ML19284A733
| ML19284A733 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/12/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| 112, NUDOCS 7903150294 | |
| Download: ML19284A733 (20) | |
Text
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VIRGINIA ELucTnic AND POWE H C O bt l% NY Hicnwox13,vlHOIN I A 202f31 March 12, 1979 Mr. Harold R. Denton, Director Serial No.
112 Office of Nuclear Reactor Regulation PO/LSC:scj Attn:
Mr. O. D. Parr, Chief Docket No.: 50-339 Light Water Reactors Branch No. 3 Division of Project Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Specification 4.0.5 of the proposed Technical Specifications for North Anna Unit 2, requires that inservice inspection of ASME Code Class 1, 2 and 3 components be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g). North Anna Unit 2 was not, however, designed to meet the detailed inservice inspection requirements of the ASME Code,Section XI.
Therefore, pursuant co 10 CFR, Section 50.55a(g)(6)(i), we request the specific exemptions for inservice inspection as outlined in the attachment.
Very truly yours, f
C. M. Stallings Vice President-Power Supply and Production Operations
Attachment:
North Anna Unit 2 Initial Inservice Inspection Requests for Relief from Applicable Codes and Addenda (first 40 month period of the first 10 year interval).
\\
D@.\\ qP 7903150999
NORTH ANNA UNIT 2 INITIAL INSERVICE INSPECTION REQUESTS FOR RELIEF FROM APPLICABLE CODES AND ADDENDA (FIRST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL) listing of the Class 1, 2 and 3 pressure The enclosed tables provide a
retaining components (and their supports) which are subject to the inspection requirements of subsections IWB, IWC, and IUD of Sect ion XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda through Summer, 1975 and for which relief is requested per 10 CFR SC.55a(g)(6)(i).
These tabulations identify the components to be inspected, the components safety class, the method of examination, the percentage of code requirements versus the inspection program, and notes on the measures which would be required to make the welds accessible for inservice examination.
Relief from the inspection requirements of each subsection is requested in cases where these inspection requirements 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.
The following provide further clarification concer..ing the Class 1, 2 and 3 system inspection programs.
(a) Articles IWC-3000 and IWD-3000 entitled, " Evaluation of Examination Results" are in the course of preparation by the Code Committee and, as yet, are not availabic for use.
Standards for examination evaluations as included in the 1974 Edition of Section XI with Addenda through the Summer, 1975, are incomplete and " Acceptance Standards for Flaw Indications "as given in Article IUB-3000 of the 1977 Edition of Section XI will be utilized.
(b) Articles IWC-4000 and IWD-4000 entitled, " Repair Procedures" state that the rules of IWB-4000 shall apply.
It is considered that the repair procedures outlined in IWB-4000 are inappropriate for the Class 2 and 3 conponents in this program and the rules of IWA-4000 will be applied.
(c) Requirements for the visual examination of Class 1 systems and components for evidence of leakage during the performance of a system pressure test following each refueling are identified by IWB-5200.
Exception is taken to the implementation of these requirements on those portions of Class 1 systems which are contained between two check valves or two normally closed valves, where pressure applied to the reactor coolant system will be retained at the first valve in the line.
The portions of systems affected by this limitation are:
(i) Cold leg injection from accumulators between check valves 2-SI-151, 2-SI-168 and 2-SI-185 and check valves 2-SI-153, 2-SI-170 and 2-SI-187, test lines to valves HCV-2850B, D and F and RHR return lines to valves MOV-2720A and B.
, w--
. (ii) Cold leg high head and boron injection between check valves 2-SI-92, 2-SI-100 and 2-SI-106 and check valves 2-SI-90, 2-SI-98 and 2-SI-104, and low head injection lines to check valves 2-SI-91, 2-SI-99 and 2-SI-105.
(iii) Hot leg high head injection between check valves 2-SI-113, 2-SI-118 and 2-SI-125 and check valves 2-SI-107 and 2-SI-119 and low head injection lines to check valves 2-SI-112, 2-SI-ll7 and 2-SI-124.
(iv) RHR take-off line between normally closed (with pressure interlock) valves MOV-2700 and 2701.
This portion of the system will be pressurized whenever the system is put into operation during plant shutdown when the reactor coolant sytem is cooled to 350*F and depressurized to 450 psig.
