ML20076E107
| ML20076E107 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/12/1983 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20076E099 | List: |
| References | |
| PROC-830812, NUDOCS 8308240134 | |
| Download: ML20076E107 (136) | |
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- EDWIN I. HATCH NUCLEAR PLANT I
! UNITS 1 AND 2
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! RESPONSE TO
! THE PROVISIONS OF 1
10 CFR 50.55a(g) l 1
" INSERVICE INSPECTION PROGRAM" l I I i
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O TABLE OF CONTENTS 1.0 I n tro du c ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -1 i 2.0 Inservice Inspection for l Cl a s s 1 Compo ne n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 l 3.0 Inservice Inspection for Cl a s s 2 Compo ne n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 4.0 Inservice Inspection for Cl a s s 3 Compone n ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 5.0 Inservice Inspection for Class 1, 2, and 3 I C ompone n t Su p ports. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 6.0 Inservice Testi ng o f Va1 ves. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 l
7.0 In servi ce Tes ti ng of Pump s. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7-1 O
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1.0 INTRODUCTION
1.1 General This document describes the revised Inservice Inspection (ISI) Program for Edwin I. Hatch Nuclear Plant, Units 1 and 2. The previous ISI programs for Hatch 1 and 2 were prepared in accordance with the 1974 Edition of Section XI with Addenda through Su m er 1975.
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 1980.
1.2 Effective Date The revised ISI program shall go into effect on January 1,1984.
1.3 Scope This document is a description of the ISI progran for Units 1 and 2 of Plant Hatch. The programs for Class 1, 2, and 3 component examinations and for pump and valve surveillance testing are included.
1.4 Component Upgrading All plant components have been reviewed to determine the appropriate classification for inservice inspection. Regulatory Guide 1.26 was used for pd guidance in determining component classifications.
It must be noted that the classification of components as ASME Class 1, 2, or 3 equivalent for inservice inspection does not imply that the components were designed in accordance with ASME requirements. The component design codes 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 80 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 Regulatory Commission (NRC) approved edition of ASfE Section XI. The inservice program for pumps and valves will be similarly reviewed and modified l
at that time. The 80-month date is being used so that the start date of the l
following 120-month interval of the ISI program for the two units will l
coincide. At that time, Hatch 2 will have completed its first 120-month interval while Hatch 1 will have completed 160 months of operation.
1.6 Responsibility Georgia Power Company bears the overall responsibility for the performance of the inservice inspection activities. Certain nondestructive examinations will be performed by qualified examination agencies. The results of such I
j examinations will be reported to Georgia Power Company for final disposition.
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1.7 Records Records and documentation of information and examination results, which provide the basis for evaluation and which facilitate comparison with results i
O 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 I
the exception of the due date for the Owner's Report for Inservice Inspection, i
Form NIS-1 (see Paragraph 137.1 for Relief Request).
, 1.7.1 Due Date for Owner's Report for Inservice Inspection, Form NIS-1
,1. 7.1.1 Requirement From Which Relief is Requested Paragraph IWA-6230 of Section XI requires that the Owner's Report for i
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 this due date is requested.
1.7.1.2 Justification The 90-day due date is unrealistic to prepare the NIS-1 Form and to have the j
i multiple reviews required. The preparation of the NIS-1 Form itself requires almost 90 days with at least another 30 days needed for the review by site personnel and the Inspector.
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- 1. 7.1. 3 Reporting in Lieu of Section XI Requirements O The NIS-1 Form will be submitted to the NRC within 120 days of the completion of the inservice inspection.
i 1.8 Methods of Examination '
The method of examination planned for each area is delineated in subsequent sectiors. Personnel performing NDT examinations will be trained in accordance with the American Society for Nondestructive Testing (ASNT) "Reconnended Practice SNT-TC-1A, Supplements and Apprendices", as applicable for technique and method used.
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 requirements of IWA-2232 of ASE Section XI except as requested by relief.
1.8.2 Radiographic Examination (RT)
Radio' graphic techniques will be used to supplement UT as required.
1.8.3 Liquid Penetrant Examination (PT)
Dye penetrant examinations will be performed whenever a surface examination is required on non-magnetic piping.
l.8.4 Magnetic Particle Examination (MT)
Magnetic particle tests will be used when surface examination of carbon steel components is required.
1.8.5 Visual Examination (VT)
Visual examinations are divided into four types:
- a. VT-1 This examination shall be conducted to determine the condition of the part, component, or surface examined.
- b. VT-2 This examination shall be conducted to locate evidence of leakage from pressure retaining components. .
- 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 oetermine conditions relating to the operability of components or devices.
d O i9 staadards for exa=taatioa eve 1uatioa The acceptance standards for Class 1 components will be either IWB-3000 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.
For Class 1, 2, and 3 component supports, the acceptance standards of Article IWF-3000 are in the course of preparation. The Winter 1981 Addenda to the 1980 Edition lists acceptance standards and since the NRC has approved this Addenda, guidance will be taken from Subarticle IWF-3400 of the Winter 1981 Addenda.
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 by utilizing Georgia Power Company approved procedures t.hich 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.
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l 1.11 Authorized inspection Agency Q IWA-1400 requires that the owner be in possession of an arrangement with an Authorized Inspection Agency to provide inspection services and IWA-2120 i
specifies the duties of the Inspector. Also, IWA-4140 requires that the services of an Authorized Inspection Agency be employed when making a welded repair.
Although Georgia is a Code state,Section XI is not in the jurisdiction of a state enforcement authority; therefore, an Inspector is not required. Also, Georgia Power Company (GPC) Quality Control and Quality Assurance provides essentially the same function by auditing all inspections, repairs, procedures, etc. In addition NRC inspectors regularly audit these same items.
Georgia Power Company will use an Authorized Inspection Agency to provide an Inspector on an as needed basis, whenever GPC feels their use is warranted.
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2.0 INSERVICE INSPECTION FOR CLASS 1 COMPONENTS 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 Os ASME Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1980. 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 al ternative. Table IWB-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 IWB-5000. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of piping (e.g., boundary is check valve), the sections will be tested together at the lower of the specified test pressures. No point in the piping shall be permitted to experience a pressure greater than the specified test pressure.
Components that are exempted from volumetric and surface examination by IWB-1220 will be hydrostatically tested per the requirements of IWA-5000 and IWB-5000.
2.1 Requests for Relief From ASME Section XI Requirements O 2.1.1 Volumetric Examination of Reactor Pressure Yessel and Closure Head i Welds 2.1.1.1 Requirement From Which Relief is Requested Item Nos. Bl .ll, Bl .12, Bl .21, and Bl .22 of Table IWB-2500-1 require the volumetric examination of Reactor Pressure Vessel (RPV) and Closure Head circumferential, longitudinal, and meridional welds. At Hatch, these examinations will be performed using ultrasonic techniques. The applicable l examination volumes are shown in Figures IWB-2500-1, -2, and -3. The 1980 Edition with Addenda through Winter 1980 also requires that welds selected for I examination are to be ext. mined 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 Summer 1975 and earlier l
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 wel d. 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 Hatch 1. For Hatch 2 approximately 15% of the total length of the p circumferential welds can be examined. The percentages for the twelve v 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 RPV 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 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.
O 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 Section V requires that prior to the angle beam examination, the base material through which the angle beams will travel shall be scanned with a straight beam transducer to detect laminar reflectors which might effect 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 to Vessel welds, were examined with a straight beam transducer and laminar reflectors which would interfere with the angle beam scans were recorded. Since the size of these reflectors will not change, it is unnecessary to perform 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.
4 2.1.3 Volumetric Examination of Reactor Pressure Vessel and Closure Head Nozzle to Vessel Welds and Nozzle Inside Radius Sections 2.1. 3.1 Requirement From Which Relief is Requested
( Item Nos. 83.90 and B3.100 of Table IWB-2500-1 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 8
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, eight-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 V N2B N to V N2C N to V N2D N to V N2E N to V O N2F N to y N2G N to V
! N2H N to V i
N2J N to Y N2K N to V i N4B 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 welds 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 lietal Piping Welds 2.1.4.1 Requirement From Which Relief is Requested O Item nos. 85.10. 85.50. 89.ii. and 89.12 of Tabie IWB-2500-i 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 Housings. These volumetric examinatic,ns are to be performed 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 Section V.
2.1.4.2 Justification Article 5 of 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 clad overlaid. 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 Testing 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 be examined in accordance with Appendix III also.
2.1.5 Basic Calibration Blocks for Pipe Weld Examinations C 2.1.5.1 Requirement From Which Relief is Requested Appendix III of Section XI delineates the requirements for the design and fabrication of basic calibration biccks 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. ,
2.1.5.2 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 Section V. For the two primary reasons listed below, these same basic calibration blocks will be used to provide the most meaningful and thorough examinations possible
(1) Side-drilled holes as calibration reflectors result in a more sensitive ultrasonic examination than one using notches.
(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.
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2.1.5.3 Testing in Lieu of Section XI Requirements The basic calibration blocks using holes as calibration reflectors will be Q used for the majority of the pipe weld examinations.
2.1.6 Reactor Pressure Vessel Nozzle to Safe-End Welds (Nominal Pipe Size
< 4 Inches) 2.1.6.1 Requirement From Which Relief is Requested Item No. B5.11 of Table IWB-2500-1 requires a surface examination of the RPV nozzle to safe-end welds with nominal pipe size <4 inches. Relief from this requirement is requested.
2.1.6.2 Justification The 2-inch Hatch 2 RPV bottom head drain nozzle to safe-end weld can not be examined due to inaccessibility. Instrumentation lines and control rod housings surround this line and prevent the examiner from performing this examination. The weld listed above is the only one with known limitations.
2.1.6.3 Testing in Lieu of Section XI Requirements This weld will be tested per IWB-5000 since it is 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 a:4 Inches 2.1.7.1 Requirement From Which Relief is Requested Item No. B9.11 of Table IWB-2500-1 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.
1 Weld Identification No. Penetration No.
B21 -FW-18A-7A X-9A B21 -FW-18B-6A X-98 E51-RCIC-4-00T-20A X-10 E41-HPCI-10-0VT-15A X-11 Ell-RHR-20-B-Dischage-13A X-12 E11-RHR-24-A-Return-3A X-13A Ell-RHR-24-B-Return-3B X-13B G31-RWCU-6-0VT-15B X-14 G31 -RWCU-6-0UT-15C X-14 E21-CORE SPRAY-10-A-3A X-16A E21-CORE SPRAY-10-B-4A X-16B Ell-RHR-4-HS-6A X-17 O
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2.1.7.2 Justification These welds are inaccessible for examination due to the design of the flued Q 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 are a flued head with a Type 308L overlay 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 run for each new weld while the weld was accessible during the repair to ensure a high quality weld.
In accordance with IWB-5221, a system leakage test is to be performed prior to startup following each reactor refueling outage. This is the same type test that detected the crack in the original pipe.
Whenever the process piping to flued-head weld (outside containment) is volumetrically examined, the accessible weld of the flued-head penetration will have a surface examination performed on it.
2.1.8 ASME Class 1 (Equivalent) Valves Exceeding 4-Inches Nominal Pipe Size and ASME Class 1 (Equivalent) Pump Casings O 2. i .8.i Requirement rrom Wnich aeiief is aequested l
l Table IWB-2500-1, Item No. B12.40 requires a visual examination of the internal pressure boundary surfaces of one valve in each 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. B12.20 requires a visual examination of the internal pressure boundary surface of one of the two Reactor Recirculation system pumps.
2.1.8.2 Justification Disassembly of these valves and pumps for the visual examination during the inspection interval, in the absence of other required maintenance, represents an unnecessary exposure to radiation and contamination. Yalves 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 j to the physical location at the bottom of the system.
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l During rcutin2 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 O- internal examination is counter to tne "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 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 Housings 2.1. 9.1 Requirement From Which Relief is Requested Table IWB-2500-1, Item No. B14.10 requires a volumetric or surface examination of the pressure retaining welds in 10% of the peripheral control rod housings. Each housing has a lower weld located at the housing flange.
2.1.9.2 Justification O The lower welds are inaccessible for examination 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 arrangement. Also, the insert and withdraw lines to the Control Rod l Drive system are connected at the top of the housing flange and prevent access to much of the weld. The combination of these factors prevents these welds from being examined.
2.1.9.3 Testing in Lieu of Section XI Requirements These welds will be tested per IWB-5000 since they are located within the hydrostatic test boundary of the Nuclear Steam Supply system.
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O O O TABLE 1 Sh.1 of 11 ISI PROGRAM FOR ASME CLASS 1 C0t90NENTS 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 l 81.11 8-A Reactor Pressure Vessel Circumferential Shell Welds Volumetric Yes, 2.1.1 and
] 2.1.2
) Bl .12 B-A Reactor Pressure Vessel Longitudinal Shell Welds Volumetric Yes, 2.1.1 and 2.1.2 I'
Bl.21 B-A Reactor Pressure Vessel Circumferential Head Welds Volumetric Yes, 2.1.1 and and Closure Head 2.1.2 i
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B1.22 B-A Reactor Pressure Vessel Meridional Head Welds Volumetric Yes, 2.1.1 and and Closure Head 2.1.2
) 81.30 B-A Reactor Pressure Vessel Shell-to-Flange Weld Volumetric Yes, 2.1.2 l i 81.40 B-A Reactor Pressure Vessel Head-to-Flange Weld Surface and Yes, 2.1.2 Closure Head Volumetric-I B1.50 B-A Reactor Pressure Vessel Beltline Region Repair Volumetric Not applicable to j Welds either Hatch unit
! B2.10 B-B Pressurizer Shell-to-Head Welds Volumetric Not applicable to
- either Hatch unit 1
i B2.20 B-B Pressurizer Head Welds Volumetric Not applicable to j either Hatch unit j B2.30 B-B Steam Generator Head Welds Volumetric Not applicable to i (Primary Side) either Hatch unit l I B2.40 B-B Steam Generator Tubesheet-to-Head Welds Volumetric Not applicable to j (Primary Side) either Hatch unit j B2.50 B-B Heat Exchangers Shell or Head Welds Volumetric Not applicable to (Primary Side) either Hatch unit 1 B2.60 B-B Heat Exchangers Tubesheet-to-Shell Volumetric Not applicable to l (Primary Side) (or Head) Welds either Hatch unit
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O O TABLE 1 Sh. 2 of 11 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 B3.10 B-D Reactor Pressure Vessel Nozzle-to-Vessel Welds Volumetric Not applicable to either Hatch unit; GPC has elected to perfonn exami-nations in accor-dance with Program B.
83.20 B-D Reactor Pressure Vessel Nozzle Inside Radius Sectioc Volumetric Not applicable to either Hatch unit; GPC has elected to perfonn 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 l 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 7 (Primary Side) either Hatch unit
O O O TABLE 1 Sh. 3 of 11 ISI PROGRAM FOR ASE CLASS 1 COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 l Examination System or Com- Method of Code Relief i
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Item No. Category ponent Description Area (s) To Be Exanined Examination Requested 2
B3.80 B-D Heat Exchangers Nozzle Inside Radius Section Volumetric Not applicable to i (Primary Side) either Hatch unit l 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 I Vessel i 83.110 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 83.130 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 j (Primary Side) either Hatch unit 1
j B3.150 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Mot applicable to j (Primary Side) either Hatch unit
! B3.160 B-D Heat Exchangers Nozzle Inside Radius Section Volumetric Not applicable to j (Primary Side) either Hatch unit i
i B4.11 B-E Vessel Nozzles External Surfaces of Visual,VT-2 No Partial Penetration Welds t
84.12 B-E Control Rod Drive External Surfaces of Visual ,VT-2 No Nozzles Partial Penetration Welds I
- B4.13 B-E Instrumentation External Surfaces of Visual ,VT-2 No 1 Nozzles Partial Penetration Welds Bt.M B-E Pressurizer External Surfaces of Visual ,VT-'2 Not applicable to Heater Penetration Welds either Hatch unit
O O O TABLE 1 Sh. 4 of 11 ISI PROGRAM FOR ASME CLASS 1 CON ONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 i
Examination System or Com- Method of Code Relief
- Item No. Category ponent Description Area (s) To Be Examined Exaraination Requested 85.10 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface and Yes, 2.1.4; Welds (Nominal Pipe Size 141n.) Volumetric 2.1.5 B5.11 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface Yes, 2.1.6 i
Welds (Nominal Pipe Size <41n.) -
B5.12 B-F Reactor Pressure Vessel Nozzle-to-Safe End Surface Not applicable to Socket Welds either Hatch unit B5.20 B-F Pressurizer Nozzle-to-Safe End Butt Welds Surface and Not applicable to (Nominal Pipe Size 241n.) Volumetric either Hatch unit B5.21 B-F Pressurizer Nozzle-to-Safe End Butt Welds Surface Not applicable to ,
(Nominal Pipe Size <4f n. ) either Hatch unit B5.22 B-F Pressurizer Nozzle-to-Safe End Surface Not applicable to l Socket Welds either Hatch unit
. 85.30 B-F Steam Generators Nozzle-to-Safe End Butt Welds Surface and Not applicable to ,
(Primary Side) (Nominal Pipe Size 2 41n.) Volumetric either Hatch unit 85.31 B-F Steam Generators Nozzle-to-Safe End Butt Welds Surface Not applicable to (Primary Side) (Nominal Pipe Size < 4fn.) either Hatch unit j B5.32 B-F Steam Generators Nozzle-to-Safe End Surface Not applicable to
^
(Primary Side) Socket Welds either Hatch unit j B5.40 B-F Heat Exchangers Surface and Not applicable to (Primary Side) Nozzle-to-Safe (Nominal Pipe SizeEnd> Butt Welds Volumetric
___41n.) either Hatch unit B5.41 B-F Heat Exchangers Nozzle-to-Safe End Butt Welds Surface Not applicable to (Primary Side) (Nominal Pipe Size < 41n.) either Hatch unit
, B5.42 B-F Heat Exchangers Nozzle-to-Safe End Surface Not applicable to 4 (Primary Side) Socket Welds either Hatch unit B5.50 B-F Piping Dissimilar Butt Welds Surface and Yes, 2.1.4 and j (Nominal Pipe Size l 41n.) Volumetric 2.1.5
I O O O TABLE 1 Sh. 5 of 11 ISI PROGRAM FOR ASME CLASS 1 C0l90NENTS 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 B5.51 B-F Piping Dissimilar Butt Welds Surface Not applicabic to (Nominal Pipe Size << 4fn.) either Hatch unit B5.52 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 86.30 B-G-1 Reactor Pressure Vessel Closure Studs, when removed Surface and No, See Note 1 i Volumetric
'l B6.40 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
< either Hatch unit B6.70 B-G-1 Pressurizer Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit 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 either Hatch unit B6.100 B-G-1 Steam Generator Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit
,i US.110 B-G-1 Steam Generator Nuts, Bushings, and Visual, VT-1 Not applicable to j Washers either Hatch unit B6.120 B-G-1 Heat Exchangers Bolts and Studs Volumetric Not applicable to either Hatch unit
! O O O TABLE 1 Sh. 6 of 11 l ISI PROGRAM FOR ASME 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 l B6.130 B-G-1 Heat Exchangers Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit l B6.140 B-G-1 Heat Exchangers Nuts, Bushing, and Visual, VT-1 Not applicable to l Washers -
either Hatch unit
! B6.150 B-G-1 Piping Bolts and Studs Volumetric Not applicable to either Hatch unit
! 86.160 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 B6.100 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 l B6,210 B-G-1 Valves Bolts and Studs Volumetric Not applicable to I
either Hatch unit l B6.220 B-G-1 Valves Flange Surface, when Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit l
B6.230 B-G-1 Valves Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit 4 B7.10 B-G-2 Reactor Pressure Vessel Bolts, Studs, and Nuts Visual, VT-1 No B7.20 B-G-2 Pressurizer Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit I
O O O TABLE 1 Sh. 7 of 11 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief i Item Wo. 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 either Hatch unit
- B7.40 B-G-2 Heat Exchangers Bolts, Studs, and Nuts , Visual, VT-1 Not applicable to i
either Hatch unit B7.53 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 B8.10 B-H Reactor Pressure Vessel Integrally Wolded Volumetric or No 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 l Applicable 88.40 B-H Heat Exchangers Integrally Welded Volunetric or Not applicable to Attachments Surface, as either Hatch unit Applicable B9.11 B-J Piping Circumferential Welds Surface and Yes, 2.1.4; 2.1.5; (Nominal Pipe Size >_4 in.) Volumetric and 2.1.7
O -
O O TABLE 1 Sh. 8 of 11 ISI PROGRAM FOR ASME CLASS 1 CON ONENTS 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 Examina tion Requested 89.12 B-J Piping Longitudinal Welds Surface and Yes, 2.1.4 and (NominalPipeSize]h4in.) Volumetric 2.1.5 B9.21 B-J Piping Circumferential Welds Surface No (Nominal Pipe Size << 4 in.)
