ML19345F247
| ML19345F247 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/27/1981 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML19345F246 | List: |
| References | |
| PROC-810127, TAC-07811, TAC-08019, TAC-7811, TAC-8019, NUDOCS 8102170013 | |
| Download: ML19345F247 (65) | |
Text
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EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 RESPONSE TO THE PROVISIONS OF
.3 CFR 50.55a(g)
" INSERVICE INSPECTION PROGRAM" l
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810'2170010 a
TABLE OF CONTENTS
- 1. 0 Introduction.
1-1 2.0 Inservice Inspection for 2-1 Code Class 1 Components...........
3.0 Inservice Inspection for Code Class 2 Components...
3-1 4.0 Inservice Inspection for Code Class 3 Components.
4-1 5.0 loservice Testing of Pumps...........
5-1 6.0 Inservice Testing of Valves..................
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1.0 INTRODUCTION
1 l _. _l, General This document describes the new Inservice Inspection Program for Edwin I. Ha tch Nuclear Plant, Unit No.1.
The original ISI program for hatch-l was prepared in accordance with the ASME Boiler and Pressure Vessel Coda, 1971 Edition, including the Summer 1972 Addenda for Class I components.
Class 2 components were limited to the Main Steam and Turbine Steam Bypass Gystems. Class 2 components were scheduled for examination in accordance with the Winter 1972 Addenda of Sectior, XI.
4 The new inservice inspection plan is an upgrading of the program to meet I
the examination requirements of the 1974 Edition of Section XI, including Addenda through the Summer,1975.
1.2 Effective Date i
The new ISI plan shall go into effect at the start of the second 40-month period of plant commercial operation. The effective date is April 30, 1979 1.3 Scope This document is a description of the ISI program for Unit 1 of Plant Hatch.
The programs for Ciass 1, 2, and 3 component examinations and for pump and valve surveillance testing are included.
i 1.4 Component Upgrading i
All plant components have been reviewed to determine the appropriate classifi-l cation for inservice inspection. Regulatory Guide 1.26 was used for guidance in determining component classifications.
It must be noted that the classification of components as ASME Clast 1, 2, or 3 equivalent for inservice inspection does not imply that the com-ponents were designed in accordance with ASME requirements. The component design codes renain as stated in the FSAR.
L l.5 Subsequent ISI Plan Revisions In accordance with the existing regulations of 10CFR50.55a, the inservice examination program for Class 1, 2, and 3 components will be reviewed near l
the end of each 40-month interval. At that time the plan will be modified as required to bring it into compliance tith the latest NRC-approved version of Section XI. The inservice testin; program for pumps and valves will be
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similarly reviewed and modified every 20 months.
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1.6 Res ponsibil i ty i
Georgia Power Company bears the'overall responsibility for the performance i
of the inservice examinations. Certain non-destructive examinations will be performed by a qualified examination agency. The results of such examina-tions will be reported to Georgia Power Company for final evaluation and
,~
i dis positio n. 1 L '_ _ LO"
l.7 Records Records and documentation of all information and inspection results, whicn provide the basis for evaluation and wh ch facilitate comparison with re-sults from previous and subsequent inspections, will be maintained and available for the active life of the plant in accordance with Section XI, IWA-6000.
1.8 Methods of Examination The method of examination planned for each area is delineated in subsequent sections. Personnel performing NDT examinations will be trained in accord-ance with the American Society for Nondestructive Testing (ASNT) " Recommended Practice SNT-TC-1 A, Supplements and Appendices", as applicable for technique and method used.
1.8.1 Ul trasonic It is anticipated that most volumetric examinations will be performed ultra-sonically. Examinatiors will be conducted in accordance with the require-ments of ASME Section XI and Section V as appropriate.
1.8.2 Radiographic Radiographic techniques will be used to supplement UT as required.
1.8.3 Liquid penetrant Dye penetrant examinations will be performed whenever a surface examination is required on non-magnetic piping.
1.8.4 Magnetic Particle Magnetic particle tests will usually be used when surface examination of carbon steel components is required.
1.8.5 Visual A visual (VT) examination is employed-to provide a report of the general condi-tion of the part, component, or evidence of leaking.
1.9 Repair Procedures Repairs to the pressure retaining boundary of ASME Class 1, 2, or 3 (equiva-lent) components will be performed in accordance with IWA-4000 by utilizing Georgia Power Company approved procedures which' generally comply with the code applicable to the construction of the component.
J 1-2 jla L., '
l 2.0 INSERVICE IMSPECTION FOR CODE CWS 1 COMPONENTS Table 1 provides a tabulation of the Class 1 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Summer 1975. These components will be inspected in accordance with the requirements of Subsection IRB tc, the extent practical. This tabulation identifies the components to be inspected, tne Section XI examination item and category, area to be examined, and the method cf examination. Where release from the inspection 1
requirements of Subsection IWE is requested, information is provided which identifies the applicable Code requirenents, justification for the release requested, and the inspection method to be usud as an alternative. Table IW3-2600 items not applicable i
to the Edwin 1. Hatch Nuclear Plant-Unit 1 have also been listed and identified i
in the interest of completeness. Items applicable to pressurized water reactors only, such as steam generators and pressurizers, have been omitted entirely.
Some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased. However, i
these components will be inspected in accordance with the requirements of Subsection IWB to the extent practicable. The repair procedures of IWB-4000 will be applied to those components constru' ted to Section III of the ASME Code.
For those e
components not constructed to Section III of the ASME Code, the rules of IWA-4000 i
will be applied.
Hydrostatic testing will be conducted in a manner that will satisfy the require =ents i
of IWA-5000 and IWB-5000. Where adjoining pipe sections have different tast pressures, they will be separated whenever practicable and each section ter.ted at its specified pressure. Where it is not practicable to separate adjoining t
sections of piping (e.g., boundary is check valve), the sections will be tested 1
together at the lower of the specified test pressures.No point in the piping shall be permitted to experience a pressure greater than the specified test pressure.
d Components that are exempted from volumetric and surface examination by IWB-1220 vill be hydrostatically tested per the requirements of IWA-5000 and IWB-5000.
2.1.1 Hydrostatic Testine 2.1.1.1 Requirements from which Relief is Recuested a.
IWB-5000 requires that hydrostatic tests be performed at a test temperature of j> 1000F. Relief is requested from this requirements for all Class 1 systems except for the Nuclear Boiler System which is restricted by fracture toughness re quirements.
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b.
Test pressure and tempe.ratr-a is required to be held for four hours prior to performing the examination. Kelief is requested from this time interval for non-insulated piping.
2.1.1.2 Justification Hydrostatic testing at a test temperature of 2[100 F would require insulation 0
a.
removal, installation of permanent or temporary heat tracing on the lines to be tested, and the replacement of the insulation. This procedure would prove to be an undue hardship without a compensating increase in the level of safety.
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j b.
The t.ime duration of four hours for hydrostatic testing on non-insulated piping is excessive. All later Addenda to the 1974 version of Section XI and the 1977 version of Section XI differentiate between insulated and non-insulated piping for determining the test duration.
2.1.1.3 Testing in Lieu of Section XI Requirements a.
The piping contract for Plant Hatch specified that the hydrostatic test pressure be performed at 700F plus the nil ductility factor. This factor has been determined to be a negative number for the piping at Plant Hatch.
Therefore, the test temperature for hydrostatic testing will be 2 700F.
b.
The test pressure and temperature for insuisted piping will be held for four hours prior to system walk-down examination. For non-insulated piping it will be held for ten minutes before walk-down.
4 2.1.2 Hydraulic Shock Suppressors for Class 1 Piping. Pumps. and Valves 2.1.2.1 Recuirement From Which Relief Recuested j
Table IWB-2500, Category B-K-2 requires visual examination of all support com-ponents and verification of support settings of snubbers and shock absorbers once per inspection interval. Relief is requested from verification of snubber settings.
2.1.2.2 Justification The hydraulic shock suppressors on Class 1 systems sre currently subjected to an ongoing inspection and testing program detailed in the plant Technical Specifica-tions. This program is designed to demonstrate continued operational readiness and structural integrity of the shock suppressors and exceeds the requirements of lg Table IWB-2500.
I 2.1.2.3 Testing in Lieu of Section T.I Requirements Hydraulic shock suppressors will be inspected and tested in accordance with Technical Specification requirements.
2.1.3 ASME Class 1 (Equivalent) Valves Exceeding 4-Inches Nominal Pipe Size i
2.1.3.1 Recuirement From Which Relief Requested Table IWB-2500, Category B-M-2, and Table IWB-2600, Item B6.7 require visual examination of the internal pressure boundary surfaces of one valve in each i
group of valves of the same design, manufacturing method, manufacturer, and function to be performed once per inspection interval.
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1 2.1.3.2 Justification 0?sassembly of these valves solely for visual inspction during inspection p
interval, in absence of other required maintenance,. presents an unnecessary exposure to radiation and contamination and Ln excessive expense.
The opening, visual inspection, and closing of these valves would require an expenditure of approximately2to3 man-rempervalve.13yighcontaminationlevelsproduce 1
airborne activities of 6 to 10 MPC of I which requires the use of in-line or constant-flow respiratory equipment.
Dose rates from the disassembled valves are typically 0.5 R/hr gamma and greater than 200 R/hr beta.
Valves on the recirculation loop suction piping would require off-loading the fuel elements and draining the reactor prior to disassembly. Work on recircu-lation pump discharge valves and RHR injection valves would require installation l1 of plugs in the jet pump risers.
Preparatory work of this scope is considered impractical for the sole purpose of conducting a visual examination.
Contamina-tion levels in the valves associated with the recirculation loops are particu-larly high due to the physical location of these valves at the bottom of the system.
During routine maintenance, the valve body internal surfaces are visually examined. Many of these valves, particularly the containment isolation valves, are disassembled for maintenance of leak-tightness.
Disassembly of other Class 1 valves solely for internal inspection is counter to the "ALARA" guide-1 lines to keep the occupational dose rates as low as reasonably achievable.
In view of the cost in dollars and man-rem, and in view of the minimal benefits obtained, we conclude that this code requirement does not provide sufficient benefits to justify such expenditures.
2.1.3.3 Alternate to Section XI Requirement Class 1 valves exceeding 4 inches nominal pipe size are subjected to visual inspection of the internal surfaces of the valve body when disassembled for maintenance.
The coverage provided by inspections during routine maintenance coupled with periodic leak tests and hydrostatic tests will provide adequate assurance of the structural integrity of the Class 1 valve bodies, while keeping exposure to radiation and contamination as low as reasonably achievable.
2.1.4 Flued Head Penetrations 2.1.4.1 Requirements for Which Relief Requested l
Table IWB-2500, Category B-J and B-K-1 requires the examination of circumfer-cotial butt welds and integrally welded pipe supports, that are located within i
flued head containment penetration assemblies.
These welds and their penetra-tion assembly number are listed below.
1 Penetration No.
Weld Identification No.
X-9A B21-FW-18A-7A X-9B B21-FW-18B-6A Amendment 1 4/79 2-3 Amendment 2 9/80
Penetration No.
Weld Identification No.
X-10 E51-RCIC-4-00T-20A x-11 E41-HPCI-10-0VT-15 A X-12 E11-RHR-20-E-Discharge-13A X-13A E11-RHR-24-A-Return-3A 1
X-13B E11-RHR-24-B-Return-3B X-14 G31-RWCU-6-0VT-15B X-14 G31-RVCU-6-0VT-150 X-16A E21-CORE SPRAY-10-A-3A X-16B E21-C01E SPRAY-10-B-4A X-17 E11-RHR-4-HS-6A 2.1.4.2 Justification These welds are inaccessible for examination due to the design of the flued head.
All of the twelve circumferential butt welds, except for two located in the RWCU penetration, are caroon steel and not subject to intergranular stress corrosion cracking (IGSCC).
Two stainless steel welds that are located in the RWCU penetration were made to rerlace a Type 304 55 pipe that had undergone IGSCC. They are a flued head with a Type 308L overlay ( > 5% ferrite) on the inside surface to a Type 304L solution annealed pipe ( <.035% carbon), and a Type 304L pipe-to-pipe weld. These welds were made in accordance with the guidelines of NUREG-0313 to minimize susceptibility to IGSCC.
2.1.4.3 Testing in Lieu of Section XI Requirements A UT baseline was run for each new weld while the weld was accecsible during U ' repair to enstre a high quality weld.
In accordance with IWB-5221 a system leakage test is to be performed prior to startup following each reactor refueling outage. This is the same type test that detected the crack in the original pipe.
Whenever the process piping to flued-head weld (outside containment) is volumetrically inspected, the accessible weld of the flued-head penetration 2
will have a surface examination performed on it.
2.1. 5 Control Rod Drive Housinas 2.1.5.1 Recuirements for Which Relief Requested 1
Table IWB-2500, Category B-0 requires examination of the pressure-retaining welds in the peripheral control rod drive housings.
Each housing has one upper weld located near the reactor vest.el bottom head and one lower weld 10-cated at the housing flange.
Amendment 1 4/79 2-3a Amendmen'. 2 9/80
2.1.5.2 Justification Because of the proximity of the upper weld to the vessel, the dose rate is too high to permit examination of this weld.
Dost rates are typically 20 to 30 R/hr and an examination would expend 10-15 m.n-rem per housing.
The lower welds are inaccessible for examination because of the location and design of the housings.
Physical accessibility by an inspector is extremely 1
limited by the close proximity of the housings to each other and by the sup-port arrangement.
Also, the insert and withdraw lines to the CRD are connec-ted at the top of the housing flange and prevent access to much of the weld.
The combination of these factors prevents these welds from being examined.
2.1.5.3 Testing in Lieu of Section XI Reouirements These welds are located within the hydrostatic test boundary of the Nuclear Steam Supply System.
Therefore, they will be tested per IWB-5000.
There are no other alternate means of testing available for these welds.
2.1.6 Piping Pressure Boundary Welds 2.1.6.1 Requirements from Which Relief is Reouested Table IWB-2600, Category B-J (Items B4.5 and B4.6) and Category B-K-1 (Item B4.9), requires the volumetric examination of pressure-retaining piping welds.
Relief is requested from performing an examination where the weld is in-accessible, or the geometric configuration prohibits a full-Code inspection.
2.1.6.2 Justification The arrangements and details of the piping systems and components are such that some examinations (as required by IWB-2600) are limited due to geometric configuration or accessibility.
Generally, these limitations exist at pipe-to-2 fitting welds, where examination can be fully performed only from the pipe side, the fitting geometry limiting or even precluding examination from the opposite side.
Welds having such restrictions will be examined to the extent practical.
However, all welds examined during the preservice examination were fully Code inspectable.
Since hangers or other obstructions may have been added after the preservice examination, examination limitations may be encountered during the performance of the ISI weld examinations.
The results from Hatch Nuclear Plant Unit No. 2 show that a full-Code examina-tion can be performed on 98 percent of the B-J welds, 81 percent of the B-K-1 welds (Valves and Piping), and 50 percent of the B-K-1 welds (Pumps).
Similar results are expected for Unit 1.
Relief will be requested at the time any weld is found not to be fully Code inspectable as provided by 10CRF50.55a(g).
Amendment 1 4/79 2-3b Amendment 2 9/80 1
')
TABLE I
'S1 PROGRAM FA ASME CDs CLASS 1 COMP 0 NEWTS P
Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Item No.
