ML070570291
| ML070570291 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/11/2006 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| O'Hara T, RI/DRS/PSB2, (610) 337-5043 | |
| References | |
| AMRM-20 | |
| Download: ML070570291 (26) | |
Text
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 2 of 26 REVISION DESCRIPTION SHEET Revision Number Description Pages and/or Sections Revised 0
Initial Issue
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 3 of 26 TABLE OF CONTENTS 1.0 Introduction........................................................................................................... 4 1.1 Purpose................................................................................................................. 4 1.2 System Description............................................................................................... 4 1.3 System and Component Intended Functions........................................................ 5 2.0 Screening.............................................................................................................. 6 3.0 Aging Effects Requiring Management................................................................... 7 3.1 Drywell Sump Penetrations (X-18 and 19)............................................................ 7 3.2 Recirculaton Pump Seal Sensing Lines and Seal Purge (X-31E, F; X-32E, F)..... 7 3.3 Traversing Incore Probe Penetrations (X-35A, B, C)............................................ 8 3.4 Traversing Incore Probe Purge Gas Penetration (X-35E)..................................... 9 3.5 Suppression Pool Drain Penetrations (X-213A and B)......................................... 9 3.6 Spare Penetrations (X-15, 17, 20, 29E, 29F, 33D, 35D, 36, 43, 44, 45, 46, 48, 50D, 50E, 50F, 101B, 106, 107 and 219)...................................................................... 9 3.7 Bolting................................................................................................................. 10 3.8 Operating Experience......................................................................................... 10 4.0 Demonstration That Aging Effects Will Be Managed.......................................... 11 4.1 Containment Leak Rate Program........................................................................ 11 4.2 System Walkdown Program................................................................................ 12 4.3 Water Chemistry Control - BWR Program........................................................... 12 4.4 Time-Limited Aging Analyses.............................................................................. 12 5.0 Summary and Conclusions................................................................................. 13 6.0 References.......................................................................................................... 14 Attachments.................................................................................................................... 16 Components Subject to AMR.................................................................. 16 Aging Management Review Results........................................................ 20 List of Mechanical Primary Containment Penetrations............................ 22
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 4 of 26 1.0 Introduction 1.1 Purpose This report is part of the aging management review (AMR) of the integrated plant assessment (IPA) performed to extend the operating license of Vermont Yankee Nuclear Power Station (VYNPS). This report demonstrates the effects of aging on passive mechanical components in primary containment penetrations that were not reviewed in other AMRRs will be adequately managed so that the intended functions will be maintained consistent with the current licensing basis as required by 10 CFR 54.21(a)(3). For additional information on the license renewal project and associated documentation, refer to the License Renewal Project Plan.
The purpose of this report is to demonstrate that aging effects for passive mechanical components will be adequately managed for the period of extended operation associated with license renewal. The approach for demonstrating management of aging effects is to first identify the components that are subject to aging management review in Section 2.0. The next step is to define the aging effects requiring management for the system components in Section 3.0. Section 4.0 then evaluates if existing programs and commitments adequately manage those effects.
Applicable aging effects were determined using EPRI report 1003056 Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools (Ref. 1). This EPRI report provides the bases for identification of aging effects based on specific materials and environments and documents confirmation of the validity of the aging effects through review of industry experience. This aging management review report (AMRR), in conjunction with EPRI report 1003056, documents the identification and evaluation of aging effects requiring management for mechanical components in the primary containment penetrations that were not reviewed in other AMRRs.
1.2
System Description
The primary containment penetrations provide the means of isolating fluid systems that pass through the primary containment in order to confine to containment radioactivity that may be released following an accident. (Ref. 2)
Mechanical penetrations for systems with a system level aging management review report are reviewed in the report for that system. The scope of this AMR is passive mechanical penetration components that are not part of a system with an aging management review report.
This report includes penetrations that are part of the CRD, RDW, NB and NM system codes in the site database. The structural portions of penetrations are addressed in AMRC-01, Aging Management Review of the Primary Containment. The internals of electrical penetration assemblies are addressed in AMRE-01, Electrical Screening and Aging Management Reviews.
The grouping of containment isolation valves from various plant systems into one consolidated review is appropriate as indicated in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, section 2.1.3.1. (Ref. 13, 16, 17) is a list of all containment mechanical penetrations and identifies the aging management review report that documents the aging management review for each penetration.
This listing is based primarily on Table B-1 of plant procedure PP 7006 since the procedure listing contains more details than the SAR Table 5.2.2. (Ref. 2, 11)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 5 of 26 1.3 System and Component Intended Functions The intended function of penetrations is to allow passage of required fluids across the primary containment boundary to support the functions of a system. For the systems covered in this report, there are no system functions that correspond to the functions in the license renewal scoping criteria except for containment integrity. The only license renewal intended function of the systems covered in this report is to provide a barrier between fission products released inside primary containment and the outside environment. This is a safety function that must be met even for nonsafety-related systems that penetrate primary containment.
