ML20128A056

Inservice Insp Program,1980 Edition of ASME Section XI W/Addenda Through Winter 1981

ML20128A056
Person / Time
Site:	Hatch
Issue date:	06/25/1985
From:	GEORGIA POWER CO.
To:
Shared Package
ML20128A035	List: ML20128A033 ML20128A056
References
PROC-850625, NUDOCS 8507020553
Download: ML20128A056 (147)

Text

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EDWIN I. HATCH NUCLEAR PLANT - UNITS 1 AND 2

. _ INSERVICE INSPECTION PROGRAM

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DISTRIBUTION LIST Copy Number Manual Holder 1 - 10 Director of Nuclear Reactor, Regulation - USNRC 11 - 15 Regional Administrator, Office of Inspection and Enforcement USNRC -

Region II 16 Senior Resident Inspector, NRC -

Plant Hatch 17 Manager of Engineering, GPC - Plant Hatch 18 Manager of Quality Assurance, GPC -

Plant Hatch 19 Superintendent of Plant Engineering Services, GPC - Plant Hatch O 20 Superintendent of Regulatory Compliance, GPC - Plant Hatch 21 ISI Engineer, GPC - Plant Hatch 22 Pump and Valve Engineer, GPC - Plant Hatch 23 - 25 Document Control, GPC - Plant Hatch 26 J. A. Edwards, GPC - Atlanta 27 J. R. Jordan, GPC - Atlanta 28 L. B. Long, SCS - Birmingham 29 W. F. Garner, SCS - Birmingham 30, 31 M. Belford, SCS - Birmingham 32 J. M. Agold, SCS - Birmingham 33 J. C. McWhorter, SCS - Birmingham

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34, 35 D. R. Barnes, SCS - Plant Hatch 36 R. A. Milstead, SCS - Birmingham 8507020553 050625 PDR ADOCK 00000321 0 PDR

EDWIN I. HATCH NUCLEAR PLANT - UNITS 1 AND 2 INSERVICE INSPECTION PROGRAM DISTRIBUTION LIST Copy Number Manual Holder 37 R. T. Oedamer, SCS - Birmingham 38 G. A. Lofthus, SCS - Birmingham 39 Superintendent of Quality Control, GPC - Plant Hatch 40 J. M. Davis, SCS - Birmingham O

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TABLE OF CONTENTS

O 1.0 Introduction................................................... 1-1 2.0 Cl as s I wi th Rel i e f Requests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 3.0 C1 ass 2 with Relief Requests................................... 3-1 4.0 Cl as s 3 wi th Rel i ef Reque sts. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 5.0 Cl ass 1, 2, and 3 Supports with Relief Requests. .. . . . . . . . . . . . . . 5-1 6.0 Val ve Testing wi th Relie f Requests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 s

1 7.0 Pump Testi ng wi th Rel ief Requests. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 8.0 General Rel i e f Reques ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8-1 i

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1.0 INTRODUCTION

O i.i ae rai This document describes the revised Inservice Inspection (ISI) Program for l Edwin I. Hatch Nuclear Plant, Units 1 and 2. The previous ISI program submitted for Hatch 1 and 2 by Georgia Power Company letter dated August 12,

1983 was prepared in accordance with the 1980 Edition of the American Society i of Mechanical Engineers (ASE)Section XI with Addenda through Winter 1980.

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This revised ISI program has been upgraded with the intent to meet, as much as

practical, the requirements of the 1980 Edition of Section XI with Addenda

{ through Winter 1981.

1 1.2 Effective Date l The revised ISI progras; shall go into effect on January 1,1986.

1.3 Scope i

This document is a description of the ISI program for Units 1 and 2 of Plant

, Hatch. The programs for Class 1, 2, and 3 component examinations as well as

for pump and valve surveillance testing are included.

l 1.4 Component Upgrading l

All plant components have been reviewed to determine the appropriate lQ i

classification for inservice inspection. Regulatory Guide 1.26 was used for guidance in determining component classifications.

! It must be noted that the classification of components as ASE Class 1, 2, or  :

j 3 equivalent for inservice inspection does not imply that the components were designed in accordance with ASME requirements. The component design codes l remain as stated in the FSAR.

1.5 Subsequent ISI Program Revisions

It is anticipated that this ISI program will be reviewed again near the end of

, 120 months of implementation of this program. At that time, the program will l

be modified as required to bring it into compliance with a later Nuclear l

Regulatory Comission (NRC) approved edition and addenda of ASME Section XI.

l The inservice program for pumps and valves will be similarly reviewed and i modified at that time.

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, 1.6 Responsibility

Georgia Power Company bears the overall responsibility for the performance of l the inservice inspection activities. Certain nondestructive examinations will

be performed by qualified examination agencies. The results of such examinations will be reported to Georgia Power Company for final disposition.

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l 1.7 Records Records and documentation of information and examination results, which O provide the basis for evaluation and which facilitate comparison with results from previous and subsequent examinations, will be maintained and available for the active life of the plant in accordance with Section XI, IWA-6000 with the exception of the due date for the Owner's Data Report for. Inservice Inspection, Fonn NIS-1 (see Paragraph 8.1.5 for Relief Request).

1.8 Methods of Examination The method of examination planned for each area is delineated in subsequent sections. Personnel performing nondestructive examinations will be trained in accordance with the American Society for Nondestructive Testing (ASNT)

"Recosamended Practice SNT-TC-1 A, Supplements and Appendices", as applicable for technique and method used. l 1.8.1 Ultrasonic Examination (UT)

It is anticipated that most volumetric examinations will be performed ultrasonically. Examinations will be conducted in accordance with the raquirements of IWA-2232 of ASME Section XI except as requested by relief.

1.8.2 Radiographic Examination (RT)

Radiographic techniques will be used to supplement UTyhen necessary.

1.8.3 Liquid Penetrant Examination (PT)

Liquid penetrant examinations in accordance with IWA-2222 of LSME Section XI will be performed whenever a surface examination is required on non-magnetic components.

1.8.4 Magnetic Particle Examination (MT)

Magnetic particle testsiin accordance with IWA-2221 of ASME Section XI will be used when surface examination of carbon steel co:nponents is required.

1.8.5 Visual Examination (VT)

Visual examinations in accordance with IWA-2210'of ASME Section XI are divided into four different categories:

,a. VT-1 ,

This examination shall be conducted to determine the condition of the part, component, or surface examined.

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b. YT-2 This examination shall be conducted to locate evidence of leakage from pressure retaining components.

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c. VT-3 This examination shall be conducted to determine the general mechanical and structural condition of components and their supports.

d. VT-4 This examination shall be conducted to determine conditions relating to the operability of components or devices.

1.9 Standards for Examination Evaluation The acceptance standards for Class 1 components will be either IWB-3000 of ASE Section XI or the Section III construction Code for the plant, as applicable.

For Class 2 and 3 components. Articles IWC-3000 and IWD-3000, respectively, are in the course of preparation. Both Articles state that the rules of Article IWB-3000 may be used. Therefore, the acceptance standards for Class 2 and 3 components will be either Article IWB-3000 or the Section III construction Code for the plant.

The acceptance standards for Class 1, 2, and 3 component supports will be either IWF-3000 or the Section III construction Code for the plant, as J applicable.

1.10 Repair Procedures Repairs to the pressure retaining boundary of ASME Class 1, 2, or 3 (equivalent) components will be performed in accordance with Article IWA-4000 utilizing Georgia Power Company approved procedures which generally comply with the Code applicable to the construction of the component. In addition, replacement of components will be performed per Article IWA-7000 of Section XI, to the extent practical.

1.11 Power Operated Valves - Stroke Timing Yalve stroke timing will be performed by measuring the interval between the start and end of valve travel as shown by the remote indicating lights, unless otherwise specified in this program.

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2.0 CLASS 1 WITH RELIEF REQUESTS Table 1 provides a tabulation of the Class 1 pressure-retaining components subject to the inspection requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Yessel Code,1980 Edition with Addenda through Winter 1981. 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 examination. Where relief from the inspection requirements of Subsection IWB is requested, information is provided which identifies the applicable Code requirements, justification for the relief requested, and the examination method to be used as an alternative. Table IWB-2500-1 f tems not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.

Hydrostatic testing will be conducted in a manner that will satisfy the requirements 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., the boundary is a 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 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.

O 2.1 Requests for Relief From ASME Section XI Requirements 2.1.1 Volumetric Examination of Reactor Pressure Vessel and Closure Head Welds 2.1.1.1 Requirement From Which Relief is Requested Item Nos. B1.11, B1.12, Bl.21, and B1.22 of Table IWB-2500-1 of ASME Section XI require the volumetric examination of Reactor Pressure Vessel (RPV) and Closure Head circumferential, longitudinal, and meridional welds. At Hatch, these examinations will be perfonned using ultrasonic techniques. The applicable examination volumes are shown in Figures IWB-2500-1, -2, and -3.

The Code also requires that welds selected for examination are to be examined for essentially 100% of their length. Relief from this requirement is requested.

2.1.1. 2 Justification At Hatch, physical limitations prevent the examination of the entire length of these welds. The 1974 Edition with Addenda through Sumer 1975 and earlier editions of Section XI required that the examination cover at least 10% of the length of each longitudinal weld and 5% of the length of each circumferential weld. For both Hatch units, the minimum lengths described above were met during previous examinations.

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For RPV circumferential and longitudinal welds, physical limitations allow approximately 5 to 15% of the total length of the welds to be examined at O Hatch 1. For Hatch 2 approximately 15% of the total length of the circumferential welds can be examined. The percentages for the twelve longitudinal welds are as follows: six will receive a 100% examination while the remaining six will receive between 30 and 67% examination.

Limitations also exist for the ultrasonic examination of RPY bottom head circumferential and meridional welds. One circumferential weld has been examined (5% of the total length) during an ISI at Hatch 1. Preservice data for Hatch 2 provides the details as to what percentage of these welds can be examined since the designs of the two RPV bottom heads are similar. For the weld described above, 25% of the lower shell to bottom head torus weld length was examined at Hatch 2. For the bottom head torus to bottom head dome weld, 73% of the weld length was examined. The dollar plate weld could not be examined due to inaccessibility caused by the Control Rod Drive housings. For the bottom head torus meridional welds, approximately 18% of the weld lengths were examined. For the bottom head dome meridional welds, approximately 25%

of the weld lengths were examined.

No known limitations exist for the ultrasonic examination of RPV Closure Head circumferential and meridional welds.

2.1.1.3 Testing in Lieu of Section XI Requirements For future examinations of RPV circumferential, longitudinal, and meridional welds, the examinations will be performed to the extent possible as described in the previous paragraphs.

2.1.2 Straight Beam Examination of Reactor Pressure Vessel and Closure Head

! Welds Including Nozzle-to-Vessel Welds 2.1.2.1 Requirement From Which Relief is Requested Subparagraph T-441.4.3 of Article 4 of ASME Section V requires that prior to the angle beam examination, the base material through which the angle beam will travel shall be scanned with a straight beam transducer to detect laminar reflectors which might affect the angle beam results.

2.1.2.2 Justification During the preservice examination at both Hatch 1 and 2, the adjacent base material for the RPV and Closure Head welds, including the Nozzle-t- Yessel welds, were examined with a straight beam transducer and any laminar reflectors which would interfere with the angle beam scans were recorded, i Since the size of these reflectors will not change, it is unnecessary to perfonn the straight beam scans again. Also, these scans would only result in additional radiation exposure without a corresponding benefit in reliability.

2.1. 2. 3 Testing in lieu of Section XI Requirements Other examinations designed to detect service-induced flaws are required by Section XI on these welds.

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2.1. 3 Volumetric Examination of Reactor Pressure Vessel and Closure Head Nozzle-to-Vessel Welds and Nozzle Inside Radius Sections Q

2.1.3.1 Requirement From Which Relief is Requested Item Nos. 83.90 and B3.100 of Table IWB-2500-1 of ASME Section XI require the volumetric examination of RPV and Closure Head Nozzle-to-Vessel welds and Nozzle Inside Radius Sections. The applicable examination volumes are shown in Figures IWB-2500-7(a) through (d). At Hatch, these examinations will be performed using ultrasonic techniques.

2.1.3.2 Justification At Hatch, physical limitations prevent the ultrasonic sound beam from passing through the entire examination volume as shown by Figure IWB-2500-7(a) through (d). At a minimum, eighty-five percent (85%) of the examination volume has ultrasonic sound beams passing through it. Showing the Nozzle-to-Vessel weld as N to V and the Nozzle Inside Radius Section as IRS, the following nozzles can not receive a full-Code examination:

Hatch Unit 1 Nozzle Identification Limited Examinations N2A N to Y N2B N to V N2C N to V O N20 N2E N to v N to V N2F N to Y N2G N to V N2H N to V N2J N to V N2K N to V N48 N to V; IRS N4D N to V; IRS Hatch Unit 2 Nozzle Identification Limited Examinations 2N4A N to V; IRS 2N4C N to V; IRS The nozzles listed above are the only ones with known limitations. Any other examinations where limitations are encountered will have such limitations reviewed and documented.

2.1.3.3 Testing in Lieu of Section XI Requirements Not applicable to this relief request.

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2.1.4 Volumetric Examination of Austenitic and Dissimilar Metal Piping Welds O 2.i.4.i Reouir-nt Fr Which Reiief is Reauested Item Nos. 85.10, B5.50, B9.11, and 89.12 of Table IWB-2500-1 of ASME Section XI require a volumetric and surface examination of austenitic and dissimilar metal piping welds. In addition, Item No. B14.10 of Table IWB-2500-1 requires either a volumetric or a surface examination of the pressure retaining welds in Control Rod Drive (CRD) housings. These volumetric examinations are to be perfonned using ultrasonic techniques in accordance with Paragraph IWA-2232 of Section XI. This paragraph specifies that austenitic and dissimilar metal piping welds are to be examined in accordance with Article 5 of ASME Section V.

2.1.4.2 Justification Article 5 of ASME Section V does not provide the detailed guidance necessary to examine austenitic and dissimilar metal piping welds with the exception of austenitic piping welds which have been repaired by weld overlay. These clad overlaid piping welds will be examined in accordance with Article 5 of Section V and Appendix III of Section XI.

2.1.4.3 Testi.ig in Lieu of Section XI Requirements Since ferritic piping welds will be examined per Appendix III of Section XI and to provide consistency, austenitic and dissimilar metal piping welds will also be examined in accordance with Appendix III.

Surface Examination of Reactor Pressure Vessel Support Skirt Weld Q 2.1.5 2.1.5.1 Requirement From Which Relief is Requested Item No. B8.10 of Table IWB-2500-1 of ASME Section XI requires volumetric or surface (as applicable) examination of integrally welded attachments (support skirt), in accordance with the examination requirements shown on Fig. No.

IWB-2500-13. At both Hatch units these examinations will be performed using either liquid penetrant or magnetic particle techniques.

l 2.1.5.2 Justification At both Hatch units, examination area C-D of Fig No. IWB-2500-13 is not l

accessible for meaningful examination because of location and geometric configuration of welded areas. Physical access by the examiner is also restricted because of high radiation and obstruction due to CRD housings and its support system. The combination of these factors prevents these welds from being examined from inside the support skirt.

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2.1.5.3 Testing in Lieu of Section XI Requirements O E= <-tion area A-B of ris. No. IWB-2500-i3 is compieteiy accessibie and iO0s of area A-B will be surface examined.

2.1.6 Reactor Pressure Yessel Jhzzle to Safe-End Welds (Nominal Pipe Size

<4 Inches) 2.1.6.1 Requirement From Which Relief is Requested Item No. 85.11 of Table IWB-2500-1 of ASME Section XI requires a surface examination of the RPY nozzle-to-safe-end welds with nominal pipe size (4 inches. Relief from this requirement is requested.

2.1.6.2 Justification The nozzle-to-safe-end welds for the nozzles listed below are physically inaccessible for surface examination. The affected nozzles are:

N10 2N10 NilA 2NilA NilB 2NllB N12A 2N12A N12B 2N128 N16A 2N16A N16B 2N168

(] In addition, the 2-inch RPV bottom head drain nozzle-to-safe-end weld at both Hatch units cannot be examined due to inaccessibility. This drain line is surrounded by instrumentation lines and CRD housings which prevent the examiner from performing this examination.

2.1.6.3 Testing in Lieu of Section XI Requirements The nozzle-to-safe-end welds listed above will receive a remote visual examination with the exception of the 2-inch drain nozzle welds. In addition, these nozzles will be pressure tested per IWB-5000 of ASME Section XI since they are located within the hydrostatic test boundary of the Nuclear Steam Supply System.

2.1. 7 Volumetric and Surface Examinations of Pressure Retaining Welds in Piping with Nominal Pipe Size 24 Inches 2.1.7.1 Requirement From Which Relief is Requested Item No. 89.11 of Table IWB-2500-1 of ASME Section XI requires the examination of pressure retaining welds in piping that are located within flued head containment penetration assemblies. These welds and their penetration assembly number for Hatch 1 are listed below. Hatch 2 has no pressure retaining welds in the penetration assemblies.

Weld Identification No. Penetration No.

1821-1FW-l SA-7A X-9A O is2i-iFv-iB8-sA l E51-l RCIC-4-D-20A x-98 X-10 lE41-lHPCI-10-D-15A X-ll 1 Ell-l RHR-208-D-13A X-12 1E11-lRHR-24A-R-3A X-13A 1 Ell-1RHR-248-R-38 X-13B 1G31-lRWCU-6-D-15B X-14 1G31-lRWCU-6-D-15C X-14 1 E21-1CS-10A-3A X-16A 1 E21 -lCS-108-4A X-16B 1E11-lRHR-4-HS-6A X-17 2.1. 7. 2 Justification These welds are inaccessible for examination due to the design of the flued head. All twelve circumferential butt welds, except the two located in the Reactor Water Cleanup (RWCU) penetration, are carbon steel.

The two stainless steel welds that are located in the RWCU penetration were made to replace a Type 304 SS pipe that had undergone IGSCC. The welds involved are a flued head with a Type 308L corrosion resistant clad 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.

2.1.7.3 Testing in Lieu of Section XI Requirements A UT baseline was performed on the two new welds in the RWCU system while they were accessible during repair to ensure a high quality weld.

In accordance with IWB-5221 of ASME Section XI, a system leakage test is to be performed on all 12 welds prior to startup following each reactor refueling outage.

All pipe-to-penetration (flued head) welds outside containment will be examined volumetrically. In addition, a surface examination will be performed on the accessible weld (s) of the flued head penetration assembly.

2.1.8 ASME Class 1 (Equivalent) Valves Exceeding 4-Inches Nominal Pipe Size and ASE Class 1 (Equivalent) Pump Casings 2.1.8.1 Requirement From Which Relief is Requested Table IWB-2500-1 Item No. B12.40 of ASME Section XI requires a visual examination of the internal pressure boundary surfaces of one valve in each l group of valves that are of the same constructional design, such as globe, gate, or check valve, and manufacturing method and that are performing similar functions in the system.

Table IWB-2500-1, Item No. 812.20 of ASME Section XI requires a visual l p examination of the internal pressure boundary surface of one of the two d Reactor Recirculation system pumps.

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i 2.1.8.2 Justification O oisassembir of these vaives aad pumps for the visuai examiaatioa durin9 the inspection interval, in the absence of other required maintenance, represents an unnecessary exposure to radiation and contamination. Valves on the Reactor Recirculation (RC) system and the Residual Heat Removal (RHR) system suction lines would require off-loading the fuel elements and draining the RPV prior to disassembly. Work on the RC system pump discharge valves and the RHR system injection valves would require the installation of plugs in the jet pump risers. Preparatory work of this scope is considered impractical for the sole purpose of conducting a visual examination. Contamination levels in the valves and pumps associated with the RC system loops are particularly high due to the physical location at the bottom of the system. During routine maintenance, the valve body and the pump casing internal surfaces are visually examined. Many of the valves, particularly the containment isolation valves are disassembled for maintenance of leak-tightness. Disassembly of other Class 1 valves and the pumps solely for internal examination is counter to the "ALARA" guidelines to keep the occupational dose rates as low as reasonably achievable. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this Code requirement does not provide sufficient benefits to justify the exposure.

2.1. 8. 3 Testing in Lieu of Section XI Requirements Class 1 pumps and Class 1 valves exceeding four inches nominal pipe size are subject to visual examination of the internal surfaces when disassembled for maintenance. The coverage provided by examinations during routine maintenance coupled with periodic leak tests and hydrostatic tests will provide adequate i assurance of the structural integrity of the Class 1 pumps and valves, while keeping exposure to radiation and contamination as low as reasonably achievable.

2.1.9 Pressure Retaining Welds in Control Rod Drive Housings 2.1. 9.1 Requirement From Which Relief is Requested ,

Table IW8-2500-1, Item No. B14.10 of ASME Section XI requires a volumetric or surface examination of the pressure retaining welds in 10% of the peripheral i Control Rod Drive housings. Each housing has a pipe-to-pipe weld located near the RPV and a pipe-to-flange weld.

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2.1.9.2 Justification The examination of these welds are limited because of the location and design of the housings. Physical accessibility by an examiner is extremely limited by the close proximity of the housings to each other and by the support l arrangement. Also, the insert and withdraw lines to the Control Rod Drive system are connected at the top of the housing flange and limit access to much i of the lower weld. The combination of these factors limit the examination of these welds.

2.1.9.3 Testing in Lieu of Section XI Requirements

O These weids wiii be pressure tested per Iws-so00 of ASME Section x1 since they are located within the hydrostatic test boundary of the Nuclear Steam Supply l system.

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TABLE 1 Sh.1 of 12 1 ISI PROGRAM FOR ASE CLASS 1 COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested 81.11 B-A Reactor Pressure Vessel Circumferential Shell Welds Volumetric Yes, 2.1.1 and 2.1.2 B1.12 B-A Reactor Pressure Vessel Longitudinal Shell Welds Volumetric Yes, 2.1.1 and 2.1. 2 Bl.21 B-A Reactor Pressure Vessel Circumferential Head Welds Volumetric Yes, 2.1.1 and and Closure Head 2.1.2 Bl.22 B-A Reactor Pressure Vessel Meridional Head Welds Volumetric Yes, 2.1.1 and and Closure Head 2.1.2 Bl.30 B-A Reactor Pressure Vessel Shell-to-Flange Weld Volumetric Yes, 2.1.2 i B1.40 B-A Reactor Pressure Vessel Head-to-Flange Weld Surface and Yes, 2.1.2 Closure Head Volumetric Bl.51 B-A Reactor Pressure Vessel Beltline Region Repair Volumetric Not applicable to Welds either Hatch unit B2.10 B-B Pressurizer Shell-to-Head Welds Volumetric Not applicable to either Hatch unit 82.20 B-B Pressurizer Head Welds Volumetric Not applicable to either Hatch unit B2.30 B-B Steam Generator Head Welds Volumetric Not applicable to (Primary Side) either Hatch unit 82.40 B-B Steam Generator . Tubesheet-to-Head Welds Volumetric Not applicable to

(Primary Side) either Hatch unit B2.50 B-B Heat Exchangers Shell or Head Welds Volumetric Not applicable to (Primary Side) either Hatch unit B2.60 B-B Heat Exchangers Tubesheet-to-Shell Volumetric Not applicable to (Primary Side) (or Head) Welds either Hatch unit

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O TABLE 1 Sh. 2 of 12 ISI PROGRAM FOR ASE CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested B3.10 B-D Reactor Pressure Vessel Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit; GPC has elected to perform exami-nations in accor-dance with Program B.

B3.20 B-D Reactor Pressure Vessel Nozzle Inside Radius Section Volumetric Not applicable to either Hatch' unit; GPC has elected to perform exami-nations in accor-dance with Program B.

83.30 B-D Pressurizer Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit B3.40 B-D Pressurizer Nozzle Inside Radius Section Volumetric Not applicable to either Hatch unit B3.50 B-D Steam Generators Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit B3.60 B-D Steam Generators Nozzle Inside Radius Section Volumetric Not applicable to (Primary Side) either Hatch unit B3.70 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit i

O O O TABLE 1 Sh. 3 of 12 ISI PROGRAM FOR ASE CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AM) 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested 83.80 B-D Heat Exchangers Nozzle Inside Radius Section Volumetric Not applicable to (Primary Side) either Hatch unit B3.90 B-D Reactor Pressure Nozzle-to-Vessel Welds Volumetric Yes, 2.1.2 and Vessel 2.1.3 B3.100 B-D Reactor Pressure Nozzle Inside Radius Section Volumetric Yes, 2.1.3 Vessel B3.110 B-D Pressurizer Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit B3.120 B-D Pressurizer Nozzle Inside Radius Section Volumetric Not applicable to

either Hatch unit i

B3.130 B-D Steam Generators Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit B3.140 B-D Steam Generators Nozzle Inside Radius Section Volumetric Not applicable to (Primary Side) either Hatch unit 83.150 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit B3.160 B-D Heat Exchangers Nozzle Inside Radius Section Volumetric Not applicable to (Primary Side) either Hatch unit 84.11 B-E Vessel Nozzles External Surfaces of Vi sual ,VT-2 No Partial Penetration Welds B4.12 B-E Control Rod Drive External Surfaces of Vi sual ,VT-2 No Nozzles Partial Penetration Welds i

B4.13 B-E Instrumentation External Surfaces of Visual,VT-2 No Nozzles Partial Penetration Welds 84.20 B-E Pressurizer External Surfaces of Visual ,VT-2 ' Not applicable to Heater Penetration Welds either Hatch unit

O O O lI TABLE I Sh. 4 of 12 ISI PROGRAM FOR ASE CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AW 2 i Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested B5.10 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface and Yes, 2.1.4 Welds (Nominal Pipe Sizel4f n.) Volumetric B5.20 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface Yes, 2.1.6 Welds (Nominal Pipe Size < 41n.)

