ML19305A404
| ML19305A404 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/30/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19305A403 | List: |
| References | |
| PROC-790430, NUDOCS 7905070544 | |
| Download: ML19305A404 (69) | |
Text
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9 Docket No. 50-P13 ATTACHMENT 1 HADDAM UECK PIANT IN-SERVICE INSPECTION AND TESTING PROGRAM l
l April, 1979 7905070544 e
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HADDAM FLECK NUCLEAR PLANT Inservice Inspection Program for ASME Code Class 1 Components The attached table provides a tabulation of the Class 1 pressure-retaining components (and their supports) that are subject to the inspection require-ments of Subsection IWB of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Summer 1975. This tabulation identifies the components to be inspected, the Section XI Examination Category, the applicable code to which the component was constructed, area to be examined, and the method of examination.
Relief from the inspection requirements of Subsec$ ion IWB is requested where these inspection require-ments have been determined to be impractical. Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative. Table IWB-2600 items that are not applicable to the Haddam fleck Plant have also been listed and identified in the interest of completeness.
The following provides further clarification concerning the Class 1 inservice inspection program:
(1) As indicated in the tabulation, 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 IWB to the extent practical.
(2) Article IWB-4000 specifies the repair procedure requirements for ASME Code Class.1 components. As components were not manufactured to the requirements of ASME Section III the rules of IWA-4000 will be applied.
(3) Article IHB-3000 specifies the standards for examination evaluation j
for ASME Code Class 1 components.
As components were not manufactured to the requirements of ASME Section III the rules of IWA-3000 will be applied.
Revision April, 1979 Q:
(4) The inservice inspection and testing programs outlined in the attached tabulation have been developed as a result of a design review.
Should certain ASi1E Section XI Code requirements be discovered to be impract'ical due to unforeseen reasons during the process of performing inspections or tests, relief will be requested from the specific Section XI Code requirement at that time.
(5) Radiation levels in certain areas or of certain components may be found to prohibit the access for operators or inspectors to perform the inspections or tests described in this program.
If source strengths cannot be reduced and access is still restricted by considerations of compliance with the requirements of Regulatory Guides 8.8 and 8.10, relief will be requested from the specific Section XI Code requirements and alternative examination or test requirements be proposed.
Codes referenced as being applicable to construction of components in the attached tables are:
ASME VIII ASME Boiler and Pressure Vessel Code,Section VIII, Pressure Vessels ASA B 31.1 USA Standard USAS B 31.1 Code for Pressure Piping
. ASA B 16.5 USA Standard USAS B 16.5 Steel Pipe Flanges, Flanged Valves and Fittings
T CONNECTICUT YANKEE ATOMIC FOWER COMPANY "f
HAODAM NECK ?;UCLEAR FLANT I
INSERVICE INSPECTION PROGRAM ASME CODE _CLt.SS 1 CO:90t;ENTS TABLE CODE TAELE IMO-2500 APPLICABLE SECTION XI K5-2500 EXAMIRATION SYSTEM OR TO EXAMINATION CODE RELIEF-ITEM "O.
CATEGORY C0;*P0NENT CONSTRUCTION AREA TO BE EXAMINED REQ'JIREMENT REQUESTED s
Bl.1
-B-A Reactor Vessel ASME VIII Intemediate to Lower Shell.
Volumetric No
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Course Circumferential Weld Interrediate Shell Course Volumetric No 81.1-B-A Longitudinal Welds (3)
Bl.1 B-A
' Lower Shell Course Longitudinal Volumetric No Welds (3) 81.2 B-B Lower Head to Shell Circumferen-Volumetric No,
tial Weld Bl.2 B-B Upper Shell Course' Longitudinal Volumetric No Welds (3)
Bl.2 B-B Upper to Intermediate Shell Volumetric No Course Circumferential Weld Bl.2 B-B Lower Head Peel Segment' Volumetric-Yes : Note 1 Meridional. Welds (6)
Bl.2 B-B Lower Head Peel Segment Volumetric Yes - Note 1 to Disc Circumferential Weld B-B Closure Head Peel Segment Volumetric No Bl.2 Meridional Welds (6)
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--+ Bl. 2 B-B Closure Head Peel Secment Volumetric Yes - Note 2 to Disc Circumferential Weld B-C
) Flange to Vessel Weld Volumetric No 81.3 i
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p-CONNECTICUT YANKEE ATOMIC POWER COMPANY.
~I HADDAM NECK NUCLEAR PLANT It' SERVICE INSPECTION PROGRAM ASME CODE CLf.SS 1 COMPONENTS
~
TABLE C'0DE -
TABLE IW3-2500 APPLICABLE SECTION XI I':5.2500 EXAFiII:ATION SYSTEM OR TO EXAMINATICN CODE RELIEF ITEM f.0.
CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED P.EQUIREMENT REQUESTED s
Bl.3 B-C Closure Head to. Flange Weld-Volumetric
.fta
.Bl.4
'B-D Outlet Nozzle to Shell Welds' (4)
Vdlunetric No s
Bl.4 B-D Inlet Nozzle to Shell Welds (4)
Volumetric No
' Bl.S.
B-E.
CRDM, Vent and In-Core Instru-Visual No mentation penetrations and CRDM Seal Nelds Bl.6 B-F Primary Nozzle to Safe-End Welds Volumetric No
& Surface-Bl.7 B-G-1 Closu-e Studs (In place)
Not Applicable No - Note 3 Bl.8 B-G-l' Closure Studs and Nuts Volumetric No
& Surface Bl.9 B-G-1 Vessel Flange Ligaments Volumetric No Bl.10 B-G-1 Closu e Washers Visual No B1.11 B-G-2 Conoseal Bolting Visual No
--** Bl.12 B-H Integrally Welded Supports Not Applicable No - Note 4 Bl.13 B-J-l Closu e Head Cladding Visual and
_No
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Surface B1.14 B-J-l Vessel Cladding Visual No o
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F CONNECTICUT YA: KEE I.TOMIC F0'**ER COM.FANY
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HA00AM tiECK 1:UCLEAR PLANT INSERVICE INEPECTION PROGRAM ASME CODE CLASS 1 J0MPONENTS o
TASLE C5DE
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N SECTION XI TA?LE I1:5-2500 APPLICABLE EXAMINATION CODE RELIEF
!G-2ECO EX23!l;ATION SYSTEM OR TO ITEii :;0.
CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED L'.lc B-N-1 Vessel Interior Surfaces and Visual No Internals Bl.16 B-N-2 Interior Attachments and Core Not Applicable No - Note 5 g,
Support Structures Bl.17 B-N-3 Core Support Structures Visual No Bl.18 B-0 Control Rod Drive Housings Volumetric No Bl.19 B-P Exempted Components Visual No B2.1
'B-B Pressurizer ASME VIII Circumferential Shell Welds (6)-
Volumetric No B2.1 B-B Longitudinal Shell Welds (5)
Volumetric No
-+ B2.2 B-D Nozzle to Vessel We..ds (6)
Volumetric No 82.3 B-E Heater Penetrations Visual No B2.4 B-F Nozzle to Safe-End Welds (6)
Surface and No Volumetric S2.5 B-G-1 Pressure Retaining Bolting Not Applicable No - Note 7 (Inplace) f B-G-1 Pressure Reta!ning Bolting Not Applicable ~ 'No - Note 7 B2.6 82.7 B-G-1 Pressu.'e Retaining Bolting Not Applicable No - Note 7 Integrally Welded Support Volumetric No B2.8 B-H 3
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HADDAM NECK hUCLEAR PLANT INSERVICE INSPECTION FROGRAM ASME CODE CLtSS 1 C0FFONENTS TABLE C6DE TASLE 11!3-2500 APPLICABLE
'SECTION XI IG-2500 EXAMINATION SYSTEM OR TO EXAMINATION CODE RELIEF ITEM NO.
CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED B2.9 B-I-2 Vessel Cladding Visual No B2.10 B-P Exempted Components Visual No B2.11 B-G-2 Manwa~y Bol' ting Visual No B3.1 B-B Steam Generators ASME VIII~
Channel Head to Tubesheet Weld Volumetric No
-(4)(Primary Side)
B3.2 B-D Nozzle to Vessel Welds Volumetric No, Note 8
-- > B 3. 3 B-F Nozzle to Safe End Welds (8)
Volumetric Yes Note 12
& Surface B3.4 B-G-1 Pressure Retaining Bolting Not Applicable No - Note 7 (In place)
B3.5 B-G-1 Pressure Retaini~ng Bolting Not Applicable No - Note 7 B3.6 B-G-1 Pressure R,etaining Boltin,g Not Applicable No - Note 7 B3.7 B-H Integrally Welded Supports ot Applicable No - Note 7 B3.8 B-I-2 Vessel Cladding Visual No B3.9 B-P Exempted Components Not Applicable No - Note 7 B3.10 B-G-2 Manway Bolting Visual
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' No B3.1 B-B Regenerative ASME VIII-Head to Shell Welds Volumetric No Heat Exchanger Shell to Tubesheet Welds Volumetric No B3.1 B-B t
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDA;i NECK MUCLEAR PLANT INSERVICE INSFECTION PROGRAM ASME CODE CL2.SS 1 COMP 0f;ENTS TABLE CODE TABLE IF:3-2500 APPLICABLE
'SECTION XI IG-2500 EX.tBI"ATION SYSTEM OR TO EXAMINATION CODE RELIEF ITE!*::0.
-CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED s
Volumetric Yes - Note 6 B3.2 B-D Nozzle to Vessel, Welds
-> B3. 3 B-F Nozzle to Safe End Welds Ndt Applicable-No - Note 7 B3.4 B-G-1 Pressure Retaining Bolting Not Applicable No - Note 7 (Inplace) 83.5 B-G-1 Pressure Retaining Bolting Not Applicable No - Note 7 B3.6 B-G-1 Pressure Retaining Bolting Not Applicable No
. Note 7 w B3.7 B-H Integrally Welded Supports Volumetric Yes - Note 10 B3.8 B-I-2 Vessel Cladding' Not Applicable No - Note 7 B3.9 B-P Exempted Components Not Applicable No - Note 7 B3.10 B-G-2 Pressure Retaining Bolting Not Applicable No
, Note 7 B4.1 B-F Piping Pressure ASA B31.1 Safe End to Pipe Welds Volumetric No Boundary and Surface B4.2 B-G-1 Pressure Retaining Bolting Not Applicable No - Note 7 (In place) 84.3 B-G-1 l
Pressure Retaining Bolting Not Applicable No - Note 7 84.4
-B-G-1 Pressure Retaining BoTting Not Applicable "No - Note 7
--+ B 4. 5 B-J Circu11ferential and Longitudinal Volumetric Yes - Note 12 Pipe Welds and 9 I
CONNECTICUT YANKEE ATOMIC POWER COMPANY
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HADDAM NECK htCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS TABLE CODE
, TAE.LE IWS-2500 APPLICABLE
-SECTION XI EXAMINATION CODE RELIEF IWB-E500 EXA"INATION SYSTEM OR-TO AREA TO BE EXAMIf:ED REQUIREMENT REQUESTED ITD' NO.
CATEG3RY COMPONENT CONSTRUCTION s
-,B4.6 B-J Branch Pipe Connection Welds Volumetric
.No Exceeding 6-inch Diameter Branch Pipe Connection Welds '
Surface No B4.7 B-J 6-inch Diameter and Smaller c
B4.8 B-J Socket Welds Surface No 084.9 B-K-1 Integrally Welded Supports Volumetric Yes - Note 10
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84,10 B-K-2 Support Components Visual No B4.11 B-P Exempted Components Visual
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No B4.12 B-G-2 Pressure Retaining Bolting
- Visual No B5.1 B-G-1 Reactor Coolant ASME VIII Pressure Retaining Bolting Volumetric No Pumps-t ASA B16.5 (In place)
-+ B5.2 B-G-1 Pressure Retaining Bolting Volumetric No and Surface 85.3 B-G-1 Pressure Retaining Bolting Visual No B5.4 l
B-K-1 Integrally Welded Supports
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Not Applicable No - Note 7 B5.5 B-K-2 Support Components
'e Visual No
% B5.6 B-L-1 Pump Casing Welds Volumetric Yes - Note 11 B5.7 B-L-2 Pump Casings Visual No B5.8 l
B-P Exempted Components Not applicable No - Note 7
' CONNECTICUT YANKEE I.TOMIC PCWER COMPANY MADDAM NECK HUCLEAR PLANT.
INSERVICE IN5PECT!0N PROGRAM ASME CODE Cl).SS 1 COM30' TENTS
~
TABLE' CODE TAILE.
IW3-2500 APPLICABLE SECTION XI 3:?-2500 EXA'!I:ATION SYSTEM OR TO REQUIREMENT REQUESTED EXAMINATION CODE' RELIEF IT:" '!0.
CATEERY COMPONENT CONSTRUCTION AREA TO BE EXAMINED s
35.9 B-G-2 Pressure Retaining Bolting '
Not Applicable No - Note 7 B5.1 B-G-1 s Valve Pressure B31.1 Pressure Retaining Bolting Volumetric No Boundary (In place)
,--* 36.2 B-G-1 Pressure Retaining Bolting Voltmetric -
No and Surface
.B6.3 B-G-1
. Pressure Retaining Bolting Visual No E6.4 B-K-1 Integrally Welded Supports Not Applicable No - Note 7 26.5 8-K-2
[
Support Components Visual No E6.6 B-M-l Valve Body Welds Not Applicable No - Note 7
~B6.7 B-M-2 Valve Bodies Visual No
-B6.8 B-P Exempted Components Visual No B6.9 B-G-2 Pressure Retaining Bolting Visual No l
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-O NOTES 1.
The examination of these welds as required by IWB-2600 from inside the vessel is restricted by the locations of the adjacent incore instru-mentation penetrations.
Examination of those areas accessible between the penetrations and conduits will be perfomed from the outside surface to the extent practical due to radiation levels.
The general area radiation levels at this location are expected to be in the 300 to 500 mr/ hour range at 3 feet from the vessel with 30,000 to 50,000 dpn surface contamination.
Examinations will not be perfonned if_ the examiners must receive a whole body dose in ~ excess of 1250 mr in order to complete any one examination.
Examinations will be performed on 5 percent or 10 percent of the total length of each' weld as required by the Code.
Examination of these welds will be performed at or near the end of the ten-year inspection interval, as allowed by the Code. Radiography cannot be utilized as an alternative examination method as access to both sides of the weld would be required.
Surface examinations would require basically the same access as ultrasonic examination and consequently, radiation levels permitting, ultrasonic examination would be perfonned.
2.
During the February,1979 refueling outage, an investigation was made by CYAPC0 and Westinghouse personnel to determine inspectibility of the RPV head peel segment welds. As can be seen from the sketch, Reference Bl.2, access for the examination of these welds is prohibited by their location relative to the CRDM penetrations, the permanent insulation and the head ventilation shroud sections. We have also attached photographs of the actual installation which shows the congestion in this area.
Inspection from the inside (clad) surface is not possible because of surface irreg-ularities, and high radiation.
Integrity of these welds will be verified during the periodic pressure tests.
3.
The reactor vessel closure studs are removed during each refueling and there will be no need for examination in place as required by INB-2600.
4.
Table IWB-2500, Category B-H, specifies that integral support pads on nozzles are excluded from the areas subject to examination.
The vessel supports of the Haddam Neck Plant vessel are pads integral with four of the eight nozzles as shown on the attached sketch, Reference Bl.12.
5.
This requirement of IWB-2600 is applicable only to boiling water type reactors.
6.
The geometric configuration of the weld surface prevents ultrasonic exam-inations being performed as required by IWB-2600.
Surface examinations will be performed on this weld in lieu of volumetric examination. a
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w 7.
There are no ' items in this examination category.
8.
The steam generator nozzles are integrally cast with the channel head and there are no welds in this category.
9.
In Loop 1 of the safety injection system, weld Number 1, a 4 inch elbow to nozzle weld is not completely inspecthble due to geometric config-uration.
This weld will be volumetrically exanined to the extent practical.
Surface examinations will be used to supplement the volumetric examinations.
- 10. The integrally welded supports are attached by fillet welds.
The config-urations of such welds is such that examinations cannot be performed to the extent required by IWB-2600 and only the base material of the component wall can be examined by ultrasonic techniques.
Surface examination will' be performed on integrally welded attachments to supplement the volumetric examination.
- 11. Volumetric examinations as required by IWB-2600 will be attempted utilizing radiographic techniques. The success of these examinations will be depen-dent upon the availability of high energy gamma sources and the level of background radiation.
Internal fitting in the pump may also provide restriction to the extent of examination that can be performed.
12.
The configuration of the (8) steam generator nozzle to safe-end welds pre-vents a complete volumetric examination fran being performed. As can be seen from the sketch, Figure B4.5, the carbon steel nozzle casting on one side and the geometry of the safe-end forging on the other side prevent full ultrasonic coverage from being possib'.e. To supplanent the limited 420 refracted L-wave examinations of the weld, transducers of other char-acterics will be utilized to the extent practical, as will surface exam-ination techniques.
It will be possible to perform a Code examination of about 60% of this weld design.
In addition, limited coverage of the steam generator safe-end to piping weld, a Category B-J weld, results from the geometry of the safe-end and the _ irregular surface condition of the weld. A volumetric examination of about 60% of this weld will also be possible.
In both cases, surface inspections will be utilized to supplement the limited volumetric examinations.
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CLASS 2 COMP 0NENTS The Class' 2 components at the Haddam Neck plant received their' first in-service inspections during the February,1979 refueling outage. The access and inspectability of the systems were limited, as discussed in the notes-accompanying the Class 2 program summary.
In all cases where examinations were limited, alternate volumetric, surface and visual inspections will be made to supplement the partial volumetric examinations, as necessary depending upon the specific limitation (s) encountered and the degree of completion of the Code Examination.
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Revision April, 1979
o CONNECTICUT YANKEE INSERVICE INSPECTION PROGRAM--CLASS 2 COMPONEh'IS ASME SECTION XI--SUBSECTION IWC "S75" ADDENDA Table Ttble IWC-2520 IWC-2600 Examination Code Applicable Examination It m No.
Category System or Component To Construction Area To Be Examined Requirement Remarks Cl.1 C-A Residual Heat Exchangrs ASFE VIII Head to Shell Welds Volumetric (2) (Tube Side)
Case 1720N Cl.1 C-A E-5-1A, 1B Secondary Shell to Tube Sheet Volumetric TEMA R Welds C1.2 C-B Nozzle to Vessel Welds Volumetric Note #6 C1.3 C-C Integrally Welded Surface Supports C1.4 C-D Tube Sheet Flange Not Applicable Note #1 Bolting C3.1 C-F Residual Heat Removal Westinghouse Pump Casing Welds Not Applicable Note #1 Pumps (2)
Specification C3.2 C-D P-14-1A, 1B Pressure Retaining Not Applicable Note #1 Bolting C3.3 C-E-1 Integrally Welded Not Applicable Note #1 Supports C3.4 C-E-2 Support Components Visual C1.1 C-A Steam Generators (4)
ASME VIII Upper Head to Shell Volumetric (Shell Side)
Special Rulings Weld E-6-1, 2, 3, 4 1270N, 1273N C1.1 C-A Upper Shell To Trans-Volumetric ition Weld 2
CONNECTICUT YANKEE INSERVICE INSPECTION PROGRAM--CLASS 2. COMPONENTS ASME SECTION XI-SUBSECTION 'IWC "S75" ADDENDA Table-Table IWC-2520 IWC-2600.