Ca tenory__
Description Area to be Examined Examina tion Recuested 81.1 B-A Reactor Vessel Circumferential and vertical Volumetric No welds in the core belt area Bl.2 B-B Reactor Vessel Circumferential and vertical Volumetric No welds in other than core belt area and meridional welds in bottom head torus, bottom head dome, and close head Bl.3 B-C Reactor Vessel Vessel-to-flange and head-to-Volumetric No flange circumferential welds Bl.4 B-D Reactor Vessel Primary nozzle-to-vessel welds Volumetric No and nozzle inside radius
- na l=
sec tion Bl.5 B-E Reactor Vessel Vessel penetrations: control Visual (IWA-No rod drives instrumentation 5000)
Bl.6 B-F Reactor Vessel Nozzle-to-safe-end welds Covered by INB-No 2600 Iten 84.1 81.7 B-G-1 Reactor Vessel Closure studs, in place See Note 1 No Closure Head Bl.8 B-G-1 Reactor Vessel Closure studs and nuts re-See Note 1 No Closure Head moved E
Bl.9 B-G Reactor Vessel Ligaments between threaded Volumetric No stud holes Ek Bl.10 B-G-1 Reactor Vessel Closure washers, bushings Visual No Closure Head os Bl.ll B-G-2 Reactor Vessel Bolting less than 2 inches
-lisuss No h
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h TABLE 1 (Cont'd) 4 Table Table IWB-2500 Method of Code Relief IWB-2600 Examination System or Component Item No.
Category Description Area to be Examined Examination Requested t
[
Bl.12 B-ll Reactor Vessel Bottom head torus to support Volumetric No skirt Bl.13 B-1-1 kc o-tor Vessel Not applicable See Note 2 No Close e llead 81.14 B-I-1 Reactor Vessel Vessel cladding Visual.
See No Note 3 Bl.15 B-N-1 Reactor Vessel Vessel interior Visual No Bl.16 B-N-2 Reactor Vessel Integrally welded core Visual No support structures and in-terior attachments 7
en Bl.17 B-N-3 Reactor Vessel Not applicable (applies to Not applicaole No PWRs only) 81.18 B-0 Reactor Vessel Control rod drive heusings Volumetric. See Yes l1 Note 10 B1.19 B-P Reactor Vessel Exempted components Visual (IWA-5000) No B4.1 B-F Piping Nozzle-to-safe-end welds Volumetric and No I-surface 2,
er B4.2 B-G-1 Piping Pressure boundary bolting Not applicable.
No greater than and equal to 2 See Note 4.
inches diameter (in place) os g o
B4.3 B-G-1 Piping Pressure boundary bolting Not applicable.
'40
(
greater than and equal to 2 See Nota 4.
s inches diameter (removed)
~84.4 B-G-1 Piping Pressure boundary bolting Not applicable No
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greater than and equal to 2
'~
u) inches
5 U
TA..d 1 (Cont'd) y Table Table IWB-2500 D:3-2600 Examination System or Component fsethod of Code Relief I tc? i:o.
Ca teeo ry_
Description Area to be Examined Examinatien Requested B4.5 B-J Piping Circumferential and longitud-Volumetric Yes.
inal welds See flote 7.
84.6 B-J Piping Branch connection welds Volumetric f;o greater than 6 inches diameter B4.7 B-J Piping Branch connection welds six Surface tio inches diameter and smaller 84.8 B-J Piping Socket welds f;ot applicable.
fio See flote 5.
B4.9 B-K-1 Piping Integrally welded supports Volumetric fio y
B4.10 B-K-2 Piping Support components Visual Yes See flote 9.
e B4.11 B-P Piping Exempted components Visual (IWA-tio 5000)
E4.12 B-G-2 Piping Pressure-retaining bol ting.
Visual flu Bolting less than 2 inches diameter B5.1 B-G-1 Pumps Pressure-retaining bol ts and Volumetric fio 1p studs greater than and equal to 2 inches (in place) a%
w B5.2 B-G-1 Pumps Pressure-retaining bolts and Volumetric &
fio studs greater than and equal Surface o
to 2 inches (when removed)
B5.3 B-G-1 Pumps Pressure-retaining bolting Visual fio and studs greater than and equal to 2 inches
t LE 1 (Cont'd) ll Table Table IWB-2500 IW3-2600 Examination System or Component Method of Code Relief Item No.
Ca tego ry,_
Description Area to be Examined Examination Requested _
B5.4 B-K-1 Pumps Integrally welded supports Volumetric No B5.5 B-K-2 Pumps Support components Visual Yes See Note 9.
B5.6 B-L-1 Pumps Casing welds Not applicable.
No See Note 6.
B5.7 B-L-2 Pumps Casings Visual Yes.
See Note 8.
B5.8 B-P Pumps Exempted components Visual (IWA-No 5000)
B5.9 B-G-2 Pumps Pressure-retaining bolting Visual No s,
if less than 2 inches B6.1 B-G-1 Valves Pressure-retaining bolting Volumetric No greater than and equal to 2 inches diameter (in place) 86.2 B-G-1 Valves Pressure-retaining bol ting Volumetric No greater than and equal to 2 inches diameter (removed)
B6.3 B-G-1 Valves Pressure-retaining bolting Visual No greater than and equal to 2 inches diameter on
=r E
B6.4 B-K-1
. Valves Integrally welded supports Not Applicable.
No See Note 11.
e k
B6.5 B-K-2 Valves Support components Visual Yes.
See Note 9.
J o'
C5.6 B-M Valves Casing welds Not Applicable.
No See Note 6.
'i TA 1 (Cont'd)
Table Table IWB-2500 IWB-cGC0 Examination System or Component tiethod of Code Relief item No.
Ca tego ry__
Description Area to be Examined Exar.i na tio n Requested B6.7 B-M-2 Valves Casings Visual Yes.
See Note 12.
B6.8 B-P Valves Exempted compinents Visual (IWA-No 5000)
B6.9 B-G-2 Valves Pressure-retaining bolting Visual No less than 2 inches no m
8n U1 e
4 o
h
G FABLE 1 l
T-NOTES Normally during each refueling outage, the reactor vessel closure studs are left in place; therefore only l
1.
a volumetric examination will be performed (Table IWB-2600 Item Bl.7).
If the studs are removed, tioth a surface and volumetric examination will be performed (Table IWB-2600 Item 81.8).
2.
Closure head does not have cladding.
Twenty locations on the closure head will be measured to determine I
the corrosion rate.
Six b x 6-inch evenly distributed accessible sections of the vessel shell cladding are to be visually t
3.
examined.
At present, piping system pressure boundary bolting greater than or equal to two inches does not esist.
4.-
If such bolting is introduced, examinations will be performed in accordance with applicable Code require-ments.
If such are introduced, 5.
At present, there are no socket welds in ASME Code-affected Class 1 piping syster.s.
applicable ASME Code examinations will be performed.
If such At present, there are no through-wall casing welds in ASME Class 1 Code-affected pumps or valves.
N 6.-
E are. int.roduced, applicable ASME Code examinations will be performed.
7.
See Request for Relief, paragraph 2.1.6.
2 I
vi E
cn 8.
Deleted.
o 9.
See Request for Relief, paragraph 2.1.2.
l1 10.
See Request for Relief, paragraph 2.1.5.
" ". 11.
There are no integrally welded valve support.s.
SS 12.
See Request for Relief, paragraph 2.1.3.
nw 8:a
- 3. 0 INSERVICE INSPECTION FOR CODE CLASS 2 COMPONENTS Table 2 provides a tabulation of the Class 2 pressure-retaining components (and their supports) subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer 1975.
These components will be inspected in accordance with the requirements of Subsection IWC to the extent practical.
This tabula-tion identifies the components to be inspected, the Section XI examination item and category, area to be examined, and the method of examination.
Release from the inspection requirements of Subsection IWC is requested where these inspection requirements have been determined to be impractical. Where release is requested, information is provided which identifies the applicable Code re-quirement, justification for the release request, and the inspection method to be used as an alternative.
Table IWC-2600 items not applicable to the Edwin I. Hatch Nuclear Plant-Unit 1 have also been listed and identified in the interest of completeness.
Items applicable to pressurized water reactors only have been omitted entirely for brevity.
Article IWC-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet available for use.
Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any inservice examinations will be made, usirg the acceptance standards for materials and welds specified in the Code under which the specific component was constructed.
Some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased.
However, these components will be inspected in accordance with the requirements of Subsection IWC to the extent practical.
Article IWC-4000, entitled " Repair Procedures," states that the rules of IW8-4000 shall apply.
It is considered that the repair procedures outlined in IWA-4000 are appropriate for the components included in this program, and therefore the rules of IWA-4000 will be applied rather than IWB-4000.
The inservice inspection programs described in this section were developed as a result of a design review.
Should certain ASME Section XI Code requirements be discovered to be impractical, in the course of inspecting the components, due to unforeseen reasons, Georgia Power Company will submit a request for release from the requirements to the NRC at that time.
Hydrostatic testing will be conducted ir a manner that will satisfy the require-ments of IWA-5000 and IWC-5000.
Where aojoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure.
Where it is not practicable to separate adjoining sections of piping (e.g., boundary is a check valve), the sections will be tested together at the lower of the specified test pressures.
No 1
point in the piping will be permitted to experience a pressure greater than the specified test pressure.
Components exempted from volumetric and surface examination by IWC-1220 will be hydrostatically tested per the requirements of IWA-5000 and IWC-5000.
Amendment 1 4/79 3-1 t
l 3.1 Requests for Relief From ASME Section XI Requirements 3.1.1 Hydraulic Shock Suppressors 3.1.1.1 Requirement From Which Relief Requested Iable IWC-2520, Category C-E-2, requires visual examination of all support components and verification of support settings for springs and snubbers once per inspection interval. Visual examinations and verification of spring settings will be performed.
Relief from the verification of snubber settings is requested.
3.1.1.2 Justification The hydraulic shock suppressors on Class 2 systems are currently subjected to an ongoing testing program per plant technical specifications.
This program 2
is designed to demonstrate the functional integrity of the shock suppressors and exceeds the requirements of Table IWC-2520.
l1 3.1.1. 3 Testing in Lieu of :. tion XI Requirements Hydraulic shock suppressors will be tested in accordance with technical speci-fications.
3.1.2 HPCI and RCIC Turbine Bolting 3.1.2.1 Requirement From Which Relief Requested Table IWC-2520, Category C-0, requires examination of pressure-retaining bolting over one inch in diameter.
The closure fasteners for the HPCI pump are studs and cap nuts. The cap nuts completely obscure the studs making an in place volumetric examination impossi-ble.
These studs will receive a surface examination when the pump is dis-assembled for maintenance. The closure studs for the HPCI and RCIC turbine have rounded ends making an in place volumetric examination impossible.
Relief from inservice examination of these fasteners is requested.
3.1.2.2 Justification The examination of the obscured stud bolts can be accomplished only by de-tensioning all bolting in sequence.
If this is done the pump (or turbine) cover should be lifted for gasket replacement.
It is anticipated that the pump (and turbine) will require disassembly for main-tenance at various times.
As the pump / turbine is tested per Section XI, Article IWP. the disassembly for the purpose of examining four studs is not practical.
3.1.2.3 Testing in Lieu of Section XI Requirements These studs will receive a surface examination when the turbine is disassembled for maintenance.
Amendment 1 4/79 3-2 ntry =
3.1.3 HPCI and RCIC Valve Bolting 3.1.3.1 Requirement From Which Relief Requested Table IWC-2520, Category C-0, requires examination of pressure-retaining bolting over one inch in diameter.
The closure studs for the HPCI and RCIC turbine stop and control valves are obscured by cap nuts or have rounded ends making an in place volumetric examination impossible.
Relief from inservice examination of these fasteners is requested.
3.1.3.2 Justification See Paragraph 3.1.2.2.
3.1.3.3 Testing in Lieu of Section XI Requirements These bolts will receive a surface examination when the valves are dis-assembled for maintenance.
3.1.4 Piping Pressure Boundary Welds 3.1.4.1 Requirement for Which Relief Requested Table IWC-2600, Categories C-F and C-G (Items C2.1, C2.2, and C2.3) requires the volumetric examination of pressure-retaining piping welds.
Relief is requested from performing an examination where the weld is inaccessible or the geometric configuration prohibits a full-Code inspection.
3.1.4.2 Justification The arrangement and details of the Class 2 piping systems and components were designed and fabricated before the examination requirements of Section XI of 2
the Code were formalized, and some examinations (as required by IWC-2600) are limited or not practical due to geometric configuration or accessibility.
Generally, the limitations exist at all fitting-to-fitting welds such as elbow-to-tee, elbow-to-valve, reducer-to-valve, etc., where geometry and some-times surface conditions preclude ultrasonic coupling or access for the required scan length. Welds having such restrictions will be examined to the extent practical.
In instances where the location of pipe supports on hangers restricts the access available for the examination of pipe welds as required by IWC-2600, examinations will be performed to the extent practical unless removal of the support is permissible without unduly stressing the system.
The results from Hatch Nuclear Plant Unit No. 2 show that a full-Code examina-tion can be performed on 97 percent of the C-F welds and 99 percent of the C-G welds.
Similar results are expected for Unit 1.
Relief will be requested at the cime any weld is found not to be fully Code inspectable as provided by 10CFR50.55a(g).
Amendment 2 9/80 3-3
- su.w,
3.1.5 Hydrostatic Testing 3.1.5.1 Requirements From Which Relief is Requested a.
IWC-5000 requires that hydrostatic tests be performed at a test temperature of 2: 1000F. Relief is requested from this requirement for all Class 2 systems except portions of the standby liquid control system which are normally heat-traced.
b.
Test pressure and temperature is required to be held for four hours prior to performing the examination. Relief is requested from this time interval for non-insulated piping.
3.1.5.2 Justification a.
Hydrostatic testing at a test temperature of 2: 100 F would require insulation removal, installation of permanent or temporary heat tracing on the lines to be tested, and the replacement of the insulation. This procedure would prove 2
to be an undue hardship without a compensating increase in the level of safety.
b.
The time duration of four hours for hydrostatic testing on non-insulated piping is excessive. All later Addenda to the 1974 version of Section XI and the 1977 version of Section XI differentiate between insulated and non-insulated piping for determining the test duration.
3.1.5.3 Testing in Lieu of Section XI Requirements a.
The piping contract for Plant Eatch specified that the hydrostatic test pressure be performed at 700F plus the nil ductility factor. This factor has been determined "to be a negative number for the piping at Plant Hatch.
Therefore, the test temperature for hydrostatic testing will be 2t 700F.
b.
The test pressure and temperature for insulated piping will be held for four hours prior to system walk-down examination. For non-insulated piping it will be held for ten minutes before walk-down.
k 3-3a i
e fI TABLE 2 c
ISI PROGRAM 3r
~1-
- ASME CODE CLASS 2 COMPONENTS Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code Relief Iten No.
Ca teg_ory_
Description Area to be Exanined Examina tic a.
2,e qu q,s_ted C1.1 C-A Residual Heat Remov-Circumferential butt welds Volumetric No al Heat Exchangers Cl.2 C-B Residual Heat Remov-Nozzle-to-vessel welds Volumetric No al Heat Exch:ngers C1.3 C-C Residual Heat Remov-Integrally welded supports Surface No al Heat Exchangers Cl.4 C-D Residual Heat Remov-Pressure-retaining bolting Visual and No al Heat Exchangers either surface or Volumetric C2.1 C-F Piping Circumferential butt welds Volumetric Yes.
u, See Note 1.
A C2.2 C-F Piping Longitudinal weld joints in Not Applicable.
No fittings C2.2 C-G Piping Longitudinal weld joints in Not Applicable.
No fittings C2.3 C-F Piping Branch pipe-to-pipe weld Volumetric No joints C2.3 C-G.
Piping Branch pipe-to-pipe weld Volumetric No joints a?
"i C2.4 C-D Piping Pressure-retaining bolting Visual and No either surface or Volumetric u,
e e
h.
