ML20056B303

Ei Hatch Nuclear Plant,Units 1 & 2 Inservice Insp Program Second 10-Yr Interval

ML20056B303
Person / Time
Site:	Hatch
Issue date:	08/01/1990
From:	GEORGIA POWER CO.
To:
Shared Package
ML20056B302	List: ML20056B301 ML20056B303
References
PROC-900801, NUDOCS 9008280101
Download: ML20056B303 (341)

Text

- .

r C INSERVICE INSPECTION PROGRAM SECOND 10 -

YEAR INTERVAL E. I. HATCH NUCLEAR PLANT UNITS I AND 2 l a

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.O REV. DATE DESCRIPTION APPV. ph APPV. APPV.

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I Hatch Nuclear _ Plant Units 1 and 2151 Program ~

-Holder Manual Number-E. C. Sorrell 1-J. D. Heidt 2

. B. K. McLeod 3 E. M. Burkett. 4 l T. N. Epps 5 M. Belford 6 NRC Inspection Engineer Hatch 7 D. R. Laakso 8 R. L. Dyle 9*

R. W. Healey 10 K. F. White 11 l

0. M. Fraser 12 ,

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v l lSI/IST APPROVAL SONOKO l Written by: J 7 3 O @ f-1 Reviewed by RAEAA]wA Eng. Supv: - -

Mgr. Eng- ha QA Review-m BOA PRB No.: 9@-121 AGM PS: b ffM/

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1. . - . - . . - . . -

1 1ABLE Of CONTENTS

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l 1.0 Introduction 1-1 thru.1-3 Figures 1 thru 9 2.0 Class I with' Relief Requests 2-1 thru 2-15' Table 1 Sheets 1 thru 14 Table 1 Notes 1 page '

3.0 Class 2 with Relief Requests 3-1 t!<ru 3-8 Table 2 Sheets 1 thru 4 4.0 Class 3 with Relief Requests 4-1 thru 4 6 Table 3 Sheets 1 thru 3 5.0 Class 1, 2, and 3 Supports with  ;

Relief Requests 5-1 thru 5-4 Table 4 Sheets 1 thru 3 6.0 General Relief Requests 6-1 thru 6-8

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1.0 INTRODUCTION

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( 1.1 GENERAL This document describes the revised Inservice Inspection (ISI) Program for Edwin I. Hatch Nuclear Plant, Units 1 and 2. -

This Program meets, as much as practical, the requirements of the 1980 Edition -

of Section XI with Addenda through Winter 1981. ,

1.2. EFFECTIVE DATE The original Program, developed to meet the Winter 1981 Addenda, became effective on January '1, 1986. .

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1.3 SCOPE l This document is a description of the ISI Program for Class 1, 2, and 3 r component examination at Units 1 and 2 of Plant Hatch. '

l 1.4 COMPONENT UPGRADINS 1 l

- All plant components have been reviewed to determine the appropriate classification for inservice inspection and testing. Regulatory Guide 1.26

! was used for guidance in determining component classifications.

It must be noted that the classification of components as ASME Class 1, 2, or l

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3 equivalent for this Program 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 SUBSE0 VENT PROGRAM REVISIONS l'

It is anticipated that this Program will be reviewed again near the end of 120

. months of implementation. At that time, the Program will be modified as required to bring it into compliance with a later Nuclear Regulatory Commission (NRC) approved edition and addenda of ASME Section XI. .Any additional relief requests for impractical requirements will be submitted per 10 CFR 50.55a(g)(iii).

The current revision, Revision 3, was issued to separate the Inservice Testing i Program from the ISI Program. The only other changes were the additions of a " Relief Request Status

• paragraph to reflect the NRC staff positions stated i

in the Safety Evaluation Report (SER) of June 22, 1989 or editorial corrections. No technical changes were made.

1.6 RESPONSIBILITY Georgia Power Company, as owner, bears the overall responsibility for the performance of the inservice inspection and testing activities in accordance with IWA-1400.

LO 000307 1-1

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1 1.7 RE0_Q_RILS n.

Records and documentation of information and examination results, which

.('v) : provide the basis for evaluation and which facilitate comparison with results ,

from previous and subsequent examinations, will be maintained and available l for the active life of the pirnt in accordance with Section XI, IWA 6000.

1.8 METHODS OF EXAMINATION l l

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

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

1.8.1 ULTRASONIC EXAMINATION (UT) l it is anticipated that most volumetric examinations will be performed j ultrasonically. Examinations will be conducted in accordance with the

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! requirements of IWA-2232 of ASME Section XI except as requested by relief.

l 1.8.2 RADIOGRAPHIC EXAMINATION (RT)

Radiographic techniques well be used to supplement UT when necessary.

1.8.3 LIQUID PENETRANT EXAMINATION (PT) t O Liquid penetrant examinations in accordance with IWA-2222 of ASME Section XI l

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( will be performed whenever a surface examination is required on non-magnetic components.

1.8.4 MAGNETIC PARTICLE EXAMINATION (MT)

Magnetic particle tests in accordance with IWA-2221 of ASME Section XI will be used when surface examination of carbon steel components is required.

1.8.5 VISUAL EXAMINATION (VT)

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

a. VT-1 This examination shall be conducted to determine the condition of the part, component, or surface examined.

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

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c. VT-3

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( I This examination shall be conducted to determine the general mechanical and structural condition of components and their supports.

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

1.9 STANDARDS FOR EXAMINATION EVALUATION The acceptance standards for Class 1 components will be either IWB-3000 of ASME Section XI or the Section III construction Code for the plant, as applicable, except whera superceded or augmented by agreement with NRC in separate submittals.

For Class 2 and 3 components, Articles IWC-3000 and' LWD-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 111 construction Code for the plant, as applicable, except where superceded or a augmented by agreement with NRC in separate submittals.

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

/*"N d Corrective measures for Class 1, 2, and 3 pressure testing will be determined per IWA-5000 of ASME Section XI.

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

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2.0 CLASS 1 WITH RELIEF REQUESTS

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Y 2.0.1 General g Table 1 provides a tabulation of the Class 1 pressure-retaining components subject to the inspection requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter 1981. These components will be inspected in accordance with the requirements of Subsection IWB to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination except where superceded or g augmented by agreement with NRC in separete submittals. Where relief from the u inspection requirements of Subsection IWE is requested, information is provided which identifies the applicable : ode requirements, justification for the relief requested, and the examination method to be used as an alternative.

Table IWB-25001 items not applicable to the Hatch Plant have also been listed and identified in the interest of completeness.

2.0.2 Hydrostatic Testina l Hydrostatic testing wi') be conducted in a manner that will satisfy the l requirements of IWA 500 and IWB-5000. I 2.0.3 Weld Selection Criteria l The extent of examination for Code Class 1 pipe welds (Category B-J) was

,m, determined by the requirements of Table IWB 2500 and Table IWB-2600 Category B-J of Section XI of the ASME Code in the 1974 Edition with Addenda through

(-) Summer 1975 as allowed by 10 CFR 50.55a. In addition, terminal ends and high stress welds were chosen when practical to upgrade the overall selection criteria.

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2.1 CLASS 1 RE0 VESTS FOR RELIEF FROM ASME SECTION XI RE0VIREMENTS l-l O

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/'~ 2.1.1 - VOLUMETRIC EXAMINATION OF REACTOR PRESSURE VESSEL AND CLOSURE HEAD

( WELDS 2.1.1.1 Reauirement From Which Relief is Reouested Item No. Bl.ll,- Bl.12, Bl.21, and B1.22 of Table IWB-2500-1 of ASME Section XI.

require the volumetric examination of reactor pressure vessel (RPV) and closure head circumferential, longitudinal, and meridional welds. At Hatch, these examinations will be performed using ultrasonic techniques. The applicable examination volumes are shown in Figures IWB 2500-1, -2, and -3.

The Code also requires that welds selected for examination are to be examined fer essentially 100 percent 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 t these welds. The 1974 Edition with Addenda through Summer 1975 and earlier editions of Section XI required that the examination cover at least 10 percent of the length of each longitudinal weld and 5 percent of the length of each circumferential weld. For both Hatch units, the minimum lengths described above were met during previous examinations. The following evaluation (listed i by code item No.) gives the percentage of weld accessible for examination and the additional welds ;o be examined so that the total weld length examined equals 100 percent of the required examination length.

Item Bl.11 - Hatch Unit 1 - There are two circumferential welds (C-3 and C-4) in the beltline region of the RPV, as shown in Figure 1. Weld C-4 has three access doors through the concrete shield, and removable RPV insulation in these areas was provided during the design. These three access ports allow the manual examination of approximately 15 percent of the weld. Weld C-3 has two usable access doors allowing approximately 10-percent coverage; therefore, a total of only 25 percent of the beltline area welds can be examined during the second 10-year interval.

During the second 10-year interval, portions of welds C-2 and C-5 will .

also be examined in order that the total equivalent length being examined equals the length of one beltline circumferential weld.

Item B1.11 - Hatch Unit 2 - There are two circumferential welds (2C-3 and 2C-4) in th~e beltline region of the RPV, as shown in Figure 2. These welds have permanent tracks which were installed during construction prior to the preservice examinations. Projected examination coverage indicates that approximately 348 inches (47 percent) of weld 2C-3 can be examined using a mechanized system and 234 inches of weld 2C-4 (32%) can be examined. Therefore, a total of approximately 79 percent of the circumferential beltline area welds can be examined during the second 10-year interval.

O 000307 2-3

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During the second 10 year interval, portions of welds 2C 2 and 2C 5 will fy also be examined in order that the total equivaient length being examinnd  ;

t i equals the length of one beltline circumferential weld. In addition, the U required examinations for the third 40 month period of the first 10 year interval will be completed.

Item B1.12 - Hatch Unit 1 - Using the same access doors as described above, approximately 20 percent to 30 percent of C-3-A, 20 percent to 30 percent of C-3-B, and 10 percent to 15 percent _of weld C-3-C can be -

manually examined. Therefore, a total of 50 percent to 75 percent of the beltline longitudinal welds can be examined during the second 10-year  ;

interval. Also, during the second 10-year interval, sufficient weld lengths will be selected from welds C-2-A, C-2-B, C-2-C and/or C-4-A, C-4-B, and C-4-C to ensure thit the equivalent length of a beltline longitudinal weld is examined.

Item Bl.12 - Hatch Unit 2 - From the preservice data it is apparent that longitudinal r: elds 2C-3-A, 2C-3-B and 2C-3-C can be 100 percent examined ushg a mechanized system with pole tracks installed during construction.

One of these three welds will be 100-percent examined during the'second 10 year interval. In addition, the required examinations for the third 40-month period of the first 10-year interval will be completed. 'I i

Item Bl .21 -- Hatch Unit 1 - Circumferential bottom head weld C-7 (Figure 9) will be 100-percent examined to the extent practical during the second 10-year interval. If it is found during examinations that 100-percent coverage cannot be obtained, specific relief will be requested

. at that time. One circumferential closure head weld will also be

( 100-percent examined during the interval.

Item Bl.21 - Hatch Unit 2 - Circumferential bottom head weld 2C 7 (Figure 10) had 73 percent of its weld length examined during preservice.

This weld will be 100-percent examined to the extent practical during the second 10-year interval. If it is found during examinations that 100-percent coverage cannot be obtained, specific relief will be requested at that time. One circumferential closure head weld will also be <

100-percent examined during the interval. In addition, the required examinations for the third 40-month period of the first 10-year interval will be~ completed.

Item B1.22 - Hatch Unit 1 - One of the bottom head meridional welds extending from circumferential weld C-5 to C-7 (Figure 9) will be 100-percent examined to the extent practical during the interval. If it is found during examinations that 100-percent coverage cannot be obtained, specific relief will be requested at that time. One meridional closure head weld will also be 100 percent examined during the interval.

000307 2-4 mu

ltem Bl.22 - Hatch Unit 2 - One of the bottom head meridional welds extending from circumferential weld 2C 5 to 2C-7 (Figure 10) will be l,_.'i - . 100-percent examined to the extent practical during the interval. If it i/s- is found during examinations that 100 percent coverage cannot be obtained, specific relief will be requested at that time. One meridional closure head weld will also be 100 percent examined during the interval. In addition, the required examinations for the third 40-month period of the first 10-year interval will be completed.

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

2.1.1.4 Relief Recuest Status A. Relief granted, with comments, by 9/29/86 SER.

B. Relief denied, based on 8/12/87 NRC memorandum, by 6/22/89 SER.

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n. l 2.1.3 VOLUMETRIC EXAMINATION OF REACTOR PRESSVRE VESSEL AND CLOSURE HEAD N0?ZLE-TO VESSEL WELDS AND N0ZZLE INSIDE RADIUS SECTIONS O .

J 2.1.3.1 Reouirement From Which Relief is Recuested Item No. B3.90 and B3.100 of Table IWB 2500-1 of ASME Section XI require the volumetric examination of RPV and closure head nozzle-to-vessel welds and nozzle inside radius sections. The applicable examination volumes are shown in Figures IWB-2500 7(a) through (d). At Hatch, these examinations will be performed using ultrasonic techniques.

2.1.3.2 Justification Examination limitations exist for the nozzle examinations at Hatch Units 1 and 2 due to a combination of permanent physical obstructions. At Hatch Unit 1, '

en insulation support ring (Figure 1) is welded just above the N2A through K.

recirculation system inlet nozzles and the NIA and B recirculation system outlet nozzles. Welded thermocouples are near nozzles N4B and N4D which partially limit coverage. The limitations exist regardless of transducer size. Hatch Unit 2 has limitations for the examination of the 2N4A and C feedwater nozzles due to interference from adjacent nozzles (Figure 2) and the transition area of tne nozzles where they are welded to the shell. As before,

! transducer size has very little impact on the coverage of these feedwater nozzle welds. Showing the nozzle-to-vessel weld as N to V and the nozzle inside radius section as IRS, the table below shows the affected nozzle, minimum coverage, and reason for limitation.

f Hatch Unit 1 Nozzle Limited Examinations Minimum Coveraae Reason N2A N to V; IRS 85% Ins. Support Ring N2B N to V; IRS 85% Ins. Support Ring N2C N to V; IRS 85% Ins. Support Ring N2D N to V; IRS 85% Ins. Support Ring i

N2E N to V; IRS 85% Ins. Support Ring

N2F N to V; IRS 85% Ins. Support Ring N2G N to V; 1RS 85% Ins. Support Ring l N2H N to V; IRS 85% Ins. Support Ring N2J N to V; IRS 85% Ins. Support Ring N2K N to V; IRS 85% Ins. Support Ring NIA N to V; IRS 85% Ins. Support Ring N1B N to V; IRS 85% Ins. Support Ring N4B N to V; IRS 95% Thermocouples N4D N to V; IRS 95% Thermocouples Hatch Unit 2 Nozzle Limited Examinations Minimum Coveraae Reason 2N4A N to V; IRS 85% Adjacent Nozzle 2N4C N to V; 1RS 85% Adjacent Nozzle 000307 2-7

2.1.3.3 Testino-in liqp of Section XI Reauirementt .

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Not. applicable to this_ relief request.

2.1.3.4 Relief Reauest Status A. Relief granted by 9/29/86 SER.-

B. 2 nozzles added - relief granted by 6/22/89 SER.

L t

w l

t j

I' l

000307 2-8 i

2.1.4 VOLUMETRIC EXAMINATION OF AUSTENTTIC AND DISSIMILAR METAL PIPING WELDS im 2.1.4.1 Recuirement from Which Relief is Recuested g item No. B5.130, B5.10, B9.11, B9.12, and 89.31 of Table IWB-2500-i of ASME Section XI require a volumetric and surface examination of austenitic and dissimilar metal piping welds. In addition, Item No. B14.10 of Table IWB-2500-1 requires either a volumetric or a surface examination of the pressure retaining welds in control rod drive (CRD) housings. These volumetric examinations are to be 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 ASME Section V.

t 2.1.4.2 Justification '

Article 5 of ASME Section V does not provide the detailed guidance necessary to examine austenitic and dissimilar metal piping welds with the exception of austenitic piping welds which have been repaired by weld overlay. These clad overlaid piping welds will be examined in accordance with Article 5 of Section V and Appendix 111 ef Section XI.

2.1.4.3 Testina in lieu of Section XI Recuirements Ferritic piping welds will be examined per Appendix Ill of Section XI. To provide consistency, austenitic and dissimilar metal piping welds will also be s q examined in accordance with Appendix Ill.

2.1.4.4 Relief Recuest Status A. Relief deemed unnecessary. Proposed alternate satisfies code. See 9/29/86 SER.

l B. Position affirmed by 6/22/89 SER.

i 000307 2-9

~2.1.5 SURFACE EXAMINATION OF REACTOR PRESSURE VESSEL SUPPORT SKIRT WELD

-t

(, 2.1.5.1 Reouirement from Which Relief is Reauested Item No. B8.10 of Table IWB 2500-1 of ASME Section XI requires volumetric or surface (as applicable) examination of integrally welded attachments (support ,

skirt), in accordance with the examination requirements shown on Fig. No.

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

2.1.5.2 Justification At both Hatch units, examination area C-D of Fig. No, IWB 2500 13 is not accessible for meaningful examination because of location and geometric configuration of welded areas. Physical access by the examiner is also-restricted because of high radiation and obstruction due to CRD housings and its support system. The combination of these factors prevents these welds from being examined from inside the support skirt.

Hatch Unit I has no access through the support skirt; therefore, the inside surface of the reactor vessel support skirt is totally inaccessible. As l- shown in Figure 6 for Hatch Unit 2, the support skirt near the skirt-to-vess+1

, weld is very limited. Health Physics indicates that the dose rate in this L area during a recent Hatch Unit 2 outage was approximately 180 mr/hr; however, l- it is very difficult to quantify the total exposure for an examination.

l Magnetic particle techniques cannot be used due to the space restrictions.

I The use of dye penetrant would require a very thorough cleaning of the weld f and adjacent base material to remove rust and scale. The preparation of the

( weld would potentially have to be performed using technic,aes such as wire brushes since power tools may not fit into the limited area.

2.1.5.3 Testina in lieu of Section XI Reauirements As an alternate, both units will have a surface examination performed on the OD of 100 percent of the weld during the second 10-year interval. Also, a limited ultrasonic examination will be performed to the extent practical to provide as much coverage as possible of the weld.

2.1.5.4 Selief Reauest Status l

l A. Relief grarited by 9/?9/86 SER.

B. Relief affirmed by f,22/89 SER.

l 000307 2-10

2.1.6 REACTOR PRESSURE VESSEL N0ZZLE TO SAFE-END WELDS (NOMINAL PIPE SIZE

<4 INCHES) n

{ }-

2.1.6.1 'Reauirement from Which Relief is Requ d ed item No. B5.20 of Table IWB-25001 of _ ASME Section XI 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 nozzle to-safe-end welds for the nozzles listed below are physically inaccessible for surface examination. The affected nozzles are.

N10 2N10 NllA 2NilA N11B 2NilB N12A 2N12A N12B 2N12B N16A 2N16A N16B 2N16B These 2-inch instrument nozzles have very limited access due to the design of the concrete shield. Each nozzle has small doors that can be opened allowing 12- to 18 inches of access. However, due to the distance the RPV wall is ,

recessed from the outside of the shield wall (e.g., insulation thickness, air I

,e - gap, and shield thickness) the weld cannot be physically reached. The 2-inct. l

-( RPV bottom head-drain-nozzle-to-safe end weld is exempted by IWB-1220(c) of ASME Section XI from examination.

2.1.6.3 Testino in Lieu of Section XI Reauirements l

The nozzle-to-safe-end welds listed above will receive a remote visual I examination with the exception of the 2-inch drain nozzle welds. In addition, I these nozzles will be pressure tested per IWB-5000 of ASME Section XI since .

they are located within the hydrostatic test boundary of the nuclear steam I supply system.

4 2.1.6.4 Relief Reauest Status A. Relief granted by 9/29/86 SER.

B. Relief affirmed by 6/22/89 SER.

g 000307 2-11

.e

2.1.7 VOLUMETRIC AND SURFACE EXAMINA110NS OF PRESSURE RETAINING WELDS IN PIPING WITH NOMINAL PIPE SIZE 24 INCHES l

U 2.1.7.1 Recuirement From Which Relief is Re3uested item No. B9.11 of Table IWB 2500-1 of ASME Section XI requires the examination of pressure retaining welds in piping that are located within flued head containment penetration assemblies. These welds and their penetration assembly number for Hatch I ar*! listed below. Hatch 2 has no pressure retaining welds in the penetration assemblies.

Weld Identification No. Pen. No. Weld Identification No. Pen. No.

1B21-lFW 18A-7A X-9A IB21-1MS-24A 17A X-7A IB21 lFW-18B 6A X 9B IB21-lMS 24B 16A X-7B IE51-lRCIC-4 D-20A X-10 IB21 lMS 240-16A X 7C IE41-lHPCI-10-D-15A X Il IB21-lM5-240 17A X-7D lE11-lRHR 200 D 13A X 12 lE11-lRHR-24A R 3A X 13A lEll-lRHR 24B-R-3A X 13B IG31-lRWCV 6-D 15B X-14 ,

IG31-IRWCV 6-D 15C X-14 IE21-1CS-10A-3A X-16A lE21 lCS-108-4A 3-16B IEll-lRHR-4-HS 6B X-17 2.1.7.2 Justification These welds are inaccessible for examination due to tae design of the flued head. All sixteen circumferential butt welds, except the two located in the l i reactor water cleanup (RWCU) penetration, are carbon steel.

The two stainless steel welds that are located in the RWCU penetration were made to replace a Type 304 SS pipe that had undergone IGSCC. The welds involved are a flued head with a Type 308L corrosion resistant clad on the inside surface to a Type 304L solution annealed pipe (90.035 percent 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 Testino in lieu of Section XI Recuirements A UT baseline was performed on the two new welds in the RWCU system while they i were accessible during repair to ensure a high quality weld.

In accordance with IWB 5221 of ASME Section XI, a system leakage test is to be performed on all 16 welds prior to startup following each reactor refueling outage.

000307 2-12

All pipe to penetration (flued head) welds outside containment will be examined volumetrically, in addition, a surface examination will be performed

(~'-)

( on the accessible weld (s) of the flued head penetration assembly.

2.1.7.4 Relief Reauest Status A. Relief granted by 9/29/86 SER.

B. 4 welds added - Relief granted by 6/22/89 SER.  ;

I i

j l

l O

000307 2-13

i 2.1.8 ASME CLASS 1 (EQUIVALENT) VALVES EXCEEDING 4 INCHES NOMINAL PIPE SIZE AND ASME CLASS 1 (EQUIVALENT) PUMP CASINGS  !

V ,

2.1.8.1 Recuirement From Which Relief is Recuested l Table IWB-2500-1, Item No. B12.50 of ASME Section XI 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 fanctions in the system.

1 Table IWB-25001, Itu No. B12.20 of ASME Section XI requires a visual examination of the C ternal pressure boundary surface of one of the two  ;

reactor recirculat... 4 , tem pumps.

1 2.1.8.2 Justification  ;

, Disassembly of these valves and pumps for the visual examination during the l inspection intc~ val, in the absence of other required maintenance, represents i an unnecessary exposure to radiation and contamination. Valves on the reactor recirculation (RC) system and the residual heat removal (RHR) system suction i lines would involve off-loading the fuel elements and draining the RPV prior to disassembly as a precautionary measure. Work on the RC system pump )

i 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 O examination. Contamination levels in the valves and pumps associated with the ,

RC system loops are particularly high due to the physical location at the (b' bottom of the system. During routine maintenance, the valve body and the pump l

I casing internal surfaces are visually examined. Many of the valves, I l particularly the containment isolation valves are disassembled for maintenance I of leak-tightness. Disassembly of other Class 1 valves and the pumps solely for internal examination is counter to the ALARA guidelines to keep the occupational dose rates as low as reasonably achievable. In view of the cost .

in man-rem and in view of the minimal benefits obtained, we conclude that this )

Code requirement does not provide sufficient benefits to justify the exposure.

i 2.1.8.3 Testina in lieu of Section XI Reauirements class 1 pumps and Class 1 valves exceeding 4 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 ptriodic 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.

2.1.8.4 Relief Recuest Statyi A. Relief granted by 9/29/86 SER.

B. Relief affirmed by 6/22/89 SER.

000307 2-14

2.1.9 PRESSURE RETAINING WELDS IN CONTROL ROD DRIVE HOUSINGS 2.1.9.1 Reauirement From Which Relief is Reauested Table INB 2500-1, Item No. B14.10 of ASME Section XI requires a volumetric or surface examination of the pressure retaining welds in 10 percent of the peripheral control rod drive housings. Each housing has a pipe-to pipe weld located near the RPV and a pipe to flange weld.

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

Figure 4.2 8 of the Hatch Unit 2 FSAR shows that there are 28 peripheral CRD housings. Each housing has an attachment weld to the reactor vessel and a weld joining the housing to the flange. Section 4.2 of the FSAR shows that the failure of a CRD housing weld will produce a maximum leakage rate of 840 gal / min. The available makeup systems are RCIC-400 gal / min, CRD-160 gal / min.,

and the transfer system to feedwater-1000 gal / min. Therefore, the reactor can be shut down and cooled in an orderly manner using makeup systems supplied by onsite power, as required by IWB-1220. Since loss of coolant would occur O-

.. during normal operation, it is our interpretation that the service transformer is the source of onsite power. (Note: Hatch Unit I should have essentially the same leakage rates and makeup capabilities).

2.1.9.3 Testina in lieu of Section XI Reauirements These welds will be aressure tested per IWB 5000 of ASME Section XI since they are located within tie hydrostatic test boundary of the nuclear steam supply system.

2.1.9.4 Relief Reauest Status A. Relief deemed unnecessary. Proposed alternate satisfies code. See 9/29/86 SER.

B. Position affirmed by 6/22/89 SER.

000307 2-15

-h p m s

I d V U TABLE I Sh. I of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH SUCLEAR PLANT, UNITS 1 AND 2 t

! Examination System or Component Method of Code Relief Item No. Cateqory Description Areafsl to Be Examined Examination Recuested B1.11 B-A Reactor Pressure Vessel Circumferential Shell Welds Volumetric Yes; 2.1.1 81.12 B-A Reactor Pressure Vessel Longitudinal Shell Welds Volumetric Yes; 2.1.1 Bl.21 B-A Reactor Pressure Vessel Circumferential Head Welds Volumetric Yes; 2.1.1

! and Closure Head 81.22 B-A Reactor Pressure Vessel Merid=-! !! sad Welds Volumetric Yes; 2.1.1 and Closure Head B1.30 B-A Reactor Pressure Vessel Shell-to-Flange Weld Volumetric No Bl.40 B-A Reactor Pressure Vessel Head-to-Flange Weld Surface and No Closure Head Volumetric B1.51 B-A Reactor Pressure Vessel Beltline Region Repair Volumetric Not applicable to Welds either Hatch unit B2.10 B-B Pressurizer Shell-to-Head Welds Volumetric Not applicable to either Hatch unit

! B2.20 B-B Pressurizer Head Welds Volumetric Not applicable to l either Hatch unit 82.30 B-B Steam Generator Head Welds Volumetric Not applicable to (Primary Side) either flatch unit B2.40 B-B Steam Generator Tubesheet-to-Head Welds Volumetric Not applicable to (Primary Side) either flatch unit B2.50 B-B Heat Exchangers Head Welds Volumetric Not applicable to j (Primary Side) either Hatch unit

. .. - _. --___=___-_ -

O O O TABLE I Sh. 2 of 14 ISI PROGRAM FOR ASME CLASS I COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Method of Code Relief Examination System or Component Reavested Categor_y Description Areafsl to Be Examined Examination item No._

Tubesheet-to-Shell Volumetric Not applicable to B2.60 B-B Heat Exchangers either Hatch unit (Primary Side) (or Head) Welds Nozzle-to-Vessel Welds Volumetric Not applicable to 83.10 B-D Reactor Pressure Vessel either Hatch unit; GPC has elected to perform examinations in accordance with Program B.

Nozzle Inside Radius Volumetric Not applicable to 83.20 B-D Reactor Pressure Vessel either Hatch unit; Section GPC has elected to perform examinations in accordance with Program B.

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

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

(

O l

TABLE I Sh. 3 of 14 ISI PROGRAN FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination _Reovested B3.80 B-D Heat Exchangers Nozzle Inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit B3.90 B-D Reactor Pressure Nozzle-to-Vessel Welds Volumetric Yes: 2.1.3 Vessel B3.100 B-D Reactor Pressure Nozzle Inside Radius Volumetric Yes: 2.1.3 Vessel Section 83.110 B-D Pressurizer Nozzle-to-Vessel Welds Volumetrir Not applicable to either Hatt'n unit B3.120 B-D Pressurizer Nozzle Inside Radius Volumetric Not applicable to i Section either Hatch unit B3.130 B-D Steam Generators Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch untt B3.140 B-D Steam Generators Nozzle Inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit B3.150 B-D Heat Exchangers Nozzle-to-Vessel Welds Volumetric Not applicable to (Primary Side) either Hatch unit -

B3.160 B-D Heat Exchangers Nozzle Inside Radius Volumetric Not applicable to (Primary Side) Section either Hatch unit 84.11 B-E Vessel Nozzles External- Surfaces of Visual, VT-2 No Partial Penetration Welds 84.12 B-E Control Rod Drive External Surfaces of Visual, VT-2 No Nozzles Partial Penetration Welds 1

- , y -v - -

._ .,..e -4 , - - , '

1 O O O i TABLE I Sh. 4 of 14 ISI PROGRAM FOR ASME CLASS I COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Cateaory DescriDtion Areafs1 to Be Examined Examination Reauested l

B4.13 B-E Instrumentation External Surfaces of Visual, VT-2 No Nozzles Partial Penetration Welds 84.20 B-E Pressurizer External Surfaces of Visual, VT-2 Not applicable to Heater Penetration Welds either Hatch unit B5.10 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface and Yes; 2.1.4 Welds (Nominal Pipe Volumetric Size 2.4 in.)

B5.20 B-F Reactor Pressure Vessel Nozzle-to-Safe End Butt Surface Yes: 2.1.6 Welds (Nominal Pipe Size <4 in.)

85.30 B-F Reactor Pressure Vessel Nozzle-to-Safe End Surface Not applicable to Socket Welds either Hatch unit B5.40 B-F Pressurizer Nozzle-to-Safe End Butt Surface and Not applicable to Welds (Ncminal Pipe Volumetric either llatch unit Size 24 ir.}

B5.50 B-F Pressurizer Nozzle-to-Safe End Butt Surface Not applicable to Welds (Nominal Pipe either flatch unit Size <4 in.)

85.60 B-F Pressurizer Nozzle-to-Safe End Surface Not applicable to Socket Welds either ifatch unit B5.70 B-F Steam Generators Nozzle-to-Safe End Butt Surface and Not applicable to (Primary Side) Welds (Nominal Pipe Volumetric either liatch unit Size 2,4 in.)

. . . -. - - - ~

p/ p. ,

'y \d V TABLE I Sh. 5 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination _Reauested 85.80 B-F Steam Generators Nozzle-to-Safe End Butt Surface Not applicable to (Primary Side) Welds (Nominal Pipe either Hatch unit Size <4 in.)

B5.90 B-F Steam Generators Nozzle-to-Safe End Surface Not applicrble to (Primary Side) Socket Welds either Hatch unit S5.100 B-F l' eat Exchangers Nozzle-to-Safe End Butt Surface and Not applicable to (Primary Side) Welds (Nominal Pipe Volumetric nither Hatch unit Size 24 in.)

85.110 B-F Heat Exchangers Nozzle-to-Safe End Butt Surface Not applicable to (Primary Side) Welds (Nominal Pipe either Hatch unit Size <4 in.)

85.120 B-F Heat Exchangers Nozzle-to-Safe End Surface Not applicable to (Primary Size) Socket Welds either Hatch unit B5.130 B-F Piping Dissimilar Butt Welds Surface and Yes; 2.1.4 (Nominal Pipe Size Volumetric 24 in.)

B5.140 B-F Piping Dissimilar Butt Welds Surface Not applicable to (Nominal Pipe size either Hatch u.iit

<4 in.)

B5.150 B-F Piping Dissimilar Metal Socket Surface Not applicable to Welds either Hatch unit B6.10 B-G-1 Reactor Pressure Vessel Closure Head Nuts Surface No

=

a v TABLE I Sh. 6 of 14 ISI PROGRAN FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS I AND 2 l Examination System or Component Method of Code Relief

( Item No. Cateoory Description Area (s) to Be Examined Examination Requested B6.20 B-G-1 Reactor Pressure Vessel Closure Studs, in Place Volumetric No; See Note 1 B6.30 B-G-1 Reactor Pressure Vessel Closure Studs, When Removed Surface and No; See Note !

Volumetric 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 i B6.90 B-G-1 Steam Generator Bolts and Studs Volumetric Not applicable to l

either Hatch unit B6.100 8-G-1 Steam Generator nange Surface, When Visual, VT-1 Not applicable to ennection Disassembled either Hatch unit B6.110 B-G-1 Steam Generator Nuts, Bushings, and Visual, VT-1 Not applicable to l Washers either Hatch unit i

B6.120 B-G-1 Heat Exchangers Bolts and Studs Volumetric Not applicable to either flatch unit l

l l

b O O TABLE I Sh. 7 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS I AND 2 Examination System or Component Nethod of Code Relief Item No. Category Description Areafs) to Be Examined Examination Reouested 86.130 B-G-1 Heat Exchangers Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit 86.140 B-G-1 Heat Exchangers Nuts, Bushing, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.150 B-G-1 Piping Bolts and Studs Volumetric Not applicable to either Hatch unit B6.160 B-G-1 Piping Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.170 B-G-1 Piping Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit B6.180 B-G-1 Pumps Bolts and Studs Volumetric No B6.190 B-G-1 Pumps Flange Surface, When Visual, VT-1 No Connection Disassembled B6.200 B-G-1 Pumps Nuts, Bushings, and Visual, VT-1 No Washers 86.210 B-G-1 Valves Bolts and Studs Volumetric Not applicable to either Hatch unit B6.220 B-G-1 Valves Flange Surface, When Visual, VT-1 Not applicable to Connection Disassembled either Hatch unit B6.230 B-G-1 Valves Nuts, Bushings, and Visual, VT-1 Not applicable to Washers either Hatch unit

n m

]

TABLE I Sh. 8 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs1 to Be Examined Examination _Reauested B7.10 B-G-2 Reactor Pressure Vessel Bolts, Studs, and Nuts Visual, VT-1 No 1

87.20 B-G-2 Pressurizer Bolts, Studs, and Nuts Visual, VT-1 Mot applicable to

! either Hatch unit i

B7.30 B-G-2 Steam Generators Bolts, Studs, and Nuts Visual, VT-1 Not applicable to either Hatch unit R7.40 B-G-2 Heat Exchangers Bolts, Studs,. and Nuts Visual, VT-1 Not applicable to either Hatch unit B7.50 B-G-2 Piping Bolts, Studs, and Nuts Visual, VT-1 No B7.60 B-G-2 Pumps Bolts, Studs, and Nuts Visual, VT-1 No B7.70 B-G-2 Valves Bolts, Studs, and Nuts Visual, VT-1 No B7.80 B-G-2 CRD Housings Bolts, Studs, and Nuts Visual, VT-1 No (When Disassembled) t B8.10 B-H Reactor Pressure Vessel Integrally Welded Volumetric or Yes; 2.1.5 Attachments Surface as Applicable 88.20 B-H Pressurizer Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable 88.30 B-H Steam Generators Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable

O O O TABLE I Sh. 9 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination Reouested 88.40 B-H Heat Exchangers Integrally Welded Volumetric or Not applicable to Attachments Surface, as either Hatch unit Applicable B9.11 B-J Piping Circumferential Welds Surface and Yes; 2.1.4 (Nominal Pipe Size Volumetric and 2.1.7 24 in.)

B9.12 B-J Piping longitudinal Welds Surface and Yes; 2.1.4 (Nominal Pipe Size Volumetric

>4 in.)

B9.21 B-J Piping Circumferential Welds Surface No (Nominal Pipe Size

<4 in.)

89.22 B-J Piping longitudinal Welds Surface No (Nominal Pipe Size

<4 in.)

89.31 B-J Piping Branch Pipe Connection Surface and Yes; 2.1.4 Welds (Nominal Pipe Volumetric size > 4 in.)

89.-32 B-J Piping Branch Pipe Connection Surface No Welds (Nominal Pipe Size <4 in.)

B9.40 B-J Piping Socket Welds Surface No; See Note 2

O O TABLE 1 sh. 10 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Method of Code Relief Examination System or Component Reauested Category Description Areafsl to Be Examined Examination Item No.

Piping Integrally Welded Volumetric or No

[

810.10 B-K-1 Surface, as Attachments Applicable Pumps Integrally Welded Volumetric or No l 810.20 B-K-1 Surface, as Attachments Applicable Integrally Welded Volumetric or Not applicable to B10.30 B-K-1 Valves Surface, as either Hatch unit Attachments Applicable Pump Casing Welds Volumetric Not applicable to B12.10 B-L-1 Pumps either Hatch unit Pump Casing Visual, VT-3 Yes; 2.1.8 812.20 B-L-2 Pumps l

i Valve Body Welds Surface Not applicable to 812.30 B-M-1 Valves either Hatch unit (Nominal Pipe Size

<4 in.)

l l Valve Body Welds Volumetric Not applicable to l 812.40 B-M-1 Valves either Hatch r_Jt (Nominal Pipe Size l

14 in.)

l l

l l

I f

i l

l f

O O O TABLE I Sh.11 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS I AND 2 Examination System or Component Method of Code Relief Item No. Cateoory Description Areafsl to Be Examined Examination Requested 812.50 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 B13.20 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-1 No (BWR) Within Beltline Region i

D13.21 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-3 No (BWR) Beyond Beltline Region B13.22 B-N-2 Reactor Pressure Vessel Core Suppurt Structure Visual, VT-3 No (BWR) i B13.30 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-I Not applicable to (PWR) Within Beltline Region either Hatch unit B13.31 B-N-2 Reactor Pressure Vessel Interior Attachments Visual, VT-3 Not applicable to (PWR) Beyond Beltline Region either Hatch unit B13.32 B-N-3 Reactor Pressure Vessel Core Support Structure Visual, VT-3 Not applicable to (PWR) (Removed) olther Hatch unit B14.10 B-0 Reactor Pressure Vessel Welds in Control Rod Volumetric or Yes; 2.1.4 Drive Housing Surface and 2.1.9 i

i

_ _ _ . _ _ _ , - - _ _ _ _ _ _ _ _ . _> _ _ _ _ _ _ _ _ __m_____________________._.________t___._____._____________..._...m__

_ _ . _ . _ . -m .._..___m . _ . _. . ___- - -

J G TABLE I Sh.12 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. CatecorY Description Areafs) to Be Examined Examination Reavested 815.10 B-P Reactor Pressure Vessel Pressure Retaining System Leakage No Boundary Test; Visual, VT-2 B15.11 B-P Reactor Pressure Vessel Pressure Retaining System Hydro- No Boundary Test; Visual, VT-2 B15.20 B-P Pressurizer Pressure Retaining System Leakage Not applicable to Boundary Test; Visual, either Hatch unit VT-2 B15.21 B-P Pressurizer Pres >:re Retaining System Hydro- Not applicable to Boundary Test; Visual, either Hatch unit VT-2 B15.30 B-P Steam Generators Pressure Retaining System Leak- Not applicable to Boundary age Test; either Hatch unit Visual, VT-2 B15.31 B-P Steam Generators Pressure Retaining System Hydro- Not applicable to Boundary test; Visual, either Hatch unit VT-2

(~ (3

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TABLE I Sh.13 of 14 ISI PROGRAM FOR ASME CLASS I COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination . System or Component Nethod of Code Relief Item No. Category Description Areafs) to Be Exami,ed Examination Reauested 815.40 B-P Heat Exchangers Pressure Retaining System Leak- Not applicable to Boundary age Test; either Hatch unit Visual, VT-2 B15.41 B-P Heat Exchangers Pressure Retaining System Hydro- Not applicable to Boundary test; Visual, either Hatch unit VT-2 B15.50 B-P Piping Pressure Retaining System Leak- No Boundary age Test;

Visual, VT-2 B15.51 8-P Piping Pressure Retaining System Hydro- No Boundary test; Visual, VT-2 B15.60 B-P Pumps Pressure Retaining System Leak- No Boundary age Test; Visual, VT-2 B15.61 B-P Pumps Pressure Retaining System Hydro- No l Boundary test; Visual, VT-2 i

O O C TABLE 1 Sh.14 of 14 ISI PROGRAM FOR ASME CLASS 1 COMPONENTS EDWIN 1. HATCH NUCLEAR PLANT, UNITS I AND 2 Examination System or Component Method of Code Relief Item No. Cateoory Description Areafs) to Be Examined Examination Requested B15.70 B-P Valves Pressure Retaining System Leak- No Boundary age Test:

Visual, VT-2 B15.71 B-P Valves Pressure Retaining System Hydro . No Boundary test; Visual, VT-2 B16.10 B-Q Steam Generator Tubing Straight Tube Design Volumetric Not applicable to either~ latch unit B16.20 B-Q Steam Generator Tubing U-Tube Design Volumetric Not applicable to either Hatch unit Reactor Pressure Head Thickness Ultrasonic No; See Note 3 Vessel Closure Head Measurements 000307

. _ _ - _ - - _ _ _ _ _ - - _ _ _ _ - _ _ _ _ , - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ = _ _ _ _ _ _ _ - _ - _ - _ _ _ - . - _ - .

4 NOTES FOR TABLE 1 O (1) During each refueling outage, the reactor pressure vessel (RPV) closure studs are normally left in place; therefore, only a volumetric examination will be performed (ASME Section XI Table IWB-25001, item No.

B6.20). If the studs are removed, both a surface and volumetric examination will be >erformed (ASME Section XI Table IWB-25001, Item No.

B6.30).

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

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

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(' 3.0 CLASS 2 WITH RELIEF REQUESTS

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3.0.1 General '

l Table 2 provides a tabulation of the Class 2 pressure-retaining components subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition with Addenda through Winter 1981. These components will be inspected in accordance with the requirements of Subsection IWC to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination except where superceded or augmented by agreement with NRC in separate submittals. Where relief from the l inspection requirements of Subsection IWC is requested, information is provided which identifies the applicable Code requirements, justification for the relief request, and the examination method to be used as an alternative.

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

3.0.2 Hydrostatic Testina Hydrostatic testing will be conducted in a manner that will satisfy the l requirements of IWA-5000 and IWC-5000.

l 3.0.3 Weld Selection Criteria l

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As required by 10 CFR 50.55a (Code of Federal Regulations), the extent of examinations for all Class 2 ECCS piping welds was determined by the I

requirements of Paragraph IWC-1220, Table IWC-2520 (Category C-F and C G welds), and Paragraph IWC-2411 of Section XI, 1974 Edition with Addenda through Summer 1975. To make this plan even more comprehensive, those welds with high Sm values were selected for examination to the extent practical.

However, some exemptions such as pressure / temperature were not und for particular systems. The following summarizes the general weld selection criteria for Class 2 systems:

3.0.3.1 RHR. Core Sorav, and HPCI l

1. Examine all required welds within the 10 year interval using the 1974 Code with Addenda through Summer 1975 for selection and the 1980 Code with Addenda through winter 1981 for technique.

2. Apply high stress and terminal ends when practical.

3. Do n.01 use pressure / temperature exemption.

4. In addition to Code requirements examine (UT or surface as applicable) welds on branch connection lines greater than one inch in diameter that could impact safety related function of system out to the first closed manual valve, reverse check valve, or power operated valve. Otherwise, component connections, piping and associated valve:, and vessels (and

, (o their supports), that are 4 inches nominal pipe size and smaller are exempt.

000306 3-1

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5. Examine 100% of attachment welds within 10 years where the base material of the attachment is greater than or equal to 3/4 inches thick.

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( 3.0.3.2 Other Class 2 Systems l

As permitted in 10 CFR 50.55a, the remaining Class 2 piping welds were selected using the 1974 Edition of the Code with Addenda through summer 1975.

The following components were exempted per IWC-1220:

1. ' Components in systems where both the design pressure and temperature are equal to or less than 275 psig and 200*F., respectively.

2. Components in systems or portions of systems, other than emergency core cooling systems, which do not function during normal reactor operation.

3. Component connections, piping and associated valves, and vessels (and their supports), that are four inctes nominal pipe size and smaller.

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( 3.1.1.1 Reauirement From Which Relief is Reauested Item No. C1.10, C1.20, and C1.30 of Table IWC-2500-1 of ASME Section XI require the volumetric examination of Class 2 vessel shell circumferential, head circumferential, and tubesheet-to shell circumferential welds, respectively. The volumetric examination of the residual heat removal (RHR) system heat exchanger circumferential welds will be performed using ultrasonic techniques. The required examination volumes are shown in ASME Section XI Figures IWC 2500 1 and -2. Relief from this requirement is requested.

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

The evaluation below lists the percentage of examination coverage and the physical limitations for each unit.

Hatch Unit 1 There are three Category C A circumferential welds in each of the two RHR heat exchangers. These welds and their UT limitations are given below. (See

( Figure 4).

IEll - 2Hx-A(B)-1 Shell Head to Upper Shell Ring - These welds cannot be examined from the shell head side due to the curvature of the head.

Only about 65 inches of a total circumference of 179 inches (approximately 36 percent) can be examined from the upper shell ring side due to support interference.

IEll - 2Hx-A(B)-2 Upper Shell Ring to Lower Shell Ring - Complete coverage is obtained from the upper shell-ring side and 0-percent coverage from the lower shell ring side due to support interference.

IEll - 2Hx-A(B)-3 Lower Shell-Ring to Flange - Complete coverage is obtained from the lower-shell-ring side. Examination from the flange side cannot be performed due to the geometry.

000306 3-4

L Hatch Unit 2 o

C There are three Category C-A circumferential welds in each of the two RHR heat exchangers. These welds and their UT limitations are given below. (See ,

Figure 3).

2 Ell - 2Hx-A(B)-1 Shell Head to Upper Shell Ring --The!.e welds cannot be examined from the shell-head side due to the c avature of the head.

Only about 65 inches of a total circumference of 179 inches (approximately 36 percent) can be examined from the upper shell-ring side due to support interft.rence.

2 Ell - 2Hx-A(B)-2 Upper Shell-Ring to Lower Shell Ring - Complete coverage '

is.obtained from the upper shell-ring side and approximately 36 percent coverage from the lower shell-ring side due to support ,

interference.

2 Ell - 2Hx '(B)-3 Lower Shell-Ring to Flange - Complete coverage is '

obta.ned from the lower shell-ring side. Examination from the flange side cannot be performed due to the geometry.