The components on Attachment 1 that are included in this report are not relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the Commission's regulations for fire protection (10 CFR 50.48), environmental qualification (10 CFR 50.49), pressurized thermal shock (10 CFR 50.61-not applicable to BWRs), anticipated transients without scram (10 CFR 50.62), or station blackout (10 CFR 50.63). (Ref. 4, 5, 6)
For license renewal the primary intended function of primary containment penetration components is to maintain system pressure boundary integrity.
Nonsafety-related portions of systems whose failure could prevent satisfactory accomplishment of safety functions [10 CFR 54.4(a)(2)] that are not reviewed in this AMRR are reviewed in AMRM-30, Aging Management Review of Nonsafety-related Systems and Components Affecting Safety-related Systems. This includes systems with penetrations reviewed in this report. For VYNPS this includes items such as piping, valves, pumps, and support elements outside of the safety class pressure boundary, that are required to be structurally sound in order to maintain the integrity of the safety class piping.
Refer to VYNPS Report LRPD-01, System and Structure Scoping Report, for additional information on scoping and intended functions of systems and structures for license renewal.
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 6 of 26 2.0 Screening Passive, long-lived components or structural elements that perform or support a license renewal component intended function are subject to aging management review. The bolting, piping, and valves for containment penetrations are passive, long-lived components that maintain system pressure boundary integrity and are therefore subject to aging management review.
The structural portions of the containment penetrations are addressed in AMRC-01, Aging Management Review of the Primary Containment. (Ref. 16)
Some containment penetrations utilize solenoid valves to bleed air off of actuators so the associated valves achieve the desired position. Pressure boundary integrity is not required for these solenoid valves since the associated components fail to the desired position on a loss of air pressure. Therefore, these solenoid valves do not require aging management review. A list of the penetration valves that have air operators with solenoids1 is provided below (see LRA-G-191177 sheet 1 for additional information):
AO-82 (solenoid SE-20-82)
AO-83 (solenoid SE-20-83)
AO-94 (solenoid SE-20-94)
AO-95 (solenoid SE-20-95)
Insulation is installed on some penetrations. For the evaluation of insulation, refer to LRPD-01, System and Structure Scoping Results, and AMRC-06, Aging Management Review of Bulk Commodities. identifies the mechanical primary containment penetrations reviewed in this report. A list of the passive, long-lived mechanical primary containment penetration components subject to aging management review in this report is included as Attachment 1.
Flow diagrams associated with this system, highlighted to identify the components requiring aging management review, are available as drawings LRA-G-191159 Sheet 5, LRA-G-191167, LRA-G-191170, LRA-G-191175 Sheet 1, LRA-G-191175 Sheet 2, and LRA-G-191177 Sheet 1.
(Ref. 10) 1 These solenoid numbers are not shown on the LRA drawing but are available in LRIS.
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 7 of 26 3.0 Aging Effects Requiring Management EPRI report 1003056 is used in this section to identify and evaluate aging effects requiring management. Aging effects that may result in loss of intended functions are cracking (i.e.,
crack initiation, crack growth, and through-wall cracking), change in material properties, loss of material, and fouling. For additional information on aging effects, refer to EPRI report 1003056.
(Ref. 1) is a list of mechanical primary containment penetration components that are included in this report. These components require aging management review in this AMRR and are highlighted on the associated LRA drawings.
The portions of these penetrations in the reactor building are exposed to indoor air at a nominal temperature between 55 and 100°F. The portions of these penetrations in the drywell are exposed to indoor air (including nitrogen when primary containment is inerted) at a temperature between 135 and 165°F. (Ref. 7)
The following sections document the determination of aging effects requiring management for the penetrations.
3.1 Drywell Sump Penetrations (X-18 and 19)
The drywell floor drains sump and equipment drains sump penetrations X-18 and X-19 have safety-related piping and valves at the primary containment penetration as shown on drawing LRA-G-191177 sheet 1. The piping and valves are carbon steel (pipe code CS-1). These components are exposed to untreated water from the sump on the internal surfaces and indoor air on the external surfaces. The defined environment of indoor air includes the nitrogen environment that would be present when primary containment is inerted. (Ref. 10, 12)
Loss of material due to microbiologically influenced corrosion (MIC) and general, pitting and crevice corrosion is an aging effect requiring management for carbon steel internal surfaces exposed to untreated water. Loss of material from erosion or flow-accelerated corrosion is not an aging effect requiring management since this piping sees intermittent flow during sump pump operation. Loss of material from galvanic corrosion is not an aging effect requiring management since the components are all carbon steel.
Cracking due to thermal fatigue is not an aging effect requiring management since the water supply is from an open sump and the water temperature will remain below the 220°F threshold for carbon steel thermal fatigue. (Ref. 10)
Loss of material from general corrosion is considered an aging effect requiring management for carbon steel external surfaces exposed to indoor air.