&g
.ABLE 2 (Cont'd) y Table Table IWB-2500 IWB-2600 Examination System or Component Method of Code P.elief Item No.
Category _
Description Area to be Examined Examina tio n Requested C2.5 C-E-1 Piping Integrally welded supports Surface No C2.6 C-E-2 Piping Support components Visual Yes.
See Note 2.
C3.1 C-F Pumps Pump casing welds Not Applicable.
No See Note 5.
C3.1 C-G Pumps Pump casing welds Not Applicable.
No See Note 5.
C3.2 C-D Pumps Pressure-retaining bolting Visual and Yes. See either surface Note 3.
or Volumetric C?..s C-E-1 Pumps Integrally welded supports Surface No C3.4 C-E-2 Pumps Support components Visual Yes.
See Note 2.
C4.1
.C-F Valves Valve body welds Not Applicable.
No See Note 5.
C4.1 C-G Valves Valve body welds Not Applicable.
No See Note 5.
?
C4.2 C-D Valves Pressure-retaining bol ting Visual and Yes.
'S either surface See Note 4.
or Volumetric no C4.3 C-E-1 Valves Integrally welded supports Surface No C4.4 C-E-2 Valves Support components Visual Yes.
See Note 2.
=
$F m
y.
~7 TABLE 2 NOTES 1.
See Request for Relief, paragraph 3.1.4.
2 1
Relief will be requested at the time any weld is found not to be fully Code inspectable as provided by 10CFR50.55a(g).
j w
o, 2l See Request for Relief, paragraph 3.1.1.
1 3.
See Request for Relief, paragraph 3.1.2.
4.
- See Request for Relief, paragraph 3. : 3.
5.
At present, there are no through-wall casing welds in ASME Class 2 pumps or valves.
If such welds are in-troduced, applicable ASME Code examinations will be performed.
1 i Elf i en.
~-
8a
4.0 INSERVICE INSPECTION FOR CODE CLASS 3 COMPONENTS This program consists of the examination areas and the visual examinations required to meet IWD-2000.
The structural integrity of the Safety Clas.; 3 components shall be demonstrated at least once every 40 months during periods of normal reactor operation or during system performance testing by verifying via visual inspection that there is no evidence of unanticipated component leakage, structural distress, or corrosion.
The structural integrity of the Safety Class 3 components shall be demonstrated at least once every ten years by performing system pressure tests at the following test pressures:
1.
For closed systems, at least 110 percent of the design pressure.
2.
For open storage tanks, at least the nominal hydrostatic pressure de-veloped with the tanks filled to design capacity.
3.
Open-ended ponions of systems may be exempted from pressure testing.
The structural integrity of the Safety Class 3 components shall be demonstrated at least once every 40 months by verifying via visual inspection that the supports and hangers for piping and components over four inches in diameter show no evidence of inadequate support, unintended restraint, or structural dis tress.
The following provides further clarification concerning the Class 3 inspection program:
1.
Article IWD-3000, entitled " Evaluation of Examination Results," is in the course of preparation by the Code committee and is not yet avail-able for use. Therefore, the rules of IWA-3000 will be used with the exception that the evaluation of any indications detected during any in-service examinations will be made, using the acceptance standards for materials and welds specified in the Code under which the specific component was constructed.
2.
Article IWD-4000, entitled " Repair Procedures," states that the rules of IWB-4000 shall apply.
It is considered that the repair procedures outlined in IWB-4000 are inappropriate for the components included in-this program, and therefore the rules of IWA-4000 will be applied.
3.
Inspection of vertical, centrifugal river intake pumps, as required by IWD-2410 (b) and (c), is impractical except at the pump discharge nozzl e.
Visual inspection of the discharge nozzle will be performed while the pump is operating. Should the pump be pulled for maintenance, the casing will be visually inspected at '_ at t.ime.
4 The designs of the service water systems do not include provision for testing buried piping as required by IWD-2600(b). Visual inspection for leakage at ground level is also impossible for portions which are buried.
Normal system functional testing demonstrates leaktight integrity of all buried or encased piping.
4-1
5.
The system pressure testing requirements of IWD-2410 (b) will not ce per-formed on lines two inches and smaller unless:
(a) They are connected to larger lines which will be pressure tested.
(b) Isolation valves are not provided so that these smaller lines may be isolated in case of leakage.
These smaller lines have wall thicknesses in excess of what ASME Section III requires for retaining internal pressure.
Using heavier-walled piping in these small lines essentially means they are over-designed for the pressure they are retaining and are not susceptible y
to the type leakages found during hydrostatic testing.
As an alterna-tive, all accessible piping two inches and smaller will be visually in-spected under normal operating pressure.
6.
System pressure testing as required by IWD-2410 (b) is impractical for certain portions of the plant service water system because it operates continuously during all modes of plant operation.
This functional oper-ation demonstrates the structural and leaktight integrity of the system.
Visual inspection will be performed while the system is under normal operating pressure to verify leaktightness.
7.
Where adjoining pipe sections have different test pressures, they will be separated whenever practicable and each section tested at its specified pressure. Where it is not practicable to separate adjoining sections of I
piping (e.g., boundary is a check valve), the sections will be tested together at the lower of the specified pressures.
No point in the piping will be pressurized above the specified test pressure.
Amendment 1 4/79 4-2 h.
4.1.1 Hydrostatic Testing 4.1.1.1 Requirements From Which Relief is Requested a.
IWD-5000 requires that hydrostatic tests be performed at a test temperature of 2: 1000F. Relief is requested from this requirement for all Class 3 systems.
b.
Test pressure and temperature is required to be held for four hours prior to performing the examination. Relief is requested from this time interval for non-insulated piping.
4.1.1.2 Justification Hydrostatic testing at a test temperature of 2: 1000F would require insulation a.
removal, installation of permanent or temporary heat tracing on the lines to be tested, and the replacement of the insulation. This procedure would prove 2
to be an undue hardship without a compensating increase in the level of safety, b.
The time duration of four hours for hydrostatic testing of non-insulated piping is excessive. All later Addenda to the 1974 version of Section XI and the 1977 version of Section XI differentiate between insulated and non-insulated piping for determining the test duration.
4.1.1.3 Testing in Lieu of Section XI Requirements a.
The piping contract for Plant Hatch specified that the hydrostatic test pressure be performed at 70 F plus the nil ductility factor. This factor has 7
been determined to be a negative number for the piping at Plant Hatch.
Therefore, the test temperature for hydrostatic testing will be;t700F.
b.
The test pressure and temperature for insulated piping will be held for four hours prior to system walk-down examination. For non-insulated piping it will be held for ten minutes before walk-down, i
l t
4-2a s
5.0 INSERVICE TESTING 0F PUMPS The 1974 ASME Section XI Code with Addendo through Summer 1975 requires inservice testing of pumps in accordance wit. section IWP.
The inservice testing program for Class 1, 2, and 3 pumps is described in Table 3.
Where tull compliance with the requirements of the Code was not possible, an explanation is provided in the table.
5.1 Requests for Relief from ASME Section XI Requirements 5.1.1 Vertical Centrifugal Pumps-Service Water and RHR Service Water Pumps l1 5.1.1.1 Requirement from Which Relief Is Requested Article IWP-4310 of Section XI requires the monitoring of all centrifugal pump bearing temperatures.
Relief from this requirement is requested for the Service 1
Water and RHR Service Water lower bearings.
5.1.1.2 Justification Only the upper bearings are accessible; the lower bearings are below the sur-ly face of the river.
Pump disassembly for bearing inspection is not practical.
I 5.1.1.3 Testing in Lieu of Section XI Requirements The lower bearings will be inspected for wear whenever a pump is pulled for maintenance.
5.1. 2 Vertical Centrifugal Pumps-RHR and Core Spray Pumps 5.1.2.1 Requirement from Which Relief Is Requested Article IWP-4310 of Section XI requires the monitoring of all centrifugal pump bearing temperatures.
Relief from this requirement is requested for the RHR and Core Spray Pump lower bearings.
5.1.2.2 Justification There are no true lower bearings in these pumps.
Only bearing surfaces exist that are cooled and lubricated by the process water.
There are no means to measure bearing temperatures.
1 5.1. 2. 3 Testing in Lieu of Section XI Requirements The bearing surfaces will be examined for wear whenever a pump is pulled for maintenance.
5.1. 3 Pump Testing Interval 5.1.3.1 Requirement From Which Relief Requested Article IWP-3400 requires an inservice test to be run on each pump once per month.
It is proposed that the pump inservice testing interval be changed to once per three months.
Amendment 1 4/79 5-1
5.1.3.2 Justification The intent of the pump testing program is to assure an increased level of plant safety by verifying the operational readiness of each pump.
An optimized testing program would assure pun.p operability and have the least impact on the degradation of the pump and its associated equipment over its service lifetime.
Excessive testing downtime jeopardizes pump availability for performance of its safety-related function, causes component wear, and does not increase the level of plant safety.
The Section XI Subgroup for Inservice Testing of pumps and valves has con-1 ducted an extensive investigation and analysis of test optimization.
Two papers written by W. E. Vesely, Probabilistic Branch, USNRC, provided a basis for cnanging from a one-month interval to a three-month test interval.
As a result, this proposed revision to the Section XI Code has been initiated to change the pump interval to nominally every three months.
5ince it has been shown by the NRC and the Section XI Subgroup that the three-month pump testing interval provides the plant with an increased level of safety, it is proposed that the Plant Hatch - Unit No. 1 pump testing in-terval be changed to every three months.
Amendment 1 4/79 5-la a
L 4
'l n
TABLE 3 (Page 1 of 4)
INSERVICE TESTING PROGRAM FOR ASME CODE CLASS 1, 2, AND 3 PUMPS ASME Pump Code Test Section XI Code Identification Pump Description Class Measured Parameters Interval Relief Requested IC41 C001A Standby liquid control 2
- 1. Inlet pressure (Pj)
Every 3 Months Yes. Notes 7, 10 lI 2
1C41 C0018
- 2. Differential pressure Every 3 Months Yes. Note 10 (AP)
- 3. Flow Rate (Q)
NA No.
Note 4
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10 h
- 5. Bearing temperature Annually No. Note 3
- 6. Lubricant level or Observe Every Yes. Note 10 2
pressure 3 Months.
T N
lEll C002A Residual heat removal 2
- 1. Inlet pressure (Pj)
Every 3 Months Yes. Note 10 1E11 C002B
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 (AP)
IE11 C002C 1E11 C002D
- 3. Flow rate (Q)
Every 3 Months Yes. Notes 1, 10
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10
- 5. Bearing temperature Annually Yes. Note 8 l1 2
- 6. Lubricant level or Observe Every Yes. Notes 6, 10 oressure 3 Months gg IE11 C001A RHR service water 3
- 1. Inlet pressure (Pj)
Every 3 Months Yes. Notes 2, 10 l1 E R.
1E11 C001B
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 (AP) 1E11 C001C
- 3. Flow rate (Q)
Every 3 Months Yes. Notes 1, 10 m$
IE11 C001D
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10 ma
- 5. Bearing temperature Annually Yes. Notes 3, 5
- 6. Lubricant level or Observe Every Yes. Notes 6, 10 pressure 3 Months.
l
ll S
TABLE 3 (2 of 4) t ASME Pump Code Section XI Code Identification Pump Description Class Measured Parameters Intervals Relief Requested 1E21 C001A Core spray 2
- 1. Inlet pressure (P )
Every 3 Months Yes. Note 10 j
1E21 C0018
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 (AP)
- 3. Flow rate (Q)
Every 3 Months Yes. Notes 1, 10
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10
- 5. Bearing temperature Annually Yes. Note 8 lI 2
- 6. Lubricant level or Observe Every Yes. Notes 6, 10 pressure 3 Months 1E21 C002A Jockey Pump 2
- 1. Inlet pressure (Pj)
Every 3 Months Yes. Notes 9, 10 Il 1E21 C002B
- 2. Differential pressure Every 3 Months Yes. Note 10 (AP) m
- 3. How rate (Q)
NA No. Note 4
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10
- 5. Bearing temperature Annually No. Note 3
- 6. Lubricant level or Observe Every Yes. Note 10 pressure 3 Months 2
Plant s rvice water 3
- 1. Inlet pressure (P )
Every 3 Months Yes. Notes 2, 10 1P41 C001A a
j IP41 C001B
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 (AP)
IP41 C001C
- 3. Flow rate (Q)
Every 3 Months Yes. Notes 1, 10 1P41 C0010
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10
((
- 5. Bearing temperature Annually Yes. Notes 3, 5 EE
- 6. Lubricant level or Observe Every Yes. Notes 6, 10 2
ll pressure 3 Months
~
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8a
f R:.
i 4
t
~
I TABLE 3(Page 3 of 4)
. Pump.
Code Test Section XI Code Identification Pump Description Class Measured Parameters Intervals Relief Requested _
IE41 C001 High-pressure coolant 2
- 1. Inlet pressure (Pj)
Every 3 51onths Yes. Note 10 injection
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 2
(6P)
- 3. Flow rate (Q)
Every 3 Months Yes. Notes 1, 10
- 4. Vibration amplitude Every 3 Months Yes. Notes 3,10
- 5. Bearing temperature Annually No
- 6. Lubricant level Observe Every Yes. Note 10 pressure 3' Months
- 7. Pump speed Every 3 Months Yes. Note 10 2
[
1E51 C001A
. Reactor core isolation 2
- 1. Inlet pressure (P )
Every 3 Mor.ths Yes. Note 10 j
cooling
- 2. Differential pressure Every 3 Months Yes. Notes 1, 10 (AP)
- 3. Flow rate (Q)
Every 3 Months.
Yes. Notes 1, 10
- 4. Vibration amplitude Every 3 Months Yes. Notes 3, 10
- 5. Bearing temperature Annually No. Note 3
- 6. Lubricant level or Observe Every Yes. Note 10 pressure 3 Months 2
- 7. Pump speed Every 3 Months Yes. Note 10 a
N 8
bU i
((
l~I TABLE 3
(
NOTES 1.
Measurement of both or and Q is not required by ASME Section XI..One of these quantities may be omitted from the '.est specified by the surveillance procedores.
2.
These pumps are vertical design with no means of direct inlet pressure measurement.
In lieu of
' direct measurement, the intake level will be measured.
This can then be converted to pump inlet pressure as:
114.5 ft - Intake Level (ft)
Inlet pressure (P ) =
2.3066 (ft/ psi) i 3.
No instrument is installed on the pump. A portable instrument will be used.
-4.
No flow instrumentation is installed on this pump.
A fixed-resistance test circuit will be used in dCCOrdance with footnote 1 of Table IWP-3100-1.
5.
See Request for Relief, paragraph 5.1.1.
T 6.
Lubricant level is to be observed for the driver thrust bearing only.
The main bearings are lubri-cated by the pump water.
7.
No direct means of measuring pump. inlet pressure is available.
Pump inlet pressure will be calcula-ted from test tank level.
1 8.
See Request for Relief, paragraph 5.1.2.
9.
These pumps are normally operating pumps and will not be shut down to measure inlet pressure.
l2
- 10. See Request for Relief, paragraph 5.1.3.
4.
n Wit an N
80
6.0 INSERVICE TESTING OF VALVES The 1974 ASME Section XI Code with Addenda through Summer 1975 requires in-service testing of valves in accordance with section IWV.
The inservice testing program for Class 1, 2, and 3 valves is described in Table 4.
Where full compliance with the requirements of 1he Code was not possible, an explana-tion is provided in the table.
6.1 Requests for Relief from ASME Section XI Requirements 6.1.1 Requirement from Which Relief Is Requested IWV-3410(g) and IWV-3520(c) state that when corrective action is required as a result of tests made during ccid shutdown, the condition shall be corrected before startup.