3.1.1.3 Testina in Lieu of Section XI Reouirements The ultrasonic examination of the shell and head circumferential welds will be supplemented by a surface examination. The tubesheet-to-shell weld cannot be properly prepared for surface examination nor can the examination be performed due to the tubesheet studs and nuts adjacent to the weld, in addition to the

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examinations described above, system pressure tests per Article IWC-5000 of ASME Section XI will be performed on these welds.

l 3.1.1.4 Relief Reauest Status A. Relief granted by 9/29/86 SER, B. Relief affirmed by 6/22/89 SER.

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'3.1.2 SURFACE EXAMINATION OF WE'.DED ATTACHMENTS ON RHR, CORE SPRAY, HpCl, AND RCIC SUCTION LINES FROM TORUS O

3.1.2.1 Reouirement from Which Relief is Recue W A Item No. C3.20 of Table IWC 2500-1 of ASME Section L m :e 100 percent surface examination of integrally welded attachmeiss on piping. Figure IWC 2500-5 determines the surface area of this examination.

Suction lines for RHR, core sprey, !!PCI, and RCIC systems penetrating the torus are seal welded to the outside surface of the torus wall. Relief is requested from the surface examination of these welded attachments.

3.1.2.2 Justification At both Hatch units, these integrally welded attachments on lines penetrating ,

the torus are obstructed by reinforcemant plahs added after plant construction. The evaluation below lists the percentage of examination coverage and describes the physical limitations for each unit.

Hatch Unit 1 As shown in Figure 7, the suction piping is surrounded by reinforcing  !

ribs which may limit access on one or more sides of the pipe, in particular, when using magnetic particle techniques. This method is preferred since the torus has a heavy coating of paint, and removing the

, paint and cleaning the surface to perform penetrant examinations would be extremely difficult with the space limitations. As shown in Figure 7

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approximately 80 percent - 100 percent of the RCIC (lE51) and HPCI (IE41) welds can be examined, approximately 50 percent - 75 percent of the core spray (IE21) welds, and approximately 25 percent or less c? the RHR (IEll) welds.

t l Hatch Unit 2 As shown in Figure 8, the welds are totally inaccessible to perform surface examinations; therefore, a visual examination will need to be performed in lieu of the Code requirements.

l 3.1.2.3 Testino in lieu of Section XI Reouirements Hatch Unit 1 l The examinations will be performed to the extent possible as described in the previous paragraph, concerning Hatch Unit 1.

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Visual examination (VT-1) in accordance with IWA-2211 will be performed to insure the integrity of these attachments.

3.1.2.4 Relief Reauest Status -

A. -Limited Relief granted 9/29/86 SER.

B. Relief withdrawn by 9/8/8B submittal.

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l 3.1.3 SURFACE EXAMINATION OF PRESSURE RETAINING WELDS IN CLASS 2 PUMPS 3.1.3.1 Reauirement From Which Relief is Reauested Item No. C6.10 of Table IWC-2500-1 of ASME Section XI requires a surface I 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. j 3.1.3.2 Justification This relief request applies to the core spray pumps and RHR pumps on Hatch l Unit 2 only. The Hatch Unit 1 pumps have a different design and do not  ;

contain pressure retaining welds (Item No. C6.10). As shown in Fi ure 5, the pressure retaining welds 2 Ell-2RHR-PLP A-1 through -6 are complete y encased in the suction casing and can be accessed only when the pump is completely l l disassembled. These welds are not the welds considered to be pressure retaining pump casing welds; therefore, it is impractical to disassemble the pump (s) solely to examine these welds. (Note: At least one of the six pumps has been disassembled for maintenance and the welds examir.ed).

3.1.3.3 Testino in lieu of Section XI Reauirementi 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 the structural integrity of these pumps, while keeping exposure to radiation and contamination as low as reasonably achievable.

(]s 3.1.3.4 Relief Reauest Status l

A. Relief granted by 9/29/86 SER.

l B. Relief affirmed by 6/22/89 SER.

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i O O O TABLE 2 Sh. I of 4 i ISI PROGRAM FOR ASME. CLASS'2 COMPONENTS l EDWIN 1. HATCH NUCLEAR PLANT, UNITS 1 AND 2 l

l

( Examination System or Component Method of Code Relief l Item No. Category Description- Areafs) to Be Examined Examination Reauested.  ;

I C1.10 C-A Pressure Vessels Shell Circumferential Welds Volumetric Yes; 3.1.1 Cl.20 C-A Pressure Vessels Head Circumferential Welds Volumetric Yes; 3.1.1 C1.30 C-A Pressure Vessels Tubesheet-to-Shell Weld Volumetric Yes; 3.1.1 C2.11 C-B Pressure Vessels Nozzles-to-Shell (or Head) Surface Not applicable to Weld Where Vessel Nominal either Hatch unit Thickness s 1/2 inch

, C2.21 C-B Pressure Vessels Nozzle-to-Shell (or Head) Surface and No Weld for Vessels Without Volumetric Reinforcing Plates Where Vessel Nominal Thickness

>l/2 inch Ct. 2 C-B Pressure Vessels Nozzle Inside Radius Volumetric No Section for Vessels with-out Reinforcing Plates

Where Vessel Nominal Thickness >l/2 inch C2.31 C-B. Pressure Vessels Reinforcing Plate Welds to Surface Not applicable to Nozzle and Vessel either Hatch unit Where Vessel Nominal Thickness >I/2 inch w

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TABLE 2 Sh. 2 of 4 ISI PROGRAN FOR ASNE CLASS 2 CONPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNIT 5 1 AND 2 Examination System or Component .

Nethod of Code Relief Item No. Category Description Areafs) to Be Examined Examination Reauested ,

C2.32 C-B Pressure Vessels Mozzle-to-Shell-(or Head) Vo' > metric - Not' applicable to

' elds for Vessels With Re-w either Hatch unit enforcing Plates Where Vessel Nominal Thickness .

>l/2 inch C3.10 C-C Pressure Vessels Integrally Welded Surface No Attachments' C3.20 C-C Piping Integrally Welded Attachments Surface No l'

C3.30 C-C Pumps Integrally Welded Surface Not applicable to Attachments either Hatch unit-C3.40 C-C Valves Integrally Welded Surface Not applicable to Attachments either Hatch unit C4.10 C-D Pressure Vessels Bolts and Studs Volumetric' Not applicable to either Hatch unit C4.20 C-D Piping Bolts and Studs Volumetric Not applicable to either Hatch unit C4.30 C-D Pumr- Bolts and Studs Volumetric Not applicable to -

either Hatch unit C4.40 C-D ,

Bolts and Studs Volumetric Not applicable to i either Hatch unit s

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O O O TABLE 2 1Sh. 3 of 4 ISI PROGRAM FOR ASNE CLASS 2 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 l

Examination System or. Component Method of Code Relief Item No. Category DescriDtior: Areafs)'to Be Examined Examination Reouested C5.11 C-F Piping Circumferential Welds Surface No (Nominal Wall Thickness 51/2 in.)

C5.12 -C-F Piping Longitudinal Welds Surface No (Nominal Wall Thickness

$1/2 in.)

C5.21 C-F Piping Circumferential Welds Surface and No (Nominal We.ll Thickness Volumetric

>l/2 in.)

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

l (Nominal Weil Thickness Volumetric  :

! >l/2 in.)  !

C5.31 C-F Piping Circumfr.rential Welds Surface No Pipe Branch Connections .

(Nominal Pipe Size

>4 in.)

C5.32 C-F Piping Longitudinal Welds Surface Not applicable to

, Pipe Branch Connections either Hatch unit' (Nominal Pipe Size

>4 in.)

l C6.10 C-G Pumps Pump Casing Welds skrface Yes; 3.I.3 C6.20 C-G Valves Valve Body Welds -- Surfice Not applicable to either Hatch unit k

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TABLE 2 Sh. 4 of'4-ISI PROGRAM FOR ASME CLASS 2 CC/PONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination Reouested i

07.10 C-H Pressure Vessels Pressure Retaining System Pres- No Components sure Test;- ,

Visual, VT-2 i C7.20 C-H Pressure Vessels Pressure Retaining System Hydro- No Components static Test; Visual, VT-2 C7.30 C-H Piping Pressure Retaining System Pres- No '

Components sure Test; Visual, VT-2 C7.40 C-H Piping Pressure Retaining Components System Hydro-static Test; No, RR 4.1.3 not presently used l4 Visual, VT-2 07.50 r-4 Pumps Pressure Retaining System Pres- No Components sure Test; Visual, VT-2 C7.60 C-H Pumps Pressure Retaining System Hydro- No Components static test; Visual, VT-2 C7.70 C-H- Valves Pressure Retaining System Pres- No Components sure Test; Visual, VT-2 C7.80 C-H Valves Pressure Metaining System Hydro- No Components static Test; Visual, VT-2 1

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- p 4.0 CLASS 3 COMPONENTS WITH RELIEF REQUESTS Id Table 3 provides a tabulation of the Class 3 pressure-retaining components subject to the inspection requirements of Subsection IWD of Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition with Addenda through Winter.

1981'. These: components will be inspected in accordance with Subsection LWD to

'the extent practical with the exception of the relief requests outlined in Paragraph 4.1 below or as superceded or augmented by agreement with NRC in separate submittals. Table IWD-2500-1 items not applicable-to Plant Hatch have also been listed and identified in the interest of completeness.

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4.1.2 SYSTEM PRESSURE TESTS ON CLASS 3 BURIED PIPING 4.1.2.1 Reauirement From Which Relief is Reauested

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Table IWD 2500-~1 of ASME Section XI requires a system pressure test for Class 3 components including buried piping.

i 4.1.2.2 Justification l The'fo110 wing portions of systems were designed without including provisions for testing buried piping as required by Paragraph IWA 5244. i Hatch Unit No. 1 Plant service water system from the valve pit at the intake structure to the diesel generator building and from the valve pit to the reactor building wall.

RHR service water system from the valve pit at the intake structure to the reactor building wall.

Reactor core isolation cooling system from valve IE51-F009 to valve IE51-F010.

High pressure coolant injection system from valve IE41-F004 to valve IE41-F010.

lLatch Unit No. 2 Plant service water system from the valve pit at the intake structure to the f diesel generator building and from the valve pit to the reactor building wall.

RHR service water system from the valve pit at the intake structure to the reactor building wall.

-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 Testino in Lieu of Section XI Reauirements Normal system functional testing demonstrates leaktight integrity of all safety-related buried piping.

4.1.2.4 Relief Reauest Status A. Not addressed by 9/29/86 SER.

B. Relief granted by 6/22/87 SER, C. Added Unit 2 information - Relief granted by 6/22/89 SER.

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' 4.1.3.1 Reauirement from Which Relief is Reauested IWC-5222 and IWD 5223 of ASME Section XI requires that Class 2 and 3 systems be tested at a pressure of 1.10 or 1.25 times the design pressure. Relief is -I requested from testing those portions where it is necessary to use a butterfly valve six inches in diameter or greater as a hydrostatic test boundary valve.

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

1 4.1.3.3 Testino in lieu of Section XI Reauirements Since there are no viable means to test those portions of the system described I above at a higher pressure, a hydrostatic test at normal operating pressure -

(i.e., system functional test or system inservice test) will be performed on those portions of these systems which have a. butterfly valve six inches in diameter or greater.  ;

4.1.3.4 Relief Reauest Status A. Relief granted by 9/29/86 SER.

B. Valve size changed from 10 to 6 inch - Relief granted by 6/22/89 SER.

000305 4-5

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4.).4 SYSTEM PRESSURE TESTS ON CLASS 3 TUBING 1 INCH IN DIAMETER 4 .1' . 4 .1 Reovirement from Which Relief is Reauested Table IWD 2500-1 of ASME Section XI requires that a system functional (or inservice) test and a system hydrostatic test be accomplished for the pressure retaining boundary. Relief is requested from visually examining small instrument tubing 1 inch in diameter in the plant service water (PSW) system and the RHR service water (RHRSW) System which does not provide a cooling function for a safety-related component.

4.1.4.2 Justification [

These lines do not provide cooling water to safety related equipment; therefore, loss of the line would not cause loss of a safety related component. In addition, leakage through the tubing would not degrade the i overall capability of these service water systems, since such flow would be negligible when compared to the rated flow of the pumps (PSW 8500 gpm each-pump and RHRSW 4000 gpm each pump). ,

l 4.1.4.3 Testino in lieu of Section XI Reauirements All pipin9 21 inch providing a safety-related function will be pressure tested, in addition, any tubing providing cooling water to a safety-related component will also be pressure tested.

' 4.1.4.4 Relief Reauest Status r

!  ! A. Relief denied by 6/22/89 SER.

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l TABLE 3 iShc l' of 3 ISI PROGRAM FOR ASME CLASS.3 COMPONENTS . .

EDWIN 1. HATCH NUCLEAR PLANT, UNITS I AND 2 Examination System or Component .

Method of Code Relief '

Item No. Category DescriDtion Areafs) to Be Examined Examination Reouested ,

DI.10 D-A Systems in Support of Pressure Retaining Visual,'VT-2 Yes; 4.1.1, 4.1.3, Reactor Shutdown Function Components and 4.1.2.

D1.20 D-A Systems in Support of. Integral Attachment- Visual, VT-3 No Reactor Shutdown Function Component Supports.and Restraints 01.30 0-A Systems in Support of Integral Attachment- Visual, VT-3 No Reactor Shutdern Functien Mechanical and Hydraulic Snubbers D1.40 D-A Systems in Support of Integral Attachment- Visual, VT No Reactor Shutdown Function Spring Type Supports  ;

i D1.50 D-A Systems in Support of Integral Attachment- Visual, VT-3 No Reactor Shutdown Function Constant Load Type Supports 01.60 D-A Systems in Support of Integral Attachment- Visual, VT-3 No Reactor Shutdown Function Shock Absorbers

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TABLE 3 Sh. '2 of 3 '

ISI PROGRAM FOR ASME CLASS 3 COMPONENTS EDWIN~I. HATCH NUCLEAR PLANT, UNITS I'AND 2 Examination System or Component' _

Method of Code Relief Item No. Category Description' Area (s) to Be Examined Examination. Reouested D2.10 D-B Systems in Support of ECC, CHR, Atmosphere Pressure Retaining Components Visual, VT-2 Yest 4.I.2, 4.I.3 l

Cleanup, and Reactor RHR D2.20 D-B Systems in Support of Integral Attachment- Visual._VT-3 No ECC, CHR, Atnosphere Components Supports and Cleanup,'and Reactor.RHR Restraints 02.30 D-B Systems in Support of ~ Integral Attachment- Visual, VT-3 No ECC, CHR, Atmosphere Mechanical and Hydraulic Cleanup, and Reactor RHR Snubbers D2.40 D-B Systems in Support of Integral Attachment- Visual, VT-3 No ECC, CHR, Atmosphere Spring Type Supports Cleanup, and Reactor RHR D2.50 D-B Systems in Support of Integral Attachment- Visual, VT-3 No ECC, CHR, Atmosphere Constant load Type Cleanup, and Reactor RHR Supports D2.60 D-B Systems in Support of Integral Attachment- Visual, VT-3 No ECC, CHR, Atmosphere Shock Absorbers Cleanup, and Reactor RHR

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TABLE 3 . Sh. 3 of 3 ,

ISI. PROGRAM FOR ASME CLASS 3 COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination _Recuested D3.10 0-C Systems in Support of Pressure Retaining Visual, VT-2 No RHR from Spent Fuel Components Storage Pool -

D3.20 D-C Systems in Support of Integral Attachment- Visual, VT-3 No RHR from Spent Fuel Component Supports and Storage Pool Restraints 03.30 D-C Systems in Support of Integral Attachment- Visual, VT-3 No RHR from Spent Fuel Mechanical and Hydraulic Storage Pool Snubbers l D3.40 D-C Systems in Support of Integral Attachment - Visual, VT-3 No RHR from Spent Fuel Spring Type Supports Storage Pool i D3.50 D-C Systems in Support of Integral Attachment- Visual, VT-3 No l RHR from Spent Fuel Constant Load Type-Storage Pool Supports D3.60 0-0 Systems in Support of Integral Attachment- . Visual, VT-3 No RHR from Spent Fuel Shock Absorbers Storage Pool i

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5.0 CLASS 1, 2, AND 3 SUPPORTS Wi1H REllEF REQUESTS Table 4 provides a tabulation of the Class 1, 2, and 3 component supports subject to the inspection requirements of Subsection IWF,Section XI of the ASME Boiler and Pressure Vessel Code,1980 Edition with Addenda.through Winter 1981. These components will be inspected in accordance with the requirements of Subsection IWF.to the extent practical. This tabulation identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination. Where relief from the inspection requirements of Subsection IWF is requested, information.is provided which identifies the applicable Code requirements, justification for i the relief request, and the examination method to be used as an alternative.

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

Paragraph IWi-1230, Supports Exempt from Examination and Test, is in the course of preparation. Later Addenda through Winter 1984 of Section XI do not provide guidance for the exemption criteria for these components. Georgia '

Power company has therefore decided to incorporate the exemption criteria for Class 1, Class 2, and Class 3 component supports found in Paragraphs IWB-1220, IWC-1220, and IWD 1220 of ASME Section XI, respectively.

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O 000305 5-2

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i l 5.1.1 REQUIREMENT TO VERIFY HOT OR COLD SETTINGS ON SPRING CANS AND SNUBBERS 5.1.1.1 Reauirement From Which Relief is Reauested Subparagraph IWF-3410(a)(5) of ASME Section XI states that a component support l condition which is unacceptable for continued service is improper hot or cold L positions for spring supports or snubbers. Relief from this requirement is l requested.

5.1.1.2 Justification l

There are no exact design positions on the scales for spring supports or l snubbers but an operational range where the indicator should be located. l Georgia Power Company will verify that the spring support is .in the operable range olus acceptable tolerances; i.e., within analyzed hot and cold load ,

settings. The support may not exactly show the precise hot or cold setting l because the analysis may have used a conservative temperature; i.e., the plant l may not see the temperature analyzed of that specific system on the specific I day when the inservice inspection was performed. The intent of the-inspection is to verify that the spring can is not outside the range specified in the _l analysis and that the can is not bottomed out.

l 5.1.1.3 Testina in Lieu of Section XI Reauiremt ,

The visual examination will verify that the indicator falls within the l operational limits. j 1

5.1.1.4 Relief Reauest Status 1 i

A. Relief granted 9/29/86 SER. ,

L B. Relief affirmed by 6/22/89 SER. l l

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~ 5.1.2 -TESTING Of HYDRAULIC AND MECHANICAL TYPE SNUBBERS 5.1.2.1 Reauirement From Which Relief is Reauested Article IWF-5000 of ASME Section XI outlines the inservice test requirements for hydraulic and mechanical type snubbers. Relief from this requirement is requested.

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

5.1.2.3 Testina in lieu of Section XI Recoirements As noted in 5.1.2.2, the testing program per the Plant Technical Specifications will be performed.

5.1.2.4 Relief Reauest Status

!- A. Relief deemed unnecessary. Technical Specification testing satisfies code. See9/29/86SER.

O B. Position affirmed by 6/22/89 SER.

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000305 5-4 17

O O O TABLE 4 Sh. I of 3 "ISI PROGRAM FOR ASME CLASS 1, 2 AND 3 SUPPORT COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component Method of. Code Relief:

Item No. Category' Description Area (s) to Be Examined Examination Reouested F1.10 F-A Plate and Shell Mechanical Connections to Visual, VT-3 Not applicable to Type Supports Pressure Retaining either Hatch unit Components and Building Structure F1.20 F-A Plate and Shell Weld Connections to. Visual, VT-3 Not applicable to-Type Supports Building Structure either Hatch' unit -

Fl.30 F-A Plate and Shell Weld and Mechanical Visual, VT-3 Not applicable to Type Supports Connections at Intermediate either Hatch unit Joints in Multiconnected Integral and Nonintegral Supports Fl.40 F-A Plate and Shell Component Displacement Visual, VT-3 Not applicable to Type Supports Settings of Guides and either Hatch unit Stops, Misalignment of Supports, Assembly of Support Items

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

o. nation E CLASS 01

. Category System EDWIN I. HATCH NUCLEAR  % PLA2, AND 3 SUPPOR F2.10 Descriptionor Component F-8 NT.UNITSIAND'2h Linear Type Supports Area (s) to Be Examined "Nik Method lst '- _

Mechanical ~,

F2.20 Examination 3 F-B ComponentsPressure RetainingConnections Visual, ViiMyff -

to Structures and Building 3Qihn F2.30 tinear Type Supports 7%ftelti F-8 EN%1 -

Linear Type Supports Building StructureWeld Connections NEo%

to Visual, VT-3 r g

Weld and Mechanical ..,

F2.40 Connections Visual, VT-3 either Hatch unitNo F-B Integral and eNonintegralJoints Supports in Multiconne Not applicable to Linear Type Supports either Hatch unit SettingsComponent Displacement Stops of Guides and Visual, VT-3 Suppor,ts, Assembly ofMisalignmentNot Support Items ofapplicable to 1

either Hatch unit

Y-TABLE 4 Sh. 2Lof-3i ISI PROGRAM FOR ASME CLASS 1, 2, AND 3 SUPPORT COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS-I AND 2 Examination- System or Component. Method of Code Relief Item No. Category Description Areafs) to Be Examined Examination Reauested F2.10 F-B Linear Type Supports- Mechanical Connections to Visual, VT-3 Not applicable to Pressure Retaining either Hatch unit Components and Building Structures >

F2.20 F-B Linear Type Supports Weld Connections to Visual, VT-3 Not applicable to Building Structure either Hatch unit F2.30 F-B. Linear Type Supports Weld and Nechanical . Visual, VT-3 Not anolicable to Connections at Intermediate either Hatch unit Joints in Multiconnected.

Integral and Nonintegral Supports F2.40 F-B Linear Type Supports Component Displacement Visual, VT-3 Not applicable to Settings of Guides and either Hatch unit Stops, Misalignment of Supports, Assembly of Support Items I

- .../.- ... .. ,,n _ ___..__, _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

O O O TABLE 4 ' Sh. 3 of 3 '

ISI PROGRAM FOR ASME CLASS 1, 2, AND 3 SUPPORT COMPONENTS EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 Examination System or Component . Method of Code Relief Item No. Category DescriDtion Areafs) to Be Examined Examination Requested F3.10 F-C - Component Standard Mechanical Connections to Visual, VT-3 No Supports Pressure Retaining Components and Building Structure F3.20 F-C Component Standard Weld Connections to Visual, VT-3 No Supports Building Structure F3.30 F-C Component Standard Weld and Mechanical Visual, VT-3 No Supports Connections at Intermediate Joints in Multiconnected Integral and Nonintegral Supports F3.40 F-C Component Standard Component Displacement Visual, VT-3 Not applicable to Supports Settings of Guides and either Hatch unit Stops, Misalignment of Supports, Assembly of Support Items F3.50 F-C Component Standard Spring. Type. Supports, Visual, VT-4 Yes; 5.1.1 and Supports Constant load Type Supports, S.I.2 Shock Absorbers, Hydraulic '

and Mechanical Type Snubbers.

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i 6.0 GENERAL REllEF REQUESTS I]:

Georgia Power Company also has several relief requests which do not apply-

directly to any individual section but are general in nature. Prior to Revision 3 of the ISI Program, this section was numbered 8.0. With the deletion of IST from this document, the new numbering. scheme was required. All SER references to these reliefs will begin with an "B" instead of a "6".

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6.1.1 BASIC CAllBRATION BLOCKS FOR PIPE WELD EXAMINATIONS l

~O 6.1.1.1 Reauirement from Which Relief is- Reauested I

Appendix III of Section XI delineates the requirements for the design and fabrication of basic calibration blocks for pipe weld examinations. . It specifies that the basic calibration block shall be fabricated with notches and

-the basic calibration block nominal diameter and thickness be equivalent to the component to be examined. Relief is requested so that existino basic calibration blocks may be used for pipe weld examinations.

6.1.'l.2 Justification g

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

reasons listed below, these same basic calibration blocks will be used to 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 l basic calibration blocks be used so future examination results can be  ;

correlated with past results. '

O V 6.1.1.3 Testina in lieu of Section XI Reauirements l

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The basic calibration blocks using side-drilled holes as calibration reflectors will be used for the majority of the pipe weld examinations.

l 6.1.1.4 Relief Reauest Status I A. Relief granted by-9/29/86 SER.

B. Relief denied by 6/22/89 SER.

000305 6-3

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6.1.2 ALLOW HATCH 2 TO START ITS SECOND 10 YEAR INSPECTION INTERVAL ON

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JANUARY-1, 1986 6.1.2.1 Reauirement from Which Relief is Reauested According to 10 CFR Part 50.55a(g)4(ii), inservice examination of components during successive 120-month inspection intervals shall comply with the requirements of the latest edition and addenda of the approved ASME Section XI Code 12 months prior to the start of the 120 month inspection interval.

Permission,is requiested to start the Hatch 2 second 10-year inspection interval ahead of schedule such that the two Hatch units would be under the same edition and addenda of the Code. The second 40-month inspection period for Hatch 2 ended on May 5, 1986. Hatch 2 would normally update for the second 10-year inspection interval in September 1989.

6.1.2.2 Justification g The Inservice Inspection requirements for Hatch I are presently in compliance with ASME Section XI, Winter 1981 Addenda, effective January 1, 1986. A move to start the second 10-year interval for Hatch 2 on January 1,1986, would require compliance with ASME Code Section XI, Winter 1981 Addenda, which is more stringent. A more comprehensive inspection would be achieved. In addition, compliance with the same Code for both units will enhance the possibility of detecting a generic problem and would also reduce cost involved in maintaining two separate programs. The PRV welds will also be examined at the same point in l ,

time as was planned in the earlier program (i.e., those welds that were scheduled during the third 40-month period will be examined during the first 40-month period of the new 10 year interval). In discussions with the NRC HNP '

licensing project manager and appropriate NRC staff personnel, they have indicated that this is a reasonable approach. The proposed change will not endanger public health and safety.

6.1.2.3 Testina in Lieu of Section XI Reauirements l None.

6.1.2.4 Relief Reauests Status A. Relief granted by 9/29/86 SER.

B. Relief affirmed by 6/22/89 SER.

000305 6-4

1 7 6.1.3 INCORPORATION OF CHANGES IN DESIGN, TESTING, AND PROCEDURES WITHOUT --

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V ANY UNREVIEWED SAFETY QUESTIONS INTO THE INSERVICE INSPECTION PROGRAM / PLAN p 6.1.3.1 Reauirement From Which Relief is Reauested

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I 10 CFR Part 50.59 allows changes to a nuclear facilty and procedural changes in accordance with Plant Technical Specifications and the safety analysis report, without prior approval from the NRC, provided there are no unreviewed safety questions. The facility's Inservice Inspection Program / Plan should be revised l to include these changes.  ;

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

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

6.1.3.2 Justification l Records of these changes will be maintained and changes in ASME Section XI requirements pertaining to these changes will be complied with. However, a revision to' the ISI Program Plan (s) for every minor change is an unrealistic,  :

costly, and time consuming task. Any delay in revising the ISI program plan (s) will not endanger public health and safety.

p 6.1.3.3 Testino in lieu of Section XI Reauirements g Records of all changes will be maintained. Changes affecting ASME Section XI' requirements shall be incorporated into the ISI Program Plan (s) whenever a need for their update is warrantged.

6.1.3.4 Relief Reauest Status i

A. Relief granted, with conditions, by 9/29/86 SER.

B. Relief and conditions affirmed by 6/22/89 SER.

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000305 6-5 l

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6.1.4 EXEMPTING SUBSECTION IWE, AND THE REFERENCESLTO IWE IN OTHER SUBSECTIONS l 6.1.4.1 Reauirement from Which Relief is Reauested 1

Table IWE-2500-1, Code categories E-A, E-A 1, E-B, E-C, E-D, E-E, E-F, E-G, and E-P of ASME Section XI, Winter 1981 Addenda delineates examination requirements of containment.

6.1.4.2 Justif;gp11e Federal Register, vol. v.. ' 2. 28/ Monday, February 7, 1983, Page 5532 relative to 10 CFR Part 50 Cod s LK Standards for Nuclear Power Plants; Item No. 4, indicates that Subsection IWE " Requirements for Class MC Components of Light '

Water Cooled Ponr !"sats" was added to Section XI by the Winter 1981 Addenda.

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

6.1.4.3 Testina in lieu of Section XI Reauirements l

None.

'V 6.1.4.4 Relief Reauest Status 1 A. Relief deemed unnecessary (IWE not required) by 9/29/86 SER.

B. Position affirmed by 6/22/89 SER.

000305 66 l O  !

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6.1. 5' ' DVE DATE FOR OWNER'S-DATA REPORT'FOR INSERVICE INSPECTION, FORM NIS-l'

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$,) ' Relief Request 8.1.5 has been withdrawn (2/24/88 submittal).

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6.1.6 REFERENCE SYSTEM FOR ALL WELDS AND AREAS SUBJECT TO SURFACE OR l VOLUMETRIC EXAMINATION 6.1.6.1 Reauirement From Which Relief is Reauested g Section IWA 2600 of ASME Section XI, with Addenda through Winter 1981, requires the establishment of a reference system for all welds and areas subject to surface or volumetric examination. This system shall permit identification of ,

each weld, the location of each weld centerline, and marking at regular intervals along the length of each wcid. Relief from this requirement is requested.

6.1.6.2 Justification g At Hatch Units 1 and 2, physical and radiological limitations prevent the actual marking of the majorit,r of the RPV welds, nozzle welds, and piping welds. In many instances, these limitations actually prohibit complete exar.ination of the welds. Relief requests have already been submitted herein for the welds which cannot be completely examined and thus will be examined to the extent possible.

Many of the welds which could be accessed are covered by insulation, it would be inappropriate to require the manhours of exposure involved to remove and replace the insulation to facilitate marking.

Each weld that has been or will be examined is referenced to permanently located fixtures in the immediate area of the subject weld. These references included such items as nozzles, plant azimuth and floor identifications, welded O attachments, and concrete embedments. Each weld is described in the inspection plan and on the examination reports in such a manner as to make it unique.

For each weld that is examined, the starting point is identified and the direction of travel is noted on the examination report in order than any indications can be accurately located. The configuration of the welds at Hatch permits the inspectors to locate the weld edges which are used to locate the weld centerline.

6.1.6.3 Testina in Lieu of Section XI Reauirements l None.

6.1.6.4 Relief Reauest Status A. Relief granted, with conditions, by 6/22/89 SER.

000305 6P

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INSERVICE TESTING PROGRAM O

SECOND IO -

YEAR INTERVAL ISI/IST APPROVAL

• • 'm E. I. HATCH NUCLEAR PLANT

.r itten by: E 70 D er f.

neviewed by al/d dd*

UNIT 5 l AND 2 Eng. Supr A Mgr.Eng* db b t -

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PR8 No.: 98"i2'1 l Agy.PS: [ Y O M I E *A '

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REV'D SY M,' W hki w, MER* MGR. MGR. OF ICE ,

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8/1/90 ISSUED FOR APPROVAL gj,/g p/,f9, e ,[$r 3/sep e/ove, e/WD

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- --y e-., .n- . . - . . - -.-.- - - - _ _ _ _ - - - _ . . - - - - - - - - - - -- . - - _ . - - - _ - - _ _ _ . . - _ - - . - - - - . - - - - - - , .

HATCH NUCLEAR PLANT IST PROGRAM

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Holder Manual Number E. C. Sorrell (Document Control) 1 _

M. Belford (ITS) 2 T. N. Epps (ITS) 3 l

B. K. McLeod (HNMS) 4 J. D. Heidt (HNEL) 5 E. M. Burkett (GPC) 6 D. M. Swann (ITS) 7 J. L. Wilkes (GPC Hatch) 8 Site ANil (c/o Q.C. Supt.-Hatch) 9

0. M. Fraser (GPC Hatch) 10 ,

l J. C. Lewis, Jr. (GPC Hatch) Il I

NRC Site Inspector Hatch 12

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J. C. McWhorter (ITS) 13 i

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TABLE OF CONTENTS

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Section Pages i

1.0 Introduction I thru 2

' Abbreviations ,

I thru 2 i 1

2.0 Valve Testing )l Introduction 1 thru 6 '

Notes 1 thru 3 )

t Table 1 1 thru 75 l Table 2 1 thru 80 3.0 Pump Testing l

! Introduction 1 thru 2 Notes 1 Table 3 1 thru 5 e Table 4 1 thru 5 4.0 Valve Relief Request l

Log 1 Relief Requests 42 pages 5.0 Pump Relief Requests ,

1 Log 1 l

Relief Requests 14 pages 6.0 Cold Shutdown Justifications Log 1 3

CS Justifications 13 pages 7.0 General Relief Requests log 1 Relief Requests 1 page 1

000953 e

1.0 IST PROGRAM INTRODUCTION i g

C 1.1 GENERAL This document describes the revised Inservice Testing (IST) Program for Edwin

1. Hatch Nuclear Plant, Units 1 and 2. -

This Program meets, to the extent practical, the requirements of the 1980 Edition of Section XI with Addenda through Winter 1981.

NRC. Generic Letter 89-04 has been used for guidance in the development of this program.

1.2 EFFECTIVE DATE The IST Program, for the Second Ten Year Interval became effective on January 1, 1986.

1.3 SL0E This document is a description of the IST Programs to be implemented for Units 1 and 2 of Plant Hatch. This document contains only the IST surveillance testing applicable to pumps and valves included in the program.  ;

1.4 COMPONENT UPGRADING All plant components have been reviewed to determine the appropriate O

d classification for inservice testing. Regulatory Guide 1.26 was used for guidance in determining coinponent classifications.

Note that the classification of pumps and valves as ASME Class 1, 2, or 3 -

equivalent for this program does not imply that the components were designed in accordance with ASME requirements. Pump and valve design remains as stated i in the FSAR.

1.5 SUBSE0 VENT PROGRAM REVISIONS It is anticipated that this Program will.be reviewed again near the end of the 120 month inspection interval and compared to a later Nuclear Regulatory Commission (NRC) approved edition and addenda of ASME Section XI. At that <

time,.the Program will be modified, if required, to comply to the extent practical with the later code edition. Any additional relief requests for impractical requirements will be submitted per 10 CFR 50.55a(g)5(iii).

1.6 RESPONSIBILITY Georgia Power Company, as owner, bears the overall responsibility for the performance of the inservice testing activities in this program per ASME Section XI, IWA-1400.

O d 000953 1

r^'s 1.7 RECORDS

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Records and documentation of information and testing results, which provide the basis for evaluation and which facilitate comparison with resbits from previous and subsequent tests, will be maintained and available for the active life of the component or system in accordance with Section XI, IWA-f000.

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1.8 METHODS OF TESTING The method of testing applicable to pumps and valves is listed adjacent to each component identification in sections 2.0 and 3.0 of this program.

ASME Section XI does not stipulate any training /certificatier. requirements for l personnel involved in pump and valve testing. At Plant Hatch, all pump and '

valve testing is performed by operations, maintenance or engineering department personnel who have been trained to perform specific testing tasks.

l 1.9 STANDARDS FOR TESTING EVALUATION The acceptance criteria applicable for each pump and valve to be tested have l been developed in accordance with ASME Section XI requirements as modified by applicable relief requests. Acceptance criteria are not provided in the IST

, Program but are supplied in the IST Plans which are available for review at  ;

the plant site. The acceptance criteria are also provided in the IST l surveillance procedures for use by testing personnel in evaluating test l

results. l l

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Pr.g3 No. 1 \

08/13/90 ygtyg ABBREVIATIONS

, ABBREVIATION DEFINITION

~- AO Air Operated Act Actuation -

Analy Analysis Bfly Butterfly -

Bldg Building ,

Brker Breaker .

C Closed CIV Containment Isolation Valve CS ' Cold Shutdown CS Core Spray Cham Chamber Ck Check

!- Cond Condensate Cont Containment DG Diesel Generator DW Drywell Depress Depressurization Disassemb Disassemble nisc Discharge Disch Discharge Drn Drain Equip Equipment Exh Exhaust Expl Explosive TW Teedwater Flr Floor Gen- Generator H2 H drogen f ~s HCU H draulic Control Unit HPCI H gh Pressure Coolant

\- / In]ection Heating, Ventilating and Air HVAC Conditioning Hx Heat Exchanger ISO Isolation Inbrd Inboard Inj Injection In3ec In]ection Inst Instrument LC Locked Closed '

LPCI Low Pressure Coolant Injection LTV Leak Tight Valve MO Motor Operated MSIV Main Steam Isolation Valve MSRV Main Steam Relief Valve Man Manual Min Minimum Mon Monitoring N2 Nitrogen O Open O/C Open/ Closed ,

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PT:g3 No. 2 08/I3/90 yggyg AggREVIATIONS

• ABBREVIATION DEPINITION l I i/ O2 Oxygen Outbrd Outboard .

PIV Pressure Isolation Valve Press Pressure -

Prod Products -

Purif Purification .

Otr Quarterly -

RBCCW Reactor Building Closed Cooling Water RCIC Reactor Core Isolation Cooling RHR Residual Heat Removal RHRSW Residual Heat Removal Service Water RO Refueling Outage '

RWCU Reactor Water Clean Up Reac Reactor Recire Recirculation Recom Recombiner Redun Redundant SGTS Standby Gas Treatment System SLC Standby Liquid Control SO Solenoid Operated SW Service Water Ser Service Sol Solenoid Stg Storage Stor Storage Sua Suction f'%g Suct Suction Supp Suppression (d Sys System TIP Transversing Incore Probe i Test Testable l Turb Turbine

! Vac Vacuum l Wkly Weekly

( Wtr Water 9

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2.0 INSERVICE TESTING OF VALVES 2.1 GENERAL This Program is written to comply with the testing rtovisions of 10 CFR 50.55a(g) which delineate the testing requirementn for ASME Class 1, 2, and 3 valves. The Code of record used to meet these provisions is the ISSO Edition of ASME Section XI, with Addenda through Winter *,981 as modified by supplemental guidance from the NRC's Generic Letter 89-04, in cases where specific Code requirements cannot ba met, relief has been r'squested from these requirements. J Valves in the program are listed by MPL Nunoer in Tables 1 and 2 for Units 1 and 2, respectively, and will be tested in accordance with the Code unless otherwise specified in this program. Several features of the Hatch program  !

are discussed below.

l 2.2 SCOPE l l

Safety-related ASME Class 1, 2, and 3 valves falling under the Regulatory i Position of Regulatory Guide 1.26 are tested using the provisions of ASME Section XI.

It is recognized that 10 CFR 50 Appendix A, GDC-1, and Appendix B, Criterion XI intend that all valves necessary for safe operation of the plant be tested to demonstrate that they will perform satisfactorily in service. This testing is to be performed to a level commensurate with the function of the valve. This testing is generally performed per the requirements of the plant Technical c Specifications or other requirements. For example, the RCIC System valves that

( do not perform a containment isolation function and the Diesel Generator fuel Oil Transfer and Air Start System valves, have been included in this Program to provide a readily accessible, documented method of testing. This testing will be performed in a method similar to that found in Section XI, and should adequately detect degradation in these particular valves.

The Spent Fuel Pool Cooling System valves have not been included in this Program because they are not safety-related. in addition, credit is taken in the FSAR for Plant Service Water as the safety-grade makeup wurce, and the RHR system is >

used as the backup cooling source.

The Core Spray Jockey Pump System valves have not been included in this Program because they are not safety-related.

2.3 STARTING POINT FOR TIME PERIOD IN TECHNICAL SPECIFICATIONS ACTION STATEMENTS t

When performing valve testing, as soon as it is recognized that a power operated valve has exceeded its limiting value of full-stroke time, the valve will be declared inoperable and the applicable Technical Specifications Action Statement entered, l

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2.4 FULL-FLOW TESTING OF CHECK VALVES

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for each check valve in this Program that is required to open to perform a

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safety-related function, the full stroke to the open position will be verified by passing the design accident flow through the valve. If the design accident flow rate is not specified, the flow rate required to fulfill the, safety related function of the valve or system will be verified.

2.5 ALTERNATIVE TO FULL-FLOW TESTING Whenever it is not practical to verify sufficient flow to prove the full-stroke opening of a check valve or closure of a valve cannot be verified through a positive means, the valve will be inspected using a sample disassembly program.

During disassembly the valve disk will be manually exercised and the internals inspected for worn or corroded parts: This type testing is designated by "disassemb" in tP exercise column of Tables 1 and 2.

The grouping of valves and the frequency of inspection will be conducted per the guidelines of Generic letter 89 04, Position 2.

2.6 BACK FLOW TESTING OF CHECK VALVES for each check valve in this Program that is required to close to perform a safety-related function, verification of closure will be by visual observation of appropriate pressure indication in the system, by leak testing, or by other positive means.

2.7 VALVES TO BE TESTED DURING COLD SHUTDOWN V' The Code permits valves to be exercised during cold shutdowns where it is not practical to exercise them during plant operation. A justification for each valve that cannot be tested during power operation is given in the " Cold Shutdown Justifications" section and noted in Tables 1 and 2. The following rules govern cold shutdown testing at Plant Hatch Units 1 and 2.

a. Georgia Power Company intends to commence testing as soon as the cold shutdown condition is achieved, but not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown, and continue until complete or the plant is ready to return to power. Plant conditions (e.g., excessive airborne activity or inerted primary containment) could affect testing, but GPC will make every effort to commence testing in a timely manner.

b. Completion of all valve testing is not a prerequisite to return to power.

c. Any testing not completed during one cold shutdown should be performed during any subsequent cold shutdowns, starting from the last test performed at the previous cold shutdown.

d. For planned cold shutdowns, where ample time is available and testing of all the valves identified for the cold shutdown test frequency in the IST Program will be accomplished, exceptions to the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> may be taken.

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000973 2

I 2.8 VALVES TO BE TESTED DURING REFUELING I p)

During refueling, any valve scheduled for a refueling test will be tested. l Also, any valve identified to be tested at cold shutdown that has not been  !

tested during the previous three months will be tested. A relief request l for each valve that cannot be tested quarterly or during cold shutdowns is  ;

given in the " Relief Request" section and noted in Tables 1 and 2. l 2.9 STROKE TIMES FOR POWER-OPERATED VALVES l

The,following bases are used to assign the limiting values of full-strcke I times for power operated valves. j

a. Maximum valve stroke times are based on manufacturer requirements, Technical Specification limits, and system functional requirements.

Additionally, maximum allowable stroke times for some valves have .

been lowered so that valve degradation will be detected in a manner consistent with Section XI intent. j

b. All maximum valve stroke times have been reviewed to ensure that they are based on component performance an( teflect actual operating valve experience,

c. The limiting values for valve stroke times are included in the Unit 1 and Unit 2 Valve Test Plans. These documents are maintained on site and are available for NRC review.

(3 2.10 PRESSURE ISOLATION VALVES (PIV)

V instrumentation to monitor the leakage downstream of the pressure isolation valves during power operation was not a design requirement of Plant Hatch.

Therefore, a pressure test is performed each refueling outage to determine the leakage. The following criteria are used during the test,

a. A valve that serves only as a pressure isolation valve (not as a dual function containment / pressure isolation valve) is tested at operating differential pressure or at a reduced pressure as allowed by IWV-3423(e), using water as the test medium. The leakage observed during the reduced pressured test is then adjusted to a " function maximum p essure value" as required by IWV-3423(e). Allowable leakage for the test is 0.5 gpm (1892 cc/ min) per inch of valve seat up to a maximum of 5 gpm (18,920 cc/ min) total leakage,

b. A valve that functions both as a PIV and as a containment isolation valve (CIV) is tested using CIV acceptance criteria since these criteria are more stringent. Acceptable leakage for these valves is always less than the PlV criterion of 1892 cc/ min, even when the adjustment to the " function maximum pressure value" is performed.

000973 3

c. Georgia Power Company conforms to the corrective action requirements of IWV-3427(a) but does not apply the requirements of IWV-3427(b).

This position was originally documented in Relief Request RR-V-37

[m) which is now superseded by the intent of Position 10, Containment v Isolation Valve Testing, in Generic letter 89-04.

2.11 CONTAINMENT ISOLATION VALVES (CIV) _

All containment isolation valves that receive a Type C, Appendix J test are included in this Program and are identified as "CIV" under Leakage in Tables 1 and 2. Any changes in the Appendix J, Type C testing scope will be reflected in this document with appropriate changes to the tables.

Georgia Power Company conforms to the requirements of IWV-3426 to the extent practical by assigning a specific leakage limit to each valve or penetration assembly. Limits are based on the type and size of each valve, the number of valves within the test boundary, and historical leakage data.

Georgia Power Company conforms to the corrective action requirements of IWV-3427(a) but does not apply the requirements of IWV-3427(b). This position was originally documented in Relief Request RR-V 37 which is now superseded by Position 10, Containment Isolation Valve Testing, in Generic Letter 89-04.

As a rule, test configurations have the least number of boundary valves '

practical to perform the Type C test; however, the piping arrangement at Plant Hatch generally requires the pressurization of a combination of CIVs and block valves simultaneously, in these cases a leakage limit is applied to r3 each penetration test configuration. During the testing of the penetration, if V the measured leakage exceeds the limit for the penetration, causes are investigated and repairs made to specific valves as necessary. The intent of Section XI to detect degradation (and repair if necessary) of each valve due to service related conditions is therefore met.

2.12 LEAK TIGHT VALVES (LTV)

These excess flow check valves have been catergorized by Georgia Power Company as needing testing to ensure adequate closure to prevent gross amounts of leakage. They do not have a specific leakage rate assigned to them and as a result are not required to be Category A or AC valves; however, per 1987 commitment with the NRC the excess flow check valves are categorized as AC.

2.13 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 at the location used in exercising the valve.

000973 4

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

2.14 FAIL-SAFE VALVES

[) Unless otherwise specified in the program tables, additional fail-safe testing U will not be performed. Stroking the valve full cycle during normal testing causes loss of power to the actuator as required by IWV-3415. Thprefore, additional testing to provide the fail-safe capability is not rcquired.

l 2.15 PASSIVE POWER OPERATED VALVES A passive power operated valve is a valve that does not perform a mechanical motion during the course of accomplishing a system safety function. These i valves are identified as such in the " Function Description" in Tables 1 and 2.