3.2 Recirculation Pump Seal Sensing Lines and Seal Purge (X-31E, F; X-32E, F)
Recirculation pump seal sensing lines and seal purge penetrations (X-31E, F; X-32E, F) consist of stainless steel piping and valves as shown on drawing LRA-G-191159 sheet 5. The piping from the penetrations X-31F and X-32F extends to drawing LRA-G-191170 for the supply to the seal from the CRD system. (Ref. 10, 18)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 8 of 26 These components are exposed to treated water on the internal surfaces and indoor air on the external surfaces. The environment of indoor air includes the nitrogen environment that would be present when primary containment is inerted. The portion of the sensing line for the containment penetration is outside of the primary containment and is expected to be at ambient temperature. The portion from the CRD supply to the seal would not be exposed to elevated temperatures since the CRD seal water is not at high temperatures. (Ref. 10, 14)
Stainless steel is inherently resistant to general corrosion and erosion. Stainless steel internal surfaces are susceptible to loss of material due to MIC, pitting and crevice corrosion in the presence of high oxygen levels and contaminants. Therefore, loss of material is an aging effect requiring management for internal wetted surfaces.
Cracking due to stress corrosion and intergranular attack is not an aging effect requiring management since the temperature remains below the 140°F threshold for these mechanisms in stainless steel. (Ref. 10, 14)
There are no aging effects requiring management for external stainless steel surfaces due to the inherent resistance of stainless steel to aging effects when not wetted or exposed to aggressive chemicals.
Cracking due to thermal fatigue is not an aging effect requiring management since the temperature remains below the 270°F threshold for stainless steel thermal fatigue. (Ref. 10, 14) 3.3 Traversing Incore Probe Penetrations (X-35A, B, C)
Traversing incore probe (TIP) penetrations (X-35A, B, and C) consist of stainless steel piping and valves through which the traversing incore probes pass through the primary containment.
These tubes are provided with an isolation valve which closes automatically upon receipt of the proper signal and after the TIP cable and fission chamber have been retracted. In series with this isolation valve, an additional or backup isolation shear valve is provided that could shear the cable and seal the tube if necessary. These penetrations are not shown on LRA drawings, but additional information is provided in UFSAR section 5.2.3.5.1 (page 5.2-15 item 4). The piping and valves are stainless steel. (Ref. 3)
Traversing incore probe (TIP) penetrations (X-35A, B, and C) are exposed to gas on internal surfaces and indoor air on external surfaces. The components are at ambient temperature during normal operation since fluids are not flowing in the tubes. There are no aging effects requiring management for internal surfaces due to the inherent corrosion resistance of stainless steel in a dry environment. (Ref. 3)
Cracking due to stress corrosion and intergranular attack is not an aging effect requiring management since the temperature remains below the 140°F threshold for these mechanisms in stainless steel. (Ref. 3)
There are no aging effects requiring management for external stainless steel surfaces due to the inherent resistance of stainless steel to aging effects when not wetted or exposed to aggressive chemicals.
Cracking due to thermal fatigue is not an aging effect requiring management since the temperature remains below the 270°F threshold for stainless steel thermal fatigue. (Ref. 3)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 9 of 26 3.4 Traversing Incore Probe Purge Gas Penetration (X-35E)
Penetration X-35E is the TIP purge gas penetration. This penetration is shown on LRA-G-191175 sheet 2. The piping and valves are stainless steel. The penetration is exposed to dry gas (nitrogen) at essentially ambient temperature on internal surfaces and indoor air on the external surfaces. The defined environment of indoor air includes the nitrogen environment that would be present when primary containment is inerted. (Ref. 3)
There are no aging effects that require management for internal surfaces of these components due to the inherent resistance of stainless steel and the presence of nitrogen.
There are no aging effects requiring management for external stainless steel surfaces due to the inherent resistance of stainless steel to aging effects when not wetted or exposed to aggressive chemicals.
Cracking due to thermal fatigue is not an aging effect requiring management since the temperature remains below the 270°F threshold for stainless steel thermal fatigue. (Ref. 3) 3.5 Suppression Pool Drain Penetrations (X-213A and B)
The suppression pool drain penetrations X-213A and B have safety-related piping at the primary containment penetration as shown on drawing LRA-G-191175 sheet 1. The piping and valves are carbon steel (pipe code CS-1). These components are exposed to treated water on internal surfaces and indoor air on external surfaces. (Ref. 10, 12)
Loss of material due to MIC and general, pitting and crevice corrosion is an aging effect requiring management for carbon steel internal surfaces exposed to water. Loss of material from erosion or flow-accelerated corrosion is not an aging effect requiring management since this piping sees intermittent flow only during sump pump operation.
Cracking due to thermal fatigue is not an aging effect requiring management since the temperature is from open drains and therefore remains below the 220°F threshold for carbon steel thermal fatigue. (Ref. 10, 15)
Loss of material from general corrosion is considered an aging effect requiring management for carbon steel external surfaces exposed to indoor air.
3.6 Spare Penetrations (X-15, 17, 20, 29E, 29F, 33D, 35D, 36, 43, 44, 45, 46, 48, 50D, 50E, 50F, 101B, 106, 107 and 219)
The spare penetrations that are not covered in other individual system AMRRs (X-15, 17, 20, 29E, 29F, 33D, 35D, 36, 43, 44, 45, 46, 48, 50D, 50E, 50F, 101B, 106, 107 and 219) are reviewed in this section. These consist of simple welded caps or plugs in addition to the pipe.