6.1.1.1 Justification lI Under such conditions startup shall be permitted as provided in the technical specifications.
6.1. 2 Requirement from Which Relief Is Recuested IWV-3410(c) states that if an increase in stroke time of 25% or more from the previous test for valves with stroke times greater than ten seconds or 50%
or more for valves with stroke times less than or equal to ten seconds is ob-served, test frequency :nall be increased to once each month until corrective action is taken.
Relief is requested for valves normally tested during cold shutdown.
6.1. 2.1 Justification Valves that are normally tested during cold shutdown or refueling cannot be tested once each month.
Stroking these valves during power coeration may place the plant in an unsafe condition.
1 6.1.2.2 Testing in Lieu of Section XI Requirements The test frequency shall be inct3ased to once each cold shutdown, not to exceed once each month.
6.1.3 Requirement from which Relief is Requested IWV-3420(f) requires a permissible leakage rate for each specific Category A valve. Only valves performing a pressure isolation function, as defined in Table 4, note 38, have Section XI permissible leakages.
6.1.3.1 Justification l
The plant design is not compatible with cnecking permissible leakages for specific valves because of the complex piping and valving arrangement; however, the 10CFR50 Appendix J local leak rate testing program for the containment isolation valves has an overall limit of 60% La based on off-site dose calcu-l Anendment 1 4/79 6-1 we
lations.
Since 60% La is an overall limit, the possibility exists tha', the majority of the containment leakage may leak through one highly degraded valve and be within the 60% La limit.
Although the uniformity of leakage through the containment penetratiorr, is relatively unimportant, it is not desirable to have the majority Of the containment leakage being emitted through one penetration.
The engineering judgement of plant management will be used to determine whether a valve is leaking excessively.
Valves which leak excessively will be repaired and retested before being placed into service.
6.1.4 Requirement from which Relief is Requested IWV-3420(g) requires valves with leakage rates to have corrective action applied to them.
Only valves performing a pressure-isolation function, as defined in Table 4, note 38, have Section XI corrective action applied to them.
1 6.1.4.1 Justification Corrective action per IWV-3420(g) cannot be applied to valves exempted from IWV-3420(f).
(See request for relief, paragraph 6.1.3) 6.1.4.2 Corrective Action in Lieu of Section XI Requirements Except for valves performing a pressure-isolation function, corrective action will consist of the repair of valves judged to be leaking excessively.
6.2 Valves to be ':ested During Cold Shutdown and Refueling Valve testing will commence as soon as possible into the cold shutdown but no later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the shutdown. Valve testing will continue during the shutdown until complete or until plant startup and return to power.
Any testing not completed at one cold shutdown will be performed during subsequent cold shutdowns before the next refueling.
During refueling, any valve scheduled for a refueling test will be tested.
Also, any valve identified to be tested at cold shutdown that has not been tested during the previous three months will be tested during the refueling.
Amendment 14/79 l.
6-la lM
.- _,_ _-. ~..
... _ -. ~-
s; vi. -..
s.
s 5
F g
B
+
A TABLE 4 INGERVICE INSPECTION VALVE TEST PLAN W f. !
fn * -
ASME CO)E CLASS 1,2, AND 3 VALVES ic' g
1 I jI rey e avauesec*
J 'O."!.
g TJf.o
'd'iE' oll!.o
- * '"a
,,,,,y
- == u ueo
=
Note 39 lI 821.F010A 1
AC 18" Check 3-E H-16062 feedwater Inboard Contafement Isolation 0
Each Refueling Outage
[ach Refueling Outage Ves. Note 2 Note 39 h
821-F0108 1
AC 18" Check 3-D H-16062 Feedwater Inboard Containment Isolation 0
Each Refuelin.g,0utage Each Refuel 1910utage Ves. Nute 2 821-F0134 1
C 6" Relief C-6 H-1606'
- aam Relief Note 3 NLA No.
Note 19 821-F0138 1
C 6" Relief C-6 H-16062 Main Steam Relief Note 3 N/A No.
Noke19 821-F01 X 1
C 6" Relief F-6 H-16062 Main Steam Relief
,____fio te_J
.._. _ N/ A _ _ _ _...e_.._N0. M_tg, J
821-F0130 1
C 6" Relief F-6 H-16062 Main Steam Relief j
Note 3 N/A No, hote 19 I
I
.I B21-F013E ll C 6" Reifef H-16062 Main Steam Relief Note 3 N/A No. Note MI F _6_.
. -. - -. -_j --
1 i
821-f013F 1
C
~6" Relief F-6 H-16062 Main Steam Re'ief Jote_i__ _ __
_. _ _ _. 5/A... _. __.
Non _.W te_ It 821-F013G
.l 1' C 6" Relief F-6 H-16062 Main Stear stelief Note 3 N/A No.
Note 19 821-F013H I
.C 6" Relief G-6 H-16062 Main Steam Relief Note 3 N/A No.
Note 19 2559 821-F013J 1
C 6" Relief G-6 H-16062 Main Steam Relief Note 3 N/A No. Note 19 821-F013E
'1 C
6" Relief F-6 H-16062 Main Steam Relief -
Note 3 N/A No, hote 19 I
B21-F0131.
1
'C 6" Relief F-6 H-16062 Main Steam Relief Note 3 N/A No, Note 19 Anendment ! 4/79 m
6-2 235) r I
_...m.
m N:
4
'T TABLE 4 2
24 4NSERVICE IMCTION VALVF TEST PLAN wn ne AWE CODE CLASS 1.2. AND 3 VALVES
. J.*J4.'.
E,i J/.
o.4*tJhem Tf.T
,Jtio
" ' " " ~ '
yf iij
.','gn,";JA%
- um ~~
o
. n.c.n e.u = u s e..u-g_
None Yes. Note 10 821-F016 1
A 3* M0 Gate E-8 H-16062 Main Steam Line Drain Intoard Iso _lation C
(Note 53)
Each Refue_ ling Outage 15 Note _39 None B21-F019 1
A 3* M0 Gate E-9 H-16062 Main Steam Line Drain Outboard Isolation C
(Note 53)
Each Refueling Outage 15 Ves. Note 39 B21-F022A 1
A 24" A0 Globe C-7 H-16062 MSIV O
Every Three Months Each Refueling Outage 3-5 Nu. Note 39 1
821-F0228 1
A 24' A0 Glote E-7 H-16062 MSly 0
Every Three Months Each Refueling Outage 3-5 No. Note 39 B21-F022C 1
A 24" A0 Globe F-7 H-16062 MSty 0
Every Three Months Each Refueling Outage 3-5 No. Note 39 1
321-F022D_
1. A, 24" AD Globe G-7_,_ H-1,6062, MSly ___
0 Every three Months _,
Each Refueling Outage _ 3-5 No. Nop 39 821-F 02V 1i A 24* A0 Globe C-9.,H.1.6062...MS. !V..
E..very Three.M.onths_., p._ac. h Refuelino._O_utage 3-5 0
E No. Note 39
(.
3
_._ g...
I !
l l0 l
I B21.F0238 1
A 24' A0 Glotw E-9 H-16062 MSIV Every Three Months Each Refueling Outage 35 No. Note.s9 i B21-F028_C _ 1._A. 24. ' A0. Glo_be F 9_
H-16_062_MS !_V 0
Every Three Months Each Refueling Outage 3-5 ho. Note 39 e
B21-F0280 1
A 24" A0 Glotu G-9 H-16062 MS!V 0
Every Three tbnths Each Refueling Outage 3-5 Na. Note 39 Note 39 921-F032A 1
At 18a' Check E-2 H-16062 Feedwater Outboard Isolation 0
Each Refueling Outage Each Refueling Outage Yes. Note 2 Note 39 821-F0328 1
AC 18" Check D-2 H-16062 Feedwater Outboard Isolation 0
Each Refueling Outage _ Each Refueling Outage __
Y es. Note 2 B21-F037A 3
C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C
None N/A Yes. Note 5 b
Arendment 14/79 6-3 M
2EE3 b
1
' (' l *
-y N[
+
TABLE 4 i,
INSERVICE INSPECTION VALVE TEST PL AN 9
p-Ashet CODE CLASS 1,2. ANO 3 VALVES r
)
I - - - -
"E N ~ -- -- --~ ff
,'ll,;M,=;;T,L
, ',(
J.#..
' A%'.".T.5%
- e=
J.%#.
u 2:.~ ~
- _ = = ~
d 821-F0378 3
C 6* Chec k H-6 H-16062 Vacuum Breaker M5RV Olscharge
'C None N/A T es. %te 3
-t----
821 F037C 3
C 't" Check..
H-6 H-16062 Vacuum Breaker M5RV Discharge C
None N/A Ves. Note S 821-F037D' 3
r 6" Check H-6 H-16062 Vacuum Brea6er M5RV Olscharge C
None N/A Ves. hote S 821-F037E 3
C 6' Check H-6 H-16062 Vacuum Breater MSRV Discharge C
None N/A f e',. Nofe 5 821-F037F 3
C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C
None N/A Ves. Note 5 821-F037G '
3 C
6" Check H-6 H-16062 Vacuum Breaker,MSRV Dluharge C, _. M ne, _, _
N/A Yes. Note S,
.F037f,
3
,. C_ 6" C, heck H-6 H-16062 Vacuum Breaker MSRV Dischar9e, C
None N/A ygg ga.
l 821-f037J 3
C 6* Check
'H6 H-16062 Vacuum Breater MSRV Dischar9e C
None N/A Yes. Note $
828 F037" 3
C 6" Check H-6 H-16062 Vacuum Breaker MSRV Discharge C
None N/A Ves. Note $
B21.F037L
,3, C
6' Check H-6 H 16062 Vacuum Breaker MSRV Discharge C
None N/A Ve4 Note $
Ves. Ntc 2 r
y 831.F0134 1
AC 3/4' Check. _- 3_ H-16066 Recirculation Pump Seal..W.a_te_r - _ - ~
0
.t.a_ch _Ref.ueling Outage-F
- -- -Fach Refueling Outage
"O i'
O Ves. Note 2
. 831-F0138 _1 _AC 3/4* Check F-3 H 1 _6066...Rec. i.rculation Pum.p Seal Wa.t.er ~
0 f a.ch Refueling Outage '- --Fach Refueling putage
. Note 40 _
- -- ~~~
~
Yes hte ?
I 831 fol7A 1
AC 3/4" Check F2 H-16066 Recirchletion Pump,5eal Water
,Q_ (a Q Refug1Jnq Out490. tech Pefutilng Outage
- I!_' E-,
Yes. Note 2 i
C 831 fol78 I
AC 3/4* Check F-2 H-16066 Recirculation Pump Seal Water 0
Each Refueling Outage ~~-
tach Refueling Outage
-- -Note 40 i
i' 3/4" AO-C B31-F019 I
A Globe D-3 H-16066 Reactor $ ample Sjstem Inboard Isolation 6
Every three months Fach Refueling Outage 5
Ves. Note 39 l
...rt.
. m 64 Acendrent 14/19 l
i
1, s
e Js TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN V4t' ASME CODE CLASS 1.2. AND 3 VALVES
---.-,--y..-.------
ll J.. r.:n
=.,;..:.m I!F g;;;;;;;;,,?y'"~"E ;; _,,
==a t.
[N av.
~-
3/4" A0 831 F020 1 A
Globe D-1 H-16066 Reactor Sample System Inboard Isolation 0
Every three months fach Refuelino Outage 5
Yes. Note.0 Yes. Note 5?
B31-F031A I
B 28" MD Cate G-7 H-16066 Reactor Recirculation 0
Cold Shutdown N/A 40 Note 25 tes. Note %2 B31.F031B 1
8 28" MD Gate H-7 H-16066 Reac tor Recircula tion 0
Cold Shutdown N/A 40 Mte 25 I
1-1/2" Esp 1.
,C41-F004A 2 D. 5hea r _ _ _
D-3 H-1606l SLC f xplosive Actuated C
No te 4 N/A No 1-1/2" E xpl.
C41-F0040__
2.' D.
Shear E-3_
H-l6061_ stC tapto. sive Actuated C
Note 4
_ N/ A No
. 11/2" Note 19 SLC 0 tboard Containment lyola tion C
0nce/18 mnths.
Fach Refueling Outage Ves.
Note V
.C41-F006,
,1 AC Check E-2
.H-1606).
9
! -1/2" Note N l1 1
C41-F00 1, AC iCheck E-2 e '6061 51 C Outboard Contairment Isolation C Onte/18 Months _
Each Refueltnq Outage Yes.
Note 26 l
l i
l i i
,.(41-F029A_
_2. _ I" Rel ief.
.. D-6..
.H-160s._
SIC Pump Discharge Pelief Valve C
Note 3 N/A No.
Note 19 No.
Note 19 C41-F0299 2 { C
,1" Relief _ _G-6 H 16061.. SLC Pump _ Discharge _ Relief Valve
,C
_ Note 3_
N/A I-- l/ 2" C41-F033A 2
C Check E-5 H-16061 SLC Pump Dischatie 1C Note 7 N/A Yes 4
L I-1/2" C41-F033R 2
C f**ck G
SLC Pun.p Discharge C
Note 7 N/A Ves
. _-5__H. _16061_ _. _..
(m]
E11-F003A 2
B 16" PC Gate D-9 H-16330 RHR Heat Exchanger Shell st_de Outlet 0
f,very Three Months N/A 82 No EiM2) f_11-F003B 2
8 16* M0 Gate D-4 H-16329 RHR Neat Exchan2er Shell side Outlet 0
t,very Three Months N/A 82 No
.(ll-F004A._. __. 2.A__
24
- M0__Ga t.e J-10
.H-16330_
Rij.R. Pump __Suc tion Torus Isola tio_n _ _. _ _ _0 Ivery,Th_ rec _ Months __
f ar.h. Refueling Outage 125. Ves. Note 40__
l1 E11-F0048 2
A 24" M0 Gate F-3 H-16329 RHR_ Pump Suction Torus Isolation 0
fvery Three Months
[ach Refueling Outage 125 Yes. Note 40 Il i
p f.- 5 Amen.iment 14/19 c
b
t-3-
3 r p iIp-hI li-1r
'r s
TAOLE 4 5
24 BNSEfWICE INSPECTION VALE E TEST PLAN 5HE E,
o, ASME CODE CLASS 1.2. AfD 3 VALVES e
ip:
II{.MTL"JWilo
.n.
d,',!,f m.h
'e,g un'to ja a
= ==== e.ma n g
F Yes. Note 40 E11-F004C 2
A 24" M0 Gate F-10 H-16330 RHR Pump Suction Torus isolation 0
Every Three Months Each Refueling Outage 125 Yes. Note 40 E11-F004D 2
'A 24" M0 Gate F-3 H-16329 PHR Pump Suction Torus ! solation 0
Every Three Months Each Refueling Outage 125 E11-F006A 2
8 20" M0 Gate F-10 H-16330 RHR Shutdown Cooling Suction C
Every Three Months N/A 110 Nn E11-F0060 2
8 20" M0 Gate F-2 H-16329 RHR Shutdown Coolf ng Suction C
Every Three Months N/A 110 No E11-F006C 2
B 20" M0 Gate F-10 H-16330 RHR Shutdown Cooling Suction C
Every Three Months N/A 110 No g
E11-F0063 2
'8 20' M0 Gate F-2 H-16329 RHR Shutdown Cooling Suction C
Every Three Months N/A 110 No Note 40
.l 2 1
A 4* M0 Ga te E7 H-16330 RHR Pump Minimum Flow Torus isolation 0
Every Three Months Each Refueling Outage 25 Ves. Note 10 E11-F007A
..-..-p_..._._____.1 t--------------------
Note 43 3
g E11-F007B 2
A 4" MD Gate
.D-5 H-16329 RHR Pump Minimum Flew forus Isolation 0
Every Three Months Each Refueling Outage 25 Ves. Note 10 None E11-F008 i
A 20" M0 Gate D-1 H-16329 RHR Shutdown Cooling 06tboard Isolation C
(Note 53)
Each Refueling Outage 24 Yes. Note 33 None E11-F009 1
A 20" M0 Gate D-1 H-16329 RHR Shutdown Cooltag Sut ton Isolation C
(Note 53)
Each Refueling Outage 24 Yes. Note 38 '
Note 40 E11-F011A 2
A 4" M0 Gate D-3 H-16330 RHR Condensate Discharge to Torus C
Every Three Months Each Refueling Outage 25 Yes. Note 10 Note 40 Ell-Fo? d ~
2 A
4" M0 Cate C-9 H-16329 RHR Condensate Discharge to Torus C
Every Three Months Each Refueling Outage 25 Yes. Note 10 No.