2.16 STROKE TIME MEASUREMENTS FOR RAPID ACTIVE VALVES .

I As originally addressed in Relief Request RR-V-3 and later in position 6 of l Generic Letter 89-04, it is not meaningful to assign a specific stroke time for many rapid acting valves with full stroke times of 2 seconds or less. It is l also not meaningful to apply the Code 50% increase in stroke time corrective  :

action to these same valves. I for specific rapid acting valves at Plant Hatch a maximum limiting valve of I full-stroke time of 2 seconds will be applied to each valve. Upon exceeding  !

this limit, the valve will be declared inoperable and corrective action taken in  ;

accordance with IWV-3417(b). These valves will be delineated in the Unit I and l 2 valve test plans available at the site for review, n 2.17 CONTROL ROD DRIVE lCRD) TESTING

' As required in Position 7 of Generic Letter 89-04, individual CRD Valves will ,

be tested to the extent practical. All valves except the scram discharge volume j vent and drain valves will be tested using the technical specification frequency. Specific frequencies for each valve and the bases for the frequency i are given in each referenced relief request.

The scram discharge volume vent and drain valves do not operate independently of one another. One switch operates all six valves and the valves are required to operate in a particular sequence to provide closure of all valves within a Technical Specification allowable time (45 seconds for Unit 1 and 60 seconds for Unit 2). Therefore individual stroke time testing of these valves is not j practical. As an alternative test, these valves will be stroke timed quarterly ,

l and the time from positioning of the control switch to closure of the last valve "

! will be confirmed to be within the Technical Specification required time. See Relief Request RR-V-39.

i The scram insert and withdraw valves are solenoid valves that full-stroke rapidly. Measuring the full-stroke required by the code is impractical for these valves; therefore, verification that the associated control rod meets the required scram insertion time will be used as the alternate method to detect l degradation of these valves.

O V

000973 5

The scram discharge volume check valves are required to open to fulfill their safety function. Required flow is achieved through these valves during the

< technical specification control rod drive insertion tests.

'x - The charging water HCU check valves are required to open and to close to fulfill their safety function. Forward flow operability is proven duringiTechnical Specification testing and reverse flow closure will be proven by a leakage /

pressure decay test.

The cooling water header HCU check valves'and the drive water insert and withdraw valves are exercised to their safety related position (closed) during weekly CRD exercise testing.

2.18 STARTVP WITH INOPERABLE VALVES When corrective action is required as a result of testing performed during a cold shutdown (or refueling), IWV-3417(b) and IWV-3523 require that the corrective action be completed prior to startup. If the Plant Technical Specifications allow startup with the subject valves inoperable, then startup will not be delayed. See Relief Request RR-V-4.

i 000973 6 O

i Hatch Nuclear Plant . Units 1 and 2 Valve Inservice Test Program ,

a NOTES

)

1. Closure of this pump discharge check valve is proven during pump j surveillance testing. There are two pumps on each train; therefore, when  !

one pump is being tested the other is not operating. For the pump being i tested to pass the required parameters _, the discharge check ~ valve on the I non operating pump must close to prevent diverted flow. If the valve remained open, the pump test would be unsuccessful. 1

2. ' Required flow is verified to be passing through the line during quarterly

' pump testing or normal operation which proves that the check valve opens. ,

1

3. The CRD cooling water check valves are exercised to their safety related i position (closed) during weekly CRD exercise tests (notch in/ notch out). '

Insertion of CRD verifies that the required pressure boundary is intact, and therefore, the check valve is closed.

4. (Not Used)

5. This check valve will be verified to open quarterly during pump testing by observation of free flow through the sight glasses located downstream of the check valve. The closed position is not safety related.

6. (Not Used)

7. Each fuel oil transfer pump is tested quarterly using an ultrasonic flow

/ instrument to measure the flow. The flow rate through the valve required Q] for the valve to fulfill its safety related position will be verified. The discharge piping from each Diesel fuel Oil Transfer Pump is supplied with two check valves in series. There are two pumps located in each 40,000 gallon storage tank which pump into a single discharge line into the associated Day Tank. Satisfactory performance of a fuel oil transfer pump test also proves closure of at least one of the in-series check valves on the associated idle transfer pump,

8. (Not Used)

9. This containment isolation valve is not leak rate tested due to the line its on terminating below the water level of the torus. No leakage test is necessary to satisfy Appendix J requirements as the torus is postulated to always remain water filled.

10. Full stroke capability of these check valves cannot be proven; there~ ore, valves will be disassembled on a rotating basis in accordance with G.L.

89 04.

000973 1 l

0

I

11. (Not used).

12. These valves are air operated valves without indicating lights or control switches. Measurement of stroke times can only be performed by observation of the stem movement when the RCIC room cooler is placed into service. This type of testing does not provide accuracies such as required by Section XI; therefore, a maximum stroke time, as short as practical, will be assigned to each valve. If the measured stroke time exceeds this value~, the valve will be declared inoperable. '.

13. The hand wheel on this stop check valve will be exercised once per quarter

' to verify closure of the valve. The open position is not safety related.

14. The air receiver inlet check valves are verified to function on a quarterly basis using a pressure decay test to verify reverse flow closure.

15. This testable check valve is tested to the open position using the test switch.

16. Drywell air temperature is measured and recorded per Technical Specification requirements. Acceptable drywell temperature verifies that the check valve is passing required flow.

17. This valve is not in the scope of Section XI. This valve has been included in the Program to provide a readily accessible, documented method of testing.

18. This valve will be disassembled and inspected on a frequency determined to provide adequate assurance that the valve is operable.

19. These RCIC valves will be tested in a comparable manner to the test required by RR V 23 for comparable function HPCI valves.

20. Exercise frequency is per Technical Specifications.

21. Stroke times cannot be measured for these valves because there are no position indicators and visual observation is not possible due to the valve design. These valves will be tested as part of the Diesel Generator Air Start Test. Acceptable diesel generator start during monthly manual start tests will be used to verify valve operability. Stroke time will be verified to be acceptable each refueling outage by system timing during auto start testing.

22. The safety relief valve function of the main steam safety relief valves is tested in accordance with a Georgia Power Company procedure. The requirements of this procedure meet or exceed the testing requirements of ASME Section XI, paragraphs lWV-3511 through IWV 3514.

23.' The forward flow opening of the N2 tank discharge check valve will be proven by acceptable inertion of the primary containment each time it is inerted.

000973 2

24. This stop check valve is locked open during normal operation and is not provided with any remote indicating Ilghts. Therefore due to the 7m_ possibility of mispositioning, it will not be exercised quarterly with the ,

manual handwheel. Closure will be proven each refueling outage as defined

(

V) in RR V 30A.

25. Forward flow operability is proven quarterly during pump testing. Closure is proven each refueling outage with a leak test.

26. Theses valve will not be partially stroked quarterly since they are inaccessible pressure isolation valves. In addition, erroneous signal

, indications cannot be readily distinguished from actual problems without shutting down the plant, de-inerting, and performing a drywell entry.

27. Typical of 137 Control Rod Drive mechanisms, i

(

I l

l l

000973 3 o

Page No. 1 08/13/90 Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise leakage Reg'd CS Just.

• • System - 1821 IB21-F010A 1 AC 18" Check E-3 H-16062 FW Inbrd. Cont. O R0 CIV No RR-V-1 Iso. RR-V-4 RR-V-37 Note 2 IB21-F010B I AC 18" Check D-3 H-16062 FW Inbrd. Cont O R0 CIV No RR-V-1 Iso. RR-V-4 RR-V-37 Note 2 IB21-F013A 1 BC 6" Relief C-6 H-16C62 Main Steam C RO NA No RR-V-4 Safety / Relief IW-3512 - RR-V-29 Note 22 IB21-F013B 1 BC 6" Relief C-6 11-16062 Main Steam C R0 NA No RR-V-4 Safety / Relief IW-3512 RR-V-29, Note 22 IB21-F013C 1 BC 6" Relief F-6 H-16062 Main Steam C RO NA No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22 i

IB21-F013D 1 BC 6" Relief F-6 H-16%2 Main Steam C RO NA .

No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22 i

bPage No. 2 o o 08/13/90 I

~

Plant Hatch Unit i Valve Test Program -

j Table 1 i

Stroke Notes

Valve Code Norm Time Re1ief l No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.,

IB21-F013E I BC 6" Relief F-6 H-16062 Main Steam C RO NA No RR-V-4 Safety / Relief IW-3512 RR-V-29 l

Note 22 i

F-6 H-16062 Main Steam No RR-V-4 IB21-F013F 1 BC 6" Relief C RO NA Safety / Relief IW-3512 RR-V-29 Note 22 1321-F013G I BC 6" Relief F-6 H-16062 Main Steam C RO NA No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22 IB21-F013H I BC 6" Relief G-6 H-16062 Main Steam C RO . . . NA No RR-V-4 l

Safety / Relief IW-3512 RR-V-29 Note 22 IB21-F013J l BC 6" Relief G-6 H-16062 Main Steam C RO NA No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22 IB21-F013K 1 BC 6" Relief F-6 H-16062 Main Steam C R0 NA No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22 IB21-F013L 1 BC 6" Relief F-6 H-16062 Main Steam C RO M4 ' No RR-V-4 Safety / Relief IW-3512 RR-V-29 Note 22

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

E I I

Page No. 3 08/13/90 Plant Hatch Unit I Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise Leakage Req'd CS Just.

Class Cat. Description Coord. PalD No.

0 R0 LTV No RR-V 4 AC 1" Excess Flow Ck D-8 H-16062 Instrument RR-V-15 IB21-F015A 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 Instrument RR-V-15 IB21-F015B 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck D-8 H-16062 Instrument RR-V-15 IB21-F015C 1 Excess Flow Check Valve 0 RO i.- LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 Instrument RR-V-15 IB21-F015D 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 I AC 1" Excess Flow Ck D-8 H-16062 Instrument RR-V-15 IB21-F015E Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 instrument RR-V-15 IB21-F015F 1 Excess Flow Check Valve 0 R0 ki No RR-V-4 AC 1" Excess Flow Ck 0-8 H-16062 Instrument RR-V-15 IB21-F015G 1 Excess Flow Check Yaive l

____- "' du lh k,

O O O Page No. 4 08/13/90 Plant flatch Unit .1 Valve Test Program Table 1 St.roke Notes ,

Norm Time Reifef Valve Code Function Pos Exercise Leakage Reg'd C5 Just.

No. Class Cat. Description Coord. P&lD 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 Instrument k.1-V-15 IB21-F015H 1 Excess Flow  ;

Check Valve I

0 R0 LTV No RR-V-4 l AC 1" Excess Flow Ck 0-8 11-16062 Instrument RR-V-15 IB21-F015J Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 Instrument RR-V-15 IB21-F015K 1 Excess flow Check Valve 0 R0 ,. LTV No RR-V-4 I AC l' Excess Flow Ck D-8 H-16062 Instrument RR-V-15 IB21-F015L Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess flow Ck C-8 H-16062 Instrument RR-V-15 IB21-F015M 1 Excess Flow

. Check Valve 0 RO LTV No RR-V-4 AC I" Excess Flow Ck D-8 H-16062 Instrument RR-V-15 1021-F015N 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-8 H-16062 Instrument RR-V-15 IB21-F015P 1 Excess Flow Check Valve

. _ _ _ _ - .A I ;

S . ~s

/

Page No. 5 08/13/90 Plant Hatch Unit i Valve Test Program

~

labic 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description- Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

IB21-F015R I AC 1" Excess Flow Ck D-8 H-16062 Instrument 0 RO LTV No RR-V-4 Excess Flow RR-V-IS Check Valve IB21-F0155 1 AC 1" Excess Flow Ck C-8 H-16062 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve i

( IB21-F016 I A 3" M0 Gate E-8 H-16062 Main Steam Line C Qtr CIV Yes RR-V-2 DRN. Inbrd.

Iso.

IB21-F019 1 A 3" M0 Gate E-9 H-16062 Main Steam Line C Qtr i . - CIV Yes MA DRN. Outbrd.

Iso.

IB21-F022A I A 24" A0 Globe C-7 H-16%2 MSIV 0 CS CIV Yes RR-V-4 RR-V-10i CS-9 IB21-F022B 1 A 24" A0 Globe E-7 H-16062 MSIV O CS CIV Yes RR-V-4 .

RR-V-10i '

05-9 IB21-F022C 1 A 24" A0 Globe F-7 H-16062 MSIV O CS CIV' Yes RR-V-4 RR-V-10 CS-9 i

. . _ . v

• v ..-.v. . ,w v- , .- ,cm,w.p.-

6'Page No. 6 O O 08/13/90 Plant Hatch Unit i Valve Test Program -

Table 1 4

Stroke Notes ,

Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leaka9e Reg'd CS Just.-

IB21-F0220 1 A 24" A0 Globe G-7 H-16062 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 C5-9 IB21-F028A 1 A 24" A0 Globe C-9 H-16062 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 C5-9 IB21-F0288 i A 24" A0 Globe E-9 H-16062 MSIV 0 CS CIV Yes RR-V-4 i RR-V-10 CS-9 IB21-F028C 1 A 24" A0 Globe F-9 H-16062 MSIV 0 CS 6 - CIV Yes RR-V-4 i RR-V-10 CS-9 1821-F0280 1 A 24" A0 Globe G-9 H-16062 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 CS-9 IB21-F032A 1 AC 18" Check F-2 H-16062 FW Outbrd. O R0 CIV No RR-V Cont. Iso. RR-V-4 RR-V-37 IB21-F0328 I AC 18" Check F-1 it-16062 FW Outbrd. O R0 CIV No RR-V-1 l Cont Iso. RR-V-4 RR-V-37 l

Page No.- 7 08/13/90 i Plant Hatch Unit i Valve Test Program Table i Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exerr,ise Leaka9e Reg'd CS Just.

IB21-F036A 2 C 1" Check 0-3 H-16299 MSRV 0/C RO MA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036B 2 C 1" Check D-3 11-16299 MSRV Q/C R0 NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036C 2 C 1" Check 0-3 11-16299 MSRV Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036D 2 C I" Check D-3 H-16299 MSRV Q/C RO so NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036E 2 C 1" Check D-3 H-16299 MSRY Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036F 2 C 1" Check E-4 H-16299 MSRV Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check I'

IB21-F036G 2 C 1" Check E-4 H-16299 MSRV Q/C R0 NA No RR-V-4 Accumulator Air RR-V-28 Supply Check

_ _ _ - _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ = _ _ _-_ - __ _-

m .p p Page No. 8 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.

IB21-F036H 2 C 1" Check E-4 H-16299 MSRV Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036J 2 C 1" Check E-4 H-16299 MSRV Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036K 2 C 1" Check D-3 H-16299 MSRV Q/C RO NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F036L 2 C 1" Check E-4 H-16299 MSRV Q/C RO . - NA No RR-V-4 Accumulator Air RR-V-28 Supply Check IB21-F037A 3 C 6" Check H-6 H-16062 Vac.'dreaker C CS NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037B 3 C 6" Check H-6 H-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037C 3 C 6" Check H-6 H-16062 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. ,, RR-V-II IB21-F0370 3 C 6* Check H-6 H-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-Il

3 _

,0 V -

V Page No. 9 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.

IB21-F037E 3 C 6" Check H-6 H-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037F 3 C 6" Check H-6 11-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037G 3 C 6" Check 11- 6 11-16062 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037H 3 C 6" Check H-6 11-16062 Vac. Breaker C C5 NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037J 3 C 6" Check H-6 H-16062 Vac. Breaker C R0 .. NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037K 3 C 6" Check H-6 H-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-Il IB21-F037L 3 C 6" Check H-6 H-16062 Vac. Breaker C RO NA No RR-V-4 MSRV Disch. RR-V-II IB21-F041 1 AC I" Excess Flow Ck B-5 11-16063 Instrument 0 R0 LTV No RR-V-4 l

Excess Flow RR-V-15 Check Valve ,

IB21-F043A 1 AC I" Excess Flow Ck C-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

l O O O ,

l Page No. 10 08/13/90 Plant Hatch Unit i Valve Test Program l Table I Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. PalD Function Pos Exercise leakage Req'd CS Just.

IB21-F0438 1 AC 1" Excess Flow Ck C-9 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve i

IB21-F045A 1 AC 1" Excess Flow Ck C-5 H-16063 Instrument 0 R0 LTV No RR-V-4 i Excess Flow RR-V-15 Check Valve IB21-F0458 1 AC 1" Excess Flow Ck C-9 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F047A I AC 1" Excess Flow Ck F-5 H-16063 Instrument 0 RO i . LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F047B 1 AC 1" Excess Flow Ck F-9 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 :

Check Valve IB21-F049A I AC 1" Excess Flow Ck F-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V Check Valve IB21-F0498 1 AC 1" Excess Flow Ck F-9 H-16063 Instrument 0 R0 (TV ' No RR-V-4 Excess Flow RR-V-15i Check Valve

O O O Page No. 11 08/13/90 ,

Plant Hatch Unit i Valve Test Program Tabic I Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Req'd C5 Just..

IB21-F051A 1 AC 1" Excess flow Ck H-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F0518 I AC I" Excess Flow Ck H-5 11-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-Y-15 Check Valve

, IB21-F05!C 1 AC 1" Excess Flow Ck H-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F051D I AC 1" Excess Flow Ck H-5 H-16063 Ins ament 0 RO .. LTV No RR-V-4 Excess flow RR-V-15 Check Valve IB21-F053A I AC 1" Excess Flow Ck J-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F0538 I AC 1" Excess Flow Ck J-5 H-16063 Instrurent 0 R0 LTV No RR-V-4 Excess Finw RR-V-15 Check Vaive IB21-F053C I AC 1" Excess Flow Ck J-5 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

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

._~

Pa e No. 12 08 13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes-Norm Time Relief Valve Code-Function Pos Exercise leakage Req'd CS Just.

No. Class Cat. Description Coord. P&ID 0 RO LTV No RR-V-4 AC 1" Excess Flow Ck J-5 H-16063 Instrument RR-V-15 IB21-F053D 1 Excess Flow Check Valve 0 R0 LTV No M-V-4 AC 1" Excess Flow Ck J-5 H-16063 Instrument I:X-V IB21-F055 1 Excess Flow' Check Valve 0 R0 LTV - No RR-V-4 AC 1" Excess Flow Ck J-5 H-16063 Instrument RR-V-15 IB21-F057 1 Excess Flow Check Valve 0 R0 ~ . LTV No RR-V-4 AC I" Excess Flow Ck 11-9 H-16063 Instrument $

RR-V-15~

IB21-F059A 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck H-9 H-16063 Instrument RR-V-15 IB21-F0598 1 Excess Flow Check Valve 0 R0 LTV No RR-Y-4 AC 1" Excess Flow Ck H-9 H-16063 Instrument RR-V-15 IB21-F059C 1 Excess Flow Check Valve 0 R0 LIV No RR-V-4 AC 1" Excess Flow Ck H-9 H-16063 Instrument- RR-V-15 1821-F059D 1 Excess Flow Check Valve

____ ll

DPage No. 13 O O 08/13/90 Plant Hatch Unit I Valve Test Program Table 1

-Stroke Notes' Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function .Pos Exercise- Leakage Reg'd .CS Just.;

IB21-F059E I AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 RO -LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F059F 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 LTV- -No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F059G 1 AC 1" Excess flow Ck H-9 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve t

IB21-F059H I AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 i. LTV No RR-V-4~_

Excess Flow RR-V-15 Check Valve l IB21-F059L 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve l

IB21-F059M 1 AC I" Excess Flow Ck H-9 H-16063 Instrument 0 R0 LTV No RR-V-4 t

Excess Flow RR-V-15 l

Check Valve t

1821-F059N 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 Liv ' No RR-V-4 Excess Flow .RR-V-15 Check Valve L

~ . . _ .

m -

[_b.

Page No. 14 08/13/90 Plant Hatch Unit 1 Valve Test Program Table 1 Stroke Notes Valve Code . Norm Time ~ Relief-No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

IB21-F059P 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 LTV- No RR-Y 8 ,.

Excess Flow RR-V-15 ~

Check Valve IB21-F059R 1 AC 1" Excess flow Ck H-9 11-16063 Instrument 0 R0 LTV No - RR-V-4 Excess Flow RR-V Check Valve

! IB21-F0595 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 R0 LTV No RR-V-4 l Excess Flow RR-V-15 Check Valve IB21-F059T I AC 1" Excess Flow Ck H-9 H-16063 Instrument 0 RO -. . -

LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB21-F059U 1 AC 1" Excess Flow Ck H-9 H-16063 Instrument' 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 ,

Check Valve IB21-F061 1 AC 1" Excess Flow Ck J-9 H-16063 Instrument 0 R0 LTV No RR-V-4 l

Eye.ess Flow RR-V-15 i

Check Valve l

IB21-F110A 3 C 10" Check H-7 H-16062 Vac. Breaker .C CS NA ' No RR-V-4 MSRV Disch. RR-V-Il l

I i

-m_ ^.- ___. - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _

m _ r e-' u-+ k,w-e-

Page No.- -15 08/13/90 Plant Hatch Unit I Valve Test Program l Table 1 l Stroke. Notes Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.:

t IB21-F1100 3 C 10" Check H-7 H-16062 Vac. Breaker C CS NA No RR-V-4.

MSRV Disch. RR-V-II l

l IB21-F110G 3 C 10" Check H-7 H-16062 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-II-IB21-F110H 3 C 10" Check -7 H-16062 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-II IB21-Flll 2 A 1" A0 Gate E-2 H-26384 Pass Sample C Qtr CIV Yes NA Valves l

IB21-Fil2 2 A l' A0 Gate E-2 H-26384 Pass Sample C Qtr . . CIV Yes NA Valves

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

O Page No. 16' O

O 08/13/90

- ^

Plant flatch Unit i Valve Test P.*ogram Table I Stroke Notes Valve Code Norm . Time ' Relief.

No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd: CS Just.

• • System - 1831 IB31-F003A I AC 1" Excess Flow Ck G-2 11-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V Check Valve IB31-F003B I AC 1" Excess flow Ck G-2 .II-16066 Instrument ~ 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F004A 1 AC 1" Excess flow Ck G-2 H-16066 Instrument O. R0 LTV No RR-V-4 Excess Flow RR-V-15.

Check Valve IB31-F004B 1 AC 1" Excess Flow Ck G-2 11-16066 Instrument 0 R0 LTV No RR-V-4 Excess flow RR-V-15 Check Valve IB31-F009A 1 AC 1" Excess Flow Ck C-10 -H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F009B 1 AC 1" Excess flow Ck E-10 -H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 4 IB31-F009C 1 AC 1" Excess Flow Ck D-10 H-16066 Instrument -0 RO LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

~

V' **i W f e.y . = - e - , , , ,_ _ _

~

O Page No. 17 O O 08/13/90 Plant Hatch Unit i Valve Test Program '

Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD function 'Pos Exercise leakage Reg'd CS Just<

IB31-F009D I AC 1" Excess flow Ck F-10 H-16066 Instrument 0 R0 LTV No .RR-V Excess Flow RR-V-15' Check Valve IB31-F010A 1 AC 1" Excess Flow Ck D-10 H-16066 Instrument 0 RO LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F010B 1 AC 1" Excess Flow Ck E-10 H-16066 Instrument 0 R0 LTV No .RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F0100 1 AC 1" Excess Flow Ck D-10 H-16066 Instrument 0 R0 s - LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

IB31-F0100 1 AC 1" Excess Flow Ck F-10 H-16066 Instrument 0 R0 LTV No RR-V-4

Excess Flow RR-V-15 i

Check Valve

(

IB31-F0llA 1 AC 1" Excess flow Ck 0-10 H-16066 Instrument 0 R0 LTV No' RR-V-4 Excess Flow RR-V-15 l

Check Valve

^

! IB31-F0llB 1 AC 1" Excess Flow Ck E-10 H-16066 Instrument 0 R0 (TV No RR-V-u Excess Flow RR-V-1., ~

Check Valve l

l

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

l l

dPage No. 18 O O l 08/13/90 Plant Hatch Unit i Valve Test Program -

Table 1 Stroke Notes Valve Code Norm Time ' Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise leakage Reg'd -CS.Just.

l IB31-F0 llc I AC I* Excess Flow Ck E-10 'H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

, IB31-F0llD 1 AC 1" Excess Flow Ck F-10 H-16066 Instrument 0 R0 LTV No RT.-V-4 l

Excess Flow .RR-V-15 Check Valve IB31-F012A 1 AC 1" Excess Flow Ck D-10 H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F012B 1 AC 1" Excess Flow Ck F-10 11-16066 Instrument 0 R0 , -

LTV No RR-V-4 Excess Flow RR-V-15 l Check Valve IB31-F012C 1 AC 1" Excess Flow Ck E-10 H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F0120 1 AC 1" Excess Flow Ck F-10 H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IB31-F013A 1 AC 3/4" Check .F-3 H-16066 Recir. Pump 0 R0 C'lV ' No' RR-V-4 "

Seal Wtr. RR-V-5

')

._--.y. -

~ . - .. - -y ,-i ..e m -

b Page No. 19.

O O 08/13/90 Plant Hatch Unit i Valve Test Program Table I Stroke Notes Valve Code Norm Time ~ Relief '

No. Class Cat. Description Coord. P&ID . Function Pos Exercise leakage Reg'd CS Just.

IB31-F0138 .I AC 3/4" Check F-3 H-16066 Recir. Pump 0 R0 .CIV No- -RR-V-4 Seal Wtr. RR-V-5 IB31-F017A 1 AC 3/4" Check F-2 11-16066 Recir. Pump 0 R0 CIV No RR-V-4 Seal Wtr. RR-V-5 IB31-F017B 1 AC 3/4" Check F-2 11-16066 Recir. Pump 0 RO CIV No RR-V-4 l Seal Wtr.' RR-V-5' t

IB31-F019 1 A 3/4" A0 Globe D-3 11-16066 Reac. Sample 0 Qtr CIV Yes MA Sys. Inbrd.

Iso.

IB31-F020 1 A 3/4" A0 Globe D-1 H-16066 Reac. Sample 0 Qtr CIV Yes NA Sys. Outbrd.

Iso.

IB31-F031A 1 B 28" M0 Gate G-7 H-16066 Reactor 0 CS NA Yes RR-V-4 Recirculation 05-1 IB31-F031B 1 B 28" M0 Gate H-7 H-16066 Reactor 0 CS NA Yes RR-V-4 Recirculation 05-1 IB31-F040A 1 AC 1" Excess Flow Ck G-8 (1-16066 Instrument 0 R0 LTVg No RR-V-4 Excess Flow RR-V-15 Check Valve I

-- ,. , , . _ _ _ _ _ _ + _ _ . , __

O Page No. - 20 O O .

08/13/90 Plant Hatch Unit i Valve Test-Program -

Table I  ;

. Stroke Notes Valve Code Norm Time Relief' No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd_ CS Just. .

1831-F040B 1 AC 1" Excess Flow Ck H-8 H-16066 Instrument 0 RO -LTV~ No RR-V-4 '

Excess Flow .RR-V-15 Check Valve IB31-F040C 1 AC I" Excess Flow Ck G-8 H-16066 Instrument 0 R0 .LTV No RR-V Excess Flow RR-V-15 Check Valve IB31-F0400 1 AC 1" Excess Flow Ck H-8 H-16066 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve jt L

____.______m_

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

Page No. 21 .-'

08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time' Relief-No. Claes Cat. Description. Coord. Pal 0 Function Pos Exercise Leakage Reg'd CS Just.,

• • System - 1011 ICll-F010A 2 B I" A0 Globe A-5 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 Volume Vent Valve ICll-F010B 2 B 1" A0 Globe A-6 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 Volume Vent Valve ICll-F0ll 2 B 2" A0 Globe D-8 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 Volume Drain Valve ICII-F035A 2 B 1" A0 Globe A-5 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 Volume Vent Valve ICll-F0358 2 B 1" A0 Globe A-6 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 Volume Vent Valve ICll-F037 2 B 2" A0 Globe C-4 H-16065 Scram Disch. O Qtr NA Yes RR-V-39 ,

Volume Drain Valve g .

ICll-HCU-ll4 2 C 3/4" Check A-6 H-16064 Scram Disch. C Note 20 NA No RR-V-38 Volume HCU Note 27 Check Valve

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

Q.

Page No.. 22 O -

O 08/13/90 .

Plant Hatch Unit 1' Valve Test Program Table 1 l Stroke Notes l

Valve Code .

. Norm Time Relief

.No. Class Cat. Description Coord. PalD Function Pos Exercise Leakage Reg'd CS Just.

ICll-HCU-IIS 2 C 1/2" Check C-6 H-16064 Charging Water C RO NA No . RR-V-4 HCU Check Valve RR-V-26:

Note 27 ICll-HCU-126 1 B 1" A0 Globe BA H-16064 Scram insert C Note 20 NA No. RR-V-27 HCU Control Note 27 Valve ICll-HCU-127 1 B 3/4" A0 Globe A-4 H-16064. Scram Disch. C Note 20 NA ' No RR-V HCU Control Note 27 Valve ICll-HCU-138 1 C I/2" Check C-4 H-16064 Cooling Water C Wkly s NA No Notes 3,6 Hrader HCU Check Valve l

l j?

l

Page No. 23 08/13/90

~

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise Leakage Reg'd CS.Just Class Cat. Description Coord. PalD No.

• • System - IC41 NA No NA l-1/2" Expl. Act. D-3 H-16061-SLC Expl. Act. C IWV-3610 1041-F004A 2 D NA No NA' 1-1/2" Expl. Act. F-3 H-16061 SLC Expl. Act. C IWV-3610 IC41-F004B 2 0 C R0 CIV No- RR-V-4 AC 1-1/2" Check E-2 H-1606l SLC Outbrd RR-V-6 IC41-F006 1 Cont. Iso.

C R0 CIV No RR-V-4 AC 1-1/2" Check E-2 H-16061 SLC Inbrd. RR-V-6 1041-F007 1 Cont. Iso.

NA No NA~

D-6 H-1606) SLC Pump Disch. C IWV-3512 1041-F029A 2 C 1" Relief Relief , .-

IWV-3512 NA No NA G-6 H-16061 SLC Pump Disch. C IC41-F0298 2 C 1" Relief Relief H-16061 SLC Pump Disch. C ~Qtr NA No Note 2 2 C 1-1/2" Check E-S 1041-F033A H-16061 SLC Pump Disch. C Qtr NA No Note 2 2 C 1-1/2" Check G-5 IC41-F033B 1

i t

_ . _ _ d

o O O-Page No. 24-08/13/90

~

Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. P&ID No.

• • System - IC51 C-3 -H-16070 TIP. Inboard 0 atr CIV Yes MA IC51-Ball A 2 A Ball Solenoid Cont. Iso.

-0 Qtr CIV Yes NA A Ball Solenoid C-3 H-16070 TIP Inboard IC51-Ball-B 2 Cont. Iso.

-CIV Yes NA:

A Ball Solenoid C-3 11-16070 TIP Inboard 0 Qtr ICSI-Ball C 2 Cont. Iso.

0 Qtr CIV Yes MA A Ball Solenoid C-3 H-16070 TIP Inboard IC51-Ball D 2 Cont. Iso. s.

0 R0 CIV- Yes RR-Y-4 A Solenoid C-8 H-16561 TIP N2 Purge RR-V-40 IC51-F3012 2 CIV CIV Ne RR-V-4 AC Check C-8 H-16561 TIP N2 Purge O R0 RR-V IC51-F3017 2 CIV 0 IWV-36IO NA No .NA 2 D Expl. Shear C-3 H-16070 TIP Outboard IC51-Shear A Iso.

NA No- NA Expl.' Shear C-3 H-16070 TIP Outboard .0 IWV-3610 IC51-Shear 8 2 D g.

Iso.

0 IWV-3610 NA No NA 2 D Expl. Shear C-3 H-16070 TIP Outboard IC51-Shear C Iso.

l' ..

O O O Pa e No. 25' 0 13/90

~ ~

i Plant Hatch Unit 1' Valve Test Program '

Table ~l i

l Stroke Notes l Valve Code . Norm Time- Relief.

I No. Class Cat. Description Coord. P&lD - Function Pos Exercise leakage Reg'd CS Just.'

l IC51-Shear D 2 0 Expl. Shear C-3 fi-16070 TIP Outboard 0 IWV-3610 NA No' NA Iso.

l t

l l

l l

l s.-

l l

l l

l ii l

l l

l

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- i 4r, <<s.*dme-*- + * / s' w+11- 4--"

• h-5-w  ; m- -- p-- -

_9m, <i.g" w g_- :g ,,__

(

~

Page No. 26 08/13/90 Plant Hatch Unit i Valve Test Program -

Table 1 Stroke Notes . ~

Valve Code Norm Time Rel ie f' .

l No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.

• • System - 1011 .

IDll-F050 2 A 1" Solenoid E-4 H-16173 Fission Prod. O Qtr CIV Yes NA Mon. Cont. Iso.

IDil-F051 2 A 1" Solenoid C-5 H-16173 Fission Prod. O Qtr CIV Yes ' NA Mon. Cont.-Iso.

IDil-F052 2 A 1" Solenoid E-5  !!-16173 Fission Prod. O Qtr CIV Yes' NA .

Mon. Cont. Iso. '

IDil-F053 2 A 1" Solenoid C-6 H-16173 Fission Prod. O Qtr CIV Yes NA Mon. Cont. Iso.

gs j'?

l

. _ . . . . , _ + - " -__ - . _ _ _ m1 * - ~

" - - - -- - ' - - " + ~,r _- - - - " - - --

_____an.:____.___-ce.____, >

= . _ ~ -_____-_n_-_ N_x

O O O Page No. 27 08/13/90

~

Plant Itatch Unit i Valve Test Program Table 1.

Stroke Notes-Norm Time Relief Valve Code Coord. P&ID Function Pos Exercise- Leakage Reg'd CS Just.

No. Class Cat. Description

• • System - IEll D-4 H-16330 RHR lix Shell 0 Qtr NA Yes NA

.lEll-F003A 2 B 16" M0 Gate Side Outlet NA Yes NA 8 16" M0 Gate D-9 H-16329 RilR !!x Shell 0 Qtr IE11-F003B 2 Side Outlet 11-16330 RilR Pump 0 Qtr NA Yes Note 9 2 24" M0 Gate F-10 IEll-F004A B Suction Torus Iso.

H-16329 RHR Pump- 0 Qtr NA Yes Note 9 24" M0 Gate F-3 IEll-F004B 2 B Suction Torus s- -

Iso.

!!-16330 RHR Pump G Qtr NA Yes Note 9 B 24" M0 Gate F-10 IEll-F004C 2 Suction Torus Iso.

H-16329 RHR Pump 0. Qtr NA Yes Note 9 B 24" M0 Gate F-3 IEll-F004D 2 Suction Torus.

Iso.-

No Notes I, 14" Check A-7 D-Il004 RHRSW Pump C Qtr NA IEll-F005A 3 C Disch Check Valve

Page No. 28 08/13/90 Plant Hatch Unit i Valve Test Program

~'

Table 1 Stroke Notes Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&ID Function Pos Exercise. Leakage Reg'd CS Just.

IEll-F005B 3 C 14" Check D-7 0-11004 RHRSW Pump C Qtr NA No Notes 1,)

,. Disch Check l Valve IEll-F005C 3 C 14" Check C-7 D-11004 RHRSW Pump C Qtr NA No Notes 1,f Disch Check Valve IEll-F005D 3 C 14" Check E-7 D-11004 RHRSW Pump C Qtr. NA No Notes 1,r Disch Check Valve IEll-F006A 2 B 20" M0 Gate F-8 H-16330 RHR Shutdown C Qtr . NA Yes NA Cooling Sys IEll-F006B 2 8 20" M0 Gate F-4 H-16329 RHR Shutdown C Qtr NA Yes MA Cooling Sys IEll-F006C 2 B 20" M0 Gate F-ll H-16330 RHR Shutdown C Qtr NA Yes NA Cooling Sys IEll-F0060 2 B 20" M0 Gate F-2 H-16329 RHR Shutdown C Qtr NA Yes NA Cooling Sys IEll-F007A 2 8 4" M0 Gate E-7 H-16330 RHR Pump Min 0- Qtr NA Yes- Note 9 Flow Torus Iso.

l l

l l

l O

Page No. 29 O O j 08/13/90 Plant Hatch Unit 1 Valve Test Program.

Table 1 Stroke Notes Valve Code Norm Time Relief' No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Juste IEll-F007B 2 B 4" M0 Gate D-6 H-16329 RHR Pump Min 0 Qtr NA Yes Note 9 Flow Torus Iso.

IEll-F008 1 A 20" M0 Gate D-2 H-16329 RHR Shutdown- C CS PIV/CIV Yes- RR-V-4 Cooling Outbrd. RR-V-37 j

Iso. CS-2 IEll-F009 1 A 20" M0 Gate D-2 11-16329 RilR Shutdown C CS PIV Yes RR-V-4

Cooling Inbrd. RR-V-37 Iso. CS-2 IEll-F0llA 2 B 4" M0 Gate D-3 H-16330 RHR Cond. C Qtr NA Yes Note 9 Disch. to Torus s- -

IEll-F0llB 2 B 4" M0 Gate D-10 H-16329 RHR Cond. C Qtr NA Yes Note 9 Disch. to Torus IEll-F015A 1 A 24" M0 Gate C-8 H-16330 LPCI Outbrd. C Qtr PIV/CIV Yes.. RR-V-37 Cont. Iso.

IEll-F015B 1 A 24" M0 Gate C-5 H-16329 LPCI Outbrd. C Qtr PlV/CIV Yes RR-V-37 Cont. Iso.

IEll-F016A 2 A 16" M0 Globe B-9 H-16330 Cont. Spray C. Qtr CIV . Yes RR-V-37 Outbrd. Iso.

IEll-F016B 2 A 16" M0 Globe B-5 H-16329 Cont. Spray C Qtr CIV. Yes RR-V-37 Outbrd. Iso.

._ -. .. _ . , _c__. .____u_.;_.____;_ _ . _ _ _

d O O Page No. 30 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief-Valve Code Function Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. P&lD No.

O Otr NA Yes NA B P4" M0 Globe C-8 H-16330 LPCI IEll-F017A 1 O Qtr NA Yes~ NA B 24" M0 Globe C-5 11-16329 LPCI IEll-F017B 1 Yes NA B 16" M0 Gate B-Il 11-16330 Containment C Qtr NA lEll-F021A 2 Spray NA Yes_ NA 8 16" M0 Gate B-3 11-16329 Containment C Qtr IEll-F021B 2 Spray CIV- No - NA H-16329 Passive Cont. C None A 4" M0 Globe A-3 lEll-F023 2 Iso. ,..

Yes NA 8 16" M0 Globe C-7 H-16330 Suppression C Qtr NA IEll-F024A 2 Pool Cooling Yes NA 16" M0 Globe C-7 H-16329 Suppression C Qtr NA 2 B IE11-F0248 Pool Cooling C IWV-3512 - NA No. Note 9 2 C 1". Relief C-8 H-16330 LPCI Relief IEll-F025A IWV-3512 NA No - Note 9 2 C 1" Relief B-5 H-16329 LPCI Relief C IEll -F025B Qtr NA : Yes Note 9-2 B 4" M0 Gate D-3 H-16330 Cond. Disch to C IEll-F026A RCIC 8

Qtr. NA Yes Note 9' 2 8 4" M0 Gate D-II H-16329 Cond. Disch to C IEll-F026B RCIC

- _ _ _ = _ c

I I IIh nib uuI I '

b i Ig b O O Page No. 31 08/13/90

~

~

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes-Norm Time Relief-Valve Code .

Function Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. P&lD No.

C' Qtr NA Yes NA.

8 6" M0 Globe C-8 H-16330 Suppression IEll-F027A 2 Pool Spray Qtr NA Yes NA 6" M0 Globe C-5 H-16329 Suppression C lEll-F027B 2 B Pool Spray Qtr CIV Yes RR-V-37 A 16" M0 Gate B-8 H-16330 Suppression C lEll-F028A 2 Pool Spray Outbrd Iso.

Qte CIV Yes RR-V-37 A 16" M0 Gate B-6 H-16329 Suppression C IEll-F0288 2 Pool Spray -

Outbrd Iso. s.

H-16329 RHR Pump Suc C IWV-3512 NA No Note 9 IEll-F029 2 C 1" Relief E-1 Relief H-16330 RHR Pump Suc C IWV-3512 NA No Note 9-1" Relief F-9 IEll-F030A 2 C Relief H-16329 RHR Pump Suc C IWV-3512 NA No Note 9 1" Relief F-4 IEll-F030B 2 C Relief H-16330 RHR Pump Suc C IWV-3512 M4 . No Note.9 IEll-F030C 2 C I" Relief F-Il Relief H-16329 RHR Pump Suc. C IWV-3512 .N4 No Note 9 1" Relief F-2 IEll-F0300 2 C Relief

Page No. 32 08/13/90 ,

~

Plant Hatch Unit 1 Valve Test Program -

Table 1 Stroke Notes Valve Code Norm- Time -Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

IEll-F031A 2 C 20" Check H-6 H-16330 RHR Pump C Qtr NA No Notes 1,2' Discharge IEll-F031B 2 C 20" Check H-7 H-16329 RHR Pump C -Qtr NA No Notes 1,2i Discharge IEll-F031C 2 C 20" Check 11 - 1 0 H-16330 RHR Pump C Qtr NA No. Notes 1,2:

Discharge IEll-F031D 2 C 20" Check 11-3 11-16329 RHR Pump C Qtr NA No Notes 1,2!

Discharge IEll-F046A 2 C 3" Check H-7 H-16330 RHR Minimum C Disassemb. NA No Note 10 Flow Line-IEll-F046B 2 C 3" Check 11 - 6 H-16329 RHR Minimum C Disassemb NA No Note 10-Flow Line IEll-F046C 2 C 3" Check H-Il H-16330 RHR Minimum .C Disassemb NA No Note 10 Flow Line IEll-F046D 2 C 3" Check H-3 H-16329 RHR Minimum C Disassemb NA No' Note.10" Flow Line IEll-F047A 2 B 16" M0 Gate .E-6 H-16330 RHR Hx Shell 0 Qtr NAi Yes NA.

Side Inlet-

OPage No. 33 O O 4 08/13/90 Plant 11atch Unit i Valve Test Program Table 1

-Stroke Notes Valve Code Norm Time. Relief.

No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

IEll-F0478 .2 B 16" M0 Gate E-7 H-16329 RHR Hx Shell 0 Qtr NA Yes NA Side Inlet IEll-F048A 2 B 24" M0 Globe D-6 H-16330 RHR Hx Shell 0 Qtr NA Yes NA Side Bypass l

l IEll-F048B 2 8 24" M0 Globe D-7 11-16329 RilR Hx Shell 0 Qtr NA Yes- NA l

Side Bypass IEll-F050A 1 AC 24" Check C-10 11-16330 LPCI Iso. C Disassemb PlV No RR-V-14 RR-V-37 Notes 17 i - - 26 IEll-F050B 1 AC 24" Check C-4 H-16329 LPCI Iso. C Disassemb PlV No RR-V-14 RR-V-37 Notes 16 26 IEll-F055A 2 C 4" Relief F-5 H-16330 RHR Hx Shell C IWV-3512 NA No Note 9 Relief IEll-F055B 2 C 4" Relief E-9 H-16329 RHR Hx Shell C IWV-3512 NA- No Note 9-Relief g lEll-F068A 3 8 10" M0 Ball H-6 H-16330 RHR Hx Ser. C Qtr NA No RR-V Wtr. Disc.

_ -a. .- :__ _ _ __ _ _ m_-. _. c _ _

=

bPage No. 34 o O 08/13/90

~

Plant Hatch Unit 1 Valve Test Program -

Table I

. Stroke Notes Valve ' Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.;

IEll-F0688 3 B 10" M0 Ball H-8 H-16329 RHR Hx Ser. C Qtr NA No 'RR-V-22 Wtr. Disc.

IEll-F073A 2 B 10" M0 Gate 'G-2 H-16330 RHRSW to RHR C -Qtr NA Yes NA Crosstie.

IEll-F0738 2 8 10" M0 Gate G-9 H-16329 RHRSW to RHR C Qtr NA -Yes' NA Crosstie.

IEll-F075A 2 B 10" M0 Gate G-4 H-16330 RHRSW to RHR C Qtr. NA Yes NA Crosstie IEll-F075B 2 B 10" M0 Gate G-9 H-16329 RHRSW to RHR C Qtr i . NA Yes NA Crosstie IEll-F078A 2 C 10" Test. Check D-4 H-16330 RHRSW to RHR C Disassemb' NA No Note'10 Crosstie IE11-F0788 2 C 10". Test. Check D-9 H-16329 RHRSW to RHR C Disassemb NA No Note 10 Crosstle lEll-F097 2 C 3" Relief D-11 H-16329 Steam Line C IWV-3512 nA No Note 9 Relief IEll-F103A 2 B 1" M0 Globe E-5 H-16330 RHR Hx Vent C Qtr RA Yes Note 9.

Iso.

.- - - , .,.a -. ..

i Page No. 35 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes.

Valve Code !iorm .

Time Relief-No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg *d CS Just.

IEll-F103B 2 B 1" M0 Globe E-9 H-16329 RHR Hx Vent C Qtr NA -Yes. Note 9 Iso.

IEll-F122A I A 1" A0 Plug 0-10 H-16330 Passive C None PlV No NA Isolation IEll-F1228 1 A 1" A0 Plug D-4 H-16329 Passive C None PIV No NA Isolation IEll-F126A 2 C- 2" Stop Check E-6 H-16328 Maintain RHR 0/C Qtr NA No Note 13 Water level IEll-F126B 2 C 2" Stop Check E-4 H-16328 Maintain RHR 0/C Qtr NA No ~ Note 13 Water level

oPage No. 36 O O -

08/13/90

' Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code .

Norm- Time Relief.

No. Class Cat. Description Coord. P&lD Function Pos. Exercise Leakage Reg'd CS Just.

• • System - IE21 .

lE21-F001A 2 B 16" M0 Gate H-8 H-16331 CS Pump Suction 0 Qtr NA Yes. Note'9 Iso.

IE21-F0018 2 B 16" M0 Gate J-8 H-16331 CS Pump Suction 0 Qtr .NA Yes Note.9-Iso.

IE21-F003A 2 C 12" Check F-9 H-16331 CS Pump C Qtr NA No -Note 2 Discharge IE21-F003B 2 C 12" Check F-Il H-16331 CS Pump C Qtr NA No Note 2 Discharge

\ l B 10".M0 Gate E-7 H-16331 CS Outbrd. O Qtr NA Yes MA Injection

I B 10" M0 Gate B-7 H-16331 CS Outbrd. 0 Qtr NA Yes NA Injection IE21-F005A I A 10" M0 Gate' E-6 H-16331 CS Press / Cont. C Qtr PlV/CIV Yes RR-V-37 Iso. .

IE21-F005R I A 10" M0 Gate B-6 H-16331 CS Press / Cont. C Qtr FIV/CIV Yes RR-V-37 Iso. ..

