ves. Note 40 l1 Q Ell-F0048 a 2 A 24* M0 Gate F-3 H-16329 RHR Pump Suc tion Torus Isolation 0 Every Three Months Each Refueling Outage 125 Ves. Note 40 El U 6-5 Amendment I 4/79

S A TABtt 4 8 INSE RVtCE INSPECTION VALVE TEST PLAN 5"EET O' ASME CODE CLASS 1.2. AND 3 VALVE 5 ~ if,'.'t,O';.*g.% ."*.'.U. [j[.

o. E*'.U.o

%L*.T off! ' 'as n' ** ama ne.s. p. ova se s an=ac a y g Ves. Note 40 E11-F004C 2 A 24* M0 Gate F-10 H-16330 RHR Pump Suction Torus Isolation 0 Every Three Months Each Refueltag Outage 125 Yes. Note 40 Ell-F004D 2 A 24* M0 Gate F-3 H-16329 RHR Pump Suction Torus isolation 0 Every Three Months Each Refueling Outage 125 Ell-FOOLA 2 8 20" M0 Gate F-10 H-16330 RHa Shutdown Cooltag Suction C Every Three Pbnths N/A 110 No E11-F006B 2 8 23* MD Cate F-2 H-16329 RHR Shutdown Cooling Suction C Every Three Months N/A 110 No E11-F006C 2 8 20* M0 Cate F-10 H-16330 RHR Shutdown Cooling Suctfon C Every Three Months N/A 110 No g E11-F0060 2 8 20" MD Gate F-2 H-16329 RHR Shutdown Coolisa Suction C Every Three Months N/A 110 No Note 43 E11-F007A 2 A 4* M0 Gate E-7 H-16330 RHR Pump Mintass Flow Torus Isolation 0 Every Three Months Each Refueling Outage 25 Yes. Note 10 Note 40 Ell.F007s 2 A 4* R) Cate D-5 H-16329 RHR Pump Minimum Flow Torus Isolation 0 Every Three N nths Each Refueling Outage 25 Yes. Note 10 Nore E11 F008 i A 20* M) Cate D-1 H-16329 RHR Shutdown Cooltag Outboard Isolation C (Note 53) Each Refueling Outage Ves. Note 33 None E11-F009 1 A 20* M0 Gate D-1 H-16329 RHR Shutdown Cooling Suction Isolation C (Note 53) Each Refueling Outage Ves. Note 38 Note 40 E11.F0114 2 A 4* M0 Gate D-3 H-16330 RHR Condensate Discharge to Torus C Every Three Months Each Refueltag Outage 25 Y es. Note 10 Note 40 E11-F0ll8 2 A 4" M0 Gate C-9 H-16329 RHR Condensate Discharge to Torus C Every Three Months Each Refueling Outage 25 Ves. Note 10' ho. Note 38 Id E11-F015A 1 A 24" PC Cate C-8 H-10330 LPCI Outboard Containment Isolation C Every Three Ptinths Each Refueling Outage 24 6-6 Amendment 14/79 ~ CD OD ON

n TABLE 4 INSERVICE INSPECTION VALVE YEST Pt. AN S* H O' ASME CODE CLASS 1.2. AND 3 VALVES I f 'U'N'l ,:.,2;/, , '),', o.n'tno O.".T of? L se o e.e -s.c. Id d! " ~ ' ' " ' ' .....c. { e_ Ell-f0158 ) A 24" M0 Late C-4 H-16329 LPCI Outboard Containment Isolation C Every Three pbnths Each Refueling Outage 24 No. Note 38] I Ell-f016A 2 A 16" PU Globe B-9 H-16330 Containment Spray Outtoard Isolatfor C Every Three Pbnths Each Refueling Outage 10 Ves. Note 40 1 1 E11-f0168 2 A 16" M0 Globe B-4 H-16329 Containment Spray Outboard Isolatton C Every Three Mohths Each Refuelin9 Outage 10 Yes. Note 40 Ell-F017A 1 8 24" m Globe D8 H-16330 LPCI O Every Three Months N/A 24 No' E11-f0178 1 8 24" to Globe D-5 H-16329 LPCI O Every Three Pbnths N/A 24 No I i E11-f019 1 C 4" Check A-1 H-16329 Head Spray C Note 6 N/A ho l l E11-1021A 2 8 16* M0 Gate 8-11 H-16330 Containment Spray C Every Three Moriths N/A 17 No E11-f0218 2 8 16" PC Cate B-2 H-16329 Containment $ pray C Every Three Moriths N/A 17 No None E11-f022 1 A 4* M0 Gate A-1 H-36329 Head Spray C (Note 53) Each Refueling Outage Yes. Note M t None E11-F023 1 4 4" MD Globe A-2 H-16329 Head Spray Outboard Isolation C (Note 53) Each Refueling Outage a Ves. hate M. Y Ell-f024A 2 8 16" MO Globe C-7 H-16330 Suppression Pool Cooling C Ev2ry Three Months N/A 110 No E11-f0248 2 8 16" M0 Globe C-6 H-16329 Suppression Pool Coolfng C Every Three Months N/A 110 ho Ves. Note 40 h Ell-F025A 2 AC I" Relief 6-8 H-16330 LPCI Injection Containment Isolation C Mote 3 Each Refueling Outage Note 19 l e N (,a ' * = " * ' ' " 6-7 Amendment 1 4/7s (M N CD CO N

.f TASLE 4 I 24 SNSERVICE INSPECTION VALVE TEST PLAN s*M T of ASME CODE CLASS 1.2. AND 3 VALVES s .!M. )[. o d*J.U.o W"a " I.a

**.u o.

j ,\\*f,g";,=gg Ves. Note 40 g Ell-F02$8 2 AC 1* Pelief C-5 H-16329 LPCI Injection-Containment Isolation C Note 3 Each Refueling Outage Note 19 Con tai n. (11-F026A 2 A 4' N0 Gate D-3 H-16330 Condensate Discharge to RCIC - Isolation C ivery Three Months Each Refueling Outage 25 YES. NOTE 40 Contain. E11-F0268 2 A 4* m Cate D-11 H-16329 Condensate Discharge to RCIC - Isolation C Every Three Months Each Refueling Outage 25 Yl5. K0ft 40 E11-F027A 2 8 6" M0 Globe D-3 H-16330 Suppression Pool Spray C Every Three Months N/A Il No E11-F:27B 2 B_ 6' M Globe D-Il H-16329 Suppression Pool 5 pray C Every Three Months N/A 11 No E11-F028A 2 A 16* M0 Gate B-8 H-16330 Suppression Pool 5 pray Outboard Isolation C Every Three Months Each Refueling Outage 25 No Ell-F0288 2 A 16" M0 Gate B-5 H-16329 Suppression Pool spray Outboard Isolation C Every Three 8tnths Each Refueling Outage 25 No Yes. Note 40 t E11-F029 2 AC l' Reitef E-2 H-16329 RNR Puay Suction-Containment Isolation C Note 3 Each Refueling Outage Note 19 Yes. Note 43 E11-F030A 2 AC 1" Relief F-9 H-16330 RHR Pump Suction-Contatruient Isolation C Note 3 Each Refueling Outage kote 19 g i Ves. Note 40 E11-F0308 2 AC I" Relief F-4 H-16329 RHR Puwp Suction-Contatteent Isolation C Note 3 Each Refuellog Outage Note 19 r Yes. Note 40 Ell-F030C 2 AC l' Relief F-11 H-16330 lutR Pump suction-Contefnment Isolation C Note 3 Each Refueling Outage Note 19 t Yes. hote 40 Ell-F0300 2 AC 1" Relief F-1 H-16329 RHR Pump Suction-Containment Isolation C Note 3 Fach Refueling Outage Note 19 [Il-F031A 2 C 20" Check H-6 H-16330 RHR Pump Discharge C Note 29 N/A _Its Ell-F031B 2 C 20" Check H-6 H-16329 RHR Pump Discharge C Note 29 N/A Yes j LeJ Ell-F031C 2 C 20" Check H-10 H-16330 RHR Pump Olscharge C Note 29 N/A Yes q O E ll-F 031D 2 C 20" Check H-2 H-16329 RHR Pump Discharge C Note 29 N/A Yes CO Every Three it>nths CX") E11-F046A 2 C 3' Check H-1 H-16330 RHR Minimus Flow Line C (Note 29) N/A No 6-8 Asendment 14/79 6