Note 38 E11-F 315A 1
'A 24* M0 Gate C-8 H-16330 LPCI outboard Containment Isolation C
Every Three Months Each Refueling Outage 24 Amenenent 14/19 6-6 9-h====
e f%
T) L M
(
+
i L
)
d' f
,4
- ).
TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN sd 7 _6_ os 24 4
ASME CODE CLASS 1.2, AND 3 VALVES L
7 f [j[.
m n't.#.o
%T.?.'
y
,, ', ' 'U
- ll
.Yf.W:/4fi;%
_A* !,..
I a*t.#.
m'=
Ell 1
A 24* M0 Gate C-4 H-16329 LPCI Outboard Containment Isolation C
Every Three Months 24 No. Note 38
_, _-F0158
., -. - - - - - - ~ ~ -. -...
- -- ~ ~ - - - - -
Each Refueling Outage-- -- --
. ~ ~ - - - - - -
[
- '316A '.-.-
~. - -.- - - - - - - - - - - - -
~~
Each Refueling Outage- -- - -
~ - - - - -
Ell-f 2
A 16* M) Globe B-9 H-16330 Containment Spray Outboard Isolation C
Every Three Months 10 Ves thte 40
- - ~.
E11-F016B 2
A-16* M0 Globe 84 H-16329 Containment Spray Outboard Isolation C
Every Three Months Each Refueling Outage IJ Ves. Nate 40 Ell rol?A 1
8 24" M0 Globe D-8 H-16330 L PCI O
Every Three Months N/A 24 No E11-F0173 I
B 24" M0 Globe D-5 H-16329 LPCI O
Every *hree Munths- -. - -..
N/A 24 No
-m.
E11-r019 1
C. 4* Check A-1 H.16329 Head Spray C
Note 6 N/A No I
N/A 17 Ne h
Ell-F021A 2
8,16* M0 Gate B-11 H 16330 Containnent Spray C
Every Three Nnths
- g
.p
.. - ~
g 3
Ell F021B l2 1
B 161 MO Gate B-2 H-16329 Containment Spray C
Every Three Months N/A 11 ho None Ell-F022 1
A 4" M0 Gate A-1 H-16329 Head Spray C
(Note $3)
Each Refueling Outage 20 ses. Note 38 i
None E11-F023 1
A 4" M0 Globe A-2 H-16329 Head Spray Outboard Isolation '
C (Note 53)
Each Refueling Outage 20 Ves. Note 38 E11 r024A 2
B 16* MD Globe C-7 H-16330 Suppression Pool Cooling C
Every Three Nnths N/A 110 No
{]
---.~ ~-.
'h
)
E11.F0248 2
8 16* MD Globe C-6 H-16329 Suppression Pool Cooltng C
Every Three Months N/A.
110 No Yes. Note 4')
lg E11-F025A' 2
AC l* Relief 8-8 H-16330 LPCI Injection Containment Isolation C
Note 3 Each Refuelino Outage Note 19 5
(<
9-6-7 Amenenent 14/79 E
E 5EE)
't We o
o
(-
TABi[ 4 INSERVICE 8MSPECT60N VALVE TFST PLAN
'ddti 7
't N
ASME CODE CL ASS 1.2. AND 3 VALVES p.,, '..l t '.
s*
'J.T.TC 4.' ;.c.
p *i g
A' 'c; 2.q;; ;
u
, e u..e %.
7_
CJ.,
%m
.t I
2 AC 1
C-5 H-16329 L PCI Injec tion-Containmect 15c14 tion I' C Ves. %te 40 E11.F0258_._ _ -. __
_ a.__ p " Relief flote 3 CarhPefuelingOutage}
yte 19 I
l
- Contain, f
E ll-F02f,A 2 A 4" f0 Ga te { _ D-3 H-16330 Condensate Discharge to PCIC - ! alatinn C (very Three Pbnths
[ach Pefueling Out3qe 25
'e5.
h'*
d
j Contain.
i 25 ll W j ?!
A_.
.ConJerisa te Disdarge to RCl( ~
Ell-F026B 4" MD Gate 0-11 H-16 329 Iwla t ion e Every Three M0nths fach Refuelinq A te;c
- ai l 2 5 8,6* R) Mode D-3
'H-16330
[11-F027A
, I Suppression Pool Spray i
[bery Three Nnths N/A Il g
..l?!816"MOGlot-e E11-F027B
._ __ 7. -11 H-If329
- .,i E very Teree Merths N/A 11 Ni.
r D Suppression Paol Spray
('
Suppression Pool Spray Outtcard Isola t u,n, C,l her y Thr ee Months Ell-F0ltA 2 4 16" M9 Ca te '.. R-3 H-I f,310 Fach Refueling Outile
?$
W l
i t
Ell-F02R8
!2 A,'16"MOGatef,,B-5 H-16129 h' Suppress inn Pool Spra/ Outhcard Isolatirm ' C i
I Fvary Three A nths Ea h Pefueling Outac, 25 N,.
l t
ves. m,e 4.,
l f ac h Pef uelifig Otit tge ' -
- >ote 19 Ell.F029 2' V '1" Pelief I _2 H-16 32')
PHR Purep suc t ion-Conta irmient Isola t 'ai, f,
Note 3 4
-4 p
3 l
l Ves. Note 40 E l l-F 031A
. ". _Pelief 1
2, AC
! F H 16110
.+___-9.
PHR Puup Suction-Cor tainwnt Isolat te C
Note 3 14(n 2efueling Outage 7 te 19 I
g
- 7. _
Yes re.te 80 til-F030B 2
AC 1" Relief F-4 H-16329 RHR Pump Suction-Contal#wnt Isolation C
.ote 3 Jach Pef ueling Outage Note 19 Ves. Note 40 Ell-F030C 2
AC 1" Relief F-11 H-16330 Rt#R Pump Suction-Conta f fment Isolation C
Note 3 lath Pefueling Outage Note 19
(
}
Ves. Note 40 Ell-F0300 2
AC 1_. " _ _ _ _ _.#elfef F-1 H 16329 PHR Pump Suction-Containment isolation C
No te 3 Each Pefueling Outage Nete 19 g
[Il F031A 2!C 20" Check
_r_
H _6
_H - 1_6 3_30_
_RHR Pump Discharge. _ _ -.
_... C_ _ Note _29_.
._ _. tt/ A.
.Ye, til-F0118 2
C 20" Check H-6 H-16329 RHR Pump Discharge C
Note 29 N/A fes Ell-F031C 2
C
_-_.,20" Check _ _-10_.. -16330_ RHR Pug Discharge C
Note 29 N/A H
H Ve*
Ell-F031D 2
C 20" Check H-2 H-16329 RHR Pump Discharge C
Note 29 N/A Yes
", d Every Three Months E11-F046A 2
C 3" Check H-7 H-16333 RHR Minimum Flow Line C
(Note 29)
N/A No h
6.,
,-,-, ( n,
~_.. _. _ _..
m
..._._m
.m.
4.m_
2
(-)
e.
gG'
x D t n - ) , s '. i 1 TABLf_ 4 10 23,. INSERVICE INSPECTION VALVE TEST PL AN s.4,, ASME CODE CLASS 1.2, AND 3 VALVES r 4^4.;l. If,)),
- o. n'iU
'Al',*/O n." ko b I5 2.'M'."h%f.'O,b .11--_. . 1?'! ' 'ac "'* ? E11.F073A 2 B 10" M0 Gate G-4 H-16330 RHR Service La ter Intertie C fvery_Three Months .._N/A.. _ ___. E., No E11-F0738 2 B 10" M0 0 te G-9 H-16329 RHR Service Water Intertie C Every._Three mnths __ _ _ _ _ _ N/ A .15.. NO Ell-F075A 2 B 10" M0 Gate G-4 H-16330 RHR Service Water Intertie C Every_Three Months ___ _ _ _ _. N/ A .X, NO Ell-F0158 2 B 10" M0 Gate G-9 H-16329 RHR Service Water Intertie C,,Every Three Months _ _ ___ _ N/A 55 NO .Every_ThreeM9nthJ__j __ _ __N/A_ _. 110.. No E11-Fil9A 3 8 IB* M0 Gate H-4 h-16330 RHR Servic.e Water Train A & B Cross C --H-16329-RH.R Service Water Train A &.B, Cross -C. Every Three__ Months. .~ . N/ A 110 1 . 1_1-Fil9B. 3 18." M0 Gate.H-9-- [ - - - Ell-F200A]3 8 2" A0 PCV D-11004 RHR Service Water Pump Minimum Flow C _ _. Note _9 __ _- _N/A._.. _. ho ,.q__ Ell-F200B 3 8 2" A0 PCV D-11004 RHR Service Water Pump Minimum Flow C Note 9 N/A No Ell-F200C 3 8 2" AD PCV D-11004 RHRServleWaterPump_MinimumFlow C Note 9 N]A No E11.F200D 3 8 2" A0 PCV D-11004 RHR Service Water Pump, Minimum Flow C Ngte_9_ N/A No 1/2" E11-t001A 3 B Solenoid D-11004 RHR Service Water Pump Cooling C No~e 48 N/A No l} 6-11 Amendrnent 14/19 G D (F'~~l 22) 0 0 PM Loi@ W ^ b TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN 5"I-- '.O' _.! _ ASME CODE CLASS 1.2. AND 3 VALVES ~ _ ~ _ _ ..t. _
- .0 a
, ll, .,a 4*:.h., ':;T,*.'" nL.% ~ ~ ~ 3-- 1j .,'ll M #';'ll.",% e 1/2* Ell-LOO 18 3 B Solenn td D-liOO4 RNR service Water Pump Cooling C Note 4' N/A - f No 1/2* Ell-LOGIC 3 8 Solenoid D-11004 RHR Service Water Pump Coolin9 C hte 48 N/A No 1/2" ._E. _l l_.L. O.. O_1_0_.. _3. B._ so.l. _e_no.._i d.._ _..__ __ D__11004_.RHP Service Wa ter Pump Coolin?__ __. C__..___ _ _ Note _48._ _,, _ _ _.__ N/ A _ _ _ No Core Spray Pump forus Suc tion Outboard E21-F001A 2 A 20" M0 Gate H-8 H-16331 Isolation 0 Every Three Months Each Ref ueling Outage 100 Ves. Note do Core Spray Pump Torus Suc tion Outboard E21. f0018 _ 2.A 20" M0 Ga te J8 H-16331 I sol a t io_n. ___.._. _ _ _ _ _.. _ _ _ _ 0_. E very T hree_ M.o. n_t hs_... Each Refueling Outage ___100 Ves. Note 40 l _ _ E.21_F0_0_3A _2 ..C
- 12. _"._ C_he. c k. F _9__ H-16331
. C. ore. Sprat Pump Discha_rge. C. i _ _ Note. _30 _._ _ N/A Ves ). C_ ).12" Chec k Core Spray Pump Discharge C ' tote 3') N/A Yes F-11 H-16331 E21-F0038 2 _ _ _ g.. __ _ H N/A 50 No E21-F004A 1 8 10" MD Gate E-7 , -16331 Core Spray Outhoard injec tion 0 ,Every Three Months, _, H 16_331_ Core Spray Outboard Injection _ _ _ O_ Every Three Months N/A 50 No J 21 - F 004 B_.. _1 B..10" M0 Gate B-7_ 7 J 21-F005A ._1..,A__,,lg"y_Ga_te. E, _6_ H,-Igl,__. Core Sgay 0utboard, Containment Isolation C Every Three Penths _ Each Refueling Outage 50 No. Note 3R _E.~21._- F.00 58_...._ }._ _A 10_".__MD _G_a_te. _8-6_ _H _16331 Core Spray Outboard Contairmwnt _ isola t_ ion _E_v_e_ry T_hre._e Mo._n__th.s_. _. E_ach Refueling Outage 50 No. Note 38 C g (21-F006A_ 1 AC 10" A0 Check D-4 H-16331 Core Spray injection C Cold Shutck,wn Each Refueling Outage Yes. Note 22 M E21-F0068., _1. AC 10* A0 Check C-4 H-16331 Core Spray injection C Cold Shutdown Each Refueling Outage Yes. Note 22 b .E. 21 - F012.A_,._7 C 2* Relief D-9 H-16331 Core Spray Pump Discharge Relief C Note 3 N/A No. Note 19 E l.F0129 2 C 2* Relief 8-9 H-16331 Core Spray Pump Dischas 3+ Relief C Note 3 N/A NO-N0 l' I 9 i 6d AmenJnent 14/19 6-12 5EE3 v- _~ k* { k [. - TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN v4 81 N__. m 24 ASME CODE CL ASS 1,2. AND 3 VALVES Z 4*42!. - ). [N. oen"Mf.o LT8
- Lo u[
.W.U*2.";finh I
- =
o ... ~ g Core Spray Test Bypass Containment E21-F015A 2 A 10" M0 Globe D-8 H-16331 Isolation C Every Three Months Each Refueling Outage $4 Ves. Note 40 Core Spray Test Bypass Containment E21-F01SB ' 2 A 10" M0 Glote C-8 H-16331 Isolation C Every Three Months Each Refueling Outage 54 Ves. Note 40 20* A0 E 21-F019A. 2 8-Butterfly J-6 H-16331 Core Spray Pump Torus Suction 0 Every Three Nnths N/A 22 No 20" A0 E21-F0198' 2 8 - But_terfly K-6 H-16331 Core Spray Pump Toru_s S_uctfon . _ _..-_.__eryf>ree Months N/A 22 No 0 Ev N 20 No E21-F031A 2 8 3" M0 Gate _F _9_ H-16331 _Co_re__S.pr.ay Pump Minim...u.m Flow . _ _ ___0 _E_ve_ry Three Months _... _._ / A E21-F0318 2 8 _3",M0_G_a t_e_ F-10 H-16331 Core.S_pr_a_y Pump Minim _um Flow . _0..._Ev.ery Three Naths . _. _ _ _ ' _/ A -. _. _ _..___... _.. -.. _. N 20 NL -~_ _- Core Spray Test Line - Containment N Yes. Note 21 _/A... _ _ E21-F036A 2._..AC___.._"_C_h ec. k.._ _ _ _3 --.9 9 H-163__31_. ._!_so.l..a_ti_o_n __. _ .C.g_. __..N/.A _ _...____.__ 3 E-I Core Spray Test Line. Containment E21-F0368 2 AC 3" Check E-10 H-16331 Isolation C N/A N/A Yes. Note 2I I E41-F001 2 8 10" M0 Gate E-12 H-16332 HPCI Steam Supply Shutoff C Every Three Nnths N/A 50 No Note 39 E E41-F002 1 A 10* M0 Gate C-2 H-16332 HPCI Steam Supply Inboard Isolation 0 Every Three Months Each Refueling Outage 50 Ves. Note 14 lI T E41-F003 1 A 10* M0 Gate C'-4 H-16332 HPCI Steam Supply Outboard Isolation 0 Every Three Months Each Refueling Outage 50 Yes. Note 39 Amendment 1 4/19 6-13 C4 EEU 0 9 h?LJ Mr8 w. 5EED b (. W A P... TABLE 4 g "' g-- INSERVICE INSPECTION VALVE TEST PLAN W" t ASME CODE CLASS 1.2. AND 3 P*sLVES I N,,3 . ?.. ga;;t T.T.T .4% fi .Yt.M."U.Ta o ... n
- g E.j_..