IE21-F006A 1 AC '10" Check D-4 H-16331 CS Injection C -Disassemb PIV No RR-V-13 '

Iso. RR-V-37 Notes 10, 26 l

i

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

O O 0; Page No. 37 08/13/90

^

Plant Hatch Unit I Valve Test Program Table 1 Stroke Notes Valve Code Norm lime Relief' No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

IE21-F006B 1 AC 10" Check C-4 H-16331 CS Injection C Disassemb' PIV No RR-V-13 Iso. RR-V-37 Notes 10,;

26 IE21-F012A 2 C 2" Relief D-9 H-16331 CS Pu'p Disch. C IWV-3512 NA No NA Relief IE21-F012B 2 C 2" Relief E-10 11-16331 CS Pump Disch. C _IWV-3512 NA No NA Relief IE21-F015A 2 B 10" M0 Globe D-8 H-16331 Core Spray Test C Qtr NA- Yes Note 9' Bypass Iso. s- -

IE21-F015B 2 B 10" M0 Globe C-8 H-16331 Core Spray Test C Qtr NA- Yes Note 9 Bypass Iso.

IE21-F018A 1 AC 1" Excess Flow Ck A-4 H-16331 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IE21-F0188 1 AC 1" Excess Flow Ck A-4 H-16331 Instrument 0- R0 LTV_'

No RR-V-4 Excess Flow RR-V-15 Check Valve- , 3 IE21-F018C 1 AC 1" Excesi Flow Ck A-4 H-16331 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

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

O Page No. 38 O O 08/13/90 Plant Hatch Unit i Valve Test Program- ~

Table 1 4

Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function 'Pos Exercise leakage Req'd CS Just.

IE21-F031A 2 B 3" M0 Gate F-9 H-16331 CS Pump Min. O Qtr NA Yes NA Flow IE21-F031B 2 B 3" M0 Gate F-10 H-16331 CS Pump Min. O Qtr NA Yes NA Flow IE21-F032A 2 C 1" Relief 11- 9 H-16331 CS Suct. Relief C IWV-3512 NA No NA IE21-F032B 2 C 1" Relief 11 - 1 1 H-16331 CS Suct. Relief C IWV-3512 NA No NA IE21-F036A 2 C 3" Check E-9 H-16331 CS Min. Flow C Disassemb NA No Notes 9,10' Iso.

IE21-F036B 2 C 3" Check E-10 H-16331 CS Min. Flow C Disassemb NA No Notes 9,10:

Iso.

IE21-F037A 1 A 1" A0 Plug 0-4 H-16331 Passive C None PIV No NA Isolation IE21-F037B 1 A 1" A0 Plug B-4 H-16331 Passive C None PIV No NA-Isolation IE21-F040A 2 C 1-1/2" Stop Check.E-6 H-16328 Maintain CS 0/C Qtr NA No Note 13 Water level 3 IE21-F040B 2 C 1-1/2" Stop Check E-4 H-16328 Maintain CS 0/C Qtr NA -No Note 13 Water Level

-. ~ , .. + g _

3

I m . (~ . p.

(/ 'k j Page No. 39 08/I3/90-Plant Hatch Unit 1 Valve Test Program Table 1 -

Stroke Notes-Valve Code Norm' lime Relief --

No. . Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CSJust.l IE21-F044A 2 C 2" Stop Check F-5 H-16328 Jockey Pump 0- R0 NA No RR'V-30A Bypass Iso. Note ?

IE21-F044B 2 C 2" Stop Check F-5 H-16328 Jockey Pump 0 RO NA No RR-V-30A Bypass Iso. ' Note 9

g. .

i !

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lII u u o '

D O O Paqe No. 40 08/13/90

~

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. Pal 0 Function No.

• • System - 1E41 H-16332 HPCI Steam C Qtr NA Yes NA IE41-F001 2 B 10" M0 Gate E-12 Supply Shutoff O CS CIV Yes RR-V-2 A 10" M0 Gate C-3 H-16332 HPCI Steam RR-V-4' IE41-F002 1 Supply Inbrd.

iso. C5-7 RR-V-37 0 Qtr CIV Yes RR-V-37 A 10" M0 Gate C-4 H-16332 HPCI Steam IE41-F003 1 Supply Outbrd.

Iso. ...

H-16332 HPCI Pump Suc. O Qtr NA Yes MA IE41-F004 2 B 16" N0 Gate D-9 from Cond.

Stor.

H-16332 HPCI Pump C Qtr PlV No RR-V-37 IE41-F005 2 AC 14" Check E-6 Note 25 Disch.

H-16332 HPCI Pump C Qtr PlV/CIV Yes RR-V-37 IE41-F006 2 A 14" M0 Cate E-S Inbrd. Disch.

Iso.

O Qtr NA' Yes NA 2 B 14" M0 Gate E-S H-16332 HPCI P IE41-F007 Dutbrd?bisch.

O O O Page No. 41 08/13/90 Plant flatch Unit i Valve Test Program Tabic 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd C5 Just.

IE41-F008 2 A 10" M0 Globe D-7 H-16332 HPCI Pump Test C Qtr PIV Yes RR-V-37 Bypass IE41-Foll 2 B 10" M0 Gate C-7 11-16332 HPCI Pump C Qtr NA Yes NA Redun. Shutoff to Cont. Stg.

IE41-F012 2 B 4" M0 Globe F-7 11-16332 HPCI Pump Min. C Qtr NA Yes Note 9 Flow inbrd.

Iso.

IE41-F019 2 C 16" Check D-9 H-16332 HPCI Pump Suc. C Qtr NA No Note 2 Cond. Sig. c-IE41-F020 2 C 2xl* Relief D-8 11-16332 IIPCI Pump C IWV-3512 NA No NA Suction Relief IE41-F021 2 C 12" Stop Check G-3 H-16332 HPCI Turb. Exh. C Note 25 NA No RR-V-304 Inbrd. Iso. Notes 9.2 IE41-F022 2 0 2" Stop Check G-4 H-16332 HPCI Turb. Exh. C Disassemb NA No RR-V-30A f

Drn. Torus Iso. Notes 9,10,24 IE41-F024A I AC 1" Excess Flow Ck C-4 H-16332 Instrument 0 R0 LTI ' No RR-V-4 Excess Flow RR-V-15 Check Valve e " , , - ,. _,__J

O O O Page No. 42 08/13/90 Plant Hatch Unit i Valve Test Program Table i Stroke Notes Norm Time Relief Valve Code Coord. P&l0 Function Pos Exercise leakage Reg'd C5 Just.

No. Class Cat. Description 0 RO LTV No RR-V-4 AC l' Excess Flow Ck 0-4 H-16332 Instrument RR-V-15 IE41-F024B 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-4 H-16332 Instrument RR-V-15 IE41-F024C 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" E, ess Flow Ck D-4 H-16332 Instrument RR-V-15 IE41-F0240 1 Excess Flow Check Valve Disassemb wNA No RR-V-30A, 2 C 2" Check G-5 H-16332 HPCI Turb. Exh. C Notes IE41-F040 Drn. Torus Iso. 9.10.25 H-16332 HPCI Pump Suc. C Qtr NA Yes NA 2 B 16" N0 Gate D-8 IE41-F041 Shutoff H-16332 HPCI Pump Suc. C Qtr NA Yes Note 9 IE41-F042 2 8 16" M0 Gate J-5 Torus Dutbrd.

Iso.

Disassemb NA . No RR-V-7, 16" Check J-7 H-16332 HPCI Pump C IE41-F045 2 C Suction Note 10 Disassemb NA No RR-V-30A, 4" Check F-8 H-16332 HPCI P g Min C Netes 9,10 IE41-F046 2 C Flow Dutbrd.

Iso.

a V Page No. 43 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

IE41-F048 2 C 2" Check H-9 H-16333 Lube Oil C Disassemb NA No Note 10 Cooling Wtr Return Check IE41-F049 2 C 20' Check G-4 H-16332 HPCI Turb. Exh. C Qtr NA No RR-V-304 Outbrd. Iso. Notes 9.25 IE41-F051 2 B 16" A0 Bfly J-4 11-16332 HPCI Pump Suc. O Qtr NA Yes Note 9 Torus Inbrd.

Iso.

IE41-F057 2 C 2" Ched 11- 1 0 11-16333 Lube Oil C Disassemb NA No Note 10 Cooling Wtr e-Return Check IE41-F059 2 B 2" M0 Globe F-8 11-16333 HPCI Turb. Lube C Qtr NA Yes MA Oil Cooling IE41-F102 2 C 1" Check G-2 H-16332 Vacuum Relief C RO NA No RR-V-4 RR-V-23 IE41-F103 2 C 1" Check G-2 H-16332 Vacuum Relief C RO NA No RR-V-4 RR-V-23 IE41-F104 2 A 2" M0 Gate G-3 H-16332 HPCI Vac. O Qtr CIf ' Yes NA Relief Outbrd.

Torus Iso.

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b Page No. 45 O O 08/13/90 4

~

Plant Hatch Unit I Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

• • System - IE51 IE51-F001 2 C 10" Stop Check G-5 11-16334 RCIC Turb. Exh. C Note 25 NA No RR-V-30A, inbrd. Iso. Notes 9.&

IE5!.rn02 2 0 2" Stop Check G-6 If-16334 RCIC Turb. Exh. C Note 25 NA No RR-V-304, Drn. Torus Iso. Notes 9.2 IE51-F003 2 8 6" A0 Bfly J-6 H-16314 RCIC Pump 0 Qtr NA Yes Note 9 Suction Torus inbrd. Iso.

IE51-F007 1 A 4" M0 Gate C-5 11-16334 RCIC Steam O CS CIV Yes RR-V-2 Supply Inbrd. .- RR-V-4 Iso. C5-7 IE51-F008 I A 4" M0 Gate C-6 H-16334 RCIC Steam 0 Qtr CIV Yes NA Supply Outbrd.

Iso.

IE51-F010 2 8 6" M0 Gate C-8 11-16334 RCIC Pump Suc. O Qtr NA Yes Note 17 from Cond.

Stor.

IE51-F0ll 2 C 6" Check D-8 11-16334 RCIC Pump Suc. C Qtr Nq No Notes 2.{

Cond. Stor.

IE51-F012 2 B 4" M0 Gate E-8 H-16334 RCIC PM 0 Qtr NA Yes Note 17 Outbrd. Disch.

D O O Page No. 46 08/13/90 Plant Hatch Unit i Valve Test Program Tabic 1 Stroke Notes Norm Time Relief Valve Code Coord. p&l0 Function Pos Exercise Leaka9e Reg'd C5 Just.

No. Class Cat. Description Qtr PlV/CIV Yes NA A 4" M0 Gate E-6 H-16334 RCIC Pump C IE51-F013 2 Inbrd. Disch.

Iso.

H-16334 RCIC Pump t Qtr PIV No Notes 17 2 AC 4" Check E-7 25 IE51-F014 Disch.

H-16335 RCIC Pump C IWV-3512 NA No Note 17 2 C 1" Relief C-6 IE51-F017 Suction Relief H-16334 RCIC Pump Min. C Qtr NA Yes Note 9 2 B 2" M0 Globe F-7 IE51-F019 Flow inbrd. v Iso.

Disassemb NA No RR-V-30A, 2" Check F-8 H-16334 RCIC Pump Min. C Notes 9,10 IE51-F021 2 C Flow Outbrd.

Iso.

H-16334 RCIC Pump Test C Qtr FIV Yes Note 17 2 A 4" M0 Globe C-6 IE51-F022 Bypass No RR-V-30A, G-7 H-16334 RCIC Turb. Exh. C Note 25 NA IE51-F028 2 C 2" Check- Note 9 Drn. Torus H-16334 RCIC Pump Suc. C Qtr NA " Yes Note 17 2 8 6" M0 Gate D-8 IE51-F027 Shutoff

O V l Page No. 47 08/13/90

~

Plant Hatch Unit i Valve Test Program Table i Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function' Pos Exercise leakage Reg'd. CS Just.

IE51-F030 2 0 6* Check J-7 H-16334 RCIC Pump C Disassemb NA No Notes 17, Suction 18 IE51-F031 2 B 6" M0 Gate J-6 11-16334 RCIC Pump C Qtr NA Yes Note 9 Suction Torus Outboard Iso.

IE51-F040 2 C 10" Check G-5 H-16334 RCIC Turb. Exh. C Note 25 NA No RR-V-30A.

Outbrd. Iso. Note 9 IE51-F044A 1 AC 1" Excess Flow Ck B-5 H-16334 Instrument 0 R0 LTV No RR-V-4 i Excess Flow RR-V-15 Check Valve v-IE51-F0448 1 AC I" Excess Flow Ck D-5 H-16334 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve IE51-F044C 1 AC 1" Excess Flow Ck 8-5 H-16334 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 i Check Valve IE51-F044D 1 AC 1" Excess Flow Ck 0-5 H-16334 Instrument 0 R0 LTV No RR-V-4 Excess flow I.

RR-V-15 i Check Valve IE51-F045 2 8 4" M0 Globe 0-11 H-16335 RCIC Steam C Qtr NA Yes Note 17 Supply Shutoff

-- ,.s g.

( Y Page No. 48 08/13/90 Plant flat-h Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise Leakage Reg'd CS Just.

IE51-F046 2 8 2" M0 Globe E-6 H-16335 RCIC Turb. Lube C Qtr NA Yes Note 17 Oil Cooling IE51-F047 2 C 2" Check G-8 H-16335 Lube Oil C Disassemb NA No Notes 17, Cooling Wtr 18 Return Check IE51-F102 2 C 1 1/2" Check F-5 11-16334 Vacuum Relief C 'R0 NA Na Notes 17, +

19 IE51-F103 2 C 1 1/2" Check F-5 H-16334 Vacuum Relief C RO NA No Notes 17, 19 a

IE51-F104 2 A 1 1/2" M0 Gate G-5 H-16334 RCIC Vac. O Qtr CIV Yes MA Relief Outbrd.

l Torus Iso.

1 IE51-F105 2 A 1 1/2" M0 Gate G-5 H-16334 RCIC Vac. O Qtr CIV Yes NA Relief Inbrd.

Torus iso.

I i

- - - - y--%, , y r -- - ,, . . , - . a- ,m, ~ --,,% ,%- - - ,, ,

O Page No. 49 O O -

08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd. CS Just.

l i ** System - 1Gil

IGil-F003 2 A 3" A0 Gate B-3 H-16176 DW Fir. Drns. O Qtr CIV Yes NA Cont. Iso.

IGil-F004 2 A 3" A0 Gate B-3 H-16176 DW Fir. Drns. O Qtr CIV Yes NA Cont. Iso.

, IGil-F019 2 A 3" A0 Gate E-3 H-16176 DW Equip. Drns. O Qtr CIV Yes NA Cont. Iso.

l IGil-F020 2 A 3" A0 Gate E-4 H-16176 DW Equip. Drns. O Qtr CIV Yes NA

( Cont. Iso.

s-l

, t

-, ~ , . , , , w n-e

O O O Page No. 50 08/13/90

~

~

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise leakage Rea'd CS Just.

Class Cat. Description Coord. P&lD No.

• • System - IG31 H-16188 RWCU Pump Soc. O CS CIV Yes RP-V-4 A 6" M0 Gate B-2 RR-V-37 IG31-F001 1 Inbrd. Iso. C5-12 H-16188 RWCU Pump Soc. O CS CIV Yes RR-V-4 A 6" MO Gate B-3 RR-V-37 1G31-F004 1 Outbrd. Iso. 05-12 O R0 CIV No RR-V-4 AC 4" Check A-4 H-16188 RWCU Disch. RR-V-18 IG31-F039 1 150.

O R0 , CIV No RR-V-4 AC 3" Check A-4 H-16188 RWCU Disch. RR-V-18 IG31-F203 1 Iso.

1 4

_ _ . _ _ _ _ _ _ _ _ . Il

O O O Page No. 51 08/13/90 Plant Hatch Unit i Valve-Test Program Table i Stroke Notes Valve Code No. Class Cat. Description Coord. P&ID Function s Exercise Leakage R d S ust.L

• • System - IP21 IP21-F353 2 A 2" Manual Gatt F-7 H-16015 Passive Cont. LC Mone CIV No NA Iso.

IP21-F420 2 A 1-1/2" Man Gate F-8 11-16015 Passive Cont. LC None CIV No NA Iso.

l

(O Page No. 52 08/13/90 i

) Plant Hatch Unit i Valve Test Program j Table I Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise leakage Reg'd C5 Just.

• • System - IP33 IP33-F002 2 A 1" A0 Globe B-4 H-16276 H2 & 02 Analy. O Qtr CIV Yea NA Cont. Iso.

IP33-F003 2 A 1" A0 Globe D-4 H-16276 H2 & 02 Analy. C Qtr CIV Yes NA Cont. Iso.

IP33-F004 2 A 1" A0 Globe E-4 H-16276 H2 & 02 Analy. O Qtr CIV Yes NA Cont. Iso.

IP33-F005 2 A 1/2" SO Globe C-4 H-16276 H2 & 02 Analy. O Qtr CIV Yes MA Cont. Iso.

IP33-F006 2 A 1" A0 Globe G-4 H-16276 H2 & 02 Analy. C Qtr CIV Yes NA Cont. Iso.

IP33-F007 2 A 1" A0 Globe H-4 H-16276 HZ & 02 Analy. O Qtr CIV Yes MA Cont. Iso.

IP33-F010 2 A 1" A0 Globe B-5 H-16276 H2 & 02 Analy. O Qtr CIV Yes NA Cont. Iso.

J IP33-F0ll 2 A 1" A0 Globe D-5 H-16276 H2 & 02 Analy. C Qtr CIV Yes MA Cont. Iso. ,.

! IP33-F012 2 A 1" A0 Globe E-5 H-16276 H2 & 02 Analy. O Qtr CIV Yes 'NA Cont. Iso.

I l.

'O

! Page No. 53 08/13/90 Plant Hatch Unit i Valve Test Program -

j Table I l

Stroke Notes Valve Code Norm Time Relief

. No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd C5 Just.:

l IP33-F013 2 A 1/2" SO Globe C-4 H-16276 H2 & 02 Analy. O Qtr CIV Yes MA Cont. Iso.

IP33-F014 2 A 1" A0 Globe G-5 H-16276 H2 & 02 Analy. C Qtr CIV Yes MA Cont. Iso.

l IP33-F015 2 A I" A0 Globe 11- 5 11-16276 H2 & 02 Analy. O Qtr CIV Yes NA

Cont. Iso.

l 5-l t

- _ . _ _ _ . _ __- _____________.___________._._____._m___.__ . . _ . . . _ _ _ _ _ _ _ _ _ _ . . _ -

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

Page No. 54 08/13/90 Plant ifatch Unit I Valve Test Program Table 1 5troke Notes Norm limp Relief Valve Code Function Pos Exercise Leakage Reo'd C5 Just.

No. Class Cat. Description Coord P&lD

• • System - IP41 H-160ll HPCI Pump Room C Disassemb NA No RR-V-19 3 C 1-1/2" Check B-8 Note 10 IP41-F024A Cooler 11-16011 HPCI Pump Room C Disassemb NA No RR-V-19 3 C 1-1/2" Check C-8 Note 10 IP41-F024B Cooler Disassemb NA No RR-V-19 3" Check D-8 H-160ll RHR & CS Pump C Note 10 IP41-F025A 3 0 Room Cooler Disassemb NA No RR-V-19 D-8 H-16011 RHR & CS Pump C IP41-F025B 3 C 3" Check Note 10 Room Cooler H-160ll RHR Pump Cooler C Disassemb NA No RR-V-19 3 C 3" Check G-7 Note 10 1P41-F026A H-160ll RHR Pump Cooler C Disassemb NA No RR-V-19 3 0 2" Check G-7 Note 10 1P41-F026B Disassemb NA No Notes 17, G-2 H-160ll RCIC Pump C IP41-F028A 3 C 1 1/2" Check Cooler Disch. 18 Chk.

Disassemb No Notes 17, G-3 H-160ll RCIC Pump C NA,,

IP41-F028B 3 C 1 1/2" Check Cooler Disch. 18 Chk.

O O O Page No. 55 08/13/90 Plant Hatch Unit i Valve Test-Program Table 1 Stroke Notes Norm Time Reitef Valve Code Function Pos Exercise Leaka9e Reg'd 05 Just.

No. Class Cat. Description Coord. P&ID H-160ll HPCI Pump Room C Qtr NA Y?s RR-V-20 3 B 2" A0 Globe B-9 IP41-F035A Cooler 11-16011 HPCI Pump Room C Qtr NA Yes RR-V-20 3 B 2" A0 Globe C-9 IP41-F035B Cooler 11-16011 RHR & CS Pump C Qtr NA Yes RR-V-20 3 8 3" A0 Globe D-9 IP41-F036A Room Cooler H-160ll RHR & CS Pump C Qtr NA Yes RR-V-20 IP41-F0368 3 8 3" A0 Globe 0-9 Room Cooler H-160ll RHR Pump Cooier C Qtr 6 NA Yes RR-V-20 3 B l-1/2" A0 Globe H-B IP41-F037A H-160ll RHR Pump Cooler C Qtr NA Yes RR-V-20 3 8 1-1/2" A0 Globe E-9 IP41-F037B H-160ll RHR Pump Cooler C Qtr NA Yes ER-V-20 3 8 1-1/2" A0 Globe J-B IP41-F0370 H-160ll RHR Pump Cooler C Rtr NA Yes RR-V-20 3 8 1-1/2" A0 Globe E-9 IP41-F0370 H-160ll RHR Pump Cooler C Qtr NA Yes RR-V-20 3 B 3" A0 Globe G-8 IP41-F039.1 H-160ll RHR Pump Cooler C Qtr NA Yes RR-V-20 3 B 3" A0 Globe G-B IP41-F0398 H-160ll RCIC Pump Rm C Qtr Nd ' Yes Notes 12.

3 B 1 1/2" A0 Globe H-2 17 IP41-F040A Cooler Control

_____ - di

O Page No. 56 O O 08/13/90 Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

IP41-F0408 3 8 1 1/2" A0 Globe H-2 H-160ll RCIC Pump Rm C Qtr NA Yes Notes 12, Cooler Control 17 IP41-F049 2 A 8" M0 Gate F-6 11-16011 Drywell Air 0 CS CIV Ves RR-V 4 Cooler Iso RR-V-37 CS-3 4 IP41-F050 2 A 8" M0 Gate D-2 11-16011 Drywell Air 0 CS CIV Yes RR-V-4 Cooler Iso RR-V-37 C5-3 IP41-F064 3 0 6" Check F-10 11-16011 Division 2 S.W. O Disassemb. NA No Note 10 Supply v-l IP41-F065 3 C 8" Check G-10 H-160ll Division 1 S.W. O Qtr NA No Note 16 Supply IP41-F1074 3 C 4" Check E-1 H-ll609 Control Room 0 Disassemb. NA No Note 10 HVAC IP41-F1075 3 C 4" Check E-1 H-Il609 Control Room 0 Disassemb. NA No Note 10 HVAC IP41-F310A 3 8 30" M0 Bfly D-6 H-Il600 S.W. to Turbine O CS NA , Yes RR-V-4 Bldg. Shutoff CS-4 IP41-F3108 3 8 30" M0 Bfly F-5 H-Il600 S.W. to Turbine O CS NA Yes RR-V-4 Bidg. Shutoff CS-4

U Page No. 57 O O 08/13/90 Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise leakage Req'd CS Just.'

IP41-F3100 3 8 30" M0 Bfly D-6 H-Il600 S.W. to Turbine O CS N. .r RR-V-4 B1dg. Shutoff CS-4 IP41-F3100 3 8 30" M0 Bfly F-5 H-11600 S.W. to Turbine O CS NA Yes RR-V-4 Bldg. Shutoff CS-4 IP41-F311A 3 C 18" Check D-2 0-11001 S.W. Pump 0/C Qtr NA No RR-V-25 Discharge IP41-F3118 3 C 18" Check D-5 D-11001 S.W. Pump 0/C Qtr NA No RR-V-25 Discharge IP41-F311C 3 C 18" Check D-3 0-11001 S.W. Pump 0/C Qtr . NA No RR-V-25 Discharge I

IP41-F3110 3 C 18" Check D-6 D-11001 S.W. Pump 0/C Qtr NA No RR-V-25 Discharge l

l IP41-F340 3 B 6" A0 Bfly B-5 H-Il600 Diesel Gen. C Qtr NA Yes RR-V-20 Cooling IP41-F438A 3 C 1 1/2" Check B-3 D-11001 Service Water 0 Qtr NA No Note 5 Motor Cooling i Wtr Check ,

IP41-F4388 3 C 1 1/2" Check A-6 D-11001 Service Water 0 Qtr NA No Note 5 Motor Cooling Wtr (. heck

I t 1 1 fs 4 4 seu - -

_ eiJ V V tl - -

oeS R R NRC R R

-O k e

o ti e STR d

rme 'g e

N o

N o

g a

k i a

e A A l N N -

u e

s i

c r

e r r x t t E Q Q m

rs oo m NP C C a

r g A C o I I r

P nr

.eg nr

.eg t ea ea s n Gh Gh e o c c T i l s l s t ei ei e c sD sD v n e e l1 u iW iW a F DS DS Ve l 0 0 ib 0 0 a 6 6 tT D l l i I I I n & - -

U P H H O F t

H c

a d

r o

o 7

2 C B B t

n a

l P

n i

o t k k p c c i e e r h h c C C s

e "

D "6 6 t

a C C C s

es da ol CC 3 3 8 "

5 A C 2 2 0 5 5 o9 5 5 N/ F F 3 e - -

e1 v 1 1 g

,/ l . 4 4 ao b P0 8 P P VN I I

O Page No. 59 O O 08/13/90 Plant Hatch Unit i Valve Test Program Table,I Stroke Notes Valve Code Norm ilme Relief-

No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.

t

• • System - IP42 ,,

IP42-F051 2 A 4" M0 Gate B-9 H-16009 RBCCW to Recir. O CS CIV Yes RR-V-4 Cont. Iso, 05-5 IP42-F052 2 A 4" M0 Gate E-9 11-16009 RBCCW to Recir. O CS CIV Yes RR-V-4 Cont. Iso. CS-5 i

t*

I!

i

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

i-Page No. 60

08/13/90 Plant Hatch Unit i Valve _ Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.

• • System - IP51 IP51-F513 2 A 2" Man. Globe F-3 H-16013 Passive Cont. LC None CIV No NA Iso.  ;

IP51-F514 2 A 2" Man. Globe F-3 H-16013 Passive Cont. LC None CIV No NA Iso.

1 jl i

O O O Page No. 61 08/13/90 Plant Hatch Unit i Valve Test Program Table I Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.

• • System - IP70 IP70-F002 2 A I" A0 Globe F-8  :;-16286 DW Pneumatic C None CIV Yes NA Cont. Iso.

IP70-F003 2 A 1" A0 Globe F-8 H-16286 DW Pneumatic C None CIV Yes MA Cont. Iso.

IP70-F004 2 A  ?" Solenoid 8-8 11-16286 DW Pneumatic 0 Qtr CIV Yes NA Cont. Iso.

IP70-F005 2 A 2" Solenoid 8-8 H-16286 DW Pneumatic 0 Qtr CIV Yes MA Cont. Iso.

i.

IP70-F066 2 A 2" Solenoid D-8 H-lE286 DW Pneumatic 0 Qtr CIV Yes MA Cont. Iso.

IP70-F067 2 A -2" Solenoid D-8 H-16286 DW Pneumatic 0 Qtr CIV Yes NA Cont. Iso.

t*

O O O PJge No. 62 0d/13/90 Plant Hatch Unit i Valve Test Program Tabla 1 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise Leakage Reg'd CS Just.

No. Class Cat. Description Coord. P&lD

• • System - IR43 Qtr NA No Notes 7,1?

0 2" Check C-2 11-11037 D.G. Fuel Oil C IR43-F009A -

Pump Discharge Check Qtr NA No Notes 7,1?

0 2" Check C-2 11-11037 D.G. Fuel Oil C IR43-F0098 -

Pump Discharge Check No Notes 7,1?

0 2" Check A-10 11-11037 D.G. Fuel Oil C Qtr NA 1R43-F009C -

Day Tank Inlet Check '

NA No Notes 7,1?.

C 2" Check A-9 H-11037 D.G. Fuel Oil C Qtr IR43-F0090 -

Day Tank Inlet Check Qtr NA No Notes 7,Il IR43-F010A -

C 2" Check D-2 H-11037 D.G. Fuel Oil C Pump Discharge Check No Notes 7,1)

C 2" Check 0-2 H-11037 D.G. Fuel Oil C Qtr NA 1R43-F0108 -

Pump Discharge Check t Qtr NA No Notes 7,1)

C 2" Check A-8 H-11037 D.G. Fuel Oil C IR43-F010C -

Day Tank Inlet Check

___--- a a

t

,q p ,g l Page No. 63 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes l Valve Code Norm Time Relief.

j No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.;

IR43-F0100 -

C 2" Check A-8 H-Il037 D.G. Fuel Oil C Qtr NA No Notes 7, Day Tank Inlet l

Check i

l IR43-F0llA -

C 2" Check B-2 11-11037 D.G. Fuel Oil C Qtr NA No Notes 7,1 l Pump Discharge l Check 1R43-F0llB -

C 2" Check B-2 11-11037 D.G. Fuel Oil C Qtr NA No Notes 7,1 Pump Discharge Check l 1R43-F0 llc -

C 2" Check A-Il 11-11037 D.G. Fuel Oil C Qtr s NA No Notes 7, Day Tank Inlet Check 1R43-F0110 -

C 2" Check A-Il H-l!037 D.G. Fuel Oil C Qtr NA No Notes 7 )

Day Tank Inlet Check 1R43-F015A -

B 1 1/2" 3-Way Sol. H-6 H-ll631 0.G. Air Start C Qtr NA Yes Notes 17,

< Valve 21 i IR43-F0158 -

B 1 1/2" 3-Way Sol. B-9 H-Il638 D.G. Air Start C Qtr NA' Yes Notes 17, Valve 21 1R43-F015C -

B 1 1/2" 3-Way Sol. H-6 H-ll631 0.G. Air Start C Qtr NA Yes Notes 17.

Valve 21

d O O Page No. 64 08/13/90

~

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time Relief Valve Code Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. P&l0 Function No.

H-Il631 D.G. Air Start C Qtr NA Yes Notes 17 IR43-F016A -

B 1 1/2" 3-Way 501. J-6 21 Valve s Yes Notes 17, B 1 1/2" 3-Way Sol. A-9 H-Il638 D.G. Air Start C Qtr NA IR43-F016B -

Yalve 21 Qtr NA Yes Notes 17, 1R43-F0160 -

B 1 1/2" 3-Way 501. J-6 11-11631 D.G. Air Start C 21 Valve Qtr NA No Notes 14 1R43-F3034A -

C 3/4" Check G-4 H-Il631 Air Receiver C 17 Inlet Check Valve

' NA No Notes 14, C 3/4" Check C-9 H-ll638 Air Receiver C Qtr IR43-F30348 -

Inlet Check 17 Valve H-II631 Air Receiver C Qtr MA No Notes 14 IR43-F3034C -

C 3/4" Check G-4 17 Inlet Check Valve H-Il631 Air Receiver C Qtr NA No' Notes 14 C 3/4" Check G-4 IR43-F3035A -

Inlet Check 17 Valve g Qtr RA No Notes 14 C 3/4" Check C-10 H-II638 Air Receiver C IR43-F30358 -

Inlet Check 17 Valve

_ "- h la n

'3 O .(V

.f~)

V-Page No. 65 08/13/90

' ~ '

Plant Hatch Unit i Valve Test Program Table 1 l

l Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.j 1R43-F30350 -

C 3/4" Check G-4 H-ll631 Air Receiver C Qtr NA No Notes 14c Inlet Check 17 Valve IR43-F3036A -

C 1/2" Relief G-5 H-11631 Air Receiver C IWV-3512 NA No Note 17 Relief Valve IR43-F30368 -

C I/2" Relief C-9 H-Il638 Air Receiver C IWV-3512 NA No Note 17 Relief Valve IR43-F3036C -

C 1/2" Relief G-5 H-Il631 Air Receiver C IWV-3512 NA No Note 17 Relief Valve l

IR43-F3037A -

C 1/2" Relief G-3 H-Il631 Air Receiver C IWV-3512 NA No Note 17 Relief Valve IR43-F30378 -

C 1/2" Relief C-Il H-Il638 Air Receiver C IVW-3512 NA No Note 17 Relief Valve IR43-F3037C -

C I/2" Relief G-3 H-ll631 Air Receiver C IWV-3512 NA No Note 17 Relief Valve I !

- - _ ._- u;_ -_ _ . _ _ _

-s_

)

v Page No. 66 08/13/90 Plant Hatch Unit i Valve Test Program ~

Table I i Stroke Notes

Valve Code Norm Time Relief i

No. Class Cat. Description Coord. P&l0 Function Pos Exercise Leakage Reg'd CS Just.

l

• • System - IT23 IT23-F004 2 A 3/4" Man. Globe D-3 H-16060 Passive Cont. C None CIV No NA iso.

IT23-F005 2 A 3/4" Man. Globe D-3 H-16060 Passive Cont. C None CIV No NA iso.

v'

+

Page No. 67 l 08/13/90

" ~

Plant flatch Unit i Valve Test Program Table 1 l

l Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.

l ** System - IT46 l IT46-F001A 3 B 18" A0 Bfly C-1 H-16020 Filter Bed C Qtr NA Yes Note 17 i Inlet from l

Reactor Bldg.

j IT46-F001u 2 B 18" A0 Bfly G-1 11-16020 Filter Bed C Qtr NA Yes Note 17

Inlet from i Reactor Bldg.

l IT46-F002A 3 B 18" A0 Bfly C-6 H-16174 SGTS Filter C Qtr NA Yes Note 17 l Outlet from Reactor Bldg.

IT46-F002B 3 B 18" A0 Bfly F-6 H-16174 SGTS Filter C Qtr NA Yes Note 17 Outlet from Reactor Bldg.

I !

_ _ _- -__________-_____._____=_._a . _ _ . _ . _ _ . - . - _ _ . - = - - . - . - - - . + _ -

- . - -~-

O O Page No. 68 08/13/50 Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Norm Time- . Relief Valve Code Pos Exercise leakage Reg'd CS Just.

Class Cat. Description Coord. P&ID Function No.

• • System - IT48 E-10 11-16000 N2 Supply Iso. C Qtr NA Yes Note 17-IT48-F013A 2 B 2" M0 Globe 11-16000 N2 Supply Iso. C Qtr NA Yes Note 17-IT48-F013B 2 B 2" MO Globe E-10 Il-16000_N2 System C IWV-3512 NA No Note 17 IT48-F035 -

C 3" Relief E-3 Relief RO NA No RR-V-4 C 2" Check A-7 11-16000 N2 Tank Disch. O Notes 17, IT48-F079 2 Check 23 C Qtr CIV Yes RR-V-37 A 6 A0 Bfly F-2 11-16000 DW & Torus ,

IT48-F103 2 Supply Iso.

C Qtr CIV Yes NA A 1" AG Globe G-4 11-16000 DW & Torus IT48-FIC4 2 Outbrd. Iso.

H-16000 DW Inerting .C. Qtr CIV Yes NA 2 A 2" A0 Globe F-7 1T48-F113 Dutbrd. Iso.

l1-16000 DW Inerting C Qtr CIV Yes NA IT48-F114 2 A 2" A0 Globe F-3 Inbrd. Iso.

2" A0 Globe G-7 11-16000 DW Inerting C Qtr Cit Yes NA 1T48-F G 2 A Dutbrd. Iso.

~

('

s

(}.

v _

v(' '\ .-

Page No. 69-08/13/90

' ^

Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time ' Relief.

ho. Class Cat. Description Coord. P&iD Function Pos Exercise Leakage Peq'd CS Just.

IT48-Fil6 2 A 2" A0 Globe G-8 H-16000 DW Inerting C Qtr CIV Yes -NA Outbrd. Iso.

IT48-Fil8A 2 A 1" Solenoid G-5 H-16000 DW Makeup C -Qtr '!F Yes NA Inbrd. Iso.

1T48-Fil88 2 A 1" Solenoid G-5 H-16000 Torus Makeup C Str CD Yes NA Inbrd. Iso.

IT48-F307 2 A IG" A0 Bfly C-9 H-16024 DW Purge inlet C Qtr rid Yes RR-V Inbrd. Iso.

IT48-F308 2 A 18"' A0 Bfly C-10 H-16024 DW Purge Inlet C Qtr i CIV Yes RR-V-37.

Inbrd. Iso.

IT48-F309 2 A 18" A0 Bfly E-10 H-16024 Torus Purge C Qtr CIV Yes RR-V-37 Inlet Inbrd.

Iso.

IT48-F310 2 A 20" A0 Bfly F-10 H-16024 Torus Purge C' Qtr. CIV Yes RR-V-37 Vac. Brker.

Iso.

IT48-F311 2 A 20" A0 Bfly F-9 H-16024 Torus Purge C Qtr CIV' . Yes RR-V-37 Vac. Brker.

Iso.

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

U Page No. 70 O O L 08/13/90 -

~

Plant flatch Unit 1 Valve Test Program -

Table 1 Stroke Notes .

Valve Code Norm Time . Relief No. Clase. Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

IT48-F318 2 A 18" A0 Bfly G-4 11-16024 Torus Purge C Qtr CIV Yes RR-V-37 Outlet Inbrd.

Iso.

IT48-F319 2 A 18" A0 Bfly 0-4 11-16024 DW Purge Outlet C Qtr CIV Yes RR-V-37 Inbrd. Iso.

IT48-F320 2 A 18" A0 Bfly 0-3 11-16024 DW Purge Outlet C Qtr CIV Yes RR-V-37 Outbrd. Isc.

IT48-F321 2 A 2" A0 Globe J-7 H-16000 DW Inerting C Qtr CIV Yes NA Outbrd. Iso.

IT48-F322 2 A 2" A0 Globe J-8 H-16000 DW Inerting C Qtr CIV Yes NA '

Inbrd. Iso.

IT48-F323A 2 0 20" A0 Test. Chk. H-8 H-16024 DW to Torus C- Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F323B 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F323C 2 C 20" A0 Test. Chk.11-8 H-16024 DW to Torus C Qtr NA No Notes 15 Vac. Breaker p .17 IT48-F323D 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17

O O O Page No. 71 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise leakage Reg'd CS'Just.

IT48-F323E 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes"15 Vac. Breaker 17 IT48-F323F 2 0 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15, Vac. Breaker 17 IT48-F323G 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F323H 2 0 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F3231 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr 6- 70% No Notes _15 Vac. Breaker 17 IT48-F323J 2 0 20" A0 Test. Chk. H-8 H-16024 DW to Torus C '

Qtr NA No . Notes 15.

Vac. Breaker -17 IT48-F323K 2 0 20" AC Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F323L 2 C 20" A0 Test. Chk. H-8 H-16024 DW to Torus C Qtr NA No Notes 15.

Vac. Breaker 17 IT48-F324 2 A 18" A0 Bfly D-10 C Qtr CIh' Yes RR-V-37 H-16024TorusPurhe Inlet Out rd.

Iso.

Page No. 72 08/13/90 - _

~

Plant flatch Unit i Valve Test Program Table 1 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.

IT48-F325 2 A 2" A0 Globe 11 - 7 H-16000 Torus inerting C Qtr CIV Yes NA Outbrd. Iso.

IT48-F326 2 A 18" A0 Bfly G-3 H-16024 Torus Purge C Qtr CIV Yes RR-V-37 Outlet Outbrd.

Iso.

IT48-F327 2 A 2" A0 Globe 11- 8 H-16000 Torus Inerting 'C Qtr CIV Yes NA Inbrd. Iso. ,

IT48-F32SA 2 AC 20" A0 Test. Chk. G-10 11-16024 Reactor Bldg to C Qtr CIV No RR-V-37 Supp. Cham. Note 15 Vac. Brker. v IT48-F328B 2 AC 20" A0 Test. Chk. G-9 H-16024 Reactor Bldg to C Qtr CIV No 'RR-V Supp. Cham. Note 15' Vac. Brker.

IT48-F332A 2 A 2" A0 Globe E-3 H-16024 Torus Purge C Qtr CIV Yes NA Outlet Outbrd.

Iso.

IT48-F332B 2 A 2" A0 Globe F-3 H-16024 Torus Purge C Qtr CIV Yes NA Outlet Outbrd. , ,

Iso. -

IT48-F333A 2 A 2" A0 Globe E-4 H-16024 Torus Purge C Qtr CIV Yes- NA Dutlet Inbrd.

Iso.

%sM-6 w ,+- W-- A- m-imW--me - - - . w-- nwe_,m-# -le--a.e +rweinemi JnA-meu- asmm_.-.--u4-ummawn'L_-+-w-.er-+

u

9 O O Page No. 73 i 08/13/90 Plant Hatch Unit I Valve Test Progr' Table I Stroke Notes' Norm Time- Relief Valve Code Coord. P&ID Function .Pos Exercise teakage Reg'd CS Just.

No. Class Cat. Description 11-16024 Torus Purge C Qtr CIV Yes MA 2 A 2" A0 Globe F-4 IT48-F3338 Outlet inbrd.

Iso.

11-16024 DW Purge Outlet C Qtr CIV Yes MA 2 A 2" A0 Globe B-3 IT48-F334A Outbrd. Iso.

ll-16024 DW Purge Outlet C Qtr CIV Yes. NA 2 A 2" A0 Globe C-3 IT48-F334B Outbrd. Iso.

CIV Yes MA-A 2" A0 Globe B-4 11-16024 DW Purge Outlet C Qtr IT48-F335A 2 Inbrd. Iso.

C-4 11-16024 DW Purge Outlet C Qtr CIV Yes ~A N IT48-F335B 2 A 2" A0 Globe Inbrd. Iso.

CIV Yes NA 2 A 2" Solenoid H-2 H-16024 Bypass-Outbrd. C Qtr IT48-F338 Iso.

Qtr CIV Yes MA 2 A 2" Solenoid H-3 H-16024 Bypass-Inbrd. C IT48-F339 Iso.

Qtr CIV Yes NA 2 A 2" Solenoid D-4 H-16024 Bypass-Outbrd. C IT48-F340 Iso. j-Qtr CIV Yes NA 2 A 2" Solenoid D-4 H-16024 Bypass-Inbrd. C IT48-F341 Iso.

- .s -

s () v /'

Page No. 74 08/13/90 Plant Hatch Unit i Valve Test Program Table I Stroke Notes .

Valve Code Norm Time Relief' j No. Class Cat. Description Coord. P&ID Function Pos Exercise . Leakage Reg'd CS Just.-

l l ~ 148-F342A 2 A 1/2" Solenoid H-8 H-16024 Torus to DW C .Qtr CIV No RR-V-31 Vac. Breaker iso.

IT48-F342B 2 A 1/2"' Solenoid H-8 H-16024 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

IT48-F342C 2 A 1/2" Solenoid d-8 H-16024 Torus to DW C Qtr CIV No RR-V-31 i Vac. Breaker Iso.

l IT48-F342D 2 A 1/2" Solenoid 11- 8 H-16024 Torus to DW C Qtr. . CIV No RR-V-3*

Vac. Breaker Iso.

IT48-F342E 2 A 1/2" Solenoid H-8 H-16024 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

IT48-F342F 2 A 1/2" Solenoid- -H-8 H-If024 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

I' IT48-F342G 2 A 1/2" Solenoid F-8 ;I-16024 Torus to DW C Qtr CIV No. RR-V-31 Vac. Breaker Iso.

,-r-, % A - .h-

-c ,

D

.Page No. 75 O O 08/13/90 Plant Hatch Unit i Valve Test Program Table 1 Stroke. Notes :

Valve Code Norm - _ Time Reliefc No. Class Cat. Description Coord. P&lD Function Pos ~ Exercise leakage Reg'd CS Just.

IT48-F342H 2 A 1/2" Solenoid H-8 H-16024 Torus to DW C Qtr CIV. No - RR-V-31 Vac. Breaker Iso.

IT48-F342I 2 A 1/2" Solenoid H-8 H-16024 Torus to DW C Qtr CIV 'No RR-V-31 Vac. Breaker Iso.

IT48-F342J 2 A I/2" Solenoid H-8 H-16024 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

IT48-F342K 2 A 1/2" Solenoid H-8 H-16024 Torus to DW C Qtr .

CIV No RR-V Vac. Breaker Iso.

IT48-F342L 2 A I/2" Solen 31 H-8 H-16024 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

l

y. . . . . w. - . . , - . . . - . m- .e -g ..+,,,.h-.m.. ,m 4 w , m. ., t

n ~

/m U U U Page No. 1 08/13/90 .

Plant Hatch Unit 2 Valve.. Test Program Table 2 Stroke Notes Valve Code Norm ' Time Relief.

No. Class Cat. Description Coord. P&ID Function Pos Exercise -leakage Req'd CS Just.

i

** System - 2821 .

2821-F010A 1 AC 18" Check E-3 11-26000 FW Inbrd. Cont. O R0 CIV No' RR-V-1.

Iso. RR-V-4 RR-V-37 Note 2 I

i 2B21-F010B 1 AC 18" Check F-3 H-26000 FW Inbrd. Cont. O R0 CIV No RR-V i Iso. RR-V-4 l RR-V-37 j Note 2 1

RR-V-4 2821-F013A I BC 6" Relief D-6 11-26000 Main Steam C RO NA No -

Safety / Relief IWV-3512 s RR-V-29 Note 22 j 2821-F0138 1 BC 6" Relief D-6 11-26000 Main Steam C R0 NA No -RR-V-4 Safety / Relief IWV-3512 RR-V-29 ,

Note 22 2821-F013C 1 BC 6" Relief D-6 H-26000 Main Steam C R0 NA No RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22- '

2B21-F0130 1 BC 6" Relief D-6 H-26000 Main Steam C RO NA .' , No. RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22

-__ __ - _ ________-__________________________ _____________________ _________ _____________________ ______________ _ _ _ _ _ _ -_ _ _ _ _ . , = _ . . . _ _ _

O O O Page No. 2 08/13/90 Plant Hatch' Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.-

2821-F013E I BC 6" Relief D-6 H-26000 Main-Steam C R0 NA No ~RR-V-4 Safety / Relief IWV-3512 RR-V-29 '

Note 22 2B21-F013F 1 BC 6" Relief D-6 11-26000 Main Steam C R0 NA No RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22 2B21-F013G 1 BC 6" Relief D-6 H-26000 Main Steam C R0 NA No RR-V-4 i Safety / Relief IWV-3512 RR-V-29 .,

l Note 22 2821-F013H I BC 6" Relief D-6 11-26000 Main Steam C RO s- NA No RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22 2821-F013K 1 BC 6" Relief D-6 H-26000 Main Steam C R0 NA No RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22 2821-F013L 1 GC 6" Relief D-6 H-26000 Main Steam C R0 NA No RR-V-4 Safety / Relief IWV-3512 RR-V-29 Note 22-2B21-F013M 1 BC 6" Relief D-6 H-26000 Main Steam C R0 IW( ' No RR-V-4 Safety / Relief- IWV-3512 RR-V-29 Note 22 e

Page No. 3 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes ~

Valve Code Norm Time Relief

' No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd 'CS Just.