Examination.
Code Applicable Examination-Item No.
Category System or Component To Construction Area To Be Examined Requirement Remarks-Cl.1
.C-A Transition to Lower Volumetric Shell Weld C1.1 C-A Lower Shell to Tube Volumetric Sheet Weld C1.2 C-B Steam Outlet Nozzle to Volumetric Shell Weld C1.2 C-B leedwater Inlet Nozzle Volumetric to Shell Weld C1.3 C-C Integrally Welded Main Surface Lower Supports C1.4 C-D Manway Bolting Visual and Surface or Volumetric PIPING C2.1 C-F Residual Heat Removal Circumferential Butt Volumetric Notes 2, 3 Weld C2.2 C-F Longitudinal Weld Volumetric Notes 2, 3 Joints in Fittings C2.3 C-F Branch Pipe to Pipe Volumetric Notes 2, 3 Weld Joints C2.4 C-D Pressure Retaining Visual'and T.ither Bolting Surface or Vslum.
Integrally Welded Surface C2.5 C-E-1 Supports 3
CONNECTICUT YASKEE INSERVICE INSPECTION PROGRAM--CLASS 2 COMPONENTS ASME SECTION XI--SUBSECTION IWC "S75" ADDENDA Table Table
~ IWC-2520 IWC-2600 Examination Code Applicable Examination Item No.
Category System or Component To Construction Area To Be Examined Requirement Remarks C2.6 C-E-2 Support Components Visual C2.1 C-F Chemical Volume Circumferential Butt Welds Volumetric
-Notes 2,3 Control System C2.2 C-F Longitudinal Weld Joints Volumetric Notes 2,3 in Fittings C2.3 C-F Branch Pipe-to-Pipe Weld Volumetric Notes 2,3 Joints
-C2.4 C-D Pressure-Retaining Visual and Either Bolting Surface or Volum.
C2.5 C-E-1 Integrally Welded Supports Surface C2.6 C-E-2 Support Components Visual C2.1 C-G Main Steam circumferential Ntt Welds Volumetric Notes 2,3,4,5 C2.2 C-G Longitudinal Weld Joints Volumetric Notes 3,4,5 in Fittings C2.3 C-G Branch Pipe-to-Pipe Weld Volumetric Notes 2,3,4,5 Joirms C2.4 C-D Pressure Retaining Visual and Either Bolting Surface or Volum.
C2.5-C-E-1 Integrally Welded Surface Supports C2.6 C-E-2 Support Components Visual (s
7 CONNECTICUT YANKEE INSERVICE INSPECTION PROGRAM-CLASS 1 COMPONENTS ASME SECTION XI-SUBSECTION IWC "S75" ADDENDA Table Table IWC-2520 IWC-2600 Examination Code Applicable Examination
- Item No.
Category System or Component To Construction Area To Be Examined Requirement Remarks C2.1 C-G Feedwater Circumferential Butt Welds - Volumetric Notes 2,3,4,5 C2.2 C-G Longitudinal Weld Joints Volumetric Notes 2,3,4,5 in Fittings C2.3 C-G Branch Pipe-to-Pipe Weld Volumetric Notes.2,3,4,51 Joints C2.4 C-D Pressure Retaining Visual and Either Bolting Surface or Volum.
C2.5 C-E-1 Integrally Welded Supports Surface C2.6 C-E-2 Support Components Visual VALVES C4.1 C-F, C-G Valve Body Welds Not Applicable Note #1 C4.2 C-D Pressure Retaining Visual and Surface Bolting or Volumetric C4.3 C-E-1 Integrally Welded Supports Not Applicable Note #1 C4.4 C-E-2 Support Components Visual 5
6
NOTES CONNECTICUT YANKEE INSERVICE INSPECTION PROGRAM -- CLASS 2 COMPONENTS ASME SECTION XI - SUBSECTION IWC "S75" ADDENDA Note #1~
There are either no items in this category or items are excluded from examination requirement of IWC-2600 by application of criteria given in IWC-1220.
Note #2 The arrangement and details of the Class 2 piping system and components were designed and fabricater before the examination requirements of Section XI of the Code were formalized and some examinations as required by IWC-2600 are limited or not practical due to geometric configuration or accessibility.
Generally these_ limitations exist at all fitting-to-fitting welds such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface conditions preclude ultrasonic coupling or access for the required scan length.
The limitations exist to a lesser degree at pipe to fitting welds, where examination can only be fully performed from the pipe side, the fitting geometry limiting or even pre-cluding examination from the opposite side.
Welds having such restrictions will be examined to the extent practical.
Note #3 In instances where the location of pipe supports or hangers restrict the-access available for the examin-ation of pipe welds as required by IWC-2600, examin-ations will be performed to the extent practical un-less removal or relocation of the support is permis-sible without unduly stressing the system.
Surface examination will be utilized to supplement volumetric examinations to the extent permitted by access.
Note #4 The first weld immediately inside the containment pene-tration on the feedwater and main steam lines is inacces-sible due to the containment liner plate blocking the weld.
Note #5 As shown on the main steam and feedwater isometrics, there are certain pipe welds as well as the welded anchor attachment on the feedwater line outside con-tainment which are presently being inspected by'the high' energy' pipe break augmented ISI program of Techni-cal Specifications Section 4.12.
1 6
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NOTES Note #6 The reinforcing collar on;the nozzle to channel weld-precludes volumetric examination.
A surface examina-
-tion of.these welds will be conducted.
l l,
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OPERATIONAL READINESS TESTING FOR PUMPS There are fourteen-(14)' pumps at Connecticut Yankee which qualify for operational readiness testing under Subsection IWP of Section XI.
All of these pumps are either under continuous service or periodically:
surveillance-tested under the plant Technical Specifications.-
The attached tabulation of pumps' identifies the pumps' to be tested,
_ pump code-classes, parameters to be measured and test intervals.
.The provisions of Subsection IWP will be adhered to insofar as installed
. instrumentation allows at a test frequency compatible with safe operating criteria.
Revision April 11, 1979
I e
CONNECTICUT YANKEE Page 1 INSERVICE PUMP TEST PROGRAM ASME SECTION XI - SUBSECTION IWP "S75" ADDENDA ASf1E CODE TEST SECTION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS MEASURED PARAMETERS INTERVAL RELIEF REQUESTED P-18-1A Charging 2
Measurcments Taken Per P-18-1B IWP-3400b
- 1. Speed (if ' variable)
N/A
- 2. Inlet Pressure (Pi)
Ibnthly Yes - tbte #1
- 3. Outlet Pressure (Po) bbnthly tb
- 4. Differential Pressure (Pi-Po) bbnthly tb
- 5. Flow Rate Fbnthly No
- 6. Vibration Amplitude Nbnthly tb
- 7. Bearing 'Itsuperature Yearly tb
- 8. Observe Inbricant Level or Pressure Monthly tb P-14-3A Residual Heat Rmoval 2
- 1. Speed (if variable)
N/A P-14-1B (RHR)
- 2. Inlet Pressure (Pi) bbnthly Yes - Note #4
- 3. Outlet Pressure (Ib)
Fbnthly No
- 4. Differential Pressure (Pi-Po) fbnthly Ib
- 5. Flow Rate Shutdown Yes - Ibte #5
- 6. Vibration Amplitude tbnthly No
- 7. Bearing Tenperature Yearly bb
- 8. Observe Lubricant Tevel or Pressure Monthly tb Revision April 11, 1979
-:7 CONNECTICUT YANKEE Page 2 INSERVICE PUMP TEST. PROGRAM ASME SECTION XI'- SUBSECTION IWP."S75" ADDENDA ASME CODE TEST SECTION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS
' MEASURED PARAMETERS INTERVAL RELIEF REQUESTED P-15-1A High Pressure Safety 2
P-15-1B Injection (HPSI)
- 1. Speed (if variable)
N/A
- 2. Inlet Pressure (Pi)
Monthly Yes - Note #4
- 3. Outlet Pressure (Po)
Monthly No
- 4. Differential Pressure (Pi-Po)
Monthly No
- 5. Flow Rate Yes-/ Note 3 i
- 6. Vibration Amplitude
!bnthly No
- 7. Bearing Terperature Yearly '
Yes-Note-#7 l
- 8. Observe Lubricant Level er Pressure Monthly No P-37-1A Service Water (SN) 3 Measurancnts taken per P-37-1B INP-3400b
.P-37-lC-
-1. Speed (if variable)
N/A P-37-lD
- 2. Inlet Pressure (Pi) lbnthly Yes - Ibte #2
- 3. Outlet Pressure (Fo)
Ibnthly NC
- 4. Differential Pressure (Pi-Po)
Monthly No
- 5. Flow Rate Monthly No
- 6. V!.bration Amplitude Monthly No
- 7. Bearing Tanperature Yearly No
- 8. Observe Lubricant Iavel or Pressure Bbnthly No
,i Revision April 11, 1979
CONNECTICUT YANKEE Page 3 INSERVICE PUMP TEST PROGRAM ASME SECTION XI.- SUBSECTION IWP "S75" ADDENDA a
ASt1E CODE TEST SECTION XI CODE-PUMP IDENTIFICATION
_ PUMP DESCRIPTION CLASS MEASURED PARAMETERS INTERVAL RELIEF REQUESTED P-32-1A Auxiliary Steam Genera-3 P-32-1B tor Feedvater (Steam
- 1. Speed (if variable)
Monthly tb Driven)
'2. Inlet Pressure (Pi)
Monthly Ib
- 3. Outlet Pressure (Ib)
Monthly No
- 4. Differential Pressure (Pi-Ib)
Monthly No
- 5. Flow Rate Refueling Yes - Ibte #6
- 6. Vibration Arnplitude bbnthly No
- 7. Bearing Tcrperature Yearly No
- 8. Observe Inbricant Level or Pressure Ibnthly No P-92-A Iow Pressure Safety 2
P-92-B Injection (LPSI)
- 1. Speed (if variable)
N/A
- 2. Inlet Pressure (Pi) tbnthly Yes - Note #4
- 3. Outlet Pressure (Po) bbnthly No
- 4. Differential Pressure (Pi-Po) bbnthly No
- 5. Flow Rate Yes - Note #3
- 6. Vibration Anplitude bbnthly Ib'
- 7. Bearing Tmperature
' Yearly Yes-Note 7 l
- 8. Observe Inbricant Ievel or Pressure bbnthly Ib i
Revision April 11,1979
NOTES ON INSERVICE PUMP TEST PROGRAM
- 1 Due to the dmands of dependent systems, the individual testing of charging pumps as requireu by IWP-3400 (a) would jeopardize safe plant operation.