< m= aan u " ^ * * " E41-F004 2 8 16* M) Gate D-9 H-16332 HPCI,, Pump)(lion _frpm Condensate Storage _. _0,Every Three Months N/A 60 No E41-F005 2 C 14" Check F-6 H-16332 HPCI Pump Olscharge C Note 31 ft/A Yes Note 38 141-F00fi 2 A 14" M0 Gate E-5 H-16332 HPCI Pump Inboard Discharge Isolation C Cold Shutdown Each Pefueling Outage 30 No, Note 51 Ves. Note 39 E41-F007 2 8 14* M0 Gate J - 6.. H-16332 HPCQump_0utboard Disch.arge O Cold Shutdown N/A 30 Note 51 Every Three F nths E41-F008 2 A 10" N) Glotu D-7 H-16332 HPCI Pump Test Bypass isolation C (Note 4 } Each Refueling Outage Ves. Note 40 Every Ttree Pbeths HPCI Pump Recundant Shutoff to Condensate f C _E_41-F011 2 8 _. 10" M0 Gate J-7 H-16332_ 5 tora,qe N/A No Eve'y Three Months E41-F012 _., 2.. A. 4* MO, Gate _. F-7,. _ H-1,6332, HPCI Pump Min.imumflow Jnboard !$olation C (Note 47) Each Refueling Outaga Yes. Note 10 E41-F019 2 C 16" Check D-9 H-16332 HPCI Pump Nction from Condensate Storage }C' Note 31 N/A Yes 12* Stop Note 40 E41-F021 2 AC Check G-3 11- % 332 HPCI Turbine Exhaust-Inboard Isolation 0 Note 31 Each Refueling Outage Yes. Note 16
- g. $ gap
%te 40 E41-F022 2 AC ghed _ g-3_.1 16337_ UPC lJu rbj ng hhp y11 Ag i_0.*lRry3 Jio l plio n 0 Note 31 Each Refueling Outage Yes. Note 16 2* A0 E41-F035 2 8 pgy G-8_ H-16333 HPCI Tu. ine tube Oil Cooling C Note g N/A No c) Every Three Months E41-F040 2 AC 2* Chek G-5 H-163))__HPCI Turbine Exhaust Drain-Torus Isolation. C (Note 31) Each Refueling Outage Yes. Note 40 (C) .E41-F041 2 8 ]}" MQ_ggg 0-8 H-16332 HPCI Pump Suction Shutoff C Every Three ftnths N/A 70 No E41-F0'2 2 A Iq* MQ_Ga,3,J.}_ H-16J)2 HPCI Pump Suction Torus Outboard Isolation.C Every Three Months Each Refueling Outage 70, Yes. Note 40 C) E41-F045 2 C 16* Check - J-7 H-16332 HPCI Pump Ouction C Note 31 N/A Ves Every Three Months E41-f046 2 AC 4" Check F-8 H-16332 HPCI Pump Minimum Flow Outtnard Isolation C (Note 31) Each Refueling Outage Yes. Note 40 g cJ 6 14 Amendrent 14/79 '5EE3 r . -. ~ - - . ~~ . ~ - _ 1 f-A..'
- g =
's TMLE 4 t lNSERVICE INSPECTION VALVE TEST PL AN v* r e _I4. o, _24._ . ASME CODE CLASS 1.2. AND 3 VALVES ._Q)L =.n. =n a% =:,,
- ~~
}$- ll$ M ';, %, . - _ " " ".- -n ~ ~" n [very Three m nths 141-F049 2 AC 20" Check G-4 H-16332 HPCI Turbine [nhaust Outboard Isolation C (Note 31) fach Refueling Outage No 16" A0 E41-F051 2 A Butte. fly J-4 H-16332 HPCI Pump Suction forus inboard Isolation 0 Every three Months fach Refueling Outage 16 Ves. Note to E41 F059 2 8 2* m Globe F-8 H-16333 HPCI Turbine tube Oil Cooling C Every Three Months N/A 17 No HPCI Vacuum Relief Outboard Torus (41 F104 2 A 2* m Cate G-3 H-16332 Isolation 0 Every Three Months Each Refueling Outage 20 Ves. Note 40 HPCI Vacuum Relief Inboard Torus Ves. Note 40 (41-F111 2 A 2* M0 Ga te G-2 H-16332 Isolation 0 Every Three Months Each Refueling Outage 20 Note 10 10" Stop fes. Note 40 E51-F001 2 AC Check G-5 H-16334 RCIC Turbine Fahaust to Torus isolation C fvery Three Months fach Refueling Outage Note 16 2* 5 top RCIC Vacuum Pump Discharge to Torus Yes. Note 40 2. Chect G.6 H-16334 Isolation Note 16 _E51 F002 9.. _AC.. _. -..., C.. _E_very Three Nnths, _ _. _. t_ach Refueling Outage.. _ _ _ _ __.._ 6" A0. Ves. Note 40 y 151-F003 2 A Butterfly J-6 H-16334 RCIC Pump Suction - Torus isolation 0 Every Three Months fach Refueling Outage 5 Note 14 3 Yes. Note 39 E51-F007 1 A 4" MD' Gate C-5 H-16334 RCIC 5 team Supply Inboard Isolation 0 Every Three Months tach Refueling Outage 20 Note 10 [51 F008 1 A 4* M0 Cate C-6 H-16334 RCIC 5 team Supply Oratboard Isolation 0 Every Three Months tach Refueling Outage 20 Yes. Note 39 E51-F013 2 A 4* 70 Ca te E-6 H-16334 RCIC Feedwater Injection C Every Three Months Each Pefueling Outage 20 No. Note 38 1 Every Three bnths Yes. Note 40 E51 f019 ' 2 A 2* M0 Globe F-7 H-16334 RCIC Pump Minimum Flow-Torus Isolation C (Note 47) Each Refueling Outage 5 Note 10 [very Three Phnths [51-F021 2 AC 2* Check F-8 H-16334 RCIC Pump Minimum Flow-forus isolation C (Note 33) Each Refueling Outage Yes. Note 40 g n..ni i 4m l WeJ M 2EE) u 7, k ' ; ~ j w D L s: 6 TA8tt 4 i 8NSERVICE INSPECT 00a8 VALVE TEST PLAN sd t f I k.. O'
- f ASME CODE CLASS 1,2 AND 3 VALVES d
- v"<"~
e f e'll.WL*y,T,% .1'Nle lf, ceOZIm TAoi sSk .f RCIC Vacuum Pump Discharge-Torus Every Three Months E51-F028 2 AC 2" Check G-7 H-16334 Isolation C (Note 33) fach Refueling Outage Yes. Note 40 (51-F031 2 A 6* M0 Gate J-6 H-16334 RCIC Ptmp Suction-Torus isolation 0 [very Three Months fac.h Refueling Outage 35 Ves. Note 40 Every Three Months 4 E51-F040 2 AC 10* Check G-5 H-16334 RCIC Turbine Enhaust-Torus isolation C (Note 33) Each Refueling Outage Yes. Note 40 1-1/2" MD E51-F104 2 A Gate G-5 H-16334 RCIC Vacuum Breaker-Torus Isolation 0 Every Three Munths Each Refueling Outage 25 Ves. Note 40 Note 40 1-1/2" M0 E51.F105 _62--_ Gate G-5 H-16334 RCIC Vacuum Breaker-Torus Isolation _0 .fve.ry_Three % nths (ach Refueling Outage 25 Ves. Note 10 A ,A 3* A0 Gate . B-3 H-16176 Drywell Floor Drains-Containment Iso 14 tim 0 . Every, Three *nths_,tagh Refueling Outage _ 20 tes. Nete 40 Gil-F003 l_2 20 Ves. Note 40 G11-F004 ' 21 A 3* A0 Gate...,._B.3.. H. _16176.,..D_rywell Floor Drains _Contatrenent Isolation.0.... E_very,T,hr, ee, Mon,t_h_,s_ __. fach Refueling Outage...,,, i Containmen t Ves. Note 40 Gil-F019 ' 2
- A0 Gate E-3 H-16176
..D_rywel_l [qu.ipment D_ra_ ins - Isolation 0__..E v e_ry._t h. _ree,.N.n._t_h._s. _._,.f ach Refueling Outage.___15__ _ _.. _. Conta inment Evert ree Months tat.h Refueling Outage 15 Ves. Note 40 G11-F020 2 A 3* A0 Gate f-4 H-161 6 Orywell Equipment Drains - Isolation 0 Th I G31-F001 'l A 6* M0 Gate B-2 H,-161' 8 RWCU Pump Suction-Inboard Isolation 0 Every Three Months Each Refueling Outage 30 Ves. Note 39 G31-F004 1 4 6* MO Ga te ' 8-3 H-16188 RWCU Pump Suction-Outboard Isolation 0 Every Three Months Each Refueling Outage 30 Ves. Note 39 i Ves. Note 39 G31-F039 I A. 4" (heck A-5 H-16188 RWCU Discharge Isolation 0 fach Refueling Outage Each Refueling Outage Note 2 8* Manual b, G41.F001A 3 8 Outterfly D-9 H-16002 FPCCU Discharge' from Sklasner Surge Tank 0 Every Three %nthg N/A No 8". k nual G41-F0018 3 8 Butterfly - D-9 H-16002 FPCCU Discharge frem Sklasner Surge Tank 0 Every Three *nths N/A No 6-16 Amen +ent ! 4/79 PAJ B K y 5ED + b s '[.i '{ (! :.- i 4 TA8tE 4 s 16 24 INSERveCE 80eSPECTlON VALVE TEST PLAN seg e, _ o, AShsE CODE CLASS 1.2. AND 3 VALVES M*. jf. t.e OJfm T E% .....a. 6* % nual G41-F002A 3 8 Butterfly F-2 H-16002 FPCCU Pump Suction 0 Every Three %nths. N/f No 6* Manual BjB_utterFly_ G41-F0028 3 H-2 d-16002 FFCCU Pump Suction 0 (very Three Months II/A No 1 6* Manual G41-F0194 3 8 Gate D-9 H-16002 FPCCU Inlet From RHR C f very Three Months N/A No 6* Manual G41-F0198 3 8 Gate D-9 H-16002 FPCCU Inlet from RHR_ C [, very Three Months N/ A N+ 16* Manual 3kB G41-F020A Gate D-11 H-16002 FPCCU Return to PHR C (very Three %nths N/A __No _,. _ a l
- Manual 6
G41-F0208 3 8] Gate D-11 H-16002 FPCCU Return to RHR C Every_Three Months _,, _ _ N/A _- 4 _ No _ _, 2" Manual AE ;Ga te,,,, F-7 H 160 LDentneraltrer Water-Containment Isolation LCl Note 53 _ _ E ac h Refuel _.in2._0utage_, ves. Note _40__ i P21-F353 2 42" Manuel P21-F406 2 AEjGate F-8 H-16015 Demineralizer Water-Containnent isolation LC Note 53 fach_ Refueling _Qutagt Yes. Note 40 l' A0 P33-F002 ' 2 A., Control B-4 H-16276 H 2 nalyzer containment Isolation 0 E very_Three_ Months tach Refueling _0utage 5 Yes. Note 40 L _0 A l' A0 P33-F003 2 A Control 0-4 H-16276 H2 & 02 Analyzer Containment Isolation , 0_,tvery Three Months Each Refuel'n2_09ta2e 5 .vts Note 40 I 1* A0 P33-F004 2 A Contes) E-4 H-16276 H2 & 02 Analyzer Containment Isolation 0 Every Three Months [ 5 Ves. Note 40 E Q fue]Ing _0ula g l' A0 P33-F006 2 4 Control G-4 H-16276 ftp & 07 Analyzer Containment Isolation, Every Three,Mnnthy Each Refueling.QutageL 5 V'S Note 40 0 P33-F007 2 A n I H-4 H-16276 H7502 Analyzer Containment Isolation 0 Every Three Months tech Refuelin23utage 5 Ves. Note 40 C3 61, - n ni i 4,,, PA> n hee) e= ~ w&p 2, S- [_ ~ /L TABLE 4 V4 E 1 -. ' OF INSERVICE INSPECTION VALVE TEbf PLAN ASME CODE CL ASS 1,2. AND 3 VALVES l-a w i.'.:.F. g;.o w,.T .J & 3 ?f? - !!{ .T!J7'2.'J '.O n .o .i, e===== n I J_ l' A0 P33-F010 2 A Control 8-5 H-16276 Hs & 02_, Analyzer _Conta1 nen, t,, Isolation 0_ Every Three Months Each Refueling Outage 5 Yes. Note _40_ 3 I" A0 P33-F011 2 A Control 05 H-16276_. Hgpg Analyzer Containment Isolation O Every Three Mrnths Each Refueling Outage 5 Ves. Note 40 l' A0 P33-F012 2 A Control E-5 H-16276 Hy & Og Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5_ ves. Note 40 1* A0 P33-F014 2 A Control G-5 H-16276 H2 & Og Analyzer Containment Isolation 0 Every Three Months Each Refueling Outage 5 Yes. Note 40 l' A0 2 &02 Analyzer Containment Isolation _0,, Every Three Months _Each Refueling Outage _ ves. Note 40 P33-F015 2 A Control H-5 H-16276 H P41-F023A 3 C 2* Check ' A-10 H 160ll CR0 Pump Room Cooler 0 Note 32 N/A- ~..._....- -. Ves P41-F0238 3 C 2* Check 8-10 H-16011 CRD Pump Room Cooler 0 Note 32 N/A_ . _ _ ves l-1/2" Check 8-8 H-160ll HPCI Pump Room Cooler C Note 18 N/A Ves P41-F024A 3 r. 1-1/2* P41-F0248 3 C Check C-8 H-16011 HPCI Pump Poom Cooler C Note 18 N/A Yes P41-F025A 3 C 3* Check 0-8 H-160ll RHR and CS Pump Room Cooler C Note 34 N/A Ves P41-F0258 3 C 3* Che<k D-8 H-160ll PHR and C5 Pump Room Cooler C Note 34 N/A Ves P41-F026A 3 C 3*. Check G-7 H-160ll RHR Pump Cooler C Note 34 N/A Yes r P41-F0268 3 C 3* Check G-7 H-160ll RHR PJup Cooler C Note 34 N/A Ves ... ~.. 6-18 Amendment ! 4/79 w M u^ c. r INSERVICE INSPECTION VALVE TEST PLAN WD ASME CODE CLASS 1.2. AND 3 VALVES J ^.4.!!. o.u*.'Jl'. "4T.".T o? %
- =o.<=
A',',M,i;2,*ih - - _ _ -. - - _J 1-1/2* P41-F028A 3 C Chett G-2 H-160ll RCIC Pug Room Cooler C Mte 35 N/A Yes 1-1/2" P41-F0288 3 C Check G-3 H-160ll RCIC Pump Room Cooler ___.c Note 35 N/A Yes ._P_4]f_0]M_,._3_.,,8_,2* A0_ _G1cbe,._g-9,.H-16011_. HPCI Pump Room Cooler,_ C_ ___ N/A Note 41 P41-F0358 3 8 2* A0 Globe C-9 H Io011 HPCI Pug Room Cooler C Note 41 N/A Na P41-F036A 3 8 3" A0 Globe D-9 H-16011 RHR and CS Pump Room Cooler. _ _ _ ,Cl I ~ Note 42 N/A No . P_4_l-F0368__. _3, B_ 3_* A.O _ Globe _09 . _H-16011 _R_HR, and CS Pump Room Con _ler C Note 42 _,_ et/A No 7 1-1/2* A0 P41-F037A 3 8 Globe H-8 H-16011 RHR Pump Cooler C Note 44 N/ A No 1-1/2" A0 P41-F0378 3 8 Globe _{-9 H -16011 RHR Pump Cooler C Note 44 N/A No 1-1/2* A0 P41-F037C 3 8 Globe J-8 H-16011 RHR Pump Cooler C Note 44 N/A No 1-1/2* A0 P41-F037D 3 8 Globe E-9 H-]6011 PHR Pump Cooler C Note 44 N/A No i g 4___ te) m 0 0 - - - ~ 6-i8, ~~ t 4m 5W m 252D b . - - ~ _.. -.. - ~ ~ - - _. - - _. -. 4ll ~' / ,L*. g l m q i l9 q.. [ 16 TABLE 4 II I* ') ItsBEftVtCE IfeSPECTIO80 VALVE TEST Pt.Ang weeo u ASWE CODE CLASE 1.2. AfsD 3 VALVES i
- T.; =.