2821-F016 I A 3" M0 Gate E-8 H-26000 Main Steam Line C Qtr CIV Yes RR-V-2 '~

DRN. Inbrd. -

Iso.

2821-F019 I A 3" M0 Gate E-9 H-26000 Main Steam Line C. Qtr CIV Yes NA DRN. Outbrd.

Iso.

2821-F022A 1 A 24" A0 Globe D-8 H-26000 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 CS-9 1

2821-F0228 1 A 24" A0 Globe D-8 H-26000 MSIV 0 CS u CIV Yes RR-V-4 RR-V-10 C5-9 2821-F022C 1 A 24" A0 Globe D-8 H-26000 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 C5-9 2B21-F0220 1 A 24" A0 Globe D-8 H-26000 MSIV 0 CS CIV Yes RR-V-4' RR-V-10 CS-9 2B21-F028A 1 A 24" A0 Globe D-9 H-26000 MSIV 0 CS Cli ' Yes RR-V-C RR-V-10 !

CS-9.

l

__ _ _ _ . _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _

- _=

Page No.

tr-4 -

L 08/13/90 l

Plant Hatch Unit 2 Valve Test Program -

l Table 2 Stroke' Notes i

Valve Code Norm Time Relief-l No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Req'd CS Just.

2B21-F0288 1 A. 24" A0 Globe D-9 H-26000 MSIV 0 CS CIV Yes RR-V.4 ,

RR-V-10 05 l 2821-F028C 1 A 24".A0 Globe D-9 H-26000 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 05-9 2B21-F0280 1 A 24" A0 Globe D-9 H-26000 MSIV 0 CS CIV Yes RR-V-4 RR-V-10 05-9 l 2B21-F036A 2 C 1" Check D-3 H-28023 MSRV 0/C R0 . . . NA No RR-V-4 Accumulator Air RR-V-28 i

Supply Check 2B21-F036B 2 C 1" Check D-3 H-28023 MSRV. 0/C R0 NA -- No RR-V Accumulator Air -RR-V-28 Supply Check ,

2B21-F0360 2 0 1" Check E-4 H-280?3 MSRV .

0/C' R0 NA No RR-V-4 Accumulator Air RR-V-28

-Supply Check 2B21-F036D 2 C 1" Check - E-4 H-28023 MSRV 0/C R0 NA No' RR-V-4

. Accumulator Air RR-V-28l Supply Check g - -~.- _ w - .w.. -r. .-y.  % , y ,.-s

O Page No. 5 O O 08/13/90

^

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&lD. Function Pos Exercise' Leakage Req'd CS Just. ,

2B21-F036E 2 C 1" Check D-3 H-28023 MSRV O/C R0 NA No RR-V 4 Accumulator Air RR-V-28.

Supply Check 2821-F036F 2 C 1" Check 0-3 H-28023 MSRV 0/C R0 NA No RR-V-4 Accumulator Air RR-V-28 Supply Check-2821-F036G 2 C 1" Check E-4 H-28023 MSRV 0/C R0 NA No RR-V-4 Accuwlator Air RR-V-28 Supply Check 2B21-F036H 2 C 1" Check E-4 H-28023 MSRV 0/C R0 ,. NA No RR-V-4 Accumulator Air RR-V-28 Supply Check 2821-F036K 2 C 1" Check D-3 H-28023 MSRV O/C R0 NA No RR-V-4 Accumulator Air RR-V-28 l

Supply Check 2821-F036L 2 C 1" Check 0-3 H-28023 MSRV O/C RO NA No RR-V-4~

Accumulator Air RR-V-28 Supply Check 2821-F036M 2 C 1" Check E-4 H-28023 MSRV 0/C RO NA ! No RR-V-4 Accumulator Air RR-V-28 Supply Check

_ .u _ _ . 2 2 _ __ , _

-) g

/ kj \v'-

Page No. 6 08/13/90

~

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reo'd CS Just.

2821-F037A 3 C 6" Check H-7 H-26000 Vac. Breaker C R0 NA No RR-V-4 MSRV Disch. RR-V-Il 2B21-F0378 3 C 6" Check H-7 11-26000 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-Il 2821-F0370 3 C 6" Check H-7 H-26000 Vac. Breaker C R0 NA No RR-V-4 MSRV Disch. RR-V-Il l

2821-F037D 3 C 6" Check 11-7 11-26000 Vac. Breaker C CS NA' No RR-V-4 MSRV Disch. RR-V-Il 2B21-F037E 3 C 6" Check 11- 7 H-26000 Vac. Breaker C RO i NA No RR-V-4 MSRV Disch. RR-V-Il 2B21-F037F 3 C 6" Check H-7 11-26000 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-Il 2B21-F037G 3 C 6" Check H-7 H-26000 Vac. Breaker C- CS NA No RR-V-4 MSRV Disch.. RR-V-Il 2B21-F037H 3 C 6" Check E-7 H-26000 Vac. Breaker C RO NA No RR-V "

MSRV Disch. RR-V-II-2821-F037K 3 C 6" Check E-7 H-26000 Vac. Breaker C T:0 Nd' No RR-V-4 MSRV Disch. RR-V-Il i

1

-e -- - - - -- " - - - - s-'. -- _ m-- --s

Pa e No. 7 08 13/90 V

' ~

Plant Hatch Unit 2 Valve Test Program

• Table 2 Stroke Notes Valve Code Norm Time Relief No. Clas.s Cat. Description Coord. P&lD' Function Pos Exercise Leakage Reg'd CS Just.

2821-F037L 3 C 6" Check E-7 H-26000 Vac. Breaker C R0 NA No RR-V-4 MSRV Disch. RR-V-Il 2BPI-F037M 3 C 6" Check E-7 H-26000 Vac. Breaker C RO NA- No RR-V-4 MSRV Disch. RR-V-Il 2B21-F041 1 AC 1" Excess Flow Ck B-5 11-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow 'RR-V-15 Check Valve 2B21-F043A 1 AC 1" Excess Flow Ck C-5 11-26001 Instrument 0 R0 LTV No RR-V-4.

Excess Flow RR-V-15 Check Valve s-

^

2821-F043B 1 AC 1" Excess Flow Ck C-9 11-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F045A 1 AC 1" Excess Flow Ck C-5 11-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B21-F045B 1 AC 1" Excess Flow Ck C-9 H-26001 Instrument 0 R0 LTV No RR-V-4

Excess Flow I, RR-V-15 l Ci.eck Valve 2B21-F047A 1 AC 1" Excess Flow Ck F-5 11-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve l

l

o o-1 l

o-Page No. 8 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroite Notes t Valve Code Norm Time Relief .'

No. Class Cat. Description Coord. P&lD Function' Pos Exercise Leakage Reg'd -CS Just.

2821-F047B 1 AC 1" Excess Flow Ck F-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F049A 1 AC 1" Excess Flow Ck F-5 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F049B 1 AC 1" Excess Flow Ck F-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F051A 1 AC 1" Excess Flow Ck !!-5 H-26001 Instrument 0 R0 . LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B21-F0518 I AC 1" Excess Flow Ck H-5 H-26001 Instrument- 0 R0 LTV No RR-V-4 .

I Excess Flow RR-V-15 i Check Valve 2821-F051C 1 AC 1" Excess Flow Ck H-5 H-26001 Instrument O. R0 LTV No RR-V-4 Excess Flow RR-V I Check Valve 2B21-F0510 1 AC 1" Excess Flow Ck H-5 H-26001 Instrument 0 R0 LTk '

No RR-V Excess flow RR-V-15 Check Valve ..

1 4

_ ~ ._ vs .--v

P% r ' .-

d U-Page No. 9

08/13/90

~ ~

Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd -05 Just.-

l l 2821-F053A I AC 1" Excess Flow Ck H-5 H-26001 Instrument 0 R0 LTV No RR-V-4 l Excess Flow RR-V-15 Check Valve 2821-F0536 I AC 1" Excess Flow Ck H-5 H-26001 Instrument 0 RO LTV No RR-V-4 Excess Flow RR-V-15 l Check Valve l 2821-F053C 1 AC I" Excess Flow Ck H-5 H-26001 Instrument 0 R0 LTV No RR-V-4 I Excess Flow RR-V-15 Check Valve 2821-F0530 1 AC 1" Excess Flow Ck H-5 H-26001 Instrument 0 R0 v LTV No RR-V-4 Excess Flow RR-V-15 Check Valve l 2821-F055 I AC 1" Excess Flow Ck J-5 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F057 1 AC I" Excess Flow Ck J-5 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve U

2B21-F059A 1 AC 1" Excess Flow Ck H-9 H-26001 Instrument 0 R0 . LTV No ~ RR-V-4 Excess Flow RR-V-15 Check Valve

acsn m m -

ePage No. -10 e -

O -

08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes-Norm Time Relief Valve Code Function :Pos. Exercise Leakage Reg'd CS Just.

Class Cat. Description Coord. P&ID No.

0- R0 LTV No RR-V-4 AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V-15 2821-F059B 1 Excess Flow Check Valve 0 R0 LTV No - RR-V-4 AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V-15 2821-F059C 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4' AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V-15 2821-F059D 1 Excess Flow Check Valve 0 RO LTV No RR-V-4 AC 1" Excess Flow Ck H-9 H-26001 Instrument ,

RR-V-15 2B21-F059E 1 Excess Flow Check Valve 0 RO- LTV No RR-V-4 AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V 2821-F059F 1 Excess flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V 2821-F059G 1 Excess Flow Check Valve ~

0 RO LTV No' RR-V-4 I AC 1" Excess Flow Ck H-9 H-26001 Instrument RR-V-15 2821-F059H Excess Flow Check Valve

____..._e..

-s -

d V Q-Pige No. 11 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code .

. Norm Time- Relief-No. Class Cat. Description 'Coord. P&l0 function Pos Exercise Leakage Reg'd CS Just.

2821-F059L 1 AC 1" Excess Flow Ck H-9 H-26001' Instrument 0 R0 LTV' No RR-V-4 Excess Flow RR-V-15.

Check Valve 2B21-F059M 1 AC .1" Excess Flow Ck H-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2P21-F059N 1 AC 1" Excess Flow Ck 11-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F059P 1 AC 1" Excess Flow Ck 11-9 H-26001 Instrument 0 RO .. LTV No RR-V Excess Flow RR-V-15 Check Valve 2B21-F059R 1 AC 1" Excess Flow Ck H-9 H-26001 Instrument 0 R0- LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B21-F059S 1 AC 1" Excess Flow Ck H-9 H-26001 Instrument 0 R0 LTV No ~ RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F059T 1 AC 1" Excess Flow Ck H-9 H-26001 Instrument 0 R0 LTY No RR-V-4 Excess Flow RR-V-15 Check Valve

I Page No. 12 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes:

Valve Code Norr Time Relief No. Class Cat. Description Coord. P&ID Function Pos _ Exercise leakage Req'd .CS Just.-

2821-F059U 1 AC 1" Excess Flow'Ck H-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15' Check Valve 2B21-F061 1 AC 1" Excess Flow Ck J-9 H-26001 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F070A 1 AC 1" Excess Flow Ck 0-9 H-26000 Instrument 0 R0 LTV No- RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F070B 1 AC 1" Excess Flow Ck D-9 H-26000 Instrument 0 R0 e LTV No RR-V-4 Excess Flow 'RR-V-15 Check Valve 2821-F070C 1 AC 1" Excess Flow Ck D-9 H-26000 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B21-F0700 1 AC I"' Excess Flow Ck D-9 H-26000 Instrument 0 R0 LTV No RR-V-4 ~

Excess Flow RR-V Check Valve 2821-F071A 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 R0 LTV No RR-V-4 Excess flow RR-V Check Valve

.m & . ,,~y .

l k .

)I u Page No. 13

08/13/90 i

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

2B21-F071B 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 R0 LTV No RR-V-4' Excess Flow RR-V-15 Check Valve 2821-F071C 1 AC 1" Excess Flow Ck B-9: H-26000 Instrument 0 R0 LTV No RR-V-4 ~

Excess Flow RR-V-15 Check Valve 2821-F0710 1 AC 1" Excess Flow Ck B-9 H-26000' Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V Check Valve

- 2821-F072A 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 RO u LTV No RR-V l Excess Flow RR-V-15 Check Valve 2821-F0728 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 R0 LTV No RR-V-4'

' Excess Flow RR-V Check Valve 2821-F072C I AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 RU LTV No RR-V Excess Flow RR-V-15 Check Valve 2821-F0720 1 AC 1" Excess Flow Ck B-9' H-26000 Instrument' O R0 LTh' No RR-V-4 Excess Flow RR-V-15 Check Valve

i Page No. 14 08/13/90 ,

Plant Hatch Unit 2 Valve Test Program Table 2 l . Stroke Notes

! Valve Code Norm Time' Relief-No. - Class Cat. Description. Coord. P&ID Function Pos: Exer cise Leakage Req'd .CS Just.

l l 2821-F073A 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 ' R0 LTV No RR-V-4 l

Excess Flow RR-V Check Valve 2821-F0738 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 R0 LTV No RR-i-4 Excess Flow RR-V-15 Check Valve 2B21-F073C 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0 R0 LTV- No RR-V-4 Excess Flow RR-V-15

' Check Valve 2B21-F073D 1 AC 1" Excess Flow Ck B-9 H-26000 Instrument 0- R0 r- LTV No - RR-V-4 Excess Flow RR-V-15 Check Valve 2821-F076A 2 C 18" A0 Check E-2 H-26000 FW Check 0 CS NA No RR-V-4 C5-11 l

2B21-F076B 2 C 18" A0 Check E-2 H-26000 FW Check 0 CS: NA No RR-V-4 05-11 2B21-F077A I AC 18" A0 Check E-3 H-26000 FW Outbrd Iso. 0 CS CIV No RR-V-4 RR-V-37 C5-10

! 2821-F0778 1 AC 18" A0 Check E-3 H-26000 FW Outbrd 150. 0' CS CIV- .No RR-V-4 RR-V-37 CS ,

~ - - - - 4 _

o- -- , , -

. , , _ _ _ _ _ _ _ _ -- __yg____, _ _ _ _ . _ . _ _ _ _ _ _

_ , _ _ . , , , ,,_.,..,.e _

,..r

Page No. 15 O O .

08/13/90

" ~~

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time. Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just..

2821-F110B 3 C 10" Check H-7 H-26000 Vac. Breaker C- CS NA No RR-V-4 MSRV Disch. RR-V-Il 2821-F110D 3 C 10" Check H-7 H-26000 Vac. Breaker C CS NA No PR-V-4 MSRV Disch. RR-V-II:

2821-F110F 3 C 10" Check H-7 H-26000 Vac. Breaker C CS. NA No .RR-V-4 MSRV Disch. RR-V-Il 2B21-F110G 3 C 10" Check H-7 H-26000 Vac. Breaker C CS NA No RR-V-4 MSRV Disch. RR-V-Il 2B21-Fill 2 A I" A0 Gate E-10 H-26384 Pass Sample C Qtr w CIV Yes MA Valves 2821-Fil2 2 A 1" A0 Gate E-10 H-26384 Pass Sample C Qtr CIV Yes. NA Valves it i

-. .- u.- ., - . - - r.. ~# ,. . . ,.. .. - - . - . ~ . . . _y_ _._m,_

m.

O O O Page No. 16 08/13/90 Plant flatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd .CS Just)

• • System - 2831 2831-F003A 1 AC 1" Excess Flow Ck G-2 11-26003 Instrument 0 R0 LTV No RR-V Excess Flow RR-V-15 Check Valve 2831-F003B 1 AC 1" Excess Flow Ck G-2 11-26003 Instrument 0 RO LTV No RR-V-4 Excess Flos RR-V-15 Check Valve 2831-F004A I AC 1" Excess Flow Ck G-2 11-26003 Instrument 0 R0 LTV No. RR-V-4 Excess Flow RR-V-15 Check Valve s.

2831-F0048 1 'AC 1" Excess Flow Ck G-2 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F009A 1 AC 1" Excess Flow Ck 0-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B31-F0098 1 AC 1" Excess Flow Ck E-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve ,

2831-F009C 1 AC 1" Excess Flow Ck E-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve

O Page No. l17 O O 08/13/90 plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&lD Function Pos Exercise . Leakage Reg'd CS Just.

2831-F0090 1 AC I" Excess Flow Ck F-9 11-26003 Instrument 0 RO -LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B31-F010A 1 AC 1" Excess flow Ck D-9 11-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F010B 1 AC 1" Excess Flow Ck F-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess F! w - RR-V-15 Check Valve 2B31-F010C 1 AC 1" Excess Flow Ck E-9 11-26003 Instrument 0 R0 . . LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F0100 1 AC l' Excess Flow Ck F-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2B31-F0llA I AC 1" Excess Flow Ck D-9 11-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F0llB 1 AC 1" Excess Flow Ck F-9 H-26003 Instrument 0 R0 LIV No RR-V-4~

Excess Flow RR-V-15 Check Valve

W .

Page No. 18

-08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 l

Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description- Coord. P&ID Function Pos Exercise teakage Reg'd 'CS Ju~t.

2831-F0 llc 1 AC 1" Excess Flow Ck E-9 H-26003 Instrument 0 R0 LIV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F0110 1 AC 1" Excess Flow Ck G-9 H-26003 Instrument' 0 R0 LTV No RR-V-4' Excess-Flow ~ RR-V-15 Check Valve 2831-F012A 1 AC 1" Excess Flow Ck E-9 H-26003 Instrument 0 R0 L1V No= RR-V-4 txcess Flow RR-V-15 Check Valve 2B31-F0128 1 AC 1" Excess Flow Ck F-9 H-26003 Instrument 0 R0 6 - LTV No RR-V-4 ,

Excess Flow RR-V-15 Check Valve 2831-F012C 1 AC 1" Excess Flow Ck E-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2831-F0120 1 AC 1" Excess Flow Ck G-9 H-26003 Instrument 0- R0 LTV No RR-V-4

' Excess Flow RR-V-15 Check Valve 2831-F013A 1 AC 3/4" Check G-3 H-26003 Recir. Pump 0 R0 CII' No RR-V-4 Seal Wtr.' RR-V-5 i

~

l l

,f Page'No. 19 08/13/90

~

Plant Hatch Unit 2. Valve Test Program -

- Table 2 Stroke Notes Valve Code .

Norm Time Relief No. Class Cat. Description Coord. P&ID ' Function Pos Exercise Leakage' Reg'd CS'Just.

2B31-F013B 1 AC '3/4" Check G-3 H-26003 Recir. Pump 0 R0 CIV No RR-V-4 Seal Wtr. RR-V-5 2831-F017A 1 AC 3/4" Check G-2 H-26003 Recir. Pump 0 R0 CIV No RR-V-4 Seal Wtr. RR-V-5 2831-F0178 1 AC 3/4" Check G-2 H-26003 Recir. Pump 0 R0 CIV No RR-V-4 Seal Wtr. RR-V-5 2831-F019 1 A 1" A0 Globe E-4 H-26003 Reac. Sample 0 Qtr CIV Yes NA Sys. Inbrd.

l Iso.

2B31-F020 1 A 1" A0 Globe E-2 H-26003 Reac. Sample 0 Qte CIV Yes NA Sys. Outbrd.

Iso.

2B31-F031A 1 B 28" M0 Gate G-7 H-26003 Reactor 0 CS NA Yes ~RR-V-4 l

Recirculation 05-1 2831-F031B 1 B 28" M0 Gate G-7 H-26003 Reactor 0 CS NA Yes RR-V-4 Recirculation CS-1 2831-F040A 1 AC. 1" Excess Flow Ck G-9 H-26003. Instrument 0 R0 LTV. No RR-V-4

' Excess Flow

RR-V-15 Check Valve

~-:.m- ,. r- . m .,_.  :

~

O O -

. O Page No. '20 08/13/90

~ '

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes:

Valve Code Norm .

Time _ Relief No. Class Cat. Description Coord. PalD Function Pos . Exercise , Leakage Reg'd CS Just.

2831-F040B 1 AC 1" Excess Flow Ck G-9 H-26003 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR Y-15 Check Valve 2831-F040C 1 AC 1" Excess Flow Ck G-9 H-26003. Instrument 0 R0 LTV No RR-V-4' Excess Flow RR-V-15' Check Valve 2831-F0400 '

AC 1" Excess Flow Ck H-9 H-26003 Instrument 0 R0 LTV No RR-V-4' Excess .210w RR-V-15 Cneck Valve-no i

i

ePage No. 21 e o 08/13/90 Plant Hatch Unit 2 Valve Icst Prograu Table 2 Stroke Notes More Tima Reli2f Valve Ccde Coord. P&l0 F'E tion Pos fxercise leakage Req'd CS Just.

No. Class Cat. Description

• • System - 2011 A-5 11-26007 Scram Disch. O Qtr NA Yes RR-V-39 2Cll-F010A 2 B 1* A0 Globe Volume Vent Valve O Qtr NA Yos AR-V-39 2 B 1" A0 Globe A-5 H-26007 Scram Disch.

2CII-F010B Voline Vent Valve O Qtr NA Yes RR-V-39 2" A0 Globe B-3 11-26007 Scram Disch.

2Cll-F0ll 2 B Volume Drain Valve O Qtr ?fA Yes RR-V-39 FCll-r035A 2 8 1" A0 Globe A-5 H-26007 Scram DiscF.

Volume Ven.

Valve v es RR-V-39 B 1" A0 Globe A-5 H-26007 Scram Disch. O Qtr MA 2Cll-F035B 2 Vc'".me Vent Valve O Qtr NA Yes RR.V.39 B 2" A0 Globe B-3 H-26007 Scram Disch.

2Cll-F037 2 Volume Drain Valve g Note 20 NA No RR-V-38 3/4" Check A-6 H-26006 Scram Disch. C Motc 27 2Cll-HCU-il4 2 C Volume HCU Check Valve

D O a (V O O Page No. 22 08/13/90

~

Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Tim Relief No. Class Cat. Description Coord. P&lD function Pos Exercise leakage' Reg'd CS Just.

2Cll-HCU-Il5 2 C 1/2" Check C-6  !!-26006 Charging Water C R0 MA No RR-V-4 HCU Check Valve RR-V-26 Note 27 2Cll-HCU-126 i B 1" A0 Globe C-E H-26006 Scram Insert C Note 20 NA No RR'l-27 110U Control Not.e 27 Valve 2Cll-HCU-127 1 B 3/4" A0 Globe B-5 11-26006 Scram Disch. C Note 20 NA No RR-V.27 HCU Control Note 27' Valve 2Cll-HCU-138 I C 1/2" Check 0-4 H-26006 Cooling Water C Wkly s - NA No Notes 36 Header HCU Check Valve

, .e.

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Page No. 23 08/13/90 Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. PalD Function Pos Exercise leakage Reg'd CS Just.

• • System - 2C41 2C41-F004A 2 0 1-1/2" Expl. Act. E-2 H-26009 SLC Expl. Act. C IWV-3610 MA No NA 1

2C41-F004B 2 0 1-1/2" Expl. Act. F-2 H-26009 SLC Expl. Act. C IWV-3610 NA No NA 2C41-F006 1 AC 1-1/2" Check E-2 H-26009 SLC Outbrd C R0 CIV No RR-V-4 Cont. Iso. RR-V-6 2C41-F007 1 AC 1-1/2" Check F-2 H-26009 SLC Inbrd. C R0 CIV Mo RR-V-4 Cont. Iso. RR-V-6 2C41-F029A 2 C 1" Relief E-5 H-26009 SLC Pump Disch. C IWV-35i2 NA No NA Relief . .-

2C41-F029B 2 C 1" Relief H-5 H-26009 SLC Pump Disch. C IWV-3512 NA No NA Relief 2C41-F033A 2 C 1-1/2" Check F-4 H-26009 SLC Pump Disch. C Qtr NA No Note 2 2C41-F033B 2 C 1-1/2" Check G-4 H-26009 SLC Pump Disch. C Qtr NA No Note 2

.m. '- _ _ _ _

u -_. -

v _ u --__ _____._____.__...___._.._________._.__m-..._m - -

_. .__-_ _a - _.___.m. _ .-.__.r_ -

_.s - __m. _ _.._m__._..._,.___.____-J

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(J G 'w)

Page No. 24 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Pen'd C5 Just.

• • System - 2C51 2051-Ba11 A 2 A Ball Solenoid C-3 H-26993 TIP Inboard 0 Qtr CIV Yes NA Cont. Iso.

2C51-Ba11 B 2 A Ball Solenoid C-3 H-26993 TIP Inboard 0 Qtr CIV Yes MA Cont. Iso.

2051-Ball C 2 A Ball Solenoid C-3 H-26993 TIP Inboard 0 Qtr CTV Yes NA Cont. Iso.

2C51-Ball D 2 A Ball Solenoid C-3 H-26993 TIP Inboard 0 Qtr CIV Yes MA Cont. Iso.

2C51-F3012 2 A Solenoid F-13 H-26993 TIP N2 Purge 0 Qtr CIV Yes RR-V-32 CIV 2C51-F3017 2 AC Check E-13 H-26993 TIP N2 Purge O R0 CIV No RR-V-4 CIV RR-V-36 l

2C51-Shear A 2 0 Expl. Shear C-3 H-26993 TIP Outboard 0 IWV-3610 NA No NA Cont. Iso.

2C51-Shear B 2 0 Expl. Shear C-3 H-26993 TIP Outboard 0 IWV-3610 NA No NA Cont. Iso. g .

2C51-Shear C 2 D Expl. Shear C-3 H-26993 TIP Outboard 0 IWV-36IO MA No NA Cont. Iso.

l l

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O Page No. 25 O O 08/13/90 Plant Hatt" Unit 2 Valve Test Program

• Table 2 Streke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd C5 Just.

2051-Shear D 2 D Expl. Shear C-3 H-26993 TIP Outboard 0 IWV-3610 NA No NA Cont. Iso.

I

_ __ ._ - _ _ _ _ _ _ _ _ _ - . _ _ -_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- - _ _ - _ _ _ _ - = _ _ _ _ _ - _ _ - _ - =_ _. -_ --

p ,

d Page No. 26 08/13/90 4

Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. PalD Function Pos Exercise Leakage Reg'd C5 Just.

• • System - 2011 2Dil-F050 2 A 1" A0 Control D-5 H-26016 Fission Prod. O Qtr CIV Yes NA Mon. Cont. Iso.

2Dll-F051 2 A 1" A0 Control F-5 H-26016 Fission Prod. O Qtr CIV Yes .NA Mor;. Cont. Iso.

2DIl-F052 2 A 1" A0 Control 0-6 H-26016 Fission Prod. O Qtr CIV Yes MA Mon. Cont. Iso.

2Dil-F053 2 A 1" A0 Control F-6 H-26016 Fission Prod. O Qtr CIV Yes NA Mon. Cont. Iso.

2Dil-F058 2 A 1* Manual Globe G-3 H-26016 Passive Cont. LC None CIV No NA iso.

2Dll-F065 2 A 1" Manual Globe F-8 H-26016 Passive Cont. LC Mone CIV No NA iso.

I i-

Page No. 27

-08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm ilm Relief Valve Code Pos Exercise Leakage Reg'd C5 Just.

Class Cat. Description Coord. P&l0 Function No.

• • System - 2EII D-4 11-26015 RHR Hx Shell 0 Qtr NA Yes NA 2 Ell-F003A 2 B 16" MO Gate Side Outlet 0 Qtr NA Yes NA 2 Ell-F003B 2 B 16* M0 Gate E-8 H-26014 RilR lix Shell Side Outlet Yes Nots; 9 8 24" N0 Gate F-8 11-26015 RHR Pump 0 Qtr NA 2Ol-F004A 2 Suction Torus Iso.

H-26014 RHR Pump 0 Qtr NA Yes Note 9 2 Ell-F004B 2 B 24" MO Gate F-3 Suction Torus .-

Iso.

H-26015 RilR Pump 0 Qtr NA Yes Note 9 2 Ell-F004C 2 B 24" M0 Gate E-9 Suction Torus Iso.  ;

F-2 H-26014 RHR Pump 0 Qtr NA Yes Note 9 f 2 Ell-F004D 2 B 24" M0 Gate i Suction Torus '

Iso.

H-21039 RilR5W Pump C Qtr NA . Nn Notes 1.2 2 Ell-F005A 3 C 14" Check C-5 i Disch. Check Valve

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f~ h b b('3 Page No. 28 08/13/90

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i Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakaga Req'd CS Just.

2 Ell-F005B 3 C 14" Check F-5 11-21039 RHR5W Pump C Qtr NA No Notes 1, Disch. Check Valve 2 Ell-F005C 3 C 14" Check D-4 H-21039 RilR5W Pump C Qtr NA tio Notes I, Disch. Check Valve 3 14" Check G-4 11-21039 RHR5W Pump C Qtr NA No Notes 1, 2E11-F005D C Disch. Check Valve 2 Ell-F006A 2 B 20" M0 Gate F-8 11-26015 RiiR Shutdown C Qtr . . NA Yes NA Cooling Sys 2 Ell-F006B 2 8 20" M0 Gate F-3 11-26014 RHR Shutdown C Qtr NA Yes NA Cooling Sys 2 Ell-F006C 2 B 20" M0 Gate F-10 H-26015 RHR Shutdown C Qtr NA Yes NA Cooling Sys 2 Ell-F0060 2 8 20" M0 Gate F-2 11-26014 R11R Shutdown C Qtr NA Yes NA Cooling Sys 2 Ell-F007A 2 B 4" M0 Gate D-5 H-26014 RHR Pump Min 0 Otr NA Yes Note 9 Flow Torus iso.

m , p.

Page No. 29 U C ,

08/13/90 Plant 11atch Unit 2 Valve Test Program Tabic 2 l

Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos- Exercise Leakage Reg'd C5 Just.

2 Ell-F007B 2 B 4" M0 Gate D-6 H-26014 RHR Pump Min 0 Qtr NA Yes Note 9 Flow Torus Iso.

2 Ell-F008 I A 20" M0 Gate D-10 11-26015 RilR Shutdown C C5 PIV/CIV Yes RR-V-4

, Cooling Outbrd. RR-V-37 Iso. 05-2 2 Ell-F009 i A 20" M0 Gate D-10 H-26015 RHR Shutdown C C5 PlV Yes RR-V-4 Cooling Inbrd. RR-V-37

Iso. 05-2 2 Ell-F011A 2 B 4" M0 Gate 0-3 H-26015 RHR Cond. C Qtr MA Yes Note 9 Disch. to Torus ..-

2E11-F0llB 2 B 4" M0 Gate D-8 H-26014 RHR Cond. C Qtr NA Yes Note 9 Disch. to Torus 2 Ell-F015A 1 A 24" M0 Gate D-7 H-26015 LPCI Dutbrd. C Qtr PlV/CIV Yes RR-V-37 Cont. Iso.

i 2 Ell-F015B 1 A 24" M0 Gate D-4 H-26014 LPCI Outbrd. C Qtr PlV/CIV Yes RR-V-37 Cont. Iso.

t 2 Ell-F016A 2 A 16" M0 Globe B-7 H-26015 Cont. Spray C Qtr CIV. Yes RR-V-37 Dutbrd. Iso. '

2 Ell-F016B 2 A 16" M0 Globe B-4 H-26014 Cont. Spray C Qtr CIV Yes RR-V-37 Outbrd.lso.

O d (V Page No. 30 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd C5 Just.

2 Ell-F017A 1 B 24" M0 Globe D-7 11-26015 LPCI O Qtr NA Yes NA 2 Ell-F0178 1 B 24" M0 Globe D-4 11-26014 LPCI O Qtr NA Yes NA 2 Ell-F0EIA 2 B 16" M0 Gate B-9 H-26015 Containment C Qtr NA Yes NA Spray 1 Ell-F0218 2 B 16" M0 Gate C-2 11-26014 Containment C Qtr NA Yes NA Spray l 2 Ell-F023 2 A 4" M0 Globe B-3 H-26014 Passive Cont. C None CIV No NA Iso.

s..

2 Ell-F024A 2 B 16" M0 Globe C-6 11-26015 Suppression C Qtr NA Yes NA  !

Pool Cooling

[

(

2 Ell-F024B 2 B 16" M0 Globe 3-6 H-26014 Suppression C Qtr NA Yes NA t

l Pool Cooling '

2 Ell-F025A 2 C 1" Relief C-7 H-26015 LPCI Relief C IWV-3512 NA No Note 9 2 Ell-F025B 2 C 1" Relief C-4 H-26014 LPCI Relief C IWV-3512 NA No Note 9 2 Ell-F026A 2 8 4" M0 Gate 0-2 H-26015 Cond. Disch to C Qtr NA . Yes Note 9 RCIC 2 Ell-F026B 2 B 4" M0 Gate E-9 H-26014 Cond. Disch to C Qtr NA Yes Note 9 RCIC

OPage No. 31 O O 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Streke Notes Valve Code Norm Time Relief No. Class Cat. Descript. ion Coord. P&l0 Function Pos Exercise Leakage Rea'd CS Just.

2E11-F027A 2 B 6" M0 Globe C-7 H-26015 Suppression C. Qtr NA Yes MA Pool Spray 2 Ell-F0278 2 B 6" M0 Globe D-5 H-26014 Suppression C Qtr NA Yes NA Pool Spray 2 Ell-F028A 2 A 16" M0 Gate C-6 H-26015 Suppression C Qtr CIV Yes RR-V-37 Pool Spray Outbrd Iso.

2 Ell-F0288 2 A- 16" M0 Gate C-7 H-26014 Suppression C Qtr CIV Yes RR-V-37 Pool Spray Outbrd Iso. s.*

2 Ell-F029 2 C 1" Relief E-9 H-26015 RHR Pump Suc C IWV-3512 NA No Note 9 Relief 2 Ell-F030A 2 C 1" Relief F-8 H-26015 RHR Pump Suc C IWV-3512 NA No Note 9 Relief 2 Ell-F030B 2 C 1" Relief F-4 H-26014 RHR Pump Suc C IWV-3512 NA No Note 9 Relief 2 Ell-F030C 2 C 1" Relief F-10 H-26015 RHR Pump Suc C IWV-3512 NA , No Note 9 Relief 2 Ell-F0300 2 C I" Relief F-2 H-26014 RH2 Pump Suc C IWV-3512 NA No Note 9 Relief

l p ,,

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l Page No. 32 l 08/13/90 l

~

Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Just.

2 Ell-F031A 2 C 20" Check H-6 H-26015 RilR Pump C Qtr NA No Notes 1,2 Discharge

! 2 Ell-F031B 2 C 20" Check H-6 H-26014 RHR Pump C Qtr NA No Notes 1,2 l Discharge i 2 Ell-F031C 2 C 20" Check H-9 H-26015 RilR Pump C Qtr NA No Notes 1,2 Discharge 2 Ell-F031D 2 C 20' Check H-3 11-26014 RHR Pump C Qtr NA- No Notes 1,2' Discharge 2 Ell-F041A 2 A 1" A0 Control A-4 H-26015 RHR Inst. Iso. O Qtr s. CIV Yes NA 2 Ell-F041B 2 A 1" A0 Control A-6 H-26014 RHR inst. Iso. O Qtr CIV Yes NA 2 Ell-F041C 2 A 1" A0 Control A-8 H-26015 RHR Inst. Iso. O Qtr CIV Yes NA 2 Ell-F0410 2 A l' A0 Control A-3 H-26014 RHR Inst. Iso. 0 Qtr CIV Yes NA 2 Ell-F046A 2 C 3" Check G-6 H-26015 RHR Minimum C Disassemb NA No Note 10 Flow line 2ill-F046B 2 C 3" Check H-5 H-26014 RHR Minimum C Disassemb NA I No Note 10 Flow Line 2 Ell-F046C 2 C 3" Check G-9 H-26015 RHR Minimum C Disassemb NA No Note 10 Flow Line

O m Page No. 33 08/13/90 Plant Match Unit 2 Valve Test Program "

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Ren'd CS Just.

2 Ell-F0460 2 C 3" Check G-2 11-26014 RilR Minimum C Disassemb NA No Note 10 Flow Line 2E11-F047A 2 B 16" M0 Gate E-5 11-26015 RilR Hx Shell 0 Qtr NA Yes NA Side inlet 2 Ell-F047B 2 B 16" M0 Gate E-6 11-26014 RHR fix Shell 0 Qtr NA Yes NA Side inlet 2 Ell-F048A 2 B 24" M0 Globe D-5 H-26015 RHR Hx Shell 0 Qtr NA Yes NA Side Bypass 2 Ell-F0488 2 B 24" M0 Globe E-6 H-26014 RHR Hx Shell 0 Qtr , NA Yes NA Side Bypass l 2 Ell-F050A 1 AC 18" Test. Check 0-9 H-26015 LPCI Iso. C Disassemb PlV No RR-V.17 R 17 Nw _ 10..

26 2EII-F050B 1 AC 18" Test. Check D-3 H-26014 LPCI 1s0. C Disassemb PIV No RR-V-17 ,

RR-V-37 Notes 10,- '

p 26 2 Ell-F055A 2 C 4" Relief F-4 H-26015 RHR Hx Shell C IWV-3512 NA No Note 9 Relief

O O O Page No. 34 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes -

Valve Code Norm Time Relief.

No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Ren'd CS Just.

2 Ell-F055B 2 C 4" Relief F-7 H-26014 RilR Hx Shell C IWV-3512 NA No Note 9 Relief 2 Ell-F068A 3 8 10" M0 Ball C-10 H-26039 RilR Hx Ser. C Qtr NA No RR-V-22 Wtr. Disc.

2 Ell-F0688 3 8 10" M0 Ball G-10 H-26039 RilR lix Ser. C Qtr NA No RR-V-22 Wtr. Disc.

2 Ell-F073A 2 B 10" M0 Gate G-4 11-25G15 RitRSW to RilR C Qtr NA Yes NA Crosstie 2 Ell-F073B 2 B 10" M0 Gate G-7 H-26014 RHRSW to RHR C Qtr . NA Yes NA Crosstie 2 Ell-F075A 2 8 10" M0 Gate G-4 H-26015 RHR5W to RHR C Qtr NA Yes MA Crosstie 2 Ell-F075B 2 B 10" M0 Gate G-4 H-26014 RHRSW to RHR C Qtr NA Yes MA Crosstie 2 Ell-F078A 2 C 10" Test. Check E-4 H-26015 RHR5W to RilR C Disassemb MA No Note 10 Crosstie l

t 2 Ell-F0788  ? C 10" Test. Check E-7 H-26014 RHRSW to RifR C Disassemb NA ' No Note 10 Crosstie

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Page No. 35 08/13/90

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Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Tine Relief No. Class Cat. Description Coord. P&l0 Function Pos Exercise Leakage Req'd 05 Just.

2 Ell-F097 2 C 3" Relief E-9 H-26014 Steam Line C IWV-3512 NA No Note 9 Relief 2 Ell-F103A 2 8 1" M0 Globe E-4 H-26015 RHR lix Vent C Qtr NA Yes Note 9 Iso.

2 Ell-F1038 2 8 1" M0 Globe E-7 H-26014 RHR Hx Vent C Qtr NA Yes Note 9 Iso.

2 Ell-F122A I A 1" A0 Plug D-8 H-26015 2 Ell-F050A C None F- No NA Passive Iso.

2 Ell-F122B 1 A l' A0 Plug 0-3 H-26014 2 Ell-F050B C None . . PIV No NA Passive 1s0.

2 Ell-F124A 2 C 2" Stop Check D-4 H-26019 Maintain RHR 0/C Qtr NA No Note 13 Water Level 2 Ell-F1248 2 C 2" Stop Check D-6 H-26019 Maintain RHR 0/C Qtr NA No Note 13 Water level l

I l

L - .

Page No. 36 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Tima Relief Valve Code Function Pos Exercise Leakage Req'd CS Just.

Class Cat. Description Coord. P&lD Flo.

• • System - 2E21 H-26018 CS Pump Suction 0 Qtr NA Yes Note 9 2 B 20" M0 Gate G-7 2E21-F001A Iso.

11-26018 CS Pump Suction 0 Qtr NA Yes Note 9 2 B 20" MO Gate H-7 2E21-F001B Iso.

ff-26018 CS Puup C Qtr NA flo Note 2 2 C 12" Check F-7 2E21-F003A Discharge H-26018 CS Pump C Qtr NA No Note 2 2 C 12" Check F-9 2E21-F003B Discharge NA Yes NA E-6 H-26018 CS Outbrd. O Qtr 2E21-F004A 1 B 10" M0 Gate Injection Yes NA C-6 ff-26018 CS Outbrd. O Otr NA 2E21-F0048 1 B 10" M0 Gate Injection PIV/CIV Yes RR.V-37 10" M0 Gate E-5 H-26018 CS Press / Cont. C Qtr 2E21-F005A 1 A Iso.

Qtr PIV/CIV Yes RR-V-37 A 10" MO Gate C-5 H-26018 CS Press / Cont. C 2E21-F0058 1 150. ,

No RR-V-16, 0-4 H-26018 CS Injection C Disassemb PIV 2E21-F006A 1 AC 10" A0 Check Pressure Iso.

E-V-37 Note:; I r 26

Page No. 37 08/13/90 Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Eeakage Ren'd C5 Just.

2E21-F0068 I AC 10" A0 Check D-4 H-26018 CS Injection C Disassemb PIV a RR-V-16 Pressure Iso. RR-V-37 Notes 10, 26 2E21-F012A 2 C 2" Relief E-7 H-26018 C5 Pump Disch. C IWV-3512 NA No NA Relief 2E21-F0128 2 0 2" Relief B-7 H-26018 CS Pump Disch. C IWV-3512 NA No NA Relief 2E21-F015A 2 B 10" M0 Globe D-7 H-26018 Core Spray Test C Qtr NA Yes Note 9 Bypass Iso. $-

2E21-F0158 2 B 10" M0 Globe D-7 H-26018 Core Spray Test C Qtr NA Yes Note 9 Bypass Iso.

2E21-F018A I AC l' Excess Flow Ck B-3 H-26018 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve i

l 2E21-F018B 1 AC 1" Excess Flow Ck B-3 H-26018 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve ,.

2E21-F018C 1 AC l' Excess Flow Ck B-4 H-26018 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve l

l . . _ _ _ _ _ _ ._ _ _ _ _ - - _ _ - _ _ _ _ - _ _ _ -

O Page No. 38 O O 08/13/90 Plant Hatch Unit 2 Valve Test Program Tatile 2 Stroke Notes Valve Code Norm Twe Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

2E21-F031A 2 8 3" MO Gate F-8 H-26018 CS Pump Min. O Otr NA Yes MA Flow 2E21-F031B 2 B 3" M0 Gate F-9 H-26018 CS Pump Min. O Qtr NA Yes MA Fiow 2E21-F032A 2 C 1" Relief G-8 11-26018 CS Suct. Relief C IWV-3512 NA No NA 2E21-F032B 2 C 1" Relief G-9 H-26019 CS Sutt. Relief C IWV-3512 NA No NA 2E21-F036A 2 C 3" Check E-8 H-26018 Min. Flow Line C Disassemb MA No Notes 9,1 Iso.

2E21-F0368 2 C 3" Check E-9 Il-26018 Min. Flow Line C Disassed NA No Notes 9,1 Iso.

2E21-F037A 1 A 1" A0 Plug D-4 H-26018 ZE21-F006A C Mone PIV No NA Passive Iso.

2E21-F0378 1 A 1" A0 Plug C-4 H-26018 2E21-F006B C None PIV No NA Passive iso.

2E21-F040A 2 C 1-1/2" Stop Check D-5 H-26019 Maintain CS 0/C Qtr NA No Note 13 Water level 3 2E21-F0403 2 C 1-1/2" Stop Check D-6 H-26019 Maintain CS 0/C Qtr NA No Note 13 Water Level

Page No. 39 O O 08/I3/90 Plant Hatch Unit 2 Valve Test Program

~

Table 2 Stroke Metes Valve Code Norm Time Relicf No. Class Cat. Description Coord. PalD Function Pos Exercise leakage Req **f CS Just.

2E21-F044A 2 C 1-1/2" Stop Check E-1 H-26019 Jockey Pump 0 RO NA No RR-V-30A Bypass Iso. Note 9 2E21-F044B 2 C 1-1/2" Stop Check E-9 H-26019 Jockey Pump 0 RO NA No RR-V-30A Bypass Iso. Note 9 e*

l i

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w - ~

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Page No. 40 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norn Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakana Reg'd CS Just'

• • System - 2E32 2E32-F001B 1 A 1-1/2" M0 Globe E-8 11-26022 MSIV Leakage C CS CIV Yes RR-V-4 Control Cont. 05-6 iso.

2E32-F001F 1 A 1-1/2" M0 Globe E-8 11-26022 MSIV leakage C CS CIV Yes RR-V-4 Control Cont. 05-6 Iso.

2E32-F00lK 1 A 1-1/2" M0 Globe E-8 H-26022 MSIV teakage C CS CIV Yes RR-V-4 Control Cont. 05-6 iso s

2E32-F00lP 1 A 1-1/2" M0 Globe E-8 H-26022 MSIV leakage C CS CIV Yes RR.V-4 Control Cont. 05-6 Iso.

l l 2E32-F002B 2 B 1-1/2" M0 Globe E-7 H-26022 MSIV Leakage C CS NA Yes RR-V-4 l

Control CS-6 2E32-F002F 2 8 1-1/2" M0 Globe E-7 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control 05-6 2E32-F002K 2 8 1-1/2" M0 Globe E-7 H-26022 MSIV teakage C CS NA . Yes RR-V-4 I

Control CS-6 2E32-F002P 2 B l-1/2" M0 Globe E-7 H-26022 MSIV Leakage C CS MA Yes RR-V-4 Control 05-6 l

l i

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O Page No. 41 O O 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Roq*el CS Just.

l l 2E32-F003B 2 B l-1/2" M0 Globe E-5 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control 05-6 Depress.

2E32-F003F 2 B 1-1/2" M0 Globe E-5 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control CS-6 Depress.

2E32-F003K 2 B l-1/2" M0 Globe E-5 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control CS-6 Depress.

2E32-F003P 2 B l-1/2" M0 Globe E-5 H-26022 MSIV Leakage C CS i - NA Yes RR-V-4 Control CS-6 Depress.

2E32-F006 2 8 1-1/2" M0 Globe C-Il H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control 05-6 2E32-F0G7 2 B l-1/2" M0 Globe D-Il H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control 05-6 2E32-F008 2 8 1-1/2" M0 Globe C-10 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control t.