- B9.22 B-J Piping Longitudinal Welds Surface No (Nominal Pipe Size <( 4 in.)
l 89.31 B-J Piping Branch Pipe Connection Welds Surface and Yes, 2.1.4 and (Nominal Pipe Sizejl 4 in.) Volumetric 2.1.5 89.32 B-J Piping Branch Pipe Connection Welds Surface No (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 810.20 B-K-1 Pumps Integrally Welded Volumetric or No Attachments Surface, as Applicable
- B10.30 B-K-1 Valves Integrally Welded Volumetric or No Attachments Surface, as Applicable i
B12.10 B-L-1 Pumps Pump Casing Welds Volumetric Not applicable to
, either Hatch unit B12.20 B-L-2 Pumps Pump Casing Visual, VT-3 Yes, 2.1.8 B12.30 B-M-1 Valves Valve Body Welds Surface Not applicable to
, (Nominal Pipe Size <C 4 in.) either Hatch unit
O O O TABLE 1 Sh. 9 of 11
- ISI PROGRAM FOR ASME CLASS 1 CONONENTS i EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method cf Code Relief Item No. Category ponent Description Area (s) To Be Examined Examination Requested B12.31 B-M-1 Valves Valve Body Welds Volumetric Not applicable to (Nominal Pipe Size 1 4 in.) either Hatch unit
] B12.40 B-M-2 Valves Valve Body Visual, VT-3 Yes, 2.1.8 (Nominal Pipe Size > 4 in.)
B13.10 B-N-1 Reactor Pressure Vessel Vessel Interior Visual, VT-3 No 1
B13.20 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-1 No (PWR)
B13.21 B-N-2 Reactor Pressure Vessel Core Support Structure Visual, VT-1 No (BWR)
B13.30 B-N-3 Reactor Pressure Vessel Core Support Structure Visual, VT-3 Not applicable to (BWR) either Hatch unit B14.10 B-0 Reactor Pressure Vessel Welds in Control Rod Volumetric or Tes, 2.1.4, 2.1.5, Drive Housing Surface and 2.1.9 B15.10 B-P Reactor Pressure Vessel Pressure Retaining Boundary System Leakage No Test; Visual ,
VT-2 1
B15.11 B-P Reactor Pressure Vessel Pressure Retaining Boundary System Hydro- No test; Visual, i
i VT-2 4
l 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 l VT-2 i
O O O TABLE 1 Sh.10 of 11 ISI PROGRAM FOR ASME CLASS 1 COW ONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com-Item No. Category Method of Code Relief 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 Hydro- Not applicable to test; Visual, either Hatch unit VT-2 B15.40 B-P Heat Exchangers Pressure Retaining Boundary System Leak- Not applicable to age Test; eitier 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; Visual, VT-2 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 l age Test; Visual, VT-2
O O o TABLE 1 Sh.11 of 11 ISI PROGRAM FOR ASME CLASS 1 C0990NENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 System or Com- Method of Code Relief Examination Requested Category ponent Description Area (s) To Be Examined Examination Item No.
Valves Pressure Retain 11g Boundary System Hydro- No B15.71 B-P test; Visual,
/T-2 Steam Generator Tubing Straight Tube Design Volumetric Not applicable to B16.10 B-Q either Hatch unit I Steam Generator Tubing U-Tube Design Volumetric = Not applicable to B16.20 B-Q either Hatch unit Head Thickness Ultrasonic No, Ses Note 3 Reactor Pressure ,
Vessel Closure Head Measurements
< s
- i #
l l
5 l
i l
l l
Notes for Table 1 -
1 (1) During each refueling outage, the reactor pressure vessel (RPV) closure
.O studs are normally left in place; therefore, only a volumetric examination will be performed (Table IWB-2500-1, Item No. B6.20). If the studs are
' removed, both a surface and volumetric examination will be performed (Table IWB-2500-1, Item No. B6.30).
(2) The Class 1 socket welds (Item No. B9.40 of Table IWB-2500-1) for both units are exempted from surface examination by paragraph IWB-1220(a).
However, selected austenitic piping welds may be examined by PT techniques.
(3) Ultrasonic thickness mea:;urements have been performed each refueling
~
outage on the RPV closure head at both units (Hatch 1-six outages and Hatch 2-three outages) to .detennine if thinning has occurred. These measurements have found no apparent thinning and therefore, these examinations will be performed once every 40-months at each unit.
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- - -. . . - - . . _ . - - . = _-
N 3.0 INSERVICE INSPECTION FO'R CLASS 2 COMPONENTS 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 O ASE Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1980. 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. Where relief from the inspection requirements of Subsection IWC is requested, information is i 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 ranner that will satisfy the requirements of IWA-5000 and 110-5000. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and eacn section tested at its specified pressure. Where it is not practicable to separate adjoining sections of piping (e.g., boundary is a check valve), the sections will be tested together at the leer of the specified test pressures. No point in the piping will be permitted to experience a pressure greater than the specified test pressure.
Componer:ts exempted from volumetric and surface examination by IWC-1220 will be hydrostatically tested per the requirements of IWA-5000 and IWC-5000.
3.1 Requests for Relief From ASME Section XI Requirements O 3.i.i volumetric Examination of Pressure Retaining Weids in Ciais 2 vesseis 3.1.1.1 Requirement From Which Relief is Requested Item Nos. C1.10, C1.20, and C1.30 of Table IWC-2500-1 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 Figures IWC-2500-1 and -2. Relief from this requirement is requested.
3.1.1.2 Justification 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 the configuration.
3.1.1.3 Testing in Liry 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 O i properly proared 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 will be perfonned on these welds.
j 3.1.2 Basic Calibration Blocks for Pipe Wald Examinations 3.1.2.1 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
^
j 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.
3.1. 2. 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 Section V. For the two primary reasons listed below, these same basic calibration blocks will be used to provide the most meaningful and thorough examinations possible:
- 1. Side drilled holes as calibration reflectors result in a more sensitive ultrasonic examination than one using notches.
4
- 2. Correlation of ultrasonic data with previous examinations as required by Subarticle IWA-1400 of Section XI makes it necessary that these i basic calibration blocks be used so future examination results can be correlated with past results.
3.1.2.3 Testing in Lieu of Section XI Requirements O The basic caiibratioa biocks usias hoies as caii8 ration refiectors wiii be used for the majority of the pipe weld examinations.
- 3.1.3 Surface Examination of Pressure Retaining Welds in Class 2 Pumps l 3.1. 3.1 Requirement From Which Relief is Requested I
- Item No. C6.10 of Table IWC-2500-1 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 .
l 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 reliability.
l 3.1. 3. 3 Testing in Lieu of Section XI Requirements l
Class 2 pump casing welds are subject to surface examination when disassembled for maintenance. The coverage provided by examinations during routine maintenance coupled with hydrostatic tests will provide adequate assurance of l the structural integrity of these pumps, while keeping exposure to radiation and contamination as low as reasonably achievable.
(
. _ - - . ,.. _ _ _ _- - _ .- - _ - _ - _ _- _ _ _ .- - .-.. _ .-.~. --_ . .,_
3 O O O I
TABLE 2 Sh. 1 of 3 ISI PROGRAM FOR ASME CLASS 2 CO@ ONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 l' Examination System or Com- Method of Item No. Category ponent Description code Relief Area (s) To Be Examined Examination Requested C1.10 C-A Pressure Vessels Shell Circumferential Welds Volumetric Yes, 3.1.1 t
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
- C2.10 C-8 Pressure Vessels Nozzles in Vessels 11/2 inch Surface Not applicable to
- Nominal Thickness either Hatch unit I
C2.21 C-B Pressure Vessels Nozzle-to-Shell (or Surface and No Head) Weld for Vessels Volumetric
! >1/2 Inch Nominal Thickness C2.22 C-B Pressure Vessels Nozzle'Inside Radius Section Volumetric No
- i. for Vessels >1/2-Inch Nominal Thickness C3.10 C-C Pressure Vessels Integrally Welded Attachments Surface No j C3.40 C-C Piping Integrally Welded Attachments Surface No C3.70 C-C Pumps Integrally Welded Attachments Surface Not applicable to q either Hatch unit C3.100 C-C Valves Integrally Welded Attachments Surface Not applicable to
] either Hatch unit I
C4.10 C-F Pressure Vessels Bolts and Studs Volumetric Not applicable to either Hatch unit i C4.20 C-F Piping Bolts and Studs Volumetric Not applicable to i
either Hatch unit I
i 1
O O O l TABLE 2 Sh. 2 of 3 l ISI PROGRAM FOR ASME CLASS 2 COW ONENTS 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 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 Hatch unit C5.11 C-F Piping Circumferential Welds Surface No i (Nominal Wall Thicknessil/2 in.)
l C5.12 C-F Piping Longitudinal Welds Surface No 1
(Nominal Wall Thicknessil/2 in.)
C5.21 C-F Piping Circumferential Welds Surface and Yes, 3.1.2 (Nominal Wall Thickness >1/2 in.) Volumetric
- C5.22 C-F Piping Longitudinal Welds Surface and Yes, 3.1.2 (Nominal Wall Thickness >1/2 in.) Volumetric C5.31 C-F Piping Circumferential Welds Surface No Pipe Branch Connections C5.32 C-F Piping Longitudinal Welds Surface Not applicable to Pipe Branch Connections either Hatch unit 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 i
C7.10 C-H Pressure Vessels Pressure Retaining Components System Pres- No
- sure Test; i Visual, VT-2 C7.11 C-H Pressure Vessels Pressure Retaining Components System Hydro- No i static Test; Visual, VT-2 i
O O O TABLE 2 Sh. 3 of 3 ISI PROGRAM FOR ASME CLASS 2 C0tPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Item No. Category Code Relief ponent Description Area (s) To Be Examined Examination _ Requested 4
i C7.20 C-H Piping Pressure Retaining Components System Pres- No sure Test;
-Visual, VT-2 C7.21 C-H Piping Pressure Retaining Components System Hydro- No i
static Test; Visual, VT-2 C7.30 C-H Pumps Pressure Retaining Components System Pres- No
- sure Test; Visual, VT-2 C7.31 C-H Pumps Pressure Retaining Components System Hydro- No i
static test; i
Visual, VT-2 C7.40 C-H Valves Pressure Retaining Components System Pres- No
- sure Test; i
Visual, VT-2 i C7.41 C-H Valves Pressure Retaining Components System Hydro- No static Test; Visual, VT-2 l
1 l
l 4
4.0 INSERVICE INSPECTION FOR CLASS 3 COMPONENTS Table IWD-2500-1 provides a tabulation of the Class 3 pressure-retaining j
O components subject to the inspection requirements of Subsection IWD of Section '
O XI of the AS!E Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1980. 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. Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of piping (e.g., boundary is a check valve), the sections will be tested together at the lower of the specified pressures. No point in the piping will be pressurized above the specified test pressure.
4.1 Requests for Relief From ASi1E 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 requires a system pressure test for Class 3 lines regardless of size.
4.1.1.2 Justification 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 requires for retaining internal pressure. Using heavier walled piping in these small lines essentially means they are over-designed for the pressure they are retaining and are not susceptible to the type leakages found during hydrostatic testing.
4.1.1. 3 Testing in Lieu of Section XI Requirements Accessible piping two inches and smaller will be visually examined under normal operating pressure.
4.1. 2 System Pressure Tests on Class 3 Buried Piping 4.1. 2.1 Requirement From Which Relief is Requested Table IWD-2500-1 requires a system pressure test for Class 3 components including buried piping.
O
4.1.2.2 Justification O The service eter systems were desisned without inciudins provisions for testing buried piping as required by Paragraph IWA-5244.
In addition, the 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.
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1 .. . . - . . ._.--_._--__ --- . . _ . _ _ . _ _ _ _ _ _ _ - ~ . . _ _ _ _ - - _ _ . - _ - . - _ _ _ _ _ - _ _ _ _ _ _ . _ _ _ _ _ , . . _ _ . - _ . _
5.0 INSERVICE INSPECTION FOR CLASS 1, 2, AND 3 C0f90HENT SUPPORTS Table 3 provides a tabulation of the Class 1, 2, and 3 component supports
' subject to the inspection requirements of Subsection IF of Section XI of the Q ASE Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1980. These components will be inspected in accordance with the requirements of Subsection IW 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 IW 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.
Tabic IF-2500-2 items not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.
Paragraph IF-1230 titled Supports Exempt from Examination and Test is in the course of preparation. Later Addenda and the 1983 Edition of Section XI do not provide guidance for the exemption critoria 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, respectively.
Article IW-5000 outlines the inservice test requirements for hydraulic and mechanical snubbers. However, snubbers on Class 1, 2, and 3 systems are currently subject to an ongoing testing program per the plant technical specifications. This program is designed to demonstrate the functional integrity of the snubbers and exceeds the requirements of Article IW-5000.
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1
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O O TABLE 3 Sh.1 of 2
- ISI PROGRAM FOR ASME CLASS 1, 2. AND 3 SUPPORT C0t@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 F-1 F-A Component Supports Mechanical Attachments, Visual, VT-3 No Including Bolting F-1 F-B Component Supports Mechanical Attachments, Visual, VT-3 No Including Bolting F-1 F-C. Component Supports Mechanical Attachments, Visual, VT-3 No Including Bolting F-2 F-A Component Supports Welded Attachments Visual, VT-3 No F-2 F-B Component Supports Welded Attachments Visual, VT-3 No
- F-2 F-C Component Supports Welded Attachments Visual, VT-3 No l F-3 F-A Component Supports Component Displacement; Visual, VT-3 No Settings of Guides and Stops; Misalignment of 4
Supports; and Assembly of Support Items f F-3 F-B Component Supports Component Displacement; Visual, VT-3 No Settings of Guides and j Stops; Misalignment of Supports; and Assembly of Support Items F-3 F-C Component Supports Component Displacement; Visual, VT-3 No i Settings of Guides and Stops; Misalignment of Supports; and Assembly of Support Items
i O O O TABLF 3 Sh. 2 of 2 ISI PROGRAM FOR ASME CLASS 1, 2, AND 3 SUPPORT COWONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Com- Method of Code Relief j Item No. Category ponent Description Area (s) To Be Examined Examination Requested F-4 F-C Component Supports Spring Type Supports; Visual,.VT-4 No Constant Load Type Supports; Shock Absorbers; ,
Hydraulic and Mechanical j Type Snubbers 4
e j
i, 1
i -
)
i I
6.0 INSERVICE INSPECTION OF VALVES The valve testing program is based on the 1980 Edition of Section XI with Addenda through. Winter 1980. Valves 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 (CIVs)
Containment Isolation Valves 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 Valve Test Plans stored in the Plant Hatch Document Control room.
Pressure Isolation Valves Pressure Isolation valves, as a rule, will be tested in the same manner as the CIVs and the observed leakage escalated per IWV-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, or a correlation between air and water leakage will be derived and
- submitted to the NRC for review.
Valves to be Tested During Cold Shutdown and Refueling O . vaive testing wiii co ence as soon as possibie into the coid 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 IWV-3415 ,
Therefore, additional testing to prove the fail-safe capability will not be performed.
Control Rod Drive System Valves See Relief Request 6.1.22
Valves Testing During Cold Shutdown See Relief Requests 6.1.9 and 6.1.19 O 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.
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Plant Hatch - Unit i Valve Testing Program Sh. 1 of 34 SYSTEM: Main Steam A Fee k ter 2
Stroke Norm Time Relief Valva Code Function Pos Exercise Leakage Req'd Request [
No. Class Cat Description Coord. PAID I '
^
FW Inbrd. Cont.lso. O R0 CIV No 6.1.1 -
B21-F010A 1 AC 18" Check 3-E H-16062 FW Inbrd. Cont. Iso. R0 CIV No 6.1.1 [.
, 821-F0108 1 AC 18" Check 3-D H-16062 O f, Note 3 NA No C 6" Relief C-6 H-16062 Main Steam Relief -
i 821-F013A 1 Note 3 NA No C 6" Relief C-6 H-16062 Main Steam Relief -
B21-F0138 1 i B21-F013C 1 C 6" Relief F-6 H-16062 N in Steam Relief - Note 3 NA No
{
Note 3 NA No B21-F013D 1 C 6" Relief F-6 H-16062 Main Steam Relief -
Note 3 NA No B21-F013E 1 C 6" Relief F-6 H-16062 Main Steam Reifef -
Note 3 NA No
. 821-F013F 1 C 6" Relief F-6 H-16062 Main Steam Reifef -
e i No 6" Relief F-6 H-16062 Main Steam Relief - Note 3 NA ,
B21-F013G 1 C j
Note 3 NA No i
i B21-F013H 1 C 6" Relief G-6 H-16062 Main Steam Relief -
I No H-16062 Main Steam Relief - Note 3 NA B21-F013J l C 6" Relief G-6 '
4 Note 3 NA No B21-F013K 1 C 6" Relief F-6 H-16062 Main Steam Relief -
Note 3 NA No
! B21-F013L 1 C 6" Relief F-6 H-16062 Mai.' Steam Relief -
j Main Steam Line C Note 1 CIV No 6.1.2 j B21-F016 1 A 3" M0 Gate E-8 H-16062
' DRfl. Inb. Iso.
) Main Steam Line C Note 1 CIV No B21-F019 1 A 3" M0 Gate E-9 H-16062 l DRN Inb. Iso.
0 Qtr. CIV Yes A 24" A0 Globe C-7 H-16062 MSIV
, B21-F022A 1 MSIV 0 Qtr. CIV Yes B21-F022B 1 A 24" A0 Globe E-7 H-16062 0 Qtr. CIV Yes A 24" A0 Globe F-7 H-16062 MSIV B21-F022C 1 4
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SYSTEM: Main Steam & Feedwater Plant Hatch - Unit i Valve Testing Program Sh. 2 of 34 Valve Code Stroke No. Class Cat Description Norm Coord. P&ID Function Pos Time Relief Exercise Leakage Req'd Request B21-F022D 1 A 24" A0 Globe G-7 H-16062 MSIY 0 Qtr. CIV Yes 821-F028A 1 A 24" A0 Globe C-9 H-16062 MSIV 0 Qtr. CIV Yes B21-F028B 1 A 24" A0 Globe E-9 H-16062 MSIV O Qtr. CIV Yes j B21-F028C A 1 24" A0 Globe F-9 H-16062 HSIV 0 Otr. CIV Yes i B21-F028D 1 A 24" A0 Globe G-9 H-16062 MSIV 0 Qtr. CIV Yes
! B21-F032A 1 AC 18" Check E-2 H-16062 Fli Outboard Iso O R0 CIV No 6.1.1 821-F0328 1 AC 18" Check D-2 H-16062 FW Outboard Iso O R0 CIV No 6.1.1 821-F037A 3 C 6" Check H-6 H-16062 Vac. 3reaker C See 6.1.3 HA Ho 6.1.3 I1SRV Disch.
4 B21-F037B 3 C 6" Check H-6 H-16062 Vac. Breater C See 6.1.3 NA No 6.1.3 MSRV Disch.
B21-F037C 3 C 6" Check H-6 H-16D62 Vac. Breaker C See 6.1.3 MSRV Disch.
NA No 6.1.3 B21-F037D 3 C 6" Check H-6 H-16062 Vac. Breaker C See 6.1.3 MSRV Disch.
NA No 6.1.3
! B21-F037E 3 C 6" Check H-6
' H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 itSRV Disch.
B21-F037F 3 C 6" Check H-6
- H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
B21-F037G 3 C 6" Check H-6 H-16062 Vac. Breaker C See 6.1.3 MSRV Disch.
NA No 6.1.3 I
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l SYSTEM: Main Steam & Feedwater Plant Hatch - Unit i Valve Testing Program Sh. 3 of 34 l t
- Stroke i
! Valvt Code Norm Time Relief ' I
- N 3. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request ,
i
} B21-F037H 3 C 6" Check H-6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 I' i MSRV Disch.
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B21-F037J 3 C 6" Check 11- 6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 ['
] MSRV Disch.
- t B21-F037K 3 C 6" Check H-6 H-16062 Vac. Breaker C See 6.1.3 NA No 6.1.3 '
MSRY Disch.
B21-F037L 3 C 6" Check H-6 H-16062 Vac Breaker C See 6.1.3 NA Ho 6.1.3 e MSRV Disch.