These valves are interlocked to automatically isolate when the reactor coolant system pressure exceeds 660 psig.
(d) Subsections IWB and IWC contcin dif fering requirements for the hydrostatic testing of Class 1 and Class 2 systems and components.
The implement ation of these requirements is impractical when the only means of pressurizing the Class 2 system is through the Class 1 system or when the boundary between the two systems is a check valve arranged for flow from Class 2 to the Class I system.
Exception is taken to the performance of the hydrostatic test required by Article IWC-2412(a) on those portions requirements as af the Class 2 systens identified below.
Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nomir.nl operating pressure in accordance with the,equirements of IWB-5221 for the adjoining Class I system.
(i)
R. C. Pump seal bypass lines from the check valves 2-CH-279, 2-CH-303, and 2-CH-326 and air operated valve HCV-2307.
(ii)
R. C. Pump seal leak off line to manually operated valves 2-CH-273, 2-CH-297 and 2-CH-356, nanual valves 2-CH-272, 2-CH-296 and 2-CH-320 and valves 2-CH-278, 2-CH-302 and 2-CH-325.
(iii)
R. C. Pump seal injection line from check valve 2-CH-260, 2-CH-284, and 2-CH-308 to manually operated valves 2-CH-233, 2-CH-237, and 2-CH-241.
(iv) Excess letdown system from valve HCV-2201 to valve HCV-2137.
(v) Letdown line from valve LCV-2460B to orifice outlet valves HCV-2200A, B and C.
p-7
. (vi) Pressurizer steam space sampling line from valve 2-RC-158 to valve TV-SS101A pressurizer lignid space sampling line from valve 2-RC-146 to valve TV-SS100A and loop sampling lines from valves 2-RC-10, 2-RC-29, 2-EC-49, 2-RC-68, 2-RC-81, 2-RC-100 and 2-RC-173 to valves HCV-SS201A, B, C aad D and HCV-SS202A, B and C.
(c) The examination requirements for Class 3 systems and componc,ts as given in the attached tabulation are in accordance with IWD-2410(c) which specifies that one hundred percent of the components be examined as required by IWA-5240 and IUD-2600 cither during normal operation or during system inservice testing.
An additional requirement of IWD-2410(b) is for the examination of Class 3 systems and components for evidence of Icakage during the perform-ance of a system pressure test in accordance with IWD-5000. The code does not stipulate that certain amounts of these examination requirements be completed within each forty month period such that the system pressure test requirements may be deferred until the eno of the ten year inspect ion interval.
However, it should be noted, that these system pressure tests when required are imprac-tical in those systems, such as component cooling, service water, spent fuel pit cooling, and boric acid transfer and recirculation, which are in continuous operation during all modes of plant operation.
The continuous functional operation se rves to demonstrate the structural and leak-tight integrity of these systers.
Visual examinations of these systems will be performed at normal operation pressures to verify leak tightness.
(f) Ultrasonic examinations will be conducted in accordance with the provisions of Appendix I and Articic 5 of Section V as required by Paragraph IWA-2232.
As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 1974 Edition, Winter, 1975 Addenda of the ASME Boiler and Pressure Vessel Code will be used for ultraconic examination of piping systems.
It is recognized that Appendix III of Section XI was issued in the Winter, 1975, Addenda and, as such, has not been officially recognized by the NRC by reference in 10 CFR 50.
However, Appendix III is the first guideline that has been published in the ASME Codes for the ultrasonic examination of pipe welds and, as such, its use is essential.
(g) As an alternative for I-3121 of Section XI:
" Calibration blocks required for the examination of welds in ferritic vessels 2 1/2 inches thick and over will be fabricated from material of the same specification, product form, and heat treatment as one of the materials being joined as allowed by article T-434.1 in the Winter, 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code."
. The reason this alternative is requested is that the Code requires that calibration blocks for the examination of welds in ferritic vessels 2 1/2 inches thick and greater be fabricated from material taken from the component nozzle drop out or material from the component prolongation. As a third alternative, when it is not possible to f abricate the block from material taken from the component, the block may be fabricated from a material of a specificatica included in the applicable examination volumes of the component.
It is required that the acoustic velocity and attenuation of such a block be demonstrated to fall within the range of beam longitudinal wave velocity and attenuation found in the unclad components.