The caps or plugs are included in the generic component type pipe. See Attachment 3 and Table B-1 of procedure PP-7006 for identification of the components and further information on the configuration for individual penetrations. Both carbon steel and stainless steel are utilized.
These are spare penetrations that are no longer used and therefore are exposed to indoor air (which includes nitrogen when inerted) on internal and external surfaces. (Ref. 10, 11, 12)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 10 of 26 Water or condensation is not expected to collect in these penetrations, but loss of material due to general corrosion from the moisture in air is an aging effect requiring management for carbon steel internal and external surfaces.
There are no aging effects for stainless steel internal or external surfaces exposed to dry internal building air due to the inherent corrosion resistance of stainless steel.
Cracking due to thermal fatigue is not an aging effect requiring management since the components are in spared penetrations that would be at ambient temperature which is below the 220oF (carbon steel) and 270oF (stainless steel) temperature thresholds for this mechanism.
(Ref. 10, 11, 15) 3.7 Bolting Pressure retaining bolting for these penetrations may be carbon steel or stainless steel and is exposed to indoor air.
Loss of material from general corrosion is considered an aging effect requiring management for carbon steel bolting exposed to indoor air. Loss of material is not an aging effect requiring management for stainless steel bolting that is not wetted.
3.8 Operating Experience The review of site specific operating experience and recent industry operating experience completed in VYNPS Report LRPD-05, Operating Experience Review Results, did not identify aging effects applicable to the penetration passive mechanical components not addressed in this aging management review report. (Ref. 9)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 11 of 26 4.0 Demonstration That Aging Effects Will Be Managed The components of the primary containment penetrations that are subject to aging management review were described in Section 2.0. For those components, Section 3.0 documented the determination of aging effects requiring management. The aging management review is completed by demonstrating that existing programs, when continued into the period of extended operation, can manage the aging effects identified in Section 3.0. No further action is required for license renewal when the evaluation of an existing program demonstrates that it is adequate to manage the aging effect such that corrective action may be taken prior to loss of the intended functions. Alternately, if existing programs cannot be shown to manage the aging effects for the period of extended operation, then action will be proposed to augment existing or create new programs to manage the identified effects of aging.
Demonstration for the purposes of this license renewal technical evaluation is accomplished by establishing a clear relationship among
- 1) the components under review,
- 2) the aging effects on these items caused by the material-environment-stress combinations which, if undetected, could result in loss of the intended function such that the penetration components could not perform its function(s) within the scope of license renewal in the period of extended operation, and
- 3) the credited aging management programs whose actions serve to preserve the containment penetrations intended function(s) for the period of extended operation. lists component types and identifies the aging effects requiring management for each material and environment combination. The Containment Leak Rate Program, System Walkdown Program, and Water Chemistry Control - BWR Program, in combination will manage the effects of aging, thereby precluding loss of the intended functions of the system. Sections 4.1 through 4.3 provide the clear relationship between the component, the aging effect, and the aging management program actions which preserve the intended functions for the period of extended operation. Section 4.4 identifies applicable time-limited aging analyses. For a comprehensive review of programs credited for license renewal of VYNPS and a demonstration of how these programs will manage aging effects, see VYNPS Report LRPD-02, Aging Management Program Evaluation Results. (Ref. 8) 4.1 Containment Leak Rate Program The penetrations are periodically tested to verify their ability to limit containment leakage. This periodic confirmation that the components can perform their intended function as well as visual observation during the testing is credited as one of the programs to manage loss of material for carbon steel penetration components.
This program applies to component types indicated on Attachment 2. For additional information on this program, see VYNPS Report LRPD-02, Aging Management Program Evaluation Results. (Ref. 8)
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 12 of 26 4.2 System Walkdown Program Under the System Walkdown Program, visual inspections are conducted to manage aging effects on components. For the primary containment penetrations, the System Walkdown Program manages loss of material for external carbon steel components by visual inspection of external surfaces. Since some internal carbon steel surfaces in these penetrations are exposed to the same environment as the external surfaces, the external surfaces will be representative of the internal surfaces. Thus, loss of material on these internal carbon steel surfaces is also managed by the System Walkdown Program.
This program applies to carbon steel bolting, piping and valves as indicated on Attachment 2.
For additional information on this program, see VYNPS Report LRPD-02, Aging Management Program Evaluation Results. (Ref. 8) 4.3 Water Chemistry Control - BWR Program To manage loss of material on carbon steel and stainless steel alloy primary containment penetration components, levels of contaminants in the treated water systems of primary containment penetrations in the scope of this report are minimized by the Water Chemistry Control - BWR Program. The Water Chemistry Control - One-Time Inspection Program utilizes inspections or non-destructive evaluations of representative samples to verify that the Water Chemistry Control - BWR Program has been successful at managing loss of material for the primary containment penetrations.