B5.30 B-F Reactor Pressure Vessel Nozzle-to-Safe End Surface Not applicable to Socket Welds either Hatch unit B5.40 B-F Pressurizer Nozzle-to-Safe End Butt Welds Surface and Not applicable to (Nominal Pipe Sizel41n.) Volumetric either Hatch unit l

85.50 B-F Pressurizer Nozzle-to-Safe End Butt Welds Surface Not applicable to (Nominal Pipe Size <41n. ) either Hatch unit B5.60 B-F Pressurizer Nozzle-to-Safe End Surface Not applicable to Socket Welds either Hatch unit

B5.70 B-F Steam Generators Nozzle-to-Safe End Butt Welds Surface and Not applicable to (Primary Side) (Nominal Pipe Size 241n.) Volumetric either Hatch unit

! d5.80 B-F Steam Generators Nozzle-to-Safe End Butt Welds Surface Not applicable to

) (Primary Side) (Nominal Pipe Size (41n.) either Hatch unit B5.90 B-F Steam Generators Nozzle-to-Safe End Surface Not applicable to '

(Primary Side) Socket Welds either Hatch unit

B5.100 B-F Heat Exchangers Nozzle-to-Safe End Butt Welds Surface and Not applicable to j (Primary Side) (Nominal Pipe Size 241n.) Volumetric either Hatch unit i

B5.110 B-F Heat Exchangers Nozzle-to-Safe End Butt Welds Surface Not applicable to (Primary Side) (Nominal Pipe Size (41n.) either Hatch unit B5.120 B-F Heat Exchangers Nozzle-to-Safe End Surface Not applicable to (Primary Side) Socket Welds either Hatch unit l 85.130 B-F Piping Dissimilar Butt Welds Surface and Yes, 2.1.4 l (Nominal Pipe Size 241n.) Volumetric

O O O TABLE 1 Sh. 5 of 12 ISI PROGRAM FOR ASE CLASS 1 C0W ONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AM) 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested B5.140 B-F Piping Dissimilar Butt Welds Surface Not applicable to (Nominal Pipe Size <41n.) either Hatch unit B5.150 B-F Piping Dissimilar Metal Socket Surface Not applicable to Welds either Hatch unit B6.10 B-G-1 Reactor Pressure Vessel Closure Head Nuts Surface No B6.20 B-G-1 Reactor Pressure Vessel Closure Studs, in place Volumetric No, See Note 1 B6.30 B-G-1 Reactor Pressure Vessel Closure Studs, when removed Surface and No, See Note 1 Volumetric Bb.40 B-G-1 Reactor Pressure Vessel Threads in Flange Volumetric No B6.50 B-G-1 Reactor Pressure Vessel Closure Washers, Bushings Visual, VT-1 No B6.60 B-G-1 Pressurizer Bolts and Studs Volumetric Not applicable to i

either Hatch unit a B6.70 B-G-1 Pressurizer Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit I

B6.80 B-G-1 Pressurizer Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.90 B-G-1 Steam Generator Bolts and Studs Volumetric Not applicable to l either Hatch unit l B6.100 B-G-1 Steam Generator Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.110 B-G-1 Steam Generator Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.120 B-G-1 Heat Exchangers Bolts and Studs Volumetric Not applicable to

, either Hatch unit l

O O O TABLE 1 Sh. 6 of 12 ISI PROGRAM FOR ASE CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested 86.130 B-G-1 Heat Exchangers Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.140 B-G-1 Heat Exchangers Nuts, Bushing, and Visual', VT-1 Not applicable to Washers either Hatch unit B6.150 B-G-1 Piping Bolts and Studs Volumetric Not applicable to either Hatch unit B6.160 B-G-1 Piping Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.170 B-G-1 Piping Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.180 B-G-1 Pumps Bolts and Studs Volumetric No B6.190 B-G-1 Pumps Flange Surface, when Visual, VT-1 No

, Connection Disassembled B6.200 B-G-1 Pumps Nuts, Bushings, and Visual, VT-1 No Washers 86.210 B-G-1 Valves Bolts and Studs Volumetric Not applicable to either Hatch unit B6.220 B-G-1 Valves Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.230 B-G-1 Valves Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit 87.10 B-G-2 Reactor Pressure Vessel Bolts, Studs, and Nuts Visual, VT-1 No l

l B7.20 B-G-2 Pressurizer Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit l

l l

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O O O TABLE 1 Sh. 7 of 12 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested B7.30 B-G-2 Steam Generators Bolts, Studs, and Nuts Visual, VT-1 Not applicable to l

either Hatch unit B7.40 B-G-2 Heat Exchangers Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.50 B-G-2 Piping Bolts, Studs, and Nuts Visual, VT-1 No B7.60 B-G-2 Pumps Bolts, Studs, and Nuts Visual, VT-1 No B7.70 B-G-2 Valves Bolts, Studs, and Nuts Visual, VT-1 No B7.80 B-G-2 CRD Housings Bolts, Studs, and Nuts Visual, VT-1 No (When Disassembled) 88.10 B-H Reactor Pressure Vessel Integrally Welded Volumetric or Yes, 2.1.5 Attachments Surface, as Applicable 88.20 B-H Pressurizer Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable 88.30 B-H Steam Generators Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit

Applicable 88.40 B-H Heat Exchangers Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable j B9.11 B-J Piping Circumferential Welds Surface and Yes, 2.1.4 (Nominal Pipe Size >4 in.)

Volumetric and 2.1.7

+

O O O l TABLE 1 Sh. 8 of 12 ISI PROGRAM FOR ASE CLASS 1 C00FONENTS l

1 EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 Am 2

Examination System or Com- Method of Code Relief

Item No. Category ponent Description Area (s) To Be Examined Examination Requested B9.12 B-J Piping Longitudinal Welds Surface and Yes, 2.1.4 (Nominal Pipe Size 24 in.) Volumetric B9. 21 8-J Piping Circumferential Welds Surface No (Nominal Pipe Size (4 in.)

i 1

B9.22 B-J Piping Longitudinal Welds Surface No l (Nominal Pipe Size < 4 in.)

89.31 B-J Piping Branch Pipe Connection Welds Surface and Yes, 2.1.4 (Nominal Pipe Size >4 in.) Volumetric B9.32 B-J Piping Branch Pipe Connection Welds Surface No J

(Nominal Pipe Size (4 in.)

89.40 B-J Piping Socket Welds Surface No, See Note 2

~

B10.10 B-K-1 Piping Integrally Welded Volumetric or No Attachments Surface, as Applicable

! B10.20 B-K-1 Pumps Integrally Welded Volumetric or No Attachments Surface, as Applicable

! B10.30 B-K-1 Valves Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit 1

Applicable l B12.10 B-L-1 Pumps Pump Casing Wal e Volumetric Not applicable to either Hatch unit B12.20 B-L-2 Pumps Pump Casing Visual, VT-3 Yes, 2.1.8 i B12.30 B-M-1 Valves Valve Body Welds Surface Not applicable to I (Nominal Pipe Size (4 in.) either Hatch unit

O O O TABLE I Sh. 9 of 12 l ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 j

Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested I

B12.40 B-M-1 Valves Valve Body Welds Volumetric Not applicable to (Nominal Pipe Size }>4 in.) either Hatch unit -

812.50 B-M-2 Valves Valve Body Visual, VT-3 Yes, 2.1.8 l (Nominal Pipe Size )>4 in.)

i B13.10 B-N-1 Reactor Pressure Vessel Vessel Interior Visual, VT-3 No i

B13.20 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-1 No (BWR) Within Beltline Region B13.21 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-3 No

(BWR) Beyond Beltline Region

! B13.22 B-N-2 Reactor Pressure Vessel Core Support Structure Visual, VT-3 No (BWR) 813.30 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-1 Not applicable to :

(PWR) Within Beltline Region either Hatch unit i 813.31 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-3 Not applicable to' (PWR) Beyond Beltline Region either Hatch unit :

B13.32 B-N-3 Reactor Pressure Vessel Core Support Structure Visual, VT-3 Not applicable to:

(PWR) (Removed) either Hatch unit 814.10 B-0 Reactor Pressure Vessel Welds in Control Rod Volumetric or Yes, 2.1.4 Drive Housing Surface and 2.1.9 i

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O O O l TABLE 1 Sh.10 of 12 l ISI PROGRAM FOR ASE CLASS 1 C0WONENTS

! EDWIN I. HATC:1 NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested B15.10 B-P Reactor Pressure Yessel Pressure Retaining Boundary System Leakage No Test; Visual, VT-2 i B15.11 B-P Reactor Pressure Vessel Pressure Retaining Boundary System Hydro- No

! test; Visual, VT-2 B15.20 B-P Pressurizer Pressure Retaining Boundary System Leakage Not applicable to Test; Visual, either Hatch unit '

VT-2 B15. 21 B-P Pressurizer Pressure Retaining Boundary System Hydro- Not applicable to test; Visual, either Hatch unit VT-2 m

1

O O O TABLE 1 Sh.11 of 12 ISI PROGRAM FOR ASE CLASS 1 C0WONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 ADO 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested B15.30 B-P Steam Generators Pressure Retaining Boundary System Leak- Not applicable to age Test; either Hatch unit Visual, VT-2 B15. 31 B-P Steam Generators Pressure Retaining Boundary System liydro- Not applicable to test; Visual, either Hatch unit VT-2 815.40 B-P Heat Exchangers Pressure Retaining Boundary System Leak- Not applicable to age Test; either Hatch unit Visual, VT-2 B15.41 B-P Heat Exchangers Pressure Retaining Boundary System Hydro- Not applicable to test; Visual, either Hatch unit VT-2 B15.50 B-P Piping Pressure Retaining Boundary System Leak- No age Test; Visual, VT-2 B15. 51 B-P Piping Pressure Retaining Boundary System Hydro- No test; Visual, VT-2 B15.60 B-P Pumps Pressure Retaining Boundary System Leak- No

, age Test; j Visual, VT-2 l

! B15. 61 B-P Pumps Pressure Retaining Boundary System Hydro- No test; Visual, VT-2 B15. 70 B-P Valves Pressure Retaining Boundary System Leak- No 4

age Test;

! Visual, VT-2

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! O O O l

l TABLE 1 Sh.12 of 12 l ISI PROGRAM FOR ASE CLASS 1 C0WONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested B15. 71 B-P Valves Pressure Retaining Boundary System Hydro- No test; Visual, VT-2 B16.10 B-Q Steam Generator Tubing Straight Tube Design Volumetric Not applicable to either Hatch unit B16.20 B-Q Steam Generator Tubing U-Tube Design Volumetric Not applicable to either Hatch unit Reactor Pressure Head Thickness Ultrasonic No, See Note 3 Vessel Closure Head Measurements

Notes for Table 1 O

(1) During each refueling outage, the reactor pressure vessel (RPV) closure studs are normally left in place; therefore, only a volumetric examination will be performed (ASME Section XI Table IWB-2500-1, Item No. 86.20). If the studs are removed, both a surface and volumetric examination will be performed ( ASME Section XI Table IWB-2500-1 Item No. B6.30).

(2) The Class 1 socket welds (Item No. B9.40 of Table IWB-2500-1 of ASME Section XI) for both units are exempted from surface examination by paragraph IWB-1220(a). However, selected austenitic piping welds may receive supplemental surface (PT) examinations.

(3) Prior to January 1,1984, ultrasonic thickness measurements were performed each refueling outage on the RPV closure head at both units (Hatch 1-six outages and Hatch 2-three outages) to determine if thinning has occurred. These measurements found no apparent thinning and therefore, these examinations will be performed once every 40-months at each unit.

O 1

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3.0 CLASS 2 WITH RELIEF REQUESTS Table 2 provides a tabulation of the Class 2 pressure-retaining components subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Yessel Code,1980 Edition with Addenda through Winter 1981. These components will be inspected in accordance with the requirements of Subsection IWC to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination. Piping in emergency core cooling systems will not use the temperature and pressure exemption; however, nominal pipe size and nominal wall thickness exemptions will be used. Where relief from the inspection requirements of Subsection IWC is requested, information is provided which identifies the applicable Code requirements, justification for the relief request, and the examination method to be used as an alternative. Table IWC-2500-1 items not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.

Hydrostatic testing will be conducted in a manner that will satisfy the requirements of IWA-5000 and IWC-5000. Where adjoining pipe sections have dif#3 rent 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., the boundary is a check valve),

the sections will be tested together at the lower of the specified test j pressures. No 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 i

O be hydrostaticaily tested Per the reRufremeats of IwA-5000 and IWC-5000.

l 3.1 Requests for Relief From ASME Section XI Requirements 3.1.1 Volumetric Examination of Pressure Retaining Welds in Class 2 Vessels 3.1.1.1 Requirement From Which Relief is Requested Item Nos. C1.10, Cl.20, and Cl.30 of Table IWC-2500-1 of ASME Section XI require the volumetric examination of Class 2 vessel shell circumferential, head circumferential, and tubesheet-to-shell circumferential welds, respectively. The volumetric examination of the Residual Heat Removal (RHR) system heat exchanger circumferential welds will be performed using ultrasonic techniques. The required examination volumes are shown in ASME Section XI Figures IWC-2500-1 and -2. Relief from this requirement is requested.

3.1.1.2 Justification 1

The shell and head circumferential weld examinations are limited by vessel supports adjacent to these welds. In addition, the ultrasonic examination of the head circumferential weld from the head side cannot be performed due to configuration. The examination volume as required by Figure IWC-2500-2 for the tubesheet-to-shell weld cannot fully be met due to configuration also.

i O

l

3.1.1.3 Testing in Lieu of Section XI Requirements The ultrasonic examination of the shell and head circumferential welds will be supplemented by a surface examination. The tubesheet to shell weld cannot be properly prepared for surface examination nor can the examination be performed due to the tubesheet studs and nuts adjacent to the weld. In addition to the examinations described above, system pressure tests per Article IWC-5000 of ASE Section XI will be performed on these welds.

3.1.2 Surface Examination of Welded Attachments on RHR, Core Spray, HPCI, and RCIC Suction Lines from Torus 3.1.2.1 Requirement From Which Relief is Requested Item No. C3.40 of Table IWC-2500-1 of ASME Section XI requires 100% surface examination of integrally welded attachments on piping. Figure IWC-2500-5 determines the surface area of this examination.

Suction lines for RHR, Core Spray, HPCI, and RCIC systems penetrating the torus are seal welded to the outside surface of the torus wall. Relief is requested from the surface examination of these welded attachments.

3.1.2.2 Justification At both Hatch units, these integrally welded attachments on lines penetrating the torus are obstructed by reinforcement plates added after plant construction. One hundred percent (100%) of the seal weld is inaccessible for a meaningful surface examination.

3.1.2.3 Testing in Lieu of Section XI Requirements Visual examination (VT-1) in accordance with IWA-2211 will be performed to insure the integrity of these attachments.

3.1.3 Surface Examination of Pressure Retaining Welds in Class 2 Pumps 3.1.3.1 Requirement From Which Relief is Requested Item No. C6.10 of Table IWC-2500-1 of ASME Section XI requires a surface examination of the pump casing welds from one Class 2 pump in each group of pumps that are of similar design, size, function, and service in a system.

Relief from this requirement is requested.

3.1.3.2 Justification Disassembly of these pumps for the surface examination during the inspection interval, in the absence of other required maintenance, represents an unnecessary exposure to radiation and contamination. During routine maintenance, the pump casing welds receive a surface examination. In view of the cost in man-rem and in view of the minimal benefits obtained, we conclude that this Code requirement does not provide a corresponding benefit in reliabil ity.

O

3.1. 3. 3 Testing in Lieu of Section XI Requirements l

O ciass 2 - c.sinri weids are suasect to surface examination when disasse.nied for maintenance. _ 'he coverage provided by examinations during routine maintenance coupled with hydrostatic tests will provide adequate assurance of the structural integrit;y of these pumps, while keeping exposure to radiation and contamination as low as reasonably achievable.

l l

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O O O TABLE 2 Sh. 1 of 4 ISI PROGRAM FOR ASE CLASS 2 COMP 0NENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested C1.10 C-A Pressure Vessels Shell Circumferential Welds Volumetric Yes, 3.1.1 C1.20 C-A Pressure Vessels Head Circumferential Welds Volumetric Yes. 3.1.1 C1.30 C-A Pressure Vessels Tubesheet-to-Shell Weld Volumetric Yes, 3.1.1 C2.11 C-B Pressure Vessels Nozzles-to-Shell (or Head) Surface Not applicable to Weld where Vessel Nominal either Hatch unit Thickness (1/2 inch C2.21 C-B Pressure Vessels Nozzle-to-Shell (or Surface and No Head) Weld for Vessels Without Volumetric Reinforcing Plates where Vessel Nominal Thickness

>l/2 inch C2.22 C-B Pressure Vessels Nozzle Inside Radius Section Volumetric No for Vessels Without Reinforcing Plates where Vessel Nominal Thickness >1/2 inch C2.31 C-B Pressure Vessels Reinforcing Plate Welds to Surface Not applicable to Nozzle to Vessel either Hatch unit where Vessel Nominal Thickness > 1/2 inch C2.32 C-B Pressure Vessels Nozzle-to-Shell (or Head) Volumetric Not applicable to for Yessels Without Reinforcing either Hatch unit Plates where Vessel Nominal Thickness >1/2 inch

O O O TABLE 2 Sh. 2 of 4 ISI PROGRAM FOR ASE CLASS 2 COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested C3.10 C-C Pressure Vessels Integrally Welded Attachments Surface No C3.20 C-C Piping Integrally Welded Attachments Surface Yes, 3.1.2 C3.30 C-C Putops Integrally Welded Attachments- Surface Not applicable to either Hatch unit C3.40 C-C Valves Integrally Welded Attachments Surface Not applicable to either Hatch unit ,

C4.10 C-D Pressure Vessels Bolts and Studs Volumetric Not applicable to either Hatch unit C4.20 C-D' Piping Bolts and Studs Volumetric Not applicable to either Hatch unit i

I

l o o o l

l TABLE 2 Sh. 3 of 4 l ISI PROGRAM FOR ASE CLASS 2 COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 Alm 2 Examination System or Com- Method of Code Relief

, Item No. Category ponent Description Area (s) To Be Examined Examination Requested l

l C4.30 C-D Pumps Bolts and Studs Volumetric Not applicable to either Hatch unit C4.40 C-D Valves Bolts and Studs Volumetric Not applicable to either H&eh unit C5.11 C-F Piping Circumferential Welds Surface No (Nominal Wall Thickness <1/2 in.)

C5.12 C-F Piping Longitudinal Welds Surface No (Nominal Wall Thickness ( 1/2 in.)

C5.21 C-F Piping Circumferential Welds Surface and No (Nominal Wall Thickness >1/2 in.) Volumetric

! C5.22 C-F Piping Longitudinal Welds Surface and No

(Nominal Wall Thickness >l/2 in.) Volumetric C5. 31 C-F Piping Circumferential Welds Surface No Pipe Branch Connections (Nominal Pipe Size > 4 in. )

C5.32 C-F Piping Longitudinal Welds Surface Not applicable to Pipe Branch Connections either Hatch unit (Nominal Pipe Size >4 in. )

C6.10 C-G Pumps Pump Casing Welds Surface Yes, 3.1.3 C6.20 C-G Valves Valve Body Welds Surface Not applicable to either Hatch unit C7.10 C-H Pressure Vessels Pressure Retaining Components System Pres- No l sure Test; Visual, VT-2 C7.20 C-H Pressure Vessels Pressure Retaining Components System Hydro- No static Test; Visual, VT-2

=

0 0 0 TABLE 2 Sh. 4 of 4 ISI PROGRAM FOR ASE CLASS 2 C0WONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 Als 2 Examination System or Com- Method of Code Relief .

Item No. Category ponent Description Area (s) To Be Examined Examination Pa p stad C7.30 C-H Piping Pressure Retaining Components System Pres- No s sure Test; Visual, VT-2 C7.40 C-H Piping Pressure Retaining Components System Hydro- No'

. static Test; l Visual, VT-2 ,

7 C7.50 C-H Pumps Pressure Retaining # Components System Pres- No sure Test; -

^

Visual, VT-2 C7.60 C-H Pumps Pressure Retaining Components System Hydro- No a '

static test; ,

Visual, VT-2 C7.70 C-H Valves Pressure Retaining Components System Pres- No sure Test; Visual, VT-2 C7.80 Valves Pressure Retaining Components System Hydro-C-tj '~

No

static Test; i , Visual, VT-2 9

l

=

4.0 CLASS 3 COMPONENTS WITH RELIEF REQUESTS O Table 3 provides a tabulation of the Class 3 pressure-retaining components subject to the inspection requirements of Subsection IWD of Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1981. These components will be inspected in accordance with Subsection IWD to the extent practical with the exception of the relief requests outlined in Paragraph 4.1 below. Table IWD-2500-1 items not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.

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., the 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.

4.1 Requests for Relief From ASME Section XI Requirements 4.1.1 System Pressure Tests on Class 3 Small Diameter Piping 4.1.1.1 Requirement From Which Relief is Requested Table IWD-2500-1 of ASME Section XI requires a system pressure test for Class 3 lines regardless of size.

p 4.1.1. 2 Justificatio::

U The system pressure test requirements for Class 3 will not be performed on lines two inches and smaller unless:

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

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

These smaller lines have wall thicknesses in excess of what ASME Section III required 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 to the type leakages found during hydrostatic testing.

4.1.1.3 Testing in Lieu of Section XI Requirements l Accessible piping two inches and smaller will be visually examined under normal operating pressure.

O

4.1.2 System Pressure Tests on Class 3 Buried Piping O 4.1.2.1 Requirement From Which Relief is Requested Table IWD-2500-1 of ASME Section XI requires a system pressure test for Class 3 components including buried piping.

4.1.2.2 Justification The service water systems were designed without including provisions for testing buried piping as required by Paragraph IWA-5244. In addition, tne visual examination for leakage at the ground level is not feasible since a majority of the piping is buried under asphalt.

4.1.2.3 Testing in Lieu of Section XI Requirements Normal system functional testing demonstrates leaktight integrity of all buried piping.

4.1.3 Pressure Test on Plant Service Water System 4.1.3.1 Requirement From Which Relief is Requested IWD-5223 of ASME Section XI requires that the Plant Service Water System be tested at a pressure of 1.10 times the design pressure. Relief is requested from testing those portions where it is necessary to use a butterfly valve ten inches in diameter or greater as a hydrostatic test boundary valve.

4.1.3.2 Justification Butterfly valves are basically flow control valves and are not intended to be block valves. The normal leakage through these large valves makes it impractical to attain and maintain the hydrostatic test pressure.

4.1. 3. 3 Testing in Lieu of Section XI Requirements A hydrostatic test will be performed on those portions of the Plant Service Water System which have a butterfly valve ten inches in diameter or greater at the normal operating pressure.

O

O O O TABLE 3 Sh. 1 of 3 ISI PROGRAM FOR ASE CLASS 3 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested

! 01.10 D-A Systems in Support of Pressure Retaining Components Visual, VT-2 Ves, 4.1.1 ; 4.1.2; Reactor Shutdown Function and 4.1.3 l1 Dl.20 D-A Systems in Support of Integral Attachment-Component Visual, VT-3 No Reactor Shutdown Function Supports and Restraints  !

Dl.30 D-A Systems in Support of Integral Attachment-Mechanical Visual, VT-3 No Reactor Shutdown Function and Hydraulic Snubbers Dl.40 D-A Systems in Support of Integral Attachment-Spring Visual, VT-3 No Reactor Shutdown Function Type Supports

Dl.50 D-A Systems in Support of Integral Attachment-Constant Visual, VT-3 No Reactor Shutdown Function Load Type Supports l Dl.60 D-A Systems in Support of Integral Attachment- Visual, VT-3 No J Reactor Shutdown Function Shock Absorbers i

l 1

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i O O O I TABLE 3 Sh. 2 of 3

ISI PROGRAM FOR ASE CLASS 3 SUPPORT COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AIS 2

Examination System or Com- Method of Code Relief i Item No. Category ponent Description Area (s) To Be Examined Examination Requested

.i

]' D2.10 D-B Systems in Support of Pressure Retaining Components Visual, VT-2 Yes, 4.1.1 ECC, CHR, Atmosphere '

. Cleanup, and Reactor RHR D2.20 D-B Systems in Support of Integral Attachment-Components Visual, VT-3 No l ECC, CHR, Atmosphere Supports and Restraints Cleanup, and Reactor RM

]

D2.30 D-B Systems in Support of Integral Attachment-Mechanical Visual, VT-3 No

ECC, CHR, Atmosphere and Hydraulic Snubbers

Cleanup, and Reactor RHR D2.40 D-B Systems in Support of Integral Attachment- Visual, VT-3 No l ECC, CHR, Atmosphere Spring Type Supports

Cleanup, and Reactor l RM D2.50 D-B Systems in Support of Integral Attachment-Constant Visual, VT-3 No ECC, CHR, Atmosphere Load Type Supports .

3 Cleanup, and Reactor

! RM

, D2.60 D-B Systems in Support of Integral Attachment- Visual, VT-3 No l ECC, CHR, Atmosphere Shock Absorbers j Cleanup, and Reactor

. RHR l

1 f.

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O O O TABLE 3 Sh. 3 of 3 ISI PROGRAM FOR ASE CLASS 3 COWONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested D3.10 D-C Systems in Support of Pressure Retaining Components Visual, VT-2 Yes, 4.1.1

RHR from Spent Fuel 4

Storage Pool D3.20 D-C Systems in Support of Integral Attachment-Component Visual, VT-3 No RHR from Spent Fuel Supports and Restraints Storage Pool D3.30 D-C Systems in Support of Integral Attachment-Mechanical Visual, VT-3 No RHR from Spent Fuel and Hydraulic Snubbers Storage Pool D3.40 D-C Systems in Support of Integral Attachment-Spring Visual, VT-3 No RHR from Spent Fuel Type Supports Storage Pool I

! D3.50 D-C Systems in Support of Integral Attachment-Constant Visual, VT-3 No RHR from Spent Fuel Load Type Supports

Storage Pool j D3.60 D-C Systems in Support of Integral Attachment- Visual, VT-3 No i RHR from Spent Fuel Shock Absorbers Storage Pool i

l

5. 0 CLASS 1, 2, AND 3 SUPPORTS WITH RELIEF REQUESTS Table 4 provides a tabulation of the Class 1, 2, and 3 component supports O subject to the inspection requirements of Subsection IWF,Section XI of the ASE Boiler and Pressure Yessel Code,1980 Edition with Addenda through Winter 1981. These components will be inspected in accordance with the requirements of Subsection IWF to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination. Where relief from the inspection requirements of Subsection IWF is requested, information is provided which identifies the applicable Code requirements, justification for the relief request, and the examination method to be used as an alternative.

Table IWF-2500-1 items not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.