For the components in North Anna Unit 2, particularly the pressuri-zer and steam generators, it will be impossible to meet the requirements of alternative 1 or 2.
Materials of the specification are readily available, but because all the components involved are clad on the inner surfaces, it would be impossibic to obtain a comparison of sound beaa velocities and attenuations in the unclad component.
The calibration standards used on North Anna Unit 2 are cladded.
The inservice inspection program outlined in the attached tabulations have been developed as a result of a design review.
Should certain ASME Section XI Code requirements he discovered to be impractical due to unforeseen reasons during the process of performing inspection or tests, or final develcpment of the Inservice Inspection program, relief will be requested from the specific Section XI Code requirement at that time.
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 test s describe 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.
The specific program for exaulnations of the Class 1, 2, and 3 systems has not been outlined as of this date for North Anna Unit 2.
The Class 3 systems included in this letter are essentially inclusive for the 1st 10 year period but it should be noted that most of the Ci sss 3 systems were not designed for periodic hydro-static tes:
There are a portion of these systems underground and the valvec used in these systems were not designed for complete leak tightness when shut off.
- Codes referenced as being applicable to construction of components in the attached tables are:
III C AStiE Boiler and Pressure Vessel Code,Section III, Class C Nuclear Vessels, 1968 Edition.
VIII ASME Boiler and Pressure Vessel Code,Section VIII, Pressure Vessels, 1968 Edition.
B 31.1 USA Standard USAS B 31.1 Code for Pressure Piping, 1967 Edition.
B 31.7 USA Standard USAS B 31.7 Code for Pressure Piping, 1969 Edition.
P6V Draft AS11E Code for Pumps and Valves for Nuclear Power, November 1968 Edition.
I
'V
NORTil ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENTS Table Table System or Area to be Examination Section XI Extent of Measures require IWB-2600 IWB-2500 Component Examined Requirement Code Relief ISI Coverage for accessability Item No.
Examination Request vs.Section XI Category B 1.7 B-G-1 Reactor Vessel Closure Studs Not Applicable No-Note 1 N/A N/A (in place)
B 1.12 B-Il Integrally Weld-Not Applicable No-Note 2 N/A N/A ed Supports B 1.16 B-N-Z Interior Attach-Not Applicable No-Note 3 N/A N/A nents and Core Support B 2.2 B-D Pressurizer Nozzle to Volumetric Yes-Note 4 90%
Note 5 Vessel Welds B 2.4 B-F Nozzle to Safe-Volumetric and Yes-Note 6 90%
Note 5 End Welds (6)
Surface B 2.5 B-G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolts (In Place B 2.7 B--G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolting B 2.8 B-Il Integrally Volumetric Yes-Note 8 90%
Note 5 Welded Vessel Jupports B 3.2 B-D Sceam Nozzle to Not Applicable No-Note 9 N/A N/A Genera:.;s Vessel Welds (Primacy 3.c.c,
u NORTH ANNA UNIT 2 INSERVICE INS?ECTION ASME CODE CIASS 1 COMPONENTS Table Table System or Area to be Examination Section XI Extent of Measures required IWB-2600 IWB-2500 Component Examined Requirement Code Relief ISI Coverage for accessability Iten No.
Examination Ecquest vs. Secticn XI Category B 3.3 B-F Nozzle to Safe Volumetric and Yes-Note 10 80%
Note 5 End Welds Surface B 3.4 B-G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolt ing (In Place)
B 3.5 B-G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolting B 3.6 B-G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolting B 3.7 B-H Integrally Weld-Not Applicable No-Note 11 N/A N/A ed Supports B 4.1 B-F Piping Press-Safe End to Volumetric and Yes-Note 12 80%
Note 5 ure Boundary Pipe Welds Surface B 4.2 B-G-1 Pressure Retain-Not Applicable No-Note 7 N/A N/A ing Bolting (In Place)
B 4.3 B-G-1 Pressure Not Applicable No-Note 7 N/A N/A Retaining Bolting B 4.4 B-G-1 Pressure Not Applicable No-Note 7 N/A N/A Retaining Bolting B 4.5 B-J Circumferential Volumetric Yes-Note 13 97%
Note 5 and Longitudinal Pipe Welds 1
i
i c.
cont.
NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENTS Table Table System or Area to l'a Examination Section XI Extent of Measures require IWB-2600 IWB-2500 Component Examined Requirement Code Relief ISI Coverage for accessability Item No.