TABtt 4 INSERVICE INSPECTION VALVE TEST PLAN S*4 L ' W ASME CODE CLASS 1,2. AND 3 V ALVES p* "'j'**"'t'*_"________,!p .s..e4...~.e,.,.,c M

m m,... 7

~..o . -. ~. Every Thrte Months

-iO468 2

C 3" Check H-5 H-16329 RHR Mininum flow tine C (Note 29) N/A No Every Three Months g sC46C 2 C 3* Chec k H-ll H-163 30 RHR Minimum Flow Line C (Note 29) N/A M Every three mnths t 146D 2 C 3" Chec k H-2 H-Ib329 kHR Minin a flow L ie C (Note 29) h/A M f I 'l-F441A i 2 B I t" PU Ga te E-6 H-16330 R4R Heat Enchanger Shell Side Inlet 0 Every Three Munths N/A 82 No Ell-f437B 2 B 16" MO Ga te E-7 H-16329 -RHR Heat E nchanger Shell Side Inlet 0 Every Three Months N/A 82 No Ell-fc45A 2 B 24" M0 Glote B-8 H-16330 RHR Heat Exchanger Shell Side Bypass O Every Three Months N/A 175 No l1 E11-f04dB 2 B 24" MO ( lobe B-5 H-16329 RHR Heat Enchanger Shell Side Bypass O Every Three Nnths N/A 175 No Yes. Note 38 24" A0 Check D H-16333 LPCI Injection Isolation C Cold Shutdown Each Refueling Outage hote 22 _ ____ __ p _-6 _E_11 -f 0$0A 1 AC Yes. Note 33 Ell-f05GB i AC 24" A0 Ched D-7 H-16329 LPCI Inia. tion Isolation C Cold Shutdown Each Refueling Outage No. Note 22 1 Contain. Ves, hote 40 E l l -F 055A 2 AC 4" Relief D-6 H-16330 RHR Heat Exchanger Shell Relief-Isolation C Note 3 Each Refueling Outage No. Mte 19 Contain. Ves. bte til l' tit-f6558 2 AC 4" Reitef D-1 H-16329 RHR Heat Exchanger Shell Relief-Isolation C Note 3 Each Refueltog Outage Na Nute 19 24" A0 Ell-F005A 2 B Butterfly E-10 H-16330 RHR Torus Suction 0 Every Three Nnths N/A 12 NO l1 24" A0 [lI.rr !S B Butterfly f-2 H-16329 RhR Torus Suction 0 Every Three Months ufA 12 gg e rv I -f 6-9 Anendrent 14/73 L4 N CD CO

t I ? TAk t 4 INSERVICE INSPECTION VALVE TEST PLAN sHE E T or ASME CODE CLASS 1.2. AND 3 VALVES l ig jg me.

pt.

-, = _ seu at: 2::w2 =w L 24" A0 E11-F065C 2 8 Butterfly E-10 H-16333 RHR Torus Suction 0 Every Three Months N/A 12 No t 24" A0 i Ell-F0650 2 8 Butterfly E-2 H-16329 RHR Torus Suction 0 Every Three Months N/A II No t E11-F016A 2 C 10" Check H-6 H-16330 RHR Heat Exchanger Service Water Intertte C NOTE 54 nja YES. M TE $4 E11-F0788 2 C 10* Check D-9 H-16329 RHR Heat Enchanger service Water intertie C WTE 54 gj3 YES. NOTC 54 Ell-F091A 2_ 8 6" to Glot,e E-2 H-16330 Steam Line to RHR Heat Enchanger Shutdown C Every Three Pt>nths N/A 65 No Ell-F0918 2_ B 6" to Globe E-11 H-16329 Steam Line to RHR Heat Exchanger Shutdown C Every Three Months N/A 65 No Yes. Note 40 E11-F097 2 AC 3" Relief D-11 H-16329 Steam Supply Relief-Containment Isolation C Note 3 Each Refueling Outage (See hote 19) i l Conta trurent g E11-F103A 2 A 1" to Globe E-5 H-16330 RHR Heat Exchanger Vent - Isolation C Every Three Months Each Refueling Outage 15 Yes. Note 40 i Conta tracnt E11-F1038 2 A 1" MO Glube E-8 H-16329 RHR Heat Exchanger Vent Isolation C Every Three Pt>nths Each Refuelin9 Outage 15 Yes. Note 40 I E11-F1404 2 8 6".O Gate E-2 H-16330 Steam Line to RHR HNt Exchanger Shutdimn C Every Three Nnths N/A 35 No e E11-F1400 2 8 6" M0 Ga te E-Il H-16329 Steam Line to RitR Heat Exchanger Shutdown C Every Three Months N/A 35 no Every three Months 3 8 10" to 8all H-6 H-16330 RHR Heat Exchanger Service Water Discharg C (Note 28) N/A ho Ell-F0f.,8A 1 Every Three Months Ell F0688 3 8 10" HQ Balli H-7 H-16329 RHR teat Exchanger Servtce Water Discharg' C (Note 28) N/A No y 6-10 knendment 14/79 ,m CD 'JD CO

s 1

1A8tE 4 N 20 INSERVICE INSPECTION VALVE TEST FLAN istit W ASME CODE CLASS 1.2. AND 3 VALVES i J kG 'Wh as es N g Me3 U Ser e ' 4ia D ,a a A Est isa soes Ji E11-F073A 2 B 10" M0 Gate G-4 H-16330 RHR 5ervice Water Intertie _C Every Qrg d nth L N/A No 60 E11-F0738 2 3 10' M0 Gate G-9 H-16329 RHR Service Water Intertie C Every Three Nnths N/A NO E11-F075A 2 8 10' M0 Gate G-4 H-16330 RHR Service Water Intertie C Every Three Months N/A No 60 E11-F0758 2 8 10" M0 Gate G-9 H-16329 RHR Service Water Intertie C Every Three Pbnths N/A NG Ell-F119A 3 8 18' MD Gate H-4 H-16330 RHR Service Lter Train A & 8 Cross C Every Thrge Nntta N PA 110 No Ell-F1198 3 8 18" M0 Gate H-9 H-16329 RHR Service Water Train A & 8 Cross _ C_ bgrLJhrgg.fksths N/A 110 No g Eli-F200A 3 8 2* A0 PCV D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A No I E11-F2008 3 8 2* A0 PCV D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A NG i f Ell-F200C 3 8 2* A0 PCV D-11004 RHR Service Water Pump Mintmum Flow C Note 9 N/A No No E11-F2000 3 P 2* A0 PCV D-11004 RHR 5ervf ce Water Puq_Minfug Flow _C_ Ng gg_j N/A 1/2" Ell-t001A 3 8 Solenoid D-11004 RHR Service Water Pump Cooling C Note 48 N/A No l1 pli Amendment 14/79 (G LN LN N CD 'O

T ABL E 4 ii INSERVICE INSPECTlON VALVE TEST PLAN V'a i ! O' ASME CODE CL ASS 1.2. AND 3 V ALVES ~ 7 --- I, y T ~ ~ ~ ~ ~ -~ "$'*"~~- E i y p s.... .m.m l jh

- I p

e. m sa p..., u...... y ' 1/ r Ell-trnis ; _3, 8_._ _S_o l. e,..o.. i. d_ _. PHR Service Water Pump toolir.1 C Note 45 _ _. N/A D-11004 ho 7 i 1/2" 3{ 8 Solenoid 0-11004 RHR Service Water Pump Cooling C Note 43 N/A No Ell-l60lc Ell.6%13 _ f q! l/2" 3 ! _B S_ol. enoi d D-11004 RHR Service Wa ter Pua.p Cooll9.. _ _C._ Note _43. __ _ _._ _ _/ A___ N No l [ Core Spray Pump forus Suc tion Outtoard -E 21 - F')01 A '2'A 20" N Ga.te H-8 H_16331 Isolation 0 Every Three H;nths Each Refueling Outage 1% Yes. Note 40 Core Spray Pump Torus Suc tion Outboard E 21.. F %1 B_ 2 .A _ _20" MO..Ga.t.eJ _8_ H - 1_6 3 3__1_ Isola tion _ -._.. --. -. _ 0 Every Three Months Each Refueling Outage 100 Yes. Note 40 _E21 f0G3A 2 C 12" Cheth F-9 H-16331 Core Spray Fump Dischar9e C Note 30 N/A tes q-Core Spray Pump Discharge C Note 30 N/A Yes _E21-F0038, 2 _1_2.. ( hec k..F _l _l._H _16 331_.- _ C l _E & F004 1 H_ 10* M0_ Ga te E-7 H-16331 Core Spaay Outboard Injection 0 Every Three Months N/A 50 M E21-f0048. It B 10" M0 Ga te B-7 H-16331 Core Spray Outboard injection 0 Every Three Months N/A 50 ho I E H 0giA } A 10" M0 Gate E-6 H-16331 Core Spray Outboard Containment Isolation C Every Three M)nths Each Refueling Ou: age 50 No. Note 33 I _ E_2_1..f.ri_nB.... i1. } A 1_0". _M_0 G_a t.e 8_-.6 H-16331 _ Core Spray Outt.oard Containment isola tion _C_ Every Three Hinths Each Refueling Outage 5_0_._. g No. Note 38 l E 21 - F 0fRA 1 AC 10" A0 Chett D-4 H-16331 Core Spray injection C Cold Shutdimn Each Refueling Outage Ves. f.c:e 22 1 ) C-4 H-16331 .. _ _C_l a' _AO._( M_ _k Core Spray injection C Cold Shutdows. Each Refueling Outaae Ves. 'ac te 2e__ _ . _ 2_1._. f.00. e. e [ l l {2" Relief D-9 H-16331 Core Spray Pump Discharge Relief C Note 3 N/A No. Note 19 .E l.l_- F 012_ A. _ ; g C 7 t [21-f0128 2 C 2" Relief B-9 H-16331 Core Spray Puu, Discharge Relief C Nete 3 N/A No. ' sole 19 ,u N 6-12 Amenter.t 14/ 79 OW N