Instrumentation is installed which will permit the recording of the outlet pressure at each pump.
However, pressure measurement on the pump inlet is not available.
We propose to use the static head pressure of the volume control tank as the inlet pressure to the pump.
Correct perfomance of these pumps can only be assessed on their con-tinued ability to perfonn the function for which they were installed.
- 2 The service water pumps are vertical design with no means of direct inlet pressure measurement as required by IWP-4200.
Inlet pressure to these pumps will be established by reference to the level of the river water to that of the pump suction. Due to the demands of dependent systems, the individual testing of service water pumps as required by IWP-3400 (a) would jeopardize safe plant operation.
- 3 The HPSI and LPSI pumps as designed and installed do not have instru-mentation for the recording of flow rates as required by IWP-3100.
During tne test runs, the pumps are operated in a fixed resistance systems, so recording the pump differential pressure is sufficient per Table IWP-3100-1.
The monthly tests are run through recirculation lines which allow for flow rates of about 60% design for the HPSI pumps and 10% design for the LPSI pumps.
See Tech Specs. 4.3.
Full flow testing of these systems is scheduled for the 1980 refueling outage.
- 4 Instrumentatian is not installed which will permit the recording of the inlet pressure. We propose to use the static head pressure of the re-fueling water storage tank as the inlet pressure for the LPSI, HPSI and RHR pumps.
- 5 The RHR pump is run on recirculation monthly per Tech Spec., 4.3, and in this mode, flow is restricted by a 3/4" recirculation line and is there-fore meaningless. Flow rate measurements will be made during cold shut-downs when the Residual Heat Removal System is in normal operation.
- 6 The Auxiliary Steam Generator Feedwater Pump (Steam Driven) hydraulic test circuit does not contain flow instrumentation. Flow rate is determined during refueling outages when a special test set up allows level changes in the Demineralized Water Storage Tank to be recorded and timed to establish this measurement.
- 7 CYAPC0 requests a waiver from IWP-4310 " Temperature Measurement - Bearings" as there is no design provision to directly measure bearing temperatures in the HPSI and LPSI pumps, and results obtained thus far using pyrometers are of questionable value. Additionally, these pumps are required to run for no longer than 30 minutes in the emergency mode, so bearing temperatures would not be expected to stabilize under these conditions.
Revision April 11, 1979
April, 1979 OPERATIONAL READINESS TESTING FOR VALVES The attached. table includes all valves in the Haddam Neck Plant which are required _to be identified under Subsection IW of ASME Section XI, Summer, 1975 Addenda as further defined in NRC staff guidelines and in meetings with NRC staff reviewers, CYAPC0 and NUSCO personnel.
Most of the valves are presently under surveillance testing requirements of plant Technical-Specifications or administratively controlled by plant regulations or requirements.
In some cases, the specific requirements of IW cannot be met due to plant design, operational requirements or infringe-ment on safety margins. These situations are noted, as required and pertinent waiver requests and alternate test schmes are presented.
Valves which cannot be tested while the reactor is at power can, for the most part, be tested during cold shutdowns.
CYAPC0 has established a program to commence testing these valves within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown conditions, and to continue as time permits on subsequent shutdowns without repeating valve tests until the entire list has been completed.
Valve testing has been underway since January,1978 and although good repeat-ability has been observed on operator stroke times, CYAPC0 requests a waiver from the requirements of IW-3410(c)(3) to enable engineering dispositions to be made on stroke time variations without necessarily committing to monthly valve tests.
In addition, CYAPC0 requests a siver from IW-3410(g) _ in that the operating status of a valve would best be detemined by plant management af ter an engineering and operations review of test data. The stroke times have been derived basically from plant desigri informatian and reviewed by plant operations personnel to verify consistancy with time restraints dictated by nomal and emergency conditions.
Leak testing of pressure isolation valvas will be conducted to the requirements of IW-3420.
In some instances, it is planred to add test connections to facilitate these tests, when the necessary cesign and material procurement has been completed.
In the interim, CYAPC0 wili develop leak testing procedures to provide qualitative assurance of pressure integrity for these valves.
Relief valve setpoints will be tested in accordance with ASME PTC25.3 - 1976 in lieu of PTC25.2 - 1966 as referenced in the Summer,1975 Addendum, as the
- earlier version has been revised and superseded.
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Reactor Coolant System 16103 - 26045 Sh. 4 PR-l10V-567 1-B Pressurizer Relief Isolation 2
GA M
C Q
MT 15 sec, to open PR-M0V-569 1-B Pressurizer Relief Isolation 2
GA M
C Q
MT 15 sec. to open PR-SV-584 1-C Pressurizer Safety 3
REL SRV:
PR-SV-585 1-C Pressurizer. Safety 3
REL SRV PR-SV-586 1-C
' Pressurizer Safety 3
REL SRV PR-SV-587 2-C Pressurizer Relief 3
REL SRV PR-SV-588 2-C Pressurizer Relief 3
REL SRV April, 1979
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m-Safety Injection System 16103 - 26045 Sh. 6 SI-CV-103 2-C LPSI Discharge to RHR System 10 CK C
CV X
SI-CV-107A 2-C "A" LPSI Pump Dischame Check 10 CK C
CV X
SI-CV-107B 2-C "B" LPSI Pump Discharge Check 10 CK C
CV X
SI-CV-856A 2-C "A" HPSI Pump Discharge Check 6
CK C
CV X
SI-CV-856B 2-C "B" HPSI Pump Dischage Check 6
CK C
CV X
SI-M0V-861A 1-A Loop 1 Safety Injection Isol.
3 GA M
C Q
MT 20 sec. to open SI-MOV-861B 1-A Loop 2 Safety Injection Isol.
3 GA M
C Q
MT 20 sec. to open SI-MOV-861C 1-A Loop 3 Safety Injection Isol.
3 GA M
C Q
MT 20 sec. to open
.I SI-MOV-861D 1-A Loop 4 Safety Injection Isol.
3 GA M
C Q
l MT 20 sec. to open j
SI-CV-862A 1-AC Loop 1 SI Isolation Check 3
CK C
CV X
LT SI-CV-8628 1-AC Loop 2 SI Isolation Check 3
CK C
CV X
LT SI-CV-862C 1-AC Loop 3 SI Iso'ation Check 3
CK C
CV X
LT SI-CV-862D 1-AC Loop 4 SI Isolation Check 3
CK C
CV X
LT SI-V-863A 1-AE Loop 1 SI Test Recirc to RWST
.75 GL H
C ET LT SI-V-863B 1-AE Loop 2 SI Test Recirc to RWST
.75 GL H
C ET
.l I
LT SI-V-863C 1-AE Loop 3 SI Test Recirc to RWST
.75 GL H
C ET LT SI-V-863D 1-AE.
.75 GL H
C ET LT SI-RV-870 2-C HPSI Relief to RWST 1
REL SRV,
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16103 - 26045 Sh. 6 CD-M0V-871 A.-
1-A Core Deluge to RV Head 6
GA M
C Q
MT 10 sec. to open CD-it0V-871B 1-A Core Deluge to RV Head 6
GA-M C
Q MT 10 sec. to open' CD-CV-872A 1-AC Core Deluge to Head Check 6
CK C
CV X
LT CD-CV-872B 1-AC Core Deluge to Head Check 6
CK C
CV X
LT 4
CD-V-873 2-E RHR to Core Deluge System 6
GA H
0 ET SI-V-854A~
2-E "A" HPSI Pump Suction Isol.
8 GA H
SI-V-854B 2-E "B" HPSI Pump Suction Isol.
8 GA H
LO ET SI-V-855A 2-E "A" HPSI Pump Dischanje Isol.
6 GA H
'ET SI-V-855B 2-E "B" HPSI Pump Discharge Isol.
6 GA H
LO ET SI-MOV-24 2-E RWST Outlet to SI & CVCS 16 GA M
LO ET SI-V-104A 2-E "A" LPSI Pump Suction Isol.
12 GA H
LO ET SI-V-104B 2-E "B" LPSI Pump Suction Isol.
12 GA H
LO ET SI-V-105A 2-E "A" LPSI Pump Discharge Isol.
_10 GA H
L0 ET SI-V-105B 2-E "B" LPSI Pump Discharge Isol.
10 GA H
SI-V-102 2-E LPSI Discharge to RHR System 10 GA H
9 9
1, SYSTEM:
SAFETY IhJECTION 1.
Valve:
SI-CV-103, 107A, 1078 Class / Category:
2-C Function:
Prevent backflow from RHR system to LPSI pumps Test Requirement:
Exercise valves to full open position every three months.
Basis for Relief:
Full or partial valve exercising requires that flow be established into the reactor vessel.
System pressure downstream of these valves does not allow flow during nonnal operations.
During cold shut-downs, available volume in the reactor vessel is insufficient to acconinodate flow required for exercising these valves.
In addition, the high flow generated by the LPSI pumps would stir up crud in the SI piping and deteriorate the chemistry of the RCS water.