Examination Request vs.Section XI Category B 4.6 B-J Branch Connec-Volumetric Yes-Note 14 20%
Note 5 tion Welds exceed-ing 6 inches diameter B 4.9 B-K-1 Integrally Welded volumetric Yes-Note 15 20%
Note 5 Supports B 5.1 B-G-1 Pump Pressure Pressure Retain-Volumetric Yes-Note 16 Note 16 N/A Boundary ing Bolts, in place B 5.2 B-G-1 Pressure Retain-Volumetric Yes-Note 17 Note 17 N/A ing Bolts, when and Surface removed B 5.4 B-K-1 Integrally Not Applicable No-Note 7 N/A N/A Welded Supports B 6.2 B-G-1 Valve Pressure Pressure Retain-Volumetric Yes-Note 17 Note 17 N/A Boundary ing Bolting, when and Surface removed B 6.4 B-K-1 Integrally Welded Not Applicable No-Note 17 N/A N/A Supports B 6.6 B-M-1 Valve Body Not Applicable No-Note 7 N/A N/A Welds 4
M
TABLE 1 NORTl! ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENT Notes:
- 1) The reactor vessel closure studs are removed during each refueling andd there will be no need for examination in place as required by IWB-2600.
- 2) The reactor vessc1 supports are integral with the primary nozzles and the examination requirement of IWB-2600 is covered by Item B 1.4.
- 3) This requirement of IWB-2600 is applicable only to Boiling Water Type reactors.
- 4) Exanination of 90 percent of the pressurizer nozzle to vessel welds (Category B-D) can be performed with the limitation permitted by I-5121.
The configuration of the nozzle welds limits 100 percent of the examina-tion coverage.
The configuration of a nozzle to vessel weld is shown in Figure B 2.2.
- 5) Exanination coverage is limited by configuration.
No additional work would improve exanination coverage.
- 6) The configuration of a typical pressurizer nozzle to safe-end weld (Category B-F) is shown in Figure B 2.4.
Ultrasonic examinations can be performed on 100 percent of the weld and the base metal on the safe-end side of the weld.
Configuration of the nozzle limits the examination to approximately 80 percent of the required base metal on the nozzle side.
Surface examina-tions can be performed to 100 percent of the code requirement.
- 7) There are no it ems in this category under the requirements of IWB-2600.
- 8) Ultrasonic examination can be performed on 100 percent of the weld and base metal on the support side of the weld. The configuration of the weld to the pressurizer limits the examination to approximately 80 percent of the code requirement.
- 9) The nozzles are integrally cast with the vessel head and there are no welds in this category.
- 10) The reactor coolant pipe to steam generator nozzle safe end welds can be examined by angle beam and straight beam from the top of the weld and from the pipe side to the extent required by T-532 of Section V.
The configuration of this weld is shown in Figure B 4.1.
Ultrasonic examina-tion from the nozzle side of the weld is not possible due to nozzle configuration.
One hundred percent of the surface examination require-ment can be performed.
.per
TABLE 1 NORTil ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENT Notes:
- 11) The supports are integrally cast with the vessel head and there are no welds in this category.
- 12) The pipe to safe end welds for the pressurizer and steam generators are covered in notes 6 and 10.
The reactor vessel safe end to piping welds are similar to the steam generator safe ends and Note 10 applies to these welds.
- 13) Limitations may occur for the examination of piping system circumferential butt welds when the welds occur at geometric discontinuities such as pipe to vessel welds, pipe to fitting welds or fitting to fitting welds.
For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces.
Examination from the fitting side would be dependent upon the geometric configuration.
Where elbows or tees are concerned, examination can be perforned from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling.
No examinations can be perforned f rom the fitting side when it is a valve or flange.
In instances where welds occur at fitting, access restrictions as outlined above occur on both sides of the weld.
In instances where the locations of pipe supports or hangers restrict the access available for the examination of pipe welds as required by IWB-2600, examinations will be performed to the extent practical unless removal of the support is permissible without unduly stressing the system.
- 14) The configuration of the reactor coolant branch nozzle connection velds is shown in Figure B 4.6.
Ultrasonic examination cannot be performed on the surface of the weld.
As an alternate method surface examination will be performed on 100 perc,at of the weld and adjacent base material.