CS-6 2E32-F009 2 8 1-1/2" M0 Globe D-10 H-26022 MSIV Leakage C CS NA Yes RR-V-4 Control 05-6 i

l

Page No. 42 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise leakana Pan'<f CS Just.

Class Cat. Descriptior. Coord. P&lD No.

• • System - 2E41 C Qtr NA Yes NA 2 B 10" M0 Gate E-10 H-26020 HPCI Steam 2E41-F001 Supply Shutoff-O CS CIV Yes RR-V-2 A 10" M0 Gate C-3 H-26020 IIPCI Steam RR-V-4 2E41-F002 1 Supply Inbrd. 05-7 Iso. RR-V-37 CIV Yes Rr..y_37 A 10" M0 Gate C-4 11-26020 HPCI Steam 0 Qir 2E41-F003 1 Supply Outbrd.

Iso.

Yes AA 16" M0 Gate D-7 H-26020 HPCI Pump Suc. O Qtr NA 2E41-F004 2 8 from Cond.

Stor.

Qtr PIV ho RR-V-37 E-5 H-26020 HPCI Pump C 2E41-F005 2 AC 14" Check Note 25 Disch PIV Yes RR-V-37 14" M0 Gate E-4 H-26020 HPCI Pump C Qtr 2E41-F006 2 A Inbrd. Disch.

Iso.

Yes NA B 14" M0 Gate E-5 H-26020 HPCI Pt g 0 Qtr NA 2E41-F007 2 Outbrd. Disch.

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Page No. 43 Cd/13/90

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Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Req'd CS Just.

2E41-F008 2 f 10" M0 Globe D-6 11-26020 ifPCI Pump Test C Qtr PIV Yes RR-V-37 Bypass 2E41-F0ll 2 B 10" M0 Gate C-6 11-26020 H/CI Pump C Qtr NA Yes NA Fiedun. Shutoff to Cont. Sig.

2E41-F012 2 B 4" M0 Globe F-6 H-26020 llPCI Pump Min. C Qtr NA Yes Note 9 Flow inbrd.

Iso.

2E41-F019 2 C 16" Check D-7 11-26020 HPCI Pump Suc. C Qtr NA No Note 2 Cond. Stg. ,. -

2E41-F020 2 C 1 1/2" Relief B-6 11-26021 IIPCI Pump C IWV-3512 NA No NA Suction Relief 2E41-F021 2 C 12" Stop Check G-3 H-26020 !1PCI Turb. Exh. C Note 25 NA No RR-V-30A Inbrd. Iso. Notes 9.6 2E41-F022 2 C 2" Stop Check -G-3 H-26020 HPCI Turb. Exh. C Disassemb NA No RR-V-30A Drn. Torus Iso. Notes 9,10,24

, 2E41-F024A 1 AC 1" Excess Flow Ck C-4 H-26020 instrument 0 R0 LTV ' No RR-V-4 Excess Flow RR-V-15 Check Valve

O O O Page No. 44 08/13/90 Piar.t flatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Time Relief Valve Code Function Pos Exercise Leakage Ren'<! C5 Just.

No. Class Cat. Description Coord. P&lD 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck 0-4 11-26020 Instrument RR-V-15 2E41-F0248 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck C-4 31-26020 !nstrument RR-V-15 >

2E41-F024C 1 Excess Flow Check Valve 0 R0 LTV No RR-V-4 AC 1" Excess Flow Ck E-4 11-26020 Instrument RR-V-15 2E41-F0240 1 Excess Flow Check Valve Disassemh NA No RR-V-30A 2 C 2" Check G-4 11-26020 HPCI Turb. Exh. C Notes 2E41-F040 Drn. Torus Iso. 9.10.25 Yes NA B 16" M0 Gate D-7 fi-26020 HPCI Pump Suc. C Qtr NA 2E41-F041 2 Shutoff li-26020 HPCI Pump Suc. C Qtr NA Yes Note 9 [

2 B 16" M0 Gate H-4 2E41-F042 Torus Outbrd.

Iso.

H-26020 HPCI Pump C Disassemb NA , No RR-V-12 2E41-F045 2 C 16" Check 11- 5 t Note 10 Suction H-26020 HPCI P g Min C Disassemb NA Hn RR-V-30A 2 C 4" Check F-6 Notes 9,1 2E41-F046 Flow Outbrd.

Iso.

d -

Page No. 45 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Time Relief  !

Valve Code Function Pos Exercise leakage Reg *d C5 Just.

No. Class Cat. Description Coord. P&ID 11-26021 Lube Oil C Disassemb NA fio Note 10 2f41-F048 2 C 2" Check G-8 Cooling Wtr Return Check Qtr ffA fio RR-V-30A 2 C 20" Check G-4 11-26020 IIPCI Turb. Exh. C Notes 9.25 2E41-F049 Dutbrd. Iso.

11-26020 HPCI Pump Suc. O Qtr NA Yes Note 9 2E41-F051 2 8 16" A0 Bfly 11 - 4 Torus Inbrd.

Iso.

11-26021 Lube Oil C Disassemb NA No Note 10 2 C 2" Check G-9 2E41-F057 Cooling Wtr

• Return Check v es NA H-26021 HPCI Turb. Lube C Qtr .NA 2E41-F059 2 B 2" M0 Globe F-7 Gil Cooling RO NA No RR-V-4 2 C 1" Check F-2 H-26020 Vacuum Relief C RR-V-23 2E41-F102 ]

RO NA No RR-V-4 2 C I" Check F-2 H-26020 Vacuum Relief C RR-V-23 2E41-FIO3 O Qtr CIV Yes NA 2 A 2" M0 Gate F-2 H-26020 HPCI Vac.

2E41-F104 Relief Outbrd.

Torus Iso.

• ',. ~ *- f . . , .

O Page No. 46 O O 08/13/90

~

Plant Hatch Unit 2 Valve. Test Program -

Tahic 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakago Req'd :CS Just.'

2E41-Flll 2 A 2" M0 Gate G-1 11-26020 HPCI Vac. O Qtr CIV Yes NA Relief Inbrd.

Torus Iso.

2E41-F121 2 A 3/8" Solenoid 11 - 9 11-26384 Pass Sample C Qtr CIV Yes NA Return 2E41-F122 2 A 3/8" Solenoid H-9 11-26384 Pass Sample C Qtr CIV Yes MA Return t

t 1

.- .c . ,

J  %/-

Page No. 47 08/13/90 Plant flatch Unit 2 valve Test Program Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&l0 function Pos Exercise Eeaka9e Reg'd C5 Just.

• • System - 2E51 2E51-F001 2 C 10" Stop Check G-5 11-26023 RCIC Turb. Exh. C Note 25 NA No RR-V-30A Inbrd. Iso. Notts 9,2(

2E51-F002 2 C 2" Stop Check F-5 11-26023 RCIC Turb. Exh. C Note 25 NA No RR-V-30A Drn. Torus 150. Notes 9,2<

2E51-F003 2 B 6" A0 Bfly 11 - 7 11-26023 RCIC Pump 0 Qtr NA Yes Note 9 Suction Toros Inbrd. Iw.

2E51-F007 I A 4" M0 Gate C-5 11-26023 RCIC Steam 0 CS CIV Yes RR-V ,

Supply Inbrd. ... RR-V-c Iso. 05-7 2E51-F008 1 A 4" M0 Gate C-6 H-26023 RCIC Steam 0 Qtr CIV Yes NA Supply Outbrd.

Iso.

2E51-F010 2 8 6" M0 Gate C-8 H-26023 RCIC Pump Suc. O Qtr NA Yes Note 17 from Cond.

Stor.

2E51-FOII 2 C 6" Check C-8 11-26023 RCIC Pump Suc. C Qtr NA, , No Notes 2,1)

-~

Cond. Stor.

2E51-F012 2 8 4" M0 Gate D-6 H-26023 RCIC Puep 0 Qtr NA Yes Note 17 Outbrd. Disch.

6 O O Page No. 48 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes

-Norm Time Relief Valve Code Function Pos Exercise leakage Req'd CS Just.

No. Class Cat. Description Coord. P&ID 11-26023 RCIC Pump C Qtr PIV fes NA 2 A 4" M0 Gate D-6 2E51 F013 Inbrd. Cisch.

Iso.

11-26023 RCIC Pump C Qtr PIV No Notes 17<

2 AC 4" Check D-6 25 2E51-F014 Disch.

11-26024 RCIC Pump '. IWV-3512 NA No Note 17 2 C 1" Relief B-6 ZE51-FC17 Suction Relief 11-26023 RCIC Pump Min. C Qtr NA Yes Note 9 2 B 2" M0 Globe E-7 2E51-F019 Flow Inbrd.

Iso. ,.-

11-26023 RCIC Pug Min. C Disasses5 NA 'to RR-V-30A 2 C 2" Check E-7 Nntes 9,{

2E51-F021 Flow Outbrd.

Iso.

11-26023 RCIC Pump Test C Qtr PIV Yes Nott- 17 '

2 A 4" M0 Globe C-6 b 2E51-F022 Bypass Note 25 NA No RR-V-30A 2 0 2" Check F-7 H-26023 RCIC Turb. Exh. C Note 9 2E51-F028 Grn. Torus Iso.

H-260?3 RCIC Ptemp Suc. C. Otr NA Yes Note 17 2 B 6" M0 Gate C-8 2E51-F029 Shutoft

i-L- v d.. v Page No. 49 08/13/90 l

Plant flatch Unit 2 Valve Test Program Tabic 2 Stroke Notes Valve Code Norm lime Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Raq'd' CS Just.

I 2E51-F030 2 C 6" Check li-8 H-26023 RCIC Pump C Disassemb. NA No Notes.17 Suction 18 2E51-F031 2 B 6" M0 Gate 11- 7 'll-26023 RCIC Pump C Qtr NA Yes Note 9

. Suction Torus Outbrd. Iso.

l l 2E51 .040 2 C 10" Check F-5 11-26023 RCIC Turb. Exh. C Note 25 ' NA No RR-V-30A Outbrd. Iso. Note.9 l 2E51-F044A 1 AC 1" Excess Flow Ck A-5 11-26023 Instroneent 0 R0 LTV No RR-V-4 l Excess Flow RR-V-15 l Check Valve 6- -

2E51-F044B 1 AC 1" Excess Flow Ck B-5 H-26023 Instrument 0 R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2E51-F044C 1 AC 1" Excess Flow Ck B-5 H-26023 Instrument O. R0 LTV No RR-V-4 Excess Flow RR-V-15 Check Valve 2E51-F044D 1 AC 1" Excess Flow Ck B-5 H-26023 Instrumer.t 0 R0 LTV. No RR-V-4 Excess Flow RR-V-15 I '

Check Valve 2E51-F045 2 B 4" M0 Globe C-10 H-26024 RCIC Steam C Qtr MA Yes . Note 17 Supply Shutoff

~

v7 l .

OPage No. 50 O O -

08/I3/90 _

Plant Hatch Unit 2 Valve Test Program

~

l. Table 2 Stroke Notes-Valve Code Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

2E51-F046 2 B 2" M0 Globe 0-6 H-26024 RCIC Turb. lube C Qtr NA Yes Note-17 Oil Cooling 2E51-F047 2 0 2" Check G-7 11-26024 Lube Oil C Disassemb NA .No . Notes 17, Cooling Wtr 18 Return Check i

2E51-F102 2 C 1 1/2" Check F-5 H-26023 Vacuum Relief C R0 NA .. No Notes 17, 19-l 2E51-F103 2 C 1 1/2" Check F-5 H-26023 Vacuum' Relief C R0 NA No Notes.'17c 19

! 2E51-F104 2 A 1 1/2" M0 Gate F-5 11-26023 RCIC Vac. O Qtr CIV Yes. NA.

Relief Outbrd.

. Torus Iso.

2E51-F105 2 A 1 1/2" M0 Gate F-4 H-26023 RCIC Vac. O Qtr CIV Yes NA Relief Inbrd.

Torus Iso.

2E51-Fil9 2 B 1" M0 Globe D-10 H-26024 RCIC Steam C Qtr NA 'Yes Note 17 Supply Shutoff

?

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Page No. 51 '~

i 08/13/90

^

Plant Hatch Unit 2 Valve Test Program '

Table 2 l Stroke Notes Valve Code .

Norm Time Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise Leakage Reg'd CS Just.

• • -System - 2Gil 2Gil-F003 2 A 4" A0 Gate B-3 11-26026 DW Flr. Drns. O Qtr CIV Yes- NA Cont.-Iso.

2GIl-F004 2 A 4" A0 Gate B-4 11-26026 DW Flr. Drns. 0 Qtr CIV Yes NA Cont. Iso.

l l

2Gil-F019 2 A 4" A0 Gate E-4 11 26026 DW Equip. Drns. O Qtr CIV Yes NA-Cont. Iso.

2Gil-F020 2 A 4" A0 Gate E-4 H-26026 DW Equip. Drns. 0 Qtr CIV Yes , NA ..

Cont. Iso.

2Gil-F852 2 .A 1-1/2" Man Gate E-Il H-26026 Passive Cont. LC None CIV No- NA Iso.

2Gil-F853 2 A 1-1/2" Man Gate D-Il H-26026 Passive Cont. LC None CIV No NA Iso.

p l

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~( jL l 'Page No. 52 08/13/90 l

Plant flatch Unit 2 Valve Test Program lable 2 j' ' Stroke Notes Valve Code Norm Time Relief I

No. Class Cat. Description Coord. P&ID Function Pos ' Exercise Leakage. Req'd CS Just.

• • System - 2G31 2G31-F001 1 A 6" M0 Gate C-2 H-26036 RWCU Pump Suc. O CS CIV Yes RR-V-4 Inbrd. Iso. RR-V-37' C5 2G31-F004 1 f- 6" M0 Gate C-3 11-26036 RWCU Pump Suc. 0- CS CIV Yes RR-V-4 Outbrd. Iso. RR-V-37' C5-12 l

l 1

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. ,~., . , - .

' 'w7 .

Page No. 53:

'08/13/90

' Plant' Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm . lime Relief No. Class Cat. Description Coord. P&l0 Function Pos . Exercise leakage Ren'd CS Just.-

• • System - 2G51 2G51-F0ll 2 B 3".A0 Control C-5 11-26042 Torus Drain 0 Qtr NA Yes .. Note 9 :

Purif. Cont.

j Iso.

2G51-F012 2 B 3" A0 Control C-5 11-26042 Torus Drain 0 Qtr ~NA Yes- -Note 9 Purif. Cont.

Iso.

2G51-F013 2 B 3" A0 Control C-2 11-26042 E21-F0028 0 Qtr NA Yes NA Bypass Control 2G51-F017 2 B 3" A0 Control C-2 11-26042 E21-F002B 0 Qtr i NA Yes NA l Bypass Control i*

?

L Page No'. 54 l 08/13/90 Plant Hatch Unit 2 Vaive Test Program Table 2- .

= Stroke Notesi Valve Code Norm Time Relief-No. Class Cat. Description Coord. P&lD function Pos Exercise Leakana Ron'd CS Just; l.

• • System - 2P21 2P21-F032 2 A 2" Manual Gate F-2 H-2604'r Passive Cont. LC None CIV No NA Iso.

2P21-F034 2 A 2" Manual Gate E2 11-26047 Passive Cont. LC None ClY No NA Iso.

s

. _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ - - -_ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ , - - -

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

Page No. 55 08/13/90 Plant liatch Unit 2 Valve Test Program Table 2 Stroke Notes Code Norm Time Relief Valve Pos Exercise. Leakage Req'd CS Just.

No. Class Cat. Description Coord. P&ID Function

• • System - 2P33 11-26048112 & 02 Analy. O Qtr CIV Yes NA 2P33-F002 2 A 1" A0 Globe B-4 Cont. Iso.

2P33-F003 2 A 1" A0 Globe C-4 11-26048 H2 & 02 Analy. C dtr CIV Yes -NA Cont. Iso.

2 A I" A0 Globe D-4 11-26048 H2 & 02 Analy. O Qtr CIV Yes NA 2P33-F004 Cont. Iso.

2 A 1" A0 Globe E-4 11-26048 H2 & 02 Analy. O Qtr CIV Yes NA 2P33-F005 Cont. Iso.

2P33-F006 2 A 1" A0 Globe. F-4 11-26048 H2 & 02 Analy. C Qtr CIV Yes NA Cont. Iso.

2P33-F007 2 A 1" A0 Globe H-4 H-26048 H2 & 02 Analy. O Qtr CIV Yes NA Cont. Iso.

2P33-F010 2 A 1" A0 Globe B-5 H-26048 H2 & 02 Analy. O Qtr CIV Yes NA Cont. Iso.

2P33-F0ll 2 A 1" A0 Globe C-5 H-26048 H2 & 02 Analy. C Qtr CIV Yes NA Cont. Iso. 3 11-26048 H2 & 02 Analy. O Qtr CIV Yes NA 2P33-F012 2 A 1" A0 Globe D-5 Cont. Iso.

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jm-(_/'

Page No. 56 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes.

Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise Leakage Reg'd CS Just.

2P33-F013 2 A 1" A0 Globe E-5 11-26048112 5 02 Analy. O Qtr CIV. Yes- NA -

Cont. Iso.

2P33-F014 2 A 1 A0 Globe F-5 H-26048112 & 02 Analy. C Qtr CIV. Yes NA Cont. Iso.

2P33-F015 2 A 1" A0 Globe 11- 5 11-26048112 & 02 Analy. O Qtr CIV Yes NA Cont. Iso.

v.* ,

. . . _ - . - . _-1, . . - - .- ._ _ ~ . . , . . . _ . . ..;

O O O Page No. 57 08/13/90

~

Plant Hatch Unit 2 Valve Test Program Table 2 Stroksi Notes Time Relief; Norm Valve Code .

Pos Exercise Leakage Req'd C5 Just.

Class Cat. Description Coord. P&l0 Function.

No.

• • System - 2P41 H-26051 HPCI Pump Room .C Disassemb NA No RR-V-19 2P41-F024A 3 C 2" Check D-4 Note 10.

Cooler 11-26051 IIPCI Pump Room C Disassemb NA No. RR-V-19 2P41-F0248 3 C 2" Check D-5 Note 10 Cooler Disassemb NA No Notes 17, 2" Check C-5 11-26050 RCIC Pump Room C 2P41-F028A 3 C -18' Cooler Disch.

Chk.

No Notes 17, 2" Check C-5 H-26050 RCIC Pump Room C Disassemb NA 2P41-F0288 3 0 18 Cooler Disch. .-

Chk.

11-26051 HPCI Pump Room C Qtr .NA Yes RR-V-20 3 8 2" A0 Globe C-4 2P41-F035A Cooler H-26051 HPCI Pump Room C Qtr NA Yes .RR-V-20'

.2P41-F035B 3 8 2" A0 Globe C-5 Cooler H-26051 RHR & CS lomp- C Qtr NA Yes -RR-V-20' 2P41-F036A 3 B 3" A0 Globe C-5' Room Cooler i'

H-26051 RHR & CS Pump C Qtr NA Yes RR-V-20 3 8 3" A0 Globe C-6 2P41-F036B Room Cooler

_ _ _ _ _ M

xJ  %) . V Page No. 58 08/13/90 Plant Hatch Unit 2 Valve. Test Program Table 2 Stroke Notes Valve Code Norm . Time Relief No. Class Cat. Description Coord. P&ID Function Pos Exercise ~ leakage Reg'd CS Just.

2P41-F037A 3 B l-1/2" A0 Globe D-7 H-26050 RHR Pump Cooler C' Qtr NA Yes RR-V-20 2P41-F037B 3 B l-1/2" A0 Globe C-9 H-26051 RHR Pump Cooler C Qtr NA Yes - RR-V-20' 2P41-F037C 3 8 1-1/2" A0 Globe D-8 H-26050 RHR Pump Cooler C Qtr It.\ Yes RR-V-20 2P41-F0370 3 8 1-1/2" A0 Globe C-8' H-26051 RHR Pump Cooler C Qtr NA Yes ' RR-V-20 2P41-F039A 3 B 3" A0 Globe D-9 H-26050 RHR Pump Room C Qtr NA Yes RR-V-20 Cooler 2P41-F0398 3 8 3" A0 Globe D-9 H-26050 RHR Pump' Room C Qtr NA Yes- RR-V-20 Cooler ,.-

2P41-F040A 3 B 2" A0 Globe D-5 H-26050 RCIC Pump Rm C .Qtr NA Yes Notes 12.

Cooler Control 17 2P41-F0408 3 8 2" A0 Globe D-5 H-26050 RCIC Pump Rm C Qtr NA Yes Notes 12, Cooler Control 17 2P41-F064 3 C 10" Check E-10 H-26050 Division 1 S.W. O Qtr NA No Note 16 Supply 2P41-F065 3 C 10" Check B-10 H-26051 Division 2 S.W. O Disassemb NA . , No Note 10 Supply 1 2P41-F098 3 C 4" Check B-3 H-26051 Control Room 0 Disassemb NA No Note 10 HVAC

_-t.__..____._ _ _ _ . . _ _ _ _

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Page No. 59  :

08/13/90 Plant Hatch Unit 2 Valve Test Program '

Table 2 Stroke Notes Valve Code Norm . Time- Relief:

No. Class Cat. Description Coord. P&l0 Function Pos Exercise Leakage Fea'd 'CS Just.

2P41-F105 3 C 4" Check F-4 11-26050 Control Room 0 Disassemb NA No Note 10.

11VAC '

2P41-Fil5A 3 B 2" M0 Gate F-6 11-26050 Ess. LPCI inv. C Qtr NA Yes NA' Inlet Iso.

2P41-Fil5B 3 8 2" M0 Gate A-3 11-26051 Ess. LPCI inv. C Qtr NA _Yes NA Inlet Iso.

2P41-F123A 3 C '2" Check F-7  !!-26050 Ess. LPCI Inv. C Disassemb NA No Note 10' Outlet Chk.

2P41-F1238 3 C 2" Check C-1 11-26051 Ess. LPCI Inv. C Disassemb NA No Note 10 Outlet r.hk.

2P41-F306A 3 C 1-1/2" Check B-7 11-21033 Service Wtr. O Qtr NA 'No Note 5 Motor Cooling 2P41-F306B 3 0 1-1/2" Check G-7 H-21033 Service Wtr. O Qtr NA No Note 5 Motor Cooling 2P41-F311A 3 C 18" Check B-3 H-21033 S.W. Pump 0/C Qtr NA No~ RR-V-25 Discharge 2P41-F311B 3 C 18" Check C-3 H-21033-S.W. Pump 0/C Qtr MA l' No RR-V-25 Discharge

- , - _ _ _ _ - = . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ - _ _ _. _ _ _ _ _

f~').

- -) v Page No. 60 08/13/90 Plant Hatch Unit 2 Valve Test Program

~

Table 2 Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. P&ID Function Pos Excrcise leakage Reg'd CS Justa 2P41-F311C 3 C 18" Check E-3 11-21033 S.W. Pump 0/C Qtr NA No RR-V-25i Discharge 2P41-F3110 3 C 18" Check D-3 11-21033 5.W. Pump 0/C Qtr NA No RR-V-25 Discharge 2P41-F316A 3 8 30" M0 Bfly A-9 H-21033 S.W. to Turbine O CS NA Yes RR-V-4 Bldg. Shutoff .05-4 2P41-F316B 3 B 30" M0 Bfly F-9 H-21033 S.W. to Turbine O CS NA Yes RR-V-4 Bldg. Shutoff CS-4 2P41-F316C 3 8 30" M0 Bfly A-10 '"-21033 S.W. to Turbine O CS s NA- Yes RR-V-4 Bldg. Shutoff CS-4 2P41-F3160 3 B 30" M0 Bfly F-10 51-21033 S.W. to Turbine O CS NA Yes RR-V-4 Bldg. Shutoff CS 2P41-F321 3 C 6" Check 1-2 H-21033 Stby. Diesel SW C Qtr NA No Note 2 Pump Discharge 2P41-F339A 3 8 6" A0 Bfly H-9 H-21033 Diesel Gen. C Qtr NA' Yes RR-V-20!

Cooling

-2P41-F3398 3 8 6" ' A0 Bfly H-7 H-21033 Diesel Gen. C Qtr NR Yes RR-V-20' Cooling

}

Page No. 61:

08/13/90 Pl>r.t flatch Unit 2 Valve Test Program Table 2 Stroke-Notes Valve Code Norm Time Relief No. Class Cat. Description. Coord.~PalD Function Pos Exercise leakage Req'd CS Just.

• • System - 2P42 2P42-F05I 2 A 6" M0. Gate B-5 11-26055 RBCCW to Recir. O CS CIV. .Yes 'RR-V-4 Cont. Iso. CS-5 RR-V-3 7. ,

2P42-F052 2 A 6" M0 Gate C-5 11-26055 RBCCW to Retir. 0- CS CIV Yes' RR-V-4 Cont. Iso. 05-5 RR.V-37 6-k

p- .

_ ;,. 3

( '- (j-Page No. 62 08/13/90 Plant Itatch Unit 2 Valve Test Program -

Table 2 Stroke Notes ~

Valve Code Norm Time . Relief-No. Class Cat. Description Coord. P810 Function Pos Exercise leakage Reg'd CS Just.

• • System - 2P51 2P51-F513 2 A 2" Man. Globe F-3 11-26058 Passive Cont. LC None ~CIV No. NA Iso.

2P51-F651 2 A 2" flan. Globe F 11-26058 Passive Cont. LC None CIV No - NA Iso.

l i*

l T

_ _-' ~ - - -_ '____.-______________________._____-__L-__:_ . _ . _ ____ t. ' _ _ ._ - -_.. - _ .- -.- -x -~me .new-" ---

., p.

,(~x.

_1 Page No. 63 08/13/90 Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Timo Relief.

No. Class Cat. Description Coord. P&lD Function- Pos Exercise Leakage Reg'd .'CS Just.

• • System - 2P64 .

2P64-F045 2 A 6" M0 Globe H-2 H-26081 Chilled Water 0 CS CIV 'Yes RR-V-4 Cont. Iso. -CS-3 RR-V-37 2P64-F047 2 A 6" M0 Globe G-Il H-26081 Chilled Water 0 CS CIV Yes RR-V-4 Cont. Iso. 3 .

RR-V-37 e

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o ..

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~~

s ( V: e r Page No. 64 08/13/90 I ~

I Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notesi l Valve Code . . Norm Time Relief No. Class Cat. Description Coord.'P&lD Function Pos Exercise leakage Rea'd CS Just..

l

• • System - 2P70 2P70-F002 2 A 1" A0 Globe F-8 11-26066 DW Pneumatic 0 Qtr CIV .Yes NA l Cont. Iso.

i l 2P70-F003 2 A 1" A0 Globe F-8 11-26066 DW Pneumatic 0 Qtr CIV Yes NA Cont. Iso.

2P70-F004 2 A 2" Solenoid B-9 11-26066 DW Pneumat'ic 0 Qtr CIV Yes 'NA-I Cont. Iso.

l 2P70-F005 2 A 2" Solenoid B-9 11-26066 DW Pneumatic 0 Qtr- CIV Yes NA I Cont. Iso.

s 2P70-F066 2 A 2" Solenoid 0-9 11-26066 DW Pneumatic 0 Qtr- CIV Yes NA

Cont. Iso.

2P70-F067 2 A 2" Solenoid D-9 ll-26066 DW Pneumatic 0 Qtr CIV' Yes NA Cont. Iso.

i

. ., _ . - , . _ _ _ -u. _ ... _ _ 1,._ _ ._

l p

Q v l.

l Page No. 65

l. 08/13/90

(

! Plant flatch Unit 2 Valve Test Program -

l Table 2 l

i.

l Stroke Notes .

Valve Code Norm Time Relief l No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Req'd CS Just.

l

• • System - 2R43 2R43-F012A -

C 2" Check 11 - 1 0 11-21074 0.G. Fuel Oil C Otr NA No Notes.7,{

Pump Discharge Check 2R43-F0128 -

C 2" Check 11- 9 11-21074 D.G. Fuel Oil C Otr NA No Notes 7,(

Pump Discharge Check 2R43-F012C -

0 2" Check 11- 8 11-21074 D.G. Fuel Oil C Qtr NA No Notes 7,{

Day Tank Inlet Check 2R43-F012D -

C 2" Check 11 - 7 11-21074 D.G. Fuel Oil C Otr NA No Notes 7,1 l

Day Tank Inlet Check 2R43-F013A -

C 2" Check F-10 H-21074 D.G. Fuel Oil C Qtr NA No Notes 7,(

Pump Discharge Check 2R43-F0138 -

C 2" Check F-10 ll-21074 D.G. Fuel Oil C Qtr NA No Notes ' 7,{

Pump Discharge Check ;3 2R43-F013C -

C 2" Check F-8 H-21074 D.G. Fuel Oil C Qtr- NA 'No Notes 7,I Day Tank Inlet Check

, i s r -

Page No. '66 08/13/90 Plant flatch Unit 2 Vaive Test Program Table 2 Stroke Notes Valve Code Norm Time Relief ~

No. Class Cat. Description Coord. P&lD Function .Pos Exercise Leakage Rea'd CS Just.

2R43-F013D -

C 2" Check F-8 11-21074 D.G. Fuel Oil C Qtr NA No- Notes 7,{

Day Tank Inlet Check 2R43-F029A -

C 3/4" Check C-10 11-21074 Air Receiver C Qtr NA No Notes'14e Inlet Check 17 Valve 2R43-F029C -

C 3/4" Check C-10 11-21074 Air Receiver C Qtr NA No Notes 14<

Inlet Check ~ 17 Valve 2R43-F032A -

C 1/2" Relief B-9 H-21074 Air Receiver C IWV-351E. NA No' Note'17 Relief Valve 2R43-F032C -

C 1/2" Re1ief B-9 H-21074 Air Receiver C IWV-3512 NA No Note 17 Relief Valve 2R43-F033A -

C 1/ 2" Relief B-ll H-21074 Air Receiver C IWV-3512 NA No Note 17 Relief Valve 2R43-F033C -

C I/2" Relief B-Il H-21074 Air Receiver C IWV-3512 NA No Note 17

- Relief Valve 2R43-F042A -

B 1 1/2" 3-Way Sol. B-7 H-21074 D.G. Air Start C Qtr NA Yes Notes 17e Valve "" '

-- '---=x.--L.

x  :~12 -

,\

C- \

Page No. 67 f' & ,

08/13/90

~

Plant Hatch Unit 2 Valve Test Program

~

Table 2 Stroke Notes Valve Code Norm . Time- Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Rea'd-'CS-Just.

2R43-F042C -

B 1 1/2" 3-Way Sol. B-7 11-21074 0.G. Air Start C Qtr .NA Yes Notes 17,;

Valve 21 2R43-F044A -

B 1 1/2" 3-Way Sol. A-7 li-21074 D.G. Air Start C Qtr NA Yes Notes 17,.

Valve 21 2R43-F044C -

B 1 1/2" 3-Way Sol. A-7 11-21074 0.G. Air Start C Qtr NA' Yes Notes 17,;

Valve 21 2R43-F095A -

C 3/4" Check C-10 11-21074 Air Reciever C Qtr NA No Notes 14, Inlet Check 17:

Valve 2R43-F095C -

C 3/4" Check C-10 H-21074 Air Reciever C Qtr NA 'No - Notes 14,;

Inlet Check 17-Valve C e.=r-s e p =g, ,iau.,*--anm+=_ v__' s __ nr-__; _ _ _

^

y__mgi ___ _ _ _ _ _ , ___ _ ,r , ...,. , _ , , _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ,

,__________f_ _ _ _ _ _ _ _ _ _ _

2. .

~

): -

Page No. 68 08/13/90

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Plant Hatch Unit 2 Valve Test Program '-

Table.2 Stroke Notes Valve Code . .

Norm .

Time ~ Relief No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reo'd: CS Just.

• • System - 2T23 2T23-F004 2 A 1" Man. Globe D-3 H-26057 Passive Cont. . C None CIV No NA-Iso.

2T23-F005 2 A l' Man. Globe D-3 H-26057 Passive Cont. C None CIV No NA Iso.

e

Page No. 69 08/13/90 Plant flatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Time .Reltef Valve Code Function Pos ' Exercise Leakage Rea'd CS Just.

No. Class Cat. Description Coord. P&ID

• • System - 2T46 Qtr NA Yes Note 17' 3 B 18" A0 Bfly C-2 H-26078 Filter Bed C 2T46-F001A Inlet from Reactor Bldg.

C Qtr NA Yes Note 17 3 B 18" A0 Bfly G-2 11-26078 Filter Bed 2T46-F0018 Inlet from Reactor Bldg.

Qtr NA Yes Note 17 3 8 18" A0 Bfly C-5 H-26078 SGTS Filter C 2T46-F002A Outlet from Reactor Bldg.

C. Qtr NA Yes Note 17 3 8 18" A0 Bfly G-S H-26078 SGTS Filter 2T46-F002B Outlet from Reactor Bldg.

Qtr NA Yes Note 17 3 8 18" A0 Bfly. C-2 H-26078 SGTS Filter Bed C 2T46-F003A Inlet from Refuel Floor Qtr NA Yes' Note.17 3 8 18" A0 Bfly G-2 H-26078 SGTS Filter Bed C 2T46-F0038 Inlet from Refuel Floor ,

_- N

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d -g Page No. 70 08/13/90 _

1

~

Plant flatch Unit 2 Valve Test Program

^

Table 2 Stroke Notes Valve Code Norm Time Relief' No. Class Cat. Description Coord. P&ID Function Pos Exercise leakage Reg'd CS Juste

• • System - 2T48 2T48-F035 2 C 3" Relief Valve B-5 H-26083 N2 System C IWV-3512 NA No Note 17 Relief l

t

2T48-F103 2 A 6" A0 Bfly 0-10 11-26083 DW & Torus C Qtr CIV Yes RR-V-37 l

Supply Iso.

2T48-F104 2 A 2" A0 Globe G-4 11-26083 DW & Torus C Qtr- CIV Yes NA Outbrd. Iso.

l l 2Td3-Fil3 2 A 2" A0 Globe G 11-26083 DW Inerting C Qtr CIV Yes NA Outbrd. Iso.

2T48-F114 2 A 2" A0 Globe H-9 H-26083 DW Inerting C Qtr CIV Yes NA l Inbrd. Iso.

! 2T48-Fil5 2 A 2" A0 Globe G-10 H-26083 DW Inerting C Qtr CIV Yes NA Outbrd. Iso.

I 2T48-Fil6 2 A 2" A0 Globe H-10 H-26083 DW Inerting C Qtr . CIV Yes NA-Outbrd. Iso.

2T48-Fil8A 2 A 1" A0 Globe J-4 H-26083 DW Makeup C Qtr CIV .Yes NA Inbrd. Iso. j 2T48-Fil88 2 A 1" A0 Globe J-5 11-26083 Torus Makeup C Qtr CIV Yes NA Inbrd. Iso.

._.r. __. m __.-- m ew-

O Page No. 71' O O

-08/13/90 Pl' ant Hatch Unit 2 Valve Test Program Table 2

.. Stroke Notes Valve Code Norm .

Time Rellef No. Class Cat. Description Coord. P&ID- Function Pos Exercise leakage Reg'd CS Just.

2T48-F209 2 A 4" A0 Gate C-9 H-26079 Inboard C Qtr CIV Yes NA Isolation 2T48-F210 2 A 4" A0 Gate C-9 H-26079 Outboard C Qtr CIV Yes NA Isolation 2T48-F211 2 A 4" A0 Gate E-8 H-26079 Inboard C Qtr CIV. Yes NA Isolation 2T48-F212 2 A 4" A0 Gate E-8 H-26079 Outboard C' Qtr CIV Yes NA Isolation 2T48-F307 2 A 18" A0 Bfly C-9 H-26084 DW Purge Inlet C- Qtr~ i. CIV Yes -RR-V-37 Inbrd. Iso. ,

2T48-F308 2 A 18" !.. Bfly C-10 H-26084 DW Purge In12t C Qtr CIV. Yes 'RR-V Inbrd. Iso.

2T48-F309 2 A 18" A0 Bfly E-10 H-26084 Torus Purge .C Qtr CIV Yes RR-V-37:

' Inlet Inbrd.

Iso.

2T48-F310 2 A 20" A0 Bfly F-10 H-26084 Torus Purge C Qtr .CIV- Yes RR-V-37 Vac. 8rker. I ,

t Iso.

2T48-F311 2 A 20" A0 Bfly F-9 H-26084 Torus Purge C Qtr CIV Yes RR-V-37 Vac. Brker. ,

Iso.-

7 Page No. 72 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code Norm .

Time Relief-No. Class Cat. Description Coord. P&lD Function Pos Cxercise Leakage Reg'd CS Justm 2T48-F318 2 A 18" A0 Bfly G-4 H-26084 Torus Purge C Qtr' CIV Yes RR-V Outlet.Inbrd.

Iso.

2T48-F319 2 A 18" A0 Bfly C-4 H-26084 DW Purge Outlet C Qtr CIV Yes RR-V-37 Inbrd. Iso.

2T48-F320 2 A 18" A0 Bfly C-3 H-26084 DW Purge Outlet C Qtr CIV Yes RR-V-37 Outbrd. Iso.

2T48-F321 2 A 2" A0 Globe G-7 H-26083 DW Inerting C Qtr CIV Yes NA Outbrd. Iso.

2T48-F322 2 A 2" A0 Globe H-7 H-26083 DW Inerting C Qtr CIV Yes NA Inbrd. Iso.

2T48-F323A 2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus C Qtr NA ~No Notes 19 Vac. Breaker- 17 2T48-F323B 2 C 18" A0' Test. Chk G-8 H-26084 DW to Torus C Qtr NA No Notesth

.Vac. Breaker 17 2T48-F323C 2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus C Qtr. NA No Notes l@

Vac. Breaker . 17 2T48-F3230 2 F 18" A0 Test. Chk G-8 H-26084 DW to' Torus C Qtr NA' No Notes 19 Vac. Breaker 17

O O O Pa 73 08/ge No.

13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Norm Time'. Relief' Valve Code Function Pos Exercise leakage Reg'd' CS Just.

Class Cat.' Description Coord. P&lD No.

No Notes 15; 18" A0 Test. Chk G-8 H-26084 DW to Torus C Qtr NA 2T48-F323E 2 C 17.

Vac. Breaker C Qtr NA No Notes 15 4 2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus 17-2T48-F323F Vac. Breaker H-26084 DW to Torus C Qtr NA No Notes'15'4 2T48-F323G 2 C 18" A0 Test. Chk G-8 Vac. Breaker -17 NA No Notes 15, 18" A0' Test. Chk G-8 H-26084 DW to Torus C Qtr 17 2T48-F323H 2 C Vac. Breaker C Qtr . . NA No Notes 15.

2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus 17 2T48-F323I Vac. Breaker C Qtr NA No Notes 15s 2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus 17 2T48-F323J Vac. Breaker C Qtr NA No Notes 15s 2 C 18" A0 Test. Chk G-8 H-26084 DW to Torus 17 2T48-F323K Vac. Breaker No Notes 15, 18" A0 Test. Chk G-8 H-26084 DW to Torus C Qtr. NA 17 2T48-F323L 2 C Vac. Breaker H-26084 Torus Purge Qtr 'CTV ' Yes RR-V-37 18" A0 Bfly D-10 C.

2T48-F324 2 A Inlet Outbrd.

Iso.

Y% e'"V 4 w (h Page No. 74

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08/13/90 i

Plant Ha'ch t Unit 2 Valve Test Program -

! Table 2 l

i Stroke Notes:-

Valve Code Norm Time. Relief-No. Class Cat. Description Coord. P&lD Function- Pos Exercise leakage Req'd CS Just.

, 2T48-F325 2 A 2".A0 Globe G-8 H-26083 Torus Inerting C- Qtr- CIV 'Yes ' NA l

Outbrd. Iso.

2T48-F326 2 A 18" A0 Bfly G-3 H-26084 Torus Purge C Qtr CIV Yes: RR-Y-37 Outlet Outbrd.

Iso.

2T48-F327 2 A 2" A0 Globe H-8 H-26083 Torus Inerting C Qtr CIV Yes NA ~

Inbrd. Iso.

2T48-F328A 2 AC 20" A0 Test. Chk G-10 H-26084 Reactor Bldg to C Qtr CIV No RR-V-37 Supp. Cham. Note 15 Vac. Brker. ,,-

2T48-F3288 2 AC 20" A0 Test. Chk G-10 H-26084 Reactor B1dg to C Qtr CIV No RR-V-37 Supp. Cham. Note 15 Vac. Brker.

2T48-F332A 2 A 2" A0 Globe E-3 H-26084 Torus Purge C Qtr .CIV. Yes ' NA Outlet Outbed.  ;

Iso. '

l 2T48-F3328 2 A 12" A0 Globe G-3 H-26084 Torus-Purge C Qtr CIV Yes NA Outlet Outbrd. . ,

Iso. t 2T48-F333A 2 A 2" A0 Globe E-4 H-26084 Torus Purge C Qtr. CIVl Yes NA.

Outlet Inbrd.

Iso.

L

_s ._

d Page No. 75 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 l Stroke Notes Valve Code form Time Relief-No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Reg'd CS Just.

2T48-F333B 2 A 2" A0 Globe G-4 H-26084 Torus Purge C Qtr CIV Yes NA Outlet Inbrd.

Iso.

2T48-F334A 2 .A 2" A0 Globe B-3 H-26084 DW Purge Outlet C Qtr CIV Yes NA Outbrd. Iso.

2T48-F3348 2 A 2" A0 Globe C-3 H-26084 DW Purge Outlet C Qtr CIV .Yes Mr. '

Outbrd. Iso.

2T48-F335A 2 A 2" A0 Globe B-4 H-26084 DW Purge Outlet C Qtr CIV Yes NA' Inbrd. Iso.

2T48-F335B 2 A 2" A0 Globe C-4 H-26084 DW Purge Outlet C Qtr CIV Yes NA Inbrd. Iso.

2T48-F338 2 A 2" A0 Globe H-2 H-26084 Bypass-Outbrd. C Qtr CIV Yes NA Iso.

2T48-F339 2 A 2" A0 Globe H-3 H-26084 Bypass-Inbrd. C Qtr CIV Yes NA Iso.

2T48-F340 2 A 2" A0 Globe D-2 H-26084 Bypass-Outbrd. C Qtr CIV Yes NA Iso. ,,

2T48-F34I 2 A 2" A0 Globe E-4 H-26084 Bypass-Inbrd. C Qtr CIV Yes NA Iso.

m. . m m +- -

+ _ .

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08/13/90 Plant Hatch Unit 2 Valve Test Program -

Table 2 Stroke Notes Valve Code Norm Time HReliefE Na. Class Cat. Description Coord. P&ID. Function Pos Exercise Leakage Reg'd CS~Just.-

2T48-F342A 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

2T48-F3428 2 A 1/2" Solen'id H-8 H-26084 Torus to DW C Qtr CIV No. RR-V-31 Vac. Breaker Iso.

2T48-F342C 2 A I/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV. No RR-V-31 Vac. Breaker Iso.

2T48-F3420 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr 1 - CIV No RR-V-31.

Vac. Breaker Iso.

2T48-F342E 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No. RR-V Vac. Breaker Iso.

2T48-F342F 2 A I/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

2T48-F342G 2 A I/2" Solenoid' H-8 H-26084 Torus ~to DW- C. Qtr CIV ' No - RR-V-31 Vac. Breaker Iso.

, ~n - m w. .ma-o.. .o, _,--

~ p. ~>,,~i r.- -- - n- m y .~ ~

,- - ,. , p C

Page No. 77 08/13/90 i

~ ^

Plant Hatch Unit 2 Valve Test Program *'

Table 2 ,

t Stroke Notes Valve Code Norm Time Relief No. Class Cat. Description Coord. PalD Function Pos Exercise leakage Reg'd C5 Just.

2T*8-F342H 2 A I/2" Sol;noid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

2T48-F3421 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

i 2T48-F342J 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

2T48-F342K 2 A I/2" Solenoid H-8 H-26084 Torus to DW C Qtr . . CIV No RR-V-31 Vac. Breaker Iso.

2T48-F342L 2 A 1/2" Solenoid H-8 H-26084 Torus to DW C Qtr CIV No RR-V-31 Vac. Breaker Iso.

2T48-F3GIA 2 A 1" A0 Globe G-9 H-25084 Torus Water 0 Qtr CIV Yes NA Level Iso.

2T48-F3618 2 A 1" A0 Globe G-5 H-26084 Torus Water 0 Qtr CIV , Yes NA Level Iso.

2T48-F362A 2 B I" A0 Globe H-9 H-26084 Torus Water 0 Qtr NA Yes Note 9 level Iso. ,

3 d q Page No. 78 08/13/90 e'lant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes Valve Code .

Norm Time Retier No. Class Cat. Description Coord. P&lD Function Pos Exercise leakage Ren'd ts Just.

Zi48-F367rt 2 B 1" A0 Globe H-5 H-26084 Torus Water 0 Qtr NA Yes Note 9 level Iso.

2T48-F363A 2 A 1" A0 Globe E-8 H-26084 Press. O Qtr CIV Yes NA Transmitter Iso.

i l 2T48-F3538 2 A l' A0 Globe D-6 H-26084 Press. 0 Qtr CIV Yes NA

Transmitter I Iso.

2T484364A 2 A I" A0 G7 e G-5 H-26084 Press. O Qtr CIV Yes MA I Transmitter ,, -

1 Iso.

1748-F364B 2 A l' A0 Globe G-8 H-26084 Press. O Qtr CIV Yes MA Transmitter Iso.

2T48-F472 2 C 2" Check B-5 H-26083 NZ Tank Disch. O RO NA No RR-V-4 Check Notes 17<

23

?

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l l

S en J {V U Page No. 79 08/13/90 Plant Hatch Unit 2 Valve Test Program Table 2 Stroke Notes

! Valve Code Norm Tim Relief No. Class Cat. Description Coord. Pa10 Function Pos Exercise leakage Reg'd- CS Just.

• • System - 2T49 l 2T49-f001A 2 B 4" M0 Gate C-3 H-26068 Hydrogen Recom. C Qtr NA Yes Note 17

, DW Shutoff l

! 2T49-F001B 2 B 4" M0 Gate C-3 H-26068 Hydrogen Recom. C Qtr NA Yes Note 17 DW Shutoff 2T49-F002A 2 A 4* M0 Gate C-4 H-26068 Hydrogen Recom. C Qtr CIV Yes MA i DW Iso.