Alternate Testing:
CYAPC0 will use gravity flow from the RWST through these lines to partially stroke the valves at reactor refueling when the RHR systen can be taken out of service. This was done at the 1979 outage.
A full flow test is proposed during the 1980 outage while the reactor core is removed.
If this test is satisfactory, it will be done once per interval.
2.
Valve:
SI-CV-856A/B Class / Category:
2-C Function:
Prevent backflow through idle pump when one pump is running (pump discharge check valve).
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
In order to full-stroke test these valves, flow must be established into the RCS, because the pump recirc.
and test line is 3/4", insufficient to simulate design conditions.
Full flow testing of the HPSI system may only be conducted with the reactor vessel head' removed.
Because of the water chenistry and radiation exposure problens associated with pumping large amounts of water in through this system, CYAPC0 proposes to test these valves as discussed below.
Alternate Testing:
These valves will be part-stroke tested quarterly, and full-stroke tested once each interval in conjunction with full flow tests of the HPSI system.
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SYSTEM:
SAFETY INJECTION (cont'd) 3.. Valve:
SI-CV-862A/B/C/D Class / Category:
1-AC Function:
Prevent backflow from the RCS to the HPSI system.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
A full-flow test of these valves would require that HPSI flow be established into the RCS. A test of this nature would require that the RPV head be re-moved, and would result in water chemistry problems and high radiation exposure to plant personnel caused by dislodging crud in the safety injection systen piping.
Alternate Testing:
CYAPC0 proposes to part-stroke test these valves at reactor refueling outages and full-stroke test them every interval in conjunction with full flow tests of the safety injection system.
4.
Valve:
CD-CV-872A/B Class / Category:
1-AC Function:
. Prevent backflow from RCS to Core Deluge subsystem.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Exercising these valves requires that the RCS be depressurized and vented, to allow flow from the-lower pressure RHR/LPSI systems to be established.
The tests cannot be conducted at cold shutdowns because of the-water chemistry and venting require-ments discussed above.-
Alternate Testing:
These valves will be part-stroke tested at reactor i
refuelings and full-stroke tested during the safety injection system tests scheduled once each interval.
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10 GA M
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MT 60 sec. to close RH-M0V-22.
2-B Containnent Sump Suction Isol.
8 GA M
C Q
MT 60 sec. to open RH-M0V-23 2-B Containment Spray Isolation 8
GA M
C Q
X CS MT 60 sec. to open RH-V-23A 2-E Containment Spray Isolation 8
GA H
LO ET RH-MOV-25 2-B Charcoal Filter Spray Isol.
2 GA M
C Q
MT 15 sec..to open RH-MOV-26 2-B Charcoal Filter Spray Isol.
2 GA M
C Q
MT 15 sec. to open RH-MOV-27 2-8 Charcoal Filter Spray Isol.
2 GA M
C Q
MT 15 sec to open RH-MOV-28 2-B Charcoal Filter Spray Isol.
2 GA M
C Q
MT 15 sec. to open RH-MOV-29 2-B Charcoal Filter Spray Header Isol.
3 GA M
C Q
MT 18 sec. to open RH-M0V-33A 2-B RHR to CVCS X-Connect 4
GA M'
C Q
X CS MT 60 sec. to open RH-MOV-33B 2-B RHR to CVCS X-Connect 4
GA M
C Q
X CS J
MT 60 sec. to open RH-MOV-34 2-B Containment Spray Isolation 8
GA M
C Q
X CS MT 60 sec. to open RH-RV-715 2-C RHR System Relief 3
REL SRV RH-M0V-780 1-A Inboard Stop - RCS Loop No. I 10 GA M
C Q
RH-MOV-781 1-A Outboard Stop - RCS Loop No. 1 10 GA M
C Q
X CS I
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RH-CV-783 2-C Containment Sump Suction Check 8
CK C
CV X
RH-CV-788A 2-C "A" RHR Pump Discharge Check 8
CK C
CV RH-CV-788B 2-C "B" RHR Pump Discharge Check 8
CK C
CV RH-MOV-803 1-A Cutboard Stop - RCS Loop No. 2 10 GA M
C Q
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RH-MOV-804 A Inboard Stop - RCS Loop No. 2 10 GA M
C Q
X CS MT 80 sec. to open LT RH-V-808A 2-B Containment Sump Suction Isol.
8 GA H
C Q
RH-CV-808A 2-C Containment Sump Suction Check 8
CK C-CV X
RH-MOV-374 2-E RHR to RWST X-Connection 6
GA M
C ET RH-V-785A 2-E "A" RHR Pump Suction Isol.
8 GA H
0 ET RH-V-785B 2-E "B" RHR Pump Suction Isol.
8 GA H
0 ET RH-V-789A 2-E "A" RHR Pump Discha ge Isol.
8 GA H
0 ET RH-V-789B 2-E "B" RHR Pump Dischage Isol.
8 GA H
0
8 GA H
0 ET RH-V-791B 2-E "B" RHR HX. Supply Isol.
8 GA H
I' ET RH-V-794A E "A" RHR HX Return Isol.
8 GA H
0 ET RH-V-7948 2-E "B" RHR HX Return Isol.
8 GA H
0 ET RH-FCV-796 2-E RHR HX Flow Control 10 CON A
0 ET Blocked open RH-FCV-602 2-E RHR HX Bypass Flow Control 8
CON A
C ET Blocked closed 4
1.-
SYSTEM: RESIDUAL HEAT REMOVAL SYSTEM 1.
Valve:
RH-MOV-23 and RH-MOV-34 Class /Ca tegory:
- 2-B Function:
Isolates containment spray system from RHR system.
Test Requirement:
Exercise valves for operability every three months.
Basis for Relief:
The containment spray system is set up such that opening either RH-MOV-23 or 34 will initiate flow.
By entering the containment and closing manual valve RHR-V-23A, the valves could be "no flow" stroked but Tech Specs. 3.11 prevent this, as it would be dis-aoling the containment spray system.
Alternate Testing:
These valves will be exercised during cold shutdowns.
2.
Valve:
RH-MOV-33A/B Class / Category:
2-B Function:
Isolates cross-connect between RHR system and charging systen.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
RH-M0V-33A and RH-MOV-33B provide a flow path from the RIR system to the charging pump suction header.
Stroking these valves varies the suction header pressure in the charging system and could cause charging pump flow oscillations.
Alternate Testing:
These valves will be exercised at cold shutdowns.
l l
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SYSTEM: RESIDUAL HEAT REliOVAL SYSTEM (cont'd) 3.
Valve:
RH-M0V-780 and RH-MOV-781 Class / Category:
1-A
, Function:
Isolates RHR supply piping _from the RCS.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
These valves are interlocked with the Reactor Coolant System such that operation is not possible unless the RCS pressure is less than 375 psig.
Alternate Testing:
These valves will be exercised at cold shutdowns.
4.
Valve:
RH-MOV-803 and RH-M0V-804 Class / Category:
1-A Function:
Isolates RHR return piping from the RCS.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
These valves are interlocked with the Reactor Coolant Systen such that operation _ is not possible unless the RCS pressure is less than 375 psig.
Alternate Testing:
These valves will be exercised at cold shutdowns.
- 5. ' Valve:
RH-CV-783 and RH-CV-808A Class / Category:
2-C Function:
Prevent reverse flow in containment sump ouction piping to RHR system.
-Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
These valves are located in piping which is nonnally drained and do not function unless water is present in the' containment sump, as would be the case during a LOCA.
It is not practicable to flood the contain -
ment floor and sump to hydraulically exercise these valves.
Alternate Testing:
Each of these valves will be disassembled and inspected to detennine interior condition and operability once each interval. RH-CV-783 was disassembled and
. inspected in February,1979 and found to be in satis-factory condition. m
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Chemical & Volume Control 16103 - 26045 Sh. 10 BA-MOV-32 2-B RWST to Ch. Pump Suction 6
GA M
C Q
X CS MT 60 sec. to open LD-MOV-200 1-B Letdown Isol. f rom RCS 3
GA M
0 Q
X CS MT 18 sec. to close LD-RV-205 2-C Letdown System Relief 3
REL SRV CH-MOV-257 2-B VCT Outlet to Ch. Pump Suction 4
GA M
0 Q
X CS
~
MT 10 sec. to close CH-CV-263 2-C "A" Ch. Pump Discharge Check 3
CK 0
CV CH-CV-272 2-C "B" Ch. Pump Discharge Check 3
CK 0
CV CH-CV-293 1-C Chaming Line to Loop No. 2 3
CK 0
CV Verify open only CH-CV-2928 1-B Chaming Line to Loop No. 2 3
GA M
0 Q
Passive Valve CH-CV-292C 1-B Chaming Line to Loop No. 2 3
GA M
0 Q
Passive Valve i
CH-M0V-292A 1-E Charging Line to Loop No. 2 3
GA M
LO ET CH-FCV-110 2-B Charging Flow Control 3
CON A
0 Q
X RR Valve op, ens Fully on SIS j
CH-FCV-110A 2-B Charging Flow Control 3
CON A
0 Q
X RR Valve opens Fully on SIS BA-CV-320 2-C Boric Acid Supply to Ch. Pumps 2
CK C
CV X
CS BA-MOV-349 3-B Boric Acid Supply to Metering Pump 2
GA M
C Q
MT 15 sec. to open BA-CV-361 3-C "B" Boric Acid Pump Disch. Check 2
CK C
CV BA-CV-370 3-C "A" Boric Acid Pump Disch. Check 2
CK C
CV BA-MOV-366 2-B Boric Acid to Ch. Sys. Isol.
2 GA M
C Q
X CS MT 18 sec. to open BA-CV-372A 2-C RWST to Ch. Pump Suction Check 6
CK C
CV X
CS BA-MOV-373 2-B RWST to Ch. Pump Suction Isol.
6 GA M
C Q
X CS MT 20 sec. to open BA-M0V-386 2-B RWST to Metering Pump Isol.