- 15) The piping system integrally welded supports are attached to the pipe by fillet welds. The configuration of such welds is such that examinations cannot be performed to the extent required by IWB-2600 and only the base material of the pipe wall can be examined by ultrasonic techniques.
Surface examination will be performed on the integrally welded attachments to supplement the limited volumetric examination.
- 16) The reactor coolant pump seal housing bolts are of the socket heat type and the configuration is such that ultrasonic examinations as required by IWB-2600 cannot be performed when the bolting is in place.
Examina-tions will only be performed to the extent required by IWB-2600 when the seal housing is disassembled for maintenance.
- 17) This examination to the extent required by IWB-2600 will only be performed when the pump or valve is disassembled for maintenance purposes or at the end of the 10 year interval when disassembly is undertaken for the performance of pump casing or valve body examinations.
I t
TABLE 2 NORTH ANNA UNIT 2 IN3ERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS Table Table System or Area to be Examination Section XI Extent of Measures required IWC-2600 IWC-2520 Component Examined Requirement Code Relief ISI Coverage for accessability Item No.
Examination Request vs.Section XI Ct.tegory C1.2 C-B Steam Generators Nozzle to Volumetric Yes-Note 1 80%
Note 2 (3)
Vessel Welds C1.3 C-C Integrally N/A No-Note 3 N/A N/A welded supports C1.2 C-B Excess Letdown Nozzle to Heat Exchanger Vessel Welds N/A No-Note 3 N/A N/A C1.3 C-C Integrally weld-N/A No-Note 3 N/A N/A Supports C1.1 C-A Residual IIeat Circumferential Volumetric Yes-Note 4 90%
Note 2 Exchangers (2)
Butt Welds C1.2 C-B Nozzle to Volumetric Yes-note 5 0%
Note 5 Vessel welds C1.1 C-A Seal Water Circumferential Volumetric Yes-Note 4 96%
Note 2 lient Exchanger Butt Welds C1.2 C-B Nozzle to Vessel N/A No-Note 3 N/A N/A Welds C1.2 C-B Non-Regenera-Nozzle to N/A No-Note 3 N/A N/A tive Letdown Vessel Welds IIent Exchanger C1.1 C-A Regenerative Circumferential Volumetric Yes-Notes 4,6 80%
Note 2, 6 IIeat Exchanger Butt Welds C1.2 C-B Nozzle to Vessel N/A No-Note 3 N/A N/A Welds C1.3 C-C Integrally welded N/A No-Note 3 N/A N/A Supports E
C1.4 C-D Pressure Retain-N/A No-Note 3 N/A N/A ing Bolting
TABLE 2 (cont.)
NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS Table Table System or Area to be Examinat ion Section XI Extent of Measures required IWC-2600 IWC-2520 Component Examined Requirement Code Relief ISI Coverage for accessability Item No.
Examination Request vs.Section XI Category C1.2 C-B Volume Control Nozzle to Vessel N/A No-Note 3 N/A N/A Tank Welds C1.2 C-B Seal Water Injec-Nozzle to Vessel N/A No-Note 3 N/A N/A tion Filters (2) weld C1.1 C-A Reactor Coolant Circumferential Volumetric Yes-Note 7 0%
N/A Filter Butt Welds C1.2 C-B Nozzle to Vessel N/A No-Note 3 N/A N/A Weld C1.1 C-A Seal Water Circumferential Volumetric Yes-Note 7 0%
N/A Return Filter Butt Welds C1.2 C-B Nozzle to N/A No-Note 3 N/A N/A Vessel Welds C2.1 C-F,C-G Piping Circumferential Volumetric Yes-Note 8 98%
Notes 2,6 Butt Welds C2.3 C-F,C-G Branch Pipe Volumetric Yes-Note 9 10%
Notes 2,9 to pipe welds C3.1 C-F,C-C Residual Heat Casing Welds N/A No-Note 3 N/A N/A Removal Pumps (2)
C3.3 C-E-1 Integrally Welded N/A No-Note 3 N/A N/A Supports C3.1 C-F, C-G Centrifugal Casing Welds Volumetric Yes-Note 10 Note 10 N/A Charging Pumps (3)
C4.1 C-F C-G Valves Body Welds N/A No-Note 3 N/A N/A C4.3 C-E-1 Integrally Welded N/A No-Note 3 N/A N/A Supports
TABLE 2 NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 2 COMP 0NENTS Notes:
- 1) The geometric configuration of the nozzle surface prevents ultrasonic ex-aminations being performed to the extent required by IWC-2600.