Paragraph IWF-1230 titled Supports Exempt from Examination and Test is in the course of preparation. Later Addenda through Winter 1984 of Section XI do not provide guidance for the exemption criteria for these components. Georgia Power Company has therefore decided to incorporate the exemption criteria for Class 1, Class 2, and Class 3 component supports found in Paragraphs IWB-1220, IWC-1220, and IWD-1220 of ASME Section XI, respectively.

5.1 Requests for Relief from ASME Section XI Requirements 5.1.1 Requirement to Verify Hot or Cold Settings on Spring Cans and Snubbers 5.1.1.1 Requirement From Which Relief is Requested O Subparagraph IWF-3410(a)(5) of ASME Section XI states that a component support condition which is unacceptable for continued service is improper hot or cold positions for spring supports or snubbers. Relief from this requirement is requested.

5.1.1.2 Justification There are no exact design positions on the scales for spring supports or snubbers but an operational range where the indicator should be located.

5.1.1.3 Testing in Lieu of Section XI Requirements The visual examination will verify that the indicator falls within the l operational limits.

5.1.2 Testing of Hydraulic and Mechanical Type Snubbers i 5.1.2.1 Requirement From Which Relief is Requested Article IWF-5000 of ASME Section XI outlines the inservice test requirements i for hydraulic and mechanical type snubbers. Relief from this requirement is requested.

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5.1.2.2 Justification Instead of using IW-5000, the ongoing testing program per the Plant Technical O Specifications will be performed. This testing program is designed to demonstrate the functional integrity of the snubbers and exceeds the requirements of Article IW-5000.

5.1.2.3 Testing in Lieu of Section XI Requirements As noted in 5.1.2.2, the testing program per the Plant Technical Specifications will be performed.

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O O O TABLE 4 Sh. 1 of 3 ISI PROGRAM FOR ASE CLASS 1, 2 AND 3 SUPPORT COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested F1.10 F-A Plate and Shell Mechanical Connections to Visual, VT-3 Not applicable to Type Supports Pressure Retaining Components either Hatch unit and Building Structure Fl.20 F-A Plate and Shell Weld Connections to Visual, VT-3 Not applicable to Type Supports Building Structure either Hatch unit F1.30 F-A Plate and Shell Weld and Mechanical Visual, VT-3 Not applicable to Type Supports Connections at Intermediate either Hatch unit Joints in Multiconnected Integral and Nonintegral Supports F1.40 F-A Plate and Shell Component Displacement Settings Visual, VT-3 Not applicable to Type Supports of Guides and Stops, Misalignment either Hatch unit of Supports, Assembly of Support Items

O O O TABLE 4 Sh. 2 of 3 ISI PROGRAM FOR ASE CLASS 1, 2 AND 3 SUPPORT COWONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested I

F2.10 F-B Linear Type Supports Mechanical Connections to Visual, VT-3 Not applicable to Pressure Retaining Components either Hatch unit and Building Structures 1 F2.20 F-B Linear Type Supports Weld Connections to Visual, VT-3 Not applicable to ,

Building Structure either Hatch unit F2.30 F-8 Linear Type Supports Weld and Mechanical Connections Visual, VT-3 Not applicable to at Intermediate Joints in either Hatch unit Multiconnected Integral and Nonintegral Supports F2.40 F-B Linear Type Supports Component Displacement Settings Visual, VT-3 Not applicable to of Guides and Stops, Misalignment either Hatch unit of Supports, Assembly of Support Items i

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O O O TABLE 4 Sh. 3 of 3 ISI PROGRAM FOR ASE CLASS 1, 2 AND 3 SUPPORT COWONENTS

EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief Ites No. Category ponent Description Area (s) To Be Examined Examination Requested F3.10 F-C Component Standard Mechanical Connections to Visual, VT-3 No Supports Pressure Retaining Components j and Building Structure

! F3.20 F-C Component Standard Weld Connections to Visual, VT-3 No Supports Building Structure

F3.30 F-C Component Standard Weld and Mechanical Connections Visual, VT-3 No Supports at Intermediate Joints in Multiconnected Integral and Nonintegral Supports F3.40 F-C Component Standard Component Displacement Settings Visual, VT-3 Not applicable to Supports .of Guides and Stops, Misalignment either Hatch unit of Supports, Assembly of

.i Support Items j F3.50 F-C Component Standard Spring Type Supports, Constant Visual, VT-4 Yes, S.1.1 and

Supports Load Type Supports, Shock 5.1.2 l Absorbers, Hydraulic and

.j Mechanical Type Snubbers

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6.0 INSERVICE INSPECTION OF VALVES The valve testing program is based on the 1980 Edition of ASME Section XI with Q Addenda through Winter 1981. Yalves in the program are listed in the valve test tables and will be tested in accordance with the code unless otherwise specified. Several features of the program are discussed below:

Containment Isolation Valves Containment Isolation Valves (CIVs) will have a type C leakage test performed per the requirements of 10 CFR 50, Appendix J. In addition, each valve or penetration will have a specific leakage limit assigned to it by Georgia Power Company. Limits will be based on type of valve, size of valve, the number of valves tested in parallel paths, and historical leakage data. These limits are available for review in the Long-Term Inservice Inspection Pump and Yalve Test Plans stored in the Plant Hatch Document Control room.

Pressure Isolation Yalves Pressure Isolation valves, as a rule, will be tested in the same manner as the CIVs and the observed leakage escalated per IWY-3423 to the function maximum pressure differential value. The maximum leakage for each valve will be .5 gpm per inch of nominal valve size or a maximum of 5 gpm (water). If air is used as the test medium the leakage will be conservatively assumed to be water leakage. Testing experience at Plant Hatch has shown that when air is used as the test mdeium the resulting leakage is higher than when water is used in the same test volume; therefore, it is conservative to test with air instead of water.

d 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 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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.

Remote Indicating Lights Valves with remote indicating lights will be observed at least once every 2 years to verify that the valve operation is accurately indicated.

Fail-Safe Valves Unless otherwise specified in the program tables the only fail-safe valves are either air operated or solenoid valves. Stroking the valve full cycle during normal testing causes loss of power to the actuator as required by IWY-3415.

Therefore, additional testing to prove the fail-safe capability will not be performed.

Control Rod Drive System Yalves See Relief Request 6.1.22 Q

Valves Testing During Cold Shutdown See Relief Requests 6.1.9 and 6.1.19.

In additon to the Relief Requests addressed above, relief is specifically requested for each valve in the Valve Test Project Tables as required. All relief requests are located following these tables.

Compressed Air Systems Valve Testing Section 9.3.1.4, Safety Evaluation of Compressed Air Systems, of the Final Safety Analysis Report (FSAR) states:

Because compressed air is not essential for the safe shutdown of the plant, the compressed air systems do not switch automatically to operation from diesel generator power following a loss of normal power.

Section 15.1.28.2, Analysis of Effects and Consequences of Loss of Instrument Air, also states:

All equipment using instrument air is designed to fail to a position that is consistent with the safe shutdown of the plant.

O rrom these statemeats made ia the rSAR. we have concluded that ao vaives in the Instrument Air and Service Air Systems should be tested under the rules of ASME Section XI.

Thermal Relief Valves The RHR Heat Exchangers were provided with small relief valves during their fabrication which provide no safety function. Much larger relief valves which provide the required relief capacity are included in this program. However, potential leakage through the thermal relief valves is tested for during the Appendix J Local Leak Rate Tests.

j Passive Power Operated Valves l

l Power operated valves which are not required to change position to accomplish l a specific safety-related function will have their positions verified quarterly and each time the valves are cycled.

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O O O SYSTEM: Main Steam & feedwater Plant Hatch - Unit i Valve Testing Program Sh. 1 of 33 St roke Valve Code Norm Time Roller Class Cat Desc rigt ion Coord. PglD Fianction Pos E me rc i se teakaes Rea'd Reauest

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B21-fol0A 1 AC la" check [-3 11-16062 IW Inbrd. Cont. l so. O RO Civ No 6.1.1 B21-f0108 1 AC 18" Check D-3 H-16062 TW Inbrd. Cont.lso. O RO CIV No 6.1.1 821-f013A 1 C 6" Relier C-6 H-16062 Main Steam Relier -

Note 3 NA No B21-f013B 1 C 6" Relier C-6 11-16062 Main Steam Relier -

Note 3 NA No B21-f013C I C / Relier '-6 11-16062 Main Steam Relier -

Note 3 NA No B21-10130 1 C t" Rclier I-6 H-16062 Main Steam Italier -

Note 3 NA No B24-F013E 1 C 6" Relier F-6 11-16062 Main Steam Relier -

Note 3 NA No B21-fol3I 1 C .6" Relier I-6 H-16062 Main Steam Relief -

Note 3 NA No B21-f013G 1 C 6" Relier F-6 H-16062 Main Steam Relier -

Note 3 NA No B21 -5 01311 1 C 6" Relier C-6 11-16062 Main Steam Relier -

Note 3 NA No B21-F013J l C 6" Relier C-6 H-16062 Main Steam Relier -

Note 3 NA No B21-F013K 1 C 6" Relier F-6 H-16062 Main steam Relier -

Note 3 NA No B21-IO13L 1 C 6" Relier F-6 H-16062 Main Steam Relier -

Note 3 NA No

'B21-f016 1 A 3" M0 Cate E-8 H-16062 Main Steam Line C Note 1 CIV No 6.1.2 DRN. Inh. Iso.

821-F019 1 A 3" MO Cate E-9 H-16062 Main Steam Line C Note 1 CIV No DRN. Inb. Iso B21-10?2A 1 A 2ft " AO Clotse C-7 11-1606? MSIV 0 Q t r. CIV Yes 6.1.23 Bd1-f0228 I A 24" A0 Clube E-l H-16062 MSIV O Qtr. CIV Yes 6.1.23 B21-5022C I A 24" A0 Clube I-7 H-16062 MSIV O Qtr. CIV Yes 6.1.23

SYSTEM: Main Steae & reedwater Plant Hatch - Unit 1 Valve Testing Program Sh. 2 of 33 Stroke Valve Code Norm Time Relief No. Class Cat De sc ri p t ion Coo rd . Pkl0 f ue":t ion Pos Exe rc i se Leakaee Rea'd Reauest 821-I022D 1 A 24" A0 Globe C-7 H-16062 MSIV O Qtr. CIV Yes 6.1.23 821-f028A 1 A 24" A0 Clobe C-9 14-16062 MSIV O Qtr. CIV Yes 6.1.23 l

821-f0288 1 A 24" A0 Clobe I-9 11-16062 MSIV O Qtr. CIV Yes 6.1.23 B21-IO28C 1 A 24" A0 Clobe F-9 11-16062 MSiv 0 Q t r. CIV Yes 6.1.23 B21-F0280 1 A 24" AO Clobe G-9 H-16062 MSIV O Q t r. CIV Yes 6.1.23 B21-I032A 1 AC 18" Check E-2 11-16062 IW Outboard ISO O RO CIV No 6.1.1 B21-f032B 1 AC 15" Check D-2 11-16062 IW Outboard ISO O 80 CIV No 6.1.1 B21-l03/A 3 C 6" Check 11 - 6 14-16062 Vac, lla the ke r C See 6.1.3 NA No 6.1.3 l

MSRV Disch.

B21-F0378 3 C 6" Check al-6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Desch.

821-f031C 3 C 6" Check 11 - 6 H-16062 Vac. D rea ke r C See 6.1.3 NA No 6.1.3

< MSRV Disch.

B21-f037D 3 C 6" Check 11 - 6 14-16062 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

i i B21-F037E 3 C 6" Check H-6 H-16062 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch..

l B21-F037I 3 C 6" Check 11 - 6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 4 MSRV Disch.

821-F031C 3 C 6" Check II-6 H-16062 V.i c . B rea ke r C See 6.1.3 NA No 6.1.3 l

HSRV Oesch.

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O O O' SYSitM: Main Steam ae feedwater Plant Itatch - Unit i Valve Testing Program Sh. 3 of 33 Stroke Valve Code Norm Time Roller geo . Class Cat Desc ri p t inn Con rd . Par 0 f ianc t ion Pos t'wercise teskaoe Rea'd Reaumat 821-F037H 3 C 6" Check h-6 H-16062 Vac . B rea ke r C See 6.1.3 NA 00 0 6.1.3 MSRV Disch.

821-F037J 3 C 6" Check H-6 H-16062 Vac. B rea ke r C See 6.1.3 NA Ito 6.1.3 MSRV Disch.

B21-F037K 3 C 6" Check 11- 6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.

821-F037L 3 C 6" Check H-6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 a MSRV Disch.

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A ,O SYSTEM: Reactor Reci rculation System Plant Hatch - Unit 1 Valve Testing Program Sh. 4 of 33 St roke Valve Code Norm Time Relief No. Class Cat Description Coord. PhlD Function Pos Exe rc i se Leakaee Rea'd Reaumat 831-f013A 1 AC 3/4" Check F-3 H-16066 Recir. Pump Seal Wtr O RO CIV No 6.1.1 831-f0138 1 AC 3/4" Check I-3 H-16066 Recir. Pump Sea l Wtr O RO CIV No 6.1.1 831-f017A 1 AC 3/4" Check F-2 H-16066 Recir. Pump Sea l Wt r O RO CIV No 6.1.1 831-f0178 1 AC 3/4" Check T-2 H-16066 Recir. Pump Seal Wtr O RO CIV No 6.1.1 831-F019 1 A 3/4" AO Clobe D-3 H-16066 Reac. Sample Sys. O Qtr CIV Yes i nb rd . 150 831-f020 1 A 3/4" AO Clobe D-1 H-16066 Reac. Sampic Sys O Qtr CIV Yes inbrd. Iso 831-F031A 1 8 28" MO Cate C-7 H-16066 Reactor Recirculation O CS NA Yes 6.1.4 831-f0318 1 8 28" MO Cate H-7 H-16066 Reactor Recirculation O CS NA Yes 6.1.4

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SYS1[M: . Standby Liquid Control System Plant Hatch - Unit i Valve Testing Program Sh. 5 of 33 Stroke Valve Code More Time Relief 30 0 . Class Cat Desc ri p t ion Coord. Par l D Function Pos Exe rc i se Leakaee flma'd ---^st C41-f004A 2 D 1-1/2" Expl D-3 H-16061 SLC Explo Act C Slote 4 16A fle SLC Explo Act C slote 4 NA geo C41-F0048 2 D 1-1/2" Expl F-3 H-1606)

C41-f006 1 AC 1-1/2" Check E-2 H-16061 SLC Outbrd C 18 mos. CIV Its 6.1.5 Cont. Iso C41-f001 1 AC 1-1/2" Cteck [-2 11-16061 StC Outbrd C 18 mos. Civ sto Cont. ISO C41-F029A 2 C 1" Relier D-6 H-16061 SLC Pump Disch. C Mote 3 NA Ito Retier C G-6 H-16061 SLC Pump Disch. C Note 3 NA No C41-f 029tl 2 1" Helier Relier C41-f033A 2 C 1-1/2" Check E-S H-16061 SLC Pump Disch. C Qtr. NA No C41-IO338 2 C 1-1/2" Check C-5 H-16061 SLC Pump Disch, C Q L r. 16A No

( Q SYSIEM: Residual Heat Removal Plant Hatch . unit 1 Va l ve Te s t ing Prog ram Sh. 6 of 33 Stroke Valve Code Norm Time Relier No. Class Cat Description Coo rd . PhlD Function Pos Exercfse Leaksee Ree'd Romaamat Eti-F003A 2 8 16" Mo Cate Viv D-9 H-16330 RilR Hx Shell O Qtr NA Yes Side outlet E11-f0038 2 B 16" Mo Cate Viv D-4 H-16329 RHR 14x Shell O Qtr NA Yes Side Outlet E11-FOO4A 2 A 24" M0 Gate Viv F-10 H-16330 RHR. Pump Suction 0 Qtr CIV Yes Torus Iso

[11-f0048 2 A 24" Mo Cate viv F-3 H-16329 RitR Pump Suction O Qtr CIV Yes

. Torus Iso E11-1004C 2 A 24" Mo Cate viv I-10 H-16330 RilR Pump Suction 0 Qtr CIV Yes To rus Iso Ell-F004D 2 A 24" Mo Cate Viv I-3 H-16329 RitR Pump Suction O Qtr CIV Yes Torus Iso Ell-FOO6A 2 B 20" M0 Cate Viv F-10 H-16330 RilR Shutdown C Qtr NA Yes CooIing Sys E11-f0068 2 8 20" Mo Cate Viv I-2 H-16329 RHR Shutdown C Qtr NA Yes CooIing Sys E11-f006C 2 B 20" Mo Cate Viv F-10 H-16330 RitR Shutown C Qtr NA Yes Cooling Sys E11-F0060 2 8 20" MO Cate Viv I-2 H-16329 RHR Shutdown C Qtr NA Yes CooIing Sys E11-f007A 2 A 4" MO Gate Viv E-7 H-16330 RHR Pump Min Flow 0 Qtr ClV Yes 6.1.2 Turus Iso E11-F0018 2 A 4" HO cate Viv D 's H-16329 RitR rump Min flow 0 Qtr CIV Yes 6.1.2

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SYSTEM: Residual Heat Removal Plant Hatch - Unit 1 Valve Testing Program Sh. 7 of 33 Strob^

Valve Code Norm Time Roller No. Class Cat Description Coord. ParID Function Pas Exe rc i se Leakane Rea'd flaeaamat E11-f008 1 A 20" M0 Cate D-1 H-16329 RHR Shutdown C Note 1 PIV. 80 0 Cooling Outbrd iso Ell-fou9 1 A 20" M0 Cate D-1 H-16329 HHH Shutdown C Note 1 POV 10e Cooling outbrd Iso

[11-F011A 2 A 4" MO Cate D-3 H-16330 RHR Cond. Disch. C Qtr Civ Yes 6.1.2 to lorus E11-F0118 2 A 4" MO Cate C-9 H-16329 RilR Cond. Disch. C Wtr CIV Yes 6.1.2 to lorus

[11-f o l ?>A 1 A 24" Mo Cate C-8 H-16330 t PC I Outbrd. C Qtr PlV Yes Cont. Iso E11-F015B I A 24" Mo Cate C-4 H-16329 LPCI Outbrd, C QLr POV Yes Cont. Iso E11-I016A 2 A 16" MO Cate B-9 H-16330 Cont. Sp ray C Qtr ClV Yes Ou tb rd , tso E11-fol6tl 2 A 16" MO Cate B-4 H-16329 Cont. Sp ray C Qtr CIV Yes Outbrd. Iso Ell-follA 1 13 24" MO Gate D-8 H-16330 LPCI O Qtr NA Yes Ell-I017B 1 8 24" Mo Cate D-S H-16329 LPCI O Qtr NA Yes Ell-IOl9 1 C 4" Chech A-1 11-16329 Head Spray C Note 2 NA No Ell-IO21A 2 B 16" M0 Cate B-11 H-16330 Containment Sp ray C Qtr NA Yes Ell-F0218 2 0 16" MO Ca t er 11 - 2 H-16329 Cim t a i nmen t Sp ray C Qtr NA Yes E11-f022 1 A 4" Mu Cate A-1 H-16329 Head Spray C Note 1 C!V No

l SYS1EM: Re s idua l Heat Removal Plant flatch - Unit i Va l ve Tes t ing P rog ram Sh. 8 of 33 St roke l Valve Code Norm Time Relief No. Class Cat Descrigtion Coord. PhlD F itng t ion Pos E xe rc i se Leaksee Ree'd Resumat E11-TO23 1 .A 4" MO Globe A-2 H-16329 Head Spray Outb rd. C Note 1 Civ Ne Iso

[11-IO24A 2 8 16" Mo Globe C-7 H-16330 Suppression Pool C Qtr NA Yes Cooling E11-TO24B 2 8 16" MO Clove C-6 H-16329 Suppression Pool C Qtr NA Yes Cooling

[11-f025A 1 AC 1" Relier B-8 H-16330 1.PC I Inj. C Note 3 ClV No Cont. Iso

[11-10258 2 AC 1" Relier C-$ 11-16329 LPCI inj. C Note 3 ClV No Cont. Iso I11-1026A 2 A 4" MO Cate D-3 H-16330 Cond. Disch. to C Qtr ClV Yes RCIC Cont. Iso

[11-f026B 2 A 4" MO Gate D-11 H-16329 Cund. Disch. to C Qtr CIV Yes RCIC Cont. Iso

[11-f027A 2 8 6" MO Cate D-3 14-16330 Suppression Pool C Qtr NA Yes Sp ray l E11-f027B 2 8 6" MO Cate D-11 Il-16329 Suppression Pool C Qtr NA Yes Sp ray E11-f028A 2 A 16" MO Cate B-8 14-16330 Suppression Pool C Qtr Cly Yes Sp ray Ou tb rd , 150 E11-f028B 2 A 16" Mo Cate B-5 H-16329 Suppression Pool C Qtr CIV Yes Spray Outbrd. 150 L11-IO29 2 AC 1" l<elser 1-? H-16329 lulR rump Suction C Note 3 CIV No l Cont. Iso

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\J O SYSIEM: Residual lleat Removal Plant Hatch - Unit 1 Valve Testing Program Sh 9 of 33 Stroke Valve Code Norm Time Relief Blo . Class Ca W es M ption Courd. P&lD Function Pos f>ercise leakage Rea'd -

at E11-F030A 2 AC 1" Relief I-9 H-16330 RHR Pump Suction C Note 3 CIV les Cont. Iso E11-F0308 2 AC 1" Relief F-4 H-16329 RHR Pump Suction C Note 3 CIV 10e Cont. Iso E11-Fu30C 2 AC 1" Relief I-11 H-16330 RHR Pump Suction C Note 3 CIV 90 0 Cont. Iso E11-F030D 2 AC 1" Relief I-1 H-16329 RilR Pump Suction C Note 3 CIV No i

Cont. Iso l

2 C Pu" Check H-6 H-16330 RilR Pump Discharge C Note 5 NA No

, [11-l031A l

E11-f0318 2 C 20" Check H-6 H-16329 RHR Pump Discharge C Note $ NA No l

E11-F031C 2 C 20" Check H-10 H-16330 RHR Pump Discharge C Note 5 NA No

[11-F031D 2 C 20" Check H-2 H-16329 RHR Pump Discharge C Note 5 NA No E11-f046A 2 C 3" Check 11- T H-16330 RHR Minimum Ilow Line C Note 5 NA No i

[11-F046B 2 C 3" check H-5 H-16329 RHR Minimum flow Line C Mote 5 NA No E11-F046C 2 C 3" Check 11 - 1 1 H-16330 RHR Minimum flow Line C Note 5 NA No E11-f046D 2 C 3" Check H-2 11-16329 RilR Minimum Flow Line C Note 5 NA No

[11-F047A 2 B 16" MO Cate L-6 11-16330 RHR lix Shell Side O Qtr NA Yes Side Inlet

[11-F0418 2 B 16" M0 Cate E-7 H-16329 ftHH 1t= Shell Side 0 Qtr NA Yes S i ste lutet

[11-F048A 2 8 24" Mo Clube B-8 H-16330 RHH HX Shell Side 0 Qtr NA Yes Bypass 1

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u V O SYSTEM: Residual Heat Removal Plant Hatch - Unit 1 Va l ve Te s t i ng Prog ram Sh. 10 of 33 Stroke Code More Time Relief Valve Pos Exe rc i se Leaksee Ree'd ilmmunst

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Class Cat Description Coo rd . MID Function -

2 8 24" M0 Globe B-5 H-16329 RilR lix Shell Side 0 Qtr NA Yes E11-F048B Bypass E11-F050A 1 AC 24" A0 Check D-6 11-16330 LPCI I nj ec . Iso C See 6.1.7 PlV Its 6.1.7 E11-f0508 1 AC 24" A0 Check D-7 H-16329 LPCI Injec.. Iso C See 6.1.7 PlV Ito 6.1.7

[11-FOSSA 2 AC 4" Relief .D-6 H-16330 RilR ilm Shell C Note 3 CIV Ito Relief Cont. Iso E11-IO558 2 AC 4" Relief D-1 11-16329 lutR lix Shell C Note 3 ClV 80 0 Rolief Cont. Iso

[11-f065A 2 B 24" Ao lirly E-10 14-16330 HilR lorus Suction 0 Qtr NA Yes E11-I0658 2 B 24" A0 Brly E-2 H-16329 RilR Torus Suction 0 Qtr NA Yes E11-f065C 2 8 24" AO Bfly E-10 H-16330 RilR Torus Suction 0 Qtr NA Yes E11-I065D 2 B 24" A0 Bfly E-2 H-16329 RilR Torus Suction 0 Qtr NA Yes

[11-I078A 2 C 10" Check H-6 H-16330 RHR Hx Ser Wtr Tie C RO NA No 6.1.8

[11-f0188 2 C 10" Check D-9 H-16329 RilR lix Ser Wtr Tie C RO NA No 6.1.8 E11-F091A 2 B 6" MO Clobe E-2 H-16330 Steam Line to RHR C Qtr NA Yes lla Shutdown

[11-fo918 2 8 6" Mo Clube E-11 H-16329 Steam tine to RHR C Qtr NA Yes H< Shutdown

[11-IO97 2 AC 3" Relier D-11 H-16329 Steam line Relief C Note 3 CIV No Cont. Iso

[11-f103A 2 A 1" MO Globe I-5 H-16330 RHR lix Vent C Qtr ClV Yes Cont Iso

p. n SYSTEM: Residual Heat Removal Plant Hatch - Unit 1 Va lve Te s t i ng Prog ram Sh. 11 of 33 Stroke Valve Code Norm Time Roller No. Class Cat Description Coo rd . ParlD Function Pos Exe rc i se Leaksee Rea'd Reaumat

[11-fl03B 2 A 1" MO Clobe E-8 H-16329 RilR lix Vent C Qtr CIV Yes Cont Iso Ell-f140A 2 B 6" MO Cate E-2 H-16330 Steam Line to RHR C Qtr NA Yes lix Shutdown E11-F1408 2 B 6" M0 Cate E-11 H-16329 Steam Line to RHR C Qtr NA Yes Hx Shutdown E11-f068A 3 tt 10" MO Ball H-6 11-16330 MHR Hx Ser. Wtr C Note 6 NA No Disch.

E11-f u68ts 3 is 10" Mo Ball 11 - 7 Il- 16329 RilR lix Se r. Wt r C Noto 6 NA No Disch.