2 GA M
C Q
MT 18 sec. to open BA-CV-387 3-C Boric Acid Pump Disch. to Ch. Pump 2
CK C
CV X
CS CH-CV-399 2-C CH. Pump Disch. to RHX 3
CK 0
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Chemical & Volume Control (cont'd:
16103 - 26045 Sh. 10 BA-V-399 3-E BA Tank Outlet Isolation 2
GA H
0 ET BA-V-352 3-E "A" BA Pump Suction Isol.
2 GA H
0 ET BA-V-359 3-E "B" BA Pump Suction Isol.
2 GA H
0 ET BA-V-362 3-E "B" BA Pump Disch. Isol.
1.5 GL H
0 ET BA-V-364 3-E "A" BA Pump Disch. Isol.
1.5 GL H
0 ET BA-V-360 3-E BA Filter Inlet Isol.
2 GL H
0 ET BA-V-371 3-E BA Filter Outlet Isol.
2 GL H
0 ET CH-V-261 2-E "A" Ch. Pump Suction Isol.
6 GA H
0 ET CH-V-270 2-E "B" Ch. Pump Suction Isol.
6 GA H
0 ET CH-V-264 2-E "A" Ch. Pump Disch. Isol.
3 GA H
0 ET CH-V-273 2-E "B" Ch. Pump Disch. Isol.
3 GA H
0 ET CH-V-286 2-E Charging to RCS; FCV-110 Isol.
3 GA H
0 ET CH-V-286A 2-E Charging to RCS; FCV-110 Isol.
3 GA H
0 ET CH-V-286B 2-E Charging to RCS; FCV-110 Isol.
3 GA H
0 ET CH-V-286C 2-E Charging to RCS; FCV-110 Isol.
3 GA H
0 ET SYSTEM:
CHEMICAL AND VOLUME CONTROL 1.
Valve:
BA-M0V-32 Class / Category:
2-8 Function:
Isolates the Refuelire Water Storage Tank from the charging pump suction header.
Test Requirenent:
Exercise valve for operability every three months.
Basis for Relief:
Cycling this valve could potentially cause a highly borated solution to reach the RCS, via the charging system, which is in continuous service.
Alternate Testing:
Exercise valve for operability at cold shutdowns.
2.
Valve:
LD-MOV-200 Class / Category:
1-B Function:
Isolates letdown flow from the RCS.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Closing this normally open valve to check operability would disrupt letdown flow. This would cause flow /
pressure transients in the charging and letdown systems.
Alternate Testing:
Exercise valve for operability at cold shutdowns.
- 3.
Valve:
CH-M0V-257 Class / Category:
2-B Function:
Isolates Volume Control Tank from charging pump 4
suction header.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Closing this normally open valve would cause the chargirs pumps to cavitate. Part stroke testi'J is not possible.
(No jog control on v' lve operator) a Alternate Testing:
Exercise valve (full-stroke) during cold shutdowns.,
o SYSTD1:
CHD11 CAL AND VOLUME CONTROL (cont'd) 4.
Valve:
CH-FCV-110, 110A Class / Category:
2-B Function:
Controls charging flow to RCS.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
These valves are arranged in parallel flow paths such that either valve can be utilized to control charging flow to the RCS. The valves are normally open and modulate to control flow. They renain open in the accident mode but assume a pre-set SIS position.
Exercising these valves full-stroke during normal operations would cause flow and pres-sure transients in the charging system.
Cold shut-down testing is not possible as stroking these valves to the accident position requires an inte-grated SIS test, performed only at refueling outages when the plant is lined up to conduct such testing.
Alternate Testing:
These valves will be full-stroke exercised at reactor refuelings during scheduled safety injection systen testing.
5.
Valve:
BA-CV-320 Class / Category:
2-C Function:
Prevents reverse flow in the boric acid solution supply line to the charging pump suction header.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Exercising this valve to the open position must be done by passing flow through it, and this could potentially cause a concentrated boric acid solution to reach the reactor, via the charging system.
Alternate Testing:
Exercise valve for operability at cold shutdowns.
6.
Valve:
BA-MOV-366 Class / Category:
2-B Function:
Isolates Boric Acid subsystem from charging pump suction header.
Test Requirement:
Exercise valve for operability every three months.
o SYSTEll:
CHEMICAL AND VOLUME CONTROL (cont'd)
Basis for Relief:
Operation of this valve while the plant is at power could potentially cause a concentrated boric acid solution to reach the reactor, via the charging i
system.
l Alternate Testing:
This valve will be exercised at cold shutdowns.
7.
Valve:
BA-CV-372A Class / Category:
2-C Function:
Prevents reverse flow into the RWST transfer line to the chargire pump suction header.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Operation of this valve while the plant is at power could cause boric acid solution to reach the reactor via the charging system. -
Alternate Testing:
This valve will be exercised at cold shutdowns.
8.
Valve:
BA-M0V-373 Class / Category:
2-B Function:
RWST to charging pump suction header isolation valve.
Test Requirement:
Exercise valve for operability every three months.
Basis for Relief:
Operation of this valve while the plant is at power could potentially cause boric acid solution to reach the reactor.
Alternate Testing:
This valve will be exercised at cold shutdowns.
9.
Valve:
BA-CV-387 Class / Category:
3-C Function:
Prevents backflow from charging pump suction header to Boric Acid subsystem.
Test Requirement:
Exercise valve for operability every three months.
' Basis for Relief:
Exercising this valve to the open position must be done by passing flow through it, and this could potentially cause a concentrated-boric acid solution to reach the reactor, via the charging system.
Alternate Testing:
This valve ~will be exercised at cold shutdowns.
4.-
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Main Steam System 16103 - 26045 Sh. 1 Stop MS-NRV-11 2-BC SG No. 1 Non-Return Valve 24 CK H
0 Q
X CS Stop MS-NRV-21 2-BC SG No. 2 Non-Return Valve 24 CK H
0 Q
X CS Stop MS-NRV-31 2-BC SG No. 3 Non-Return Valve 24 CK H
0 Q
X-CS Stop
~
MS-NRV-41 2-8C SG No. 4 Non-Return Valve 24 CK H
0 Q
X CS MS-SV-11 2-C SG No. 1 Main Steam Safety 6
REL SRV MS-SV-12 2-C SG No. 1 Main Steam Safety 6
REL SRV MS-SV-13 2-C SG No.1 Main Steam Safety 6
REL SRV MS-SV-14 2-C SG No. 1 Main Steam Safety 6
REL SRV MS-SV-21 2-C SG No. 2 Main Steam Safety 6
REL SRV MS-SV-22 2-C SG No. 2 Main Steam Safety 6
REL SRV MS-SV-23 2-C SG No. 2 Main Steam Safety 6
REL SRV MS-SV-24 2-C SG No. 2 Main Steam Safety 6
REL SRV MS-SV-31 2-C SG No. 3 Main Steam Safety 6
REL SRV MS-SV-32 2-C SG No. 3 Main Steam Safety 6
REL SRV MS-SV-33 2-C SG No. 3 Main Steam Safety 6
REL SRV MS-SV-34 2-C SG No. 3 Main Steam Safety 6
REL SRV MS-SV-41 2-C SG No. 4 Main Steam Safety 6
REL SRV MS-SV-42 2-C SG No. 4 Main Steam Safety 6
REL SRV MS-SV-43 2-C SG No. 4 Main Steam Safety 6
REL SRV MS-SV-44 2-C SG No. 4 Main Steam Safety 6
REL SRV MS-PICV-1206A 3-B Steam Supply to Aux. FP "A" 2
CON A
C Q
MT 60 sec. to open MS-PICV-1206B 3-B Steam Supply to Aux. FP "B" 2
CON A
C Q
MT 60 sec. to open MS-TV-1211-1 2-BC Main Steam Supply to Turbine 24 Stop A
0 Q
X CS CK MT 3 sec. to close MS-TV-1211-2 2-BC Main Steam Supply to Turbine 24 Stop A
0 Q
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l Main Steam System (cont'd) 16103 - 26045 Sh. I b
MS-TV-1211-3 2-BC Main Steam Supply to Turbine 24 Stop A
0 Q
X CS CK MT 3 sec. to close MS-TV-1211-4 2-BC Main Steam Supply to Turbine 24 Stop A
0 Q
X CS CK MT 3 sec. to close Stop MS-NRV-18 2-BC SG No.1 Atmospheric Dump 3
CK H
0 Q
Stop MS-NRV-28 2-BC SG No. 2 Atmospheric Dump 3
CK H
0.
Q Stop MS-NRV-38 2-BC SG No. 3 Atmospheric Dump 3
CK H
0 Q
Stop MS-NRV-48 2-BC SG No. 4 Atmospheric Dump 3
CK H
0 Q
MS-SV-1216A 3-C Aux. FP "A" Safety Valve 3
REL SRV MS-SV-12168 3-C Aux. FP "B" Safety Valve 3
REL SRV i
SYSTEll: MAIN STEAM SYSTEM 1.
Valve:
MS-NRV-11, 21, 31, 41 Class / Category:
2-BC Function:
Non-return stop check valves in main steam lines from steam generators.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
Failure of valve in a non-conservative position would cause a loss of system function.
Alternate Testing:
Full-stroke testing at cold shutdowns.
2.
Valves:
MS-TV-1211-1, -2,
-3, -4 Class / Category:
2-BC i
Function:
Main Steam Supply to Turbines Test Requirenent:
Exercise valve for operability and measure stroke time every three months.
Basis for Relief:
- Failure of valve in non-conservative position would cause loss of system function.
Alternate Testing:
Full-stroke exercise and measure stroke time during cold shutdown.
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12 GA M
0 Q
X CS FW-MOV-12 2-B SG No. 2 FW Cont. Valve Isol.
12 GA M
0 Q
X CS FW-f10V-13 2-B SG No. 3 FW Cont. Valve Isol.