TABLE 4 Wf' ~ INSERVICE INSPECT 60N VALVE TEST PLAN ASME CODE CLASS 1.2. AND 3 VALVES ,sp l d< -. . [...... is

g; g '7,--

- - - - -,,;g "' ~~~- .s.... n.n... m... 3 g g o Core Spray Test Bypass Contairant E?l-folS4 2 A 10' MD Glate 0-3 H-16331 Isolation t. Every Three Months Each Ref ueling Outage 54 Ves. Note 40 l I i Core Spray Test Bypass Containir'ent l E21-f0158 2 A 10" MO Glota: C-8 H.16331 Isolation C Every Three Hmths Each Refueling Outage 54 Yes. Note 40 20" A0 l E?l-l019A 2 B Butterfly J-6 H-16331 Core Spray Pump Torus Suction 0 Every Three M)nths N/A 22 No 20" A0 E21-F013S 2 B Butterfly k-6 H-16331 Core Spray Pump forus Suction 0 Every Three Hinths N/A 22 No E21-I03lA 2 8 3" M0 fate F-9 H-16331 ' Core Spray Pump Minimum flow 0 Every Three Months N/A 20 No E 21-F031B 2 B 3" MO Gate F-10 H-16331 Core Spray Pump Minimum Flow 0 Every Three Hunths N/A 20 No Core Spray Test Line - Containment E 21 -F 03t,A 2 AC 3" Check E-9 H-16331 Isolation C N/A N/A Yes. Note 21 ? I Core Spray Test Line - Containment N/A V es. Note 21 _f_21 - F03t>B._ _AC 3_"_C_he_c_k _ _ E__1_0_H.1 _6331_ Isolation _C ___. N/A __-. _ _ _ _ _ _,,i 2 e 641-F001 2 B 10" M0 Gate E-12 H-16332 HPCI Steam Supply Shutoff C Every Three Months N/A 50 Na o Note 39 l E41-F002 1 A 10" M) Gate C-2 H-16332 HPCI steam Supply Inboard Isolaticn 0 Every Three Months Each Refueling Outage 50 Yes. Note 14 ]I E41-f003 1 A 10" M) ba t e C-4 H-16332 HPCI Steam Supply Outtoard Isolation 0 Every Three M2nths Each Refueling Outage 50 Yes. %vte 39 g l1 P o,em Peo 9 79) Amendment 14/79 6-13 N L.y LN N CD LN

I TABLE 4 BNSERVICE INSPECTION VALVE TEST PLAN MU' 08 ASME CODE CLASS 1,2, AND 3 VALVES U-1 ' l. 4 4 ,l . 7% 1.,~ ','.T*.T j,4'! " " ' " ~ li .'lf;nll;ft,% !j~$ Ej e w.o n- _ _ _ _4J ~ ,__4...__.._ 2 E41 F004 2 B 16" N0 Gate 0-9 H-16332 NEj Pump Suction from Condensate Storane O Every Three Months N/A 60 No E41-F005 2 C 14" Check F-6 H-16332 HPCI Pump Discharge C Note 31 H/A Yes $0 Note 38 E41-F006 2 A 14" M0 Gate E-5 H-16332 HPCI Pump inboard Discharge isotation C Cold Shutdown Each Refueling Outage No. Note 51 Yes. Note 39 E41-F001 2 B 14" PO Ga te E-6 H-16332 HPCI Pump Outboard Discharge O Cold 5hutdown N/A Note 51 Every Three Pbnths E41-f008 2 A 10" M) G1ch D-? H-16332 HPCI Pump Test Bypass ! solation C (Note 46) Lach Refueling Outage Yes. Note 40 i HPCI Pin p Redundant Shutof f to Condensate Every Three Ptnths E41.F011 2 8 [0* M) Ca te C-7 H-16332 itgry. C N/A 60 No Every Three Months E41-F012 2 A 4" M0 Ca te F-7_ H-16332 Hgl Pump Minimum Flow Inboti__hglation C (Note 47) Each Refueling Outage Yes. Note 10 d E41-f019 2 16" Check 0- 9 H-16332 HPCI Pump Suction from Condensate Storage C Note 31 N/A Yes 12" Stop Note a0 l E41-F021 2 AC Check G-3 Pj-16332 HPCI Turbine Exhaust-Inboard Isolation 0 Note 31 Each Refueling Outage Yes. Note 16 - 2* Stop N te 40 E41 F022 2 AC Check G-4 H-lh3JL ilPCLIurbine Inhau:1 Drain-1grn hgljlig,n 0 Note 31 Each Refueling Outage Ves. Note 16 2* A0 E41-F035 2 B EV G-8 H-163))_ HPCI Turtine tube Oil Cooling C Note 9 N/A No Every Three Months E41-F040 2 3 l' Mc h G-5 H-16332 HPCI Turbine Exhaust Drafn-Torus isolation C (Note 31) Each Refueling Outage Yes. Note 43 Eal-TC41 2 B J6" MD Cate D-8 H-16332 HPCI Pump Suction Shutoff C Every Three Ptnths N/A 70 No i TN ) E41-F042 2 A Jk" MQ_ Ggt

J-5 H-16332 HPCI Punp Suction Torus Outboard Isolation C

Every Three Months Each Refueling Outage 10 Ves. Note a3 bJ L.-J E41.F045 2 C 16" Check J-7 H-16332 HPCi Pump Suction C Note 31 N/A _ Yes Every Three Months E41-F046 2 AC 4" Check F-8 H-16332 HPCI Pump Minimum Flow Outboard Isolation C (Note 31) Each Refueling Cutage Tel. Note 40 CD . - ~..,n C 6-14 A*endment 14/19 A

TABLE 4 N 24 INSERvlCE INSPECT 60N VALVE TEST PL AN set E T 08 ASME CODE CLASS 1,2 AND 3 VALVES J?J.!!. [.I,I aMOU.c,=

3 nI<.%

IIENeDEr i Every Three Months E41-f049 2 AC 20" Check G-4 H-16332 HPfl Turbine Exhaust Outboard Isolation C (Note 31) Each Refueling Outage No I 16* A0 E41-F051 2 A Butterfly J-4 H-16332 HPCI Pump Suction Torus Inboard Isolation 0 Every Three Months Each Refueling Outage 16 Yes. Note 10 E41-F059 2 0 2* M0 Globe F-8 H-16333 HPCI Turt,ine tube Oil Cooling C Every Three Months N/A 11 No HPCI Vacuum Relief Outbuard Torus E41-F164 2 A 2* N0 Gat' G-3 H-16332 Isolation 0 Every Three Months Each Refueling Outage 20 Ves. Note 4P HPCI Vacuum Relief Inboard Torus Yes. Note 40 E41-fill 2 A 2* M0 Gate G-2 H-16332 Isolation 0 Fvery Three Months Each Refueling Outage 20 Note 10 10" Stop Yes. Note 40 E51-F001 2 AC Chec k G-5 H-16334 RCIC Turbine Eshaust to forus Isolation C Every Three Hunths Each Refueling Outage Note 16 -4 I 2* Stop RCIC Vacuum Pump Discharje to Torus Yes. Note 40 E 51-F002 2 AC Check G-6 H-16334 Isolation C Every Three Months Each Refueling Outage Note 16 6" A0 Yes. Note 40 E51-F003 2 A Butterfly J-6 H-16334 RCIC Pump Suction - Torus isolation 0 Every Three Months Each Refueling Outage 5 Note 14 I Yes. Note 39 E51.F001 1 A 4" M) Gate C-5 M-16334 RCIC Steam Supply Inboard Isolation 0 Every Three Months Each Refueling Outage 20 Note 10 E51.F008 i A 4" M0 Gate C-6 H-16334 RCIC Steam supply Outhoard Isolation 0 Every Three Months Each Refueling Outage 20 Yes. Note 39 E 51-F013 2 A 4" M0 Gate E-6 H-16334 RCic Feedwater Injection C Every Three Months Each Refueling Outage 20 No. hote 38 Every Tnree ibnths Yes. Note 40 E51-F019 21 A 2* M0 Globe F-T H-16334 RCIC Pung Minimum Flow-Torus isolation C Each Refueling Outage 5 Note 10 l _ Every Three Months E51-F021 2' AC ;2" Check F-8 H-16334 RCIC Pump Minimum Flow-Torus isolation C (Note 33) Each Refueling Outage Yes. Note 40 6-15 Amendwnt 14/79 h) La L. J N C3 O LJ1