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i SYSTEM: Reactor Recirculation System Plant Hatch - Unit i Valve Testing Program Sh. 4 of 34 '
r Stroke Valva Code Norm Time Relief !-
No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request ,
B31-F013B 1 AC 3/4" Check F-3 H-16066 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 f
B31-F017A 1 AC 3/4" Check F-2 H-16066 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 f B31-F0178 1 AC 3/4" Check F-2 H-16066 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 B31-F019 1 A 3/4" A0 Globe D-3 H-16066 Reac. Sample Sys. O Qtr CIV Yes I
< Inbrd. Iso B31-F020 1 A 3/4" A0 Globe D-1 H-16066 Reac Sample Sys. O Qtr CIV Yes Inbrd. Iso B31 -F031 A 1 B 28" M0 Gate G-7 H-16066 Reactor Recirculation 0 CS NA Yes 6.1.4 B31-F031B 1 B 28" M0 Gate H-7 H-16066 Reactor Recirculation 0 CS NA Yes 6.1.4 a
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O O . O SYSTEM: Standby Liquid Control System Plant Hatch - Unit 1 Valve Test Program Sh. 5 of 34 Stroke Valve Code No. Class Cat Description More Time Relief
, Coord. PSID Function Pos Exercise Leakage Req'd Request I
C41-F004A 2 D l-1/2" Expl D-3 H-16061 SLC Explo Act C Note 4 NA No C41-F004B 2 0 1-1/2" Expl F-3 H-16061 SLC Explo Act C Note 4 NA No
! C41-F006 1 AC 1-1/2" Check E-2 H-16061 SLC Outbrd 18 mos.
C CIV No 6.1.5 Cont. Iso C41-F007 1 AC 1-1/2" Check E-2 H-16061 SLC Outbrd C 18 mos. CIV No Cont. Iso
' C41-F029A 2 C 1" Relief D-6 H-16061 SLC Pump Disch. C Note 3 NA No Relief C41-F0298 2 C 1" Relief G-6 H-16061 SLC Pump Disch. C Note 3 NA No t
Relief C41-F033A 2 C 1-1/2" Check E-5 H-16061 SLC Pump Disch. C Qtr. NA No C41-F033B 2 C 1-1/2 Check G-5 H-16061 SLC Pump Disch. C Qtr. NA No 1
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i O O O i SYSTEM: Residual Heat Removal Plant Hatch - Unit 1 Valve Test Program Sh. 6 of 34 i -
Stroke l Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request
, Ell-F003A 2 8 16" M0 Gate Viv D-9 H-16330 RHR Hx Shell 0 Qtr NA Yes Side Outlet i
Ell 4003B 2 B 16" M0 Gate Viv D-4 H-16329 ' RHR Hx Shell 0 Qtr' NA Yes
- Side Outlet
) Ell-F004A 2 A 24" M0 Gate Viv F-10 H-16330 RHR Pump Suction 0 Qtr CIV Yes Torus Iso 1
j E11-F0048 2 A 24" M0 Gate Viv F-3 H-16329 RHR Pump Suction 0 Qtr CIV Yes Torus Iso
, Ell-F004C 2 A 24" M0 Gate Viv F-10 H-16330 RHR Pump Suction 0 Qtr CIV Yes Torus Iso I
Ell-F0040 2 A 2A" N0 Gate Viv F-3 H-16329 RHR Pump Suction 0 Qtr CIV Yes Torus Iso l Ell-F006A 2 B 20" H0 Gate Viv F-10 H-16330 RHR Shutdown C Qtr NA Yes
! Cooling Sys
}
. E11-F006B 2 B 20" M0 Gate Viv F-2 H-16329 RHR Shutdown C Qtr NA Yes
] Cooling Sys '
! Ell-F006C 2 8 20" M0 Gate Viv F.10 H-16330 RHR Shutdown C Qtr NA Yes j Cooling Sys
- Ell-F006D 2 B 20" M0 Gate Viv F-2 H-16329 RHR Shutdown C Qtr NA Yes j
Cooling Sys l Ell-F007A 2 A 4" N0 Gate Viv E-7 H-16330 RilR Pump Min Flow 0 Qtr CIV Yes 6.1.2 l
Torus Iso t Ell-F007B 2 A 4" M0 Gate VId D-5 H-16329 RHR Pump Min Flow 0 Qtr CIV Yes 6.1.2 i
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SYSTEM: Residual Heat Removal Plant Hatch - Unit i Valve Test Program Sh. 7 of 34 ;
Stroke i Valve Code Norm Time Relief !
N o. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request E11-F008 1 A 20" l10 Gate D-1 H-16329 RHR Shutdown C Note 1 PIY No )
Cooling Outbrd Iso E11-F009 1 A 20" M0 Gate D-1 H-16329 RHR Shutdown C Note 1 PIV No e
Cooling Outbrd Iso E11-F011 A 2 A 4" M0 Gate D-3 H-16330 RHR Cond. Disch. C Qtr CIV Yes 6.1.2 '
to Torus j E11-F011B 2 A 4" M0 Gate C-9 H-16329 RHR Cond. Disch. C Qtr CIV Yes 6.1.2 to Torus 1
E11-F015A 1 A 24" M0 Gate C-8 H-16330 LPCI Outbrd, C Qtr PIV Yes i Cont. Iso Ell-F0158 1 A 24" M0 Gate C-4 H-16329 LPCI Outbrd, C Qtr PIV Yes '
Cont. Iso Ell-F016A 2 A 16" H0 Gate B-9 H-16330 Cont. Spray C Qtr CIV Yes
. Outbrd. Iso E11-F0168 2 A 16" M0 Gate B-4 H-16329 Cont. Spray C Qtr CIV Yes Outbrd. Iso E11-F017A 1 B 24" M0 Gate D-8 H-16330 LPCI O Qtr NA Yes Ell-F0178 1 B 24" M0 Gate D-5 H-16329 LPCI O Qtr NA Yes
{
E11-F019 1 C 4" Check A-1 H-16329 Head Spray C Wote 2 NA No
]
E11-F021A 2 B 16" M0 Gate B-11 H-16330 Containment Spray C Qtr NA Yes
- E11-F0218 2 B 16" M0 Gate B-2 H-16329 Containment Sprcy C Qte NA Yes 4
Ell-F022 1 A 4" H0 Gate A-1 H-16329 Head Spray C Note 1 CIV No -
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l O O O SYSTEM: Residual Heat Removal Plant Hatch - Unit i Valve Test Program Sh. B of 34 Valve Code Stroke Norm No. Class Cat Description Coord. PAID Function Time Relief Pos Exercise Leakage Reg'd Request E11-F023 1 A 4" M0 Globe A-2
' H-16329 Head Spray Outbrd. C Note 1 CIV No Iso E11-F024A 2 B 16" M0 Globe C-7 H-16330 Suppression Pool C Qtr NA Yes Cooling Ell-F0248 2 B 16" M0 Globe C-6 H-16329 Suppression Pool C Qtr NA Yes Cooling E11-F025A 1 AC 1" Relief B-8 H-16330 LPCI Inj. C Note 3 CIV No Cont. Iso E11-F0258 2 AC 1" Relief C-5 H-16329 LPCI Inj. C Note 3 CIV No Cont. Iso Ell-F026A 2 A 4" H0 Gate D-3 H-16330 Cond. Disch. to C Qtr CIV Yes RCIC Cont. Iso E11-F0268 2 A 4" M0 Gate D-Il H-16329 Cond. Disch. to C Qtr CIV Yes RCIC Cont. Iso E11-F027A 2 8 6" M0 Gate D-3 H-16330 Suppression Pool C Qtr HA Yes Spray Ell-F027B 2 8 6" M0 Gate D-ll H-16329 Suppression Pool C Qtr NA Yes Spray Ell-F028A 2 A 16" M0 Gate B-8 H-16330 Suppression Pool C Qtr CIV Yes Spray Outbrd. Iso E11-F0288 2 A 16" M0 Gate B-5 H-16329 Suppression Pool C Qtr CIV Yes Spray Outbrd. Iso Ell-F029 2 AC 1" Relief E-2 H-16329 RHR Pump Suction C Note 3 CIV No Cont. Iso
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7 O O' O SYSTEM: Residual Heat Removal Plant Hatch - Unit i Valve Test Program Sh. 9 of 34 Valve Code Stroke No. Class Cat Description Norm Coord. P&ID Function Pos Time Relief Exercise Leakage Req'd Request E11-F030A 2 AC 1" Relief F-9 H-16330 RHR Pump Suction C Note 3 CIV No i Cont. Iso E11-F0308 2 AC 1" Relief F-4 H-16329 RHR Pump Suction C Note 3 CIV No Cont. 150 E11-F030C 2 AC 1" Relief F-11 H-16330 RHR Pump Suction C Note 3 CIV No Cont. Iso Ell-F0300 2 AC 1" Relief F-1 H-16329 RHR Pump Suction C Note 3 CIV No Cont. Iso E11-F031A 2 C 20" Check H-6 H-16330 RHR Pump Discharge C Note 5 NA No E11-F0318 2 C 20" Check H-6 H-16329 RHR Pump Discharge C Note 5 NA No E11-F031C 2 C 20" Check H-10 H-16330 RHR Pump Discharge C Note 5 NA No E11-F0310 2 C 20" Check H-2 H-16329 RHR Pump Discharge C Note 5 NA No E11-F046A 2 C 3" Check H-7 H-16330 RHR Minimun Flow Line C Note 5 NA No E11-F046B 2 C 3" Check H-5 H-16329 RHR Hinimum Flow Line C Note 5 NA No E11-F046C 2 C 3" Check H-11 H-16330 RHR Minimum Flow Line C Note 5 NA No E11-F046D 2 C 3" Check H-2 H-16329 RHR fiinimum Flow Line C Note 5 NA No E11-F047A 2 B 16" M0 Gate E-6 H-16330 RHR Hx Shell Side 0 4 Qtr NA Yes Side Inlet E11-F047B 2 B 16" M0 Gate E-7 H-16329 RHR Hx Shell Side 0
- Qtr NA Yes Side Inlet E11-F043A 2 8 24" M0 Globe B-8 H-16330 RHR Hx Shell Side 0 Qtr NA Yes Bypass a
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> SYSTEM: Residual Heat Removal Plant Hatch - Unit i Valve Test Program Sh.10 of 34 4
- Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage P,eq'd Request i
Ell-F0488 2 B 24" M0 Globe B-5 H-16329 RHR Hx Shell Side 0 Qtr NA Yes Bypass Ell-F050A 1 AC 24" A0 Check D-6 H-16330 LPCI Injec. Iso C See 6.1.7 PIV ho 6.1.7 i E11-F0508 1 AC 24" A0 Check D-7 H-16329 LPCI Injec. Iso C See 6.1.7 PIV No 6.1.7 i
i E11-F055A 2 AC 4" Relief D-6 H-16330 RHR Hx Shell C Note 3 CIV No l
Relief Cont. Iso k Ell-F055B 2 AC 4" Relief D-7 H-16329 RHR Hx Shell C Note 3 CIV No
, Relief Cont. Iso Ell-F065A 2 B 24" A0 Bfly E-10 H-16330 RHR Torus Suction 0 Qtr NA Yes Ell-F065B 2 B 24" A0 8 fly E-2 H-16329 RHR Torus Suction 0 Qtr NA Yes Ell-FOS 5C 2 B 24" A0 Bfly E-10 H-16330 RHR Torus Suction 0 Qtr NA Yes Ell-F065D 2 B 24" A0 Bfly E-2 H-16329 RHR Torus Suction 0 Qtr NA Yes Ell-F078A 2 C 10" Check H-6 H-16330 RHR Hx Ser Wtr Tie C R0 NA No 6.1.8
. Ell-F0788 2 C 10" Check D-9 H-16329 RHR Hx Ser Wtr Tie C R0 NA No 6.1.8 Ell-F091A 2 B 6" M0 Globe E-2 H-16330 Steam Line to RHR C Qtr NA Yes Hx Shutdwn
, Ell-F0918 2 B 6" M0 Globe E-11 H-16329 Steam Line to RHR C Qtr NA Yes j Hx Shutdwn
- Ell-F097 2 AC 3" Relief D-Il H-16329 Steam Line Relief C Note 3 CIV No Cont. Iso Ell-F103A 2 A 1" M0 Globe E-5 H-16330 RHR Hx Vent C Qtr CIV Yes l Cont Iso i
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O O SYSTEM: Residual Heat Removal Plant Hatch - Unit i Valve Test Program Sh. 11 of 34 Yalve Code Stroke Norm Time Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Reg'd Request E11-F103B 2 A 1" M0 Globe E-8 H-16329 RHR Hx Vent C Qtr CIV Yes Cont Iso Ell-F140A 2 B 6" H0 Gate E-2 H-16330 Steam Line to RHR C Qte NA Yes Hx Shutdown E11-F140B 2 B 6" H0 Gate E-11 H-16329 Steam Line to RHR C Qtr NA Yes Hx Shutdown E11-F06BA 3 B 10" M0 Ball H-6 H-16330 RHR Hx Ser. Wtr C Note 6 NA No Disch.
E11-F0688 3 B 10" H0 Ball H-7 H-16329 RHR Hx Ser. Wtr C Note 6 NA No Disch.
E11-F073A 2 B 10" M0 Gate G-4 H-16330 RHR Ser. Wtr Intertie C Qtr NA Yes Ell-F073B 2 B 10" M0 Gate G-9 H-16329 RHR Ser. Wtr Intertie C Qtr NA Yes I E11-F075A 2 B 10" H0 Gate G-4 H-16330 RHR Ser. Wtr Intertie C Qtr NA Yes E11-F075B 2 B 10" H0 Gate G-9 H-16329 RHR Ser. Wtr Intertie C Qtr NA Yes E11-Fil9A 3 B 18" H0 Gate H-4 H-16330 RHR Ser. Wtr Train C Qtr NA Yes A & B Cross J
Ell-F1198 3 B IB" M0 Gate H-9 H-16329 RHR Ser. Wtr Train C Qtr NA Yes A & B Cross Ell-F200A 3 8 2" A0 PCY -
D-11004 RHR Ser. Wtr. Pump C Note 9 NA No Flow Ell-F2008 3 B 2" A0 PCV -
D-11004 RHR Ser. Wtr. Pump C Note 9 NA No Flow Ell-F200C 3 8 2" A0 PCV -
D-17004 RHR Ser. Wtr. Pump C Note 9 NA No Flow ,
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! O O O SYSTEM: Residual Heat Removal Plant Hatch - Unit 1 Valve Test Program Sh.12 of 34 j
Valve Code Stroke Norm Time Relief
$ No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request
! E11-F200D 3 8 2" A0 PCY -
D-11004 RHR Ser. Wtr. Pump C Note 9 '
NA No j Flow E11-LOO 1A 3 B 1/2" Solenoid -
D-11004 RHR Ser. Wtr Pump C Note 7 NA No Cooling
) E11 -L001B 3 8 1/2" Solenoid -
D-11004 RHR Ser. Wtr Pump C Note 7 NA No Cooling l E11-LOO 1C 3 B 1/2" Solenoid -
D-11004 RhR Ser. Wtr Pump C Note 7 NA No 4
Cooling E11-LOO 10 3 8 1/2" Solenoid -
D-11004 RHR Ser. Wtr Pump C Note 7 NA No i Cooling l
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O O O SYSTEM: Core Spray System Plant Hatch - Unit i Valve Test Program Sh. 13 of 34 Valve Code Stroke Norm Time Relief No. Class Cat Description Coord. Pa!D Function Pos Exercise Leakage Req'd Request E21-F001A 2 A 20" M0 Gate H-8 H-16331 CS Pump Suction Out 0 Qtr CIV Yes E21-F0018 2 A 20" M0 Gate J-8 H-16331 CS Pump Suction Out 0 Qtr CIV Yes
! E21-F003A 2 C 12" Check F-9 H-16331 CS Pump Discharge C Note 5 NA No 4
E21-F00?B 2 C 12" Check F-11 H-16331 CS Pump Discharge C Note 5 NA No l E21-F004A 1 8 10" M0 Gate E-7 H-16331 CS Outbrd. Injection 0 i
Qtr NA Yes E21 F004B 1 8 10" M0 Gate B-7 H-16331 CS Outbrd. Injection 0 Qtr NA Yes E21-F005A 1 A 10" M0 Gate E-6 H-16331 CS Outbrd. Cont. Iso C Qtr PIV Yes l E21-F005B 1 A 10" M0 Gate B-6 H-16331 CS Outbrd. Cont. Iso C Qtr PIV Yes E21-F006A 1 A:: 10" A0 Check D-4 H-16331 CS Pressure Iso C See 6.1.7 PIV No 6.1.7 E21-F006B 1 AC 10" A0 Check C-4 H-16331 CS Pressure Iso C See 6.1.7 P!V No 6.1.7 i
< E21-F012A 2 C , 2" Relief D-9 H-16331 CS Pump Disch. Relief C
' Note 3 NA No E21-F0128 2 C 2" Relief B-9 H-16331 CS Pump Disch. Relief C Note 3 NA No
! E21-F015A 2 A 10" M0 Globe D-8 H-16331 Core Spray Test C Qtr CIV Yes Bypass Cont. Iso E21-F015B 2 A 10" M0 Globe C-8 H-16331 Core Spray Test C Qtr CIV Yes l Bypass Cont. Iso
! E21-F019A 2 8 20" A0 Bfly J-6 H-16331 Core Spray Pump 0 Qtr NA Yes Torus Suc.
5 i E21-F01S3 2 B 20" A0 Bfly K-6 H-16331 Core Spray Pump 0 Qtr NA j Yes Torus Suc.
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{ SYSTEM: Core Spray System Plant Hatch - Unit i Valve Test Program Sh.14 of 34 Valve Code Stroke
! Norm Time Relief
] No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request i
j E21-F031A 2 B 3" M0 Gate F-9 H-16331 CS Pump ttin. Flow 0 Qtr NA Yes E21-F031B 2 B 3" Mc Gate F-10 H-16331 CS Pump Min. Flow 0 Qtr NA Yes
! E21-F036A 2 AC 3" Check E-9 H-16331 CS Test Line See 6.1.6
, Cont. Iso i
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o O O SYSTEM: High Pressure Coolant Injection Plant Hatch - Unit i Valve Test Program Sh 15 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request E41-F001 2 B 10" M0 Gate E-12 H-16332 HPCI Steam Supply C Qtr NA Yes Shutoff E41-F002 1 A 10" No Gate C-2 H-16332 HPCI Steam Supply 0 Qtr CIV Yes 6.1.2 Inbrd. Iso E41-F003 1 A 10" t*0 Gate C-4 H-16332 HPCI Steam Supply 0 Qte CIV Yes Outbrd. Iso E41-F004 2 B 16" M0 Gate D-9 H-16332 HPCI Pump Suc. O Qtr NA Yes from Cond. Stor.
E41 -F005 2 C 14" Check F-6 H-16332 HPCI Pump Disch. C Note 5 NA No l E41-F006 2 A 14" M0 Gate E.5 H-16332 HPCI Pump Inbrd. See 6.1.10
' C PIV Yes 6.1.10 Disch. Iso 1 E41-F007 2 B '14" f10 Gate E-6 H-16332 C HPCI Pump Outbrd. See 6.1.10 O NA Yes 6.1.10 Disch.
E41 -F008 2 A. 10" 'h0 Globe D-7 H-16332 HPCJ Pump Test ( (
Note 1 CIV No e
BygissIso. f E41-F011 2 B 10" M0 Gate C-7 H-16332 HPCI Pump Redun. C Note 14 NA No Shutoff to Cond. Stg.
I E41-F012 2 A 4" H0 Gate F-7 H-16332 HPCI Pump Min. Flow C g Qtr CIV Yes 6.1.2
. Inbrd. Iso E41-F019 2 C 16" Cneck D-9 H-IS332 HFCI Pump Suc. C Note 5 NA No from Cond. Stg.