E11-F073A 2 B 10" MO Cate G-4 H-16330 RilR Ser. Wtr intertie C Qtr NA Yes E11-f0738 2 8 10" MO Cate C-9 H-16329 RHR Ser. Wtr Intertie C Qtr NA Yes E11-F075A 2 8 10" MO Cate C-4 H-16330 RHR Ser Wtr Intertie C Qtr NA Yes Ell-folSB 2 B 10" MO Cate C-9 H-16329 RHR Ser. Wtr intertie C Qtr NA Yes

[11-F119A 3 B 18" M0 Cate 11 - 4 H-16330 RHR Ser. Wt r T ra in C Qtr NA Yes A & B Cross E11-I119B 3 15 18" M0 Cate H-9 H-16329 RHR Ser. Wt r t ra in C Qtr NA Yes A & B Cross E11-f200A 3 B 2" A0 PCV -

D-11004 RHR Ser. Wt r. Pump C Note 9 NA No Flow

[11-f2006 3 B 2" A0 PCV -

D-11004 RHit Nt r. Wt r. Pump C Note 9 NA No iIow E11-F200C 3 8 2" AO PCV -

D-110J4 RHR Se r. Wt r. Pump C Note 9 NA No flow

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

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I SYSTEM: Nesidual Heat Removal Plant Hatch - Unit i Valve lasting Program sh, 12 of 33

f Stroke i Valve Code Isors Time Relief geo. Class Cat Desc rip t ion Coo rd . ParID function Pos Exe rci se Leaksee Ama'd - - 21 E11-F2000 3 B 2" AO PCV - D-11004 RHR Ser. Wtr Pump C Ilote 9 IsA sto Flow I

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SYSTEM: Core Spray System Plant Hatch - Unit 1 Valve Testing Program Sh. 13 of 33 Stroke Code Norm Time Roller Valve Pos Exe rc i se leakaee Ree'd Ilmaumat eso . Class Cat Descriglion Coo rd . Par I D Function 2 A 20" Mo Cate H-8 H-16331 CS. Pump Suction Out 0 Qtr CIV Yes E21-FOO1A 2 20" MO Cate J-8 H-16331 CS Pump Suction Out O Qtr CIV Yes

[21-F0018 A 12" Check F-9 H-16331 CS Pump Discha rge C Note 5 NA 90 0

[21-FOO3A 2 C E21-f003B 2 C 12" Check F-11 48-16331 CS Pump Di scha rge C Note 5 NA 10 0 B 10" MO Cate E-7 11-16331 CS Outbrd. Injection O Qtr NA Yes E21-f004A 1 B 10" HO Cate B-1 H-16331 CS Outbrd, i nj ec t ion 0 Qtr NA Yes

[21-f0048 1 A 10" MO Cate E-6 11-16331 CS Ou t b rd . Cont. Iso C Qtr P1V Yes

[21-800$A 1 A 10" Mo Cate B-6 H-16331 CS Outbrd. Cont. Iso C Qtr PlV Yes E21-f00$8 1 AC 10" A0 Chech D-4 H-16331 CS Pressure iso C See 6.1.7 PlV No 6.1.7

[21-FOO6A 1 E21-FOO6B 1 AC 10" A0 Check C-4 H-16331 CS Pressure Iso C See 6.1.7 PlV No 6.1.7 C 2" Relief D-9 H-16331 CS Pump Disch.Relier C Note 3 NA No E21-1012A 2 2 B-9 H-16331 CS Pump Disch.Rollof C Note 3 NA No

[21-F0128 C 2" Relier

[21-I015A 2 A 10" MO Clobo D-8 44-16331 Core Spray Test C Qtr ClV Yes Bypass Cont. Iso 2 A 10" MO Globe C-8 H-16331 Core Spray Test C Qtr CIV Yes E21-I015B Bypass Cont. Iso E21-5019A 2 8 20" AO Brly J-6 H-16331 Core Spray Pump 0 Qtr NA Yes lurus Soc.

[21-I0190 2 u 20" A0 BIly k-6 H-16331 Cu ru Sp ray Pump 0 Qtr NA Yes Torus Suc.

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

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SYSTEM: Core Spray System Plant )tatch - Unit i Valve Testing Program Sh. 14 of 33

' . St roke I- . i~7V alve - Code .

-' Norm Time iteIlof '

Class Cat Descriotion Coo rd . P&lD function Pos Fxercise Leakaee Rea'd "- - - -^ t t

-No.

i l'- 9 H-16331 CS Pump Min. Flow 0 Qtr NA yo g',

E21-f031A 2~ 8 ._3" Mo Cate ^

• E21-I0318 2 B 3" Mo Cate F-10 H-16331 CS Pump Min. flow 0 Q't r NA 'Yeh I

i E21-F036A 2 AC 3" Check ,

E-9 H-16331 CS Test Linel' C See 6.1.6 CIV 00 0 6.1.6 Cont. Iso . ,

I CS lest l_ i no C See 6.1.6 ' Civ - ilo - 6.1.6 i E21-F036B 2 AC 3" Check t-10 Il-16331 i Cont. Iso t

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SYST[M: High Pressure Coolant inject ion Plant Hatch - Unit i Valve Testing Program Sh. 15 of 33 St roke VaIve Code Norm Iime ReIlef geo . Class Cat Desc ri ot ion Coord. PklO function Pos Exe rc i se leakaee Rea'd Ileaumat

[41-f001 2 8 10" Mo Cate E-12 H-16332 HPCI Steam Supply C Qtr NA Yes Shutoff' E41-f002 1 A 10" M0 Cate C-2 H-16332 HPCI Steam Supply 0 Qtr ClV Yes 6.1.2 Inbrd. Iso E41-IOO3 1 A 10" Mo Cate C-4 H-16332 IIPCI Steam Supply 0 Qtr CIV Yes Outbrd. 150

[41-8004 2 11 16" Mo Cate D-9 H-46332 HPCI Pump Suc. O Qtr NA Yes from Cond. Stor.

[41-IOory 2 C 14" Check I-6 11-16332 HPCI Pump disch. C Note 5 NA No E41-f006 2 A 14" MO Gate E-5 H-16332 HPCI Pump anbrd. C See 6.1.10 PlV Yes 6.1.10

~ Di scla. Iso 141-f007 2 8 14" Mo Cate E-6 H-16332 IIPCI Pump outbrd. O See 6.1.10 NA Yes 6.1.10 Disch.

141-I008 2 8 10" MO Clobe D-7 H-16332 HPCI Pump lest C Note 1 NA No Hypass L41-f011 2 S 10" M0 Cate C-7 H-16332 IIPC I Punip Redun. C Note 14 MA No Shutoff to Cond. Stg.

[41-5012 2 A 4" Mo Cate F-1 H-16332 elPCI Pump Min. Flow C Qtr CIV Yes 6.1.2 inbrd. Iso

[41-f019 2 C 16" Check D-9 H-16332 HPCI Pump Suc. C hote 5 NA No 4 from Cond. Stg.

j I41-f021 2 AC 12" Stop Ciecek C-3 H-16332 HrCI turb. Exh. C See 6.1.12 CIV No 6.1.11 l ub s al. Iso 6.1.12 l

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O) e (a3 (a3 SYSTEM: High Pressure Coolant injection Plant Hatch - Unit 1 Valve Testing Prograa . Sh. 16 of 33 i s Stroke Valve Code Norm Time Relief

_lgo . Class Cat Desc ri p t ion Coo rd . P&lD function Pos E xe rc i se Leakaee Rea'd Reauest

[41-F022 2 AC 2" Stop Check C-84 11-16332 IIPC I Tierb. Exh. C See 6.1.12 CIV leo 6.1.11 Drn. torus Iso 6.1.12 E41-F02$ 2 B 1" A0 Globe J-8 11-16333 Ba r Cond. Cooling C Qtr NA Yes Ef1-f026 4 2 B 1" A0 Clobe J-8 61-16333 Ba r cond. Cooling C Qtr NA Yes I41-f 035 2 B 2" A0 PCV C-8 11-16333 IIPC I inerb. Lube C Note 10 NA 10 0 Oi1 Cooling E41-f040 2 AC 2" Check C-5 11-16332 itPCs Iurb. Lah. C See 6.1.12 CIV No 6.1.12 Drn. Torus i so y L41-F041 2 6 16" MO Cate D-8 11-16332 itPCI Pump Suc. - C Qtr NA Yes Sliutoff E41 - F Ola2 2 A 16" MO Cate J-5 H-16332 IIPCI Pump suc. C Qtr CIV Yes Torus Outbrd. Iso E41-F04S 2 C 16" Check J-7 11-16332 HPCI Pump Suction C See 6.1.13 NA No 6.1.13 Et4 1-IO164 2 AC 4" Check F-8 H-16332 IIPCI Pump Min flow C Note 5 CLV No Outbrd. Iso E41-fois9 2 AC 20" Check G-84 11-16332 ItPCI Turb. Exh. C See 6.1.12 CIV No 6.1.12 Outbrd. 150 E8:1-f051 2 A 16" A0 Ufy J-84 61-16332 IIPC I Pump Suc. O :Qtr Civ Yes To ries inbrd. Iso E41-F059 2 8 2" MO Globe F-8 H-16333 IIPCI Turb. Lube Oil C Qtr NA Yes CooIeng Lf1-f104 4 2 A 2" Mo Cate G-3 11-16332 li t*C l vac. Re1ier 0 Qtr ClV Yes outbrd. Torus Iso E41-f111 2 A 2" MO Cate C-2 11-16332 llPCI Vac. Relier 0 Qtr CIV Yes inbrd. Torus 150

~ %s SYST[M: Reactor Core isolation Cooling Plant flatch - Unit i Valve Testing Program Sh. 17 of 33 Stroke Valve Code Nore Time Relief No. Class Cat Description Coo rd . PalD function Pos Exe rc i se teaksee Ree'd Reauest ES1-F001 2 AC 10" Stop Check C-5 H-16334 RCic Turb. Exh. C See 6.1.12 C8V No 6.1.11 to Torus Iso 6.1.12 E51-F002  ? AC 2" Stop Check C-6 H-16334 RCIC Vac Pump C See 6.1.12 CIV leo 6.1.11 Disch, to Torus Iso 6.1.12 ESt-F003 2 A 6" A0 Bfly J-6 H-16334 RCIC Pump Suction 0 Qtr CIV Yes 6.1.2 Torus Iso E51-f007 1 A 14 " MO Cato C-5 li- 163 3fs RCIC Stease Supply 0 Qtr CIV Yes 6.1.2 Inbrd. Iso ESI-f008 1 A 8" 6 MO Cate C-6 H-16334 HCIC Steam Supply 0 Qtr CIV Yes Ou tb rd iso E$1-F013 2 A 4" MO Gato E-6 H-163384 HCIC Feedwater inj. C QLr PlV Yes E51-F019 2 A 2" MO Globe F-7 H-16334 HCIC Pump Min. Flow C Note 8 ClV No 6.1.2 Torus Iso E$1-F021 2 AC 2" Check F-8 H-1633:4 HCIC Pump Min. Flow C Note $ ClV No Torus Iso E$1-F028 2 AC 2" Check C-1 11-163384 RCIC Vac. Pump Disch. C See 6.1.12 CIV No 6.1.12 Torus Iso E$1-f031 2 A 6" MO Gate J-6 H-16334 RICI Pump Suction 0 Qtr CIV Yes Torus Iso E51-F010 4 2 AC 10" Check C-5 H-1633ts RCIC lurb. Exh. C See 6.1.12 CIV Yes 6.1.12 Torus Iso E51- F 1014 2 A 1-1/2" Ho Cato C '2 H-16334 lu:lC Vac. Brker 0 Qtr ClV Yes 6.1.2 lorus Iso E51-F105 2 A 1-1/2" MO Gate 'G-5 14-163384 RCIC Vac. Brker 0 Note 10 ClV Yes Torus Iso

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O O SYS1[M: Hadwaste Plant Hatch - Unit 1 Valve Testing Program Sh. 18 of 33 Stroke Valve Code Norm Time Relief No. Class cat Desc ri p t ion Coo rd . P4fD Function Pos Exe rc i se leakaee Rea'd t -- at G11-FOO3 2 A 3" A0 Cate B-3 H-16176 DW f i r. Drns. 0- Qtr CIV Yes Cont. Iso G11-IOO4 2 A 3" AO Cate B-3 H-16176 DW Ii r. Drns. O Qtr CIV Yes Cont. Iso Cll-IOl9 2 A 3" AO Cate E-3 14-16176 DW Equip. Drns. O Qtr CIV Yes i Cont. Iso 1

I C11-f020 2 A 3" AO Cate E-4 14-16176 DW Equip. Drns. O Qtr ClV Yes Cont. Iso

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O SYSTEM: Reactor Water Cleanup Plant Hatch - Unit i Valve Testing Program Sh. 19 or 33

- Stroke

' Valve Code Norm Time Roller No. Class Cat Desc ri pt i on Coo rd . Parl D runction Pos Exe rc i se teakane Rea'd ?_r --- s t C31-F001 1 A 6" MO Cate B-2 11-16188 RWCU Pump Suc. O Qte CIV Yes inbrd. Iso C31-IUOl4 1 A 6" MO Cate D-3 11-16188 RWCU Pump Suc. O Qtr CIV Yes Ou t b rd . Iso G31-IO39 1 A 86 " Check A-5 11-16188 RWCU Disch. Iso O R0 CIV No 6.1.1

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O O O I SYSTEM: Demine ra l i zed Wa te r Plant Hatch - Unit i Valve Testing Program Sh. 20 of 33-Stroke Valve Code Norm Time Roller Jo . Class Cat Desc ript ion Coord. Pkl0 Function Pos Exe rci se Leakaos Rea'd Reauest P21-F353 2 AE 2" Manual Gate F-7 H-16015 Demin. Water LC Note .1 CIV - No 4 Cont. Iso 1 P21-f8064 2 AE 2" Manual Cate F-8 H-16015 Cont. Iso LC Note 1 CIV No t

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O O O SYSilM: 112 and Oy Analyter Plant Hatch - Unit I V.elvo lesting Prog ram Sli . 21 or 33 St roke V.ilve Code Norm Time Relier No. Class Cat Descrigtion Coord. P&lD Function, Pos l_xnreise leakaue Rea'd Reeuest P33-f002 2 A I" AO Control 0-8e 14-16276 H 2 & Og Analy. o 4tr CIV Yes Cont, sho P33-f003 2 A I" A0 Control 0-4 H-16276 H O Qtr CIV Yes C$n& t. Og IsoAnaly.

P33-F004 2 A I" A0 Control L-4 H-16276 Hg&Of Analy. O Qtr CIV Yes Cont. Iso P33-fuG6 2 A 1" A0 Control C-8s 11-16216 lig & Og Analy. O Qtr CIV Yes Cont. Iso P33-f001 2 A 1" AO Control H-4 H-16216 Hg & 02 Analy. O 4tr CIV Yes Cont. Iso P33-f010 2 A 1" AO Control B-5 H-16276 Hg&O2 Analy. O Qtr CIV Yes Cont. Iso P33-foll 2 A 1" A0 Control D-5 H-16276 H2 & Og Analy. O Qtr ClV Yes Cont. 150 P33-I012 2 A 1" AO Control E-5 H-16276 H 2 &O2 Analy. O Qtr CIV Yes Cont. iso P33-F014 2 A 1" A0 Control G-5 H-16276 H2 & Og Analy. O Qtr CIV Yes Cont. Iso P33-F015 2 A 1" AO Control H-5 H-16276 H2 & Og Analy. O Qtr CIV Yes Cont. Iso

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G SYS1FM: Plant Service Water Plant Hatch - Unit i Valve Testing Program Sh. 22 or 33 St roke Valve Code Norm Time Roller No. Class Cat Desc ri p t ion Coo rd . P&lD function Pos Exe rc i se Leakaos Rea'd Reauest P41-f023A 3 C 2" Check A-10 H-16011 CRD Pump Room Cooler 0 Note 11 NA No P41-f023B 3 C 2" Check B-10 11-16011 CRD Pump Room Cooler 0 Note 11 NA No Pist-f023A 4 3 C 1-1/2" Check 0-8 41-16011 IIPCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 P41-f028B 4 3 C 1-1/2" Check C-8 11-16011 IIPCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 P41-1025A 3 C 3" Check D-8 11-16011 RilR & CS Pump Room C See 6.1.14 NA No 6.1.14 Cooler P41-F025[1 3 C 3" Check D-8 11-16011 RilR & CS Pump Hoom C See 6.1.14 NA No 6.1.14 Cooler P81-f026A 4 3 C 3" Check G-7 11-16011 lulR Pump Cooler C See 6.1.186 NA No 6.1.14 P41 - F 026l1 3 C 3" Check C-7 H-16011 RilR Pump Cooler C See 6.1.14 NA No 6.1.14 P41-f028A 3 C 1-1/2" Check C-2 H-16011 RCIC Pump Room C See 6.1.14 NA No 6.1.14 Coo l e r P41-f028B 3 C 1-1/2" Check C-3 11-16011 RCIC Pump Room C See 6.1.14 NA No 6.1.14 Cooler Pfal-f 035A 3 11 2" A0 Clobe D-9 11-16011 IIPCI Pump Room C Qtr NA Yes 6.1.15 Cooler Pfa l-l O 3 Sin 3 11 2" A0 Globe C-9 11-16011 IIPC I Pump Room C Qtr NA Yes 6.1.15 Cooler P41-f036A 3 11 3" A0 Clobe D-9 11-16011 RilR & CS Pump C Qtr NA Yes 6.1.15 l{uom Cooler P41-f0360 3 il 3" Ao clube D-9 11-16011 RilR & CS Pump C Qtr NA Yes 6.1.15 Room Cooler

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SYSTEM: Plant Service Water Plant flatch - Unit 1 Valve Testing Program Sh. 23 or 33 Stroke Valve Code Norm Time Roller No. Class Cat Desc ri pt i on Coord. PUD Function Pos Exe rc i se Leakaoe Rea'd Reauest P41-F037A 3 8 1-1/2" AO Globo 41- 8 11-16011 filiR Pump Cooler C Qtr NA Yes 6.1.15 P41-F0378 3 15 1-1/2" AO Clube E-9 0-16011 RilR Pump Cooler C Qtr NA Yes 6.1.15 P41-f037C 3 0 1-1/2" AO Globe J-8 11-16011 HilR Pump Cooler C Qtr NA Yes 6.1.15 P41-iO370 3 0 1-1/2" A0 Clube E-9 11-16011 RilR Pump Cooler C Qtr NA Yes 6.1.15 P41-F039A 3 Fl 3" A0 Globe G-8 41-16011 RilR Pump Cooler C Qtr NA Yes 6.1.15 P41-f0390 3 11 3" A0 G1obe G-8 Il-16011 RilR Pump CooIer C Qtr NA Yes 6.1.15 P41-F040A 3  !! 2" A0 G1obe 11 - 2 11-16011 RC1C Pump Room C Qtr NA Yes 6.1.15 Cooler P41-F040B 3 15 2" A0 Clube 11 - 3 11-16011 RCIC Pump Room C Qtr NA Yes 6.1.15 Coo l e r P41-F042A 3 8 3" A0 Globe A-10 H-16011 CRD Pump Room 0 Qtr NA Yes 6.1.15 Coo le r P41-for:28 3 0 3" A0 Globe Il- 10 11-16011 CR0 Pump Room 0 Qtr NA Yes 6.1.15 Cooler P41-F049 2 A 8" MO Cate F-6 11-16011 D rywe l l Air 0 CS CIV Yes 6.1.16 Cooler Iso P41-F050 2 A 8" M0 Gate D-2 11-16011 D rywe l l Air 0 CS CIV Yes 6.1.16 Coo l e r I so P41-F064 3 C 6" Check F-10 11-16011 Division I supply 0 Note 11 NA No P41-1065 3 C 8" Check G-10 16-16011 Divir. ion il supply 0 Note 11 NA No

O O O SYSTEM: Plant Service Water Plant llatch - Onit i Valve Testing Program Sh. 24 of 33 Stroke Valve Code Norm Time Relief No. Class . Cat Description Coo rd . PalD function Pos E xe rc i se Leakaoe Ree'd Renaamat P41-f208A 3 8 3" AO PCV - D-11001 S.W. Press Regulator 0 Note 9 NA No P41-f208B 3 8 3" A0 PCV -

D-11001 S.W. Press Regulator 0 Note 9 NA No P41-F208C 3 Il 3" A0 PCV -

D-11001 S.W. Press Regulator 0 Note 9 NA No P41-F208D 3 8 3" AO PCV - D-11001 S.W. Press llegulator 0 Note 9 NA No P41-I310A 3 B 30" MO Brly -

D-11001 Iurb. Bldg. Supply 0 CS NA Yes 6.1.17 Shutoff P41-F310B 3 11 30" MO lirly -

D-11001 turb. ti l d g . Supply 0 CS NA Yes 6.1.17 Shutorr P41-f310C 3 0 30" MO tirly - D-11001 .rurb. Bldg. Supply 0 CS NA Yes 6.1.17 Shutorr P41-1310D 3 il 30" HO lirly -

D-11001 lurb. Ilidg. Supply 0 CS NA Yes 6.1.17 Shutoff P41-f311A 3 B 18" Check -

D-11001 Pump Di scha rge O Note 11 NA No P41-f311B 3 B 18" Check -

D-11001 Pump Discharge O Note 11 NA No P41-F311C 3 8 18" Check - D-11001 Pump Discha rge O Note 11 NA No P41-f311D 3 il 18" Check -

D-11001 Pump Discharge O Note 11 NA No

. - . _ , . _ .. - . _ _ _ _ _ _ . _ . . . . _ . . . _ _ _, _ _ . _ __.-..__m. ____ . - . . _ . _ . . . _ - . . . _ . ._ , __~.__ _ _ . . . _ . _ . . . _ . _ _ . ._ _

7 O O O 1

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SYSTEM

RB Closed Cooling Water Plant Hatch - Unit 1 Valve Testing Program Sh. 25 of 33 Stroke

$ Valve Code Norm ' Time Relief Jo . Class Cat _ Description Coo rd . Parl D Function Pos Exe rci se Leakaos Rea'd Reaumat  ;

]  !

j Pa2-FOS s 1 2 A sad Ho Cate B-9 H-16009 .RBCCW to Recir. O CS CIV Yes 6.1.18 Cont. Iso f P842- F052 2 A la" MO Cate E-9 H-16009 RBCCW to Recir. O CS C1V Yes 6.1.18  ;

j Cont. 150 i

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! SYSTEM: Servico Ai r Plant Hatcle - Unit 1 Va l ve T es t i ng Prog ram , Sh. 26 of 33 4

! Stroke i Valve Code .

Norm Time Relief i No. Class Cat De sc ri pt ion Coo rd . PartD Function Pos Exe rc i se Leaksee Rea'd Reauest i

PSI-I513 2 AE 2" Man. Globo F-3 H-16013 . Se r. Ai r Cont. Iso LC Note 1 CIV No

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PSI-f51:4 2 AE 2" Man. Globe I-3 H-16013 Ser. Ai r Cont. Iso LC Note 1 CIV No 1

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O O O SYSTEM: Drywell Pnetma t ic Plant Hatch - Unit 1 Valve Testing Program Sh. 27 of 33' Stroke 4

Valve Codo Norm Time Relief i No. Class Cat Descriotion Coord. Par t D Function' Pos Exe rc i se ' Leakane Ree'd Reauest l P70-F002 2 A 1" A0 Control F-8 H-16236 DW Pneumatic Cont. O Qtr. CIV Yes i iso 1

P70-F003 2 A 1" AO Control F-8 11-16286 DW Pneumatic Cont. O Qtr CIV Yes Iso P70-F004 2 A 2" A0 Control C-8 11-16286 DW Pneumatic Cont. O QLr CIV Yes i Iso PTO-FOOS 2 A 2" AO Control D-8 11-16286 DW Pneumatic Cont. O QLr CIV Yes 1 Iso 1

I P70-IO2O 2 AC 2" Clieck C-7 11-16286 DW Pneumatic Cont. O RO ClV No 6.1.1 j iso l

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SYSIEM

Standby Cas Ireatment Plant Hatch - Unit 1 valve Testing Program Sh. 28 of 33

' Stroke

' Valve Code Norm Time Relief.

No. Class Cat Desc ri pt ion Coord. Parl[) Function Pos Fxercise Leakaee Rea'd Reauest I 146-tOO1A 3 8 18" AO Brly C-1 11-16020 f i l te r Ded inlet C Qtr' NA- Yes f rom iteactor Bldg.

146-f001B 3 8 18" AO Brly C-1 14-16020 Fil ter Red inlet C Qtr NA Yes

' f rom Reactor Bldg.

146-f002A 3 8 18" A0 Brly C-6 H-16114 F i l te r Ded C Qtr NA. Yes l

Discharge

) 146-f002B 3 8 18" A0 Brly F-6 H-16114 ri t ter Red C Qtr NA Yes i D i scha rge i

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f n n SYSTEM: Containment Purge and Inerting Plant flatch - Unit i Valve Testing Program Sh. 29 of 33 Stroke Valve Code Norm ilme Relief No. Class Cat Dels_c_r r ip t i on Coord. falD Flyic don Pos Fxe rc i se Leakaee Ree'd Reeuest.