b: .u.. . ~. ..... ;.4 04 - r.T.A% .il w . l.... _e_. _.. L P41-F0394 3 8 3* A0 Globe G-8 p.16011__ RHR Pump Cooler C Note 42 N/A No P41-F0398 3 8_ 3* A_0 Globe G-8 H-16011 RHR Pung Cooler C Note 42 N/A b P41-F040A 3 8 2" A0 Globe N-2 H-I6011 RCIC_Pynp Roone Cooler C Note 41 N/A 880 i P41 TC408 3 8 2* A0 Globe H-3 H-16011 ,RCIC Pump Room Cooler. C _ Note 43 N/A ho l P41.F042A 3 8 3".A0 Globe A-10 H-16011 CRD Puay Room Coolee _ _. O _Nate 32 . _ _ N/ 4,_, _ _No._ _ I P41-F0428 3 8 3" A0 Globe B-10 H-16011 CRD f g Room. Cooler 0 Note 32 , _ _ _ N/ A No j ves. Note 4;I l P41-F049 2 A 8" M0 Gate F-6 H Drywell Air Coolers-Isolation 0 Note 52 55 Note 24 _-16011_. -. - - - - - - - - _ _fach Refueling Outage - q -_ Ves. Note 40 P41-F050 2 ~A '8" MO Gate 0-2 H-160ll Drywell Air Coolers-Isolation 0 Note 52 fach Refueling Outage 55 Note 24 P41 F064 3 C 6* Check F-10 H-160ll Division I supply 0 Note 36 N/A No P41-F065 3 C 8" Check G-10 H-160ll Division Il Supply 0 foote 37 N/A No 4 Every three %nths l D-11001 4 ,f M-fggg( _ 3 8 3* A0 PCV $*rvice Water,fregsgre Regu]atoL. _C (Note g .N/A No Every Three %nths { P41-F M _.,,3.B 3* A0 PCV D-11001 Service deter _fressure_Regujator C (Note 9) _N/A Na i Every Three %nths ( )_ M208C_ 3 8 3" A0 PCV 0-13001 seryfce Water Pressure Regulatgr C (Note 9) _N/A No d fvery three %nths P41-f2080 _ 3 8 3* A0 PCV D-11004 Se[yke Water Pressdegulator C @te9} N/4, NO 5: 30" N) tote Ves. Note 52 lt 0-11001 Turbine A 1)dt"2 Supply _$hytq[f O C9[djhutdown .,N/ A U, Note 24 P41-F310A_ 3 8 Butterfly 30* MO note Yes. Isote 52 l1 P41-F3108 3 8 Butterfly D-11001 Turt Ine Sulldingjupp]Dhutoff 0 Cold Shutdown N/A II f8Cte 24 6-19 Arenht i 4/19 g '5553 1 - - - - - _ - - - ~. _ -. -~.- - - - -.. - - - -...~ m 'h g 4 e c'- r ,t ?.- TABLE 4 I. 180NRVICE 18erECTIO88 VALVE TEST PLAss s*ev 2._ rw 28 f' AssE CODE CLASS 1.2. A800 3 VALVES i N'. !. )[. u.OJI.o TE oh ess...s.4 cv s...c m.ove a e p_ 30* M0 loote Ves. Note 52 P41-F310C 3 8 Sutterfly D-11001 Turbine Building supply Shutoff 0 Cold Shutdown N/A 27 Note 24 30" PO loote Ves. Note 52 P41-F3100 3 8 Butterfly D-11001 Turbine Butiding Supply shutoff 0 Cold Shutdown N/A 27 Note 24 i l' Every Three Months P41-L003A 3 8 Solenntd-0-11001 Service Water Pump - Cooling Shutoff C (Note 48) N/A No l' Every Three Phanths P41-LOO 38 3 8 Solenold _ D-1100L Service Water, Puny _ Cooling Shut _of f C. (Note 48) N/A No i l' Every Three Months P41-LOO 3C 3 8 Solenoid 0-11_001_. Service Water Pug-Cooling Shutoff C (Note 43) N/A No I I l' Every Three Months P41-LOO 30 3 8 Solenoid D-11001 Service Water Pung - Cooling _ Shutoff ._ (Note 48) N/A _No C RBCCW to Rectrculation Pump Containment Ves. Note 40 P42-F051 2 A 4* M0 Ga te 89 . _.160_0_9 Isolation 0 Cold Shut. _E a__c_h_Ref_u_el i ng O_u_t._a ge_m_3%~Note _. _52 g p RBCCW to Recirculation Pump Containment fes. Note 40 P42-F052 2 A 4
- M0 Ga te E-9 H-16009 Isolation 0
Cold Shut. Each Refueling Outage 35 note 52 2* Manuel P51-F513 2 AE Globe F-3 n.16013 Serytce Air contatnment Isolation LC Note 53 Each Refueling Outage Tes. Note 40 l 2* Menual P51-F514 2 AE Globe F-3 H-16013 Service Air Containment Isolation LC Note 53 Each Refueltag Outage Ves. Note 40 em 6-20 Amenenent 14/79 G l L_3 V-eJ L Q We) IE7) R a l 2EEi w .J 5 1 J. n m1 'A TABLE 4 INSERVICE 18eSPECTION VALVE TEST PLAN s** O . tw 2! ASME CODE CLASS 1.2. AND 3 VALVES 78.U. )[. os O*4Um W.".T o$f k h i A'l.M/af,T,1. w* 1* A0 Yes. Note 40 P70-F002 2 A Centrol F-8 ti-]_6266._.Drywell Pneumatic Containment isolation 0 Every Three Months Each Refueling Outage 5 1
- A0 Ves. Note 40 P70-F003 2
A Con.tr_gt F-8 H-16286 Drywell Pneumatic Containment Isolation 0 Every Three Months Each Refueling Outage 5 2* A0 Yes. Note to P70-7004
- 1. A._ Ion. trol.
C-Q_.3-1636 Orywell Pneumatic Containment isolation 0 Every Three Months Each Refueling Outage 5 2" A0 Yet. Note 40 _P70_-F005 2 A' Control D-8 H-16286 Drywell Pneumatic Containment Isolation 0 Every Three Nnths Each Refueling Outage 5 Note 2 PR-10N_J, AC_. 2* Ded_. _C-7_.it-162]L6_ Drywell Pneumatic Containment Isolation 0 fach Refueling Outage Each Refueling Outage Yes. Note 40 18* A0 _146-F001 A 3._ R_.59tterfis _C-L it-160M_ Filter Bed Inlet from Reactor Building C Every Three Months N/A 30 No 18" A0 1 146-F0015_ .3 , B _.. Butterfly. _G-l. H-}6C?p_ Filter Bed Inlet from Reactor Butiding C Every Three Months N/A 30 Nn 6" A0 ,_I48-fl03_J._ A_. Butterfly _ _LL H-16000_ Drywfll ), Torus, Supply. Isolation C Every_Three m nths Each Refueling Outage 5 Ves. Note 40 l' A0 _148-1104 2 J_... Control G-4 R-16000__03ywell & Torus Makeup-Outboard Isolation C_ Ewer g ree Months Each Refueling Outage 5 Ves. Note 40 2" A0 .,148-JII3 2 3.. Io.ntrg] _ F.7 g-1g__Drg1_Inerting Outboard Isolation C Every Three Months Each Refueling Outage 5 Yes. Note 40 2" A0 S _. 7. _A__ Control G-L g-16000_ _ Torus Inerting Outboard Isolation C Every Three Months Each Refueling Outage 5 Ves. Note 40 .146-fl14___.I _A._. Control _._ f-il g-1 sono Drywell Inerting Inboard Isolation C Every Three m nths Each Refueling Outage 5 Ves. Note 40 2* A0 ._.L4$-fl15 ' 2 e.T48-F116 2* A0 2 A fontrei G-8 H-16000 Torus inerting Inboard Isolation C Every Three Months Eeth Refueling Outage 5 Yes. Note 40 =., m 6-21 Anenchnent 14/79 Amendnent 2 9/80 o Y A TABLE 4 24 INSEftVICE INNECTION VALVE TEST PLAN sHE E t m ASME CODE CLASS 1.2. AND 3 VALVES E*2.L'a )[. ne EYU.om O*eT d% f TEUe'd1N o e a l' Yes. hote 40 148-F118A - 2 A Solenoid G-5 H-16000 Torus Hakeup Inboard Isolation 0 Every Three Months Each Refueling Outage 5 l' Yes. Note 40 T48-F1188 2 A Solenoid G-5 H-16000 Torus %keup Inteard Isolation 0 Every Three Nnths Each Refueling Outage 5 2* A0 148-F321 2 A Control J-7 H-16000 Drywell Inerting Outboard Isolation C Every Three N nths Each Refueling cutaje 5 Ves. Note 40 2* A0 T48-F322 2 A Control J-8 H-16000 Drywell Inerting Inboard Isolation C Every Three N nths Each Refueling Outage 5 Yes. Note 40 2* A0 148-F325 2 A Control H-7 H-16000 Torus inerting Outboard Isolation C Every Three Nnths Each Refueling Outage 5 Ves. Note 40 2* A0 T48-F327 2 A Control H-8 H-16000 Torus inertgg Inboard, tsolation C_Every_Three Nnths Each Refueling 0utage 5 Yes. Note 40 I 18* A0 Note 53 T48-F307 2 A Butterfly C-9 H-16024 Drywell Purge Inlet-letcard Isolation C None Each Refueling Outage 5 Yes. Nate_,40 18* A0 ~ Note 53 T43-F308 2 A Butterfly C-10 H-16024 Drywell Purge Inlet-Outboard Isolation C None Each Refueling _0utage_ 5_..jes._ Note,4_0 Note 53 18' A0 T48-F309 2 A Butterfly E-10 H-16024 Torus Purge inlet-Inboard Isolation C None Each Refueling _0utage _5_ _Ves. _, Note 40, 20' A0 N0t' T48-F310 2 A Butterfly F-10 H-15024 Torus Purge Vacuum Breaker Isolation C Every Three N nths Each Refueling Outa g 27 Ves. Note 40 20* A0 Note T48-F311 2 A Butterfly F-9 H-16024 Torus Purge Vacuum Breaker Isolation C Esery Three N nths Each Refueling Outage 27 Yes. Note 40 18* AG T48-F318 2 A Butterfly G-4 H-16024 Torus Purge Outlet-Inboard Isolation 0 Every Three % nths Each Refueling Outage 5 Yes._. Note 40 Note 53 18* A0 T48-F319 2 A Butterfly D-4 H-16024 Drywell Purge Outlet-Inboard Isolation C None Each Refueling Outage 5 Ves. Note 40 en u. s m A 6-27 Arendment 14/79 saY .m. . ~. f. I L 1.
- a..
..) TABLE 4 IfeSEftVICE leerECT8081 VALVE TEST PLAN 5"H ' O' 7 ASSE CODE CLASS 1,2, AND 3 VALVES .".%U. )[.
- o. n".Nf==. UT.T sJe* b
' = "oa - ;.If o 2.*f.?'".*MT.h 18' A0 Note 53 148-F320 2 A Butterfly 0-3 H-16024 Drywell Purge Outlet-Outboaid Isolation C None Each Refueling Outage 5 fes. Note 40 l1 18' A0 T48-F323A 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C_ Once Per mnth N/A No 18" A0 748-F3238 2 _C __ Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per mnth N/A N 18" A0 T48-F323C 2 C Check ' H-8 H-16024 Drpell to Torus Vacuum Breaker C_ Once Per Nath N/A N 18" A0 T48-F3230 2 C Check H-8 H-16024 Drywell to Torus Vacuum Brea6er C Once Per mnth N/A No 18* A0 148-F323E_ 2 C Check H-8 H-16024 Drywelto Torus, Vacuum _Brea6er _C_ Dnce Per _m nth ,_ N/A, _. _ _ No_ 18' A0 T48-F323F 2 C Chec k H-8 H-16024 Orywell to Torus Vacuum, Breaker __ C...Once Per Neth_ _ , _ _ N/ A _ 18" 40 T48-F323G 2 C Check H-8 H-16024 Drywell to Torus Vacuum greaker Once Per % nth N/A feo 18' A0 T48-F323H 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Nnth N/A No 18* A0 T48-F323I 2 C Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Nnth N/A No T48-F323J 2 C '8 H-16024 Drywell to Torus Vacuum Breaker C Once Per m ath N/A d-No 18" A0 T48-F323K 2 C Check H-8 H-16024 Drywell to To W acuum Breaker .g _ Once Per % nth N/A y No o IB* A0 T48-F323L 21L Check H-8 H-16024 Drywell to Torus Vacuum Breaker C Once Per Nath N/A No o
- m. e m NnEn$ 1 kfD 5559 c==
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e l I. I L L. 54 .i $e TABLE 4 INSERVICE INSPECTION VALVE TEST PLAN W f ' 2 3. o* 24 __ ASME CODE CL ASS 1.2. AND 3 VALVES Th;5 a{ '.: <.>.w.. "'"l'*"*"_". jp .m.e. .a ..n o e,3 .n a j j ..~.~ 18" A0 Nete 53 T48-F324 2 A Butterfly D-10 H-16024 Torus Purge Inlet - Outboard Isolation C None Each Refueling Outage 5 Yes. M te 40 18" A0 T48-F326 2 A Butterfly G-3 H-16024 Torus Purge Outlet - Outboard Isolation 0 Ivery Three Months Each Refueling Outage 5 Yes. Note 43 20" A0 Reactor Butiding to suppression Chamber 148-F328A 2 AC Check 6-10 H-16024 Vacuum Brealer C Every Three Months Each Refueltog Outage Yes. Nete 40 20" A0 Reactor Building to Suppression Chamber T48-F3288 2 AC Check G-9 H-16024 Vacuum Breaner C Every Three Months Each Refueling Outage Ves. Note 40 2" A0 T48-F332A ,2 A Control E-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Nnths Each Refueling Jutage 5 Yes, pote 40 2" A0 _T48-F3328__ 2 A Cont rol F-3 H-16024 Torus Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 Yes. Note 40 I 2" A0 ! 2 A Con trol. E-4 H-16024 . orus Purge Outlet - Intoard Isola tion. - - Every Three Nnths-. Ea.ch. Refueling Outage.. T C 5 Ves. Nate 40 T48-F333A. 2" A0 6 }2'A Control F-4 H-16024 Torus Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 Ves. Note 40 T48-F333B 2" A0 T48-F334A 2 A Control B-3 H-16024 Drywell Purge Outlet - Outboard Isolation C Every Three Months Eat.h Refueling Outage 5 Ye1. Note 40 2" A0 T48-F3348 2 A Control C-3 H-16024 Drywell Purge Outlet - Outboard Isolation C Every Three Months Each Refueling Outage 5 Ves. Note 40 } 2" A0 Tg T48-F335A 2 A Con trul B-4 H-16024 Drywell Purge Outlet - Inboard Isolation C Every Three Months Each Refueling Outage 5 Ves. Note 40 T48-F3358 2 A ntrol C-4 H-16024 Drywell Purge Outlet - Inboard Isolation C Every Three N nths Each Refueling Outage 5 Ves. Note 4' 2" l [ .._.-F33R T48 2 A Solenold H-2 H-16024 Bypass - Outhoard Isolation C Every Three Months Each Refueling Outage 5 tes. Note 6-24 Amendment 1 4 JE9
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r TASLE 4 88eSERVICE 19eWECT8081 VALVE TEST PLA8s sure i 24_ w 24
. AMBE CODE CLASS 1.2. AleD 3 VALVES h [8.