Examinations will be performed to the extent practical from the weld and vessel surfaces adjacent to the weld.
2)
Examination is limited due to configuration,t.o additional work would improve coverage.
- 3) There are either no items in this category or items are excluded from exami-nation requirements of IWC-2600 by application of criteria given in IWC-1220.
The specific details of exclusions are:
(a) Letdown heat exchanger inlet and outlet nozzles are 2 inch diameter.
(b) Regenerative heat exchanger inlet and outlet nozzles are 3 inch dia-meter, there are no integrally welded supports or precsure retaining bolting on this vessel.
(c) Seal water return filter inlet and outlet nozzles are 3 inch diameter, there are no integrally welded supports or pressure retaining bolting on this vessel.
(d) Volume control tank inlet and outlet nozzles are 4, 3 and 2 inch dia-meter.
(c) Excess letdown heat exchanger inlet and outlet nozzles are 2 inch diameter, there are no integrally welded supports.
(f) Seal water injection filter inlet and outlet nozzles are 2 inch diameter.
(g) There are no integrally welded supports on the cteam generators.
(h) Reactor coolant filter inlet and outlet nozzles are 2 inch diameter and cover flange bolting is 3/4 inch diameter.
(i) Residual heat removal pump casings have no pressure containing welds, there are no integrally weldcJ supports.
(j) Seal water heat exchanger, inlet and outlet nozzles are 4 inch diameter, tubesheet flange bolting is 7/8 inch diametcr.
(k) There are no Class 2 valves with pressure containing welds or integrally welded supports.
- 4) The curvature of the weld reinforcement, heat configuration, and/or the flange configuration limits the extent that examinations can be performed for re-flectors transverse to the weld as required by T-535.2 of Section V.
Ex-aminations will be performed to the extent p ra c t ical.
TABLE 2 NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS
- 5) The residual heat exchanger nozzle to shell welds are covered by reinforcement rings and are not accessible for examination by either volumetric or surface techniques.
The area will be subject to visual examination for evidence of leakage during system pressure tests.
- 6) The location of support members may prevent ultrasonic examinations being performed to the extent required by IWC-2600.
Examinations will be performed to the extent practical unless support components can be removed to provide additional access.
- 7) The thickness of the materials utilized for construction of this component (0.165 to 0.185 inches) is such that meaningful results could not be expected with ultrasonic examination as required by IWC-2600.
Surface and visual examination of these velas will be performed as an alternative method.
8)
Examination of Class 2 piping system welds is limited to those occurring at gecmetric discontinuities such that some limitations may be expected at all locations. For pipe to fitting or pipe to vessel nozzle welds, examina-tions; can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be de-pendent upon the geometric configuration. Where elbows or tees are concerned, examination can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange.
In all cases one hundred percent of the weld material can be examined.
In instances where welds occur at fitting to fitting, access restricti3ns as outlined above occur on both sides of the weld.
In instances where ultrasonic examinations cannot be performed on one hundred percent of the volume of the weld and heat affected zone, surface examinations may be performed to supplement the limited volumetric examination.
- 9) The same restrictions to the examination of branch pipe to pipe welds occur in Class 2 systems as discussed in Note 14 in the Class 1 systems with ex-aminations being performed from the pipe side only.
Surface examinations would be performed to supplement the limited volumetric examination. However, the Class 2 branch connections located on the main steam lines are all covered, except for three 6" relief lines, with welded reinforcement rings or collars and are not accessible for either surface or volumetric examinations.
- 10) The pressure retaining welds in the charging pump casings are not normally accessible for examination as required by IWC-2600.
Examination of these welds will only be performed during this interval if the pump is disassemb-led for maintenance.