This program applies to carbon steel and stainless steel piping and valves as indicated on. For additional information on this program and the Water Chemistry Control -
One-Time Inspection Program, see VYNPS Report LRPD-02, Aging Management Program Evaluation Results. (Ref. 8) 4.4 Time-Limited Aging Analyses The primary containment penetrations reviewed in this report are not exposed to elevated temperatures and the associated metal fatigue. Therefore, metal fatigue analyses are not TLAA applicable to this AMRR.
See VYNPS Reports LRPD-03, TLAA and Exemption Evaluation Results, and LRPD-04, TLAA
- Mechanical Fatigue, for further review of time-limited aging analyses.
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 13 of 26 5.0 Summary and Conclusions The following aging management programs address the aging effects requiring management for the primary containment penetration includes in this report.
Containment Leak Rate Program System Walkdown Program Water Chemistry Control - BWR Program For additional review of programs credited for license renewal of VYNPS, see VYNPS Report LRPD-02, Aging Management Program Evaluation Results. contains the aging management review results for the primary containment penetrations included in this report.
In conclusion, programs described in Section 4.0 will provide reasonable assurance that the effects of aging on the primary containment penetrations will be managed such that the intended functions will be maintained consistent with the current licensing basis throughout the period of extended operation.
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 14 of 26 6.0 References
- 1. Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools, Revision 3, EPRI, Palo Alto, CA: 2001. 1003056
- 2. VYNPS Updated Final Safety Analysis Report (UFSAR) Revision 19-1 Section 5.1
- 3. TIP Information Drawing 5920-FS-1596 Sheet 1 Rev. 0 Drawing 5920-FS-1596 Sheet 2 Rev. 3 Email from John Hoffman/ John Stasolla May 19, 2004 UFSAR Revision 19-1 Section 5.2.3.5.1
- 4. ENN-MS-S-009-VY, Vermont Yankee Site Specific Guidance and System Safety Function Sheets, Rev. 0, 3/22/05
- 5. Document SADBD, Topical Design Basis Document for Safety Analysis, Rev. 4
- 6. VYNPP Safe Shutdown Capability Analysis, Rev. 7, 6/26/04.
- 7. VYNPS Updated Final Safety Analysis Report (UFSAR) Revision 19-1 sections 3.8.3 and 5.2.3.7
- 8. VYNPS Report LRPD-02, Aging Management Program Evaluation Results.
- 9. VYNPS Report LRPD-05, Operating Experience Review Results
- 10. Flow Diagrams G-191159 Sheet 5 Rev. 16, G-191170 Rev. 48, G-191175 Sheet. 1 Rev. 70, G-191175 Sheet. 2 Rev. 20, G-191177 Sheet. 1 Rev. 39
- 11. Site procedures:
OP 2115 Rev. 45, Primary Containment OP 4030 Rev. 37, Type B and C Primary Containment Leakrate Testing OP 4031 Rev. 9, Type B and C Primary Containment Leak Rate Calculations and Evaluations PP 7006 Rev. 9, Primary Containment Leakage Rate Testing
- 12. BWR QC-10, Ebasco Piping Specification, 3/15/70
- 13. NUREG-1800, Rev. 1, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 15 of 26
- 14. AMRM-33, Reactor Coolant System Pressure Boundary
- 15. Memorandum VYS97-062, Torus Temperature Limit During Testing
- 16. AMRC-01, Aging Management Review of the Primary Containment
- 17. AMRE-01, Electrical Screening and Aging Management Reviews
- 18. PDCR 83-01 Recirc Pump Seal Purge System
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 16 of 26 - Components Subject to AMR ENVIRONMENT: AIR - INDOOR (EXTERNAL)
Comp ID Comp Type Comp Name Material PRIM. CONT. CS BOLTING bolting PRIM. CONT. CS BOLTING carbon steel PRIM. CONT. SS BOLTING bolting PRIM. CONT. SS BOLTING stainless steel ENVIRONMENT: AIR - INDOOR (INTERNAL)
Comp ID Comp Type Comp Name Material PRIM. CONT.
SPARED CS PIPING piping PRIM. CONT. SPARED CS PIPING carbon steel PRIM. CONT.