(

l 2T49-F002B 2 A 4" M0 Gate C-4 H-26068 Hydrogen Recom. C Qtr CIV Yes MA l DW Iso.

l 2T49-F004A 2 A 4" M0 Gate F-5 H-26068 Hydrogen Recom. C Qtr CIV Yes MA l Gas S Water Iso.

j 2T49-F004B 2 A 4" M0 Gate F-5 H-26068 Hydrogen Recom. C Qtr CIV Yes MA i Gas & Water Iso.

2T49-F005A 2 B 4" MG Gate F-4 H-26068 Gas & Water C Qtr NA Yes MA Return 2T49-F0058 2 B 4" M0 Gate F- 4 H-26068 Gas & Water C Qtr NA 3' Yes NA i Return

0 Page No. 80 0 -O 08/13/90

~ '

Plant llatch Unit 2 Valve Test Program -

Table 2 l

Stroke Notes Valve Code . Norm Time Relief No. Class Cat. Descrii. tion Coord. Pal 0 Function Pos Exercise Leakage Reg'd CS Just.

2T49-F006A 2 B 3/4" M0 Globe !I-5 H-26068 Water Feed from C Qtr NA Yes NA RHR 2T49-F006B 2 B 3/4" M0 Globe 11 - 5 H-26068 Water Feed from C Qtr NA Yes NA RHR 2T49-F007A 2 B 3/4" M0 Globe H8 H-26068 Water Feed from C Qtr NA Yes NA RHR 2T49-F007B 2 B 3/4" M0 Globe H-8 H-26068 Water feed from C Qtr NA Yes NA RHR 2T49-F009A 2 C 1" Relief F-4 H-26068 Relief / Cont. C IWV-3512 .NA No Note 9 Iso. Valve 2T49-F0098 2 C 1" Relief F-4 H-26068 Relief / Cont. C IWV-3512 NA No Note 9 Iso. Valve 11 l

3.0 INSERVICE TESTING OF PUMPS

,/~-

\ }

vs 3.1 GENERtt This Program is written to comply with the testing provisions of 10 CFR 50.55a which delineate the testing requirements for ASME Class 1, 2, and 3 pumps. The code of record used to meet these provisions is the 1980 Edition of ASME Section XI, with Addenda through Winter 1981 as modified by supplemental guidance from the NRC's Generic Letter 89 04. In cases where specific Code requirements cannot be met relief has been requested frotn the requirements. The pump testing programs for Unit I and Unit 2 are presented in Tables 3 and 4, respectively.

Extensivo guidance has been taken from the OM 6 standard for testing the pumps at Plant Hatch An enhanced velocity vibration monitoring program w 11 be used in lieu of the standard Code requirements in conjunction with nt w acceptance criteria. These changes are discussed in relief request '

Rit *>- 6.

2.2 SCOPE Safety related ASME Class 1, 2, and 3 pumps f alling under the Regulatory Position of Regulatory Guide 1.26 and supplied with an emergency power source are tested using the provisions of ASME Section XI.

It is recognized that 10 CFR 50 Appendix A, GDC 1, and Appendix B, (n) v Criterion XI intend that all pumps necessary for safe operation of the plart be tested to demonstrate that they will perform satisfactorily in scNice. This testing is to be performed to a level commensurate with the function of the pump. This testing is generally performed per the requirements of the plant Technical Specifications or other requirements.

The RCIC Pumps and the Diesel Generator Fuel Oil Transfer Pumps have been included in this Program to provide a readily accessible, documented method of testing. This testing will be performed in a method similar to that found in Section XI, and should adequately uetect degradation in these particular pumps.

The Spent Fuel Pool Cooling Pumps have not been included in this Program i because they are not safety related. In addition credit is taken in the FSAR.for Plant Service Water as the safety-grade makeup source, and the RHR system is used as the backup cooling source.

The Core Spray Jockey Pumps have not been included in this Program because they are not safety-related.

l 000953

(V]

1 A

i 3.3 J P Mt TESTING WITH MINIMUM FLOW 11NES l

(' 'N There are no purrps tested at Plant Hatch using minimum flow lines as the

(_j flow path. All pumps are provided with full flow test lines; therefore,  ;

the Generic Letter 89 04 concern over possible damage during this type of

~

1 pump testing is not applicable. _ l 3.4 STARTING POINT FOR TIME pfR10D IN TECHNICAL SPECIFICATIONS ACTION STATEMENTS ,

)

When performing pump testing, as soon as the data are recognized as being within the " Required Action Range", the associated pump will be declared i' inoperable and the applicable Technical Specification Action Statement entered.

3.5 INSTRUMENT ACCURACIES Relief has been requested to allow the use of installed instruments on any pump where the total loop accuracy may fall outside the Code limits. See RR P 7.

p v

l I

l 000953 2

\ n l

l

i Hatch Nuclear Plant - Units 1 and 2 Pump Inservice Test Program N0l[S

)

1. This system was not designed to perform Section XI type pump testing, and will not be tested per Section XI since it is not covered by the ,

Regulatory Position of Regulatory Guide 1.26. However, as discussed in the Scope Section of this document, testing will be performed in a manner similar to that in Section XI, and should adequately detect degradation.

'Since instrumentation was not provided to measure flow (or pressure),

a portable ultrasonic type instrument will be used to measure flow.

The piping basically forms a fixed resistance system; therefore, measurement of Po and Pi is not deemed tessary. If the flowrate decreases below a procedural specified value, the pump will be declared inoperable. This value will be determined using the guidance set forth in Relief Request RR P 6 for hydraulic parameters as mcdified to take into account the repeatability of this type of flow measuring device.

2. The Diesel Generator Fuel Oil Transfer Pumps are located inside the storage tanks with the motor and pump coupling area located above the tank. This arrangement provides inherent deficiencies for detection of degradation through vibration testing. Therefore, best effort ,

motor vibration measurements will be taken quarterly to assist in the detection of degradation in the pumps.

[ 3. Diesel fuel Oil Transfer Pumps are lubricated by the diesel fuel being pumped. Lubricant level or pressure is, therefore, not applicable, l

l 4. As discussed in the Scope section of this document, testing of the RCIC Pumps is included in this Program only for completeness, since they are not safety-related.

l 000953 1 O

v

L

l. O O O l IIATCH NUCLEAR PLANT-UNIT I PUMP INSERVICE TESTING PROGRAM

(. ,

TABl0 3 l

l ASME Pump Code .

Actual Section XI Code l Identification Pump Description Class Measured Parameters Test Interval Relief Requested l C41-C001A Standby liquid Control 2 1. Inlet pressure NA RR-P-5 (Positive Displacement) l C41-C0018 2. Differential pressure NA RR-P-5

3. Flowrate Every 3 mo RR-P-2,6 l 4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant icvel or Every 3 mo No i

pressure E11-C002A Residual lleat Renoval 2 1. Inlet pressure Every 3 mo RR-P-1 (Centrifugal)

Ell-0002B 2. Differential pressure Every 3 mo RR-P-6,7 Ell-C002C 3. Flowrate Every 3 mo RR-P-6.7 Ell-00020 4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA g

, RR-P-6

6. Lubricant icvel or NA RP-P-4 pressure 000953 1

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

7 3

% 'D N_]

-HATCH NUCLEAR PLANT-UNIT I PUMP INSERVICE TESTING PROGRAM TABLE 3 ASME Pump Code Actual Section XI Code Identification Pump Cescription Class Measured Parameters Test Interval Relief Requested E11-0001A RHR Service Water 3 1. Inlet pressure Every 3 mo RR-P-3 (Vertical Line Shaft)

Ell-C0018 2. Differential pressure Every 3 mo RR-P-3.6 Ell-0001C 3. Flowrate Every 3 mo RR-P-6 Ell-00010 4. Vibration amplitude Every 3 mo RR-P-6 5 Bearing temperature NA RR-P-6 l 6. Lubricant level or Every 3 mo RR-P 4 pressure i

E21-C001A Core Spray 2 1. Inlet pressure Every 3 mo RR-P-7 (Centrifugal)

E21-C001B 2. Differential pressure Every 3 mo RR-P-6

3. Flowrate Every 3 mo RR-P-6

4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant icvel or NA RR-P-4 pressure 000953 2 l

1

! O O O IIATCil NUCLEAR PLANT-UNIT 1 PUMP INSERVICE TESTING PROGRAM TABLE 3 ,

ASME Pump Code Actual Section XI Code Identification Pump Description Class Measured Parameters Test Interval- Relief Requested E41-0001 High Pressure Coolant 2 1. Inlet pressure Every 3 mo No l Injection l (Centrifugal) 2. Differential pressure Every 3 mo. RR-P-6

3. flowrate Every 3 mo RR-P-6

4. Vibration amplitude Every 3 mo RR.P.6

5. Bearing temperature Mr. RR-P-6

6. Lubricant level or Every 3 mo No l pressure i

j 7. Pump speed Every 3 mos. No E51-C001 Reactor Core Isolation 2 1. Inlet pressure Every 3 me. No Cooling (Centrifugal) 2. Differential pressure Every 3 mo. Note 4

3. Flowrate Every 3 me. Note 4

4. Vibration amplitude Every 3 me. Noia 4

5. Bearing temperature NA

" Note t ,

6. Lubricant level or Every 3 me. No pressure

7. Punip speed Every 3 me. No  !

000953 3

, D O O HATCH NUCLEAR PLANT-UNIT I PUMP INSERVICE TE5ilNG PROGRAM TABLE 3 l ASME l Pump Code Actual Section XI Code i identification Pump Description Class Measured Parameters Test interval Relief Reevested l

P41-C001A Plant Service Water 3 1. Inlet pressure Every 3 mo RR-P-3 i

(Vertical line Shaft) j P41-0001B 2. Differential Pressure Every 3 mo RR-P-3,6 P41-00010 3. Flowrate Every 3 mo RR P-6 l

P41-C001D 4. Vibration amplitude Every 3 mo '< R - P - 6

5. Bearing temperature NA RR-P-6

6. Lubricant level or NA RR-P-4 pressure l

i l

l

! 000953 4

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4 -(ww w- -V -

y >+ w -r+' ,-,- w w ,*i-w - - - - * *b -w w w

O O O HATCH NUCLEAR PLANT-UNIT I PUMP INSERVICE TESTING PROGRAM TABLE 3 ,

ASME Pump Code Actual Section XI Code identification Pump Description Class Neasured Parameters Test Interval Relief Reemsted lY52-C001A Diesel Fuel Oil Transfer NA 1. Inlet pressure NA Note 1 l (Vertical Line Shaft) j lY52-0001B 2. Differential pressure NA Note 1-i

lY52-C0010 3. Flowrate Every 3 me. Note 1 lY52-0101A 4. Vibration amplitude Every 3 mo. Note 2 lYS2-0101B 5. Bearing temperature NA Note I lY52-01010 6. Lubricant icvel or NA Nnte 3 pressure s .

1I 00095.5 5

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Y Y llATCH NUCLEAR PLANT-UNIT 2 PUMP INSERVICE TESTING PROGRAM TABLE 4 ASME Pump Code Actual Section XI Code Identification Pump Description Class Measured Parameters Test interval Relief itcquested 2C41-C001A Standby liquid Control 2 1. Inlet pressure NA RR-F-5 ,

(Positive Displacement) 2C41-C0018 2. Differential pressure NA RR P-5

3. Flowrate Every 3 mo RR-P-2,6

4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant level or Every 3 mo No pressure 2 Ell-C002A Residual Heat Removal 2 1. Inlet pressure Every 3 mo RR P-7 (Vertical Line Shaft) 2 Ell-0002B 2. Differential pressure Every 3 mo RR-P-6.7 2 Ell-0002C 3. Flowrate Every 3 mo RR-P-6,7 2 Ell-00020 4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant level or NA I RR-P-4 pressure 000953 I

(.m ,

b '

11ATCil NUCLEAR PLANT-UNIT 2 PUMP INSERVICE TESTING PROGRAM TABLE 4 ASME Pump Code Actual Sectiot. XI Code Identification Pump Description Cl a s_s ' Measured Parameters Test Interval Relief Requested 2 Ell-0001A RHR Service Water 3 1. Inlet pressure Every 3 mo RR-P-3 (Vertical Line Shaft) 2 Ell-C0018 2. Differential pressure Every 3 mo RR-P-3,6 2 Ell-0001C 3. Flowrate Every 3 mo RR-P-6 2 Ell-C001D 4. Vibration amplitude Every 3 mo RR-P-6

5. Bearing temperature NA RR-P-6 l 6. Lubricant level or NA RR-P-4 pressure b **

l 2E21-C001A Core Spray 2 1. Inlet pressure Every 3 mo RR-P-7 (Vertical Line Shaft) i 2E21-C0018 2. Differential pressure Every 3 mo RR-P-6

, 3. Flowrate Every 3 mo RR-P-6 ,

1

4. Vibration amplitude Every 3 mo RR-P-6 f 5. Bearing temperature NA RR-P-6

6. Lubricant level or NA RR-P-4 pressure 000953 2

IIATCli NUCLEAR PLANT-UNIT 2 PUMP INSERVICE TESTING PROGRAM TABLE 4 ASME Pump Code Actual Section XI Code Identification Pump Description Class Measured Parameters Test interval Relief Requested 2E41-C001 High Pressure Coolant 2 1. Inlet pressure Every 3 mo. No injection (Centrifugal) 2. Differential pressure Every 3 mo. RR-P-6

3. Flowrate Every 3 mo. RR-P-6  :

4. Vibration amplitude Every 3 mo. RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant level or Every 3 mo. No pressure

7. Pump speed Every 3 mo. ,.- No 2E51-C001 Reactor Core Isolation 2 1. Inlet pressure Every 3 mo. No Cooling (Centrifugal) 2. Differential pressure Every 3 mo. Note 4

3. Flowrate Every 3 co. Note 4

4. Vibration amplitude Every 3 cm. Note 4

5. Bearing temperature NA  !

Note 4

6. Lubricant level or Every 3 r.o. No pressure

7. Pump speed Every 3 mo. No 000953 3

HATCil NUCLEAR PLANT-UNIT 2 PUMP INSERVICE TESTING PROGRAM TABLE 4 ,

ASME Pump Code Actual Section XI Code Iden'. fication Pump Description Class Measured Parameters Test Interval Relief Requested 2P41-0001A Plant Service Water 3 1. Inlet pressure Every 3 mo. RR-P-3 (Vertical Line Shaft) 2P41-C001B 2. Differential pressure Every 3 me. RR-P-3,6 2P41-C001C 3. Flowrate Every 3 mo. RR-P-6 2P41-C0010 4. Vibration amplitude Every 3 mo. RR-P-6

5. Bearing temperature NA RR-P-6'

6. Lubricant level or NA RR-P-4 pressure 2P41-C002 Standby Diesel Gen. 3 1. Inlet pressure Every 3 mo. RR-P-3 Service Water (Vertical Line Shaft) 2. Differential pressure Every 3 mo. RR-P-3,6

3. Flowrate Every 3 mo. RR-P-6

4. Vibration amplitude Every 3 mo. RR-P-6

5. Bearing temperature NA RR-P-6

6. Lubricant level or NA RR-P-4 pressure 000953 4

+-m_ -

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

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O O O IIATCH NUCLEAR PLANT-UNIT 2

PUMP IK'aERVICE TESTING PROGRAM

, , TABLE 4 ASME Pump Code Actual Section XI Code Identification P > mp Description Class Neasured Parameters Test Interval Relief Requested 2Y52-C00lA Diesel Fuel Oil Transfer NA 1. Inlet pressure NA Note 1 (Vertical Line Shaft) 2Y52-0001C 2. Differential pressure NA Note 1 2Y52-CIOIA 3. Flowrate Every 3 mo. Note 1 2YS2-C101C 4. Vibration amplitude Every 3 me. Note 2

5. Bearing temperature NA Note 1

6. Lubricant level or NA Note 3 ,

pressure s'

r i

000953 5

. . - .- ~ . . .-

. i 4.0 VA.LVL_RJL IE F RE0VE ST LOG

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i L- ') Status Relief Reoue_s_t Comments RR V-1 NRC Approval Requested 2 RR V-2 NRC Approval Requested RR V 3 Superseded by GL 89-04 RR-V 4 NRC Approval Requested RR V-5 NRC Approval Requested RR V-6 NRC Approval Requested

' RR V 7 Superseded by GL 89 04 RR V 8 Withdrawn RR V-9 Withdrawn RR V 10 NRC Approval Requested RR V Il NRC Approval Requested RR V 12 Supe;seded by GL 89-04 RR-V 13 Sur,erseded by GL 89 04 RR V 14 Superseded by GL 89 04 RR V 15 'iRC Approval Requested RR-V 16 Superseded by GL 89 04 l RR V 17 Superseded by GL 89 04 RR V-18 NRC Approval Requested RR-V 19 Superseded by GL 89 04 RR V 20 NRC Approval Requested RR V 21 Superseded by GL 89 04 RR V 22 NRC Approval Requested i f RR-V-23 NRC Approval Requested

( RR V 24 Withdrawn Valves deleted from program RR-V-25 NRC Approval Requested j RR V-26 Superseded by GL 89 04 RR V 27 Superseded by GL 89-04 RR V-28 NRC Approval Requested RR V-29 NRC Approval Requested RR V-30 Superseded by RR V 30A RR-V 30A NRC Approval Requested RR-V 31 NRC Approval Requested RR-V-32 NRC Approval Requested RR V-33 Withdrawn RR V 34 Withdrawn RR V 35 Withdrawn RR V-36 NRC Approval Requested RR-V 37 Superceded by GL 89 04 RR-V-38 Superseded by GL 89 04 RR V 39 NRC Approval Requested

' RR V 40 NRC Approval Requested RR-V-41 NRC Approval Requested 000356 i- vp i

F

i REllEF REQUEST RR V 1

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SYSTEM: Feedwater _

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VALVE (S): B21-F010ALB, B21-F032A&B, 2B21-F010A&B CATEGORY: AC  ;

CLA$$: 1 FUNCT10ft: Feedwater Line Containment Isolation  ;

TEST REQUIREMENT: Verify reverse flow closure quarterly per IWV 3520 l

BASIS FOR RELIEF: Introducing reverse flow in the main feedwater lines during power operation would introduce main feedwater flow l transients into the reactor and safety systems and l potentially trip the reactor. Also, entry into the area l to perform testing during power operation is not allowed. i To attempt to perform this test during a cold shutdown I

l could delay the startup of the unit. l l l l

rm ALTERNATE TESTING: Closure of these valves will be proven each refueling l Q outage during Local Leak Rate Testing.

l I 000356 O

REllEF REQUEST RR V-2

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SYSTEM: NA VALVE (S): B21 F016 E41 F002 E51 F016 2B21-F016 2E41 F002 2E51 F007 CATEGORY: A CLASS: I and 2 FUNCTION: NA TEST REQUIREMENT: 1WV-3423(d) requires that gate valves that have a functional differential pressure greater than 15 psi be tested for leakage in the same direction as when the valve is performing its function.

BASIS FOR RELIEF: The correct direction is to pressurize from the inboard side of the v61ve; however, the piping on the inboard side runs directly from the valve to the torus (or reactor vessel) and cannot be pressurized for testing.

Al. TERNATE TESTING: These containment isolation valves will be leak rate tested in a nonconservative reverse direction as addressed

(_)

(/

in the containment leak rate test program for Type C leakage tests, t

000356 3

(V

REllEF REQUEST RR V 3 SYSTEM: NA l Valves with stroke times of 2 seconds and less '

VALVE (S):

CATEGORY: A and B .

CLASS: 1, 2, and 3 FUNCTION: NA TEST REQUIREMENT: lWV-3413(b) requires that the stroke time of all  !

power operated valves shall be measured to the nearest I second for stroke times of 10 seconds or.less. IWV 3417 requires that on any one test of power operated valves, if an increase in stroke time of 50 percent or more from the I previous test for valves with stroke times of M seconds or less occurs, the test frequency shall t? inc. eased to once each .:, nth until corrective action is tdur, 1 BASIS FOR REllEF: Accurate measurement of stroke times wht:h are 2 seconds j or less is not pract cal.

ALTERNATE TESTING: These valves will be fud-stroke tested. A full stroke time of 2 seconds will be allowed for these valves.

/'

Acceptance of the test will be based only on the stroke

( time limit and not on the "50 percent" criterion in IWV 3417.

l

, VALVES NEEDING THIS TYPE OF REllEF COMPLY WITH THE l PROVISIONS OF GENERIC LETTER 89 04, POSITION 6. VPON EXCEEDING THE 2 SECOND MAXIMUM LIMITING VALUE, THE VALVE WILL BE DECLARED INOPERABLE AND CORRECTIVE ACTION TAKEN IN COMPLIANCE WITH IWV-3417(b). THE SPEClfl0 APPLICATION OF THIS TEST]NG CRITER10N WILL BE IDENTIFIED IN THE IST PLANS AND THE SURVEILLANCE PROCEDURES WHICH ARE AVAILABLE FOR REVIEW AT THE PLANT SITE.

000356

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s REllEF REQUEST

- ('~} RR V 4 G!

SYSTEM: NA .

VALVE (S): Valvesexercisedonlyduringcoldshutdownorrefueiing

^

CATEGORY: A, B, C, and AC CLASS: 1, 2, ar.d 3 FUNCTION: NA l

TEST REQUIREMENT: IWV 3417(b) and IWV 3523 indicate that when corrective I action is required as a result of tests made during cold I shutdown, the condition shall be corrected before startup. 1 l

BAS 15 FOR REllEF: The plant Technical Specificatons provide the requirements l and plant conditions necessary for plant startup.

. ALTERNATE TESTING: Under such conditions.startup shall be permitted as provided by the Technical Specifications. ,

i l

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000356

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RELIEF REQUEST 7y RR V 5

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v SYSTEM: Reactor Recirculation VALVE (S): 831 F013A&B, B31 F017A&B, 2831-F013A&B, 2831-F017A&B-CATEGORY: AC .

CLASS: 1 FUNCTION: Recirculation Pump Seal Water TEST REQUIREMENT: Verify reverse flow closure quarterly per IWV 3520 BASIS FOR RELIEF: These valves are located in the Recirculation Pump Seal Water injection lines which require continuous flow during power operation in accordance with the pump manufacturer's recommendations. Quarterly testing could damage the seals. Also, to attempt to perform this test during a cold shutdown could delay the startup of the unit.

ALTERNATE TESTING: Closure of these valves will be proven each refueling outage during Local Leak Rate Testing.

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l 000356 j

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I REllEF REQUEST

. RR-V .()

SYSTEM: Standby Liquid Control (SBLC)-

1 VALVE (S): C41-F006, C41 F007, 2C41 F006, 2C41 F007 l CATEGORY: AC .

j i

CLASS: 1  ;

FUNCTION: SBLC Injection Line Isolation I TEST REQUIREMENT: Verify forward flow operability and closure quarterly per

.lWV 3520.

L BASIS-FOR REllEF: Testing of these normally closed valves quarterly or during cold shutdown would require: (1) actuation and restoration of the explosive valves (2) entry into the containment to operate manual valves and (3) disablement of the SBLC system.

ALTERNATE TESTING: Required flow through these valves is achieved once per 18 months during Technical. Specifications testing. Closure is verified during Local Leak Rate Testing each refueling ,

outage because to attempt to perform the closure test l during cold shutdown could delay in the startup of the I

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9 000356

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

g RELIEF REQUEST

,- RR-V 7 ,

+ l}3 SYSTEM: HPCI ,,

VALVE (S): E41 F045

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CATEGORY: C CLA55: 2 FUNCTION: HPCI Pump Suction ,

TEST REQUIREMENT: Verify forward flow operability quarterly per IWV-3520 BASIS FOR REllEF: This normally closed check valve is located on the hPCI pump suction line and cannot be stroked. The valve does not experience flow during any normal mode of reactor coeration 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.

ALTERNATE TESTING: Every second refueling outage the valve will be disassembled to prove that the valve is capable of full stroking and that its internals are structurally sound (no

O loose or excessively corroded parts). This frequency is

() considered adequate to detect degradation which would prevent the valve from meeting its safety function. The valve remains in the closed position in a torus water environment and does not experience flow which could cause wear. Also, all past inspections of this valve have shown little, if any, degradation other than the expected corrosion.

THE ALTERNATE TESTING IN THIS REllEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89 04. THE GROUPING OF VALVES AND THE FRE0VENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89 04.

000356

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REllEF REQl'EST RR V-8 O SYSTEM: NA

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VALVE (S): E41-iO21, E41 F022, E51 F00., E51-F002 --

2E41-F021, 2E41-F022, 2E51 F001, 2E51-F002 CATEGORY: AC CLASS: 2 FUNCTION: Containment isolation TEST REQUIREMENT: lWV-3423 requires that valves be leak tested with the pressure differential in the same direction as when the valve is performing its function.

BASIS FOR REllEF: This turbine exhaust t06teinment 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.

ALTERf4 ATE TESTil4G: As an alternative, the valve is closed with the closure mechanism and leak tested from the reverse side. The leak O.= test, as defined in the containment leak rate test program, is conservative since the test pressure tends to lift the disc from the seat much in the same manner as reverse testing a globe valve.

GEORGIA POWER COMPANY HAS WITHDRAWN THIS REllEF REQUEST.

000356 0

S RELIEF REQUEST L

RR V-9

)

SYSTEM: RCIC

-VALVE (S): E51-F001, E51 F002. E51-F021. E51-F028. E51 F040 -

2E51-F001, 2E51 F002, 2E51 F021, 2E51-F028, 2E51 F040

~

CATEGORY: AC CLASS: 2 FUNCTION: Containment Isolation TEST REQUIREMENT: Verify reverse flow closure quarterly per IWV-3520 BASIS FOR REllEF: These valves are in the normally closed position except when the RCIC pump is run. The only positive means to verify closure is to pressurize and introduce reverse flow which is done during the Local Leak Rate Test. To perfore this test quarterly would require that the RCIC system be made inoperable during the test. Also, to attempt to perform these tests during cold shutdown could delay the startup of the unit.

ALTERNATE TESTING: These valves will have their closure verified each refueling outage during the Local Leak Rate Tests.

LJ GEORGIA POWER COMPANY HAS WITHDRAWN THIS REllEF REQUEST.

t 000356 o

k .!EF REQUEST

, RR V 10 i._)

SYSTEM: Main Steam ,.

VALVE (S): B21-F022A D, B21-F028A D, 2021-F022A D, 2B21-F028A-D 1

CATEG0F.s: A CLASS: 1 FUNCTION: Main Steam Isol. tion Vr.lves TEST REQUIREMENT: Relief is requested from applying the requirements of IWV 3427(b) to the main steam isolation valves.

BASIS FOR RELIEF: ASME Section XI requires that the valves be tested once per 24 months unless a test shows that the margin between the measured leakage rate and the maximum permissible rate has been reduced by 50 percent or greater. In this case the frequency of testing should be doubled (or approximately every 12 months) to coincide with a cold shutdown. Also, trending of the leakage rates is required.

The Technical Specifications require that these valves be 7 tested on a much more frequent basis or once per refueling

(' outage. Thes* 24 inch globe valves are tested by applying 28 psig between the inboard and outbosrd valves with a maximum allowable leakage of 11.5 SCFH. This allowable leakage is small when compared to other Category A valves.

Some leakage may occur through mechanically sound valves because the inboard valve is reverse tested, which tends to lift the globe from the seat, thereby allowing leakage that would not occur during a normal pressurization.

Since the normal testing frequency applied by tne Technical Specifications is sinilar to those reouired by IWV-3427(b), the provisions of IWV-3427(b) need~not be applied. Using the conservative test, with low allowable leakages at a frequency of once per refueling outage, any significant degradation of the valve will be detected.

ALTERNATE TESTING: Testing will be conducted per the Technical Specifications a described above.

000356

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RELIEF REQUEST RR V Il SYSTEM: Main Steam VALVE (S): B21-F037A H, J-L 2B21-F037A H, K-M B21-F110A,0,G,H 2B21-F110B, D, F, G CATEGORY: C CLASS:- 3 FUNCT10th Main Steam Relief Valve Discharge Vacuum Breaker i TEST REQUIREMENT: Verify opening quarterly per IWV-3521 BASIS FOR RELIEF: These normally closed check valves are located in containment and therefore are inaccessible durino peer operation and cold shutdowns when the contai m at is inerted. To attempt to perform these tests during an

. unscheduled cold shutdown could delay the startup of the unit.

L i ALTERNATE TESTING: To ensure the operability of these \alves and not 4 potentially delay the startup of the ur.it, the test frequency will Se based on the functir a' the corresponding 5nV. Vacuum breakers installed on SRV discharge lines that have a relief or ADS function will be O tested each refueling outage. Vacuum breakers installed on SRV discharge lines that have a relief or aw-low set function (B21-F037A, C, G, H, B21-F110A, C, G, H, t

2B21-F037B, D, F, G and 2B21-F110B, D, F, G) will be tested each Cold Shutdown when de-inerted or Refueling Outage due to the increased probability of a water leg forming in these lines.

These valves are tested by visually inspecting each disc, ensuring that the disc moves freely, and by determining the opening force required to unseat the disc.

000356

e 4

< s RELIEF REQUEST =

,l. RR V 12 A._j' SYSTEM: HPCI 2.

VALVE (S): 2E41-F045 CATEGORY: C CLASS: 2 FUNCTION: HPCI Pump Suction TEST REQUIREMENT: Verify forward flow operability quarterly per IWV-3520.

BASIS FOR-REllEF: This normally closed check valve is located on the HPCl pump suction line and cannot be stroked. The valve does not experience-flow during any normal mode of reactor ,

operatio", vi shutdown conditions. . Testing of this valve l would require pumping water from the torus to the '

conde'isate storage tank, thereby lowering the water quality in the tank. g

' ALTERNATE TESTING: Every second refueling outage the valve will be disassembled to prove that the valve-is capable of full-

,, stroking and that its internals are structurally sound (no. l

) loose or excessively corroded parts). This frequency-is

.(V considered adequate to detect degradation which would prevent the valve from meating its safety function. The  !

valve-remains in tne closed position in a torus water environment and does not expereince flow which could cause wear. Also, all past inspections of this valve have shown little, if any, degradation other than the expected corrosion. 1 I

'THE ALTERNATE TESTING IN THIS RELIEF REQUEST IS SUPERSEDED

.BY GENERIC LETTER 89-04. THE GROUPING 0F VALVES AND THE FRLhUENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89 04.

000356 v -

_ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . _________.___-m_u- _ _ . _ _ _ . . - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . . _ ___.___._._-_r _ - _ _ _ _ _ _ . _ _ _

I REllEF REQUEST RR V 13 L_.Y SYSTEM: Core Spray E21 F006A,B '

VALVE (S):

CATEGORY: AC .

CLASS: 1 FUNCTION: Core Spray injection and Pressure Isolation TEST REQUIREMENT: Verify forward flow operability quartarly per IWV-3520. ,

BASIS FOR RELIEF: These valves do not see flow during any normal mode of operation or shutdown conditions.

-ALTERNATE TESTING: Every second re eling outage ene of the two'normally closed check o!.es will be disassembled (on a rotating basis) to , e e that the valve is capable of full stroking and that its internals are structurally sound (no loose or excessively corroded parts). This frequency is considered adequate to detect degradation which would prevent the valve from meetings its safety function. Valve integrity (misalignments, etc.) of each valve will be proven each f.s refueling outage during leak rate tests because these

(') valves are pressure isolation valves and must pass the.

leakage tests. If the valve is determined to be inoperable during the inspection, the other valve will be disassembled during that outage.

THE ALTERNATE TESTING lN THIS RELIEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89 04. THE GROUPING OF VALVES AND THE FREQUENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89-04.

f^s 000356

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REllEF REQUEST O- RR V 14 L)

SYSTEM: RHR VALVE (S): Ell-F050A,8 CATEGORY: AC CLASS: 1 FUNCTION: LPCI innd Pressure Isolation TEST REQUIREMENT: Verify forward flow operability quarterly per IWV 3520.

BASIS FOR RELIEF: These valves do not receive sufficient flow to assure that the valve fully opens during any normal mode of operation or shutdown condition.

ALTERNATE TESTING: 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. Therefore, every second refueling outage one of the two check valves will be disassembled (on a l rotating basis) to prove that the valve is capable of full l .- , stroking and that its internals are structurally sound (no

( loose or excessively corroded' parts). This frc:;rney is l

l V) considered adequate to detect degradation which wtuld

! prevent the valve from meeting its safety function. Valve integrity (misalignment,etc.) of each valve will be proven i each refueling outage during leak rate tests and must pass i the leakage tests. If the valve is-determined to be l inoperable during the inspection, the other valve will l

then be disassembled.

l-l l

l THE ALTERNATE TESTING IN THIS REllEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89 04. THE GROUPING OF VALVES AND THE FREQUENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89 04.

( 000356

RELIEF REQUEST RR V 15

-SYSTEM: Nuclear biler, Reactor Recirculation, CS, HPCI, and RCIC VALVE (S): B21-F015A-H, B21 F015J-N, B21-F015P, B21-F015R&S, B21-F041, B21-F043A&B, B21-F045A&B, B21 F947A&B, B21-F049A&B, B21 F051A-D, B21-F053A 0, B21-F055, B21-F057, B21-F059A H,'B21 F059L-N,

-B21-F059P, B21-F059R U, B21-F06), B31-F003A&B, B31-F004A&B, B31 F009A-D, B31-F010A-D, B31-F0llA-D, B31-F012A-D, B31-F040A D, E21-F01BA C, E41 Fo?4A D, E51-F044A D, 2B21-F041, 2B21-F043A&B, 2B21-F045A&B, 2B21 F047A&B, 2B21 F049ALB, 2B21 F051 A-D, 2B21 F053A D, 2B21-F055, 2B2.1-F057, 2B21-F059A H, 2B21-F059L-N, 2B21-F059P, 2B21 F059R U, 2Bil Ft#61, 2B21 F070A-D, 2B21-F071 A D, 2B21 F072A-D, 2B21-F073A D,- 2B31-F003A&B, 2B31-F004 A&B, 2B31-F009A-D, 2B31-F010A D, 2B31-F011 A D, 2B31-F012A-D, 2B31-F040A D, 2E21-F01BA-C, 2E41-F024A D, 2E51-F044A-D CATEGORY: AC CLASS: 1 FUNCTIO. Active contairiment isolation valves TEST. REQUIREMENT: IWV 3521 requires operability test of check valves and IWV-3522 describes the-required testing procedure.

BASIS FOR REllEF: The test requirements for check valves in the ASME Code are intended for testing simple check valves. The excess flow check valves are designed to actuate and limit flow i

in the case of an instrument line break downstream of the valve and installation of these valves meets the _

provisions of NRC Safety Guide 11 (Unit 1) or Reg. Guide l.11 (Unit 2). The valves limit the leakage in the event of an instrument line break to within the capacity of the reactor coolant makeup system. The more critical requirememt for the valves is to remain open when a fault does not exist to guarantee the reactor protection function of the instruments. The instruments served by these valves are critical during both plant operation and cold shutdown. Testing of these valves requires the removal from service of portions of the reactor protection

, instrumentation for an extensive period of time which is not justified.

ALTERNATE TESTING: Section 4.7.D.1.b (Unit 1) and Section 4.6.3.4 (Unit 2) of the Plant Technical Specifications specifies the frequency (Unit 1 - at least once per operating cycle and Unit 2 -

at least once per 1B months) of testing to verify operability and flow limiting capability of excess flow O check valves.

000356 l

l

4 REllEF REQUEST RR V 16 iv) SYSTEM: Core Spray

. VALVE (S): 2E21.F006A,8 1 CATEGORY: AC ,

I CLASS: 1 FUNCTION: Core Spray injection and Pressure Isolation TEST REQUIREMENT: Verify forward flow operabi'ity quarterly per IWV 3520.

BASIS FOR REllEF: These valves do not see flu during ny normal mode of operation or shutdown conditions.

ALTERNATE TESTING: Every second refueling outage one of the two normally closed check valves will be disassembled (on a rotating basis) to prove that the valve is capable of full stroking l

and that its internals are structurally sound (no loose or l

excessively corroded parts). This frequency is considered l adequate to detect degradation which would prevent the valve from' meeting its safety function. Valve integrity l (misalignments, etc.) of each valve will be proven each refueling outage during leak rate tests because these I valves are pressure isolation valves and nust pass the (d

\

o l l leakage tests. If the valve is determined to.be

l. inoperable during the inspection, the other valve will j then be disassembled during the outage.

\

l THE ALTERNATE TESTING IN THIS RELIEF REQUEST IS SUPERSEDED l BY GENERIC LETTER 89 04. THE GROUPING'0F VALVES AND THE l

FREQUENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89-04.

l l 000356 l

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I RFLIEF REQUEST RR.V-17 O SYSTEM: RHR 2 Ell-F050A,B i VALVE (S):

CATEGORY: AC-  ;

CLASS: 1 FUNCTION: LPCI and Pressure Isolation TEST REQUIREMENT: Verify forward flow operability quarterly per IWV 3520.

BASIS FOR REllEF: These valves do not receive sufficient flow to assure that the valve fully opens during any normal mode of operation or shutdown condition.

ALTERNATE TESTING: 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. Therefore, every .econd refueling outage one of the two check valves will be disassembled (on a rotating basis) to prove that the valve is capable of full stroking and that its internals are structurally sound (no loose.or excessively corroded parts). This frequency is considered to be adequate to detect degradation which O would prevent the valve from meetings its safety function.

. Valve integrity (misalignment,etc.) of each valve will be proven each refueling outage during leak rate testing.

If the valve is determined to be inoperable during the inspection, the other valve will also be disassembled.

THE ALTERNATE TESTING IN THIS REllEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89 04. THE GROUPING OF VALVES AND THE FRE0VENCY OF INSPECTION WILL BE CONDUCTED PER THE GUIDEL: ES OF POSITION 2 0F GENERIC LETTER 89-04.

000356 O

REllEF REQUEST RR V 18-SYSTEM: Reactoi Water Cleanup ..

VALVE (S): G31-F039, G31-F203 CATEGORY: AC CLASS: -1 i r

FUNCTION: RWCU Discharge-Line Containment Isolation i TEST REQUIREMENT: Prove reverse flow closure BASIS FOR RELIEF: This normally cren check valve is located in the RWCU main flow path. Setaring RWCU to perform this test during-power operatior, may cause a fluctuation in reactor water chemistry. Also, flow in one of the feedwater lines would have to be shutoff during this test (See RR-V-1). To attempt to perform this test during cold shutdowns could l pottntially delay the restart of the unit.

ALTERNATE TESTING: The check valve will be proven to close each refueling outage during the local leak rate tests.

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000356 O

REllEF REQUEST ,

y RR-V 19 i~~ j; SYSTEM: Plant Service Water VALVE (S): P41 F024A&B, P41 F025A&B, P41-F026A&B 2P41 F024A&B e CATEGORY: C i

CLASS: 3 FUNCTION: Provide cooling water flow to RHR, HPCI,- and CS pump / pump room coolers ,

TEST REQUIREMENT: Verify forward flow operability i BASIS _FOR REllEF: During quarterly testing of the HPCI, RHR, and Core Spray o Pumps the coolers are placed in operation, thereby stroking these valves. However, the design of the system does not-provide for positive verification of the flow-rate through each valve, i

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ALTERNATE TESTING: One valve will m. disassembled each refueling outage on a rotating basis to ensure that the design function of-the

.g. valve can be achieved. If the valve is determined to be ,

nonfunctional, an additonal valve will be disassembled.

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

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THE ALTERNATE TESTING IN THIS RELIEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89-04. THE GROUPING 0F VALVrS AND THE FREQUENCY OF INSPECTION WILL-BE CONDUCTED PER THE GUIDELINES OF POSITION 2 0F GENERIC LETTER 89 04.

000356 A ,

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RELIEF REQUEST ,

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. SYSTEM: Plant Service Water VALVE (S): P41-F035A&B,P41-F036A&B,P41-F037A-D,P41-F039A&B,341-F340, 2P41 F035A&B, 2P41-F036A&B, 2P41-F037A D, 2P41-F039A&B, 2P41-F339A&B CATEGORY: C 1

. . 1 CLA$5: 3 ,

FUNCTION: Cooling Water TEST REQUIREMENT: IWV-3413(b) requires' stroke times shall be measured to the ,

nearest second, for stroke times 10 seconds or less, or 10 l percent of the specified limiting stroke time for I full-stroke times longer than 10 seconds. j 1

, IWV 3417 requires t'at if the stroke time increases by 25 l percent from the previous test for valves with full-stroke times greater than 10 seconds or 50 percent'Or valves- i with full-stroke times less than 10 sec:;nds, the test frequency shall be increased to once each month until corrective action is taken.

f7 BASIS FOR RELIEF: These valves are air operated valves without ' indicating Q light 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 IWV 3413(b) and IWV 3417.

ALTERNATE TESTING: A maximum stroke time which will be as short as practical l will be assigned to each valve. If the measured stroke l- time exceeds this value, the valve will be declared j inoperable.

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i REllEF REQUEST RR V 21 7

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SYSTEM: Core Spray VALVE (5): E21-F036A,B 2E21 F036A,B, CATEGORY: AC -

CLASS: 2 FUNCTION: Core Spray Test Line Containment Isolation TEST REQUIREMENT: IWV-3520 requires that check valves be exercised at least once per 3 months and IWV-3421 requires that Category A  :

valves be leak tested.

BASIS FOR REllEF: Since there is no valve between the check valve and the torus the line cannot be pressurized to ensure closure of the valve. This valve is the inboard containment isolation valve for the core spray test line. The outboard isolation is a closed system as defined in the Appendix J program. This valve is sealed from the primary containment atmosphere because the test line terminates below the water level of the torus and the leakage is not included in the Type C Ic ,' leak rate testing.

b ALTERNATE TESTING: The integrated leak rate te will prove that leakage through the valve and closeo . system does not occur. There are no other practical means of testing this check valve for closure. l l

l THESE VALVES ARE LOCATED IN THE MINIMUM FLOW LINE, NOT THE TEST LINE. THEIR FUNCTION IS TO OPEN TO PROVIDE CORE I SPRAY PUMP MINIMUM FLOW PROTECT'.0N AND TO CLOSE FOR l CONTAINMENT BOUNDARY. THEREFORE, THIS REllEF REQUEST 15 BEING WITHDRAWN BY GEORGIA POWER COMPANY. VALVES lE21-F036A, E AND 2E21-F036A, B WILL BE DISASSEMBLED AND INSPECTED IN ACCORDANCE WITH POSITION 2 0F GL 89-04.

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REllEF REQUEST' I RR V 22 SYSTEM: RHR Service Water _

VALVE (S): E11 F068ALB,-2 Ell F06BA&B-CATEGORY: B CLASS: 3 FUtiCTION: RHR Service Water Flow / Pressure Regulation TEST REQUIREMENT: Exercise and' Stroke Time BASIS FOR REllEF: This valve cannot be opened unless the assoriated RHR service water pump is running. However, if the valve is fully opened with the pump operatinL the pump would then run out and cause potential damage to the pump.

ALTERt1 ATE TESTING: The quarterly pump test demonstrates that the valve is operating correctly. If the valve did not finction, it would be determined by improper test results.

O 000356

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REllEF REQUEST RR V 23 SYSTEM: HPCI

. VALVE (S): E41-F102, E41-F103, 2E41 102, 2E41 103 i CATEGORY: C  ;,

CLASS: 2 FUNCTION: Provide vacuum relief for the HPCI turbine exhaust line.

TEST REQUIREMENT: Verify forward flow epcrability and reverse flow closure quarterly per IWV-3520.

BASIS FOR REllEF: Operability of these check valves cannot be proven by normal process flow since they are acting simply as vacuum relief valves, if a vacuum forms in the turbine exhaust line due to steam condensation, the disc will lift from the seat sufficiently to allow air into the line.

Otherwise, there is no movement of the disc.

ALTERNATE TESTING: During the local leak rate test each refueling outage on Unit 1, the piping is pressurized between valves E41 Flll and E41-F104. Valve E41-F103 will then be vented as part of the test to ensure that. flow passes through the check valves. (Note: Same test will be performed on Unit 2 O-valves). This flow rate will be greater than that required for vacuum relief. Closure of the valves is proven by HPCI pump operation. If the valve did not close, steam would bypass the suppression pool into the torus bay: air space and cause a resultant temperature increase.

000356 O

RELIEF REQUEST RR-V-24 O SYSTEM: RHR Service Water VALVE (S)': Ell F200A D, 2 Ell-F207A D 1 CATEGORY: B  ;

CLASS: 3' FUNCTION: RHR SW Pump minimum flow line open/close TEST REQUIREMENT: Stroke timing and corrective action requirements in lWV 3413 and.lWV-3417, respectively.

BASIS FOR RELIEF: These valves do not have remote indicating lights which would allow for accurate measurement of the stroke times.

or total application of the required corrective action.

ALTERNATE TESTING: These valves will be stroke timed by observing the stem movement and then timing that movement. Acceptance of the test will be based only on the stroke time limit and not-on the cther crit 9rion in IWV 3417.

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THESE VALVES HAVE BEEN DELETED FROM THE IST PROGRAM; THEREFORE, THIS REllEF REQUEST IS WITHDRAWN.

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REllEF REQUEST RR V 25~

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SYSTEM: Plant Service Water ,,

VALVE (S): P41 F311A D, 2P41 F311A D L '

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CLASS: 3' x

FUNCTION: Pump discharge check valve TEST REQUIREMENT: Prove that these normally open check valves close by t IWV-3522(b).- t BASIS FOR-REllEF: There are:no direct means to verify closure of these

-valves.

L ALTERNATE-TESTING: Closure must be verified to ensure that flow from an- I L operating pump on the train is not diverted back through a t non-operating pump and thereby degrading the performance- 1 h

l of the operating pump,  ;

l Closure of the valve is confi*med whenever the pump is

'. . sFutoff since performance of the other pump does not-degrade.

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L-Note: Opening is verified by required flow.

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RELIEF REQUEST RR V 26 ry.

't SYSTEM: CRD VALVE (S): C11 HCU ll5, 2Cll HCV 115 -

CATEGORY: B  ;

CLASS: 2 FUNCTION: Charging Water Header Check Valves TEST REQUIREMENT: IWV-3522 requires that check valves he exercised quarterly to the position required to fulfill . heir safety function.

BASIS FOR REllEF: Reverse flow closure verification of the charging water header check valves requires that the CRD pumps be stopped to depressurize the charging water header. This test can not be performed during normal operation because storping the pumps results in lose of cooling water to all CRD mechanisms and seal damage could result. Additionally, this test cannot be performed during cold shutdown because the CRD pumps supply seal water to the reactor i recirculation pumps and one of the recirculation pumps is l

normally kept in operation.