' No 6.1.11 Ir.ord. Iso 6.1.12
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% h, SYSTEM: High Pressure Coolant Injecti n Plant Hatch - Unit i Valve Test Program Sh. 16 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pes Exercise Leakage Reg'd' Request E41-F022 2- AC 2" Stop Check G-4 H-16332 HPCI Turb. Exh. C See 6.1.12 CIV No 6.1.11 Drn. Torus Iso 6.1.12
! E41-F025 2 B- 1" A0 Globe J-8 H-16333 Bar Cond. Cooling ' C Qtr NA Yes E41 F026 2 0 1" A0 Globe J-8 H-16333 Bar Cond. Coolipi! C Qtr N4 Yes E41-F035 2 B 2" A0 PCV G-8 H-16333 HPCI Turb. Lube C Note 10 NA No 011 Cooling E41-F040 2 AC 2" Check G-5 H-16332 HPCI Turb. Exh. C See 6.1.12 CIV No 6.1.12 Drn. Torus Iso E41-F041 2 B 16" M0 Gate D-8 H-16332 HPCI Pump Suc. C Qtr NA Yes
- Shutoff E41-F042 2 A 16" M0 Gate J-5 H-16332 HPCI Pump Suc. C Qtr CIV Yes Torus Outbrd. Iso E41-F045- 2 C 16" Check J -7 H-16332 HPCI Pump Suction C See 6.1.?3 NA No 6.1.13 E41-F046 2 AC 4" Check F-8 H-16332 HPCI Pump Min Flow C Note 5 CIV No Outbrd. Iso E41-F049 2 AC 20" Check G-4 H-16132 HPCI Turb. Exh. C See 5.1.12 CIV No 6.1.12 Outbrd. Iso E41-F051 2 A 16" A0 Bfly J-4 H-16332 HPCI Pump Suc. O Qtr CIV Yes Torus Inbrd. Iso E41-F059 2 B 2" M0 Globe F-8 H-16333 HPCI Turb. Lube Oil C Qtr NA Yes Cooling E41-F104 2 A 2* M0 Gate G-3 H-16332 HPCI Vac. Relief 0 Qtr CIV Yes Outbrd. Torus Iso E41-F111 2 A 2" M0 Gate C-2 H-16332 HPCI Vac, Relief 0 Qtr CIV Ns Inbrd. Torus Iso
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O O SYSTEM: Reactor Coolant Isolation Cooling Pl?nt Hatch - Unit i Valve Test Program Sh.17 of 34 ,
Valve Code Stroke Norm Time M s. Class Cat Description Coord. PAID Function Rei1ef Pos Exercise Leakage Reg's Request E51-F001 2 AC 10" Stop Check G-5 H-16334 RCIC Turb. Exh. C See 6.1.12 CIV No 6.1.11 to_ Torus Iso 6.1.12 E51-F002 2 AC 2" Stop Check G-6 H-16334 RCIC Vac Pump C See 6.1.12 CIV No 6.1.11 Disch. to Torus Iso 6.1.12 E51-F003 2 A 6" . 50 Bfly J-6 H-16334 RCIC, Pump Suction 0 Qtr CIV hs 6.1.2 Torus Iso E51-F007 1 A 4" M0 Gate' C-5 H-16334 RCIC Steam SuppTy- 0 Qtr CIV Yes 6.1.2 Inbrd. Iso t
E51-F008 1 A. 4" M3 Gate, C-6 H-16334 RCIC Steam Supp1,y 'O Qtr .C!Y Yes Outbrd Iso E51-F013 2 A 4" ."0 Gate E-6 H-16334 RCIC Feedwate* Inj. C Qte . PIV 'Yes E51-F019 2 A 1" M0 Globe F-7 H-16334 RCIC Pump Min. Flow C Note 8 CIV Torus Iso -
No 6.1.2 E51-F02;
N2 '
Torus Iso E51-F028 2 AC 2" Check G-7 H-16334 RCIC Vac. Pump Disch. C See 6.1.12 CIV Toras Iso No 6.1.12 E51-F031 2 !
A 6" ff0 Gate J-6 11-16334 RICI Pump Suction 0 '
Qtr CIV Yes Torus Iso E51-F040 2 AC 10" Check G-5 H-16334 4.; C Turt. Exte. C See 6.1.12 CIV Yes 6.1.12 '
Torus Iso E51-F104 2 A 1-1/2" M0 Gate G-5 H-16334 i RCIC Vac Brker 0 Otr CIV Yes 6.1.2 Torus Iso l E51-F105 2 A 1-1/2" M0 Gate G-5 H-16334 i RCIC Vac. Brker 0 ::cto 10 CIV Yes Torus Iso i
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O O O SYSTEM: Radneste Plant Hatch - Unit 1 Valve Test Program Sh.18 of 34 Stroke Valve Code More Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request
, G11-F003 2 A 3" A0 Gate 8-3 H-16176 DW Fir. Drns. O Qtr CIV Yes 3 Cont. Ise 1'
G11-F004 2 A 3" A0 Gate 8-3 H-16176 DW Fir. Drns. O Qtr CIV Yes
] Cont. Iso t
G11-F019 2 A 3" A0 Gate E-3 H-16176 DW Equip. Drns. C Qtr CIV Yes ;
Cont. Iso
! G11-F020 2 A 3" A0 Gate E-4 11-16176 DW Equip. Drns. O Qtr CIV Yes Cont. Iso 5
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SYSTEM: Reactor Water Cleanup Plant Hatch - Unit i Valve Testing Program Sh.19 of 34 Stroke Valve Code Norm Time Reifef r i No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Reg'd R: w st ;
G31-F001 1 A 6" N0 Gate B-2 H-15188 RWCU Pump Suc. O Qtr CIV Yes Inbrd. Iso r
G31-F004 1 A 6" M0 Gate B-3 H-16188 RWCU Pump Soc. O Qtr CIV 7es '
No 6.1.1 f i l F
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SYSTEH: Fuel Pool Cooling & Cleanup System i
Plant Hatch - Unit i Valve Testing Program Sh. 20 of 34 Valve Code Stroke No. Class Cat Description Coard. PalD Norm Time Relief Function Pos Exercise Leakage Req'd Request G41-F001A 3 B 8" kn. Bfly D-9 H-16002 FPCCU Disch. O Qtr NA No from Skisumer Surge Tank G41-F0018 3 8 8" kn. Bfly D-9 H-16002 FPCCU Disch. O Qtr NA No from Skisumer Surge Tank G41-F002A 3 8 6" kn. Bfly F-2 H-16002 FPCCU Pump Suction 0
' Qtr NA No G41-F002B 3 8 6" kn. Bfly H-2 H-16002 FPCCU Pump Suction 0 Qtr NA No G41-F019A 3 8 6" k n. Gate D-9 H-16002 FPCCU Inlet from C RHR Qtr NA No I
G41-F019B 3 B 6" Man. Gate 0-9 I H-16002 FPCCU Inlet from C Qtr R4 No RHR G41-F020A 3 8 6" Man, Gate D-11 H-16002 FPCCU Return from C Qtr NA No RHR G41-F0208 3 8 6" Man. Gate D-11 H-16002 FPCCU Return from C Qtr NA No RHR 1
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1 O O O SYSTEM: Demineraliz d Water Plant Hatch - Unit i Valve Testing Program Sh. 21 of 34 Stroke Valve Code More Time Relief !
Mo. Class Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Request I i t i P21-F353 2 AE 2" Manual Gate F-7 H-16015 Demin. Water LC Note 1 CIV No !
Cont. Iso P21-F406 2 AE 2" Manual Gate F-8 H-16015 Demin. Water LC Note 1 CIV No I
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o o o SYSTEH: H2 and 02 Analyzer Plant Hatch - Unit i Valve Testing Program Sh. 22 of 34 Stroke
? Valve Code Norm Time Relief
[ No. Class Cat Descrip:fon Coord. P&ID Function Pos Exercise Leakage Peq'd Regeost P33-F002 2 A l' A0 Control 9-4 H-16276 H2 402 Analy. O Qtr CIV Yes Cont. Iso P33-F003 2 A l' A0 Contro! D-4 H-16276 H2 402 Analy. O Qtr CIV Yes Cont. Iso P33-F004 2 A l' A0 Control E-4 H-16276 H2 402 Analy. O Qtr CIV Yes ,
Cont. Iso
) P33-F006 2 A 1" An Control G-4 H-16276 H2 402 Analy. O Qtr CIV Yes Cont. Iso i
l P33-F007 2 A 1".A0 Control H-4 H-16276 H2 802 Analy. O Qtr CIV Yes Cont. Iso P33-F010 2 A l' A0 Control B-5 H-16276 H2 802 Analy. O Qtr CIV Yes '
. Cont. Iso P33-F011 2 A l' A0 Control D-5 H-16276 H2 &02 Analy. O Qtr CIV Yes Cont. Iso P33-F012 2 A 1" A0 Control E-5 H-16276 H2 402 Analy. 0 Qtr CIV Yes
- Cont. Iso
! P33-F014 ? A l' A0 Control G-5 H-16276 H2 &02 Analy. O Qtr CIV Yes Cont. Iso '
P33-F015 2 A 1" A0 Control H-5 H-lC276 h2 402 Auly. O Qtr CIV Yes q Cont. Isc 1
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O O SYSTEN: Plant Service Nater Plant Hatch - Unit i Valve Testing Program Sh. 23 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord, P&ID Function Pos Exercise Leakage Reg'd Pvpst P41-F023A 3 C 2" Check A-10 H-16011 CRD Pump Room Ccoler 0 Note 11 NA No P41-F0238 3 C 2" Check B-10 H-16011 CRD Pump Room Cooler 0 Note 11 NA No P41-F024A 3 C 1-1/2" Check B-8 H-16011 HPCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 P41-F024B 3 C 1-1/2" Check C-8 H-16011 HPCI Pump Room Cooler C See 6.1.14 NA No 6.1.14 P41-F025A 3 C 3* Check D-8 H-16011 RHR & CS Pump Room C See 6.1.14 NA No 6.1.14 Cooler P41-F0258 ? C 3" Check D-8 H-16011 RilR & CS Pump Room $ee 6.1.14 C NA No 6.1.14 Cooler P41-F026A 3 C 3" Check G-7 H-16011 RHR Pump Cooler See 6.1.14 C NA No 6.1.14 P41-F0268 3 C 3* Check G-7 H-16011 RHR Pump Cooler See 6.1.14 C NA No 6.1.14 P41-F028A 3 C 1-1/2" Check G-2 H-16011 RCIC Pump Room See 6.1.14 C NA No 6.1.14 Cooler P41-F0288 3 C 1-1/2" Check G-3 H-16011 RCIC Pump Room C See 6.1.14 NA No 6.1.14 Cooler P41-F035A 3 B 2" A0 Globe B-9 H-16011 HPCI Pump Room C Qtr NA Yes 6.1.15 Cooler P41-F035B 3 B 2* A0 Globe C-9 H-16011 HPCI Pump Room C Qtr NA Yes 6.1.15 Cooler P41-F036A 3 B 3" A0 Globe D-9 H-160ll RHR & CS Pump C Qtr NA Yes 6.1.15 Room Cooler P41-F036B 3 8 3" A0 Globe D-9 H-16011 RHR & CS Pump C Qte NA Yes 6.1.15 Room Cooler
O O O 4
SYSTEM: Plant Service Water Plant Hatch - Unit 1 Valve Testing Program Sh. 24 of 34 Valve Code Stroke i Norm Time Rellef No. Class Cat Description Coord. PAID Function Pos Exercise Leiakage Req'd Request P41-F037A 3 B 1-1/2" A0 Globe H-8 H-16011 RHR Pump Cooler C Qtr NA Yes 6.1.15 P41-F037B 3 B 1-1/2" A0 Globe E-9 H-16011 RHR Pump Cooler C Qtr NA Yes 6.1.15 P41-F037C 3 B 1-1/2" A0 Clobe J-8 H-16011 RH3 Pump Cooler C Qtr NA Yes 6.1.15 P41-F0370 3 8 1-1/2" A0 Globe E-9 H-16011 RHR Pump Cooler C Qtr NA Yes 6.1.15 P41-F039A 3 B 3" A0 Globe G-8 H-16011 RHR Pump Cooler C Qtr NA Yes 6.1.15 i
P41-F0398 3 B 3" A0 Globe G-8 H-16011 RHR Pump Cooler C Qtr NA Yes 6.1.15 P41-F040A 3 B 2" A0 Globe H-2 H-16011 RCIC Pump Room C Qtr NA Yes 6.1.15 Cooler P41-F0408 3 8 2" A0 Globe H-3 H-16011 RCIC Pump Room C Qtr NA Yes 6.1.15 Cooler P41-F042A 3 8 3" A0 Globe A-10 H-M011 CR0 Pump Room 0 Qtr NA Yes 6.1.15 Cooler P41-F0428 3 8 3" A0 Globe B-10 H-16011 CR0 Pump Room 0 Qtr NA Yes 6.1.15 Cooler P41-F049 2 A 8" H0 Cate F-6 H-16011 Drywell Air 0 CS Civ Yes 6.1.16 Cooler Iso P41-F050 2 A 8" M0 Gate D-2 H-16011 Drywell Air 0 CS CIV Yes 6.1.16 Cooler Iso P41-F064 3 C 6" Check F-10 H-16011 Division I supply 0 Note 11 NA No P41-F065 3 C 8" Check G-10 H-16011 Division II supply 0 Note 11 NA No
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SYSTEM: Plant Service Water Plant Hatch - Unit i Valve Testing Program Sh. 25 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description ,Coord. P&ID Function Pos Exercise Leakage Reg'd Request P41-F208A 3 B 3" A0 PCV - U-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 i P41-F208C 3 8 3" A0 PCV - D-11001 S.W. Press Regulator 0 Note 9 NA No P41-F208D 3 B 3" A0 PCV -
D-11001 S.W. Press Regulator 0 Note 9 NA No
- P41-F310A 3 B 30" M0 Bfly ' -
D-11001 Turb. Bldg. Supply 0 CS NA Yes 6.1.17 i
Shutoff P41-F3108 3 B 30" H0 Bfly -
D-11001 Turb. Bldg. Supply 0 CS NA Yes 6.1.17 i
Shutoff P41-F310C 3 8 30" M0 Bfly -
D-11001 Turb. Bldg. Supply 0 CS NA Yes L3.17 Shutoff j P41-F3100 3 8 30" HO 6 fly - D-11001 Turb. Bldg. Supply 0 CS NA Yes 6.1.17 Shutoff P41-F311A 3 8 IB" Check -
D-11001 Pursp Discharge O Note li NA No P41-F3118 3 B IB* Check - D-11001 Sump Discharge O Note 11 NA No P41-F311C 3 B 1B" Check -
D-11001 Pimp Discharge C Note 11 NA No P41-F311D 3 B IC" Check - D-11001 Pump Discharge O Note 1. NA No i
P41-L003A 3 B 1" Solenoid -
D-11001 S.W. Pump Cooling 0 Note 7 NA Wo Shutoff P41-LOO 3B 3 8 1" Solenoid -
D-11001 S.W. Pump Cooling 0 Note 7 NA No Shutoff g P41-L003C 3 B 1" Solenoid -
D-11001 S.W. Pump Cooling 0 tiete 7 NA No Shutoff P41-L003D 3 8 1" Solenoid -
D-11001 S.W. Pump Cooling 0 Note 7 NA No j Shutoff
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O O SYSTEM: R8 Closed Cooling Water Plant Hatch - Unit 1 Valve Testing Program Sh. 26 of 34 Stroke l Valve Code Norm Time Relief i No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request l P42-F051 2 A 4" M0 Gate B-9 H-16009 RBCCW to Recir. O CS CIV Yes 6.1.18 Cont. Iso P42-F052 2 A 4" M0 Gate E-9 H-16009 RBCCW to Recir. O CS CIV Yes 6.1.18 j Cont. Iso 1
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- SYSTEM
- Service Air Plant Hstch - Unit 1 Valve Testing Program Sh. 27 of 34 Stroke
! Valwe Code Norm Time Relief No. Class _ Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request P51-F513 2 AE 2" Man. Globe F-3 H-16013 Ser. Air Cont. Iso LC Note 1 CIV No P51-F514 2 AE 2" Man. Globe F-3 H-16013 Ser. Air Cont. Iso LC Note 1 CIV ho a
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o O O SYSTEM: Drywell Preumatic Plant Hatch - Unit i Valve Testing Program Sh. 28 of 34 Valve Code Stroke Norm Time Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage 4 Req'd Request i P70-F002 2 A 1" AG Control F-8 H-16286
' DW Pneumatic Cont. O Qtr CIV Yes
] Iso P70-F003 2 A l' A0 Control F-8 H-IS286 DW Pneumatic Cont. O Qtr CIV Yes
~
P70-F005 2 A 2" A0 Control D-8 H-16286 DW Pneumatic Cont. O Qtr CIV Yes Iso P70-F020 2 AC 2" Check C-7 H-16286 DW Pneumatic Cont. O R0 CIV No 6.1.1 j 1s0 l
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! O O O SYSTEM: Standby Gas Treatment Plant Hatch - Unf t i Valve Testing Program Sh. 29 of 34 i
- Valve Code Stroke Norm Time Relief l No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd I
Request
! T46-F001A 3 B 18" A0 Bfly C-1 H-16020 Filter Bed Inlet C Qtr i
NA Yes from Reactor Bldg.
! T46-F0018 3 8 18" A0 Bfly G-1 H-16020 Filter Bed Inlet C Qtr NA Yes J
from Reactor Bldg.