SPARED SS PIPE piping PRIM. CONT. SPARED SS PIPE stainless steel ENVIRONMENT: GAS (INTERNAL)
Comp ID Comp Type Comp Name Material PRIM. CONT. TIP SS PIPE piping PRIM.CONT. TIP SS PIPE stainless steel SOV-7-107 valve body N2 SUPPLY TO TIP PURGE SYSTEM OUTBOARD CONTAINMENT ISOLATION stainless steel V7-1 valve body TRAVELSING INCORE PROBE (TIP) NITROGEN PURGE LINE CHECK VALVE stainless steel V7-90 valve body TIP PURGE SYSTEM BLOCK VALVE stainless steel V7-91 valve body TIP PURGE SYSTEM TEST CONNECTION stainless steel V7-92 valve body TIP PURGE SYSTEM TEST CONNECTION stainless steel V7-93 valve body TIP PURGE SYSTEM TEST CONNECTION stainless steel V7-94 valve body TIP PURGE SYSTEM BLOCK VALVE stainless steel
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 17 of 26 - Components Subject to AMR ENVIRONMENT: GAS (INTERNAL)
Comp ID Comp Type Comp Name Material V7-96 valve body TIP PURGE SYSTEM TEST CONNECTION stainless steel ENVIRONMENT: TREATED WATER (INTERNAL)
Comp ID Comp Type Comp Name Material BV-7-1 valve body TRAVERSING INCORE PROBE (TIP) stainless steel BV-7-2 valve body TRAVERSING INCORE PROBE (TIP) stainless steel BV-7-3 valve body TRAVERSING INCORE PROBE (TIP) stainless steel PRIM. CONT. CS PIPE IN TREATED WATER piping PRIM. CONT. CS PIPE IN TREATED WATER carbon steel PRIM. CONT. SS PIPE IN TREATED WTR piping PRIM. CONT. SS PIPE IN TREATED WTR stainless steel S-7-1 valve body TIP SHEAR VALVE WITH EXPLOSIVE ACTUATOR stainless steel S-7-2 valve body TIP SHEAR VALVE WITH EXPLOSIVE ACTUATOR stainless steel S-7-3 valve body TIP SHEAR VALVE WITH EXPLOSIVE ACTUATOR stainless steel SL-2-2-7A valve body RPCW FLOW LIMITING VALVE stainless steel SL-2-2-7B valve body RPCW FLOW LIMITING VALVE stainless steel SL-2-2-8A valve body EXCESS FLOW ISOL FOR P12-2-28A & P12-2-25A stainless steel SL-2-2-8B valve body EXCESS FLOW ISOLATION FOR P12-2-28B & PT2-2-25B stainless steel V20-400A valve body TORUS DRAIN VALVES LOWER LEVEL TORUS NORTHWEST carbon steel V20-400B valve body TORUS DRAIN VALVES LOWER LEVEL TORUS SOUTHEAST carbon steel V2-2-10A valve body RPCW GLOBE VALVE stainless steel V2-2-10B valve body RPCW GLOBE VALVE stainless steel V2-2-9A valve body RPCW GLOBE VALVE stainless steel
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 18 of 26 - Components Subject to AMR ENVIRONMENT: TREATED WATER (INTERNAL)
Comp ID Comp Type Comp Name Material V2-2-9B valve body RPCW GLOBE VALVE stainless steel V3-406 valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-407 valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-408A valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-408B valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-410A valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-410B valve body RECIRC PUMP SEAL PURGE VALVE stainless steel V3-412A valve body VALVE stainless steel V3-412B valve body VALVE IS LOCATED ON IN-BOARD SIDE OF THE TORUS NOT NEAR THE CATWALK stainless steel V3-413A valve body VALVE stainless steel V3-413B valve body VALVE SOUTH EAST TORUS, DRYWELL SIDE OF SOUTH TORUS LADDER, HAS PERMANENT WORK PLATFORM stainless steel
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 19 of 26 - Components Subject to AMR ENVIRONMENT: UNTREATED WATER (INTERNAL)
Comp ID Comp Type Comp Name Material PRIM. CONT. CS PIPE IN UNTREATED WATER piping PRIM. CONT. CS PIPE IN UNTREATED WATER carbon steel RV-20-82A valve body DRYWELL FLOOR DRAIN ISOLATION RELIEF VALVE carbon steel RV-20-94A valve body DRYWELL EQUIPMENT DRAIN ISOLATION RELIEF VALVE MFG. CONSOLIDATED/DRESSER carbon steel V20-78A valve body TEST CONN RX BLDG 238' DRYWELL AREA carbon steel V20-79A valve body TEST CONN RX BLDG 238' DRYWELL AREA carbon steel V20-82 valve body BALL VALVE INBD ISOL CRP 9-4 carbon steel V20-83 valve body BALL VALVE OUTBD ISOL CRP 9-4 RX BLDG 238', DRYWELL FLOOR DRAIN ISOL VALVE carbon steel V20-92A valve body TEST CONN RX BLDG 238' DRYWELL AREA carbon steel V20-93A valve body TEST CONN RX BLDG 238' DRYWELL AREA carbon steel V20-94 valve body BALL VALVE INBD ISOL CRP 9-4 carbon steel V20-95 valve body BALL VALVE OUTBD ISOL CRP 9-4 carbon steel