. i . k I TABLE 4 Ib 08 sMEI INSERVICE INSPECTION VALVE TEST PLAN l ASME CODE CLASS 1.2. ANO 3 V ALVES l d$g lh ' ,$l,< Mfgg. t . d*2.' T.'.".T on* L .* *'l, % v-mm _ _li "~a I-RCIC Vacuum Pump Olscharge-Torus Every Three Months AC '2* Check G-7 H-16334 Isolation C (Note 33) Each Refueling Outage Ves. Note 40 f2 E51-F 028 I t E51-f031

2. A 6" MO Ga te J-6 H-16334 RCIC Pump Suction-Torus isolation 0

Every Three Months Each Refueling Outage 35 Yes. Note 43 Every Three Months (51.F040 2 AC l0* Check G-5 H-16334 RCIC Turbine Exhaust-Torus isolation C (Note 33) fach Refueling Outage Yes. Note 40 I 'l-1/2" PO A I ate G-5 H-16334 RCIC Vacuum Breaker-Torus isolation 0 Every Three Ptanths Each Refueling Datage 25 Ves. Note 40 E51-F104 2 G Note 40 l !1-1/2* pt) G G-5 H-16334 RCIC Vacuum Breaker-Torus Isolation 0 Esery Three m nths Each Refueling Outage 25 Ves. Note 10 E51-F105 2 A 4 ate A 3" A0 Gate B-3 H-16176 Drywell Floor Drains-Containment Isolation 0 Every Three Months ___Each Refueling Outage Ves. Note 40 2_t G11-f003 15 Yes. Note 40 B-3 H-16176 Drywell Floor Drs;ns-Containment Isolation 0 Every Three Pbnths Each Refueling Outage {3"A0 Gate Gil-f004 2 I ^ Containment Gil-F019 2 A 3" A0 Cate E-3 H-16176 Drywell Equipment Drains - Isolation 0 Every Three Hunths Each Refueling Outage 15 Yes. Note 40 1 Containment G11-f020 2 A 3" A0 Gate E-4 H-? 6176 Drywell Equipnent Drains - Isolation 0 Every Three Months Each Refueling Oatage 15 Yes. Note 40 G31-f001 1 A 6* M0 Gate B-2 H-16188 RWCU Pump Suction-Inteard Isolation 0 Every Three Months Each Refueling Outage 30 Yes. hote 39 G31-f 004 1 A 6* M0 Cate B-3 H.15188 RWCU Pump Suction-Outboard Isolation 0 Every it.ree Months Each Refueling Outage 30 Yes. Note 39 Yes. Note 39 G31-F039 1 a 4" (heck A-5 H-16188 RWCU Discharge isolation 0 Each Refueling Outage Each Refaeling Outage Note 2 6* Manual N/A M 10 Skinw.er Surge Tark 0 Every Three Months, rf_l-F009A l 3 _B Butterfly ' D il H-16002 FPCCU Discharge 6* N nual l U Skirmer Surge Tank 0 Every Three Months N/A l

No G41-F0098 3

B l Butterfly 011 H-16002 FPCCU Discharge N. A"'nd"'"t I 4/I9 (,.a 6-16 La N O< Ch

TABLE 4 16 24 4NSERVICE INSPECTION VALVE TEST PLAN 'd" ASME CODE CLASS 1.2. AND 3 VALVES n'.~a:l }l, d *l d m LTW ~~ ;~;;; ^ ~,,, _, fh 5 ' M?w 's 3 6* Mariual G41-F0024 3 B Butterfly __ F-2 H-16002 FFClu Pump Suction 0 Every Three Hmths NLA M 6" Manual G41-F0028 3 8 Butterfly _ H-2 _H-16002 ]CCU_PumpSuctioa Every lhree Months N/ A _ _ _ _h _ O 6* N nua l (Al-Ful94 3 8 Gate 0-9IH-16002 F PCCU Inlet from RHR C Every Three Months Nf_4 No 6* Manual G41-F0196 3 B Gate D-9 H-16002 FPCCU Inlet imm RHR C Every Three Months N/A g _ _ _No_ 6" Manual . G.41 F 020A _ 3 . El _ Ga ty _ _ _D-l 11_16002 _{_PLg_l Mturn to RNR Every Three n>nths N/A N3 C 1 G41-{0200 3 . B_ Ga t,e _ _ D _I f', h;16002_ 6" Manual FP_CCU Return to,RHH _ Every Three_ Months _ _ N/ A C 2* Manual P21-F353 2 AE Gate F-7 H.lur .elizer Water-Contairment Isolation tt Note 53 r,ch pefueling O dage Yes. Note 40 2* Marusal _Pil-F406 _ _2 AE Ga te i Demt..cralizer Water-Containnent Isolation LC Note 53 Each Refueling Outage Yes. Note ' l' B-4l_h-16276_Hy & Og Analyzer Containnent Isolation 0 Eve y Three Months Each Refueling Outa2e 5 Yes. A te 40 ' P33-F002 2 A Control 1" A0 i P33-f003 2 A Contml D-4 H-16276 Hg_& Og Analyzer Containment Isolation 0 Ev m Three H>nths Each Refuelin2.0u__ tar 5 Yes. Note 40 I l' A0 P33-F004 2 A Control E-4 H-16276 H2 &02 Analyzer Containment Isolation 0 Every Three K>nths Each Refuelin1 0utaae Ves. Note 4 I" A0 _P13-[00_b. _2 A Control G-4 H-16276 Hg & Oy Analyzer Containment Isolation O_ Every Three Months Each Refueling Oqtagt 5 Yes. Note G l' A0 l2 A Contr.q ___ H-4 H-16276 H2 & Og Analyzer Containnent Isolation 0 Every Thre. N nths f ach Refdngjutage 5 Yei Note 4C Pil-f007 g 6-17 Amndmert 1 4 79 f N (>J L.4 N CD sc N

TA6LE 4 II ,d_ INSERVICE INSPECTION VALVE TEST PLAN sm a t. ASME CODE CLASS 1.2. AND 3 VALVES u. u f, p m.,c,;;fl""7 j;j x.n, .. =,

r. 2..w,:
1" A0 P31-F010 2

A IControl B _8, H-16276_ If2 A 0; Analyzer rontairnent Isolation 0 Every Three Months (ach Refueling Outage 5 Yes. Feate 40