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i O O O SYSTEM: Containment Purge and Inerting Plant Hatch - Unit i Valve Testing Program Sh. 30 of 54 Stroke l Valve Code Norm Time Relief l No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request i
! T48-F103 2 A 6" A0 Bfly F-2 31-16000 DW & Torus Supoly C Qtr CIV Yes i Iso j T48-F104 2 A 1" A0 Control G-4 H-15000 Dwg & Torus C Qtr CIV Yes 1
Outbrd. Iso T48-F113 2 A 2" A0 Control F-7 H-16000 DW Inerting Outbrd C Qtr CIV Yes
! Iso T48-F114 2 A 2" A0 Control F-8 H-16000 DW Inerting Inbrd C Qtr CIV Yes Iso i T48-Fil5 2 A 2" A0 Control G-7 H-16000 DW Inerting Outbrd C Qtr CIV Yes Iso T48-F116 2 A 2" A0 Control G-8 H-16000 DW Inerting Outbrd C Qtr CIV Yes
< Iso T48-F118A 2 A 1" Solenoid G-5 H-16000 Torus Makeup 0 Qtr CIV Yes Inbrd Iso T48-F1188 2 A 1" Solenoid G-5 11-16000 Torus Makeup 0 Qtr CIV Yes
- Inbrd Iso T48-F321 2 A 2" A0 Control J-7 H-16000 DW Inerting .C Qtr CIV Yes l Outbrd. Iso l T48-F322 2 A 2" A0 Control J-8 H-16000 DW Inerting C Qtr CIV Yes Inbrd. Iso i
, T48-F325 2 A 2" A0 Control H-7 H-16000 Torus Inerting C Qtr CIV Yes 1
Outbrd. Iso T48-F327 2 A 2" A0 Control H-8 H-16000 Torus Inerting C Otr CIV Yes Inbrd. Iso l
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O O O SYSTEM: Containment Purge and Inerting Plant Hatch - Unit i Valve Testing Program Sh. 31 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request T48-F307 2 A 18" A0 Bfly C-9 H-16024 DW Purge Inlet C Note 1 CIV No Inbrd Iso T48-F308 2 A 18" A0 Bfly C-10 H-16024 DW Purge Inlet C Note 1 CIV No Inbrd Iso j T48-F309 2 A 18" A0 Bfly E-10 H-16024 Torus Purge Note 1 C CIV No l
Inlet Inbrd Iso T48-F310 2 A 20" A0 Bfly F-10 H-16024 Torus Purge Vac. C Qtr CIV Yes Brker Iso T48-F311 2 A 20" A0 Bfly F-9 H-16024 Torus Purge Vac. C Qtr CIV Yes Orker Iso I48-F313 2 A 18" A0 Bfly G-4 H-16024 Toms Purge 0 Qtr CIV Yes Outlet Irbrd Iso T48-F319 2 A 18" A0 Bfly D-4 H-16024 DW Purge C Note 1 CIV No Outlet Inbrd Iso T48-F320 2 A 18" A0 Bfly D-3 H-16024 DW Purge Outlet C Note 1 CIV No Outbrd Iso
. T48-F323A 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No Breaker
- T48-F323B 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No I
Breaker T48-F323C 2 C 18" A0 Check H8 H-16024 DW to Torus Vac. C Qtr NA No Creaker T48-F323D 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No Breaker T48-F323E 2 C 18" A0 Check H-8 H-16024 DW to Torts Vac. C Qtr NA No
- Breaker
O O O SYSTEM: Containment Purge and Inerting Plant Hatch - Unit i Valve Testing Program Sh. 32 of 34 Stroke Valve Code Norm Time Relief l No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request
. T48-F323F 2 C 18" A0 Check H-S H-16024 DW to Torus Vac. C Qtr 11 4 No Breaker T48-F323G 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No Breaker T48-F323H 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr HA No Breaker T48-F323! 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No Breaker T48-F323J 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr NA No Breaker T48-F323K 2 C 18" A0 Check H-8 H-16024 DW to Torus Vac. C Qtr HA No Breaker T48-F323L 2 C 18" A0 Check H-8 H-16024 CW to Torus Vac. C Qtr NA No Breaker T48-F324 2 A 18" A0 Bfly D-10 H-16024 Torus Purge C Note 1 CIV No
- Inlet Outbrd. Iso T48-F326 2 A IS* A0 Bfly G-3 H-16024 Torus Purge O Qtr CIV Yes Outlet Outbrd. Iso T48-F328A 2 AC 20" A0 Check G-10 H-16024 Reactor Bldg. to C Qtr CIV No Suppression Cham Vac. Brker T48-F3288 2 AC 20" A0 Check G-9 H-16024 Reactor Bldg. to C Qtr CIV No Suppression Cham Vac. Brker i
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. SYSTEM: Containment Purge and Inerting Plant Hatch - Unit i Valve Testing Program Sh. 33 of 34 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Req'd Request T48-F332A 2 A 2" A0 Control E-3 H-16024 Torus Purgt C Qte CIV Yes Outlet Outbrd Iso T48-F332B 2 A 2" A0 Control F-3 H-16024 Torus Purge C Qtr CIV Yes Outlet Outbrd Iso T48-F333A 2 A 2" A0 Control E-4 H-16024 Torus Purge C Qtr CIV Yes Outlet Inbrd Iso T48-F333B 2 A 2" A0 Control F-4 H-16024 Torus Purge C Qtr CIV Yes Outlet Inbrd Iso T48-F334A 2 A 2* A0 Control B-3 H-16024 DW Purge Outlet C Qtr CIV Yes Outbrd Iso T48-F334B 2 A 2" A0 Control C-3 H-16024 DW Purgo Outlet C Qtr CIV Yes Outbrd Iso T48-F335A 2 A 2" A0 Control B-4 H-16024 DW Purge Outlet C Qtr CIV Yes Inbrd Iso T48-F335B 2 A 2" A0 Control C-4 H-16024 DW Purge Outlet C Qtr CIV Yes Inbrd Iso T48-F338 2 A 2" Solenoid H-2 H-16024 Bypass-Outbrd Iso C Qtr CIV Yes T48-F339 2 A 2" Solenoid H-3 H-16024 Bypass-Inbrd Iso C Qtr CIV Yes T48-F340 2 A 2" Solenoid D-4 H-16024 Bypass-Outbrd Iso C Qtr CIV Yes T48-F341 2 A 2" Solenoid D-4 H-16024 Bypass-Inbrd Iso C Qtr CIV Yes l
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o O O SYSTEM: Cont.sinnent Purge and Inerting Plant Hatch - Unit i Valve Testing Program Sh. 34 of 34 Valve Code Stroke Norm Time Relief 4 No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request T48-F342A 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F342B 2 A 1/2" Solenoid H-8 H-16024 i Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F342C 2 A 1/2" Solenoid H-8 H-16024
' Torus to DW Vac C Note 12 CIY No Breaker Iso T48-F342D 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F342E 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIY No Breaker Iso T48-F342F 2 A 1/2" Solenoi. E-8 H-16024 Torus to DW Vac C Note 12 CIM No Breaker Iso T48-F342G 2 A 1/2" Solenoid H-8 H-16024 j Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F342H 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F3421 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso T48-F342J 2 A 1/2" Solenoid H-8 H-16024 Torus to fr4 Yac C Note 12 CIV No Breaker Iso j T48-F342K 2 A 1/2" Solenoid H-8 H-16024 Torus tc. 0W Vac C Note 12 CIV No Breaker Iso T48-F342L 2 A 1/2" Solenoid H-8 H-16024 Torus to DW Vac C Note 12 CIV No Breaker Iso t
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O O O SYSTEM: Main Steam & Feedsater Plant Hatch - Unit 2 Valve Testing Program Sh.1 of 43 Stroke
, Valve Code Norm Time Relief i
No. _ Class Cat Description Coord. PAID Function Pos Exerci a Leakage Req'd Request 2021-F010A 1 AC 18" Check E-3 H-26000 FW Inbrd. Cont. Iso. O R0 CIV No 6.1.1 2821-F010B 1 AC 18" Check F-3 H-26000 FW Inbrd. cont. Iso. CIV O R0 No 6.1.1 2B21-F013A 1 C 6" Relief D-6 H-26000 Main Steam Relief - Note 3 NA No 2821-F0138 1 C 6" Relief D-6 H-26000 Main Steam Relief -
Note 3 NA No 2821-F013C 1 C 6" Relief D-6 H-26000 Main Steam Relief -
Note 3 NA No 2B21-F0130 1 C 6" Relief D-6 H-26000 Main Steam Relief - Note 3 NA No l 2B21-F013E C 6" Relief D-6 H-26000 Main Steam Relief 1 -
Note 3 NA No 2B21-F013F 1 C 6" Relief D-6 H-26000 Main Steam Relief - Note 3 NA No 2B21-F013G 1 C 6" Relief D-6 H-26000 Main Steam Relief -
Note 3 NA No 2B21-F013H 1 C 6" Relief D-6 H-26000 Main Steam Relief - Note 3 NA No 2B21-F013K 1 C 6" Relief D-6 H-26000 min Steam Relief . Note 3 IIA No 2B21-F013L 1 C 6" Relief D-6 H-26000 Main Steam Relief -
Note 3 NA No 2B21-F013M 1 C 6" Relief D-6 H-26000 Main Steam Relief - Note 3 NA No 2B21-F016 1 A 3" M0 Gate E-8 H-26000 Main Steam Line C Note 1 CIV No 6.1.2 DRN. Inb. Iso.
2B21-F019 1 A 3" H0 Gate E-9 H-26000 min Steam Line C Note 1 CIV No DR4. Inb. Iso.
2821-F022A 1 A 24" A0 Globe D-8 H-26000 MSIV 0 Qtr. CIV Yes l
2821-F0228 1 A 24" A0 Globe D-8 H-26000 MSIV 0 Qtr. CIV Yes 2B21-F022C 1 A 24" A0 Globe D-8 H-26000 MSIV 0 Qtr. CIV Yes 1
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SYSTEM: Main Sttam & Feedwater Plant Hatch - Unit 2 Valve Testing Program Sh. 2 of 43 Stroke Yalve Code More Time Relief No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request 2821-F022D 1 A 24" A0 Globe D-8 H-26000 MSIV O Qtr. CIV Yes 2B21-F028A 1 A 24" A0 Globe D-9 H-26000 MSIV 0 Qtr. CIV Yes i 2821-F028B 24" A0 Globe D-9 H-26000 1 A MSIV 0 Qtr. CIV Yes j 2821-F020C 1 A 24" A0 Globe D-9 H-26000 MSIV 0 Qtr. CIV' Yes 2B21-F028D 1 A 24" A0 Globe D-9 H-26000 MSIV O Qtr. CIV Yes 2821-F037A 3 C 6" Check E-7 H-260C0 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
2821-F037B 3 C 6" Check E-7 H-26000 Vac, Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
2821-F037C 3 C 6" Check E-7 H-26000 Vec. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
! 2B21-F031D 3 C 6" Check E-7 H-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
2B21-F037E 3 C 6" Check E-7 H-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
2821-F037F 3 C 6" Check E-7 H-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
, 2B21-F037G 3 C 6" Check E-7 H-26000 Vac. Becaker C See 6.1.3 N4 No 6.1.3 MSRV Disch.
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O O O SYSTEM: Main Steam a Feeevater Plant Hatch - Unit 2 Valve Testing Program Sh. 3 of 43 1 Stroke i Valve Code Norm Time Relief i No. Class Cat Description Coord. P&lD Function Pos Exercise Leakage Reg'd Request 2B21-FG37H 3 C 6" Check E-7 H-26000 Vac.' Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch.
2B21-F037K 3 C 6" Check E-7 H-26000 Vac. Dreaker C See 6.1.3 NA No 6.1.3
! MSRV Disch.
2B21-F037L 3 C 6" Check E-7 H-26000 Vac. Dreaker C See 6.1.3 NA No 6.1.3 MSRV Di.ch.
2821-F037M 3 C 6" Check E-7 H-26000 Vac. Breaker C See 6.1.3 NA No 6.1.3 MSRV Disch. ,
, 2821-F076A 2 C 18" A0 check E-2 H-26000 FW Check 0 Note 13 NA No
- ?B21-F0768 2 C 18" A0 check F-2 H-26000 FW Check 0 Note 13 NA Ho 2B21-F077A 1 AC 18" A0 check E-3 H-26000 FW Cutbrd 150 0 Note 13 CIV No 2B21-F0778 1 AC 18" A0 check E-3 H-26000 FW Outbrd 150 0 Note 13 CIV No ,
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1 O O O SYSTEM: Reactor Recirculation System Plant Hatch - Unit 2 Valve Testing Program Sh. 4 of 43 1
Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PSID Function Pos Exercise Leakage Req'd Request j
2B31-F013A 1 AC 3/4" Check G-3 H-26003 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 2B31-F0138 1 AC 3/4" Check G-3 H-26003 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 2831-F017A 1 AC 3/4" Check G-2 H-26003 Recir. Pump Seal Wtr 0 R0 Cif No 6.1.1 2831-F0178 1 AC 3/4" Check G-2 H-26003 Recir. Pump Seal Wtr 0 R0 CIV No 6.1.1 2D31-F019 1 A 1" A0 Globe E-4 H-26003 aeac. Sample Sys. O Qtr CIV Yes t Inbrd. Iso 2831-F020 1 A 1" A0 Globe E-2 H-26003 Reac. Sample Sys. O Qtr CIV Yes Inbrd. Iso 2Bil-F031 A 1 8 28" M0 Gato G-7 H-26003 Reactor Recirculation 0 CS t1A Yes 6.1.4 I 2831-F0318 1 8 28* MD Gate G-7 H-26003 Reactor Recirculation 0 CS NA Yes 6,1.4 I
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SUTEM: Standby Liquid Control Plant Hatch - Unit 2 Va.ve Testing Program Sh. 5 of 43 Valve Code
- Stroke Norm Time ReMef No. Class Cat Description Coord. P&ID Functiun Pos Exercise Leakage Req'd Regrest j
2C41-F004A 2 D 1-1/2" Exp1 E-2 H-26009 k.C Explo Act C Note 4 NA No ,
2C41-F004B 2 D 1-1/2" Exp1 F-2 H-26009 SLC Explo Act C Note 4 NA No
! 2C41-F006 1 AC 1-1/2" Check E-2 H-?6009 SLC Cutbrd C 18 mos. CIV No 6.1.5 Cont. Iso 2C41-F007 1 AC 1-1/2" Check F-1 H-26009 SLC Outbrd C IS mos. CIV No
) Cont. Iso 2C41-F029A 2 C 1" Relief E-5 H-26009 SLC Pump Disch, C Note 3 NA No Relief 2C41-F029B 2 C 1" Relief H-5 H-26009 SLC Pump Disch. C Note 3 NA No Relief 2C41-F033A 2 C 1-1/2" Check F-4 H-26009 SLC Pump Disch. C Qtr. NA No i 2C41-F033B 2 C 1-1/2* Check G-4 H-260t'9 SLC Pump Disch. C Qtr. NA No l
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SYSTEM: Fission Products Monitoring System Plant Hatch - Unit 2 Valve Testing Program Sh. 6 of 43 Stroke
- Valve Code Norm Time Relief Ka. Class Cat Description Coord. PAID Function Pos Exercise Leakage Req'd Request 2011-F050 2 A 1" A0 Control D-5 H-26016 Fission Prod. Mon. O Qtr CIV Yes Cont. Iso 2D11-F051 2 A l' A0 Control F-5 H-26016 Fission Prod. Mon. O Qtr CIV Yes Cont. Iso 2011-F052 2 A l' A0 Control D-6 H-26016 Fission Prod. Mon. 0 Qtr CIV Yes Cont. Iso ,
i 2Dil-F053 2 A 1" A0 Control F-6 H-26016 Fission Prod. Mon. LC Qtr CIV Yes
, Cont. Iso 2011-F058 2 AE 1" LC Manual G-3 H-26016 Fission Prod. Mon. LC Note 1 CIV No Cont. Iso 2011-F061 2 AE 1" LC Manual F-8 H-26016 Fission Prod. Mon. LC Note 1 CIV No Cont. Iso I
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O O O SYSTEM: Residual Heat Removal Plant Hatch - Unit 2 Valve Testing Program Sh. 7 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Request 2E11-F003A 2 8 16" M0 Gate Viv D-4 H-26015 RHR Hx Shell 0 Qtr HA Yes Side Outlet 2E11-F0038 2 8 16" M0 Gate Viv E-8 H-26014 RHR Hx Shell 0 Qtr NA Yes Side Outlet 2E11-F004A 2 A 24" M0 Gate Viv E-8 H-26015 RilR Pump Suction 0 Qtr CIV Yes Torus Iso 2E11-F004B 2 A 24" M0 Gate Viv F-3 H-26014 RHR Pump Suction 0 Qtr CIV Yes Torus Iso 2E11-F004C 2 A 24" M0 Gate Viv E-9 H-26015 RHR Pwnp Suction 0 Qtr CIV Yes Torus Iso 2E11-F004D 2 A 24" M0 Gate Viv F-2 H-26014 RHR Pump Suc 0 Qtr CIV Yes Torus Iso 2E11-F006A 2 B 20" M0 Gate V1v F-8 H-26015 RHR Shutdown C Qtr NA Yes Cooling Sys 2E11-F0068 2 8 20" M0 Gate Viv F-3 H-26014 RHA Shutdown C Qtr NA Yes Cooling Sys 2E11-F006C 2 8 20" M0 Gate Viv F-10 H-26015 R!lR Shutdown C Qtr NA Yes Cooling Sys 2E11-F006D 2 8 20" M0 Gate Viv F-2 H-26014 RHR Shutdown C Qtr NA Yes Cooling Sys 2E11-F007A 2 A 4" M0 Gate Viv D-5 H-26014 RHR Pump Min Flow 0 Qtr CIV Yes G.1.2 Torus Iso 2E11-F007B 2 A 4" M0 Gate Viv D-6 H-26014 RHR Pump Min Flow 0 Qtr CIV Yes G.I.2
O O O SYSTEM: Residual Heat Removal Plant Match - Unit 2 Valve Testing Program Sh. 8 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request 2E11-F008 1 A 20* M0 Gate Viv D-10 H-26015 R:1R Shutdown C Note 1 PlV No Cooling Outbrd Iso i 2 Ell-F009 1 A 20" M0 Gate Viv D-10 H-26015 RilR Shutdown C Note 1 PIV No l Cooling Outbrd Iso 2E11-F011A 2 A 4" M0 Gate D-3 H-26015 RilR Cond. Disch. C Qtr CIV Yes 6.1.2 to Torus 2E11-F0118 2 A 4" M0 Gate D-8 H-26014 RHR Cond. Disch. C Qtr CIV Yes 6.1.2 to Torus 2E11-F015A 1 A 24" M0 Gate D-7 H-26015 LPCI Outbrd, C Qtr PIV Yes Cont. Iso 2 Ell-F015B 1 A 24" M0 Gate D-4 H-26014 LPCI Outbrd, C Qtr ply Yes Cont. Iso 2E11 F016A 2 A 16" M0 Gate B-7 H-26015 Cont. Spray C Qtr CIV Yes Outbrd. Iso 2E11-F'016B 2 A 16" M0 Gate B-4 H-26014 Cont. Spray C Qtr CIV Yes Outbrd. Iso 2E11-F017A 1 8 24" M0 Gate D-7 H-26015 LPCI O Qtr NA Yes 2E11-F0178 1 B 24" M0 Gate D-4 H-26014 LPCI O Qtr NA Yes i
2E11-F019 1 C 4" Check B-2 11-26014 Head Spray C Note 2 NA No 2 Ell-F021A 2 B 16" M0 Gate B-9 H-26015 Containment Spray C Qtr NA Yes l 2 Ell-F0218 2 B 16" M0 Gate C-2 H-26014 Containment Spray C Qtr NA Yes 2 Ell-F022 1 A 4* M0 Gate B-2 H-26014 Ilead Spray C Note 1 CIV No I
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O O O SYSTEM: Residual Heat Removal Plant Hatch - Unit 2' Valve Testing Program Sh. 9 of 43 Valve Code Stroke Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakap Reg'd Request 2E11-F023 1 A 4" Mf1 Glot,e B-3 H-26014 Head Spray Outbrd. C Note 1 CIV No Iso.
2E11-F024A 2 B 16" M0 Globe C-6 H-26015 Suppression Pool C Qtr NA Yes Cooling 2E'.') -F0248 2 B 16" Pk) Globe D-5 H-26014 Suppression Pool C Qtr NA Yes Cooling 2E11-F025X 2 AC 1" Relief C-7 H-26015 LPCI Inj. C Note 3 CIV No Cont. Iso 2E11-F0258 2 AC 1" Relief C-4 H-26014 LPCI Inj. C Note 3 CIV No Cont. Iso p 2E1 -F026A 2 A 4" M0 Gate D-2 H-26015 Cond. Disch. to C ytr CIV Yes
/ ' RCIC Cont. Iso 2E11-F0268 2 A 4" t10 Gate E-9 H-26014 Cond. Disch. to C Qtr CIV Yes RCIC Cont. Iso
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u 2 Ell-F027A 2 B i 6" H0 Gate C-7 14 26015 &;ppression Pool C t ~ Qtr NA Yes
+
, Spray 3 , ., ,
2E11-F027B 2 8 t 6" M0 Gate , D-5 H-26014 Suppression Pool C Qtr NA Yes
, Spray r
2E11-F028A 2 A 16" M0 Gate C-6 H-26015 Suppression Pool C Qtr CIV Yes
, Spray Outbrd. Iso 2E11-F028B 2 A 16" M0 Gate C-7 H-26014 Suppression Pool y
C Qtr CIV Yes Spray OuthrJ. Iso 2E11-F029 2 AC 1" Relief E-9 , < H-26015 RHR Pump Suc C Note 3 CIV No Cont. Iso ,
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SYSKM: Residual Heat Removal 3* *m. t Hattv - linit 2 Valve Testing Program Sh.10 of 43 t
6 I 4 SWde l' Valve No.
Code Class Cat Description J3 * *
$ Norm Time Relief Coord. P&ID
[+ Function Fos Exercise Leakage Req'd Request
- 2 Ell-F030A 2 AC 1" Relief F-8 $ H-26014 RHR Pump Suction C Note 3 CIV No 7 Cont. Iso 2 Ell-F0308 2 - AC , 1" Relfal F-4 H-26015 RHR Pump Suction C _ Note 3 CIV No j Cont. Iso j$ '
2 Ell-F030C 2 AC 1"RAltef F-10 . H-26014 RHR Pump Suction ,C Note 3 CIV No
- / Cont. Iso ,.,
}
, 2 Ell-F0300 2 AC 1" Relief F-2 1
, 53-26015 RHR Pump Suction. C Note 3 CIV No
, , Cont. Iso 2 Ell-F031A 2 C 20" Check H-6 H-26015 RHR Pump Discharge C Note 5 NA No 2 Ell-F031B 2 C 20" Chxck H-6 H-26014 RHR Pump Discharge C Note S NA ' No 2 Ell-F031C 2 C 20" Check H-9 H-26015 RHR Pump Discharge C Note 5 NA No 2 Ell-F031D 2 C 20" Check H-3 H-26014 RHR Pump Discharge C Note 5 NA No I
2 Ell-F041A 2 A l' A0 Control C-8 H-26015 RHR Inst. Iso 0 Qtr CIV Yes l 2 Ell-F041B 2 A l' A0 Control D-2 H-26014 a RHR Inst. Iso 0 Qtr CIV Yes 2 Ell-F041C 2 A 1" A0 Control C-8 H-26015 RHR Inst. Iso 0 Qtr CIV Yes 2E11-F041D 2 A 1" A0 Control C-2 H-26014 RHR Inst. Iso 0 Qtr CIV Yes 2 Ell-F046A 2 C 3" Check G-6 H-26015 RHR Minimum Flow Line C Note 29 NA No
, 2 Ell-F0468 2 C 3" Check H-5 H-26014 RHR Min
- mum Flow Line C Note 29 NA No
?E!1-F046C 2 C 3" Check G-9 H-26015 RHR Minimum Flow Line C Note 29 flA No 2 Ell-F046D 2 C 3" Check G-2 H-26014 RHR Minimum Flow Line C Note 29 NA No l
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SYSTD4i Residual Ndat Removal Plant Hatch - Unit 2 Valve Testing Program Sh.11 of 43
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Stroke Valve Code Norm - . Time Relief Class Cat Description Coord. P&lD Function + Pos Exercise Leakage Req'd Request No. ,
2E11-F047A 2 8 16" M0 Gate E-5 H-26015 Rii:t Hx Shell Side 0 Qtr NA' Yes Side Inlet ,
16" M0 Gate ' . f-6 H-26014 RHR Mx Stell Side 0 Qtr NA Yes ,r 2E11-F047B 2 B -
-y kide Inlet 24" M0 Globe .PHR Hx Shell Side 0 Qtr HA Yes 2E114048A 2 B D'-5 LH-26015 Bypass
. '2E11-F048B 2 B 24" M0 Globe E-6 H-26014 RHR Hx Shell Side 0 Qtr NA Yes Bypass i 2 Ell-f050A I AC 24" A0 Check D-9 H-2001$. LPCI Injec. Iso C See 6.1.7 P!V No 6.1.7 24" A0 Check D-3 H-26014 LPCI Injec. Iso C See 6.1.7 ply No ,6.1.7 2E11-F0508 1 AC 3 2E11-F055A 2 AC 4" Relief F-4 H-26015 RHR Hx Shell C Note 3 C1V No Relief Cont. Iso 2E11-F0E!8 2 AC 4" Reifer F-71' H-26014 RHR Hx Shell C Note 3 CIV No Relief Cont.150 2E11-F065A 2 B 24" A0 Brly F-8 H-26015 RHR Torus Suction 0 Qtr NA Yes 2E11-F0658 2 8 24" A0 Bfly F-3 H-26014 RHR Torus Suction 0 Qtr NA Yes I
- 2 Ell-F065C 2 8 24" A3 Bfly 'F-9 H-26015 RHR Torus Suction 0 Qtr NA Yes 2E11-F065D 2 B 24" A0 Bfly F-2. H-26014 RHR Torus Suctio'n 0 Qtr NA Yes 2E11-F078A 2 C 10" Check E-4 H-26015 RHR Hx Ser Wtr Tie C R0 NA No 6.1.8 2E11-F0788 2 C 10" Check E-7 H-26014 RHR Hx Ser Wtr Tie C RO NA No 6.1.8 2E11-F091A 2 8 6" M0 Globe E-2 H-26015 Steam Line to RHR C (tr NA Yes Hx Shutdwn
O O O SYSTEM: Residual Heat Removal Plant Hatch - Unit 2 Valve Testing Program Sh.12 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request 6* M0 Globe E-9 H-7bA14 Steam Line to RiiR C Qtr M; Yes 2E11-F0918 2 8 Hx Shutdwn 2E11-F097 2 AC 3" Relief E-9 H-26015 Steam Line Relief C Note 3 CIV No Cont. Iso 2E11-F103A 2 A 1" M0 Globe E-4 H-26015 RHR Hx Vent C Qtr CIV Yes Cont Iso 2E11-F1038 2 A 1" M0 Globe E-7 H-26014 RHR Hx Vent C Qtr CIV Yes Cont Iso 2E11-F140A 2 8 0" M0 Gate E-2 H-26015 Steam Line to RHR C QLr NA Yes
. Hx Shutdown 2E11-F140B 2 8 6" M0 Gate E-9 H-26014 Steam Line to RHR C Qtr NA Yes Hx Shutdown 2E11-F068A 3 8 10" M0 Ball C-10 H-26015 RHR Hx Ser. Wtr C Note 6 NA No Disch.