148-F103 2 A 6" AO Brly F-2 11-16000 DW & lorus Supply C Qtr CIV Yes Iso T48-F104 2 A 1" AO Control C-4 11-16000 Dwg & Torus C Qtr CIV Yes Ou tb rd . Iso 148-F113 2 A 2" AO Control F-/ H-16000 DW Inerting Outbrd C Qtr ClV Yes Iso l

T48-F114 2 A 2" A0 Control F-8 11-16000 DW Inerting Inbrd C QLr CIV Yes Iso I48-F115 2 A 2" A0 Control C-7 41-16000 DW Inerting Outbed C QLr CIV Yes

Iso

il8-F116 l 2 A 2" A0 control G-8 11-16000 DW Inerting Outbrd C Qtr CIV Yes l

Iso 4

T48-I118A 2 A 1" Solenoid C-5 H-16000 Torus Makeup 0 QLr CIV Yes i inbrd Iso 1

Ita8-f118B 2 A 1" Solenoid G-5 H-16000 lorus Maheup 0 QLr CIV Yes i nb rd iso 148-I321 2 A 2" AO Control J-7 11-16000 DW Inerting C Qtr ClV Yes i Outbrd. Iso j 148-F322 2 A 2" A0 Control J-8 16-16000 DW l eie r t i ng C Qtr CIV Yes Inbrd Iso

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4 j 184 8-F 325 2 A 2" A0 Control 11 - 7 li-16000 Torus inerting C Qtr CIV Yes Outbol. iso I48-f327 2 A 2" A0 Contiol 11 - 8 11-16000 locus inerting C QLr CIV Yes i nb rd . Iso l 4

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O O O SYSTEM: Containment Purge and inerting Plant flatch - Uni t 1 Valve Testing Program Sh. 30 of 33 Stroke l Valve Code Norm Time Roller

__No.

Class Cat De sc ri p t ion Coo rd . P&[Q function Pos Exercise Leakaae Rea'd Reauest T48-F307 2 A 18" AO Brly C-9 11-16024 DW Purge inlet C Note 1 CIV No Inbrd iso T48-f308 2 A 18" AO Brly C-10 H-16024 DW Purge inlet C Note 1 CIV No I nb rd Iso T48-F309 2 A 18" A0 Bfly [-10 11-16024 Torus Purge C Note 1 CIV No i n i c't inbrd Iso T48-I310 2 A 20" AO Brly F-10 11-16024 f orus Purge Vac. C Qtr CIV Yes q

Brker Iso I48-I311 2 A 20" A0 lirly F-9 11-16024 Torus Purge Vac. C QLr ClV Yes

- Brker I so 5

T48-f318 2 A .18" A0 Bfly C-4 18-16024 T o n.s Purge 0 Qtr CIV Yes outlet inbrd Iso 148-I319 2 A 18" A0 Brly D-4 H-16024 DW Purge C Note 1 CIV No Outlet inbrd Iso 148-I320 2 A 18" AO Brly 0-3 H-16024 DW Purge Outlet C Note 1 CIV No Outbrd Iso T48-f323A 2 C 18" AO Check 11 - 8 11-16024 DW to Torus Vac. C QLr NA No B rea ke r 148-I323B 2 C 18" AO Check 11 - 8 18-16024 DW to lorus Vac. C Qtr NA No B rea ke r 148-F323C 2 C 18" AO Check H-8 H-16024 DW to torus Vac. C Qtr NA No 11rea ke r

! T48-I323D 2 C 18" A0 Check it-8 11-16024 l)W to lorus Vac. C Qtr NA No B rea ke r T48-F323E 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C QLr NA No B rea ke r 1

e

l SYSTEN: Containment Purge and Inerting Plant flatch - Unit i Valve Testing Program Sh. 31 of 33 St roke Valve Code Norm Time Relief i

No. Class Cat De sc riglion Coo rd . PAID function Pos Exe rc i se Leakaee Rea'd Reauest T48-f323f. 2 C 18" A0 Check H-8 H-16024 DW to f orus Vac. C Qtr NA No B rea ke r 148-F323G 2 C 18" AO Check 11- 8 H-16024 DW to lorus Vac. C Qtr NA No B rea ke r T48-f323H 2 C 18" AO Check H-8 11-16024 DW to Torus Vac. C Qtr NA No

. Brea ke r I48-F3238 2 C 18" Ao Check 11 - 8 it-16024 DW to lorus Vac. C Qtr NA No B rea ke r 4

T48-F323J 2 C 18" Ao Check it-8 H-16024 DW to forus Vac. C Qtr NA No

Brea ke r l 148-f323K 2 C 18" A0 Check 11 - 8 H-16024 DW to Torus Vac. C Qtr NA No Brea ke r l

T48-F323L 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No B rea ke r l 148-F324 2 A 18" AO BFly D-10 H-16024 f orus Purgo C Note 1 CIV No j inlet Outbrd. Iso f T48-F326 2 A 18" A0 Bfly C-3 H-16024 lorus Purge 0 Qtr Cl7 Yes Outlet Outbrd. Iso a

l I48-F328A 2 AC 20" AO Check C-10 H-16024 Heactor Hldg. to C Qtr CIV No Supp res s ion Cham Vac. Brker T48-f328B 2 AC 20" A0 Check C-9 H-16024 Reactor Bldg. to C Qtr ClV No Suppsatssion Cham Vac. Brker d

1 4

5 i

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G,O LJ SYSTEM: Containment Purge and inerting Plant Hatch - Unit 1 Valve Testing Program Sh. 32 or 33 Stroke Valve Code Norm Time Roller

_No. Class Cat Desc r ip tion Coord. P440 Function Pos Exe rc i se leakaae Rea'd Reauest T48-I332A 2 A 2" AO Control E-3 11-16024 Torus Purge C QLr CIV Yes Outlet Outbrd iso T48-F332B 2 A 2" AO Control F-3 61-16024 Torus Purgo C Qtr CIV Yes Outlet Outbrd Iso Tf8-F333A 4 2 A 2" AO Control E-la 11-160284 Torus Purge C Qtr CIV Yes Outlet inbrd Iso 188-I3330 4 2 A 2" AO Control F-4 11-160214 Torus Purge C Qtr ClV Yes Outlet i nb rd Iso 184 8-F 3384A 2 A 2" A0 Control 0-3 H-16024 DW Pu rge ou t l e t C Qtr CIV Yes '

Outb rd iso 148-F3318 4 2 A 2" AO Control C-3 11-160214 DW Purge Outlet C Qtr CIV Yes Ou tb rd Iso T48-F335A 2 A 2" AO control 8 - 14 H-160214 DW Pu rge Ou t le t C Qtr CIV Yes i nb rd iso T48-F3350 2 A 2" AO Control C-4 41-16024 DW Purge Outlet C Qtr CIV Yes i nb rd 150 T48-F338 2 A 2" Solenoid 11 - 2 H-16021: Bypass-Outbrd Iso C Qtr ClV Yes 148-F339 2 A 2" Solenoid 18 - 3 11-16024 Bypass-Inbrd Iso C Qtr ClV Yes 184 8-F 384 0 2 A 2" Solenoid D-4 H-160214 Bypass-Outbrd iso C Qtr CIV Yes TI8-I341 4 2 A 2" Solenoid D-Is H-160284 Bypa ss- I nb rd iso C Qtr CIV Yes

SYSifM: Containment Purge and inerting Plant Hatch - Unit i Valve Testing Program Sh. 33 of 33 Stroke Code Norm Time Relier Valve Pos Exo rc i se leakage Rea'd Reauest No. Class Cat Description Coo rd . P&LD function H-16D24 C Note 12 CIV No 148-F342A 2 A 1/2" Solenoid it-8 forus to DW Vac B rea ke r I so T48-r342B 2 A 1/2" Solenoid 11 - 8 11-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso 148-I342C 2 A 1/2" Solenoid 11 - 8 11-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso 2 A 1/2" Solenoid 41-16024 Torus to DW Vac C Note 12 CIV No 148-F342D 64 - 8 Breaker Iso 148-I342E 2 A 1/2" Solenoid 11 - 8 11-16024 Torus to DW Vac C Note ik ClV No Breaker Iso H-16024 C Note 12 CIV No 148-F342F 2 A 1/2" Solenoid 11 - 8 Torus to DW Vac Breaker Iso 148-f342C 2 A 1/2" Solenoid 11 - 8 11-16024 Torus to DW Vac C Note 12 CIV No Breaker iso 148-f342tl 2 A 1/2" Solenoid 11 - 8 11-16024 forus to DW Vac C Note 12 CIV No Breaker Iso 2 A 1/2" Solenoid 14-16024 Torus to DW Vac C Note 12 CIV No

, 148-F3421 11 - 8 t Breaker Iso 4

148-F342J 2 A 1/2" Solenoid 11 - 8 11-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso 148-I342K 2 A 1/2" Solenoid 11 - 8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker 1so a

148-f342L 2 A 1/2" Solenoitt Il-8 11-16024 f o rus to DW Vac C Note 12 ClV Na Breaker Iso j

I

Q ry p\

h SYST[M: Main Steam & Feedwater Plant flatch - Unit 2 Valve Testing Program Sh. 1 of as2 Stroke Valve Code Norm Time Relief

_Ito . Class Cat Descripdon Coord. P&lD Functi_on Pos Exe rc i se Leakage Rea'd Reauest 2821-f010A 1 AC 18" Check E-3 H-26000 IW Inbrd. Cont.lso. O RO CIV No 6.1.1 2821-f0108 1 AC 18" Check r-3 H-26000 IW Inbrd. Cont.lso. O RO ClV No 6.1.1

2821-f013A 1 C 6" Relier D-6 H-26000 Main Steam Relief' -

Note 3 NA No 2821-1013B 1 C 6" Relier D-6 H-26000 Main Steam Relier -

Note 3 NA No 2tl21-fol3C 1 C 6" Relier D-6 18-26000 Main Steam Relier -

Note 3 NA No 2821-f013D 1 C 6" Relier D-6 11-26000 Main Steam itelief' -

Note 3 NA No 2B21-IO13E 1 C 6" Relier D-6 18-26000 Main Steam Relier -

Note 3 NA No 2B21-f013F 1 G 6" Relier D-6 11-26000 Main Steam Relier -

Note 3 NA No 2B21-F013G 1 C 6" Relier D-6 H-26000 Main Steam Relier -

Note 3 NA No 2821-F013H 1 C 6" Relier D-6 H-26000 Main Steam itelier -

Note 3 NA No 2821-f013K 1 C 6" Relier D-6 H-26000 Main Steam Relier -

Note 3 NA No 2B21-f013L 1 C 6" Relier D-6 11-26000 Main Steam Relief' -

Note 3 NA No 2B21-6013M 1 C 6" Relier D-6 H-26000 Main Steam Relier -

Note 3 NA No 2821-F016 1 A 3" Mo Cate E-8 H-26000 Main Steam Line C Note 1 CIV No 6.1.2 DRN. Inb. Iso.

4 2821-F019 1 A 3" Ho Cate t-9 H-26000 Main Steam Line C Note 1 ClV No

. DRN. Inb. Iso.

i 2tl21-IO22A 1 A 28 " A0 Globe 6 D-8 H-26000 MSlV O Qtr. CIV Yes 6.1.23 2821-F0228 I A 23 " A0 Clobe 4 D-8 H-26000 MSIV O Qt r. CIV Yes 6.1.23 2821-IO22C 1 A 28 " A0 Globe 4 D-8 H-26000 MSIV O Qtr. CIV Yes 6.1.23 i

e

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v-SYSILM: Main Steam & feedwater P l a n t fla tch - Un i t 2 Va l ve T e s t i ng P rog ram Sh. 2 of 42 St roke Valve Code Norm Time Relief Class cat Description Consd. P&lD function Pos Exe rc i se Leakaae 'Rea'd Renaamst

_Mo.

2821-F022D 1' A 24" AO Clobe D-8 11-26000 MSIV 0 Qtr. CIV Yes 6.1.23-2021-I028A 1 A 24" AO Clobe D-9 11-26000 MSIV O Qt r. CIV Yes .6.1.23 2821-I028B 1 A 24" AO Clobe D-9 11-26000 MSIV O Qtr. CIV Yes 6.1.23 2821-F028C 1 A 24" A0 Globe D-9 61-26000 MSIV O Qtr. CIV Yes 6.1.23 2B21-F0280 1 A P4" AO Clobe D-9 Il-26udo MSiv 0 Q t r. ClV Yes 6.1.23 2B21-F037A 3 C 6" Check E-1 11-26000 Vac. lirea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

i 2821-f0318 3 C 6" Check I-I 61-26000 Vac. lirea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

2821-I037C 3 C 6" Check E-7 64-26000 Vac. Ilrea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch, 2821-F037D 3 C 6" check E-7 H-26000 Vac. lirea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch, a 2821-I037E 3 C 6" Check I-7 11-26000 Vac. lirea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

4 2821-I03/r 3 C 6" Check L-7 11-26000 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

2B21-f037C 3 C 6" Check E-7 11-26000 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSRV Disch.

I

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O O O SYSTEM: Main Steam & reedwater Plant Hatch - Unit 2 Valve Testing Program Sh. 3 of.42 Stroke Valve Code Norm Time Roller No. Class Cat DescriEtion Coo rd . P&lD runc.gion Pos Exe rc i se Leakaoe Ree'd Reauest 2821-F037H 3 C 6" Check E-7 H-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.

2821-F031K 3 C 6" Check E-1 11-26000 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSHV Disch.

2821-F037L 3 C 6" Check E-7 11-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSHV Disch.

2821-F037M 3 C 6" Check E-l 11-26000 Vac. B rea ke r C See 6.1.3 NA No 6.1.3 MSitV Di sch.

2821-FOl6A 2 C 18" AO Check E-2 H-26000 lW Clieck 0 Note 13 NA No 2821-f0168 2 C 18" Ao Check F-2 11-26000 FW Check 0 Note 13 NA No 2821-F077A 1 AC 18" AO Check E-3 H-26000 IW Outbrd Iso o Note 13 CIV No 2821-I0778 1 AC 18" A0 Check E-3 H-26000 FW Outbrd-Iso 0 Note 13 CIV No

O O O SYSTEM: Reactor Recirculation System Plant Hatch - Unit 2 Valve Testing Program Sh. 4 of 42 Stroke Code Norm Time Relief Valve Pos Exe rci se Leekaee Ree'd Itenuest peo . Class Cat Desc ri p tion Coord. PkID Function i 2831-F013A 1 AC 3/4" Check C-3 11-26003 Reci r. Pump Sea l WLr 0 RO CIV No 6.1.1 2831-fol38 1 AC 3/4" Check C-3 11-26003 Recir. Pump Seal Wtr 0 RO CIV No 6.1.1 3/4" Check C-2 H-26003 Recir. Pump Seal Wtr 0 RO CIV No 6.1.1 2831-f017A 1 AC 2B31-fol78 1 AC 3/4" Check G-2 31-26003 Recir. Pump Seal WLr 0 R0 CIV No 6.1.1 2831-5019 I A 1" AO Globe E-4 H-26003 Reac. Sample Sys. O QLr CIV Yes i nb rd . Iso A 1" A0 Clobe E-2 11-26003 Reae. Sampic Sys. O QLr CIV Yes 21531-F020 1 lubsd. Iso 2831-F031A 1 B 28" M0 Cate C-7 11-26003 Reactor Recirculation 0 CS NA Yes 6.1.4 2831-f0318 1 B 28" MO Cate C-7 H-26003 Reactor Reci rculation 0 CS NA Yes 6.1.4 i

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O O O SYSIIM; Standby L.iquid Control Plant Hatch - Unit 2 Valve Testing Program Sh. 5 of.as2 Stroke VaIvo Code Norm Time ReIlef No. Class Cat Description Coo rd . PAID Function Pos Exe rc i se Leakaee Rea'd Resumat 2C81-FOO8sA 4 2 D 1-1/2" Expl E-2 H-26009 SLC Explo Act C Note le NA No 2C41-f0048 2 D 1-1/2" Exp1 I-2 H-26009 SLC Explo Act C Note 4 NA No 2C41-f006 1 AC 1-1/2" Check E-2 H-26009 St C Outb rd C 18 mos. CIV No 6.1.5 Cont. Iso 2C41-IOO7 1 AC 1-1/2" Check F-1 H-26009 SLC' Ou t b rd C 18 mos. ClV No

! Cont. Iso 2Cl1-f029A 4 2 C 1" Relier E-5 18-26009 SLC Pump Disch. C Note 3 NA No

' Relier

! 2C41-F029B  ? C 1" Helier H '> 11-26009 SLC Pump Disch. C Note 3 NA No i

Relier 2C41-I033A 2 C 1-1/2" Check F-84 H-26009 SLC Pump Disch. C Qtr. NA No l 2C41-f033B 2 C 1-1/2" Check C-14 H-26009 SLC Pump Disch. C Qt r. NA No i

J

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i 9

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1 4

4 1

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i i

4

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SYSTEM: Fission Products Monitoring System Plant fla tcli - Uni t 2 Valve lesting Program Sh. 6 of Is2 Stroke Valve Code Norm Time Relief peo. Class Cat De sc ript ion Coo rd . Pgjp Function Pos Exe rc i se teakaoe Rea'd Reauest 2011-F050 2 A 1" AO Control D-5 H-26016 Fission Prod. Mon. O Qtr CIV Yes 4

Cont. Iso

. 2011-F051 2 A 1" A0 control F-5 11-26016 rission Prod. Mon. O Qtr CIV Yes

! Cont. Iso 2D11-f052 2 A 1" AO Control D-6 18-26016 Fission Prod. Mon. O QLr ClV Yes Cont. Iso i 2Dil-Fu53 2 A 1" AO Control F-6 H-26016 fissinn Prod. Mon. LC Qtr CIV Yes i

Cont. Iso J

2D11-F058 2 AE 1" LC Manual G-3 ll-26016 fission Prod. Mon. LC Note 1 CIV No Cont. Iso 2D11-F061 2 AE 1" LC Manual F-8 H-26016 Fission Prod. Hon. LC Note 1 CIV No Cont. Iso ,

u j

i i

y 1

4 1

I I

% ("h /*N SYSIEM: Residual llea t Remova l Plant flatch - Unit 2 Valve Testing Program Sh. 7 of 42 Stroke Valve Code Norm Time Roller A. Class Cat Desc rip t ion Coord. P&JD fianction Pos Exercise teakaae Rea'd Reeuest 2E11-f003A 2 B 16" MO Cate Viv D-4 it-26015 RilR lix Slie l l 0 Qtr NA Yes Side Outlet 2E11-FOO3B 2 0 16" MO Cate Viv E-8 18-260184 RilR lix Stie l l 0 Qtr NA Yes Side Outlet 2E11-F004A 2 A 284 " MO Cate Viv I-8 H-26015 RilR Pump Suction O Qtr CIV Yes Torus Iso 2E11-IOut8 4 2 A 284 " MO Gate Viv F-3 11-260184 HilR l'aimp Suet ion 0 Qtr CIV Yes lo rus lho 2011-foulC4 2 A 28 " Mo Cate Viv 6 E-9 11-26015 HilR Pu.op Suction 0 Qtr CIV Yes lorus Iso 2E11-IDO! 4D 2 A 28 " MO Gate Viv 4 F-2 11-260184 RilR Pump Suc 0 Qtr CIV Yes Turns Iso 2L11-IDO6A 2 0 20" M0 Cate Viv F-8 14-26015 RilR Shutdown C Qtr NA Yes Cooling Sys 2E11-LOO 6B 2 8 20" MO Cate Viv I-3 11-260184 RitR Shutdown C Qtr NA Yes CooIing Sys 2011-I006C 2 8 20" MO Cate Viv I-10 11-26015 HilR Slautdown C Qtr NA Yes Coo 1ing Sys 2E11-I0060 2 0 20" MO Cate Viv i-2 11-26014 HilR Shutdown C Qtr NA Yes CooIing Sys 2E11-F007A 2 A 4" MO Gate Viv D-5 H-260184 lulR Pump Min i Iow 0 Qtr CIV Yes 6.1.2 Torus Iso Pt11-I0010 2 A is" Hu G.ito Viv D-6 11-260186 luik Pump Min flow 0 Qtr CIV Yes 6.1.2

,m ,

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SYSTEM: Re s i dtsa l lleat Removal Plant Hatch - Unit 2 Valve Testing Program Sh. 8 of 462 -

Stroke Valve Code Norm line Relief No. Class Cat Desc ri p t ion Coord. Pacl D f ianc t ion Pos Exe rc i se Leakaee Rea'd Reeuest '

2E11-IOO8 1 A 20" MO Gate Viv D-10 ll-26015 HilR Shutdown C Note 1 PlV No Coo l i ng Outb rd Iso 2E11-I009 1 A 20" MO Cate Viv D-10 11-26015 RilR Shutdown C Note 1 PlV No Coo l ing Outb rd 150 2011-f011A 2 A 4" MO Cate D-3 26015 RiiR Cond. Disch. C Qtr CIV Yes 6.1.2 to lorus o

2E11-IO118 2 A 4" HO Cate 'D-8 H-260186 RilR Cond. Disch. C Qtr CIV Yes 6.1.2 to Torus ,

A 24" Mo Cate D-f it-26015 L PCI ou t b rd . C Qtr ply Yes 2 Ell-f015A 1 Cunt. Iso 2 Ell-f01$8 1 A 24" M0 Cate D-4 64-26014 LPCI Ou t b rd . C" Qtr PlV Yes Cont, iso 2 Ell-f016A 2 A 16" It3 Cate B-7 18-26015 Cont. Sp ray . C Qtr CIV Yes Ou tb rd . Iso 2 Ell-I0160 2 A 16" M0 Cate B-84 18-260184 Cont. Sp ray C Qtr CIV Yes

+

Ou tb rd . Iso 2 Ell-f011A 1 11 2 34 " M0 Cate D-T 18-2601') LPCI O Qtr NA Yes 2E11-folTB 1 B 21 " Ho Cate 4 .0-4 18-26014 LPCI O Qtr NA Yes 2E11-F019 1 C 4" Check B-2 11-26014 licad Spray . C Note 2 NA No 2E11-IO21A 2 0 16" MO Cate B-9 Il-26015 Containment Sp ray ,

C QLr NA Yes 2011-F0218 2 B 16" Mo Cate? C-2 18-26018s Cain t.s i nmen t Spray C Qtr NA Yes 2L11-f022 1 A 4" M0 Cate B-2 18-26014 blead Spray C Note 1 CIV No

O O O SYSTEM: Res i dtia l Heat Removal Plant Hatch - Unit 2 Valve Testing Program Sh. 9 of. as2 Stroke valve Code Norm Time Relief No. Class Cat Descriotion Coo rd . P&lD fainction Pos Exe rc i se Leaksee Hee'd Reauest 2E11-f023 1 A 4" MO Clobe B-3 H-260184 licad Spray Outbrd. C Note 1 CIV No Iso 2E11-f028A 4 2 B 16" MO Clobe C-6 H-2601S Suppression Pool C QLr NA Yes Cooling 2 Ell-f024B 2 B 16" MO Globe D-S 18-26018e Suppression Pool C Qtr NA Yes Cooling ,

2 E l l- f 02'; A 2 AC 1" Relier C-1 11-26015 LPCI Inj. C Note 3 CIV No i Cont. Iso 1

2E11-f 02Sil 2 AC 1" fte l ief' C-4 11-260184 L l'C l inj. C Note 3 CIV No

- Cont. Iso 2E11-f026A 2 A 4" MO Cate D-2 H-2601S Cond. Disch. to C Qtr CIV Yes RCIC Cont. Iso 2E11-f026B 2 A 4" Ma Cate E-9 H-26014 Cond. Disch, to C Qtr ClV Yes l

RGIC Cont. Iso i 2E11-f027A 2 B 6" MO Cato C-1 H-260lS Suppression Pool C QLr NA Yes i Sp ray 2E11-f027B 2 B 6" MO Cate D-S 18-26014 Suppression Pool C Qtr NA Yes Sp ray 2 Ell-f028A 2 A 16" MO Cate C-6 Il-2601S Suppression Pool C Qtr CIV Yes Spray Outbrd. Iso 2E11-IO28B 2 A 16" MO C.ste C-7 11-260114 Suppression Pool C Qtr CIV Yes Spr ay Outbrd. Iso

' 2L11-lo29 2 AC 1" ite l i ni f' l-9 il-26n t's itillt l' ump Sue C Note 3 CIV No

Cont. Iso  !

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J d. .O3 SYSifM: Residual iteat Removal Plant Hatcli - Unit 2 Valve Testing Program Sh. 10 of 42 Stroke Valve Code Norm Time Relief

_No. Class Cat Description Coo rd . PaelD function Pos Exe rc i se Leakaoe Rea'd Reauest 2E11-f030A 2 AC 1" Relief F-8 11-260184 RilR Pump Suction C Note 3 CIV No Cont. Iso 2E11-f030B 2 AC 1" Relief I' - 4 18-26015 RitR Pump Suction C Note 3 CIV No Cont. Iso 2E11-f030C 2 AC 1" Relief I-10 11-260114 RilR. Pump Suction C Note 3 CIV No -

Cont. Iso 2E11-50300 2 AC 1" Relief I-2 11-26015 RilR Pump Suction C Note 3 CIV No Cont. Iso 2E11-f031A 2 C 20" Cliec k 11 - 6 11-26019 RilR Pump Di sclia rge C Note S NA No 2011-IO31B 2 .C 20" Clice k 11 - 6 18-260114 RilR Pump Diseliarge C Note S NA No 2[11-f031C 2 C 20" Clieck it-9 11-2601$ RilR Pump Disclia rge C Note S NA No 2E11-f031D 2 C 20" Check 11 - 3 11-260184 HilR Pump Discha rge C Note 5 NA No 2E11-f011A4 2 A 1" A0 Control C-8 11-26015 RHR Inst. Iso 0 Qtr CIV Yes 2E11-f or atti 2 A 1" A0 Control D-2 11-26011 HilR inst. Iso 0 Qtr CIV Yes 2L11-fol1C i 2 A 1" AO Control C-8 11-26015 RitR inst. Iso  % 0 Qtr ClV Yes 2E11-f08104 2 A 1" A0 Control C-2 11-260184 DhR inst. Iso o

• Qtr ClV Yes 2E11-IOl6A 4 2 C 3" Clicck G-6 11-2601S IlllR Minimum flow Ling C k Note 29 NA No 2E11-fol6B4 2 C 3" Clieck 11- 5 11-2601:4 RilR Minimum flow Line C Note 29 NA No 2L11-f ul 6C l 2 C 3" Clicek C-9 Il-2601's lutR llinimum Ilow Line C Note 29 NA No 2L11-lul604 2 C 3" Clicek G-2 H-260114 RilR Minimum f'10w Line C Note 29 NA No

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SYSIEM: Residua 1 Heal Remova1 Plant liatcli - Unit 2 Vaive Testing Program Sh. 11 of 42 Stroke Valve Code Norm Time Relief Jo , Class Cat Duscription Coord. PaclD Function Pos Exe rc i se Leakage Rea'd Reauest 2E11-I017A 4 2 B 16" MO Cate E-5 Il-26015 HilR Hx Shell Sido 0 Qtr NA Yes Side inlet 2E11-F0478 2 B 16" MO Cate E-6 14-260184 RHR Hx Shell Side O QLr NA Yes Side inlet 2E11-F084 8A 2 B 284 " 840 Globe 0-5 H-26015 lutR Hx Shel l Side 0 QLr NA Yes Bypass 2E11-F018B 4 2 B 21 " MO Clobe 4 E-6 11-260184 RilR lix Shell Side 0 Qtr NA Yes Bypass 2E11-f050A 1 AC 18" Ao Check D-9 11-26015 LPCI Injec. Iso C See 6.1.7 PlV No 6.1.7 2 Ell-f050B 1 AC 18" AO Check D-3 11-260184 LPCI enjec. Iso C See 6.1.7 PlV No 6.1.7 2E11-f055A 2 AC 4" Relief F-14 H-26015 HilR lix Shel l C Note 3 ClV No Relief Cont. Iso 2E11-F055B 2 AC i" t Relief F-7 Il-260184 HilR lix Shell C Note 3 CIV No Relief Cont. Iso 2E11-I065A 2 8 284 " AO Bfly F-8 H-26015 HilR forus Suction 0 Qtr NA Yes 2 Ell-F065B 2 B 24" AO Bfly I-3 H-260184 RHR forus Suction 0 Qtr NA Yas 2 Ell-I065C 2 B 216 " A0 Bfly f-9 11-26015 RHR lorus Suct ion 0 Qtr NA Yes 2 Ell-I065D 2 B 214 " A0 Bfly F-2 11-260134 RilR f orus Suction 0 QLr NA Yes 2E11-I078A 2 C 10" check E-84 H-26015 RHR Hx Ser Wtr Tie C RO NA No 6.1.8 2011-F078B 2 C 10" Check I-T H-26018e f(llR H + Se r Wt r T i e C RO NA No 6.1.8 2E11-F091A 2 8 6" MO Clube E-2 H-26015 Steam Line to RHR C Qtr Na Yes HX Shutdown

O O O SY51[M: Residual Quat Removal Plant Hatch - Unit 2 Valve Testing Program Sh. 12 of" 42

- Stroke Valve code Norm Time Relief' No. Class Cal _ De sc ri p t ion Coo rd . P410 function Pos Exe rc i se Leakaee Ree'd Reauest 2E11-fo918 2 B 6" MO Clobe E-9 18-26014 Steam t.ine to RHR C Qtr NA Yes llX Shutdown 2E11-I097 2 AC 3" Relier E-9 11-26015- Steam Line Relief C Note 3 CIV No Cont. Iso 2E11-F103A 2 A 1" MO Globe E-4 H-26015 RilR lix Vent C Qtr CIV Yes Cont. Iso 2011-f103B 2 A 1" MO Clobe E-T 11-26014 RilR lix Vent C Qtr ClV Yes Cont. Iso 2E11-I140A 2 B 6" MO Gate E-2 ll-2601S Steam Line to 10lR C Qtr NA Yes llX Shutdown 2E11-F140B 2 0 -6" MO Ga te E-9 61-26014 Steam Iine to RilR C 4tr NA Yes HX Shutdown 2E11-lO68A 3 il 10" MO Ball C-10 18-26015 RilR Hx Ser. Wtr C Note 6 NA No Disch.