1" A0 P13-I0ll 2

A Control L-5 H.16276 H2 &07 nalyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 Yes. Nate 40 A 1" A0 P33-1012 2 A Control f-5 H-16276 Hg,102 Analyzer Conta f rnent Isolation 0 Every Theee Months [ath Refueling Outage 5 Ves. Note 40 1" A0 P 3 3-F 014 2 A Control _ G-5 H_.16276 H2 & Og Analyzer Contairenent Isolation 0 [very Three Pbnths Each Refueling Outage 5 Yes. Note 40 I" A0 P33-f015 2 A Contrul H-5 H-16276 'H2 &02 Analyzer Contatnment Isolat te,i 0 Every Three Months Each Refueling Outage 5 Yes. Note 40 P41-F023A 3 C 2" Ched A-10 H-160ll CR0 Pug Room Cooler 0 Note 32 N/A Yes P41 f023ti 3 C 2" Check B-10 H-16011 CRD Pump Roran Cooler 0 Note 32 N/A Yes 1-1/2" Check 8-8 H-160ll HPCI Pump Roosn Cooler C Note 18 h/A Ye> P41 f024A 3 C l - 1/ 2" F41-f024tl 3 C Ched C-8 H-160ll HPCI Pug Room Cooler C Note 18 N/A Yes P41-F025A 3 C 3" Ched D-8 H-160ll RHR and CS Pump Room Cooler C Note 34 N/A Yes -f/ /tB. 3 l P41 C 3" Check D-8 H-160ll RHR and CS Pump Rocen Cooler C Note 34 N/A Yes p.. 4 4 ~~t---..--_.--___---

l._

i l l I f-Pa.-F026Al 3 C i 3" thed G-7 H-16011 RHR Pump Cooler C Note 34 N/A Yes - -. 7 l P44-F02tB 3 C 3" Ched G-1 H-160ll RHR Pump Cooler C Mote 34 l N/A ies b .-__.-----L_-' __.._______1.-._ . _ ~ LM t>- 18 At a-ridimen t 1 4/19 (N N C.3 x0 CO

I INSE RVICE INSPECTaON VALVE T EST PL AN see a 1 a ASME CODE CL ASS 1.2. AND 3 VALVES f I ..,.l.. a;;'s J1 +. t.l - fY? Y -;,_3---- 71:l., + . l: ;, : n~ c -.~ _.,.___....___L_. l-1/2" l F41-f028A 3 t Ched G-2 H-160ll RCIC Pump Room Cooler C Note 35 i N/A j - Yes l l-1/2" I I P41-F0288 3 C Ct.ed G-3 H-160ll RCIC Pung. Room Cooler L Note 35 N/A i-Ves 1 P41-F035A 3 B 2" A0 Glot*..B.-9 H..16011 - CI Pump Room Cool.er . _ -.ho.t._e.41 N/A_. _. - _.. -.is HP. C 4' e i -P41-f0350 - _3 8 2" A0 Glot,e C-9 H-100l. i.. -HFCI Pump Room Coole.r. _..Nott_41_. _..;..., Nc C N/_ A _ _ _] i F41-f0 RA 3 B P A0 610 tee D-9 H-16011 RHR and C5 Pump ~ m Cooler C foote 42 N/A No I 4-- 4 P41-f036B 3 B 3" A0 Glutt D-9 H-1601] RHR and C5 Pump Room Cooler C Note 42 N/A to e 1-1/2" Ad _P41. _.f. 0_3_1A_... _3_ _8_. G_l _otee_ -.._ __ 7 _. H_- 8_ .H_- I f.O. l _l RHR Pump Cooler C Note 44 N/A 40 1-1/2" A0 I P41-F0378 3 B G1ctee j f-9 H-I t.01 L RHR Pump Cooler C Note 44 N/A l-No 1-1/2" AJ P41-f0RC 3 B Glote .j._J-8 H-1001] RHR Pump Cooler i Note 44 N/A Nc 1-1/2" 40 P41-F037D 3 B Glot,e l E-9 H-I t 01 ] RHR Pump Cooler C_ __ __ Note _44_ __,_ N/A ___ _}) _ j l i ? [ l 6 4 l l g I. I l 1 ,m .ie. = -e-- ..m --_--w-m -.+e_..-w.-. e-se..w.e m -e -4..+ e i r'J {. i t i 'J i l 1 ColM ndTrI k 4((J o CW

TABL E 4 18 "' 24 INSLF4VICE INSPECTION VALVE TEST Pt AN "8' ASME CODE CLASS 1.2. AND 3 VALVES lP ?Oo 4c."'t ..I,..*. p;a ..s.... j a, b,' M-l.*.' ' " 7.".r. *l .~ u. ..a -n n p P4).F 6 A 3 B 3' A0 Glot>e G-B H-16011 RHR Pung Cooler C Nte 42 N/A No P41-F03s 3 _3 B 3" A0 Glot.e G-8 H-I tall i RHR Puup (noler C Nte 42 N/A E i 6 _5-41 -F w;i 4 3 B 2" A0 Glut.e H-2 H-I tAlll RCIC Pung Room Cooler C Note 43 NA M i P41-604'B 3 8 2" A0 Glot>e H-3 H-l&)ll RCIC Pump Room Cooler C hte 43 N/A No F41.F642A 3 8_ 3"_ A0 Glot;e A-ly H -I t,0_I l (RD Pung Room Cooler 0 Note 32 _ _ _ NfA No 1 F41 -F 042B 3 8 3* A0 Glot,e B-10 H-16011 CRD Puny Room Cooler 0 Note 32 _ _ _ N/A M P41-F049 2 A 8" M0 Gate F-6 H-160!! 0 Note 52 Yes. Note 40 Drywell Air Coolers _ Isolation _ _.. _ _ _ _ _ Each kefueling Outage 55 Note 24 P41.F050 2 A 8" MG Gate D-2 H-16011 Drywell Air Coolers-Isolation 0 Note 52 fach Refueling Outage 55 Note 24 Yes. Note 40 F41-F064 3 0 6" Check F-10 H-16011 Division I Supply 0 Note 36 N/A No P41 3 C 8 G-10 H 16011 ____ -F065 -___._ _" Check.. _ - Division II supply 0 Note 37 N/A No t-- 7 Every Three Months p 3 b '3* A0 PCV D-Il001 Service Water fressure Pegulator C _ J No te 9) __ h _ _ N/ A l-No _ 4 h f ggaA_ 4 i I j Every Three Months FJI-F204_ _ 3 B 3*A0PO .D-11001 5 l - Segt e W te@ essure Regulator C (Note 9) _ __P.f A No p 1 l r Au PCV D-11001 Service Water Pr essure Regula tor C{ (Nore 9) 7./ 4 N Every Three Months f F ! t - F fMC _[ 3} B i u I Every Three N nt% P41.F 2 gy _ [ 3 0 3" A0 KV D-11001 Service Water Pressttre_ Regulator C (Note 9L N/A No 30" MO ti lote Ves. Note 52 l1 P41-F 310 A 3 8 Butterfly D-11001 Tuf t ne CyQJjn2 5.upply_5_hutof(_____ 0 Col d hutJuwn_ _ __ _ N/A 27_ Note 24 ~ C 30* MO 'ote Yes. Note 52 ]l C y l.Fsics 3 B Butterfly D-Il001 Turbine Building Supply Shutoff 0 Col <f Shutdown NLf. 27 hte 24 ..~..m 6-19 Amen &ent 14H3

e 1ABLE 4 19 24 INSE RVICE INSPECTION VALVE TEST PLAN SWI O' ASME CODE CLASS 1.2. AND 3 VALVES .!'4.'. f )[. onWJhca. ATieT oE%

h

N***** ,,,,,c,,,y,,, ,,, m, 30* PO Note Tes. Note 52 i P41-F310C 3 8 Butterfly D-11001 Turbine Building Supply Shutoff 0 Cold shutdown N/A 27 Note 24 4te Yes. Note 52 30" MO P41-F3100 3 8 Butterfly D-11001 Turbine Butiding Supply shutoff 0 Cold Shutdown N/A 27 No te 24 l l' l Every Three Naths P41-LOO 3A 3 B Sagenoid D-11001 Service Water Pump - Coo 149 shutoff C (Note 48) N/A No l' Every Three Months P41-L0038 3 0 Solenoid D-11001 Service Water Pump - Coolin2 hutoff C (Note 48) N/A No S 1* Every Three Months 3 P41-LOO 3C 3 8 Solenoid D.11001 Service Water Pumg - Cooling shutoff C (Note 48) N/A No I l-Every Three Months P41-LOO 3D 3 8 Solenoid D-11001 Service Water Pump - Cooling shutof f C (Note 48) N/A No _.. -. _ IL*1CCW to Rectrculation Pug Containment Yes. Nota 40 P42-F051 2 A 4" N0 Gate 8-9 H-16009 Isolation 0 Full-Cold shut. Each Refueling Outage 35 No. Note 52_ R8CCW to Recirculation Pump Containment I'5* "Ot" 40 P42-F052 2 A 4* MD Gate E-9 H-16009 Isolation 0 Full-Cold Shut. Each Refueling Outage 35 No. Note M _ 2* Manual F51-f 513 2 AE Globe F-3 H-16013 Serylce Air Contafewnt Isolation LC Note 53 Each Refueling Outage TES. NOTE 40 2" Manual P51-f 514 2 AE clode p.3 H-16013 5ervice Air Contalnn nt Isolattun LC Note 53 Each Refueling Outage Y[5. NOTE 40 . - =. o r.. 6-20 AnenJnent 3 4/19 i I I'd t,a L.4 a N