! (' N ALTERNATE TESTING: Reverse flow c'osure will be verified at each refueling (j outage by performance of a HCU accumulator pressure decay

test.

l THE ALTERNATE TESTING IN THIS REllEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89-04. THE TESTING OF THESE VALVES WILL BE PERFORMED IN ACCORDANCE WITH POSITION 7 0F GENERIC l LETTER 89-04.

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RELIEF REQUEST

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SYSTEM: CRD VALVE (S): Cll-HCV 126, Cll HCU 127, 2Cll-HCU-126, 2Cll-HCU 127-CATEGORY: B CLASS: 2 FUNCTION: Scram Inlet and Outlet Valves TEST REQUIREMENT: IWV-3400 requires that these valves be tested quarteriy.

BASIS FOR REllEF: The Hydraulic Control Units (HCU) are integrally designed systems for controlling rod drive movements. Individual l valve testing is not possible without causing a control rod scram with a resulting change in core reactivity.

Quarterly testing of these valves increases the potential to violate plant Technical Specifications which govern the methods and frequency of reactivity changes. In addition, these are power operated valves that full-stroke in milliseconds and are not equipped with remote position indicators. Therefore, measuring their full-stroke time is impractical. Verifying that the associated control rod ,

meets the scram insertion time limits defined in the l O Technical Specifications provides an alternate method of i

~O detecting valve degradation. Trending the stroke times of these valves is impractical and-unnecessary since they are indirectly stroke timed and no meaningful correlation ,

between the scram time and valve stroke time can be l' obtained.

ALTERNATE TESTINC: Technical Specification Control Rod Scram insertion Time testing serves to verify proper operation of each of these valves. As a minimum,10% of the CRDs on Unit.1 are scram timed on a. rotating basis every 16 weeks and 10% of the CR0s on Unit 2 are tested every 120 days. After each major refueling outage and prior to power operation, all operable. control rods on Unit 1 shall be scram tested from the fully aithdrawn position. Following any reactor shutdown (Units 1 and 2) that is greater than 120 days,-

all control rods shall be scram tested.

1 THE ALTERNATE TESTING IN THIS RELIEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89-04. THE TESTING OF THESE VALVES WILL BE PERFORMED IN ACCORDANCE WITH POSITION 7 0F GENERIC LETTER 89 04.

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RELIEF REQUEST RR V-28

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-[- " SYSTEM: -1821'and 2B21 VALVE (S): IB21 F036A, B, C, D, E, F, G, H, J, K, L- ~_. .l 2B21 F036A, B, C, D, E, F, G, H, v. L, M -

CATEGORY: C CLASS: 2 FUNCTION: MSRV Accumulator Check valves

• TEST REQUIREMENT: Verify reverse flow closure quarterly per IWV-3520 -

BASIS FOR RELIEfi These valves cannot be tested during power operation since entry into the drywell is required. To attempt to perform these tests during cold shutdowns would potentially delay the startup of the unit. l l

ALTERNATE TESTING: Reverse flow closure of these valves is verified each l refueling outage by a special leak test procedure similar i to Appendix J, Type C, Leak Testing. .

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'000356

REllEF REQUEST RR-V 29 7

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w/ - SYSTEM: Nuclear Boiler System

. VALVE (5): IB21 F013A H, J, K, and L -

2821-F013A H, K, L, and M

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CATEGORY: BC $

CLASS: 1 FUNCTION: Nuclear Boiler System over-pressure protection TEST REQUIREMENT: IWV-3410 requires that Category B valves which cannot be stroke exercised during plant operation be exercised at cold shutdown and it requires that power operated valves be stroke timed.

BASIS FOR REllEF: Failure of these valves to close while being stroke tested during power operation would cause a loss of the primary reactor coolant. These valves cannot be exercised at pressure below 100 psig and the position of the main stage of this 2 stage relief valve can only be' determined by indirect means.

ALTERNATE TESTING: At least once per 18 months for Unit 2, when the reactor n steam dome pressure is greater than 100 psig these valves (j shall be manually opened and observed, to ensure that

' either;

1. The control valve or bypass position responds accordingly, or

2. There is a corresponding change in measured steam flow.

Once during the operating cycle for Unit 1, at a reactor pressure greater than 100 psig, each relief valve.shall be manually opened until thermoccuples downstream of the valve indicate steam flow.

000356 O

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REllEF REQUEST j

-RR V 30

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SYSTEM: Core Spray l VALVE (S): E21-F044A, B 2E21 F044A, B 1 I CATEGORY: . AC -

CLASS:. 2 l

L FUNCTIOR- Containment isolation for the Jockey Pump Minimum Flow Line l 1 i L TEST REQUIhrMENT: Reverse flow closure quarterly per. lWV-3520 j i

l BASIS FOR REllEr: The only safety related function of this normally open l

check valve is containment isolation. The only viable means of proving closure is by introducing reverse flow during the Local Leak Rate Tests. To perform this test  ;

quarterly would require removing the associated pump from i operation. Also, to perform this test during cold '

I shutdowns could delay the startup of tne unit.

ALTERNATE TESTING: Reverse flow closure each refueling outage during the l Local Leak Rate Tests, j l

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-THIS RELIEF REQUEST IS Si)NRSEDED BY REllEF REQUEST RR V 30A.

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REllEF REQUEST RR V 30A yR SYSTEM: Core Spray, RCIC, HPCI ,

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' VALVE (S): E21 F044A, B, E41 F021, E41-F022, E41-F040, E41 F046, E41 F049, E51 F001 E51 F002, E51-F021, E51 F028 E51.F040, 2E21-F044A, B, 2E41 F021, 2E41-F022, 2E41 F040, 2E41-F046, 2E41 F049, 2E51-F001, 2E51 F002, 2E51-F02),

2E51 F028, 2E51 F040 CATEGORY: C.

CLASS: 2 FUNCTION: Containment isolation Barrier l TEST REQUIREMENT: Reverse flow closure quarterly per IWV-3520 BASIS FOR RELIEF: These valves function as containment isolation barriers.

The only viable means of proving closure is by performing l a pressure test. To perform the tests quarterly would I require removing the associated systems from operation.

Also, to attempt to perform these tests during cold shutodwn could delay the startup of the unit.

r-~N. ALTERNATE TESTING: Reverse flow closure each refueling outage by performance

'd of a leak rate test similar to an Appendix J type test. j The use of such a test is in compliance with position 3 of j GL 89-04. -l 000356

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2 REllEF REQUEST p-~ RR V 31 i )

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SYSTEM: Containment Purge and inerting _

VALVE (S): 148-F342A l, 2T48-F342A L CATEGORY: A -

CLASS: 2 FUNCTION: Torus to Drywell Vacuum Breaker Test Valve and Air Line Containment l 1 solation j TEST REQUIREMENT: Exercise to prove closure and stroke time quarterly. i BASIS FOR REllEF: Energization of this normally closed solenoid valve by the I test switch allows air flow to the test _ cylinder, which l then moves the disc of the vacuum breaker check valve to the open position. When the test switch is released, the -l L solenoid valve closes tne air supply, the air cylinder '

depressurizes through the exhaust port, ana the check l valve disc closes. The open/ closure of the check valve is- '

verified by indicating lights; however, there are no' ,

positive means of verifying the closure of the solenoid '

valve or of performing stroke. time measurement.

L A ALTERNATE TESTING: Closure of the air supply by the solenoid valve is

('--) verified by closure of the check valve. If the solenoid a did not block the air supply when de-er.ergized the vacuum breaker check valve would remain open. However, the

closure time of the solenoid valve is independent of the closure time of the check valve and therefore cannot be measured.

In addition, closura of the solenoid valve is verified each refueling outage during Local Leak Rate Testing.

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REllEF REQUEST RR.V 32 >

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SYSTEM: TIP System .

VALVE (S): 2C51 F3012 ,

CATEGORY: A CLASS: 2 FUNCTION: Containment Isolation TEST REQUIREMENT: IWV 3413 requires that power operated valves be stroke timed. .

BASIS FOR fiLIEF: There is no way to determine the position of the valve other than indirect means,'i.e., flow measurement.

ALTERNATE TESTING: This valve will be exercised quarterly and the flow will be observed as an indirect means of determining stem position. .

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RELIEF REQUEST p RR V 33 m)

SYSTEM: Diesel Generator Air Start 1

VALVE: R43 F015A, B & C,,R43-F016A, B, & C CATEGORYi B .

CLASS: -

FUNCTION: Diesel Generator air start solenoids TEST REQUIREMENTS: Measure Stroke Time BASIS FOR RELIEF: These are three-way-solenoid valves mounted on the diesel generator (DG)-skid mounted package. They are in the DG air start line between the air receiver tanks and the air start manifolds. Since each generator has two tanks and two manifolds, the DG may start on air supplied by either or both tanks. The diesel generator test procedure verifies operability of each of these valves independently, on an alternating basis by isolating one air start header anc'. starting the DG from one header at a' time. Stroke time cannot be measured because there are no position indicatnre and visual observation is not possible 7 due to valve design. The total time from initiation to DG l operation is measured such that each valve's stroke time 1]

i is verified as acceptable. The DG start test is performed more frequently than required by Section X1 so that actual valve testing criteria are more limiting than Section XI reouirements.

ALTERNATE TESTING: Taese valves will be tested as part of the diesel generator air start test. Acceptable diesel generator '

start time will be used to verify' valve operability and acceptable stroke time, i 1 l l L GEORGIA POWER COMPANY HAS WITHDRAWN THIS REllEF REQUEST l SINCE TESTING OF THIS VALVE WILL BE ACCOMPLISHED IN A l

! MANNER SIMILAR TO THAT IN SECTION XI. HOWEVER, THE METHOD '

l OF TESTING AND MAJOR LIMITATIONS ARE INCLUDED IN THIS-PROGRAM FOR COMPLETENESS.

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REllEF REQUEST RR V 34

\f SYSTEM: Diesel Generator Air Start _

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VALVE: 2R43 F042A & C, and 2R43-F044A & C CATEGORY: B 5 CLASS: -

FUNCTION: Diesel Generator air start solenoids TEST REQUIREMENTS: Measure stroke time BASIS FOR RELIEF: ~These are three way solenoid valves mounted on the diesel generator (DG) skid mounted package. They are in the DG air start line between the air receiver tanks ard the air ,

start manifolds. Since each generator has two tanks and  ;

two manifolds, the UG may start on air cupplied by either  ;

or both tanks. The diesel generator test procedure '

verifies operability of each of these vi.lves independently, on an alternating basis, by isolating one air start header and starting the DG from one header at a time. Stroke time cannot be measured because there are no position indicators and visual observation is not possible  !

due to valve design. The total time from initiation to DG

!o j- operation is measured such that each valve's stroke time is verified as acceptable. The DG start test:is performed more frequently than required by Section XI so that actual valve testing criteria are more limiting than Section XI requirements.

ALTERNATE TESTING: These valves will be tested as part of the diesel generator air start test. Acceptable diesel generator start time will be used to verify valve operability and acceptable stroke time.

GEORGIA POWER COMPANY HAS WITHDRAWN THIS REllEF REQUEST SINCE TESTING 0F THis VALVE WILL BE ACCOMPLISHED IN A MANNER SIMILAR TO THAT IN SECTION XI. HOWEVER, THE METHOD OF TESTING AND MAJOR LIMITATIONS ARE INCLUDED IN THIS PROGRAM FOR COMPLETENESS.

000356

RELIEF REQUEST i <

RR V 35 O SYSTEM: HPCl System VALVE (S): E41-F048, E41 F057, 2E41-F048,:2E41-F057 1.

CATEGORY: C CLASS: 2 FUNCTION: - Lube Oil Cooler Check Valves TEST REQUIREMENT: IWV-3520 requires that check valves be exercised quarterly and disk movement verified by positive means.

BASIS FOR REllEF: These valves are exercised quarterly during pump testing, but a positive means of disk movement can only be verified during annual testing when the turbine bearing temperatures are allowed to stablize.

ALTERNATE TESTING: These valves will be verified to open annually during pump testing based on the turbine bearing temperature being within the acceptable limits.

O GEORGIA POWER COMPANY HAS WITHDRAWN THIS REllEF REQUEST.

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RELIEF REQUEST RR-V 36

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(V) SYSTEM: .TIP System

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. VALVE (S): C51-F3017, 2C51-F3017 j CATEGORY: AC- -

CLASS: 2 FUt4CTI0ti: Containment- Isol ation TEST REQUIREMEt1T: -Verify reverse closure quarterly per IWV-3520

BASIS FOR RELIEF

These normally open valves are located in the-containment and therefore are inaccessible during power operation. To attempt to perform these-tests during an unscheduled cold

shutdown could delay the startup of the unit, i l

l ALTERt1 ATE TESTitlG: Closure of these valves will be proven each refueling outage during Local Leak Rate lesting. ,

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REllEF REQUEST-RR-V 37 f3

)_ SYSTEM: All VALVE (S): AllCategoryAandACvalves6in, nominal. diameter}ndlarger CATEGORY: A, AC - .

CLASS: 1 and 2 FUNCTION: Containment and Pressure Isolation TEST REQUIREMENT: IWV 3427(b) requires that for valves 6 in, nominal pipe size and larger, if a leakage rate exceeds the rate determined-by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or greater, the test frequency shall- be doubled; the tests shall be scheduled to coincide with a cold shutdown until corrective action is taken, at I which time the original test trequency shall be resumed.

If tests show a leakage rate increasing with time, and a projection based on three or J. ore tests indicates that the leakage rate of the nex6 scheduled test will exceed the maximum permissible leakege rate by greater than 10%, the valve shall be replaced or repaired.  ;

BASIS FOR REllEF: -IWV 3427(b) is apparently attempting to predict the

/G failure of a valve based on gradual degradation that is o-d a trendable nature. This would apply to a valve where the seat, internals, etc. are wearing at a measurable rate, l and the eventuhl failure of the valve could be predicted from successive leakage tests.

However, historical data at Plant Hatch have demonstrated that, in general, valves do not exhibit gradually j increasing leakage rates as implied by IWV-3427(b). The l two general patterns of behavior for valves are: (1)- l essentially constant leakage rates followed by sudden I failure or (2) erratic test results which do not trend. l Therefore, trending as required by IWV-3427(b) does not i serve any useful function. l l

ALTERNATE TESTING: Valves with leakage limits exceeding the allowable limits I will be repaired or rer.. aced per IWV 3427(a).

l PER POSITION 10 0F GENERIC LETTER 89 04, THE TRENDING q REQUIRED BY IWB 3427(b) IS NO LONGER REQUIRED TO BE l PERFORMED. l l

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REllEF REQUEST i

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RR V 38

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l SYSTEM: CRD VALVE (5): C)) HCU ll4, 2Cll HCV ll4 --

I CATEGORY: C '.

. I CLASS: 2 FUrkTION: Scram Discharge Checks '

TEST REQUIREMENT: Verify forsard flow operability quarterly per IWV 3520.

l-l BASIS FOR REllEF: These valves are located on the scram discharge line of each CRD. Flow through each check valve is experienced only during the scram of the associated CRD unit. I ALTERNATE TESTING: Required flow is achieved through the valves during the l Technical Specification Control Rod Scram Insertion tests.

As a minimum, 10% of the CRDs on Unit I are scram timed on

a rotating basis every 16 weeks and 10% of the CRDs on Unit 2 are tested every 120 days, After each major refueling outage and prior to power operation, all operable control rods on Unit I shall be scram tested from m the fully withdrawn position. Following any ;eactor

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shutdown (Units 1 and 2) that is greater than 120 days, (d all control rods shall be scrarc, tested.

THE ALTERNATE TESTING IN THIS REllEF REQUEST IS SUPERSEDED BY GENERIC LETTER 89 04. THE TESTING OF THESE VALVES WILL BE PERFORMED IN ACCORDANCE WITH POSITION 7 0F GENERIC i LETTER 89 04.

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RELIEF REQUEST RR-V 39 SYSTEM: CRD VALVE (S): Cll F010A&B, Cll-Foll, Cll F035A&B, Cll F037 -

2Cll-F010A&B, 2Cll F0ll, 2Cll F035A&B, 2Cll F037 CATEGORY: B $

CLASS: 2 FUtiCTION: Scram discharge volume vent and drain valves

?EST REQUIREMEllT: Establish limiting values of valve stroke time and measure individual valve stroke time per IWV-3413.

BASIS FOR REllEF: A limiting value of stroke time etnnot be specifiec for the scram discharge volume vent and drain valves and they can not be individually stroked and timed. In order to prevent water hammer induced damage to the system during a full CRD scram, plant Technical Specifications require that system valve operation is adjusted so that the outboard vent and drain valves (F035ALB, F037) fully close at least five seconds after ::2 m pettive inboard vent and drain valve (F010A&B) during a full core scram. All valves must be fully closed in less than forty five (45) seconds for Unit 2 and sixty (60) seconds for Unit 2.

Also, the system is adjusted so that the inboard vent and drain valves (F010A&B, F0ll) start to open at least five seconds after each respective outboard vent and drain valve (F035ALB, F037) upon reset of a full core scram.

The valves are not equipped with individual valve control and cannot be individually stroke timed. Because of the adjustable nature of the valve control, individual valve stroke timing would not provide any meaningful information for monitoring valve degradation.

ALTERt1 ATE TESTING: The valves will be exercised quarterly and the total valve sequence response time verified to be less than Technical Specifications requirements.

4 00356

REllLF REQUEST RR-V 40 ,

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SYSTEM:

VALVE (S): C51 F3012 ,

CATECORY: A CLASS: 2 FUNC110ft: Containment isolation l TEST REQUIREMENT: IWV 3413 requires that power operated valves be stroke l timed.

1 BASIS FOR RELIEF: The valve is not equipped with remote position indicator  ;

and there are no other system provisions that could be I used to determine the position of the valve.

ALTERiiATE TESTING: The valve will be exercised closed each refueling outage and closure verified by means of Appendix J, lype C, local leak rate testing, i

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REllEF REQUEST RR-V 41 O SYSTEM: Plant Service Water

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VALVE (5): P4).F552A&C _

CATEGORY: C -

2 CLASS: 3 FUNCTION: Diesel Generator Discharge Line Check Valvec TEST REQUIREMENT: Verify for.sard flow operability quarterly for ikV 3520, 1

BASIS FOR REllEF: These normally closed check valves are located in the l cooling water discharge lines of diesel generators 3A and

10. There-are no system design provisions to verify forward flow operability-by flow rate measurement.

ALTERNATE TESTING: Each diesel generator is in operation for a minimum of one hour during diesel generator testing at least once per i quarter. . Partial forward flow operability is verified during the diesel generator testing by monitoring diesel 1 generator temperature. In addition, each diesel generator is operated for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at each refueling outage. l Forward flow operability is verified during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '

O test period by monitoring diesel generator temperature.

\j Acceptable operation of the diesel generators during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test period verifies that the valves have opened sufficiently to perform their design function.

000356 4

5.0 PUMP REllEF RE00ES1 LOG

' Relief Recuest Ellint ComenD RR P 1 Withdrawn RR P 2 Awaiting NRC Approval RR P 3 Awaiting NRC Approval -

RR P-4 Awaiting Nilt Approval -

RR P-5 Awaiting NRC Approval RR-P 6 (4 pages) Awaiting NRC App'roval RR P-7 Awaiting NRC Approval RR P-8 Withdrawn RR P 9 Withdrawn i  ; RR P 10 Withdrawn RR P-11 Withdrawn 0

000356 9

PUMP RLLIEf REQUE51

[ FR-P 1

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$YSTEM: RHR Service Water and Plant Service Water .

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Georgia Power Company has withdrawn this Relief Request since it is ne longer i

applicable. i l

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000953 i

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1 PUMP REllEr REQUEST <

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(v ) P *< P 2 l i

SYSTEM: Standby Licuid Control ,

l PUMP (S): C41 C001ALB, 2041 C001ALB CLASS: 2 I I I TEST REQUIREMENT: Table IWP 41101 requires that flow be measured within l 12 percent of full scale and IWP 3500 requires that the pump run a minimum of 5 minutet prior to taking data.

BASIS FOR REllEF: Instrumentation was not provided during construction to measure the required flowrate. Also, due to the size '

of the test tank the required 5 minute test cannot be ,

met. I i ALTERNATE TESTING: The system is pligned so that it forms a closed loop through the test tank. Flow is retirculated throJgh L l

the pump and tank until ct..ditions stablize, and i'len l 1

the system is realigned to perform the testing described below.

Flowrate is measured by the change in the standby l liquid control test tank level during a two minute test I g period. The standby liquid control (SBLC) is aligned l l so that ear: pump takes suction from a demineralized '

l water uurce and discharges through a throttle valve adjusted to obtain a reference discharge pressure. The level of the test tank is then measured and the pump is run for two minutes. After the two minute run, the tank level is again measured. Flowrate is then determined by the following equation.

Flow (gpm) = a Tank level fin,1 x 4.91001/in, 2 min.

l for a situation in which the flowrate is measured by l instrument, a 0 100 gpm instrument would normally be used for the SBLC pump flowrate of approximately 43 1 gpm. The required accuracy of this instrument would be l

12 percent or 12 gpm. This corresponds to a

! 10.4 inch / min water level ir, the test tank. Therefore, l the accuracy of the measured flowrate should be well within Code allowance.

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, d. 000953 I

PUMP REllEF REQUEST RR P 3 MSTEM: RHR Service Water, Plant Service Water, Standby Diesel Generator Service Water PUhPS: Ell C091A 0, P41 C001A D, 2E11-C001A-D, 2P41-C001A D, 2P41-C002 CLA55: 2 and 3 TEST REQUIREMENT: Table IWP 41101 requires that pressure be measured within 2 percent of full scale.

BASIS FOR RELIEF: No inlet pressure instrumentation is provided.

ALTERNATE TESTING: Inlet pressure is determined for this group by measuring the river level at the intakr structure. The differential pressure is then:

AP = Po + [(114.5 f t River Water Level) x 0.433) where AP is the differential pressure, Po the outlet pressure, and 114.5 ft. is the elevation of the discharge pressure gauge. This-method of measurement is well within the code requirements for the O determination of the differential pressure.

e 000953 O

I 7-~q PUMP RELIEF REQUES1 (J RR. P-4

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SYSTEM: Residual Heat Removal (RHR), RHR Service Water, Core Spray, j Plant Service Water, Standby Diesel Generator. 1 PUMP (S): Ell CO0lA D, Ell-C002A D, [21 C001A&B, P41-C001A D, 2 Ell-C001A D, 2 Ell 0002A D, 2E21-C001A&B, 2P41-C001A D, 2P41 C002. j 1

CLASS: 2 and 3  ;

TEST REQUIREMEl4T: Table IWP 31001 requires that the proper lubricant i level or pressure be observed.

BASIS FOR REllEF: This pump is lubricated by the process fluid that is being pumped.

ALTERf1 ATE TESTING: The applicable parameters in Table IWP 31001 will be measured. (See RR P 6) t 000953 i%

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,c PUMP RELIEF REQUE51 O RR P 5 I

' SYSTEM: Standby Liquid Control -

C41-C001A&B, 2C41-C001A&B 1 FUMP(S): )

CLA$S: 2 I 1

TEST REQUIREMENT: Table IWP 3100-1 requires that inlet pressure, I differential pressure, and flowrate be measured.

l BASIS FOR RELIEF: The standby liquid control pumps are positive i displacement pumps for which the differential pressure l is indeptndent from the inlet pressure. Therefore, inlet pressure and differential pressure are 1 inconsequential. No differential pressure or inlet pressure will be measured. l l

ALTERNATE TESTING: These pump tests will be performed by setting the discharge pressure equal to a predetermined reference value for each test, and then measuring the flowrate ,

and comparing it to acceptance criteria. l 1

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000953 l

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PUMP RELIEF REQUEST O SYSTEM: All

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PUMP (S): All CLASS: 2 and 3 TEST REQUIREMENT: Table IWP-3100 2 requirements for the allowable ranges of test quantities, applicable sections that reference Table IWP 3100 2, IWP 4500 Vibration Requirements, IWP 4110 Instrument Quality, IWP 4120 Instrument Range, and Bearing Temperature Requirements of IWP 4310 and Table IWP-31001.

BASIS FOR REllEF: IWP-3210 states that if these ranges cannot be met, the Owner may specify in the record of tests the reduced range limits that will allow the pump to fulfill its function. in addition experience has shown that IWP testing is not the most effective way to determine the mechanical condition of a pump. With the proposed testing described below, significant degradation of safety-related pumps should be detectel.

ALTERNATE TESTING: It is recognized in the industry that sibration testing is more indicative of pump mechanical cindition for certain pumps than hydraulic testing; tt.erefore, it is O. proposed that an enhanced vibration progtgm be used as the primary indicator of degradation. A tost program based on ASME/ ANSI OM 6 (1987) and recent industry experience will be used to perform velocity vibration measurements in scr. junction with hydraulic testing.

Details of this program are given in the following attachment.

000953 Page 1 of 4

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1 IES11NS METHOD 3t05f i i V) in lieu of the vibration requirements in Table IWP-31001, peak vibration velocity will b's used. Except for slow speed pumps less than 600 rpm, i velocity gives a better indication of pump mechanical condition than does  !

displacement. Hatch Nuclear Plant does not have any pumps that~will be tested l below 600 rpm. In the event testing of low RPM pumps becomes necessary, ,

displacement measurements will be used. .  ;

I VlBRATIONAL POINTS  ;

. 1 In lieu of the requirements of IWP-4510, broad band, peak vibration velocity  ;

measurements will be taken on each pump. l l a. On centrifugal pumps measurements will be taken in a plane approximately l perpendicular to the rotating shaft in two orthogonal directions. These ,

i measurements shall be taken on each accessible pump bearing housing. l L Measurements shall also be taken in the axial direction on each accessible pump thrust bearing housing, if no pump bearing housings are accessible due to pump design or physical interference, then the measurements will be taken at the accessible location that gives the best indication of lateral / axial rump vibration. This location is either on the pump casing, l

the motor bearing casing, or the motor casing.

b. On vertical line shaft pumps measurements will be taken in a plane  !

approximately perpendicular to the rotating shaft in two orthogonal directions in the area of the upper pump bearing housing (essentially l

lq < meeting Section XI). Thrust measurements will not be taken since d measurements on top of the motor would be of limited benefit and would i usually require installation of scaffolding due to the height of the assembly. Access would still be limited for several pumps, especially in the River Intake Structure, due to piping interference.

l It is recognized in the industry that the vibration testing of this type l of pump has been of limited benefit for degradation detection due to the problems ir.herent with the design of the pumps. As discussed in the l Hydraulic Para ter Acceptance Criteria degradation will primarily be id%tified through hydraulic testing using acceptance criteria that is j more stringent than Section XI.

c. On reciprocating pumps, a measurement will be taken on the bearing housing of the crankshaft, approximately perpendicular to both the crankshaft and the line of the plunger travel.

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000953 Page 2 of 4 l l

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l Vl%A110N INS 1RUMEN1 RANGl l x '

() In lieu of the Instrument Range requirements of IWP 4120, there will be no range requirements used dur .o the nature of the instrument. The adjustable 1

amplitude range selector determines the full-scale meter range.

l In lieu of the Frequency Response Range of IWP-4520 which requires a frequency i range of one half minimum speed to at least the maximum rotational speed, the l range will be from 1/3 rinimum speed (or less) to at least the maximum  !

rotational speed. 1

. l VlBRATION ACCEPTANCE CRITERIA )

In lieu of the acceptance criteria of Table IWP 3100-2, the following ranges will be used.  ;

Acceptable Alert Required Action l Pumn Tyne Ranoe Range Ranoe Centrifugal and 52.5Vr >2.5Vr to 6Vr >6Vr vertical deep or or draft * >.325 to .70 in./s ).70 in./s Positive $2.5Vr >2.5Vr to 6Vr >6Vr Divlacement C

• Small absolute changes in vibration for smooth running pumps (e.g.,

\ s 075 in./sec.) would potentially result in Alert and Required Action i Ranges being declared for exceeding the 2.5Vr or 6Vr limits even  !

though the pump is operating satisfactorily.

The Alert Range for smooth running pumps is >0.19 to 0.45 in./sec. and the Required Action Range starts at any value above 0.45 in./sec.

HYDRAULIC PARAMETER ACCEPTANCE CRITERIA In lieu of the Table IWP 3100 2 allowable ranges for flow and pressure, the ranges shown in the table below will be used.

Upper ranges have been expanded from 1.03 to 1.10, since the requirement to declare a pump inoperable when the pump performance exceeds the reference parameter by 3% is impractical. Combinations of individual instrument inaccuracies, hydraulic characteristics of each type pump, and inaccuracies associated with matching the reference point by throttling can result in exceeding the existing 3% limit without any degradation being experienced by ,

the pump. As an example, when testing the high flow / low head Plant Service Water Pumps at approximately 6500 gpm and 140 psi, the existing upper limit will allow a margin of 195 gpm but only 4 psi.

000953 Page 3 of 4 1

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3 .Thc alert range has been deleted for the centrifugal pumps to allum operatior '

) in a hydraulic window. Detection of degradation will be primarily

• accomplished through the use of the enhanced velocity vibration prograt TM lower required action parameter remains the same as for Section XI.

For vertical deep draft pumps, the lower values for the alert ind required action ranges are more stringent than the parameters in Section XI. Vibration testing of these type pumps has been showm by experience to be less meaningful than for other type pumps. Therefore, degr.adation will be identified through changes in hydraulic parameters.

For positive displacement pumps, the lower values for the alert and required action ranges are the same as those in Section XI.

Test Acceptable Alert Required i

Ouantity Ranae Ranae Action Ranae l

Epsitive Displacement Pumps l

P .93 to 1.lPr .90 to (.93Pr <.90 or >l.lPr Q .95 to 1.lQr .93 to <.950r <.93 or >1.10r Vertical Deep Draft pumps LP .95 to 1.ltPr .93 to <.95tPr <.93 or >1.1.Pr I \'

i Q .95 to 1.lQr .93 to <.950r <.93 or >l.10r Centrifuaal Puens LP .90 to 1.ltPr ......... <.90 or >1.1.'r )

Q .90 to 1.lQr ......... <.90 or >l.lQr BEARING TEMPERATURE MEASUREMENTS i

in lieu of the bearing temperature measurement requirement of Table IWP-31001

. and IWP-4310, the velocity vibration measurements and the hydraulic parameter l measurements will be taken. Continuous bearing temperature measurements of I continuously running pumps would be a good indicator of bearing wear.

l However, these pumps run intermittently and do not have installed I instrumentation to provide such readings. Industry experience has shown that l the once per year temperature measurement required by the Code has not proven l to.be beneficial in detecting pump degradation.

l The extended pump running time required to achieve the needed temperature stability could result in unnecessary wear on the pumps, and result in increased pump maintenance and repair. Deletion of this measu*ement will not have a significant affect on the pump monitoring program, since the other required test parameters are being measured.

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r~s PUMP REllEF RE0VEs1 RR P-7 SYSTEM: All PUMP ($'t loop Accuracy: All pumps

• Range: Ell C002A 0, E21-C001A&B 2 Ell-C002A D, 2 Ell C001 A&B CLASS: 2 and 3 TEST REQUIREMENT: IWP 4100 defines the required accuracy and full scale range for each instrument used to measure the test parameters.

BASIS FOR REllEF: Instrumentation is used which meets the acceptable instrument accuracies defined in Table lWP 41101.

L However, the total loop accuracy is not easily determined (there are several calculational techniques) and the total loop accuracy may fall outside the Code limits.

Also, in some speciff e cases the installed instruments have a range greater '. nan 3 times the reference value, o These include the O to 600 psig RHR outlet pressure is") gauges with reference values of approximately 160 to 180 psig, the O to 25.000 gpm RHR flow gauges with

! reference values of approximately 7500 gpm, and the O to 15 psig test pressure gauge used to measure inlet pressures ranging from about 4 to 7 psig.

The purpose of the Code range requirement is to ensure accurate readings so that the test is repeatable. The intent of this requirement is met in these cases.

ALTERNATE TESTING: The instrumentation used by Georgia Power Company to i measure pump operability parameters should provide data that is sufficiently accurate to allow assessment of pump condition and to detect pump degradation. In cases where it is determined by engineering that the instruments do not provide sufficient accuracy to assess pump degradation, additional test instrumentation will be used.

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.V 000953 L

l PUMi' REliti REQUE51 RR-P-8 j I

SYSTEM: Diesel Generators fuel Oil Transfer j

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Georgia Power Company has withdrawn this relief request since pump testing of this component will be accomplished in a manner similar to that in Section XI.

However, methods of testing and major limitations are described in this program for completeness.

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l 000953

PUMP REllir R!Dutsi RR P 9 SYSTEM: Diesel Generators fuel Oil Transfer ..

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i Ge+rgia Power Company has withdrawn this relief request since pump testing of this component will be accomplished in a manner similar to that in Section XI.

However, methods of testing and msjor limitations are described in this O

V program for completeness.

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i PUMP REllEr REQUEST

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0. RR P-10 SYSTEM: Diesel Generators Fuel Oil Transfer _

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Georgia Power Company has withdrawn this relief request since pump testing of this component will be accomplished in a manner similar to that in Section XI.

However, methods of testing and major limitations are described in this i

('N program for completeness.- i

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000953 I I

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i PUMP RELIEi REQUEST RR P-ll  ;

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SYSTEM: Diesel Generators Fuel Oil Transfer q i

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Georgia Power Company has withdrawn this relief request since pump testing of this component will be accomplished in a manner similar to that in Section XI.

However, methods Jf testing and major limitations are described in this l

Oi program for completeness.

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'O 000953 V

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I 6.0 COLD SHUTDOWt1 JUSTIFICAT10ti (CSJ) LOG

-s W Status Coment t CS 1 NRC Concurrence Requested .

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CS-2 NRC Concurrence Requested CS 3 NRC Concurrence Requested ,

CS-4 NRC Concurrence Requested '

CS S NRC Concurrence Requested  !

CS 6 NRC Concurrence Requested CS 7 NRC Concurrence Requested CS 8 Withdrawn i CS-9 NRC Concurrence Requested 1 CS 10 NRC Concurrence Requested i CS 11 NRC Concurrence Requested j CS 12 (2 pages) NRC Concurrence Requested 1

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l 100356 O

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COLD SHUTDOWN JUSTiflCAT10N

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SYSTEM: Reactor Recirculation System VALVE (S): 831-f03]A,B 2B31-f031A,B CATEGORY: B CLASS: 1 FUNCTION: Valves close to provide loop isolation QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time COLD SHUTDOWN TEST JUSTiflCATION: Closure during normal operation requires a reduction in power to trip the associated recirculation pump. Closure also creates a potential for exceeding the permissible temperature differential between the loops. In addition, the area is inaccessible during normal operation, which -

precludes an operator from manually opening the valve in case of actuator failure.

QUARTERLY PARTIAL

/N STROKE TESTING: None. The valve circuitry does not allow partial closure

\s_l . of the valve, COLD SHUTDOWN TESTING: Exercise and stroke time t

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9 000355 O

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COLD SHUTDOWN JUST1FICAT10N CS 2 7

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SYSTEM: Residual Heat Removal ..

VAYLE(S): Ell F008, Ell-F009, 2 Ell-F008, 2 Ell-F009 CATEGORY: A CLASS: 1 FUNCTION: RHR Shutdown Cooling Pressure Isolation QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time s

COLD SHUTDOWN TEST JUSilFICATION: These pressure isolation valves are interlocked to prevent valve epening during power operation. Therefore, they must be tested during cold shutdown conditions. >

QUARTERLY PARTIAL STROKE TESTING: None COLD SHUTDOWN TESTING: Exercise and Stroke Time T

000356 )

COLD SHUTDOWN JUSTlFICATION -

C5-3 v'

SYSTEM: Plant Service Water and Chilled Water System .

VALVE (S): D41-F049, P41-F050, 2P64-F045, 2P64 F047 CATEGORY: A CLASS: 2 FUNCTION: Drywell Air Cooler Containment Isolation QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time COLD SHUTDOWN TEST JUSTlFICATION: Closure of this valve would totally interrupt flow to the the drywell coolers or the cooler condensers. This interruption may cause an increase in drywell temperatures which would require removing the unit from operation.

QUARTERLY PARTIAL STROKE TESTING: None. The valve circuitry does not allow partial closure l

of this valve.

. (3 V COLD SHUTDOWN l l TESTING: Exercise and Stroke Time L

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i COLD SHUTDOWN JUSTIFICATION CS 4 (3

N,j SYSTEM: Plant Service Water ..

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VALVE (S): P4. F310A D, 2P41-F316A D CATEGORY: B CLASS: 3 FUNCTION: Turbine Building Supply Shutoff QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time COLD SHUTDOWN TES1 JUSTiflCATION: Closure of these normally open valves during power operation would interrupt flow to the turbine building equipment normally cooled by service water.

QUARTERLY PARTIAL STROKE TESTING: None. The valve circuity does not allow partial closure j of this valve. j COLD SHUTDOWN )

/"T TESTING: Exercise and Stroke Time '

000356 O

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CC D SHUTDOWN JUSTlflCATION I CS 5 SYSTEM: Reactor Building Closed Cooling Water (RBCCW)

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VALVE (S): P42-F051 P42-F052, 2P42 F051, 2P42 F052 CATEGORY: A CLASS: 2 FUNCTION: RBCCW to Recirculation Pumps Containment isolation QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time COLD SHUTDOWft TEST JUSTIFICATION: Closure of these normally open valves would shut of f the cooling water flow to the reactor recirculation pumps which could result in possible damage-to the pumps.

QUARTERLY PARTIAL STR0KE TESTit1G: None COLD SHUTDOWN TESTING: Exercise and Stroke Time O

0 000356

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COLD SHUTDOWN JUSTIFICAT10tl i

CS 6 SYSTEM: MS!V Leakage Control System =

VALVE (S): 2 E32- F001 B., F , K, P 2E32-F002B.F,K,P 2E32-F003B.F,K,P 2E32 F006, 2E32-F007, 2E32 F00&, 2E32-F009 CATEGORY: .A/B CLASS: 2 FUNCTION: MSIV Leakage Control QUARTERLY TEST F +.ar. MENT: Exercise and Stroke Time

'+ 00WN

(' , , U , t lCAT 10ft : These valves are interlocked to main steam line pressure

'and cannot be operated with norma' operating steam line pressure.

Opening these valves during normal operation with an inadvertent opening of the second inline motor operated valve could cause extensive damage to downstream low pressure components.

QUARTERLY PARTIAL STROKE TESTING: None COLD SHUTDOWN TESTING: Exercise and Stroke Time.

0003S6 O

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COLD SHUTDOWN JUSTIFICAT10f4 CS 7 SYSTEM: HPCI VALVE (S): E41 F002, 2E41-F002

[51-F007, 2ESI-F007 CATEGORY: A CLASS: 1 FUNCTION: HPC1/RCIC Steam Supply Containment Isolation QUARTERLY TEST REQUIREMENT: Exercise and Stroke Time COLD SHUTDOWN TEST JUSTIFICAT10fi: F)ilure in the closed position during t0 sting would ender the entire system inoperable with entry i'ito the containment required for repair.

QUARTERLY PARTIAL STROKE TESTINGL: None COLD SHUTDOWN TESTING: Exercise and Stroke Time 4

0 0003S6

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COLD SHUTDOWN JUSilFICATION CS E SYSTEM: Core Spray VALVE (S): Ell-F122A&B,E21F037ALB,2 Ell-F122A&B,2E21-F037AL5-CATEGORY: A i CLASS: 1 FUNCTION: Valve (2)E21 F006A&B Bypass QUARTERLY TEST REQUIRrMENT: Exerci.se and Stroke Time COLD SHUTDOWN TEST JUSTlFICATION: This valve is a pressure isolation valve and cannot be opened during normal operation since the low pressure piping could become over pressurized.

QUARTERLY.PARTlAL STROKE TESTING: None COLD SHUTDOWN TESTING: Exercise L-d Stroke Time O

THIS COLD SHUTDOWN JUSTIFICATION HAS BEEN WITHDRAWN BY GEORGIA POWER COMPANY. THESE VAtVES ARE PASSIVE PRESSURE ISOLATION VALVES AND EXCRCISING AND STROKE TIMING 15 NOT REQUIRED BY ASME SECTION XI.

9 000356 O

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[4 c ll7 COLD SHUTDOWN JUSTlFICATION a; x M

gv CS-9 J-SYSTEM: Main Staam

VALVE (S): 'B21F022AD,B21F028AD,2B21-F022AD,2821-F028Ad' 1 CATEGORY: A

!- CLASS: 1 FUNCTION: Main Steam Isolation Valves QUARTERLY TEST-REQUIREMENT: Exercise and Stroke Time E COLD SHUTDOWN

-TEST JUSTIFICATION: Full stroke testing these valves during normal reactor i operation requires isolating one of the four main stean  ;

iines. Isolation of these lines results in primary l sptem pressure sp1kes, reactor power fluctuations, and- j l increased flow in the unisolated . steam lines. This I unstable operation can lead to a reactor scran, and as R discessed in NUREG-06?S, pressure transients esulting from full stroke testing MSIVs increase the chances of i actuating primary system safety / relief valves. Also, .,

A stroking these valves during power operation requires j s

l- decreasing the unit to 75% power, therefore, resulting in

.a substantial capacity factor loss prior to, during, and' after the test. j l QUARTERLY PARTIAL l L STROKE TESTING:- Yes  ;

COLD : SHUTDOWN i TESTING: Exercise and stroke time i- i l

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COLD SHUTDOWN-JUSilFICATION CS 10

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SYSTEM: . Nuclear Boiler (Feedwater) .

VALVE (S): 2B21 F077A&B ,

CATEGORY: AC CLASS: 1 FUNCTION: .Feedwater Containment isolation QUARTERLY: TEST REQUIREMENT: Closure COLD SHUTDOWN TEST JUSTlFICATION:- These check valves cannot be closed against feedwater flow during normal operation. To test these valves during power operation would require removing 50% of feedwater flow to the reactor.

. QUARTERLY PARTIAL

-STROKE TESTING: None COLD SHUTDOWN These normally open feedwater check valves have an air-O TESTING:

assist for tight closure anri position indicating lights.

Closure will be proven each cold shutdown, but not more frequently:than once per 3 months, by observing the' indicating lights.

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COLD SHUTDOWN JUSTiflCATION-05 11 m -

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- SYSTEM: Nuclear Boiler (Feedwater) r VALVE (S): 2B21-F076A&B ,-

.: CATEGORY: C

( CLASS: 2 5 FUNCTION:'- Feedwater Isolation QUARTERLY TEST g_ REQUIREMENT: Closure

(: COLD SHUTDOWN TEST JUSTIFICATION: These check valves cannot be clor.ed against feedwaisr flow during normal operation. .To test these valves p during power operation would require removing 50% of=

- feedwater flow to the reactor.

E -QUARTERLY PARTIAL' g . STROKE ~ TESTING: None

= COLD SHUTDOWN ,

TESTING:- These normally open feedwater check valves have an. air assist for tight closure and position indicating lights.

Closure will be proven each cold shutdown, but not more =

frequently than once per 3 months, by observing the indicating lights.

000'356 m

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COLD.SHU100WN JUSTIFICATION i

-T. CS 12

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SYSTEM: Reactor Water Cleanup System (RWCU)

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VALVE (S)i- G31 F001, G31-F004- .

2G31 F001,'2G31-F004 L CATEGORY: A' CLASS: 1

!; FUNCTION: RWCU Pump Suction Isolation Valves l

l: QUARTERLY TEST.

L REQUIREMENT: Exercise and Stroke . me Closed L

l- COLD SHUTDOWN ll REQUIREMENT: The RWCU System .s in operation during norma.i. pleat operation in order to maintain reactor cooiant themis;ry

!- within Technical Specifications limits. The isolation valveso are open whenever RWCU System is in operation supplying reactor coolant as pump suction source for processing and eventual return to reactor coolaat inventory. Exercising and stroke timing these ulves quarterly requires the entire RWCU System to be aken out lfN

!- of service which could result in the degrM ed chemical-l- ()

L makeup of reactor coolant and subjects the antiri RWCU System to unnecessary transients. These= unnecessary I transients could lead to degradation and failure of other L related -system components (e.g., pumps, valves, l' demineralizers) and the' potential loss of the system L availability which could-cause required shutdown.

Exercising and stroke timing these valves-also results in ,

undue hardships and exposure limits to personnel involved i in.the actual surveillance activity. The steps necessarj te exercise and stroke time these valves are briefly described below. ,

1. Take RWCU Demineralizers out of service.

2. Trip operating RWCU Pump.

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3. Exercise and stroke time valves closed.

4. Align system valves to required position for system to be placed inservice with reactor at operating l

conditions.

000356 V

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CS 12 (Cont'd)

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5. Restart RWCU Pump. (Standard p1 ant practice is to position operator in pump room to monitor start.

RWCU pumps are located in a High. Radiation Area

.and Health Physic,s escort is required.)

6. After pump is restarted and system flow stabilizes,

, the demineralizers are returned to service.

NOTE: RWCU System is normally put into service prior to reactor ,

startup. Returning the system to service with reactor at '

normal operating conditions poses the potential for a system auto-isolation which results in additional work of having to backwash the demineralizers before_ returning them to service.

QUARTERLY PARTIAL STROKE TEST!!:G: None. The system logic does not allow partial closure of these valves.

' COLD SHUTDOWN l- TESTING: Exercise and stroke time, 1O 000356 L.O 1

720 GEr/ERAL'REllEr RE0 VEST LOG 4

Relief Reouest.

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RR G 14 NRC Approval Requested ... l 1

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GENERAL REllEF REQUEST SYSTEM: All Incorporation of changes in etsign, testing, and procedures without any unreviewed safety questions into the Inservice Testing Program /Pl ans.

TEST REQUIREMENT: 10 CFR Part 50.59 allows changes to a nuclear facility _ and procedural changes in accordance with Plant Technical Specifications and the safety analysis report, without prior approval from the NRC, provided there are no unreviewed safety questions. The facility's Inservice Testing Program / Plan should be revised to include these changes.

Changes such as valve operator, stroke times, pump performance, etc., made in compliance with 10 CFR 50.59, which affects the ASME Section XI requirements may not be shown on the existing revision of the IST Program / Plans documents.

Relief is requested from thi!, inconsistency.

BASIS FOR RELIEF: Records o~ these changes will be maintained and changes in ASME Section XI requirements pertaining to these changes will

^9 -be complied with. However, a revision to the IST Program / Plans for every minor change is an unrealistic, costly, and time consuming task. Any delay in revising the IST Program / Plans will not endanger public health and safety.

ALTERNATE.

TESTING: Records of all changes will be maintained. Changes affecting ASME Section XI requirements will be incorporated into the IST Program / Plans whenever a need for their update is warranted.

NOTE: This relief request was formerly identified as " Relief Request 8.1.3" in the 151 Program, it is'merely being rastated as it applies to the IST Program.

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