12 GA M
0 Q
X CS FW-MOV-14 2-B S" No. 4 FW Cont. Valve Isol.
12 GA M
0 Q
X CS FW-MOV-35 3-B Aux. FP Disch. to SG's 3
GA M
C Q
MT 15 sec. to open FW-CV-143-1
~
2-C FW Supply to SG No. 1 12 CK 0
CV X
Verify open only FW-CV-143-2
'2-C FW Supply to SG No. 2 12 CK 0
CV X
FW-CV-143-3 2-C FW Supply to SG No. 3 12 CK 0
CV X
FW-CV-143-4 2-C FW Supply to SG No. 4 12 CK 0
CV X
FW-CV-153B 3-C "A" Aux. Feedpump Disch. Check 3
CK C
CV X
CS FW-CV-184 3-C "B" Aux. Feedpump Disch. Check 3
CK C
CV X
CS FW-CV-156-1 2-C Aux. FW Supply to SG No. I 1.5 CK C
CV X
CS FW-CV-156-2 2-C Aux. FW Supply to SG No. 2 1.5 CK C
CV X
CS FW-CV-156-3 2-C Aux. FW Supply to SG No. 3 1.5 CK C
CV X
CS FW-CV-156-4 2-C Aux. FW Supply to SG No. 4 1.5 CK C
CV X
CS FW-FCV-1301-1 2-8 SG No. 1 FW Reg. Valve 8
CON A
0 Q
X CS MT 60 sec. to close FW-FCV-1301-2 2-8 SG No. 2 FW Reg. Valve 8
CON A
0 Q
X CS MT 60 sec. to close FW-FCV-1301-3 2-8 SG No. 3 FW Reg. Valve 8
CON A
0 Q
X CS MT 60 sec, to close FW-FCV-1301-4 2-B SG No. 4 FW Reg. Valve 8
CON A
0 Q
X CS MT 60 sec. to close FW-HICV-1301-1 2-B SG No.1 FW Reg. Bypass Valve 1.5 CON A
C Q
X CS MT 30 sec. to open FW-HICV-1301-2 2-8 SG No. 2 FW Reg. Bypass Valve 1.5 CON A
C Q
X CS MT 30 sec to open FW-HICV-1301-3 2-B SG No. 3 FW Reg. Bypass Valve 1.5 CON A
C Q
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Feedwater System (cont'd) 16103 - 26045 Sh. 2 FW-HICV-1301-4 2-B SG No. = 4 FW Reg. Bypass Valve 1.5 CON -
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SYSTEM: FEEDWATER SYSTEM 1.
Valve:
FW-M0V-11, 12, 13, 14 Class / Category:
2-B Function:
Stop valves in feedwater lines to steam generators.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
Open passive valve during operations and emergency conditions.
Failure of valve in non-conservative position would cause loss of system function.
Alternate Testing:
These valves will be cycled at cold shutdowns.
2.
Valves:
FW-CV-153B, 184 Class / Category:
3-C Function:
"A" and "B" auxiliary feedpumps discharge checks.
Test Requirement:
Exercise to open position every three months.
Basis for Relief:
Full or partial stroke testing of these valves requires that an auxiliary feedpwap be started and flow be established to the Steam Generators.
This test is undesirable while the reactor is at power because of the steam generator thermal shock potential.
The pumps take suction on the Deminer-alized Water Storage Tank (cold water).
Alternate Testing:
These check valves will be exercised at cold shut-down.
3.
Valves:
FW-CV-156-1, -2,
-3, -4 Class / Category:
2-C Function:
Check valves in auxiliary feedwater supply to steam generators.
Test Requirement:
Exercise to open position every three months.
Basis for Relief:
Full or partial stroke testing of these valves requires that an auxiliary feedpump'be started and flow be established to the Steam Generators.
This test is undesirable while the reactor is at power because of the steam generator thennal shock potential. The pumps take suction on the Deminer-i alized Water Storage Tank (cold water). c
a SYSTEM: FEEDWATER SYSTEM (cont'd) 4.
Valves:
FW-FCV-1301-1,
-2,
-3, -4 Class / Category:
2-B Function:
Main feedwater regulating valves.
Test Requirement:
Exercise for operability every three months..
Basis for Relief:
Failure of valve in non-conservate position would cause loss of system function.
Alternate Testing:
These valves will be cycled at cold shutdowns.
5.
Valves:
FW-HICV-1301,
-2,
-3, -4 Class / Category:
2-B Function:
Feedwater regulating bypass valves.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
Cycling these normally closed valves during operation causes severe veter hammer problens.
Alternate Testing:
These valves will be cycled at cold shutdowns. --. _,
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Service Water System 16103 - 26045 Sh. 9 SW-MOV-1 3-B East Header Isolation 12 GA M
0 Q
X CS MT 60 sec. to close SW-MOV-2 3-B West Header Isolation 12 GA M
0 Q
X CS MT 60 sec, to close SW-MOV-3 3-8 CCHX "A" Discharge 16 GA M
0/C Q
'X CS MT 60 sec. to close SW-MOV-4 3-B CCHX "5" Discharge 16 GA M
0/C Q
X CS MT 60 sec. to close SW-MOV-5 3-B RHRHX "B" Supply 12 GA M
C Q
X 5 yr.
MT 60 sec, to open SW-M0V-6' 3-B RHRHX "A" Supply 12 GA M
C Q
X 5 yr.
MT 60 sec. to 9 pen SW-A0V-8 3-B Boron Recovery Return Isol.
8 CON A
C Q
MT 5 sec. to-open SW-A0V-9 3-B SFP HX Return Isol.
6 CON A
0 Q
MT 5 sec. to close SW-V-129 3-B "A" Diesel Cooling Return 4
CON A
C Q
MT 15 sec. to open SW-V-130 3-B "B" Diesel Cooling Return 4
CON A
C Q
MT 15 sec. to open SW-CV-276A 3-C "A" SW Pump Disch. Check 16 CK 0
CV SW-CV-2768 3-C "B" SW Pump Disch. Check 16 CK 0
CV SW-CV-276C 3-C "C" SW Pump Disch. Check 16 CK 0
CV SW-CV-276D 3-C "D" SW Pump Disch. Check 16 CK 0
CV m
SYSTEM: SERVICE WATER SYSTEM 1.
Valves:
SW-MOV-1, 2 Class /Ca tegory:
3-B Function:
East and West service water header isolation valves.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These valves control service water cooling to several essential plant loads. Failure of valve in non-open position could cause overheating of these loads resulting in loss of generation.
Alternate Testing:
These valves will be exercised at cold shutdowns.
2.
Vmlves:
SW-MOV-3, 4 Class / Category:
3-B Function:
Canponent cooling heat exchangers cooling water dis-charge stops.
Test Requirement:
Exercise for operability every three months.
Basis for Relief:
These valves control service water cooling to the canponent cooling heat exchangers. Failure of valve in non-open position could cause overheating resulting in loss of generation.
Alternate Testing:
These valves will be exercised at cold shutdowns.
3.
Valves:
SW-MOV-5, 6 Class / Category:
3-B Function:
These valves open to supply service water to the residual heat exchangers in the. event of a failure in the component cooling system. There is no auto-matic operation.
Basis for Relief:
Stroking these valves requires that the service water system be cross-connected with the component cooling water system to provide energency flow to the Resid-ual Heat Removal Heat Exchangers.- The service water system utilizes water from the Connecticut River, and the component cooling water system.is a closed system containing potentially contaminated water.
Cross-connecting could result in releasing non-con-fonning water to the river, and require a major cleanup of system components, which would require.
E.
SYSTEM:
SERVICE WATER SYSTEM (cont ld) that they be taken out of service during the restoration process.
These valves were satisfactorily cycled during the February,1979 refueling outage when special arrangements could be made to minimize the cleanup..They had not been stroked in the past ten years, so the tests concluded that the valves were still able to fulfill their function.
Alternate Testing:
We propose to exercise these valves each five years.
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-m Containment Isniation DH-TV-1847 1-A Drain Header 1.5 CONT A
0.
Q MT LT X
ILRT BD-V-506 2-AE SG No. 1 Blowdown 2
GA H
C ET LT X
ILRT BD-V-515 2-AE SG No. 2 Blowdown 2
GA H
C ET LT X
ILRT BD-V-522 2-AE SG No. 3 Blowdown 2
GA H
C ET LT X
ILRT BD-V-529 2-AE SG No. 4 Blowdown 2
GA H
C ET LT X
ILRT BD-TV-1312-1 2-A SG No. 1 Blowdown 1
CONT A
0 Q/MT X
CS LT X
ILRT BD-TV-1312-2 2-A SG No. 2 Blowdown 1
CONT A
0 Q/MT X
CS LT-X ILRT BD-TV-1312-3 2-A SG No. 3 Blowdown 1
CONT A
0 Q/MT X
CS LT X
ILRT BD-TV-1312-4 2-A SG No. 4 Blowdown 1
CONT A
0 Q/MT X
CS LT X
ILRT CC-CV-885 2-AC CC Wtr. to Neutron Shield Tank 1.5 CK CV X
Passive Cooler LT X
ILRT CC-TV-1831 2-A CC Water from Neutron Shield Tank 1.5 CONT A0 Q/MT X
CS Cooler LT X
ILRT CC-V-884 2-AE Neutron Shield Tank Fill Line 1.5 GA H
ILRT VS-TV-1848 2-A Air Monitor Sample from Containmen t 1 GA A0 Q/MT X
CS LT X
ILRT S0V-12-1 2-A Air Monitor Sample f rr.m Containmen L.75 GA S0L Q/MT X
CS LT X
ILRT VS-CV-1104 2-AC Air Monitor Sample to Containment 1
CK CV X
Passive LT X
ILRT I
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Containment Isolation (cont'd)
CC-CV-731 2-AC i CC Water Supply to Drain Cooler 3
CK CV X
Passive LT X
ILRT FCV-611 2-A CC Water from Drain Cooler 3
CONT A0 Q/MT
-X CS LT X
ILRT VH-V-507 2-AE Primary Vent Header 2
GA H
ILRT VH-V-5078 2-AE Primary Vent Header 2
GA H
ILRT DH-TV-554 2-A PRT Drain 2
GA A0 Q/MT X
CS LT X
ILRT WD-HICV-1840 2-A Sump Pump Discharge 2
CONT A0 Q/MT X
CS LT.