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 20 of 26 - Aging Management Review Results Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs Bolting Pressure boundary Carbon steel Air - indoor (ext)
Loss of material System walkdown Stainless steel Air - indoor (ext)
None None Piping Pressure boundary Carbon steel Air - indoor (ext)
Loss of material System walkdown Air - indoor (int)
Loss of material System walkdown Treated water (int)
Loss of material Water chemistry control
- BWR Untreated water (int)
Loss of material Containment leak rate Stainless steel Air - indoor (ext)
None None Air - indoor (int)
None None Gas (int)
None None Treated water (int)
Loss of material Water chemistry control
- BWR
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 21 of 26 - Aging Management Review Results Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs Valve body Pressure boundary Carbon steel Air - indoor (ext)
Loss of material System walkdown Treated water (int)
Loss of material Water chemistry control
- BWR Untreated water (int)
Loss of material Containment leak rate Stainless steel Air - indoor (ext)
None None Gas (int)
None None Treated water (int)
Loss of material Water chemistry control
- BWR
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 22 of 26 - List of Mechanical Primary Containment Penetrations Penet. # Description Drawing Reviewed in AMRR X-2 Personnel lock G-191148 G-191175 Sheet 1 AMRC civil portions AMRM mechanical portions X-5 A-H Drywell /torus vent pipe G-191175 Sheet 1 AMRC civil portions AMRM mechanical portions X-7A, B, C, D Main steam lines G-191167 AMRM-33 X-8 Main steam line drain G-191167 AMRM-33 X-9A, B Feedwater G-191167 AMRM-33 X-10 RCIC steam supply G-191174 Sheet. 1 AMRM-33 X-11 HPCI steam supply G-191169 Sheet 1 AMRM-33 X-12 RHR from reactor vessel G-191172 AMRM-33 X-13A, B RHR to RV G-191172 AMRM-33 X-14 Reactor water cleanup from reactor vessel G-191178 Sheet 1 AMRM-33 X-15 Spare-welded cap na AMRM-20 X-16A,B Core spray G-191168 AMRM-03 and AMRM-33 X-17 Spare-welded cap na AMRM-20 X-18 Drywell floor drain sump G-191177 Sheet 1 AMRM-20 X-19 Drywell equipment drain sump G-191177 Sheet 1 AMRM-20 X-20 Spare-welded cap na AMRM-20 X-21 Spare-welded cap G-191160 Sheet 6 AMRM-16 X-22 Instrument air to drywell G-191160 Sheet 4 AMRM-16 X-23 RBCCW drywell inlet G-191159 Sheet. 3 AMRM-12 X-24 RBCCW drywell outlet G-191159 Sheet. 3 AMRM-12 X-25 Drywell purge and vent outlet/CAD outlet G-191175 Sheet. 1 VY-E-75-002 AMRM-08 X-26 Drywell purge and vent inlet/ nitrogen inlet/ CAD inlet G-191175 Sheet 1 VY-E-75-002 AMRM-08 X-27A-F Instrument lines to reactor primary system A, B-G-191267 Sht 1 C&D - G-191168 E&F - G-191169 Sht 1 AMRM-33 X-28A-F Instrument line to reactor primary system A-E - G-191267 Sheet 1
F-G-191167 AMRM-33
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 23 of 26 - List of Mechanical Primary Containment Penetrations Penet. #
Description Drawing Reviewed in AMRR X-29A-D Instrument line to reactor primary system G-191267 Sheet 1 AMRM-33 X-29E, F Spare-welded cap na AMRM-20 X-30A-F Instrument line to reactor primary system G-191167 AMRM-33 X-31A-D Instrument line to reactor primary system G-191167 AMRM-33 X-31E, F Recirc. pump seal purge G-191159 Sheet 5 G-191170 AMRM-20 X-32A-D Instrument line to reactor primary system G-191167 AMRM-33 X-32E, F Recirc. pump seal purge G-191159 Sheet 5 G-191170 AMRM-20 X-33A, B, C, E, F Instrument lines to CRD, HPCI, RCIC A - G-191267 Sheet 1 and G-191170 B&C - G-191169 Sheet 1 E&F - G-191174 Sheet 1 AMRM-33 X-33D Spare-welded cap na AMRM-20 X-34A-D Main steam instruments G-191167 AMRM-33 X-34E, F Recirc loop spare test tap G-191167 AMRM-33 X-35A, B, C Transversing incore probe 5920-FS-1596 Sh. 2 Ref. 3 AMRM-20 X-35D Spare na-see Ref. 3 AMRM-20 X-35E Traversing incore probe purge G-191175 Sh. 2, 5920-428 and Ref. 3 AMRM-20 X-36 Spare-welded cap G-191167 AMRM-20 X-37A, B, C, D (89 lines)
CRD insert G-191170 AMRM-33 X-38A, B, C, D (89 lines)
CRD withdraw G-191170 AMRM-33 X-39A, B Drywell spray G-191172 AMRM-02 X-40A, B, C, D
Drywell instruments G-191172 G-191175 Sheet 1 AMRM-08 X-40A-A, A-B, A-C, A-D, A-E, A-F Jet pump instruments G-191267 Sheet 1 and 2 AMRM-33 X-40B-A, B-B, B-C, B-D, B-E, B-F Jet pump instruments/PASS G-191267 Sheets 1 and 2 AMRM-33