T ABL E 4 INSEHVICE INSPECTION VALVE TEST PLAN 5'" L 1 W ASME CODE CLASS 1.2. AND 3 VALVES Igf f s. v.a.- 2( I,,, t .e .....a..,a ....&.n .s..e.s.e. %.,m. t .g 9 g ~ ms,.. s l' A0 Ves. Note 4J P/0-f002_,_ 2 (_ (g nt rp]_ _. _I-8 H -l MM. Drywell Pneumatic Containment Isolation 0 Every Three N nths Each Refueling Outage 5 1" A0 Ves. Note 40 !99-f99)_ 2 A_ _ [qntrgl F-8 H-162P6 Drywell Pneumatic Containment Isolation 0 Every Three Months Each Refueling bo' age 5 2" A0 Ves, hote 40 F/0-f M4 2 A [gnirg). .(-H H-162tQ_,Drywell Pneuma tic Containment Isolation 0 Every Three Nnths Each Refueling Outage 2" A0 Ves. Note 40 Plo-FuoS 2 A Ccntr ol D-8 H-16286 Drywell Pneumatic Containmerit Isola tion 0 E very Three M)nths Each Refueling Outage 5 Note 2 P hh f 020 ? A,C 2" (hect.. _ (-l_ H-]b?86_ ' Orywell Pneumatic Contalennent Isolation 0 Each Petueling Outage Each Refueling Outage Yes. Note 40 18" A0 T46-f001A .} S Butte;rfly (-]. H-10020 Filter Bed inlet from Reactor Building C. Every lhree Months N/A No 18" A0 1 14h-f0018 .J B Butterfly _G-1 !!-16020 Filter hed Inlet from Reactor Building C Every Three Months N/A No b" A0 .141-f l 03 .7 Butterfly _ f-Z lhlh000_ grywell__ & _ Torus supply - Isolation C Every Three Hinths Each Refueling Outage 5 Ves. Note 40 1" A0 fl.-F104 2 A Contrgl _. _G-4 H-16000_ _Drywell & Torus Makeup-Outboard Isolation C Every Three Nnths Each Refueling Outage 5 Ves. Note 40 2" A0 T3 -fll}. 2 A CQf)tr91_ El. !bl001t Dgywell Inerting Outboard Isolation C Every Three Months Each Refueling Outage 5 Yes. hote 40 Ves. Nute 40 l 2" A0 14-fils _2.A_ Control _ _ha 11 :16000. ArMil Inerting Inboard Isolation C Every three n>nths tach Refueling Outage 5 2" A0 T4htils 2 A Control _ . G-1 11-16000_ Torus Inerting Outboard Isolation C Every_Three Months Each Refueling Outage Ves. Nate 40 2" AG - 11 6 LA._ _Cuntml fc.d IL:.lt!ML..hrys inertingyboard Isolation C Every Three M)nths j_Each Refueling Outaqej 5 Yes. Note 40 6-21 Are nkent 1 4/ D bJ U N N

6 L I I 1ABLE 4 21 $'4 INSERVICE INSPECTION VALVE T[ST PLAN AFA4E CODE CLASS 1.2, AND 3 VALVES f I ,,,,,,,,,,, ', ', " ' " ~ !N #v.nu.iit: ! j I j! I ..ca.:!. era n:A =. -L i c_ 1* Yes. Note 47 i T48.fil84 2 A_ Solenoid G-5 H-16000 Torus Makeup Inboard Isolation 0 Every Three Months Each Refueling Outage 5 1" Yes. Note !! 148-F1168 2 A Solenoid G-5 H-16000 Torus Makeup inboard Isolation 0 Every Three Nnths Each Refueling Outage 5 2* A0 T48.F32) 2 A Centrol J-7 H-16000 Drywell Inerting Outboard Isolation C Every Three Months Each Refueling Outage 5 Yes. Note SI I 2* A0 _2 _A Control J-8 H-lb000 Drywell inerting Inboard Isolation C Every Three Nnths Each Refueling Outage 5 Yes. Note 43 g 148 F322 t 2" A0 148-F325 2 A Control H-7 H-16000 Torus Inerting Outboard Isolation C Esery Three Months Each Refueling Outage 5 Ves. Note s(* l 2* AG T48-F327 2_ _ A_ Contrul H-8 H-16000 Torus inerting Inboard Isolation C Every Three Manths Each Refueling Outage, 5 Yes. Note 40 I i Note 53

18" A0 148-F307 2_

A_ Butterfly C-9 H-16024 Drywell Purge Inlet-Inboard Isolation C Mone' Each Refueling Outa2'_ Yes. hote 40 m te 53 18" A0 Yes. Note 4ej T48-F308 2 A Butterfly C-10 H-16024 Drywell Purge Inlet-Gutboard Isolation C None Each Refueling Outage 2 Note 53 l 18" A0 T48-F309 2 A Butterfly E-10 H-16024 Torus Purge inlet-Inboard Isolation C None Each Refueling Outage Ves. Not_e a0 i Note 20" A0 148-F310 2 A Butterfly F-10 H-16024 Torus Purge Vacuuta Br. taker Isolation C [very Three N nths Each Refueling Outage _ { Yes. Note 40 ? 20" A0 Note 148-F311 2 A Butterfly F-9 H-16024 Torus Purge Vacuum Breaker Isolation C Every Three Months Each Refue11pq Outage 27 Yes. Note 40 18* A0 T43-F318 2 A Butterfly G-4 H-16024 Torus Purge Outlet-Inboard Isolation 0 Every Three N nths Each Refueling Outage _ 5 Ves. Note 40 Hote 5? 18" A0 T4tt-F 319 2 A Butterfly D-4 11-16024 Drywell Purge Outlet-Inboard Isolation C None Each Refueling Outage Yes. hnte 40 .. ~..... N 6-22 Amendment I oli* A 'A N 'A

i .i l TA8tC 4 8 INSEflVICE INSPECTION VALVE TEST PLAN s*4 E t 08 ASME CODE CLASS 1.2. AND 3 VALVES g !!.,');. Q,! fi$ un s*.*df.o ' 'T*.4' .J.% ., !?. e _,yl,',7*ll,*,' p,78,,__ t nac ma I 18" Aa ibte 53 T48-F320 2 A Butterfly D-3 H-16024 Drywell Purge Outlet-Outtoard Isolation C None Each Refuellng Outage Yes, hote 40 lI 18* A0 I 148-F323A 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Nath N/A No 18* A0 141-F1238 2 C Chec k H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Nath N/A No 18* A0 T48-F323C 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per m ath N/A No 18* A0 i 148-F3230 2 C Chec k H-8 H-16024 { D' ywell to Torus Vacuum Breaker C Or.ce Per m ath n/A No r 18* A0 T48-F323E 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Pbnth R/A No r 18* A0 T43-F323F 2 C_ Chec k H-8 H-16024 Dg well to Torus Vacuum Breaker C Once Per Pbnth N/A ho 18" A0 T43-F323G 2 C Check H-8 H-16024 M il to Torus Vacuum Breaker C Once Per Pbath h/A No 18" A0 T43-f32TI 2 C Check H-8 H-16024 Drpeell ta Torus Vacuum Breaker C Once Per ibnth N/A No 18" A0 T48-F323I 2 C Check H-8 H-16024 Drywell to Torus Vacuse Dreder C Once Per ibnth N/A No 18* A0 T48-F323J 2 C Check H-8 H-16024 Drywell to Torus Vacuum Bre.ber C Once Per Ibnth N/A No 18" A0 T48-F321 2 C Cf.eck H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Pbath N/A ho I 18* A0 T4f ' 2 C iCheck H-8 gi-16024 prywell to Torus Vacuum Breaker C Once Per Month N/A ho 6 23 Anenenent 14/73 N k.' d CN N -4