2E11-F068B 3 B 10" MO tlail C-10 H-26014 RilR lix Ser. Wt r C Note 6 NA No Disch.

2L11-lul3A 2 11 10" MO Cate G-4 11-2601S RilR Ser. Wtr intertie C Qtr NA Yes 2011-101315 2 11 10" MO Cate C-1 il-26014 RilR Ser WLr Intertie C Qtr NA Yes 2011-5075A 2 in 10" MO Cate G-4 11-26015 RilR Ser. Wtr Intert le C Qtr NA Yes 2E11-f075B 2 In 10" MO Cate C-7 ll-26014 RilR Se r. Wt r intert ie C Qtr NA Yes 2L11-fIl9A 3 il 18" No C.it.e C-fl 11-21039 1:HR Ser. Wtr T ra in C Qtr NA Yes A e B Cross

SYSTEM: Residual lleat Removal Plant Hatch - Unit 2 Valve Testing Program Sh. 13 of 42 St roke Valve Code Norm Time Roller No. Class Cat Description Coo rd . P4tl.D Funclion Pos Exe rc i se Leakaee Rea'd Reauest 2011-F1198- 3 B '18" Mo Cate C-8 11-21039 RitR Ser. Wt r T ra in C Qtr NA Yes A ar 11 Cross 2E11-F126A 3 8 1-1/2" A0 PCV B-2 11-21039 Sea l Wa te r to RitR C Note 16 NA No S.W. Pump P re ssu re

! Control 2[ll-F126B 3 8 1-1/2" A0 PCV J-2 11-21039 Seal Water to RHR C Note 16 NA No S.W. Pump Presstere j Control i

2E11-F201A 3 11 1" Solenoid B-3 11-21039 RilR Service Wa ter C Note 7 NA No Pump Cooling Water 2 Ell-I20115 3 0 1" Solenoid F-3 H-21039 luiR Survice Water C Note 7 NA No Puhip Coo 1ing Water z 2011-F201C 3 11 1" Solenoid D-2 H-21039 RilR Service Water C Note 7 NA No Pump Cooling Water

! 2E11-F201D 3 8 1" Solenoid C-2 H-21039 RilR Service Water C Note 7 NA No Pump Cooling Water 2011-I20TA 3 8 2" A0 PCV 15-f4 11-21038: RHR Se rv ice Wa te r C Note 9 NA No Pump Min. Flow 2E11-F201B 3 B 2" A0 PCV F -14 11-21038 RHR Service Water C Note 9 NA No Pump Min. Flow

. 2011-F207C 3 8 2" A0 PCV D-f4 it-2103f4 RilR Service Water C Note 9 NA No Pump Min, flow 2L11-F2010 3 8 2" A0 PCV C-Is 18-21038: luik tio rvice Water C Note 9 NA No Pump Min. Flow s

. , . p SYSTEM: Core Spray System Plant Hatch - Unit 2 Valve Testing Program Sh. 14 of 42 Stroke Valvo Code Norm ilme Relief Class Cat Desc ri p[ ion Coord. Phlp l yrLcLj gn Pos Exe rc i se Leakage Rea'd Reausst Jo .

2E21-1001A 2 A 20" MO Cate C-7 11-26018 CS Pump Suction Out 0 Qtr CIV Yes 2E21-F0018 2 A 20" Mo Cate 11 - 7 61-26018 CS Pump Suction Out 0 Qtr CIV Yes 2E21-I003A 2 C 12" Check I' - 7 11-26018 CS Pump Discharge O Note $ NA No 2E21-f003B 2 C 12" Check I-9 41-26018 CS Pump Discha rge O Note 5 NA No 2E21-foulA l 1 B 10" MO Cate E-6 41-26018 CS Outbrd. Injection 0 Qtr NA Yes 2[21-f008tl4 1 li 10" MO Cate C-6 11-26018 CS Outhed, injection 0 QLr NA Yes 2021-fouSA 1 A 10" M0 Cate E-5 11-26018 CS Outhrd. Cont. Iso C Qtr PlV Yes 2E21-I00511 1 A 10" MO Gate C-5 11-26018 CS Outhrd, Cont. Iso C Qtr PlV Yes 2E21-1006A 1 AC 10" A0 Check D-14 41-26018 CS injection C See 6.1.7 PlV No 6.1.7 2E21-10068 1 AC 10" Ao Check D-14 11-26018 CS injection C See 6.1.7 PlV No 6.1.7 2E21-f012A 2 C 2" Relier E-7 18-26018 CS Pump Disch.Relier k Note 3 NA No 2[21-F012B 2 C 2" Relier C-8 11-26018 CS Pump Disch.Relier C Note 3 NA No 2E21-F015A 2 A 10" MO Clobe D-7 11-26018 Core Spray Test C Qtr CIV Yes Dypass Cont. Iso 2E21-f01$ll 2 A 10" MO Clobe D-1 11-26018 Core Spray lost C Qtr ClV Yes Bypass Cont. Iso 2E21-F019A 2 B 20" A0 13rly G-S 11-26018 Core Spray Pump 0 Qtr NA Yes Torus Suc.

2[21-f0198 2 0 20" A0 urly 11 - 9 11-26018 Core spray Pump 0 Qtr NA Yes Torus Suc.

O O O SYSTIM: Core Spray System Plant Hatch - Unit 2 Valve Testing Program Sh. 15 of 42 Stroke valve Code Norm Time Relief No. C l a_is Cat Description Coo rd . P&lD Flinc t ion Pos Exe rc i se Leakaee Ree'd' Reaumat

', 2E21-F031A 2 B 3" M0 Cate F-8 H-26018 CS Pump Min. Flow 0 Qtr NA Yes 2E21-F031B 2 B 3" MO Cate F-9 H-26018 CS Pump Min. Flow 0 Qtr NA Yes 2E21-F036A 2 AC 3" Check E-8 H-26018 CS lest Line C See 6.1.6 CIV No 6.1.6 Cont. Iso 2E21-f036B 2 AC 3" Check E-9 H-26018 CS Test Line C See 6.1.6 CIV No 6.1.6 Cont. Iso 5

4 2E21-f018A 44 2 AC 1-1/2" Stop E-1 H-26018 Jockey Pump 0 RO CIV No 6.1.1

Check Cont. Iso 2E21 - F 08aI4 B 2 AC 1-1/2" Stop f-9 H-26018 Jockey Pump 0 80 CIV No 6.1.1 j

Clieck Cont. Iso I.

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O O O SYSTEM: MSIV Leakage Control System Plant Hatch - Unit 2 Valve Testing Program Sh. 16 of 42 j Stroke

Valve Code Norm Time Relief Rea'd No. Class Cat De sc ri pt ion Coord. P&lD Function Pos Exe rc i se teskaee Reauest 2E32-f001B, -1 A 1-1/2" MO Clobe E-8 11-26022 MSIV Leakage Control C Qtr CIV Yes F. K, P Cont. Iso 2E32-FOO28, 2 8 1-1/2" M0 Clube L-7 11-26022 MSIV Leakage Control C Qtr NA Yes F. K. P Cont. Iso 2E32-f003B, 2 B 1-1/2" MO Clobe E-5 11-26022 MSIV leakage Control C Qtr NA Yes F. K, P Cont. Iso

! 2[32-f006 2 B 1-1/2" HO Globe C-11 11-26022 MSIV Leakage Control C CS NA Yes 6.1.20 2E32-f007 2 8 1-1/2" MO Globe D-11 18-26022 MSIV leakage Control C CS NA Yes 6.1.20 4 f 2[32-8008 2 B 1-1/2" MO Clobe C-10 H-26022 MSIV Leakago Control C CS NA Yes 6.1.20 2E32-f009 2 B 1-1/2" M0 Globe D-10 H-26022 MSIV Leakage Control C CS NA Yes 6.1.20 4

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SYSIEM: liigh Pressure Coolant injection Plant Hatch - Unit 2 Valve Testing Program Sh. 17 of 42 Stroke Valve Code Norm Time Roller No, Class Cat De sc_I, int {o_fi Coo rJ1, P&lD fijnc h p Pos Exe rc i se leakaoe Rea'd Reauest 2E41-F001 2 B 10" Mo Cate .E-10 H-26020 llPC I Steam Supply C Qtr NA Yes Shutoff 2E 41 - f (IO2 1 A 10" MO Cate C-3 11-20020 HPCI Steam Supply 0 Qtr CIV Yes 6.1.2 I nb rd . Iso 2E41-1003 1 A 10" Mo Cate C-4 18-26020 It PC I Steam Supply 0 4tr CIV Yes Outbrd. Iso 2E41-f00fs 2 11 16" MO Cat.e D-1 11-26020 IIPC I Pump Suc. O Qtr NA Yes from Cond. Stor.

PEtel-Fou$ 2 C 18 " L'e . d 4 L-S 11-26020 llPC I Pump Disch. C Note S NA No 4

2111-f006 4 2 A 184 " MO Cate t -is H-26020 HPCI Pump inbrd. C See 6.1.10 PlV Yes 6.1.10

'Disch. Iso 2[41-f007 2 B 18 " MO Cate 6 E-S 11-26020 llPC I Pump Outbrd. O Sco 6.1.10 NA Yes 6.1.10 2 Disch.

i 2[81-f008 4 2 0 10" MO Clobe D-7 18-26020 llPC I Pump C Note 1 NA No lest Ilypa ss 2[41-1011 2 15 10" MO Cate C-6 it-26020 llPC I Pump Hedun. C Note 14 NA No Shtstorf' to Cond. Sig.

2E11-F012 4 2 A 4" MO Cate I-6 H-26020 llPCI Pump Min. Ilow C Qtr CIV Yes 6.1.2 I nb rd . Iso 2Etel-F019 2 C 16" Check D-7 H-26020 HPCI Pump Suc. C Note S NA No

. from Cond. Stg.

2141-1021 2 AC 12" Stop Chech G-3 li-26020 H 1'G I lurb. Exh. C See 6.1.12 CIV No 6.1.11 lubsd. 150 6.1.12 s

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SYSTEM: High Pressure Coolant injection Plant Hatch - Unit 2 Valve Testing Program Sh. 18 of 42 Stroke Valve Code Norm Time Relief No. Class Cat Desc ri pt i on Coo rd . P&lD Funclion Pos Exe rc i se Leakage Rea'd Reauest 2E841- F022 2 AC 2" Stop Check G-3 11-26020 llPC I Turb. Exh. C See 6.1.12 CIV No 6.1.11 Drn. Torus Iso 6.1.12 2El1-F035 4 2 B 2" AO PCV F-7 11-26021 HPCI Tusb. Lube C Note 10 NA No Oii Cooling 2E41-f040 2 AC 2" Check G-lo ll-26020 llPCI lurb. Exh. C See 6.1.12 CIV No 6.1.12 I Drn. forus Iso 2E41-F011 4 2 B 16" M0 Cate D-F '-?26020 IIPC I Pump Suc. C QLr NA Yes Shutorr 2E41-IO42 2 A 16" Ho Cate 11 - 84 11-26020 HPCI Pump Suc. C Qtr CIV Yes Torus outbrd. Iso 2E41-F045 2 C 16" Check it-5 it-26020 llPCl Pump Suction C See 6.1.13 NA' No 6.1.13 4 2Et1-F016 4 4 2 AC 1" 4 Check F-6 H-26020 HPCI Pump Min Flow C Note 5 ClV No i Outbrd. Iso 2E11-fol9 4 4 2 AC 20" Check C-4 11-26020 HPCI Turb. Exh. C See 6.1.12 ClV No 6.1.12 Ou tb rd . 150 i

2Ll1-FO$1 4 2 A 16" A0 Brly 11 - 14 H-26020 HPCI Pump Suc. O Qtr CIV Yes Torus inbrd. Iso 2E41-F059 2 B 2" MO Globe F-7 11-26020 HPCI lurb. Lube oil C QLr NA Yes Cooling 1

2[41-F104 2 A 2" M0 Cate I-2 H-26020 llPCI Vac. Holier O Qtr CIV Yes Outbrd, forus Iso 2Ll1-F111 4 2 A 2" HO Gato G-1 61-26020 11001 Vac, Relier 0 QLr CIV Yes i nb rd , lorus Iso 1

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p p u U .O-SYSTEM: Reactor Core Isolation Cooling Plant Hatch - Unit 2 Valve Tcsting Program Sh. 19 of 42 Stroke Valve Code Norm Time Relief glo . Class Cat Desc ri p t ion Coo rd . PklD Iunction Pos Exe rc i se Leakaee Rea'd Reauest 2E51-I001 2 AC 10" Stop Check C-5 H-26023 RCIC Turb. Exh. C See 6.1.12 CIV No 6.1.11 to Torus Iso 6.1.12 -

2E51-F002 2 AC 2" Stop Check C-5 H-26023 RCic Vac Pump C See 6.1.12 CIV No 6.1.11 Disch. to Torus Iso 6.1.12 2051-1003 2 A 6" A0 Hrly 6 11-26023 ftcic Pump Suction 0 Qtr CIV Yes 6.1.2 Torus Iso 2E51-I007 1 A 4" Mo Cate C-5 H-26023 RCIC Steam Supply 0 Qtr CIV Yes 6.1.2 lubrd. 150 2151-f008 1 A 4" Mo Cate C-6 11-26023 ftCIC Steam Supply 0 QLr ClV Yes Outbrd Iso 2E51-fol3 2 A 4" MO Gato D-6 11-26023 RCIC Icedwater inj. C QLr PlV Yes 2E51-IO19 2 A 2" MO Clobe E-7 H-26023 RCIC Pump Min. Ilow C Note 8 CIV No 6.1.2 Torus Iso 2E51-f021 2 AC 2" Check E-7 11-26023 RCIC Pump Min, flow 'C Note 5 CIV No Torus Iso 2[51-IO28 2 AC 2" Check I-7 11-26023 RCIC Vac. Pump Disch. C See 6.1.12 CIV No 6.1.12 lorus Iso 2E51-I031 2 A 6" MO Cate H-6 11-26023 RCIC Pump Suction 0 QLr CIV Yes Torus Iso 2E51-f040 AC AC 10" Check F-5 H-26023 RCIC lurb. Exh. C See 6.1.12 CIV Yes 6.1.12 Torus Iso 2LSI-Il04 2 A 1- 1/;'" MO Ga te 1 *> 11-26021 licic Vac. Brke r O Qtr CiV Yes lorus Iso 2E51-fl05 2 A 1-1/2" MO Cate F-4 18-26023 RCIC Vac. Brker 0 Qtr CIV Yes 6.1.2 Torus Iso

O O O SYSTEM: Radwaste Plant Hatch - Unit 2 Valve Testing Program Sh. 20 of 152 Stroke Code Norm Time Relief Valve Class Cat Desc ri p t ion Coord. ParID Function Pos Exe rci se Leakaae Rea'd Reaumat No.

2G11-F003 2 A 3" AO Gate B-3 H-26026 ' DW F i r D rn s . O Qtr CIV Yes Cont. Iso 2C11-f0086 2 A 3" AO Gate u.a6 H-26026 ' IX! F i r. D rns . O Qtr CIV Yes Cont. Iso 2Gil-fu19 2 A 3" AO Cate F-86 H-26026 DW Equip. Drns. O Qtr. CIV Yes Cont. Iso 2G11-f020 2 A 3" AO Cate E-16 H-26026 DW Equip. Drns. O Qtr CIV Yes Cont. 150 2G11-f852 2 At 1-1/2" Han Gate f-11 H-26026 Cliem. dra ins LC Note 1 CIV No Cont. Iso 2Gil-f853 2 AE -1/2" Man Cato D-11 H-26026 Chem, drains LC Note 1 CIV Mo Cont. Iso

O. O O SYST[M: Reactor Water Cleanup Plant Hatch . Unit 2 Valvo Testing Program Sh. 21 of 42

. Stroke Valve Code Norm Time Relief.

No. Class Cat De sc rip t ion Coo rd . fAID Function Pos Exe rc i se te3kaee Rea'd Itamaamat 2G31-F001 1 A 6" M0 Cate C-2 H-26U36 HWCU Pump Suc. 0 'Qtr CIV Yes i nb rd . 150 2G31-F004 1 A 6" MO Gate C-3 H-26U36 HWCU Pump Suc. O Qtr CIV Ves Outbrd. 150

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, SYSTEM: Demi ne ra l i zed Wa te r Plant Hatch - Unit 2 Valve Testing Program Sh. 23 of 352

.I Stroke Valve Code . Norm Time Relief j A. Class Cat Desc r i p t io.t Coo rd . ParID Function Pos Exerci se Leakaee Rea'd - -- at l 2P21-I032 2 AE 2" Manual Cate F-2 H-26047 Domin. Water LC Note 1 CIV 00 0 Cont. Iso l 2P21-FD34 2 AE 2" Manual Cate F-2 H-26047 Demin. Water LC Note 1 CIV Ile a Cont. Iso i

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O O O Plant Hatch - Unit 2 Valve Testing Program Sh. 24: er 42 SYSTEM: H, and 0, Analyzer Stroke Norm Time Roller Valve Code Coord. P&lO Function Pos Exercise i.ea ksee Rea'd Reauest glo . Class Cat Descriotion H-26048 &03 Analy. O Qtr CIV Yes 2P33-FOO2 2 A 1" AO Control B-4 H2 Cont. Iso H-26048 H &03 Analy. O Qtr CIV Yes 2P33-FOO3 2 A 1" AO Control C-4 nt. 150 H-26048 Hg & Og Analy. O Qtr ClV Yes 2P33-FOO4 2 A 1" AO Control 0-4 Cont. Iso H-26048 H, & 03 Analy. O Qtr CIV Yes 2P33-FOO5 2 A 1" AO Control E-4 l C6nt. Iso I CIV Yes 1" AO Control F-4 H-26048 H 2 & O2 Analy. O Qtr 2P33-f 006 2 A Cont. Iso H-26048 O Qtr CIV Yes

. 2P33-FOO7 2 A 1" AO Control H-4 H, & 03 Analy.

Ma t . Iso H-26048 H2 & Og Analy. O Qtr CIV Yes 2P33-f010 2 A 1" AO Control 8-5 Cont. Iso H-26048 Hg&Of Analy. O Qtr CIV Yes 2P33-FOli 2 A 1" AO Control C-5 Cont. Iso 112 & O, Analy. O Qtr Civ Yes 2P33-F012 2 A 1" AO Control 0-5 H-26048 Cent. Iso H-26048 O Qtr CIV Yes 2PJ3-fol3 2 A 1" AO Control E-5 H2 &O Analy.

Cont, so

's H-26048 112 &O2 Analy. O Qtr ClV Yes 2P33-F014 2 A 1" AO Control 1 Cont. Iso l CIV Yes 2 A 1" AO Control 11-26048 H2 &O2 Analy. O Qtr

} 2P33-FOl5 ll 's Cont. Iso i

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Plant flatch - Unit 2 Valve Testing Program Sh. 25 or 42 SYSILM: Plant Service Water St roke Code Norm Time Roller Valve Pos Exe rc i se teakaee Reo'd Mr-- at Class Cat Description Coord. P&lp Function

_No.

D-4 H-26051 H PCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 2P41-F024A 3 C 1-1/2" Cleeck D-5 H-26051 HPCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 2P41-F024B 3 C 1-1/2" Check 2P41-f025A 3 C 3" Check D-6 11-260$1 HHH & CS Pump Room C See 6.1.14 NA No 6.1.14 Cooler C 3" Check D-6 H-26051 RHR & CS Pump Room C See 6.1.14 NA No 6.1.14 1 2P41-F02$B 3 1 Cooler 1

3" Check C-8 H-260$0 RHR Pump Cooler C See 6.1.14 NA No 6.1.14 2P41-fu26A 3 C H-26050 RHR Pump Cooler C See 6.1.14 NA No 6.1.14 2P41-F0268 3 C 3" Clieck C-9 C-$ H-260$0 RCIC Pump Hoom C See 6.1.14 NA No 6.1.14 2P41-f028A 3 C 1-1/2" Clieck Cooler C-4 H-26050 RCIC Pump Room C See 6.1.14 NA No 6.1.14 2P41-fu28B 3 C 1-1/2" Check Cooler 2" A0 Globe C-4 H-26051 HPCI Pump Hoom C Qtr NA Yes 6.1.15 2P41-F035A 3 8 Cooler 8 2" AD Clube C-$ H-260$1 HPCI Pump Room C Qtr NA Yes 6.1.15 2P41-f035B 3 Cooler i

3" AO Clobe C-S H-26051 RHR & CS Pump C Qtr NA Yes 6.1.15 2P41-f036A 3 8 Room Cooler 3" A0 Globe C-6 H-26051 RHR & CS Pump C Qtr NA Yes 6.1.15 2P41-F036B 3 15 Room Cooler i

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SYSTIM: Plant Service Water Plant flatch - Unit 2 Valve Testing Program Sh. 26 er 42 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID feuclion Pos Exe rc i se Leakaoe Rea'd Reeuest 2 P41-F037 A 3 B 1-1/2" AO Clobe D-7 H-26050 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F037B 3 8 1-1/2" AO Clobe C-9 18-26051 RilR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F037C 3 8 1-1/2" AO Clobe D-8 H-26050 RilR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F037D 3 8 1-1/2" AO Clobe C-8 18-26051 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-IO39A 3 8 3" AO Clobe D-9 li-26050 RilR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F0398 3 8 3" AO Globe D-9 11-26050 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F040A 3 6 2" AO Clube D-5 18-26050 RCIC Pump Room C Qtr NA Yes 6.1.15 Cooler 4

2P41-f040B 3 8 2" AO Clobe D-5 H-26050 RCIC Pump Room C Qtr NA Yes 6.1.15 I,

Cooler 2P41-F042A 3 B 3" AO Clube C-2 H-26051 CRD Pump Room O Qtr NA Yes 6.1.15 4

Cooler 2P41-F042B 3 8 3" AO Globe C-3 H-26051 CRD Pump Room O Qtr NA Yes 6.1.15 Cooler 2P41-F096A 3 8 8" AO Brly E-4 18-26050 Drywell O CS NA Yes 6.1.16 i

Cooler 2P41-F0968 3 6 8" A0 Brly E-2 11-26050 Drywell O CS NA Yes 6.1.16 Cooler 1

2P41-F311A 3 8 18" Check B-3 11-21033 S.W. Pump 0 Note 11 NA No g

Di scha rge

! 2P41-F3113 3 B 18" Check C-3 11-21033 S.W. l' ump 0 Note 11 NA No Di scha rge 2P41-F311C 3 B 18" Check [-3 H-21033 S.W. Pump 0 Note 11 NA No l

Discharge i 2P41-F311D 3 8 18" Check C-3 H-21033 S.W. Pump 0 Note 11 NA No Di scha rge 2P41-F315A 3 B 10" MO Brly A-9 H-21033 S.W. to Reactor LO Mote 15 NA No Bldg. Shutorr 2P41.F3158 3 8 10" MO Bray F-9 H-21033 S.W. to Reactor LO Note 15 NA No Bldg. Shutorf

O O O SYSTEM: Plant Service Water Plant Hatett - Unit 2 Valve Testing Program Sh. 27 of 42 Stroke Valve Code Norm Time Relief No. Class Cat Desc r ipt ion Coord. P&lD Function Pos Exe rc i se Leakane Rea'd --- at 2P41-f316A 3 15 30" M0 Bfly A-9 11-21033 S.W. to lurbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-F316B 3 8 30" Mo Bfly F-9 H-21033 S.W. to Turbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-f316C 3 0 30" MO Bfly A-10 18-21033 S.W. to lurbine O CS NA Yes 6.1.17 Bldg. Shutoff 2Prl-f3160 a 3 is 30" Mo Bfly t-10 18-21033 S.W. to lierbine O CS NA Yes 6.1.17 Didg. Shutoff 2P41-1319A 3 11 I" Solenoid B-l 18-21033 S.W. Pismp Cooling O Note 7 NA No Water Shutof f 2P41-f 319t1 3 15 I"t Solenoid C-1 H-21033 ~S.W. Pump Cooling O Note 7 NA No Wa ter Shutoff 2P41-f319C 3 15 1" Solenoid E-1 H-21033 S.W. Pump Cooling O Note 7 NA No Water Shutof f 2P41-I319D 3 8 1" Solenoid C-1 H-21033 S.W. Pump Cooling 0 Note 7 NA No Water Shutoff 2Pt:1-F320A 3 tt 3" A0 PCV A-3 H-21033 S.W Pump Min. Flow C Note 9 NA No 2P41-1320ft 3 8 3" AD PCV C-3 11-21033 S.W. Pump Min. Flow C Note 9 NA No 2P41-I320C 3 8 3" AD PCV E-3 H-21033 S.W. Pump Min. Flow C Note 9 NA No 2P41-F320D 3 e5 3" A0 PCV i-3 H-21033 S.W. Pump Min. Flow C Note 9 NA No

O O O SYSTEM: Plant Service Water Plant Hatch - Unit 2 Valve lesting Program Sh. 28 of 42 Stroke Valve Code Nore Time Roller Blo . Class Cat Desc rip t ion Cgg rd . P41D Function Pos Exe rc i se leakaee Rea'd N ~^ st 2P41-F334A 3 8 1" A0 PCV C-T H-21033 S.W.. Pump CooIing - Note 16 NA No Water Press. Reg.