2E11-F06BB 3 8 10" M0 Ball G-10 H-26014 miR Hx Ser. Wtr C Note 6 NA No
, Disch.
2E11-F073A 2 8 10" M0 Gate G-4 H-26015 RHR Ser. Wtr Intertie C Qtr NA Yes 1
j 2E11-F0738 2 B 10" H0 Gate G-7 H-26014 RHR Ser. Wtr Intertie C Qtr NA Yes 2 Ell-F075A 2 B 10' M0 Gate G-4 11-26015 RHR Ser. Wtr Intertie C Qtr NA Yes 2E11-F075B 2 B 10" HO Gate G-7 H-26014 RHR Ser. Wtr Intertie C Qtr NA Yes 2E11-F119A 3 B 18" M0 Gate C-8 H-21039 RHR Ser. Wtr Train C Qtr NA Yes A & B Cross J
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b SYSTEM: Residual Heat Removal Plant Hatch - Unit 2 Valve Testing Program Sh.13 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. Pa!D ! Function Pos Exercise Leakage Req'd Request 2E11-F1198 3 B 18" M0 Gate G-8 H-21039 RHR Ser. Wtr Train C Qtr NA Yes A & B Cross 2 Ell-F126A 3 8 1-1/2" A0 PCV B-2 H-21039 Seal Water to RHR C Note 9 NA Na S.W. Pump Pressure Control 2 Ell-Fl26B 3 B 1-1/2" A0 PCY J-2 H-21039 Seal Water to RHR C Note 9 NA No S.W. Pump Pressure Control 2 Ell-F20lA 3 B 1" Solenoid B-3 H-21039 RHR Service Water C Note 7 NA No Pump Cooling Water
! 2E11-F201B 3 8 1" Solenoid F-3 H-21039 RHR Service Water C Note 7 NA No Pump Cooling Water 2E11-F201C 3 8 1" Solenoid D-2 H-21039 RHR Service Water C Note 7 NA No Pump Coolinn bbter 2E11-F201D 3 8 1" Solenoid G-2 H-21039 RHR Service Weter C Note 7 NA No Pump Cooling W a ter 2E11-F207A 3
- 8 2" A0 PCV B-4 H-21034 RHR Service Water C Note 9 NA No Pump tiin. Flow 2E11-F2078 3 B 2" A0 PCV F-4 H-21034 RHR Service Water C Note 9 NA No Pump tiin. Flow 2E11-F207C 3 8 2" A0 PCV D-4 H-21034 RHR Service Water C Note 9 NA ho Pump Min. Flow
- 2E11-F207D 3 B 2" A0 PCV G-4 H-21034 RHR Service Water C Note 9 NA No Pump Min. Flow
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$1STEH: Cora Spray System Plant Hatch - Unit 2 Valve Testing Program Sh.14 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PalD Function Pos Exercise Leakage Ree'd Request 2E21-F001A 2 A 20" M0 Gate G-7 H-26018 CS Pump Suction Out 0 Qtr CIV Yes 2E21-F0018 2 A 20" M0 Gait H-7 H-26018 CS Pump Suction Out 0 Qtr CIV Yes 2E21-F003A 2 C 12" Check F-7 H-26018 CS Pump Discharge O Note 5 NA No 2E21-F0038 2 C 12" Check F-9 H-26018 CS Pump Discharge O Note 5 NA Nu l
1 j 2E21-F004A 1 B 10" M0 Gate E-6 H-26018 CS Outbrd. Injection 0 Qtr NA Yes 2E21-F004B 1 B 10" M0 Gate C-6 H-26018 CS Outbrd. Injection 0 Qtr NA Yes 2E21-F005A 1 A 10* 10 Gate E-5 H-26018 CS Outbrd. Cont. Iso C Qtr PIV Yes 2E21-F0058 1 A 10" M0 Gate C-5 H-26018 CS Outbrd. Cont. Iso C Qtr P1V Yes j 2E21-F006A 1 AC 10" A0 Check D-4 H-26018 CS Injection C Sec 6.1.7 CIV No 6.1.7 2E21-F0068 1 AC 10" A0 Check D-4 H-26018 CS Injection C See 6.1.7 CIV No 6.1.7 2E21-F012A 2 C 2" Relief E-7 H-26018 CS Pump Disch. Relief C Note 3 NA No 4
2E21-F012B 2 C 2" Relief C-8 H-26018 CS Pump Disch. Relief C Note 3 NA No 4
2E21-F015A 2 A 10" M0 Glo:4 D-7 H-26018 Core Spray Test C Qtr CIV Yes 8ypass Cont. Iso I 2E21-F0158 2 A 10" M0 Globe D-7 H-26018 Core Spray Test C Qtr CIV Yes
' 8ypast. Conc. Iso f 2E21-Fi!9A 2 B 20" A0 Bfly G-5 H-26018 Core Spray Pump 0 Qtr LA Yes Torus Suc.
l 2E21-F0198 2 8 20" A0 Bfly H-5 H-26018 Core Spray Pump 0 Qtr NA Yes Torus Suc.
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O O O SYSTEM: Core Spray Systen Plant Hatch - Unit 2 Valve Testing Program ' Sh.15 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Request
' 2E21 F031A 2 B 3" M0 Gate F-8 H-26018 CS Pump Hin. Flow 0 Qtr NA Yes
! 2E21-F031B 2 B 3" M0 Gate F-9 H-26018 CS Pump Min. Flow 0 Qtr MA Yes
' See 6.1.6 6.1.6 2E21-F036A 2 AC 3" Check E-8 H-26018 CS Test Line C CIV No l 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 2E21-F044A 2 AC 1-1/2" Stop E-1 H-26018 Jockey Pump 0 R0 CIV No 6.1.1 1 Check Cont. Iso
! 2E21-F044B 2 AC 1-1/2" Stop E-9 H-26018 Jockey Pump 0 R0 CIV No 6.1.1 1 Check Cont. Iso i
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O O O SYSTEM: MSiv Leakage Control System Plant Hatch - Unit 2 Valve Testing Program Sh.15 t,f 43 Stroke Valve Code Worm Time Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Req'd Request 2E32-F001B, 1 A 1-1/2" MD Globe E-8 H-26022 MSIV Leakage Control C Qtr CIV Yes F.K.P Cont. Iso
- . g 2E32-F0028, 2 8 1-1/2" MD Globe E-7 H-26022 MSIV Leakage Control C Qtr I4A Yes i F.K.P Cont. Iso l
2E32-F0038, 2 8 1-1/2" M0 Globe E-5 H-26022 MSIV Leakage Control C Qtr NA Yes F.K P Cont. Iso ,
2E32-F006 2 8 1-1/2" M0 Globe C-11 11-26022 MS!V Leakage Control C CS NA Yes 6.1.20 i
! 2E32-F008 2 8 1-1/2" M0 Globe C-10 H-26022 MSIV Leakage Control C CS NA Yes 6.1.20 l 2E32-F009 2 B 1-1/2" M0 Globe D-10 H-26022 MSIV Leakage Control C CS NA Yes 6.1.20 f,
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O O O SYSTEM: High Pressure Coolant Injection Plant Hatch - Unit 2 Valve Testing Program Sh.17 of 43 Stroke Valve Code Norm Time Relief Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request 4
No.
10" M0 Gate E-10 H-26020 HPCI Steam Supply C Qtr flA Yes 2E41-F001 2 8 Shutoff 2E41-F002 1 A 10" N0 Gate C-3 H-26020 HPCI Steam Supply 0 Qtr CIV Yes 6.1.2 Inbrd. Iso 10" M0 Gate C-4 H-26020 HPCI Steam Supply 0 Qtr CIV Yes 1 2E41-F003 1 A Outbrd. Iso 16" M0 Gate D-7 H-26020 HPCI Pump Suc. O Qtr NA Yes
, 2E41-F004 2 B j
from Cond. Stor.
2E41-F005 2 C 14" Check E-5 H-26020 HPCI Pump Disch. C Note 5 NA No 2E41-F006 2 A 14" N0 Gate E-4 H-26020 HPCI Pump inbrd. C See 6.1.10 PlV Yes 6.1.10 Disch. Iso 2E41-F007 2 B 14" M0 Gate E-5 H-2G020 HPCI Pump Outbrd. O See 6.1.10 NA Yes 6.1.10 Disch.
2E41-F011 2 8 10" it) Gate C-6 H-26020 HPCI Pump Redun. C Note 14 NA No Shutoff to Cond. Stg.
2E41-F012 2 A 4" M0 Gate F-6 H-26020 HPCI Pump Min. Flow C Qtr CIV Yes 6.1.2
' Inbrd. Iso 2E41-F019 2 C 16" Check 0-7 H-26020 HPCI Pump Suc. C Note 5 NA No from Cond. Stg.
2E41-F021 2 AC 12" Stop Check G-3 H-26020 HPCI Turb. Exh. C See 6.1.12 CIV No 6.1.11 Inbrd. Iso 6.1.I2 i
)
l 4
o O O SYSTEM: High Pressure Coolant Injection Plant Hatch - Unit 2 Valve Testing Program Sh.18 of 43 Valve Code Stroke Class Norm
, No. Cat Description Coord. PAID Function Time Relief i Pos Exercise Leakage Req'd Request 2E41-F022 2 AC 2" Stop Check G-3 H-26020
! HPCI Turb. Exh. C See 6.1.12 CIV No 6.1.11 Orn. Torus Iso
'; 2E41-F040 2 AC 2" Check G-4 H-26020 HPCI Turb. Exh. C See 6.1.12 CIV Drn. Torus Iso No 6.1.12 2E41 -F041 2 B 16" M0 Gate D-7 H-26020
+
HPCI Pump Suc. C Qtr NA Yes Shutoff 2E41-F042 2 A 16" H0 Gate H-4 H-26020 HPCI Pump Suc. C Qtr CIV Yes Torus Outbrd. Iso 2E41-F045 2 C 16" Check H-5 H-26020 HPCI Pump Suction C See 6.1.13 NA No 6.1.13 2E41-F046 2 AC 4" Check F-6 H-26020 HPCI Pump Min Flow j C Note 5 CIV No Outbrd. Iso 2E41-F049 2 AC 20" Check G-4 H-26020 HPCI Turb. Exh. C See 6.1.12 CIV No 6.1.12 Outbrd. Iso l 2E41-F051 2 A 16" A0 Bfly H-4 H-26020 j HPCI Pump suc. O Ctr CIV Yes i Torus Irabre. Iso 2E41-F059 2 B 2" H0 Globe F-7 H-26020 HPCI Turb. Lube Oil C Qtr NA Yes Cooling 2E41-F104 2 A 2" H0 Gate F-2 H-26020 HPCI Vac, Relief 0 Qtr CIV Yes Outbrd. Torus Iso 1 2E41-F111 2 A 2" M0 Gate G-1 H-26020 HPCI Vac. Reifef 0 Qtr CIV Yes Inbrd. Torus Iso a
O O O SYSTEM: Reactor Coolant Isolation Cooling Plant Hatch - Unit 2 Valve Testing Program Sh. 19 of 43 i
- Valve Code Stroke Norm Relief No. Class Cat Description Coord. PAID Function Pos Exercise Time Leakage Req'd Request 2E51-F001 2 AC 10" Stop Check G-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 G-5 H-26023 RCIC Vac Pump C See 6.1.12 CIV No 6.1.11 Disch. to Torus Iso 6.1.12 2E51-F003 2 A 6" A0 Bfly H-6 H-26023 RCIC Pump Suction 0 Qtr CIV Yes 6.1.2 Torus Iso 2E51-F007 1 A 4" M0 Gate C-5 H-26023 RCIC Steam Supply 0 Qtr CIV Yes 6.1.2 Inbrd. Iso 2E51-F008 1 A 4" M0 Gate C-6 H-26023 RCIC Steam Supply 0 Qtr CIV Yes Outbrd Iso 2E51-F013 2 A 4" M0 Gate D-6 H-26023 RCIC Feedwater Inj. C Qtr PIV Yes
?E51-F019 2 A 2* M0 Globe E-7 H-26023 RCIC Pump Min. Flow C Note 8 CIV No 6.1.2
. Torus Iso 2E51 -f021 2 AC 2" Check E-7 H-26023 RCIC Pump Min. Flow C Note 5 CIV No Torus Iso 2E51-F028 2 AC 2" Check F-7 H-2602.3 RCIC Vac. Pump Disch. C j See 6.1.12 CIV No 6.1.12 Torus Iso 2E51-F031 2 A 6" M0 Gate H-6 H-26023 RCIC Pump Suction 0 Qtr CIV Yes
, Torus Iso 2E51-F040 AC AC 10" Check F-5 H-26023 i RCIC Turb. Exh. C See 6.1.12 CIV Yes 6.1.12 Torus Iso 2E51-F10% 2 A 1-1/2" M0 Gate F-5 H-26023 RCIC Vac. Brker 0 Qtr CIV Yes Torus Iso 2E51-F105 2 A 1-1/2" M0 Gate F-4 H-26023 i
RCIC Vac. Brter 0 Qtr CIV Yes 6.1.2 Torus Iso I
i i
- - . - . - - __ . - - . = .
i O O O I SYSTEH: Radwaste Plant Hatch - Unit 2 Valve Testing Program Sh. 20 of 43 Valve Code Stroke i Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request 2Gil-F003 2 A 3" A0 Gate B-3 H-26026 DW Fir. Drns. O Qtr CIV Yes Cont. Iso 2Gil-F004 i A 3" A0 Gate' B-4 H-26026 DW Fir. Drns.
j O Qtr CIV Yes Cont. Iso i 2Gil-F019 2 A 3" A0 Gate E-4 H-26026 DW Equip. Drns.
O Qtr CIV Yes
. Cont. Iso
{ 2Gil-F020 2 A 3" A0 Gate E-4 H-26026 DW Equip. Drns. O Qtr CIV Yes j Cont. Iso 2Gil-F852 2 AE l-1/2" Man Gate E-Il H-26026 Chen, drains LC Note 1 CIV No i Cont. Iso 2G11-F853 2 AE l-1/2" Man Gate D-ll H-26026 Chem. drains LC Note 1 CIV No Cont. Iso i
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1 O O O SYSTEM: Reactor Water Cleant(p Plant Hatch - Unit 2 Valve Testing Program Sh. 21 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Request
! 2G31-F001 1 A 6' N0 Gate C-2 H-26036 RWCU Pump Suc. O Qtr Civ Yes i Inbrd. Iso i
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O O O
)
SYSTEM: Fuel Pool Cooling'and Cleanup Plant Hatch - Unit 2 Valve Testing Program Sh. 22 of 43 i
Valve Code Stroke Norm Time Relief l No. Class Cat Description Coord. PAID Function Fos Exercise Leakage Req'd Request j 2G41-F017 3 8 6" Man Gate G-1 H-26039 Fuel Pool Cooling C Qtr NA No i
RHR Intertie i 2G41-F019 3 8 6" Man Bfly G-2 H-26039 Fuel Pool Cooling 0 Qtr NA No RHR Intertie 2G41-F033 3 8 6" Man Bfly E-11 H-26039 Fuel Pool Cooling 0 Qtr NA No RHR Intertie 2G41-F034 3 0 6" Man Gate E-Il H-26039 Fuel Pool Cooling C Qtr NA No RHR Intertie f
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O O O SYSTEM: Torus Drainage and Purification System Plant Hatch - Unit 2 Valve Testing Program Sh. 23 of 43 i
Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. P81D Function Pos Exercise Leakage Req'd Request j
i j 2G51-F002 2 AE 8" Man Gate D-4 H-26042 Torus Drain and LC Note 1 CIV Ho Purif. Cont. Iso l 2G51-F011 2 AE 3" A0 Control C-5 ?l-26042 Torus Drain and LO Qtr CIV Yes Purif. Cont. Iso
Purif. Cont. Iso I
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. _ . _ _ - _ _. m.....
l O O O :
! SYSTEM: Demineralized Water Plant Hatch - Unit 2 Valve Testing Program Sh. 24 of 43 Stroke Valve Code Norm Time Relief I Class Cat Description Coord. P8ID Function Pos Exercise Leakage Req'd Request No.
1 2P21-F032 2 AE 2* Manual Gate F-2 H-26047 Demin. Water LC Note 1 CIV No Cont. Iso l l
2P21-F034 2 AE 2' Manual Gate F-2 H-26047 Domin. Water LC Note 1 CIV No Cont. Iso i
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O O O SYSTEM: H2 and 02 Analyzer Plant Hatch - Unit 2 Valve Testing Program Sh. 25 of 43 Stroke Valve Code Norm Time Relief
, No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request ,
2P33-F002 2 A 1" A0 Control B-4 H-26048 H2 & Q Analy. O Qtr CIV Yes
. Cont. Iso 2P33-F003 2 A 1" A0 Control C-4 H-26048 H2 &02 Analy. O Qtr CIV Yes Cont. Iso l
2P33-F004 2 A l' A0 Control D-4 H-26048 H2 &02 Analy. O Qtr CIV Yes Cont. Iso 2P33-F005 2 A l' A0 Control E-4 H-26048 H2 &02 Analy. O Qtr CIV Yes Cont. Iso 2P33-F006 2 A 1" A0 Control F-4 H-26040 H2 &02 Analy. O Qtr CIV Ves Cont. Iso i
. 2P33-F010 2 A 1" A0 Control b-5 H-26018 H2 & 04 Analy. O Qtr CIV Yes Cont. Iso 2P33-F011 2 A 1" A0 Control C-5 H-26D48 H2 802 Analy. O Qtr CIV Yes i Cont. 150 i 2P33-F012 2 A 1" A0 Control D-5 H-26048 H2 802 Analy. O Qtr CIV Yes Cont. Iso
- 2P33-F013 2 A 1" A0 Control E-5 H-26048 H2 &02 Analy. O Qtr CIV Yes Cont. Iso 1 2P33-F014 2 A 1" A0 Control F-5 H-26048 H2 &02 Analy. O Qtr CIV Yes Cont. Iso 2P33-F015 2 A 1" A0 Control H-5 H-26048 H2 &02 Analy. 0 Qtr CIV Yes l Cont. Iso
+
r 1
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. -_-_. . - - - - .- - . - - . . . - . .-. .- - . .~
O o u O Plant Hatch - Unit 2 Valve Testing Program Sh. 26 of 43 SYSTEM: Plant Service Water Stroke Norm Time Relief Valve Code Exercise Leakage Req'd Reouest Class Cat Description Coord. PalD Function Pos No.