e e e TABLE 4 INSERV6CE INSPECTION VALVE TEST PLAN WHi 2L o, 24 ASME CODE CLASS 12. AND 3 VALVES J.Ulm f )[. u 7$An. OIR oE% N'* @f eYOU/Mo _ 4 ___ _ 18" A0 Note 53 T48-f 324 2 A Butterfly 0-10 H-16024 Torus Purge Inlet - Outboard Isolation C i4one Each Refueling Outage Ves. Note 40 f 18* A0 T43-F 326 2 A 8utterfly j G-3 H-16024 Torus Purge Outlet - Outboard Isolation 0 Every Three Months Each Refueling Outage 5 Yes. hote 40 20 A0 Reactor Bi.llding to suppression Chamber 148-F328A 2 AC Check g G-10 H-16024 Vacuum Breaker C Every Three Nnths Each Refueling Outage Yes. Note 40 t 20" A0 Reactor 8utiding to Suppression Chanter y8-F3288_. 2 A Check G-9 H-16024 Vacuum Bre46er C Every Three Months Each Refueling Outage Yes. Note 40 _C, 2* A0 l T48-F332A 2 A Control 1 E-3 H-16024 Torus Purge Outlet - Outtioard Isolation C Every Three Ptaths Each Refueling Outage 5 Ves. Note 40 2* A0 _T_4 8__F 3_3 2__8. _ _2 6 F-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Ptinths Each Refueling Outage 5 Yes. Note 40 A Control 2* A0 l 3 T48-F 333A 2 A Con trol , E-4 H-16024 Torus Purge Outlet - Inboard Isolation C Every Three Nnths Each Refueling Outage 5 Yes. Note 40 l 2* A0 t T4b-F3338 2 A Con tml F-4 H-16024 Torus Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 Yes. Note 40 2* A0 g4a.r334A 2 A Control 8-3 H-16024 Drywell Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 Yes. Note 40 2* A0 T43 - F 334.B_ 2_ A_ Control C-3 H-16024 Drywell Purge Outlet - Outboard Isolation C_ Every Three Months Each Refueling Outage 5 Yes. Note 40 2* A0 14a-F33',A 2 A Control B-4 H-16024 Drywell Purge Outlet - Inboard isolation C Every Three Months Each Refueling Outage 5 Yes. Note 40 2* A0 T48-F3358 2 A Control C-4 H-16024 Drywell Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 Ves. Note 4J 2* T48-F13H i 2 iA Solenoid H-2 H-16024 Sypass - Outtw.ard Isolatten C Every Three Nnths Each Refueling Outage 5 Ves. hote 40 N 6-24 Amendment I 4/19 V4 L-a N LTT

e e TABLE 4 a4 t T _ d __ ve N INSEHVICE INSPECTION VALVE TEST PL AN ASME CODE CLASS 1.2. AND 3 VALVES y ';,~n ;.7 p :: =.. _.=_ _.t. . ~:- 7 ::. =.. :. x a.1. T44-F339 l2 A l era; id H-3 H-lbO24 Bypass-Int 4)ard Isolation C Every Three Pt nths Each liefueling Outa.}e 5 Yes. Note 40 1-9__' __5 Yes. Ncte 40 2-l2 A Solenoid D4 H-It024 Bypass-Guttmard Isolation C Every Three Months Each Refueling Outage T44-F340 l 2" .. _- 4__ -16tl24 Bypass-Intx;ard Isolation C Every Thr N nths Each Refueling Outage _5 Ves. Note 41 j.2 0 H A Solenoi1 143-F 341 .7-_ l 1/2" 148-F 342A ' 2 l A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C kte 45 Each Refueling Outage Yes. Mte 40 1/2" T'rus to Drywell Vac Brkr. Isolation C Nte 45 Each Refueling Outage Ves, hote 40 T48-13428 2 A Solenoid H-8 H-16024 o 1/2" T48 f 342C I 2 A Solenoid H-8 H-lCO?4 Torus to Drywell Vac. Brkr. Isolation C Note 45 Each Refueling Outage Yes. Ate 40 1/2" T48-f342D 2 A Solenold H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C Not? 45 fach Refueling Outage Ves. Note 40 g 1/2" T48-F 34?E 2 A Solenoid H-8 H-It.624 Torus to Drywell Yac. Brkr. Isolation C hote 45 Each Refueling Outage Yes. Note 40 l I/2" Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C Note 45 Each Refueling Outage Ves. Nete 40 148-F 342F j 2 4 A t 1/2" T4e-1342G l 2 ' A Solenoid H8 H-16024 Torus to Drywell Vac. Brkr. Isolation C Note 45 Each Refueling Outage Yes. %te 40 1/2" T43-F342H 2 A Solenoid H-e H-It>024 Torus to Drywell Vac. Br kr. Iso.ation C %te 45 l Each Refueling Outage fes. % te 49 1/2" ._ ____ote 45. _ - _ _ E_a_c_h__Re f_ue_ l.i ng O_u_ t_a ge Yes_. _ Note 40 ,H-16024 _C_ N Torus to Drywell Vac. Brkr. Isolation T48-F3421 2 A Solenoid H-b 1/2" Brbr. lC. Ncte 45 Each kefueling Outage, - ves. ikte 40 14o-F142)} 2, E Sol er.o t d H-8 'i 16024 Torus to Drywell Vac.__ I s_ol a t ion.. _ _ _6 -9 1/2" l ~ -_a.-. _e f. ue l _i ng Ou ta ge. Yes. Note 40_-. t ch R A Solenuid IH e C Note 45 IV T48-f 34?k, 2._ ____ ___ _ j.. _,!H-lou 24 Torus to Drywell Va_c. Brkr_. Isolation _ - - - U l I/2~ l'4 T48-F 342L l 2 A Solenoid H-fi,H-16024 Torus to Drywell Vac. Brkr. Isolation C Note 45 Each Refueling Outa.je Yes. Note 40 N Amendnent 14/73 6-25 Os

TABLE 4 NOTES 1. The exercise test is a full-stroke test at the frequency specified unless otherwise noted. 2. This isolation valve is a normally-open simple check valve with flow through it during normal operation. The only means of verifying closure is to introduce reverse flow through the valve and measure the leak-1 age. This verification is performed each refueling during the local leak rate te 's. 3. The test frequency for safety and relief valves is as required by IWV-3510(a). 4. The testing of the standby liquid control explosive-actuated valves will be performed to Technical Speci-fication 4.4.A. This testing exceeds the requirements of IWV-3610. 5. This simple check valve has no safety-related function during a LOCA. It is designed to prevent a water leg from forming in the relief valve discharge line under vacuum conditions. The function is not impor-tant for mitigating the consequences of an accident. Since there is normally no flow through the valve and it is a simple check valve, there is no means to test operability. cn 6. E11-F019 is a normally-closed check valve in the head spray discharge line. Opening of the valve cannot E be verified unless flow is introduced through the line. Flow through this line during normal power oper-ation will not be allowed because of the thermal stresses and reactivity fluctuations that would result as a result of the injection of cold water into the vessel. Therefore, operability of this valve will be verified during the normal head spray operation that precedes cold shutdown. 7. The operability of this normally-closed check valve will be proven every three months during the Standby Liquid Control System pump operability tests. 3

J 8.

Relay logic prevents this valve from opening during normal power operation to safeguard downstream low-L ~J pressure piping. Therefore, it will be tested during a cold shutdown (not to exceed once every three months). N 9. This valve is an air-operated pressure control valve that opens and closes at set pressures. Stroke times ~(( are not applicable for this type valve since the valve is not required to open or close in a specific time. As an alternative, operability will be proven every three months during pump operability tests. s sa ,a $ 10. This containment isolation valve will be leak rate tested in a non-conservative reverse direction as ad-II dressed in the containment leak rate test program for the type C leakage tests. The correct direction is to pressurize from the inboard side of the valve; however, the piping on the inboard side runs directly from the valve to the torus and cannot be pressurized for testing. ~ a

TABL'i4 NOTES Page 2 11. deleted 12. deleted 13. deleted 14. This containment isolation valve will be leak rate tested in a non-conservative reverse direction as ad-dressed in the containment leak rate test program for the type C leakage tests. The correct direction is to pressurize from the inboard side of the valve; however, the piping on the inboard side runs directly from the valve to the reactor (via the main steam lines) and cannot be pressurized for testing. 15. deleted 16. This turbine exhaust isolation valve is a normally-closed stop check valve with the closure mechanism in the " locked open" position. The valve then functions as a simple check valve. The only means to verify positive closure in the " locked open" position is to introduce reverse flow from the inboard side and o3 d3 measure leakage; however, the piping on the inboard side runs directly from the valve to the torus and 'd cannot be pressurized for testing. As an alternative, the valve is closed with the closure mechanism and leak tested from the rever,e side. The leak test, as defined in the containment leak rate test program, is conservative since the test pressure tends to lif t the disc from the seat. 1 17. deleted 18. Proper ilPCI pump room cooler operability is verified every three months during the liPCI pump operability test. Proper cooler operability verifies that proper flow is being obtained through the cooler and the y)

s a check valve has opened.