2P41-F3348 3 8 1" AO PCV C-1 H-21033 S.W. Pump Cooling -

Note 16 NA No Water Press. Reg.

2P41-I339A 3 8 6" AO Brly 11 - 9 H-21033 Diesel Cen. Cooling C Qtr NA Yes 6.1.15 2P41-F3398 3 B 6" A0 Brly H-7 H-21033 Diesel Cen. Cooling C Qtr NA Yes 6.1.15 2P41-f340 3 8 6" AO Brly 11 - 5 H-21033 Diesel Cen. Cooling C Qtr NA Yes 6.1.15

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

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i SYSTEM: RS Closed Cooling Water Plant Hatch - Unit 2 Valve Testing Program Sh. 29 er 42

{

i St roke 4 valve Code Norm Time Roller j slo . Class Cat Desc ript ion Coo rd . Par t D function Pos Exe rc i se Lea kaoe Ree'd "- - - a t l

2P42-FO51 2 A 6".MO Cate B-5 H-26055 RISCCW to Recir. O CS CIV Yes 6.1.18 Cont. Iso l 2P42-f 052 2 A 6" MO Cate C-5 H-26055 RBCCW to Recir. O CS CIV Yes 6.1.18 Cont. Iso lI 4

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SYSTEM: Service Air Plant Hatch - Unit 2 Valve Testing Program Sh. 30 of est i

Stroke

{ peorm Time Roller j Valve 80 0 . Code Clasp . Cat DescM otson Coord. PitlD_ _ fsanction Pos Exercise Leaksee Itee' ai - -- - - it l

.f 2P51-f 513 2 AE 2" Man. Globe F-3 H-260$8 Se r. Ai r Con t . 150 LC 100te 1 ' Cly Igo 2 PSI-F 6'21 2 AE 2" Man. Globe F-3 H-260$8 Ser. Ai r Cont. 1s0 LC 100te 1 CIV 10 0 t

i

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O O ;O SYSTEM: Chilled Water System Plant Hatch - Unit 2 Valve Testing Program Sh. 31 of 42 Stroke Code llo ra Time flelief Valve Pos Exe rci se Leah ce flee' d 10 0 . Class Cat Desc ript ion Coofd. ParID Funqijgn - - - - 21 A 6" 940 clobe C-11 H-26081 Ch i l led Wa te r O CS CIV Yes 6.1.16 2P64-F045 2 Cont, 150 2 A 6" 900 Clobe C-8 H-26081 Chilled Water O CS CIV Yes 6.1.16 2 P64-F047 Cont. iso

O O 0 SYSTEM: Orywell Pnetuna t ic Plant Hatch - Unit 2 Valve Testing Program Sh. 32 of 452 Stroke Valve Code Nore Time lle lief

_lgo . Class Cat Descrjption Coo _rd . 'fk!D F1ancdon Pos Exe rc i se Leakane Rea'd "r -- r t 2P10-F002 2 A 1" AO Control I-8 H-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso 2 P70-I003 2 A 1" AO Control I-8 H-26066 DW Pnetunatic Cont. O Qtr CIV Ves Iso 2Plo-f 00te 2 A 2" AO Control C-7 H-26066 DW Poetama t i c Con t. O Qtr CIV Yes iso-2 P10- F OO'> 2 A 2" AO Control D-7 18-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso 2PTO-1020 2 AC 2" Clieck C-6 18-26066 DW Pneumatic Cont. O RO ClV No 6.1.1 Iso

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

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! SYSIEM: .ILRT Plant Hatch - Unit 2 Valve Testing Progree Sh. 33 of 42 i

Stroke valve Code teo rm Time negler j 80 0 . -Class Cat Desc rigt ion Coo rd . Pari D function Pos Exe rc i se Leahrrr Ama'd --t 2T23-f004 2 A 3/4" Man.-Globe D-3 H-26057 ILRT Cont. Iso C Isote 1 CIV IIe

! 2T23-FOO$ 2 A 3/4" Man. Globe D-3 H-26057 ILRI Cont. Iso C Ilote 1 CIV 10e i

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Q.Y SYSIEM: f i re Protection Plant IIatch - Unit 2 Valve Testing P rog ram Sh. 34 of 42 Stroke Valve Code Norm Time Roller No. Class Cat Descripljon Coord. P&lD function Pos Exe rc i se leakaoe Rea'd Raouest 2143-f159 2 AC 3" Check F-5 H-210ll fire Protection C Note 1 ClV No Cont. Iso 2T43-F160 2 AE 3" Man. Cate F-5 81-21017 fire Protection LC Note 1 CIV 16 0 Cont. Iso i

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

o o 9 i SYSTIM: Standby Gas T reatment Plant Hatch - Unit 2 Valve Testing Program Sh. 35 of 42 St roke Code Norm Time Relief Valve Pos Exe rc i se Leakaea Rea'd Reaumat No. Class Cat De sc rip t ion Coord. P&lD Function 18" AO Bfly C-2 H-26078 F i l ter Bed inlet- C Qtr NA Yes

2T46-F001A 3 8 from Reactor Bldg. .

.i 2T46-foo1B 3 8 18" AO Bfly G-2 Il-26078 F i l te r Bed Inlet C Qtr NA Yes f rom Reactor Bldg.

[ C NA Yes 2T46-5002A 3 8 18" A0 Brly C '; H-26018 SGIS Filter Qtr l

Bed Outlet 2T46-F002B 3 8 18" A0 Brly C-5 H-26078 SGTS Filter C Qtr NA Yes Bud Outlet 18" AO Hfly C-2 H-26018 SGIS filter C Qtr NA yes

2I46-f003A 3 3 i

Bed inlet from Heruel Floor 2I46-f003B 3 8 18" A0 Bray G-2 H-26018 SGIS f ilter C Qtr NA Yes

} Bed Intet from Peruel Floor 1

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O O o SYSTEM: Containment Purge and inerting Plant Hatch - Unit 2 valve lesting Program Sh. 36 of 42 i e Stroke i Code More Time Roller Valve glo . Class Cat Description Coord. ParID Fune don Pos Exe rc i se Leakaee Ree'd -- at 2

2148-F103 2 A 6" A0 Brly D-10 H-26083 DW & Torus Supply C -Qtr CIV Yes Iso 1

2148-F104 2 A 1" A0 Control C-4 H-26083_ Dwg & Torus C Qtr CIV Yes Outbrd. Iso 2 A 2" AO Control G-9 H-26083 DW Inerting Outbrd C Qtr Civ Yes l 2143-F113 Iso A .H-26083 DW Inerting Inbrd C Qtr CIV Yes 2T48-I114 2 2" AO Control 15- 9 Iso i

i 2148-Ill5 2 A 2" Ao control G-10 H-26083 DW Inerting outbrd C Qtr ClV Yes Iso 1

! 2348-fl16 2 A 2" A0 Control 66- 1 0 - H-26083 DW - ine rt ing Outb rd C Qtr CIV Yes i

Iso i 2148-F118A 2 A 1" Solenoid J-4 H-26083 lorus Makeup O Qtr CIV Yes i nb rd Iso 2148-F1188 2 A 1" Solenoid J-5 H-26083 lorus Makeup 0 QLr CIV Yes i nb rd Iso k DW Inorting C Qtr CIV Yes 1 2T48-F321 2 A 2" AO Control G-7 lt- 260ts3

! Outbrd. Iso 1 2148-F322 2 A 2" AO control H-1 li-26083 DW Inerting C Qtr CIV Yes i

inbrd. Iso e 2148-f325 2 A 2" AO Control C-8 H-26083 Torus inerting C Qtr CIV Yes l

j Outbrd. Iso 2148-F327 2 A 2" A0 control ll-8 H-26083 torus inerting C Qtr CIV Yes 1 inbrd. Iso 1 ,

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sysitM: Conta a nacent Purge and enerting Plant Hatcla - Usiit 2 Valve Testing Program Sh. 37 of 42 St roke t Valve code Norm Time Relief Class Cat thisc ri p t ion Coo rd,_ _P41 D [ungtion Pos Exe rc i se Leaksee llen' d lleaumat

_ Iso .

2148-F3ul 2 A 18" A0 Brly C-9 H-26084 DW Purge inlet C flote 1 ClV Ito i leib rd Iso 2I48-F308 2 A 18" AO Brly C-10 H-26084 DW Purge Inlet C flote 1 CIV 11 0 inb rd Iso 2148-F309 2 A 18" AO Brly E-10 H-26084 forus' Purge C llote 1 CIV Ito inlet inb rd Iso 2148-F310 2 A 20" A0 Brly F-10 18-26084 lorus Purge vac. C Qtr CIV Yes Brker Iso

! 2I48-r311 2 A 20" Ao tirly I-9 H-26084 forus Purge Vac. C Qtr CIV Yes Brker Iso

].

! 2148-F318 2 A 18" A0 Brly G-4 H-26084 Torus Purge O Qtr CIV Yes j Outlet i nb rd Iso 4

! 2148-F319 2 A 18" A0 Brly C-4 H-26084 DW Purge C Note 1 CIV Yes outlet inbrd Iso 2148-F320 2 A 18" A0 Brly C-3 H-26084 DW Purge Outlet C Note 1 CIV No 1 Outhrd Iso i 2148-F323A 2 C 18" A0 Clieck G-8 H-26084 DW to lorus Vac. C Qtr NA No B reake r 2148-F323B 2 C 18" A0 Clieck C-8 H-26084 DW to lorus Vac. C Qtr NA No

!!rea ke r i

! 2148-F323C 2 C 18" A0 Clieck C-8 H-26084 DW to Torus Vac. C Qtr NA No lireal o r 2148-f323D 2 C IB" AO Check G-8 H-26084 DW to lorus Vac. C Qtr NA No Brea ke r 1

I 2148-F323E 2 C 18" Ao check C-8 H-26084 DW to lorus vac. C Qtr NA No Breake r l

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a SYSTIN: Conta inment Purge and inerting Plant Hatch - Unit 2 Valve Testing Program Sh. 38 or 42 Stroke Valve Code Norm Time Roller No. Class Cat Descriglion Coord. Pk1D function Pos f we rc i se leakaec Ree'd Resumat 2i48-f323F 2 C 13" AO Check G-8 11-26084 DW to . Torus Vac. C Qtr NA Ito Brea ke r 2148-F323G 2 C 18" AO Check C-8 11-26084 DW to lorus Vac. C Qtr NA 00 0 Brea ke r 2I48-I323tl 2 C 18" AO Check G-8 18-26084 DW to lorus Vac. C Qtr NA No B rea ke r 2it8-F323l 4 2 C 18" AO Check G-8 H-26084 DW to lorus Vac. C Qtr NA No Breake r l

2148-I323J 2 C 18" A0 Check G-8 H-26084 DW to lorus Vac, C Qtr NA No B rea ke r 2T48-F323h 2 C 18" AO Check G-8 H-26084 DW to Torus Vac. C Qtre \ NA No B rea ke r 2148-f323L 2 C 18" AO Check C-8 H-26084 DW to lorus Vac. C Qtr NA No B rea ke r 2148-F324 2 A 18" A0 BFly D-10 H-26084 Torus Pierge C Note 1 CIV No Inlet Outbrd, 150 21:48-F326 2 A 18" A0 BFly C-3 H-26084 lorus Pierge C Qtr CIV Yes Outlet Outbrd. Iso 2148-F328A 2 AC 20" A0 Check G-10 H-26084 Heactor Bldg. to O Qtr CIV No Suppression Cham Vac. Brker

2I48-I3288 2 AC 20" A0 Check G-9 18-26084 Reactor Bldg. to C Qtr CIV No

! Siippiession j Chaas Vac. Brker.

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SYSTIM: Containment Purge and inerting P l a nt Ha tch - Un i t 2 ' Va l ve Te s t i ng P rog ram Sh. 39 of ap2 i

Stroke valve Code Norm Time llel ler 10 0 . Class Cat Dogcriotion Coo rd . Parl D function Pos Exe rc i se teakaee Rea'd - -- at 2T48-I332A 2 A 2" AO Control E-3 H-26084 forces Purge C Qtr CIV Yes Outlet Otetbrd Iso 2T88-I332B 4 2 A 2" AO control C-3 H-26084 f o rus Purgo C Qtr CIV Yes Outlet outbrd Iso 2i48-F333A 2 A 2" AO Control E-4 H-26084 Torus Purge C Qtr CIV Yes Outlet inbrd Iso 2I48-F333B 2 A 2" AO Control G-4 H-26088 lorus Purgo C Qtr ClV Yes Outlet inbrd Iso 2188-F331A 6 4 2 A 2" AO Control B-3 H-26084 DW Pu rge ou t l e t C Qtr CIV Yes Outbrd iso 2its8-I334B 2 A 2" A0 Control C-3 H-26084 DW Pu rge Ou t l e t C Qtr CIV Yes Outb rd Iso 2148-F335A 2 A 2" AO Control B-4 H-26084 DW Purgo Outlet C Qtr ClV Yes inb rd iso 2184 8-f 3 3'#H 2 A 2" AO Control C-4 H-26084 ()W Pu rgo Ou t l e t C Qtr CIV Yes Inbrd Iso 211s8-I338 2 A 2" Diaphragm H-2 H-26084 Bypass-Outbrd Iso C Qtr CIV Yes 2188-1339 4 2 A 2" Diaphragm H-3 H-2f>084 Hypass-Inbsd Iso C QLr ClV Yes 2it 8-F3:40 4 2 A 2" Solenoid D-2 H-260884 Bypa s s-Ou tb rd Iso C 4tr CIV Yes 2148-F34l 2 A 2" Solenoid E-84 H-26084 Bypass-Inbrd Iso C Qtr ClV Yes

O O O SYST[N: Containment Purge and inerting Plant Hatch - Unit 2 Valve Testing Prograa 'Sh. 40 of 42 Stroke Valve Code Norm Time Roller Class Cal Descriglion Coo rd . PMg Function Pos Exe rc i se Leakaqe Rea'd Reenamat Jo .

2il8-I382A 4 4 2 A 1/2" Solenoid 11- 8 11-26084 Torus to DW Vac C Note 12 ClV No Breaker Iso 2Tt8-F31a28 4 2 A 1/2" Solenoid 11 - 8 11-26081 Torus to DW Vac C Note 12 CIV No Breaker Iso 2if8-1382C 4 4 2 A 1/2" Solenoid 11- 8 11-26084 lorus to DW Vac C Note 12 CIV No Breaker Iso 2il8-F382D 4 4 2 A t/2" Solenoid 11- 8 11-260884 Torus to DW Vac C Note 12 CIV No Breaker iso 2I48-F 38 21:

6 2 A 1/?" Solenoid 14 - 8 11-260814 lorus to DW Vac C Note 12 ClV No Breaker e so 2148-I3842F 2 A 1/2" Solenoid 11- 8 11-26081e losus to DW Vae C Note 12 CIV No Breaker Iso 2It8-F382C 4 4 2 A 1/2" Solenoid it-8 H-26084 lorus to DW Vac C Note 12 CIV No B rea ke r I so

. 2il 8-F38s2tl 4 2 A 1/2" Solenoid 11 - 8 61-260884 Torus to DW Vac C Note 12 CIV No Breaker 1 s0 2148-I3821 4 2 A 1/2" Solenoid 11- 8 Il-2608ts forus to DW Vac C Note 12 CIV No D rea ke r I so

, 2il:8-F38 2J4 2 A 1/2" Solenoid 11 - 8 61-26084 Torus to DW Vac C Note 12 CIV No

' Breaker iso i 2184 8-F342K 2 A 1/2" Solenoid it-6 11-26084 forus to DW Vac C Note 12 CIV No i lis eaker 150 218 8-63821.

4 4 2 A 1/2" Solenoid al- ti 11-260814 losus to DW Vac C Note 12 CIV No Breaker 150 j

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O O O SYSTIM: Containment Purge and Inerting Plant Hatch - Unit 2 Valve Testing Program Sh. 41 of 42 Stroke Valve Code Norm Time Roller leo. Class Cat De sc ri p t ion Coord. P41D function Pos Exe rc i se leakage Rea'd Reaumat 2T48-F361A 2 A 1" AO control C-9 H-260884 lorus Water O Qtr CIV Yes Level 150 2T48-F36tB 2 A 1" AO Control C-5 H-26084 Torus Water O Qtr CIV Yes Level Iso 2148-F362A 2 A 1" AO Control 11 - 9 H-260884 Torus Water O Qtr CIV Yes level Iso 2 Ts48-F 362B 2 A I" AO Control 11 - 5 11-260884 forus Water O Qtr CIV Yes Level Iso 2I48-I363A 2 A 1" AO Control E-8 Il-26084 P re ss . T ransmi t te r O QLr CIV Yes Iso 2 T848- F 3638 2 A 1" AO Control D-6 H-260884 Press. T ransm i t te r O Qtr CIV Yes Iso 2I48-I368 4 A 2 A 1" AO Control C-8 H-260884 P re s s . I ra nsm i t te r O QLr CIV Yes Iso 2il48-F36f3 4 2 A 1" AO Control C-5 11-26079 Press. T ra nsm i t te r O Qtr CIV Yes

< iso 2148-F209 2 A 8" 4 AO Gate C-9 H-26019 i nboa rd isolation O QLr CIV Yes 2148-F210 2 A 8" AO Cate 4 C-9 H-26019 Ou t boa rd isolation O Qtr ClV Yes 2Tf8-F211 i 2 A 8" 4 AO Cate E-8 11-26079 inboa rd isolation O Qtr CIV Yes 2T88-F212 4 2 A 1" 4 AO Cate E-8 H-26079 Outboa rd Isolation O QLr CIV Yes i

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O O O SYSTEM: Containment Purge and inerting Plant Hatch - Unit 2 Valve Testing Program Sh. 42 of 42 Stroke Valve Code Norm Time Roller Jo . Class Cat Desc ri p t i on Coord. Phl0 function Pos Exe rc i se Leakaoe Rea'd Reaumat 2il9-IOOlA, 4 2 B 1"4 MO Cate C-3 11-26068 H2 Recomb. 18 7 C QLr NA Yes g from DW Shutoff 2149-F002A, 2 A 1" 4 MO Cate C-84 H-26068 H2 Recomb. 112 C Qtr ClV Yes B frou DW 150 2Tl9-I003A, 4 2 B 3" Flow Control C-5 11-26068 Hr. Recomb, 182 C Note 16 NA No B f ram' DW Shutorr

. 2it9-FOO1A, 4 4 2 A 8" MO Gate F *.) H-26068 lip Recomb. Gas C Qtr CIV Yes B a nd Wa te r I so 2if4 9-l00';A, 2 15 4" MO Cate F -la 11-26068 fly Recomb. Cas C Qtr NA Yes B and wa te r I so 2il9-f006A 4 2 h 3/8" MO Globe 4 11- 5 H-26068 H2 Recomb. Water C QLr NA Yes B Feed from RHR 2Ti9-l001A4 2 0 3/4" HO Globe H-8 H-26068 Hy Recomb. Water 0 Qtr NA Yes B Iced from RHR 2119-I008A4 2 B 3" MO Globe D-7 H-26068 112 Recomb, 0 QLr NA Yes B flow Control 21:49-F009A 2 AC 1-1/2" Relier F-84 18-26068 Relier Valve C Mote 3 CIV No B Cont. Iso i

j j This document was processed by the Birmingham lext Processing Center, Southern Company Services, Inc.

I l Ot99n4 i

Class 1, 2, and 3 Valve Testing Program "a***:

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1. This valve will not be stroked because it is a passive containment isolation valve. It is normally closed and does not have to open to perform any safety-related function.

2. E11-F019 (or 2E11-F019) is a normally closed passive check valve in the Head Spray line. The only function of the valve is to provide Head Spray flow during shutdown to collapse the steam bubble.

3. The test frequency is as required by IWV-3511. The opening pressure will be determined per the requirements of ASME PTC 25.3-1976.

4. The testing of the Standby Liquid Control System explosive-actuated valves will be performed per the Technical Specifications requirements which exceed the requirements of IWV.

l S. The opening function of this normally closed check valve is proven every 3 i

months during pump operability testing. Design flow will be passed through the valve.

6. This valve is exempted from testing per IWV-1200. The function of this flow control valve is system control only.

7. This fail-open solenoid valve which is controlled by the pump starting sequence will be removed per design change in a future outage. In the interim O the fail-open function of the valve will be proven every quarter during pump testing. At the time the pump is tested the cooling water flow will be verified through a sight glass.

l 8. This normally closed valve opens and closes at set pressures. The l safety-related function of this valve is in the closed position as a l containment isolation valve. Operability of the valve is proven during pump testing.

9. This valve is a fail-open A0 pressure control valve that opens and closes at set pressures. The primary function of the valve is to regulate system pressure as the pump is started up. Operability of the valve is proven during

! pump testing.

1

10. This valve is a self-modulating pressure control valve that is exempt from testing per IWV-1200(a). The fail-open position will be verified during pump testing by observing that the valve is open when there is no flow through the valve.

11. This check valve is normally full open, therefore it does not have to change position to perform any safety related function.

12. This valve is used for testing valves T48-F323A-L (or 2T48-F323A-L) and has no safety related function.

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13- This aar ally-open feedwater check valve has an air assist for tight O closure and position indication lights. Closure will be proven each cold l

shutdown, but not more frequent than once per 3 months, by observing the indicating lights.

14. This normally closed valve is opened during testing only; therefore, it j is passive and does not require testing.

15. This valve is locked open and has no safety related function requiring stroking the valve.

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16. This valve functions only as a pressure / flow control valve; therefore, it is exempt per IWV-1200.

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6.1 Relief Requests for Class 1, 2, and 3 Valves 6.1.1 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months.

6.1.1.1 Basis for Relief This containment isolation valve is normally open with design flow passing through it during normal operation. The only practical method of verifying closure is to introduce reverse flow through the valve and measure leakage.

6.1.1.2 Alternate Testing l

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This verification is performed each refueling outage during local leak rate j testing.

6.1.2 Test Requirement l

IWV-3423(d) requires that gate valves with the functional differential pressure greater than 15 psi be tested for leakage in the same direction as when the valve is performing its function.

6.1.2.1 Basis for Relief 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 (or the reactor vessel) and cannot be pressurized for testing.

6.1.2.2 Alternate Testing

This containment isolation valve will be leak rate tested in a

! non-conservative reverse direction as addressed in the containment leak rate j test program for the type C leakage tests.

6.1. 3 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months.

6.1.3.1 Basis for Relief This valve is designed to prevent a water leg from forming in the relief line discharge line under vacuum conditions. Since there is no flow through the valve and it is a simple check valve, it cannot be tested as required.

6.1.3.2 Alternate Testing Each refueling outage (when the containment is de-inerted) the movement of the disc will be observed to see that it moyes freely.

6.1.4 Test Requirement IWV-3411 requires that valves be exercised at least once per 3 months.

6.1.4.1 Basis for Relief This valve cannot be full-stroked during power operation because flow to the core would be reduced by one-half. The valve control circuitry does not allow

. partial stroking of the valve.

6.1.4.2 Alternate Testing O This valve will be tested each cold shutdown but not more frequently than once per 3 months.

6.1.5 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months.

6.1. 5.1 Basis for Relief This normally closed standby liquid control check valve cannot be opened without introducing flow through it with a pressure greater than reactor pressure.

6.1.5.2 Alternate Testing Design flow through this valve is achieved once per 18 months due to the requirements of the Technical Specifications.

6.1.6 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months and IWY-3421 requires that Category A valves be leak tested.

6.1.6.1 Basis for Relief Since there is no valve between the check valve and the torus the line cannot be pressurized to ensure closure of the valve. This valve is the inboard containment isolation valve for the core spray test line. The outboard isolation is a closed system as defined in the Appendix J program. This valve l

is sealed from the primary containment atmosphere because the test line terminates below the water level of the torus and the leakage is not included in the type C local leak rate testing.

6.1. 6. 2 Alternate Testing l

The integrated leak rate test will prove that leakage through the valve and I closed system does not occur. There are no other practical means of testing this check valve.

1 1 6.1.7 Test Requirements IWV-3521 requires that check valves be exercised at least once per 3 months, i

6.1. 7.1 Basis for Relief These normally closed check valves do not receive " full-open" flow during normal operation or shutdown conditions. There has been no practical method demonstrated to fully stroke these valves.

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6.1. 7. 2 Alternate Testing j

These valves were supplied with a test switch to allow partial stroking during operation; however, the design of the test mechanism does not provide proper testing. Modifications are to be performed, and if they prove successful, the l valves will be partially stroked once per 3 months.