HP"! Pump Room Cooler C See 6.1.14 NA No 6.1.14 1-1/2" Check D-4 H-26051 2P41-F024A 3 C HPCI Pump Room Cooler C See 6.1.14 NA Na 6.1.14 1-1/2" Check 0-5 H-26051 2P41-F024B 3 C RHR & CS Pump Room C See 6.1.14 MA No 6.1.14 3" Check D-6 H-26051 2P41-F025A 3 C Cooler f
RHR & CS Pump Room C See 6.1.14 NA No 5.1.14 3* Check D-6 H-26051 2P41-F0258 3 C Cooler RHR Pump Cooler C See 6.1.14 NA No 6.1.14 2P41-F026A 3 C 3" Check C-3 H-26050 H-26050 RHR Pump Cooler C See 6.1.14 NA No 6.1.!4 2P41-F0268 3 C 3" Check C-9 RCIC Pump Room C See 6.1.14 NA No 6.1.14 2P41-F028A 3 C 1-1/2" Check C-5 H-26050 Cooler 1
RCIC Pump Room C See 6.1.14 NA No 6.1.14 2P41-F028B 3 C 1-1/2" Check C-4 H-26050 Cooler HPCI Pump Room C Qtr NA Yes 6.1.15 2P41-F035A 3 8 2" A0 Globe C-4 H-26051 Cooler HPCI Pump Room C Ctr NA Yes 6.1.15 2" A0 Globe C-5 H-26051 4
2P41-F0358 3 B Cooler RHR & CS Pump C atr NA Yes 6.1.15 2P41-F036A 3 8 3" A0 Globe C-5 H-26051 Room Cooler I
RitR & CS Pump C Qtr HA ves 6.1.15 2P41-F0368 3 8 3" A0 Globe C-6 H-26051 Room Cooler 1
J 4
4
- __ . - - _- .-- . . ~ . . .
O O O SYSTEM: Plant Service Water Plant Hatch - Unit 2 Valve Testing Program Sh. 27 of 43 Stroke Valve Code Norm Tine Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Req'd Request 2P41-F037A 3 8 1-1/2" A0 Globe D-7 H-26050 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F0378 3 b 1-1/2" A0 Globe C-9 H-26051 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F037C 3 8 1-1/2" A0 Globe D-3 H-26050 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F037D 3 B 1-1/2" A0 Globe C-8 H-26051 RHR Pump Cooler C Qtr NA Yes 6.1.15 2P41-F039A 3 8 3* A0 Globe D-9 H-26050 RHR Pump Cooler C Qtr HA Yes 6.1.15 t 2P41-F0398 3 8 3" A0 Globe D-9 H-26050 .RHR Pump Cooler C Qtr NA Yes 6.1.15 ,
2P41-F040A 3 B 2" A0 Globe D-5 H-26050 RCIC Pump Room C Qtr NA Yes 6.1.15 Cooler 2P41-F0408 3 8 2" A0 Globe D-5 H-20050 RCIC Pump Room C Qtr NA Yes 6.1.15 Cooler l 2P41-F042A 3 B 3" A0 Globe C-2 H-26051 CRD Pump Room 0 Qtr NA Yes 6.1.15 Cooler i
2P41-F0428 3 B 3" A0 Globe C-3 H-26051 CRD Pump Room 0 Qtr NA Yes 6.1.15 Cooler 2P41-F096A 3 8 8* A0 Bfly E-4 H-26050 Drywell O CS NA Yes 6.1.16 Cooler 2P41-F0%8 3 B 8" A0 Bfly E-2 H-26050 Drywell O CS NA Yes 6.1.16 Cooler 2P41-F315A 3 8 10" M0 Bfly A-9 H-21033 S.V. to Reactor LO Note 15 NA No Bldg. Shutoff 2P41-F3158 3 8 10" M0 Bfly F-9 H-21033 S.W. to Reactor LO Hote 15 NA No Bldg. Shutoff i
4
. _ _ _ . . _ _,_ m D
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- s. Q SYSTEH: Plant Service Water Plant Hatch - Unit 2 Valve Testing Program Sh. 28 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PAIO Func tion Pos Extecise Leakage Req'd Request 2P41-F316A 3 B 30" M0 Bfly A-9 H-21033 S.W. to Turbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-F3168 3 8 30" M0 Bfly F-9 H-21033 S.W. to Turbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-F316C 3 8 30* M0 Bfly A-10 H-21033 S.W. to Turbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-F3160 3 8 30" M0 Bfly F-10 H-21033 S.W. to Turbine O CS NA Yes 6.1.17 Bldg. Shutoff 2P41-F319A 3 8 1" Solenoid B-1 H-21033 S.W. Pump Cooling 0 Note 7 H% No Water Shutoff 2P41-F319B 3 8 1" Solenoid C-1 H-21033 S.W. Pump Cooling 0 Note 7 NA Ho Water Shutoff 2P41-F319C 3 8 1" Solenoid E-1 H-21033 S.W. Pump Cooling 0 Note 7 HA No Water Shutoff 2P41-F3190 3 8 1" Solenoid G-1 H-21033 5.W. Fump Cooling 0 Note 7 RA No
' Water Shutoff 1
i 2P41-F320% 3 B 3" A0 PCV A-3 H-21033 S.W. Pump Hin. Flow C Note 9 NA No 2P41-F3208 3 8 3" A0 PCV C-3 H-21033 S.W. Pump liin. Flow C Note 9 NA No 2P41-F320C 3 B 3* A0 PCV E-3 H-21033 S.W. Pump Min. Flow C Note 9 NA No i 2P41-F3200 3 B 3" A0 PCV F-3 H-21033 S.W. Pump flin. Flow C Note 9 N4 No a
4 l
_ . _ _ _ .__ -- - _ _ ._. _~ __
I l O O O SYSTEM: Plant Service Water Plant Hatch - Unit 2 Valve Testing Program Sh. 29 of $3 '
Stroke Valve Code Norm Time Reitef
- No. Class Cat Description Coord. P810 Function Pos Exercise Leakage Req'd Request i
{ 2P41-F334A 3 8 l' A0 PCV C-7 H-21033 S.W. Pump Cooling -
Note 9 NA No Water Press. Reg.
2P41-F3348 3 B 1" A0 PCV G-1 H-21033 S.W. Pump Cooling -
Note 9 NA No Water Press. Reg.
l 2P41-F339A 3 8 6" A0 Bfly H-9 H-21033 Diesel Gen. Cooling C Qtr NA Yes 6.1.15 I 2P41-F3398 3 B 6" A0 Bfly H-7 H-21033 Diesel Gen. Cooling C Qtr NA Yes 5.1.15 i
2P41-F340 3 8 6" A0 Bfly H-5 H-21033 Diesel Gen. Cooling C Qtr NA Yes 5.1.15 i i
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! SYSTEM: RB Closed Cooling Water Plant Hatch - Unit 2 Valve Testing Program Sh. 30 of 43 l
{
i Valve Code 3troke Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request
! 2P42-F052 2 A 6" M0 Gate C-5 H-26055 RBCCW to Recir. O CS CIV Yes 6.1.18 l Cont. Iso 1
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I i O O O i
i Plant Hatch - Unit 2 Valve Testing Program SYSTEM: Service Air Sh. 31 of 43 1
i Stroke f
Valve Code Norm Time Re11ef
! No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request i
i 2P51-F513 2 AE 2" Man. Globe F-3 H-26058 Ser. Air Cont. Iso LC Note 1 CIV No i
2P51-F651 2 AE 2" Man. Globe F-3 H-26058 Ser. Air Cont. Iso LC Note 1 CIV No 4
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O O SYSTEM: Chilled Water System Plant Hatch - Unit 2 Valve Testing Program Sh. 32 of 43
., Stroke i Valve Code Norm Time Relief No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Req'd Request 2P64-F045 2 A 6' M0 Globe G-11 H-26081 Chilled Water 0 CS CIV Yes 6.1.16 Cont. Iso 2P64-F047 2 A 6" M0 Globe G-8 H-26081 Chilled Water 0 CS CIV Yes 6.1.16 Cont. Iso 4
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. . - _ _= _ . - . _ _ _
SYSTEM: Drywell Pneumatic Plant Hatch - Unit 2 Valve Testing Program Sh. 33 of 43 Valve Code Stroke Norm
- No. Class Cat Description Coord. PAID Function Time Relief i Pos Exercise Leakage Req'd Request
! 2P70-F002 2 A l' A0 Control F-8 H-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso i
2P70-F003 2 A 1" A0 Control F-8 H-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso I
2P70-F004 2 A 2" A0 Control C-7 H-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso
'; 2P70-F005 2 A 2" A0 Control D-7 H-26066 DW Pneumatic Cont. O Qtr CIV Yes Iso 2P70-F020 2 AC 2" Check C-6 H-26066 DW Pneumatic Cont. O R0 CIV Iso No 6.1.1 i
i i
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4 6
4
~ _ _ - ._ . _ _ _ _ _ . ._ _ _ . . _ . _ _ _ __ __ _ . _ . .
- O O O .
SYSTEM: ILRT i Plant Hatch Unit 2 Valve Testing Program Sh. 34 of 43
- l I Stroke -
Valve Code Norm '
No. Class Cat Description Time Relief Coord. PdID Function Pos Exercise Leakage Req'd Request '
2T23-F004 2 A 3/4" Man. Globe D-3 H-26057 ILRT Cont. Iso C Note 1 CIV No 2T23-F005 2 A 3/4" Man. Globe D-3 H-26057 ILRT Cont. Iso C Note 1 CIV No
- ?
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. . - - - . - . . . _ _ . _= . - - .. . .- __ .._ _ . _ -_ . - .
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O O O SYSTEM: Fire Protection Plant Hatch Unit 2 Valve Testing Program Sh. 35 of 43 Valve Code Stroke Norm Time Relief
- No. Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request i 2T43-F159 2 AC 3* Check F-5 H-21017 Fire Protection C Note 1 CIV No l Cont. Iso ,
2T43-F160 2 AE 3" Man. Gate F-5 H-21017 Fire Protection LC Note 1 CIV No
]
4 Cont. Iso i
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. O O O SYSTEM: Standby Gas Treatment Plant Hatch Unit 2 Valve Testing Program Sh. 36 of 43 Stroke Valve Code Nore Time Relief No. Class Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Request 2T46-F001A 3 B 18" A0 Bfly C-2 H-26078 Filter Bed Inlet C Qtr NA Yes from Reactor B1dg.
, 2T46-F001B 3 B 18" A0 Bfly G-2 H-26078 Filter Bed Inlet C Qtr NA Yes
- from Reactor Bldg.
2T46-F002A 3 B 18" A0 Bfly C-5 H-26078 SGTS Filter C Qte NA Yes Bed Outlet
, 2T46-F0028 3 8 18" A0 Bfly G-5 H-26078 SGTS Filter C Qtr NA Yes i Bed Outlet 2T46-F003A 3 B 18" A0 Bfly C-2 H-26078 SGTS Filter C Qtr NA Yes Bed Inlet from Refuel Floor 2T46-F003B 3 B 18" A0 Bfly G-2 H-26078 SGTS Filter C Qtr NA Yes
! Bed Inlet from i Refuel Floor i
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O O O SYSTEM: Containment Purge and Inerti g Plant Hatch Unit 2 Valve Testing Program - Sh. 37 of 43 Stroke Valve Code Norm Time Relief No. Class Cat Description Coord. PAID Function Pos Exercise Leakage Req'd Request 2T48-F103 2 A 6" A0 Bfly , D-10 H-26083 DW & Torus Supply - C Qtr CIV Yes Iso ,
/ ,
2T48-F104 2 A 1*.A0 Control G-4 H-26083 Dwg & Torus C Qtr CIV 'Yes j
- Iso 2T48-Fil4 2 A 2" A0 Control H-9 H-26083 DWInertingInbef .C Qtr '
CIV Yes Iso ,
3 2T48-F115 2 A 2" A0 Control G-10 H-26083 DW Inerting Outbrd C- Qtr CIV Yes Iso .- ,
2T48-F116 2 fA 2" ,80 Control H-10 H-26083 DW Inerting Outbrd C - Qtr CIV Yes Iso ,
. u 2T48-F118A 2 A ~1" Solenoid 3-4 H-26083 1- brus Nkeup > + ) 0. Qtr CIV -
- Yes
/
- Ltard Iso ,
l 2T48-F1138 2 A '1* Solenoid J-5 < H-26083 Torus Nkeup 0 Qtr CIV Yes
' i Inbrd Iso -
l.Fi48-F321 2 A 2" A0 Control G-7 , N 6083 DW Inerting C Qtr CIV Yes Outbrd. Iso
?
2-
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2T48-F322 2 A 2" A0 Control H-7 , H-26083 DW Inerting C Qtr . C!V Yes O
) ~
Inked. Iso ;
l 2T48-F325 2 A '2" Ao Control G-8;* H-26033 Torus Inerting C Qtr CIV Yes
) . Outbrd. Iso 2TG-F327 2 A 2" A0 Control H-8 H-26083 Torus Inerting C Qtr CIV Yes Inbrd. Iso 4 .
- 4' .-
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SYSTC4: Containment Purge and Inerting d Plant Hatch Unr12 YAve Testing Program f g Sh. 38 of'43 , ?
~ s fd
- . - Stroke Valve Code j Norm Time Relief
- No. Class Cat Description Coord. P81D < yunction Pos Exercise Leakage Req'd Regrast - g ,
i . e
}" ,
2T48-F307 2 A 18" A0 Bfly C-9 H-26084 DW Purp Inlet C Note 1 -M/ No e# > s Lebed 33o ', :
g# , + t + 1
-f 2T48-P08 2 g A .e. g 73" A0 Bfly C-10 H-26D84 . s?W Pwge,'tt,let C Note 1 ClV ,i No .
e 5 , . ,
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y 5 2T43-F32. I '* A 18" A0 Bfly E-10
'n-?6094 . <- ' brus Ny C Note 1 CIV No' ' #.i.
- 1 ,Irn'.s "bbrd Iso ff , ,,
., 2T48-F'M0j '*1 A . 20" A0 Bfly F-10 H-2608% ThusPurgeVac. C Qtr ,
CIV Yes l," -? " # \
g g ,
Brker Iso i, ,- ' j '
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f 2T48-F311 2 A 20" A0 Bfly F-9 H-26034. Torus Purge Vac. C Qtr CIV Yes i. . p
, f Brker Iso i
2T48-F318 2 AL 18" A0 Bfly G-4 H-26081 Torus Purge 0 Qtr ' CIV Yes Outlet Inbrd Iso ' -
2T48-F319 2 A 18" A0 Bfly C-4 E-26084 DW Purge C Note l' CIV Yes Outlet Inbrd Iso 2T48-F220 2 A 18" A0 Bfly C-3 H-26034 DW Purge Outlet C Note 1 CIV No Outbr4 Iso 2T48-F323A 2 C 18" A0 Check G-8 H-26084 DW to Torus Vac. C Qtr NA No Bresier 2T48-F323B 2 C 18" A0 Check G-8 .H-26084 DW to Torus Vac. C Qtr NA No Breaker 2T48-F323C 2 C 18" A0 Check G-8 H-26084 DW to Torus Vac. C Qtr NA No Breaker 2T48-F3230 2 C 18" A0 Check G-8 H-26084 DW to Torus Vac. C Qte NA No Breaker 2T48-F323E 2 C 18" A0 Check G-8 H-26084 DW to Torus Yac. C Qtr NA No Breaker
~ .
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d SYSTEM: Containment Purge and Inerting Plant Hatch Unit 2 Valve Testing Program Sh.[M cf 43
. - ~c $
Stroke Valve Code --
s Nom Time Reifef No. Class Cat Tescription i Coord. P810 Fur.c tf N Pos Exercise Leakage Req'd Re p 2T48-F223F 2 C 18* A0 theck , ' G-8 H-26084 DW to Torus Yac. C Qtr NA No
,_ r Breaker t 2T48-F323G 2 C
18" Ai) CMcK' G-8 H-26084 DW to Torus Yac. C Qtr NA No i Breaker e, ~
a p
2748-F323H 2 C 18" A0 Check 6-8 et-26084 DW to Torus Vac. C Qtr NA No Breaker l q 2T48-F3231 2 C 18" A0 Cf.eck "3:8- H-26084 DW to Torus Yac. C Qtr NA No
- Breaker t
2T48-F 323J 2 C 18" A0 Cheet -G-8 H-26084 DW to Torus Vac. C Qte NA No
- Brcsker '
2T40-F323K 2 C 18" A0 Check G-8 H-26084 DW to Torus Vac. C Qtr NA No l
_ Breaker -
2T48-F323L 2 C 18" AO Lheck G-8 H-260M DW to Torus Vac. C Qtr NA No Breaker j 2T48-F324 2 A 18" A0 Bfly. D-10 H-26084 Torus Purge C Note 1 CIV No i
Inlet Dutbrd. Iso 1
j 2T48-F326 2 A 18" A0 Bfly G-3 H-26081 Torus Purge CIV ' Ye:.
C Qtr _.s -
l Outlet Outbrd. Iso 2T48-F328A 2 AC 20" A0 Check G-10 H-26084 Reactor Bldg. to 0 Qtr CIV No
. Suppression
, ' ' Cham Vac. Brker 2T48-F3288 2 AC 20" A0 Check G H-26084 Reactor Bldg. to C Qtr CIV No Suppression
] ~.
Cham Vac. Brker K
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SYSTEM: Containment Purge and Inerting Plant Hatch Unit 2 Valve Testing Progree Sh. 40 of 43 Stroke 4
Valve Code No. Class Cat Description Norm Tfw Relief Coord. P&ID Function Pos Exercise Leakage Req'd Request 2T48-F332A 2 A 2" A0 Control E-3 H-26084 Torus Purge C Qtr CIV Yes Outlet Outbrd Iso 2T48-F332B 2 A 2" A0 Control G-3 H-26084 Torus Purge C Qtr CIV Yes Outlet Outbrd Iso 2T48-F333A 2 A 2" A0 Control E-4 H-26084 Torus Purge C Qtr CIV Yes Outlet Inbrd Iso 2T48-F333B 2 A 2" A0 Control G-4 H-26084 Torus Purge C Qtr CIV Yes Outlet Inbrd Iso
) 2T48-F334A 2 A 2" A0 Control B-3 H-26084 DW Purge Outlet C Qtr CIV Yes Outbrd Iso 2T48-F3348 2 A 2" A0 Control C-3 H-26084 DW Purge Outlet C Qtr CIV Yes
\ Outbrd Iso 2T48-F335A 2 A 2" A0 Control B-4 H-26084 DW Purge Outlet C Qtr CIV Ye:;
1 Inbrd Iso 2T48-F1358 2 A 2" A0 Control C-4 H-26084 DW Purge Outlet C Qtr CIV Yes Inbrd Iso l 2T48-F338 2 A 2" Diaphrage H-2 H-26084 Bypass-Outbrd Iso C Qtr CIV Yes
- 2T48-F339 2 A 2" Diaphrage H-3 H-26084 Bypass-Inbrd Iso C Qtr CIV Yes j 2T48-F340 2 A 2" Solenoid D-2 H-26094 Bypass-Outbrd Iso C Qtr CIV Yes 2T48-F341 2 A 2" Solenoid E-4 H-26084 Bypass-Inbrd Iso C Qtr CIV Yes e
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2 O O O SYSTEN: Containment P'Jrge and Inerting Plant Hatch Unit 2 Valve Testing Program Sh. 41 of 43
$troke Valve Code Norm Time Relief No. Clas? Cat Description Coord. PalD Function Pos Exercise Leakage Req'd Reauest 2T48-F342A 2 A 1/2" Solenotd H-8 H-26084 Torus to DW Vac C Note 12 ClY No Breaker Iso 2T43-F342B 2 A 1/2" Solenoid H-8 H-260d4 Torus to DW Yac C Note 12 CIV No Breaker Iso 2T48-F342C 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Yac C Note 12 CIV No Breaker Iso 2Ta8-F342D 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Vac C Note 12 ClY No Breaker Iso 2T48-F342E 2 A 1/2* Solenoid H-8 H-26084 Torus to DW Vac C Note 12 CIV No Breaker Iso 2T48-F342F 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Vac C Note 12 CIV No I Breaker Iso -
2T48-F342G 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Yac C Note 12 ClY No Breaker Iso 2T48-F342H 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Yac C Note 12 CIV No Breaker Iso 2T48-F342I 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Yac C Note 12 CIV No Breaker Iso 2T48-F342J 2 A 1/2" Solenold H-8 H-26084 Torus to DW Vac C Note 12 CIV No
( Breaker Iso I
2T48-F342K 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Vac C Note 12 CIV No
- Breaker Iso 2T43-F3a2L 2 A 1/2" Solenoid H-8 H-26084 Torus to DW Yac C Note 12 CIV No Breaker 150 i
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t O O O SYSTEH: Containment Purge and Inerting Plant Hatch Unit 2 Valve Testing Program Sh. 42 of 43 Stroke Valve Code Noru No. Class Cat Description Coord.