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 24 of 26 - List of Mechanical Primary Containment Penetrations Penet. #
Description Drawing Reviewed in AMRR X-40C-A, C-B, C-C, C-D, C-E, C-F Jet pump instruments G-191267 Sheet 1 and 2 AMRM-33 X-40D-A, D-B, D-C, D-D, D-E, D-F Jet pump instruments/PASS G-191267 Sheet 1 and 2 AMRM-33 X-41 Reactor recirculation water sample G-191167 AMRM-33 X-42 Standby liquid control G-191171 AMRM-33 X-43 Spare-welded cap na AMRM-20 X-44 Spare-welded cap na AMRM-20 X-45 Spare-welded cap na AMRM-20 X-46 Spare-welded cap na AMRM-20 X-47 Drywell to primary containment atmosphere compressor G-191160 Sheet 3 and 4 AMRM-16 X-48 Spare-welded cap na AMRM-20 X-49A, B RCIC instruments G-191174 Sheet. 1 AMRM-33 X-49C, D, E, F SRV bellows pressure G-191167 AMRM-33 X-50A, B, C Containment air sample inlet G-191165 Sheet 2 VY-E-75-002 AMRM-08 X-50D Spare-welded cap na AMRM-20 X-50E Spare-welded cap na AMRM-20 X-50F Spare-welded cap na AMRM-20 X-51A Spare-with valve G-191167 (E-4)
AMRM-04 X-51B Spare-with valve G-191167 (E-4)
AMRM-04 X-51C, D SRV leak detection G-191167 AMRM-04 X-51E Instru. air to SRV G-191160 Sheet 4 AMRM-16 X-51F Jet pump instruments G-191267 Sheet. 1 AMRM-33 X-52A, B SRV leak detection G-191167 AMRM-04 X-52C Spare-with valve G-191167 (D-4)
AMRM-04 X-52D Spare-with valve G-191167 (D-4)
AMRM-04 X-52E, F Instrument line to drywell G-191175 Sheet 1 AMRM-08 X-101B Spare-welded cap na AMRM-20 X-106 Spare-welded cap na AMRM-20 X-107 Spare-welded cap na AMRM-20
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 25 of 26 - List of Mechanical Primary Containment Penetrations Penet. #
Description Drawing Reviewed in AMRR X-201A, B, C, D, E, F, G, H Vent line G-191175 Sheet 1 AMRC civil portions AMRM mechanical portions X-202A, B, C, D, E, F, G, H, J, K Suppression chamber to drywell vacuum breakers G-191175 Sheet 1 AMRM-08 X-203A, B, C, D, E, F, G, H Suppression chamber to drywell vacuum breakers G-191175 Sheet 1 AMRM-08 X-205 Drywell and suppression chamber purge and vent inlet/ nitrogen inlet/ cad inlet G-191175 Sheet 1 VY-E-75-002 AMRM-08 X-206 A, B, C, D Spare with valves G-191175 Sheet 1 AMRM-08 X-206E, F Instrument line to suppression chamber G-191175 Sheet 1 AMRM-08 X-209 A Spare with valves G-191175 Sheet 1 AMRM-08 X-209B, C Thermowells in suppression chamber G-191175 Sh 1 (M-6)
AMRC-01 X-209D H2 sample return VY-E-75-002 AMRM-08 X-210A,B CS /HPCI/RHR/RDW test return G-191168 (CS)
G-191169 (HPCI)
G-191174 (RHR)
G-191177 (RDW)
AMRM-02, -03,-05, and -06 X-211A,B RHR to suppression chamber G-191172 AMRM-02 X-212 RCIC turbine exhaust G-191174 Sheet 1 AMRM-06 X-213A and B
Suppression pool drain G-191175 Sheet 1 AMRM-20 X-215 Thermowells in suppression chamber G-191175 AMRC-01 X-216 Containment air sample outlet G-191165 Sheet 2 VY-E-75-002 AMRM-08 X-217 Instrument line to suppression chamber G-191175 Sheet 1 AMRM-08 X-218 Drywell and suppression chamber purge and vent outlet/CAD outlet G-191175 Sheet 1 VY-E-75-002 AMRM-08 X-219 Spare-welded cap na AMRM-20
VYNPS License Renewal Project Aging Management Review of the Primary Containment Penetrations AMRM-20 Revision 0 Page 26 of 26 - List of Mechanical Primary Containment Penetrations Penet. #
Description Drawing Reviewed in AMRR X-220 Containment air sample Inlet VY-E-75-002 AMRM-08 X-221 HPCI turbine exhaust G-191169 Sheet 1 AMRM-05 X-222 HPCI turbine exhaust drain G-191169 Sheet 1 AMRM-05 X-223 RCIC vacuum pump discharge G-191174 Sheet 1 AMRM-06 X-224A, B RHR from suppression pool G-191172 AMRM-02 X-225 HPCI from suppression pool G-191169 Sheet 1 AMRM-05 X-226A, B Core spray from suppression pool G-191168 AMRM-03 X-227 RCIC from suppression pool G-191174 Sheet 1 AMRM-06 X-228 Instrument line to suppression chamber G-191175 Sheet 1 AMRM-08 X-229 Instrument line to suppression chamber G-191175 Sheet 1 AMRM-08 X-230 PCAC rupture disc G-191175 Sheet 1 AMRM-08 X-231A-D Spare-with valves G-191175 Sheet 1 AMRM-08 X-231E, F, G, H Instrument lines to suppression chamber G-191175 Sheet 1 AMRM-08 X-232 RCIC turbine exhaust vacuum breaker G-191174 AMRM-06 and AMRM-08 X-233 HPCI turbine exhaust vacuum breaker G-191169 AMRM-05 and AMRM-08