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l T48-F339 2
A Solenoid H-3 H-16024 Bypass-Inboard Isoletfon.
C Every Three Months
__Each Refueling Outa?e i
Ves. Note 40 2
T48-F340 2
A Solenoid 0-4 H-16024 Bypass-Outboard Isolation C
Every Three Months Each Refueling Ou u e 5
Tes. Note 40 v
2*
T48-F341 2
A Solenoid D-4 H-16024 Bypass-Inboard Isolation C
Every Three Months Each Refueling Outage 5
Ves. Note 40 1/2" b
T48-F 342A 2
A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
Isote 45 Each sefueling Outage Ves. Note 40 i
1/2*
T48-F3428 2
A Solenold H-8 H-16024 Torus to Drywell Vac Brkr. Isolation C
Note 45 Each Refueling Outage Ves. Isote 43
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l/2" T48-F342C 2
A Solenold H-8 H-16024 Torus to Drywell vac. Brkr Isolation C
Note 45 Each Refueling Outage Yes. Note 40 1/2*
T48-F3420 2
A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
Note 45 Each Refueling Outage, Yes. Note _40 y
l l
1/2" T48-F342E 2
A solenoid H-8 H-16024 Torus to Drywell Vac. Erkr. Isolation C
Note 45 Each Pefueling Outage Ves. Note 40 1/2" T48-F342F 2
A 501enold H-8 A-16024 Torus to Drywell Vac. Srkr. Isolation C
Note 45 Each Refueling Outage Yes. Note 40 1/ 2*
T48-F342G 2
'A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
Note 45 Each Pefueling Outage Yes. Note 40 1/2" T48-F342H 2
A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
flote 45 Each Refueling Outage
[
Ves. Note 40 T48-F342!
2 A
Solenold H-8 H-16024 Torus to Drywell Vac Brkr. Isolation C
Note 45 Each Refueling Outage Yes. Note 40 1/2" T48-F342J 2
A Solenoid H1 H-16024 Torus to Drywell Vac. Brkr. Isolation C
Note 45
_E _ach Pefueling Outage _- _Yes. Note 40 7
T48-F342K 2
A Solenoid H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
_ _ Note 45 Each Refueling Outage.g. Yes. '4ote 40 1
1/ 2" l
g.
T48-F 342L 2
A Solenold H-8 H-16024 Torus to Drywell Vac. Brkr. Isolation C
Note 45 Each Pefueling Outage Ves. Note 40 6-25 Amendment 14/19
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TABLE 4 N0TES 1.
The exercise test is a full-stroke test at the frequency specified unless otherwise noted.
2.
This isolation valve is a normally-open simple check valve with flow through it during normal operation.
The only means of verifying closure is to introduce reverse flow through the valve and measure the leak-1 age.
This verification is performed each refueling during the local leak rate tests.
3.
The test frequency for safety and relief valves is as required by IW-3510(a).
4.
The testing of the standby liquid control explosive-actuated valves will be performed to Technical Speci-fication 4.4.A.
This testing exceeds the requirements of IW-3610.
5.
This simple check valve has no safety-related function during a LOCA.
It is designed to prevent a water leg from forming in the relief valve discharge line under vacuum conditions. The function is not impor-tant for mitigating the consequences of an accident.
Since there is normally no flow through the valve and it is a simple check valve, there is no means to test operability.
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6.
E11-F019 is a normally-closed check valve in the head spray discharge line. Opening of the valve cannot 4
be verified unless flow is introduced through the line.
Flow through this line during normal power oper-ation will not be allowed because of the thermal stresses and reactivity fluctuations that would result as a result of the injection of cold water into the vessel.
Therefore, operability of this valve will be verified during the normal head spray operation that precedes t.old shutdown.
8 7.
The operability of this normally-closed check valve will be proven every three months during the Standby Liquid Control System pump operability tests.
3 8.
Relay logic prevents this valve from opening during normal power operation to safeguard downstream low-pressure piping.
Therefore, it will be tested during a cold shutdown (not to exceed once every three months).
9.
This valve is an air-operated pressure control valve that opens and closes at set pressures.
Stroke times are not applicable for this type valve since the valve is not required to open or close in a specific time.
As an alternative, operability will be proven every three months during pump operability tests.
I 10.
This containment isolation valve will be leak rate tested in a non-conservative reverse direction as ad-
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dressed in the containment leak rate test program for the type C leakage tests. The ocrect direction is to pressurize from the inboard side of the va?ve; however, the piping on the inboard side runs directly from the valve to the torus and cannot be pressurized for testing.
h.
FABLE 4 NOTES Page 2 11.
deleted 12.
deleted 13.
deleted 14.
This containment isolation valve will be leak rate tested in a non-conservative reverse direction as ad-dressed in the containment leak rate test program for the type C leakage tests.
The correct direction is to pressurize from the inboard side of the valve; however, the piping on the inboard side runs directly from the valve to the reactor (via the main steam lines) and cannot be pressurized for testing.
15.
deleted 16.
This turbine exhaust isolation valve is a normally-closed stop check valve with the closure mechanism in the " locked open" position.
The valve then functions as a simple check valve. The only means to verify positive closure in the " locked open" position is to introduce reverse flow from the inboard side and as d3 measure leakage; however, the piping on the inboard side runs directly from the valve to the torus and cannot be pressurized for testing.
As an alternative, the valve is closed with the closure mechanism and leak tested from the reverse side.
The leak test, as defined in the containment leak rate test program, 3
is conservative since the test pressure tends to lift the disc from the seat.
17.
deleted 18.
Proper llPCI pump room cooler operability is verified every three months during the llPCI pump operability test.
Proper cooler operability verifies that proper flow is being obtained through the cooler and the check valve has opened.
19.
The opening pressure will be determined per the requirements of ASME PTC 25.2-1966.
20.
deleted Only closure is required to fulfill the safety function of this check valve; however, since there is no
- ![21. valve between the check valve and the torus, closure cannot be verified by a leak rate test.
There are si no practical means to verify closure of this valve.
j[22.
This testable check valve cannot be opened against reactor pressure using the test switch.. Therefore, it will be tested during a cold shutdown (not to exceed once every three months).
This test opens the
,g valve approximately 10%.
There are no means to fully stroke the valve because flow is never introduced 23 through the valve.
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TABLE 4 NOTES Page 3 23.
deleted 24.
Closure of this valve during normal power operation would interrupt flow to the turbine building equip-ment normally cooled by service water.
As an alternative, it will be exercised during a cold shutdown (not to exceed once every three months).
25.
Valve 831-F031A(B) is a reactor recirculation loop closure valve.
Closure of this valve during normal i
power operation would reduce cooling water flow to the core by one-half and place the plant in an unsafe con-dition.
Therefore, it will be tr 'ed during a cold shutdown (not to exceed once every three months).
26.
This norcally-closed Standby Liqui Mntrol check valve cannot be opened without introducing flow through it with a' pressure greater than rea ir pressure. This ir, done at least once per operating cycle per Technical Specification 4.4. A during the pump flowrate testing.
27.
Baseline stroke times shall be established during the first exercise test for this valve.
Tg 28.
E11-F068A(B) is a pressure regulating control valve that modulates with changing pressure.
This valve does not fully open or close during system operation.
Therefore, stroke times are not applicable.
Proper system parameters during pump operability tests will verify the valve is functioning correctly.
29.
The opening function of this normally-closed check valve will be proven every three months during the RHR pump operability tests.
30.
The opening function of this normally-closed check valve will be proven every three months during the Core Spray pump operability tests.
1 31.
The opening function of this normally-closed check valve will be proven every three months during the HPCI pump operability tests.
32.
Proper CRD room temperature is a positive verification that the normally-operating CRD coolers are func-y tioning correctly.
This verifies that proper flow is being obtained through this valve and that it is g
open.
1
- 5r9 33.
The opening function of this normally-closed check valve will be proven every three months during the RCIC pump operability tests.
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J TABLE 4 NOTES Page 4 34.
Proper RHR and Core Spray pump room cooler operability is verified every three months during the RHR and the Core Spray Pump operability tests.
Proper cooler operability verifies that proper flow is being obtained through the cooler and the check valve is open.
35.
Proper RCIC pump room cooler operability is verified every three months during the RCIC pump operability test.
Proper cooler operability verifies that pr q er slow is being obtained through the cooler and the check valve is open.
36.
P41-F064 is a normally-open check val a supplying cooling water to the normally-operating CRD pump room cooler and the drywell air coolers.
Proper temperatures in these areas verify the valve is functioning correctly.
37.
P41-F065 is a normally-open check valve supplying cooling water to the normally-operating reactor recir-culation pump MG set coolers.
Proper temperatures in these areas verify the valve is functioning cor-i' rectly.
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1 38.
This category "A" valve communicates with the reactor coolant and provides a pressure isolation function.
It will be leak tested at the containment accident pressure (59.5 psig) and the test value extrapolated per the code to a value corresponding to system functional differential pressure. When air is used as the test medium, the test value will be assumed to be water leakage, which builds further conservatism into the test.
Limiting leakage values will be determined by the relief valve capacity in the low pressure piping.
39.
This category "A" valve is a containment isolation valve that communicates with the reactor coolant, but provides no pressure isolation function to protect low pressure piping.
Leakage through this valve is not considered to be significant in the pipe break outside containment analysis.
Therefore, this valve will be leakage tested per Appendix J criteria only.
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fp 40.
This category "A" valve is a containment isolation valve that communicates only with the containment at-g mosphere.
Therefore, it will be leakage tested per Appendix J criteria only.
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O FABLE 4 NOTES Page 5 41.
This is'an air-coerated, normally-closea, fail-open valve supplying cooling water to the HPCI coolers.
It has neither manual open/close switches nor position-indicating lights.
Actuation is accomplished by the same signal that controls the cooler.
Because of the characteristics of an air-operated valve and its method of actuation, a meaningful stroke time cannot be measured.
Any failure of the valve actuator will result in the valve going to the open position, which is the safety-related position.
As an alternative, HPCI pump room cooler operability is verified every three months during HPCI pump operability tests.
Proper cooler operability verifies that proper flow is being obtained and the valve has opened.
42.
This is an air-operated, normally-closed, fail-open valve supplying cooling water to the RHR and CS coolers.
It has neither manual open/close switches nor position-indicating lights.
Actuation is accomplished by the same signal that controls the cooler.
Because of the characteristics of an air-operated valve and its method of actuation, a meaningful stroke time cannot be measured. Any failure of the valve actuator will result in the valve going to the open position, which is the safety-related position. As an alternative, RHR and CS pump room cooler operability is verified every three months j'
during RHR and CS operability pump operability tests.
Proper cooler operability verifies that proper g
flow is being obtained and the valve has opened.
i 43.
This is an air-operated, normally-closed, fail-open valve supplying cooling water to the RCIC coolers.
It has neither manual open/close switches nor position-indicating lights.
Actuation is accomslished by the same signal that controls the cooler.
Because of the characteristics of an air-operated valve and its method of actuation, a meaningful stroke time cannot be measured. Any failure of the vahe actuator will result in the valve going to the open position, which is the safety-related position.
As an alter-native, RCIC pump room cooler operability is verified every three months during RCIC pump operability tests.
Proper cooler operability verifies that proper flow is being obtained and the valve has opened.
44.
This is an air-operated, normally-closed, fail-open valve supplying conling water to the RHR pump heat exchanger.
It has neither manual open/close switches nor position indicating lights.
Actuation is ac-complished by the same signal that controls the pump.
Because of the characteristics of an air-operated
!I valve and its method of actuation, a meaningful stroke time cannot be measured.
Any failure of the valve
{,'
actuator will result in the valve going to the open position, which is the safety-related position.
As s
an alternative, RHR pump tests are run every three months.
Proper operation of the pump verifies it is yg receiving cooling water through the open valve.
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TABLE 4 NOTES Page 6 45.
This containment-isolation valve is a normally-closed \\" solenoid valve that supplies air to the Torus to Drywell Vacuum Breakers for testing purposes.
The operability of this valve is proven each month when the vacuum breaker (T48-F323) is cycled.
Stroke times cannot be determined for this valve since it has no indicating lights.
46.
E41-F008 is a th)ottle valve used to test the llPCI pump.
Since it does not fully close or open during operation, stroke time measurement does not apply.
Operability of this valve is confirmed every three months during pump operability tests.
47.
This valve is a minimum flow valve that opens and closes at set pressures.
Since it is not required to open or close in a specific time, stroke time measurements do not apply.
Operability of this valve is confirmed every three months during pump operability tests.
48.
This is a solenoid valve that provides cooling water to the service water pump.
It is interlocked with the pump start logic system and does not have indicating lights. Because of the method of actuation T
and the lack of indicating lights, stroke times cannot be determined.
Proper operation of this valve Et is verified every three months during pump operability tests by proper system parameters.
49.
Closure of this valve during normal power operation would interrupt flow to the reacte-building equip-I ment normally cooled by service water.
As an alternative, it will be exercised during a cold shutdown (not to exceed once every three months).
50.
Closure of this valve during normal power operation would interrupt cooling water flow to the reactor recirculation pump bearings and cause possible overheating.
Therefore, it will be fully-stroked during a cold shutdown (not to exceed once every three months) and partially-stroked every 3 months.
51.
Valve E41-F007 cannot be closed during normal operation because its failure in the closed position would result in the loss of the HPCI system. Valve E41-F006 cannot be opened during normal power operation without first closing E41-F007.
Therefore, the operability of E41-F006 and E41-F007 will be demonstrated during a cold shutdown (not to exceed once every three months).
@I52.
Relief is requested from partially stroking this valve during normal power operation.
Because of control circuitry, this valve cannot be partially stroked. Once the valve is given the signal to open or close, g[
it will go to the fully open or closed position. As an alternative, it will be full-stroked each cold shutdown (not to exceed once every three months).
ao Exemption is requested from the quarterly stroke requirements of Section XI because this valve is a pas-
"' 53.
42 sive containment isolation valve.
It is normally closed and does not have to open to perform any safety-Q' related function.
A TABLE 4 NOTES Page 7 4
- 54. Testing during nomal operation requires removing the associated RHR train from operation due to differen-tial pressure across the valve, thereby decreasing the level of plant reliability. Relief is requested from 1
quarterly stroke requirements; valve would then be tested during refueling outages.
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