TABLE 3 NORT11 ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 3 COMPONENTS Component Code Applicable Method of Section XI of Code System Description / Identification to Construction Examination Relief Request Component Component Cooling Pumps CC-P-1A NA Visual / Operating Pressure Cooling CC-P-1B Surge Tank CC-TK-1 VIII Visual / Operating Pressure IIcat Exchangers (Shell Side)
CC-E-1A VIII Visual / Operating Pressure CC-E-1B RIIR Pump Seal Coolers Ril-E-2A NA
' Visual /Opereting Pressure Rll-E-2 B R.C. Pump L.O. and Stator RC-P-1A NA Visual / Operating Pressure Coolers RC-P-1B RC-P-lC Fuel Pool llent Exchanger FC-E-1A VIII Visual / Operating Pressure (Shell Side)
FC-E-1B Non-Regenerative IIcat Cll-E-2 VIII Visual / Operating Pressure Exchanger (Shell Side)
Seal Water IIcat Exchanger C11-E-1 VIII Visual / Operating Pressure (Shell Side)
ElIR lleat Exchangers RIl-E-1A VIII Visual / Operating Pressure (Shell Side)
Ril-E-1 B Excess Letdown Heat Exchanger CH-E-4 VIII Visual / Operating Pressure (Shell Side)
Neutron Shield Tank Coolers NS-E-1A VIII Visual / Operating Pressure (Shell Side)
NS-E-1B CRDM Shroud Cooling Coils HV-E-6A NA HV-E-6B HV-E-6C Piping B31.1 & B31.7 Visual / Operating Pressure Hangers and Supports N/A Visual
TABLE 3 (cont.)
NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 3 COMPONENTS Component Code Applicable Method of Section XI of Code System Description / Identification to Construction Examination Relief Request Chemical and Boric Acid Tanks CH-TK-1A VIII Visual / Operating Pressure Volume Control CH-TK-1B Not Stamped CH-TK-lC Boric Acid Transfer Pumps CH-P-2A P&V Class III Visual / Operating Pressure CH-P-2B CH-P-2C CH-P-2D Boric Acid Filter CH-FL-1 IIIC Visual / Operating Pressure Boric Acid Blender CH-BL-1 NA Visual / Operating Pressure Piping B31.1 & B31.7 Visual / Operating Pressure Hangers and Supports N/A Visual Spent Fuel Spent Fuel Pit Pumps FC-P-1A NA Visual / Operating Pressure Pit Cooling FC-P-1B Spent Fuel Pit Heat FC-E-1A VIII Visual / Operating Pressure Exchangers (Tube Side)
FC-E-1B Piping B31.1 & B31.7 Visual / Operating Pressure Hangers and Supports NA Visual Service Water Service Water Pumps SW-P-1A Visual / Operating Pressure SW-P-1B Auxiliary Service Water SW-P-4 Visual / Operating Pressure Pump Recire. Spray Heat RS-E-1A VIII Visual / Operating Pressure Exchangers RS-E-1B RS-E-lC RS-E-ID 4
cont.
NORTH ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 3 COMPONENTS Component Code Applicable Method of Section XI of Code System Description / Identification to Construction Examination Relief Request Charging Pump Lube CH-E-SA Visual / Operating Pressure Oil Coolers CH-E-5B CH-E-5C Charging Pump Seal Coolers CH-E-7A Visual / Operating Pressure CH-E-7B CH-E-7C Component Cooling Heat CC-E-1A VIII Visual / Operating Pressure Exchangers (Tube Side)
CC-E-1B Pipe Penetration Cooling Visual / Operating Pressure Coils Air Compressors SA-C-1 Visual / Operating Pressure IA-C-1 Air Compressor Coolers SA-E-1 Visual / Operating Pressure IA-E-1 Piping B31.7 Visual / Operating Pressure Valves not provided to permit isolation of underground por-tions of piping.
Request relief from IRD-2600(b).
Hangers and Supports Visual Casing Cooling Casing Cooling Pumps RS-P-3A Visual / Operating Pressure RS-P-3B Casing Cooling Tank RS-TK-1 Visual / Operating Pressure Piping B31.7 Visual / Operating Pressure Hangers and Supports Visual
.~
NORTl! ANNA UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 3 COMPONENTS Component Code Applicable Method of Section XI of Code System Description / Identification to Construction Examination Relief Request Auxiliary Pumps FW-P-2 Visual / Operating Pressure Feedwater FW-P-3A FW-P-3B Condensate Storage Tank CN-TK-1 Visual / Operating Pressure Piping Visual / Operating Pressure Hangers and Supports Visual Main Steam to Piping Visual / Operating Pressure Turbine Driven Auxiliary Hangers and Supports Visual Feedwater Pump
.