( At least one of the RHR system check valves will receive shutdown cooling flow i through it during cold shutdown conditions; however, the flow is not l sufficient to fully open the valve.

l i Valve integrity will be proven during leak rate tests each refueling outage because this valve is a pressure isolation valve and must pass the leakage tests.

One of the two valves in the system will be disassembled on a rotating basis every other refueling outage. If the valve is detemined to be non-functional, so that design flow would not pass through the valve, the other valve would then be disassembled and inspected.

6.1.8 Test Requirement l

IWV-3521 requires that check valves be exercised at least once per cycle.

6.1.8.1 Basis for Relief Testing of this normally closed check valve during normal operation requires Q removing the associated RHR train from operational status in order to relieve the differential pressure across the valve, thereby decreasing the level of plant reliability.

6.1.8.2 Alternate Testing The valve will be tested each refueling outage but not more frequently than once per 3 months.

6.1.9 Test Requirement IWV-3417(a) 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 observed, 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. 9.1 Basis for Relief 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.

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6.1. 9. 2 Alternate Testing O 1hese vaives .iii be stroked every coid shutdown but not more frequentiy inan once per 3 months.

6.1.10 Test Requirement IWV-3411 requires that valves be exercised at least once per 3 months.

6.1.10.1 Basis for Relief Valve E41-F007 cannot be closed during normal operation because its failure in the closed 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.

6.1.10.2 Alternate Testing The operability of E41-F006 and E41-F007 will be demonstrated during each cold shutdown but not more frequently than once per 3 months.

6.1.11 Test Requirement IWV-3423 requires that valves be leak tested with the pressure differential in the same direction as when the valve is performing its function.

6.1.11.1 Basis for Relief This turbine exhaust containment 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 piping on the inboard side of the valve runs directly from the valve to the torus and cannot be pressurized for testing.

6.1.11.2 Alternate Testing As an alternate, the valve is closed with the closure mechanism and leak tested from the reverse side. The leak test, as defined in the containment leak rate test program, is conservative since the test pressure tends to lift the disc from the seat much in the same manner as reverse testing a globe valve.

6.1.12 Test Requirement IWV-3521 requires that check valves be exercised every 3 months.

6.1.12.1 Basis for Relief Check valves E51-F001, E51-F002, E51-F028, E51-F040, E41-F021, E41-F022, E41-F040 and E41-F049 are located on the RCIC or HPCI turbine steam exhaust lines. During quarterly pump testing these valves are partially stroked during system operation; however, test conditions do not provide sufficient i J flow to prove that the valves are fully open.

6.1.12.2 Alternate Testing n One of these valves will be disassembled on a rotating basis each refueling U outage. If the valve is determined to be non-functional, so that design flow would not pass through the valve, an additional valve will be disassembled.

Failure of this valve would require disassembly of the remaining valves.

6.1.13 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months.

6.1.13.1 Basis for Relief Valve E41-F045 is a normally closed check valve located on the HPCI pump suction line and cannot be stroked. This valve does not see flow during any normal mode of reactor operations or shutdown conditions. Testing of this valve would require pumping water from the torus to the condensate storage tank, thereby lowering the water quality in the tank.

6.1.13.2 Alternate Testing Degradation of this valve is not expected because wear does not occur in a closed check valve. To ensure that the valve will open if needed, it will be disassembled every other refueling outage to prove that the disc is free to move.

6.1.14 Test Requirement IWV-3521 requires that check valves be exercised at least once per 3 months.

O 6.1.14.1 Basis for Relief Nomally closed check valves P41-F024A&B, P41-F025A&B, P41-F026A&B, and P41-F028A&B (or Unit 2 valves 2P41-F024A&B, 2P41-F025A&B, 2P41-F026A&B, and 2P41-F028A&B) supply service water L. RHR & Core Spray, HPCI, and RCIC pump and pump room coolers. During quarterly testing of the pumps, the coolers are placed in operation, thereby stroking these valves. However, the design of the system does not provide for positive verification of the flow rate through each valve.

6.1.14.2 Alternate Testing One valve will be disassembled each refueling outage on a rotating basis to ensure that the design function of the valve can be achieved. If the valve is detemined to be non-functional, an additional valve will be disassembled.

Failure of this valve will require the disassembly of the remaining valves for that unit.

6.1.15 Test Requirement IWV-3413(b) requires stroke times shall be measured to the nearest second, for stroke times 10 seconds or less, or 10% of the specified limiting stroke time for full-stroke times longer than 10 seconds.

i i IWV-3417 requires that if the stroke time increases by 25% from the previous test for valves with full-stroke times greater than 10 seconds or 505 for valves will full-stroke times less than 10 seconds, the test frequency shall O be incre. sed to once each month untii corrective action is taken.

6.1.15.1 Basis for Relief These valves are air operated valves without indicating lights or control l switches. Measurement of stroke times can be perfomed only by observation of the stem movement when the associated room cooler is placed into operation.

This type of testing does not provide the accuracy required by IWY-3413(b) and IWV-3417.

i 6.1.15.2 Alternate Testing

A maximum stroke time which will be as short as practical will be assigned to i each valve. If the measured stroke time exceeds this value, the valve will be declared inoperable.

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6.1.16 Test Requirement IWV-3411 requires that valves be exercised at least once per 3 months.

l 6.1.16.1 Basis for Relief l

Closure of this normally open valve would totally interrupt flow to the drywel' coolers. This interruption may cause an increase in drywell temperature which would require removing the unit from operation. The valve cannot be partially stroked due to control circuitry.

6.1.16.2 Alternate Testing This valve will be stroked every cold shutdown but not more frequently than once per 3 months.

6.1.17 Test Requirement IWV-3411 requires that valves be exercised at least once per 3 months.

6.1.17.1 Basis for Relief Closure of this valve during normal power operation would interrupt flow to the turbine building equipment normally cooled by service water. This valte cannot be partially stroked due to control circuitry.

6.1.17.2 Alternate Testing This valve will be stroked every cold shutdown but not more frequently than once per 3 months.

6.1.18 Test Requirement IWY-3411 requires that valves be exercised at least once per 3 months.

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6.1.18.1 Basis for Relief Closure of this valve during normal operation would shut off the cooling water O to a Reactor Recirculation System pump.

6.1.18.2 Alternate Testing This valve will be stroked every cold shutdown but not more frequently than once per 3 months.

6.1.19 Test Requirement IWV-3417(b) and IWV-3523 state that when corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup.

6.1.19.1 Basis for Relief Startup of the plant is governed by the Technical Specifications.

6.1.19.2 Alternate Testing Under such conditions startup shall be permitted as provided in the Technical Specifications.

6.1.20 Test Requirement IWY-3411 requires that valves be exercised at least once per 3 months.

6.1.20.1 Basis for Relief If this valve is opened during normal operation, a single failure of the second isolation valve in the line or operator error may result in damage to the lower-pressure piping and equipment. Due to control circuity this valve cannot be partially stroked.

6.1.20.2 Alternate Testing This valve will be stroked every cold shutdown but not more frequently than once per 3 months.

6.1.21 This Relief Request number is not used l

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6.1.22 Test Requirement IWV-1100 provides the rules and requiremants for inservice testing of certain Class 1, 2, and 3 valves which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident.

The Control Rod Drive (CRD) System valves will not be individually tested per this requirement.

6.1.22.1 Basis foe Relief The Plant Technical Specifications require all operable withdrawn control rods to be exercised at least once per week when above a designated power level.

After each refueling outage, all control rods capable of normal insertion shall be scram timed from the fully withdrawn position. Also,10% of the rods shall be scram timed from the fully withdrawn position at least once per 120 days of operation. The Technical Specifications give the allowable insertion times for these tests.

6.1.22.2 Alternate Testing The Technical Specifications adequately demonstrate the operability of the Control Rod Drive System and the additional requirements of ASE Section XI would not increase the level of safety. Therefore, Technical Specifications testing will be used in lieu of the ASME Section XI requirements.

Q 6.1.23 Test Requirement As a result of experience in leak rate testing of the Main Steam Isolation Valves (MSIV) at Plant Hatch, Georgia Power Company (GPC) requests relief from the application of some of the requirements of IWV-3427(b) of the 1980 edition of the ASME Section XI Code to the future testing of these valves. The sixteen valves affected by this relief requested are Hatch Unit 1 valves 1821-F022A, B, C, D and 2821-F028A, B, C, D.

The ASME Section XI Code requires that Category A valves, such as the MSIVs, be tested at least once every 24 months unless a test shows that the margin (between the measured leakage rate and the maximum permissible rate) has been l reduced by 50% or greater. If there is a reduction in margin by 50% or l

greater as discussed above, the frequency of leakage testing should be doubled (i.e., performed approximately every 12 minths) and performed to coincide with a cold shutdown. In addition, trending of the leakage rates is required.

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7.0 Inservice Testing of Pumps

, The 1980 ASE Section XI code with Addenda thru Winter 1981 requires inservice Q testing of pumps in accordance with Section IWP. The inservice testing program for Class 1, 2, and 3 pumps is described in the following tables. Where full compliance with the Code is not practical, relief has been requested.

Per IWP-3210, Georgia Power Company has set their own allowable ranges of test parameters.

Vibration Limits For the RHR Service Water Pumps, the Plant Service Water Pumps, and the Standby Diesel Generator Service Water Pumps, the following ranges are different than those found in Table IWP-3100-2.

Test Quantity Acceptable Alert Required Action 0<VR s 2.0 0 <V s 2 VR 2VR <V s 3VR V >3YR 2<VR s5 0<V s (2+VR ) (2+VR ) < Y s (4+VR ) V >(4+VR)P VR >5 0 <V s (1.4YR) 1 4VR <Vsl.8VR V>l.8VR VR is procedurally set to be a minimum of 1.5 mils. Per manufacturers reconcendations, these pumps will operate satisfactorily with vibrations in excess of 4 mils.

Flow and Differential Pressure Limits For the RHR Pumps, the Core Spray Pumps, the Standby Liquid Control Pumps, the RHR Service Water Pumps, the Standby Diesel Generator Service Water Pumps, the Jockey Pumps, the HPCI pump, and the RCIC pump, the following ranges are different than those found in Table IWP-3100-2.

Test Quantity Acceptable Alert Required Action AP .93 to 1.05 APR 2.9 and <.93 APR <.9 or > 1.05 APR Q .94 to 1.05 QR 2.9 and <.94 Qg <.9 or > 1.05 QR These values were determined through a review of historical data and the use of such will not impact the ability to detect degradation of the pumps.

For the Plant Service Water Pumps, the following ranges are different than those found in Table IWP-3100-2.

Test Quantity Acceptable Alert Required Action AP .93 to 1.1 APR 2.9 and <.93 A PR <.9 or>l .1 A PR Q .94 to 1.1 QR 2.9 and <.94 QR <. 9 or > 1.1 QR O

These values were determined through a review of historical data and the use of such will not impact the ability to detect degradation of the pumps. The Q variance for these pumps is due primarily to using a manual butterfly valve for throttling and the subsequent inability to match the flow-rate of the previous test.

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O O O Plant Hatch - Unit No.1 Inservice Inspection Program for

' ASME Code Class 1, 2, and 3 Pumps i ASME Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested C41-C001 A Standby Liquid Control 2 1. Inlet pressure NA 7.1. 5 C41-C0018 2. Differential pressure NA 7.1.5

3. Flow rate Every 3 mos. 7.1.2

4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure

Ell-0002A Residual Heat Removal 2 1. Inlet pressure Every 3 mos. No Ell-00028 2. Differential pressure Every 3 mos. No l

j Ell-0002C 3. Flow rate Every 3 mos. No 1

l Ell-00020 4. Vibration amplitude Every 3 mos. No l S. Bearing temperature Annually 7.1.1

\

j 6. Lubricant level or Every 3 mos. 7.1.4 pressure l

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Plant Hatch - Unit No. I 1 Inservice Inspection Program for j ASE Code Class 1, 2, and 3 Pumps

! ASME '

Pump Code Section XI Code Identification Pump Description Class_

Measured Parameters Test Interval Relief Requested E11-C001A RilR Service Water 3 1. Inlet pressure Every 3 mos. 7.1.3 E11-C0018 2. Differential pressure Every 3 mos. 7.1. 3 E11-C0010 3. Flow rate Every 3 mos. No L11-C0010 4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually 7.1.1

6. Lubricant level or Every 3 mos. 7.1.4 l pressure E21-C001 A Core Spray 2 1. Inlet pressure Every 3 mos. No

, E21-C0018 2. Differential pressure Every 3 mos. No

3. Flow rate Every 3 mos. No

4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually 7.1.1

6. Lubricant level or Every 3 mos. 7.1. 4 4 pressure a

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O O o Plant Hatch - Unit No.1 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASE '

Pump Code Section XI Code Ideatification Pump Description Class Measured Parameters Test Interval Relief Remested i

! E41-C001 High Pressure Coolant 2 1. Inlet pressure Every 3 mos. No i Injection

2. Differential pressure Every 3 mos. No i

3. Flow rate Every 3 mos. No i

i

4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No l

i pressure

7. Pump speed Every 3 'mos. No l

t i E51-C001 Reactor Core 2 1. Inlet pressure Every 3 mos. No

Isolation Cooling

2. Differential pressure Every 3 mos. No

3. Flow ra te Every 3 mos. No l Every 3 mos.

i 4. Vibration amplitude No J

5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure 1

7. Pump speed Every 3 mos. No

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Plant Hatch - Unit No.1 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASE '

Pump Code Section XI Code Idextification Pump Description Class Measured Parameters Test Interval Relief Reesested E2)-0002A Jockey pump 2 1. Inlet pressure Every 3 mos. No E21-C002B 2. Differential pressure Every 3 mos. No

3. Flow rate NA 7.1. 7 I 4. Vibration amplitude Every 3 mos. No

'I 5. Bearing temperature Annually No I

6. Lubricant level or NA 7.1.4 pressure P41-C001 A Plant Service Water 3 1. Inlet pressure Every 3 mos. 7.1. 3 P41-C001B 2. Differential pressure Every 3 mos. 7.1. 3 P41-C001C 3. Flow rate Every 3 mos. No P41-C001D 4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually 7.1.1 i 6. Lubricant level or Every 3 mos. 7.1.4 pressure l

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P1 ant Hatch - Unit No. 2 Inservice Inspection Program for

' ASE Code Class 1, 2, and 3 Pumps l

ASE Pump Code Section XI Code Ide7.ti fication Pump Description Class Measured Parameters Test Interval Relief Requested 2C41-C001A Standby Liquid Control 2 1. Inlet pressure NA 7.1. 5 l

2C41-C001B 2. Differential pressure NA 7.1.5

! 3. Flow rate Every 3 mos. 7.1.2

}

I 4. Vibration amplitude Every 3 mos. No i

S. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure 2 Ell-C002A Residual Heat Removal 2 1. Inlet pressure Every 3 mos. No l 2E11-C002B 2. Dif ferential pressure Every 3 mos. No 2 Ell-0002C 3. Flow rate Every 3 mos. No

! 2E11-C0020 4. Vibration amplitude Every 3 mos. No 1

S. Bearing temperature Annually 7.1.1

6. Lubricant level or Every 3 mos. 7.1. 4 3

pressure j

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O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class i., 2, and 3 Pumps ASE Pump Code Section XI Code Identi fication Pump Description Class Measured Parameters Test Interval Relief Requested 2E11-C001A RHR Service Water 3 1. Inlet pressure Every 3 mos. 7.1. 3 2E11-C001B 2. Differential pressure Every 3 mos. 7.1.3 2E11-C001C 3. Flow rate Every 3 mos. No 2E11-0001D 4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually 7.1.1

6. Lubricant level or Every 3 mos. 7.1.4 pressure 2E21-C001 A Core Spray 2 1. Inlet pressure Every 3 mos. No 2E21-C001B 2. Differential pressure Every 3 mos. No i 3. Flow rate Every 3 mos. No

4. Vibration amplitude Every 3 mos. No S. Bearing temperature Annually 7.1.1 i

6. Lubricant level or Every 3 mos. 7.1. 4 pressure i

O O o Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASME J Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested l

2E21-C002A Jockey pump 2 1. Inlet pressure Every 3 mos. No 2E21-C002B 2. Differential pressure Every 3 mos. No

! 2E21-C003A 3. Flow rate NA 7.1.7 2E21-C0038 4. Vibration amplitude Every 3 mos. No

! 5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure j 2P41-C001 A Plant Service Water 3 1. Inlet pressure Every 3 mos. 7.1. 3 2P41-C0018 2. Differential pressure Every 3 mos. 7.1.3 2P41-C001C 3. Flow rate Every 3 mos. No 2P41-C001D 4. Vibration amplitude Every 3 mos. No l

S. Bearing temperature Annually 7.1.1 1

6. Lubricant level or Every 3 mos. 7.1.4 pressure

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[ O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps i ASE Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested 2P41-C002 Standby Diesel 3 1. Inlet pres:ure Every 3 mos. 7.1.3 Gen. Service Water

2. Differential pressure Every 3 mos. 7.1. 3 i 3. Flow rate Every 3 mos. No

4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually 7.1.1

6. Lubricant level or NA 7.1.4 pressure 2E41-C001 High Pressure 2 1. Inlet pressure Every 3 mos. No l Coolant Injection

2. Differential pressure Every 3 mos. No

3. Flow rate Every 3 mos. No I

4. Vibration amplitude Every 3 mos. No l

4 5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure i

7. Pump speed Every 3 mos. No I

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O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASME i

Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested 2E51-C001 Reactor Core 2 1. Inlet pressure Every 3 mos. No Isolation Cooling

2. Differential pressure Every 3 mos. No

3. Flow rate Every 3 mos. No

4. Vibration amplitude Every 3 mos. No

5. Bearing temperature Annually No

6. Lubricant level or Every 3 mos. No pressure

7. Pump speed Every 3 mos. No s

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O 7.1 Relief Requests for Class 1, 2, and 3 Pumps 7.1.1 Test Requirement IWP-4310 requires that the temperature of bearings outside the main flow path be measured.

7.1.1.1 Basis for Relief The bearings (or bearing surfaces) are cooled by tne process fluid that is being pumped.

7.1.1.2 Alternate Testing The bearings will be inspected for wear whenever the pump is disassembled for maintenance.

7.1.2 Test Requirement Table IWP-4110-1 requires that flow be measured within 12% of . full scale.

7.1. 2.1 Basis for Relief i Flowrate is measured by the change in the Standby Liquid Control test tank 1evel during a two minute test period.

Q 7.1.2.2 Alternate Testing l Georgia Power Company has determined that the method of calculating flow is I within an acceptable accuracy.

7.1.3 Test Requirement Table IWP-4110-1 requires that pressure be measured within 12% of full scale.

7.1.3.1 Basis for Relief Inlet pressure is determined for this group by measuring the river level at the intake structure. The differential pressure is then:

O P = Po + (114.5' - River Water Level) x 0.433 7.1. 3. 2 Alternate Testing .

This method of measurement is well within the code requirement for the determination of the differential pressure.

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7.1.4 Test Reerirement Table Ilf-3100-1 requires that the proper lubricant level or pressure be observed.

7.1.4.1 Basis for Relief This pump is lubricated by the process fluid that is being pumped.

7.1.4.2 Alternate Testing The applicable parameters in Table IWP-3100-1 will be measured.

7.1. 5 Test Requirement Table IWP-3100-1 requires that inlet pressure, differential pressure, and flowrate be measured.

7.1.5.1 Basis for Relief The Standby Liquid Control pumps are positive displacement pumps for which the outlet pressure is constant regardless of inlet pressure. No A P or inlet pressure measurements will bo made.

7.1.5.2 Altcenate Testing O The outlet pressure and the flowrate is measured.

7.1.6 Relief Request number not used 7.1.7 Test Requirement Table IWP-3100-1 requires that both the differential pressure and the flowrate be measured.

7.1. 7.1 Basis for Relief The only function of this pump is to maintain a water inventory in the RHR and Core Spray piping system and flow rate instrumentation is not required.

However, discharge is into a fixed resistance system; therefore, measurement of both parameters is not required to determine degradation of the pump.

7.1.7.2 Alternate Testing The differential pressure will be measured during each pump test.

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8.0 EMRAL RELIEF REQUESTS 1

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directly "toar ' "" 'but any individual section are " "' ""'*"

general in nature. da "a' '*

I 8.1 Remasts for Relief From ASME Section XI Requirements 8.1.1 Basic Calibration Blocks for Pipe Wald Examinations 8.1.1.1 Requirement From Which Relief is Requested Appendix III of Section XI delineates the requirements for the design and fabrication of basic calibration blocks for pipe weld examinations. It specifies that the basic calibration block shall be fabricated with notches and that the basic calibration block nominal diameter and thickness be equivalent to the component to be examined. Relief is requested so that existing basic calibration blocks may be used for pipe weld examinations.

8.1.1.2 Justification The majority of existing Hatch basic calibration blocks used for pipe weld examinations were fabricated with diameters, thicknesses, and side-drilled holes in accordance with the 1974 Edition of ASME Section V. For the two primary reasons listed below, these same basic calibration blocks will be used

, to provioe the most meaningful and thorough examinations possible:

1. Side-drilled holes as calibration reflectors result in a more sensitive ultrasonic examination than one us'ng notches.

O 2. Correlation of ultrasonic data with previous examinations as required by Subarticle IWA-1400 of Section XI makes it necessary that these basic calibration blocks be used so future examination results can be correlated with past results.

8.1. l . 3 Testing in Lieu of Section XI Requirements The basic calibration blocks using side-drilled holes as calibration reflectors will be used for the majority of the pipe weld examinations.

8.1.2 Allow Hatch 2 To Start its Second 10-Year Inspection Interval on January 1,1986 8.1.2.1 Requirement from Which Relief is Requested According to 10 CFR Part 50.55a(g)4(11), inservice examination of components during successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the approved ASME Section XI Code 12 months prior to the start of the 120-month inspection interval.

Permission is requested to start Hatch 2, the second period (80 months) of Hatch 2 will end on January 5,1986. This date virtually coincides with the

' start date of the second 10-Year interval for Hatch 1 (January 1,1986).

Permission is requested to start the Hatch 2 second 10-Year inspection interval 40 months ahead of schedule such that the two units would comply with O the same Code requirements.

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8.1.2.2 Justification

O w. i orm. I -tion re,ui-e. for natch i are presenti, in couance with ASE Section XI, Winter 1980 Addenda. A move to start the second 10-Year

' interval for Match 2 on January 1,1986 would require compliance with ASME Code Section XI, Winter 1981 Addenda, which is more stringent and is the latest approved Code. A more comprehensive inspection would be achieved. In

addition, compliance with the same Code for both units will enhance the possibility to detect a generic problem and would also reduce cost involved in maintaining two separate programs. The RPV welds will also be examined at the same point in time as was planned in the earlier program (i.e., those welds that were scheduled during the third forty-month period will be examined during the first forty-month period of the new ten-year interval). In l discussions with the NRC HNP Licensing Project Manager and appropriate NRC t

staff personnel, they have indicated that this is a reasonable approach. The l

proposed change will not endanger public health and safety.

8.1.2.3 Testing in Lieu of Section XI Requirements l None.

8.1.3 Incorporation of Changes in Desiga, Testing, and Procedures without any Unreviewed Safety Questions into The Inservice Inspection Program / Plan 8.1.3.1 Requirement From Which Relief is Requested 10 CFR Part 50.59 allows changes to a nuclear facility and procedural changes in accordance with Plant Technical Specifications and the safety analysis -

O report, withcut prior approval from the NRC, provided there are no unreviewed safety questions. The facility's Inservice Inspection Program / Plan should be revised to include these changes.

Changes such as valve operator, stroke time, pump perfonnance, welds, etc.,

i made in compliance with 10 CFR 50.59, which affects the ASPE Section XI requirements may not be shown on the existing revision of the ISI program plan document. A relief is requested from this inconsistency.

8.1.3.2 Justification Records of these changes will be maintained and any changes in ASME Section XI requirements pertaining to these changes will be complied with. However, a revision to the ISI Program Plan (s) for every minor change is unrealistic, costly and time consuming task. Any delay in revising the ISI program plan (s) will not endanger public health and safety.

8.1.3.3 Testing in Lieu of Section XI Requirements Records of all changes will be maintained. Changes affectir:g ASME Section XI requirements shall be incorporated into the ISI Program Plan (s), whenever a need for their update is warranted.

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l 8.1.4 Exempting Subsection IWE. and the References to IE in other Subsections O 8.i. i ir ent from Which Reifef is Re ested l

Table IE-2500-1, code categories E-A, E-A-1, E-8, E-C, E-D, E-E, E-F, E-G, and E-P of ASE Section XI, Winter 1981 Addenda delineates examination requirements of containment.

8.1.4.2 Justification Federal Register, Vol. 48, No. 28/ Monday, February 7,1983, Page 5532 relative to 10 CFR Part 50 Codes and Standards for Nuclear Power Plants; Item No. 4, indicates that Subsection IWE, " Requirements for Class MC Components of Light Water Cooled Power Plants" was added to Section XI by Winter 1981 Addenda.

However,10 CFR Paragraph 50.55a presently only incorporates those portions of Section XI that address the ISI requirements for Class 1, 2, and 3 components and their supports. The regulations do not currently address the ISI of containments. Since this amendment is only intended to update current regulatory requirements to include the latest Code adder.da, the requirements of Subsection IWE are not imposed upon Licensees by the NRC as a result of this amendment.

8.1.4.3 Testing in Lieu of Section XI Requirements None.

8.1.5 Due Date for Owner's Data Report for Inservice Inspection, Fom NIS-1 8.1.5.1 Requirement From Which Relief is Requested Paragraph IWA-6230 of ~ Section XI requires that the Owner's Data Report for Inservice Inspection, Form NIS-1, shall be filed with the enforcement and regulatory authorities (in this case, the Nuclear Regulatory Commission) within 90 days of the completion of the inservice inspection. Relief from the ISI completion date relative to the reporting requirement and the due date are requested.

8.1.5.2 Justification The 90-day due date from the completion of the inservice inspection is unrealistic to prer = e the NIS-1 Form and to have the multiple reviews required. The preparation of the NIS-1 Form itself requires al'mt 90 days with at least another 30 days needed for the review by site peeser.nel and the l Inspector.

8.1. 5. 3 Reporting in Lieu of Section XI Requirements Form NIS-1 will be submitted to the NRC within 120 days after completion of the outage in which the examinations were perfonned.

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