X ILRT WD-lV-1846 2-A Sump Pump Discharge 2
CONT A0 Q/MT X
CS LT X
ILRT DH-TV-1843 2-A Vapor Seal Head Tank Drain 1.5 GA A0 Q/MT X
CS LT X
ILRT DH-TV-1844 2-A Vapor Seal Head Tank Drain 2
GA A0 Q/MT X
CS LT X
ILRT LM-TV-1811A 2-A Open Bulb Leak Monitoring
.375 GA A0 Q/MT X
CS LT X
ILRT LM-TV-1811B 2-A Open Bulb Leak Monitoring
.375 GA A0 Q/MT X
.CS LT X
ILRT LM-TV-1812 2-A Closed Bulb Leak Monitoring
.375 GA A0 Q/MT X
CS LT X
ILRT CC-CV-853 2-AC CC Water to RCP Oil Coolers 6
CK CV X
Passive LT X
ILRT CC-TV-1411 2-A CC Water from RCP Oil Coolers 6
CONT A0 Q/MT X
CS LT X
ILRT CC-FCV-608 2-A CC Water from RCP Thermal Barrier 3
CONT A0 Q/MT X
CS LT X
ILRT I
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m Containment Isolation (cont'd)
CC-CV-721 2-AC CC Water to RCP Thermal Barrier 3
CK CV X
Passive LT X
ILRT WG-A0V-558 2-A PRT Vent Trip
.75 GL A0 Q/MT X
CS LT X
~
WG-TV-1845 2-A PRT Vent Trip 1
GA A0 Q/MT X
CS LT X-ILRT SS-V-984A 2-A PRT Sample
.5 GL H
Q X
Passive
~
LT X
ILRT SS-TV-950 2-A Loop and Pressurizer Drain
.375 GL A0 Q/MT X
CS LT X
ILRT SS-TV-955 2-A Pressurizer Steam Space
.375 GL A0 Q/MT Y
CS LT X
ILRT SS-TV-960 2-A Pressurizer Liquid Space
.375 GL A0 Q/MT X
CS LT X
ILRT SS-TV-965 2-A Loop 1 Hot Leg
.375 GL A0 Q/MT X
CS LT X
ILRT DH-TV-1842A 2-A Valve Stem Leak-Off 1.5 CONT A0 Q/MT X
CS LT X
ILRT DH-TV-18428-2-A Valve Stem Leak-Off 1.5 CONT A0 Q/MT X
CS LT X
ILRT SS-V-999 2-AE Neutron Shield Tank Sample
.375 GA H
ILRT SS-V-999A 2-AE Neutron Shield Tank Sample
.375 GA H
ILRT PW-CV-139 2-AC Primary Water to Containraent 2
,C K C
CV X
Passive LT X
ILRT PW-CV-140 2-AC Primary Water to Containment 2
CK C
CV X
Passive LT X
ILRT HC-V-212 2-AE Space Heating Condensate Return 3
GA H
ET LT X
ILRT o
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PU-V-242 2-AE Refueling Cavity Purification 3
GA H
C ET LT X
ILRT PU-V-242A 2-AE Refueling Cavity Purification 3
GA H
C ET LT X
ILRT HS-CV-295 2-AC Containment Space Heating Supply 6
CK C
CV X
Passive LT X
ILRT HS-CV-295A 2-AC Containment Space Heating Supply 6
CK C
CV X
Passive LT X
ILRT BV-1-1B 2-AE Containment Pu ge Air Exhaust 42 BFLY H
C ET LT X
ILRT HCV-1101 2-AE Containment Purge Air Exhaust Bypas s8 GA H
C ET LT X
ILRT BV-1-1A 2-AE Containment Pug e Air Supply 42 BFLY H
C ET LT X
ILRT P50 2-AE Fuel Transfer Tube 24 GA H
C ET LT X
ILRT SA-V-411A 2-AE Air Monitor Purge
.75 GA H
C ET LT X
ILRT SA-V 413 2-AE Service Air Supply to Containment 2
GA H
C ET LT X
ILRT LD-A0V-202 1-A Letdown Orifice Control 2
CONT A
0/C Q/MT X
CS LT X
ILRT LD-A0V-203 1-A Letdown Orifice Control 2
CONT A
0/C Q/MT X
CS LT X
ILRT LD-A0V-204 1-A Letdown Orifice Control 2
CONT A
0/C Q/MT X
CS LT X
}
CH-TV-334' 2-A Seal Water Return Line Trip 4
CONT A
0 Q/MT X
CS LT X
ILRT l
CH-CV-305A 1-AC RCP No. 1 Seal Water Supply 2
CK 0
CV X
CS LT X
ILRT -
I O
w 5
E 5
2 a
E c
8 5
5 0 $e m
w5 m8 e
up 60 5
~
w Sie es e
a a
za ms as ms
[
NE d$
G E
E WE EE
- d
=
Containment Isolation (cont'd)
CH-CV-305B 1-AC RCP. No. 2 Seal Water Supply 2
CK 0
CV X
CS LT X
ILRT CH-CV-305C 1-AC RCP No. 3 Seal Water Supply 2
CK 0
CV X
CS LT X
ILRT CH-CV-305D 1-AC RCP No. 4 Seal Water Supply 2
CK 0
CV X
CS LT X
ILRT DH-TV-1841 1-A Drain Header 1.5 CONT A
0 Q/MT LT X
ILRT DH-TV-1844 2-A PRT Drain 2
GA A0 Q/MT X
CS LT X
ILRT FM-MOV-31 2-A Aux. Containment Spray From 8
GA M0 C
Q/MT X
Passive Fire System
'~
X ILRT FW-CV-192 2-AC Aux. FW Supply to SG No. 4 1.5 CK C
uV X
Passive LT X
ILRT FW-CV-194 2-AC Aux. FW Supply to SG No. 3 1.5 CK C
CV X
Passive X
T '.RT FW-CV-196 2-AC Aux. FW Supply to SG No. 2 1.5 CK C
CV X
Passive X
ILRT FW-CV-198 2-AC Aux. FW Supply to SG No. I 1.5 CK C
CV X
Passive X
ILRT FH-CV-296 1-AC Loop Fill Header Check 2
CK C
CV X
None Passive LT X
ILRT 4
r, SYSTEM: VARIOUS - CONTAINMENT ISOLATION 1.
Valves:
See List of CIV's Class / Category:
2-A, 2-AC, 2-AE Function:
To insure containment integrity in event of require-ments to isolate.
Test Requirement:
Exercise all active valves every three months and detennine leak tightness not less than once every two years.
Basis for Relief:
This list consists only of valves whose safety function is containment isolation. Those CI valves which are used also far system pressure isolation are listed under the particular system in which they operate.
Operability testing of these valves during nonnal plant operation could cause a loss of containment integrity and/or system function if a valve failed in a non-conservative position.
Because the safety function of these valves is to pro-vide containment integrity by their leak tightness, these valves are and have been leak tested under Tech.
Spec. requirements based on " App. J, Type C" tests.
See Tech. Spec. 4.4.
In that leakage tests are conducted to satisfy con-tainment integrity requirenents, waivers from IWV-3420 (b) " Analysis of Leakage Rates" and (g) " Corrective Action" are requested. CYAPC0 proposes.to demonstrate leak tightness by following containment integrity rules, which observe an integrated acceptance criterion for these test parameters, in lieu of individual valve perfonnance measurement.
Alternate Testing:
CYAPC0 proposes to use existing procedures for exercising and leak testing of valves used as containment isolation.
Modifications to procedures as agreed upon by CYAPC0 and NRC Staff concerning " App. J" tests and exemptions will be reflected in this program.
All " active" containment isolation valves are exercised at cold shutdowns by a procedure to demonstrate the Reactor Containment Atmospheric Control System Functions properly should an overpressure situation exist in the reactor containment, by verifying that all automatic actions required of the system under this condition do occur.
l All passive valves (those not required to change position).per NRC Guidelines do not require exercising.
I.o n
LEGEND FOR VALVE TESTING-Q
- Exercise valve (full stroke) for operability every (3) months.
LT
- Valves are leak tested per Section XI Article IWV-3420.
ILRT - Valves are leak tested in conjunction with containment inte-grated leak test.
- Stroke time measurements are taken per Section XI Article IWV-3410.
CV
- Exercise check valves to the position required to fulfill their function every (3) months.
SRV - Safety and relief valves are tested per Section XI Article IWV-3510.
- Verify and record valve position before operations are performed and after operations are conpleted, and verify that valve is locked or sealed.
- Exercise valve for operability every cold shutdown.
- Exercise valve for operability every reactor refueling.
i l
i -
f-o Docket No. 50-213 l
ATTACID4ENT 2 HADDAM NECK PLANT ISI/IST PROGRAM PHOTOGRAPH DESCRIPTIONS April, 1979 l
[_
[O O
Photo #1 This view shova the installation of the reactor vessel head studs.
The sheet metal shown is part of the head ventilation shroud assembly.
The white coiln,are rod position indicators, the gray boxes are rod drive gripper coils, and the white pubstance between control rod drive mechanisms is a " poured in" insulation which is permanently installed.
t Photo #2 This view is of top of head. The square bar in the foreground is for lifting the head. The striped pipe contains core instrumentation, and the gray boxes with the eye bolts are the rod drive gripper coils, i
!