Time Relief P&ID Function Pos Exercise Leakage Req'd Request 2T48-F361A 2 A 1" A0 Control G-9 H-26084 Torus Water 0 Qtr CIV Yes Level Iso 2T48-F3618 2 A 1" A0 Control G-5 H-26034 Torus Water 0 Qtr CIV Yes Level Iso 2T48-F362A 2 A 1" A0 Control H-9 H-26084 Torus Water 0 Qtr CIV Yes Level Iso j 2T48-F3628 2 A 1" A0 Control H-5 H-26084 Torus Water 0 i
Qtr CIV Yes 4
Level Iso 2T48-F363A 2 A 1" A0 Control E-8 H-26084 Press. Transmitter 0 Qtr CIV Yes a
Iso
, 2T48-F3638 2 A 1" A0 Control D-6 H-26004 Press. Transmitter 0 Qtr CIV Yes Iso l 2T48-F364A 2 A 1" A0 Control G-8 H-26084 Press. Transmitter 0 Qtr CIV Yes Iso 4
2T48-F3648 2 A 1" A0 Control G-5 H-26079 Press. 7eansmitter 0 Qtr CIV Yet 1so 2T48-F209 2 A 4" A0 Gate C-9 H-26079 DW TorusAP Iso 0 Qtr CIV Yes j 2T48-F210 2 A 4" A0 Cate C-9 H-26079 DW TorusAP Iso 0 Qtr CIV Yes 2T48-F211 2 A 4" A0 Gate E-8 H-26079 DW TorusAP Iso 0 Qtr CIV Yes j 2T48-F212 2 A 4" A0 Gate E-8 H-26079 OW TorusAP Iso 0 Qtr CIV Yes l
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, O O O SYSTEM: Containmenit Purge and Inerting Plant Hatch Unit 2 Valve Testing Program Sh. 43 of 43 Stroke Valve Code Nem Time neller
& Class Cat Description Coord. P&ID Function Pos Exercise Leakage Reg'd Request 2T49-F001A, 2 8 4" M0 Gate C-3 H-26028 Hg Recoe. H2 C Qtr NA Yes B from DW Shutoff 2T49-F002A, 2 A 4" M0 Cate C-4 H-26328 H2 Recomb. H2 C Qtr CIV Yes B from DW Iso
, 2T49-F003A, 2 B 3* Flow Control C-5 H-26018 H7 Recoub. H2 C Note 9 NA No B from DW Shutoff 2T49-F004A, 2 A 4" M0 Gate F-5 H-26028 H2 Recomb. Gas C Qtr CIV Yes B and Water Iso 2T49-F005A, 2 8 4" M0 Gate F-4 H-26029 H2 Recomb. Gas C Qtr NA Yes B and Water Iso 2T49-F006A 2 8 3/4" M0 Globe H-5 H-26028 H2 Recne6. Water C Qtr NA Yes
- B ' Feed f
- -on RHR 4
2T49-F007A 2 8 3/4" M0 Globe H-8 H-26028 H2 Recono. Water 0 Qtr NA Yes B Feed from RHR 2T49-F0084 2 8 3" H0 Globe D-7 H-26028 H2 Recomb. O Qtr N?. Yes B Flow Control I 2T49-F009A 2 AC 1-1/2" Relief F-4 H-26028 Relief Valve C Note 3 CIV No j B Cont. Iso 1
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Class 1, 2, and 3 Valve Testing Program Notes O
- 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 nonna11y 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 IW-3511. The opening pressure will be detennined per the requirements of ASE PTC 25.3-1976 ,
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- 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 IW.
- 5. The opening function of this normally closed check valve is proven every 3 months during pump operability testing. Design flow will be passed through i
the valve.
- 6. This valve is a pressure or flow regulating valve that modulates. This valve is exempt from testing per the requirements of IW-1200(a).
- 7. This fail-open solenoid valve will be removed per a design change in a future outage. In the interim, the power to the valve will be removed and the O valve left in the open position. As a result the valve is not important to safety.
- 8. This valve is a minimum flow valve that opens and closes at set pressures. This valve is exempt from testing per IW-1200(a). However, operability is proven during pump tests.
- 9. This valve is an A0 pressure control valve that opens and closes at set pressures. This valve is exempt from testing per IW-1200(a). However, the operability of the valve is shown during pump tests.
- 10. This valve is a self-modulating pressure control valve that is exempt from testing per IW-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 T43-F323A-L (or 2T48-F323A-L) and has no safety related function.
- 13. This normally-open feedwater check valve has an air assist' for tight closure and position indicating lights. Closure will be proven each cold Q shutdown, but not more frequent than once per 3 months, by observing the indicating lights.
m-- - p 4-amy, ,igmm-ew ey i-n-- ----e- --e-q. .,,,-__,-ww my,yww-e------.y-reyy n -e----wwwg.w -.wam-wwa ww e y ..ymom,i-yggmywem.y *mumpmy7y- -y-w gwweeg---- - - -+m --g-P-y"v--me---
.. . _ _ _ _ _. ._ . _ _ - - _ _ - _ _ _ _ = . - _ .
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- 14. This normally closed valve is opened during testing only; therefore, it is passive and does not require testing.
Q 15. This valve is locked open and has no safety related function requiring stroking the valve.
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i 6.1 Relief Requests for Class 1, 2, and 3 Valves l
Test Requirement '
6.1.1 l
O IW-3521 requires that check valves be exercised at least once per 3 months. l 2
- 6.1.1.1 Basis for Relief 1
This containment isolation valve is normally open with design flow passing i through it during normal operation. The only practical method of verifying j clasure is to introduce reverse flow through the valve and measure leakage.
6.1.1.2 Alternate Testing This verification is performed each refueling outage during local leak rate i testing.
6.1.2 Test Requirement IW-3423d 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.
t 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 test program for the type C leakage tests.
6.1.3 Test Requirement IW-3521 requires that check valves be exercised at least once per 3 months.
6.1.3'.1 Basis for Relief l This valve is designed to prevent a water leg from forming in the relief line discharge ifne 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 refuelfr.g outage (when the containment is de-inerted) the movement of the disc will be observed to see that it moves freely.
6.1.4 Test Requirement Q
IW-3411 requires that valves be exercised at least once per 3 months.
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.n. - - - - - - - . , , - . . - . . , _ - . - - - . ~ , - _ . . . - . - - - - - . . . - - . . _ . , _ _ . . _ . _ _ _ . - _ , , . - - - - - . - . , - - . - - - _ - - . - - - _ , , .
6.1. 4.1 Basis fer 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 O partial stroking of the valve.
6.1.4.2 Alternate Testing This valve will be tested each cold shutdown but not more frequently than once per 3 months.
6.1.5 Test Requirement IW-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 Inis valve is achieved once per 18 months due to the requirements of the Technical Specifications.
6.1.6 Test Requirement Q IW-3521 requires that check valves be exercised at least once per 3 months and IW-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 tores 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 i is sealed from the primary containment atmosphere because the test line i
terminates below the water level of the torus and the leakage is not included l in the type C local leak rate testing.
6.1.6.2 Alternate Testing The integrated leak rate test will prove that leakage through the valve and l closed system does not occur. There are no other practical means of testing this check valve.
6.1.7 Test Requirements IW-3521 requires that check valves be exercised at least once per 3 months.
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6.1.7.1 Basis for Relief These normally closed check valves do riot receive " full-open" flow during normal operation or shutdown conditions. There has been no practical method O demonstrated to fully stroke these valves.
6.1.7.2 Alternate Testing 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 valves will be partially stroked once per 3 months.
i At least one of the RHR system check valves will receive shutdown cooling flow through it during cold shutdown conditions; however, the flow is not sufficient to fully open the valve.
Valve integrity will be proven during leak rate tests each refueling outage because tests. this valve is a pressure isolation valve and must pass the leakage One of the two valves in the system will be disassembled on a rotating basis every other refueling outage. If the valve is determined 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 Q IW-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 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 IW-3417(a) states that if an increase in stroke time of 25% or more from the previous test for valves with stroke ties 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.
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6.1. 9.1 Basis for Relief Valves that are normally tested during cold shutdown or refueling cannot be N tested once each month. Stroking these valves during power operation may (d place the plant in an unsafe condition.
6.1.9.2 Alternate Testing These valves will be stroked every cold shutdown but not more frequently than
^
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. Yalve 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 O IWv-3423 requires tnat vaives be ieek tested witn tne pressure differentiei 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 valvo.
6.1.12 Test Requirement IWV-3521 requires that check valycs be exercised every 3 months.
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6.1.12.1 Basis for Relief Check valves E51-F001, E51-F002. E51-F028, E51-F040 E41-F021, E41-F022, O E41-F040 and E41-F049 are locatea on the RCIC or HeCI turbine steam exhaust lines. During quarterly pump testing these valves are partially stroked during system operation; however, test conditions do not provide sufficient flow to prove that the valves are fully open.
6.1.12.2 Alternate Testing One of these valves will be disassembled on a rotating basis each refueling 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 IW-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.
O 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 dit, assembled every other refueling outage to prove that the disc is free to move.
6.1.14 Test Requirement IW-3521 requires that check valves be exercised at least once per 3 months.
6.1.14.1 Basis for Relief Normally closed check valves P41-F024AaB, 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 to 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 net provide for positive verification of the flow rate through each valve.
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6.1.14.2 Altarnate 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 Q determined to be non-functional an additional valve will be disassembled.
Failure of this valve will require the disassembly of the remaining valves for a
that unit.
6.1.15 Test Requirement IW-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.
IW-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 50% for valves will full-stroke times less than 10 seconds, the test frequency shall be increased to once each mnth until corrective action is taken i 6.1.15.1 Basis for Relief These valves are air operated valves without indicating lights or control switches. Measurement of stroke times can be performed 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 IW-3413(b) and IW-3417.
6.1.15.2 Alternate Testing l
O A -ximum stroke time 4ii be assigned to each vaive. If the measured stroke time exceeds this value the valve will be declared inoperable.
6.1.16 Test Requirement IW-3411 requires that valves be exercised at least once per 3 months.
6.1.16.1 Basis for Relief Closure of this normally open valve would totally interrupt flow to the
! drywell 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 i
once per 3 months.
6.1.17 Test Requirement IW-3411 requires that valves be exercised at least once per 3 months.
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6.1.17.1 Basis for Relief i
ciosure or this va've durias aor ai power operatioa ou'd $aterrupt <1o to O the turbine building equipment normally cooled by service water. This valve 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 IW-3411 requires that valves be exercised at least once per 3 months.
6.1.18.1 Basis for Relief Closure of this valve during normal operation would shut off the cooling water 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 C IW-3417(b) and IW-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 IW-3411 requires that valves be exercised at least once per 3 nonths.
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.
. . = _ - -- ._ . . - - -. _ _ _ . . - -
i 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 Test Requirement IW-3411 requires that valves be exercised at least once per 3 months.
6.1.21.1 Basis for Relief Closure of this valve during normal power operation will interrupt cooling water flow to the reactor building equipment normally cooled by service water. The characteristics of the valve operator and its control logic permit the partial stroking of this valve; however, the position indicating lights show only the fully opened and fully closed positions. The potential that exists for interrupting flow to essential equipment during the partial stroking outweighs any gains that may exist.
6.1.21.2 Alternate Testing l This valve will be stroked every cold shutdown but not more frequently than j once per 3 months.
6.1.22 Test Requirement '
l IW-1100 provides the rules and requirements 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 l
O consequences of an accident.
l The Control Rod Drive (CRD) System valves will not be individually tested per
, this requirement.
l l 6.1.22.1 Basis for 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.
1 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 Section XI would not increase the level of safety. Therefore, Technical Specifications testing will be used in lieu of the Section XI requirements.
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7.0 Inservice Testing of Pumps The 1980 ASE Section XI code with Addenda thru Winter 1980 requires inservice n
V 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 qualities.
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 AP .93 to 1.1 A PR 2 9 and <.93APR <.9 or> 1.1 A P R Q .94 to 1.1 QR 1.9 and <.94 QR < 9 or>l l QR 0 <VR i 2.0 0<V$2VR 2VR <V i 3VR V>3VR 2 <VR 15 0 <V i(2+VR ) (2+VR ) < Y i(4+VR) Y>I4+VR )
VR >5 0 <V 1(1.4YR ) l 4VR <Vil.8VR V > 1.8VR O va is Procedurcily set to be a m'aimum or 1 s miis- Per manufacturers recoisnendations these pumps will operate satisfactorily with vibrations in excess of 4 mils.
For the RHR Pumps, the Core Spray Pumps, the Standby Liquid Control Pumps, the Jockey Control 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 A Pg >.9 and < .93 A PR <.9 or>1.05 A PR Q .94 to 1.05 Qg 1.9 and < .94 Qg < .9 or > 1.05 QR 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.
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7.1.1.1 Basis for Relief
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n The bearings (or bearing surfaces) are cooled by the process fluid that is U being pumped.
4 7.1.1.2 Alternate Testing The bearings will be inspected for wear whenever the pump is disassembled for maintenance.
The bearing temperature of the pump motor will be monitored.
7.1.2 Test Requirement Table IWP-4110-1 requires that flow be measured within i 2% of full scale.
7.1.2.1 Basis or Relief Flowrate is measured by the change in the Standby Liquid Control test tank level during a two minute test period.
l 7.1.2.2 Alternate Testing Georgia Power Company has determined that the method of calculating flow is within an acceptable accuracy.
7.1. 3 Test Requirement O Tedie twe-4iio-i reautres taet Pressure be measured withia 12% of fui1 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:
P = Po + (114.5' - River Water Level) x .0433 7.1.3.2 Alternate Testing This method of measurement is well within the code requirement for the determination of the differential pressure.
7.1. 4 Test Requirement Table IWP-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 lubricant level of the motor will be observed.
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 differential pressure positive is a constant regardless of inlet pressure.
7.1.5.2 Alternate Testing The outlet pressure and the flowrate is measured.
7.1.6 Test Requirement Table IW-3100-1 requires that the proper lubricant level or pressure be observed.
7.1.6.1 Basis for Relief The pump is lubricated by the process fluid that is being pumped.
7.1.6.2 Alternate Testing O For the other pumps without a lubricating system the motor oil is observed; however, the motor bearings for this pump have grease fittings.
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.
i 7.1.7.2 Alternate Testing The differential pressure will be measured during each pump test.
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- O O O
- Plant Hatch - Unit No.1 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps i
ASE Pump Code l Identification Pump Description Section XI Code i Class Measured Parameters Test Interval Relief Requested C41 C001A Standby Liquid Control 2 1. Inlet pressure NA 7.1.5 i
! C41 C0018 2. Differential pressure MA 7.1.5 ll
- 3. Flow rate Every 3 mos. 7.1.2
- 4. Vibration amplitude Every 3 mos. No
- 5. Bearing temperature Annually No 1
- 6. Lubricant level or Every 3 mos'. No pressure j
i Ell C002A Residual Heat Removal 2 1. Inlet pressure Every 3 mos. No Ell C002B 2. Differential pressure Every 3 mos. No j Ell C002C !
- 3. Flow rate Every 3 mos. No '
4 Ell C002D 4. Vibration amplitude Every 3 m)s. No
- 5. Bearing temperature Annually 7.1.1 1
- 6. Lubricant level or Every 3 mos. 7.1.4 pressure i
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O O Plant Hatch - Unit No.1 i Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASE Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested Ell C001A RHR Service Water 3 1. Inlet pressure Every 3 mos. 7.1.3 Ell C001B 2. Differential pressure Every 3 mos. 7.1. 3 f Ell C001C 3. Flow rate Every 3 mos. No l
4 Ell C001D 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 E21 C001A Core Spray 2 1. Inlet pressure Every 3 mos. No Every 3 mos.
E21 C001B 2. Differential pressure No
- 3. Flow rate Every 3 mos. No
- 4. Vibration anplitude Every 3 mos. No l 5. Bearing temperature Annually 7.1.1
- 6. Lubricant level or Every 3 mos. 7.1.4 j pressure i
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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 AS!E Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested
- E21 C002A 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
- 4. Vibration amplitude Every 3 mos. No
- 5. Bearing temperature Annually No
- 6. Lubricant level or NA 7.1.6 pressure P41 C001A 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 4 pressure 1
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- o Plant Hatch - Unit No.1 o o Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps
! ASE
! Pump Code Section XI Code i Identification Pump Description Class Measured Parameters Test Interval Relief Requested E41 C001 High-pressure Coolant 3 1. Inlet pressure Every 3 mos. No Injection
- 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 l 6. Lubricant level or Every 3 mos. No pressure
- 7. Pump speed Every 3 mos. No E51 C001 Reactor Core 2 1. Inlet pressure Every 3 mos. No Isolation Cooling
- 2. Differential pressure Every 3 mos. No i
i 3. Flow rate Every 3 mos. No l
- 4. Vibration amplitude Every 3 mos. No
- 5. Bearing temperature Annually No
- 6. Lubricant level or Every 3 mos. No j pressure
) 7. Pump speed Every 3 mos. No 1
i
O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASE !
Pump Code Section XI Code I Identification Pump Description Class Measured Parameters Test Interval Relief Requested
}
! 2C41 C001A Standby Liquid Control 2 1. Inlet pressure NA 7.1.5 2C41 C001B 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 4
- 6. Lubricant level or Every 3 mos. No pressure 2E11 C002A Residual Heat Removal 2 1. Inlet pressure Every 3 mos. No y 2E11 C002B 2. Differential pressure Every 3 mos. No 2E11 C002C 3. Flow rate Every 3 mos. No l 2E11 C002D 4. Vibration amplitude Every 3 mos. No ,
j 5. Bearing temperature Annually 7.1.1
- 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 ASME Code Class 1, 2, and 3 Pumps ASME
. Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested j 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 C001D 4. 'if bration amplitude Every 3 mos. No
- 5. Bearing temperature Annually 7.1.1
- 6. Lubricant level or Every 3 mos. 7.1.4 pressure 2E21 C001A Core Spray 2 1. Inlet pressure Every 3 mos. No i
2E21 C001B 2. Differential pressure Every 3 mos. No
- 3. Flow rate Every 3 mos. No
- 4. Vibration amplitude Every 3 mos. No i
- 5. Bearing temperature Annually 7.1.1
, 6. Lubricant level or Every 3 mos. 7.1.4
- pressure 1
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O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASME Code Class 1, 2, and 3 Pumps ASME Pump Code Section XI Code Identification Pump Description Class Measured Parameters Test Interval Relief Requested 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 C003B 4. Vibration amplitude Every 3 mos. No
- 5. Bearing temperature Annually No
- 6. Lubricant level or Every 3 mos. No pressure 2P41 C001A Plant service water 3 1. Inlet pressure Every 3 mos. 7.1.3 2P41 C001B 2. Differential pressure Every 3 mos. 7.1.3 2P41 C001C 3. Flow rate Every 3 mos. No l
2P41 C001D 4. Vibration amplitude Every 3 mos. No i 5. Bearing temperature Annually 7.1.1
- 6. Lubricant level or Every 3 mos. 7.1.4 pressure t
O O O Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ME Pump Code Identi fication Pump Description Class Section XI Code Measured Parameters Test Interval Relief Requested
! 2P41-C002 Standby Diesel 2 1. Inlet pressure Every 3 mos. 7.1.3 Gen. Service Water
- 2. Differential pressure Every 3 mos. 7.1.3 s
l 3. Flow rate Every 3 mos.
- 4. Vibration ampl?tude Every 3 mos.
- 5. Bearing temperature Annually
- 6. Lubricant level or NA 7.1.6
, pressure
! 2E41 C001 High Pressure 2 1. Inlet pressure Every 3 mos. No Coolant Injection 3
i
- 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 -
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Plant Hatch - Unit No. 2 Inservice Inspection Program for ASE Code Class 1, 2, and 3 Pumps ASE Pump -
Code Identification Pump Description ClassSection XI Code '
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 1
- 3. Flow rate Every 3 mos. flo !
1
- 4. Vibration amplitude Every 3 mos. No ,
1
- 5. Bearing temperature Annually Mo
- 6. Lubrica.1t level or Every 3 mos. Peo pressure .
1 -
- 7. Pump speed . Every 3 acs. ; No' i
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