u 'sa 19. The opening pressure will be determined per the requirements of ASME PTC 25.2-1966. 20. deleted CD C13 f[21. Only closure is required to fulfill the safety function of this check valve; however, since there is no valve between the check valve and the torus, closure cannot be verified by a leak rate test. There are (( no practical means to verify closure of this valve. Sg 22. This testable check valve cannot be opened against reactor pressure using the test switch. Therefore, it will be tested during a cold shutdown (not to exceed once every three months). This test opens the valve approximately 10%. There are no means to fully stroke the valve because flow is never introduced 23 through the valve. so

TABLE 4 NOTES s Page 3 23. deleted 24. Closure of this valve dering normal power operation would interrupt flow to the turbine building equip-ment normally cooled by service water. As an alternative, it will be exercised during a cold shutdown (not to exceed once every three months). 25. Valve B31-F031A(B) is a reactor recirculation loop closure valve. Closure of this valve during normal y power operation would reduce cooling water flow to the core by one-half and pla 2 the plant in an unsafe con-dition. Therefore, it will be tested during a cold shutdown (not to exceed once every three months). 26. This normally-closed Standby Liquid Control check valve cannot be opened without introducing flow through it with a pressure greater than reactor pressure. This is done at least once per operating cycle per Technical Specification 4.4.A during the pump flowrate testing. 27. Daseline stroke times shall be established during the first exercise test for this valve. cn E 28. E11-F068A(B) is a pressure regulating control valve that modulates with changing pressure. This valve does not fully open or close during system operation. Therefore, stroke times are not applicable. Proper system parameters during pump operability tests will verify the valve is functioning correctly. 29. The opening function of this normally-closed check valve will be proven every three months during the RJR pump operability tests. 30. The opening function of this normally closed check valve will be proven every three months during the Core Spray pump operability tests. a I J 31. The opening f unction of this normally-closed check valve will be proven every three months during the HPCI pump operability tests. c_3 gp 32. Proper CRD room temperature is a positive verification that the normally-operating CRD coolers are func-43 g tioning correctly. This verifies that proper flow is being obtained through this valve and that it is gp open. 6 5 33. fhe opening function of this normally-closed check valve will be proven every three months during the RCIC pump operability tests. t

TABLE 4 fl0TES Page 4 34. Proper RHR and Core Spray pump room cooler operability is verified every three months during the RhR dnd the Core Spray Pump operability tests. Proper cooler operability verifies that proper flow is being obtained through the cooler and the check valve is open. 35. Proper RCIC pump room cooler operability is verified every three months during the RCIC pump operability test. Proper cooler operability verifies that proper flow is being obtained through the cooler and the check valve is open. 36. P41-F064 is a normally-open check valve supplying cooling water to the normally-operating CRD pump room cooler and the drywell air coolers. Proper temperatures in these areas verify the valve is functioning correctly. 37. P41-F065 is a normally-open check valve supplying cooling water to the normally-operating reactor recir-culation pump HG set coolers. Proper temperatures in these areas verify the valve is functioning cor-T rectly. 1 N 38. This category "A" valve communicates with the reactor coolant and provides a pressure isolation function. It will be leak tested at the containment accident pressure (59.5 psig) aid the test value extrapolated per the code to a value corresponding to system functional differential pressure. When air is used as the test medium, the test value will be assumed to be water leakage, which builds further conservatism into the test. Limiting leakage values will be determined by the relief valve capacity in the low ^J pressure piping. 4 39. This category "A" valve is a containment isolation valve that communicates with the reactor coolant, but ![j provides no pressure isolation function to protect low pressure piping. Leakage through this valve is not considered to be significant in the pipe break outside containment analysis. Therefore, this valve will be leakage tested per Appendix J criteria only. p C.) 5 5 40. This category "A" valve is a containment isolation valve that communicates only with the containment at-5 mosphere. Therefore, it will be leakage tested per Appendix J criteria only. a rt w

IABLE 4 t NOTES 6 Page S 41. This is an air-operated, normally-closed, fail-open valve supplying cooling water to the HPCI coolers. It has neither manual open/close switches nor position-indicating lights. Actuation is accomplished by the same signal that controls the cooler. Because of the characteristics of an air-operated valve and its method of actuation, a medningful stroke time Cannot he measured. Any failure of the valve actuator will result in the valve going to the open position, which is the safety-related position. As an alternative,llPCI pump room cooler operability is verified every three months during HPCI pump operability tests. Proper cooler operability verifies that proper flow is being obtained and the valve has opened. 42. This is an air-operated, normally-closed, fail-open valve supplying cooling water to the RHR and CS coolers. It has neither manual open/close switches nor position-indicating lights. Actuation is accomplished by the same signal that controls the cooler. Because of the characteristics of an air-operated valve and its method of actuation, a meaningful stroke time cannot be measured. Any failure of the valve actuator will result in the valve going to the open position, which is the safety-related position. As an alternative, RHR and CS pump room cooler operability is verified every three months f during RHR and CS operability pump operability tests. Proper cooler operability verifies that proper g flow is being obtained and the valve has opened. g 43. This is an air-operated, normally-closed, fail-open valve supplying cooling water to the RCIC coolers. It has neither manual open/close switches nor position-indicating lights. Actuation is accomplished by the same signal that controls the cooler. Because of the characteristics of an air-operated valve and its method of actuation, a meaningful stroke time cannot be measured. Any failure of the valve actuator p) will result in the valve going to the open position, which is the safety-related position. As an alter-t, ; native, RCIC pump room cooler operability is verified every three months during RCIC pump operability t,a sa tests. Proper cooler operability verifies that proper flow is being obtained and the valve has opened. 44. This is an air-operated, normally-closed, fail-open valve supplying cooling water to the RHR pump heat exchanger. It has neither manual open/close switches nor position indicating lights. Actuation is ac-comnlished by the same signal that controls the pump. Because of the characteristics of aa air-operated ~ E vc ve and its method of actuation, a meaningful stroke time cannot be measured. Any failure of the valve actuator will result in the valve going to the open position, which is the safety-related position. As an alternative, RHR pump tests are run every three months. Proper operation of the pump verifies it is receiving cooling water through the open valve. o 'A

e 45. This containment-isolation valve is a normally-closed Y' solenoid valve that supplies air to the Torus 'e to Drywell Vacuum Breakers for testing purposes. The operability of this valve is proven each month when the vacuum breaker (T48-F323) is cycled. Stroke times cannot be determined for this valve since 5 it has no indicating lights. 46. E41-F008 is a throttle valve used to test the HPCI pump. Since it does not fully close or open during operation, stroke time measurement does not apply. Operability of this valve is confirmed every three months during pump operability tests. 47. This valve is a minimum flow valve that opens and closes at set pressures. Since it is not required to open or close in a specific time, stroke time measurements do not apply. Operability of this valve is confirmed every three months during pump operability tests. 48. This is a solenoid valve that provides cooling water to the service water pump. It is interlocked with the pump start logic system and does not have indicating lights. Because of the method of actuation y and the lack of indicating lights, stroke times cannot be determined. Proper operation of this valve ti is verified every three months during pump operability tests by praper system parameters. 49. Closure of this valve during normal power operation would interrupt flow to the reactor building equip-ment normally cooled by service water. As an alternative, it will be exercised during a cold shutdown 1 (not to exceed once every three months). 50. Closure of this valve during normal power operation would interrupt cooling water flow to the reactor rx) recirculation pump bearings and cause possible overheating. Therefore, it will be fully-stroked during a LN cold shutdown (not to exceed once every three months) and partially-stroked every 3 months. tw d 51. Valve E41-F007 cannot be closed during normal operation because its failura in the clnsed position would result in the loss of the HPCI system. Valve E41-F006 cannot be opened during normal power operation without first closing E41-F007. Therefore, the operability of E41-F006 and E41-F007 will be demonstrated rs) during a cold shutdown (not to exceed once every three months). jf52. Relief is requested from partially stroking this valve during normal power operation. Because of control circuitry, this valve cannot be partially stroked. Once the valve is given the signal to open or close, it it will go to the fully open or closed, position. As an alternative, it will be full-stroked each cold g shutdown (not to exceed once every three months). "" S3. Exemption is requested from the quarterly stroke requirements of Section XI because this valve is a pas-4 sive containment isolation valve. It is normally closed and does not have to open to perform any safety-Gj related function.

54. Testing during nonnal operation requires removing the associated RHR train from operation due to differen-tial pressure across the valve, thereby decreasing the level of plant reliability. Relief is requested from quarterly stroke requirements; valve would then be tested during refueling outages.

TABl.E 4 NOTFS Paqe 6}}

ML19270G442

Text

1.0 INTRODUCTION

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