ML18136A023
| ML18136A023 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/28/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 720, NUDOCS 7910020455 | |
| Download: ML18136A023 (73) | |
Text
...
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGIN.IA 23261 September 28, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. O. D. Parr, Chief Serial No. 720 PO/ATV:baw Docket No.:
50-281 License No.:
DPR-37 Light Water Reactors Branch No. 3 Division of Project Management U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Requested Relief From Inservice Inspection and Testing Requirements Surry Power Station Unit No. 2 Pursuant to 10 CFR 50.55a(g), the Virginia Electric and Power Company hereby submits its programs for inservice inspection and testing of pumps and valves during the last forty month period of the first ten year interval for Surry Power Station Unit 2.
Per 10 CFR 50.55a(g)(4) the ASME Code and addenda "in effect" for this period have been determined to be the 1974 Edition of Section XI with Addenda thru the Summer of 1975.
Surry Unit 2 was not, however, designed to meet the detailed inservice inspection and testing requirements of the ASME Code,Section XI.
Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), we request specific relief from ASME Code require-ments pertaining to inservice inspection and testing of pumps and valves as outlined in attachments A, Band C.
The implementation of this program will begin on January 1, 1980 to allow the testing program to begin in an orderly manner and with the proper administrative controls.
Very truly yours,
- ~-
.,,.fl C. M. Stalh.ngs 7
Vice President-Power Supply and Production Operations Attachments A Surry Unit 2, Requested Relief from the Inservice Inspection Requirements for Class 1, 2 and 3 components as set forth in Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda through the Summer of 1975 (last 40 month period of the first 10 year interval).
B Surry Unit 2, Requested Relief from the Inservice Testing Requirements for Pumps as set forth in Subsection IWP to Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda thru the Summer of 1975 (last 40 month period of the first 10 year interval).
191002ofS.5
e e
VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton C Surry Unit 2 Requested Relief from the Inservice Testing Requirements for valves as set forth in Subsection IWV to Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda thru the Summer of 1975 (last 40 month period of the first 10 year interval).
D Surry Unit 2, Marked Up Flow Diagrams Showing ASME Code Class 1, 2 and 3 System Boundaries Relative to Inservice Inspection and Testing.
E Surry Unit 1, Revision to our letter serial No. 332C/111776 dated August 8, 1979, Page 16 of Requested Relief from In-service Testing Requirements of valves as set forth in Sub Section IWV to Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda thru the Summer of 1975 (last 40 month period of the first 10 year interval).
2
ATTACHMENT A SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE INSPECTION REQUIREMENTS FOR CLASS 1, 2 and 3 COMPONENTS AS SET FORTH IN SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THROUGH THE SUMMER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)
The enclosed tables provide a listing of the Class 1, 2 and 3 pressure-retaining components (and their supports) which are subject to the inspection requirements -of Subsections IWB, IWC and IWD of Section XI of the ASME Boiler and Pressure Vessel Code 1974 Edition with Addenda thru the Summer of 1975.
These tabulations identify the components to be inspected, the components safety class, the applicable code to which the component was built, and the method of 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 concerning 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 available 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 IWB-3000 of the 1977 Edition of Section XI will be utilized.
(b)
Articles IWA-4000, IWB-4000, IWC-4000 and IWD-4000 entitled "Repair Procedures" in the 1977 Edition of Section XI with Addenda thru the Summer of 1978 provide additional guidelines for making repairs and will be used in lieu of those contained in the 1974 Edition of Section XI with Addenda thru the Summer of 1975.
(c)
Requirements for the visual examination of Class 1 systems and com-ponents for evidence of leakage during the performance of a system pressure test following each refueling are identified by IWB-520.0.
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-109, 130 and 147 and 2-SI-107, 128 and 145, test lines to valves HCV-2850B, D and F, RHR return to valves MOV-2720B and check valve 2-RH-47.
During normal operation these portions of the systems are filled and pressurized to the normal accumulator operating pressure of 620 to 665 psig (refer to drawings 11548-FM-87A and 89B).
(ii) Hot leg injection between check valves 2-SI-88, 91 and 94 and check valves 2-SI-238, 239 and 240 and check valves 2-SI-226, 227.
These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11548-FM-89B).
(iii) Cold leg low head injection line between check valves 2-SI-79, 82 and 85 and check valves 2-SI-241, 242 and 243; and high head and boron injection to check valves 2-SI-235, 236 and 237 (refer to drawing 11548-FM-89B).
(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 system is cooled to 350°F and depressurized to 450 psig (refer to drawing 11548-FM-87A).
(d)
Subsections IWB and IWC contain differing requirements for the hydrostatic testing of Class 1 and Class 2 systems and components.
The implementation 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 1 system.
Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412(a) on those portions of the Class 2 systems identified below.
Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal operating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system.
(i)
R. C. Pump seal bypass lines from the flow orifice to valve HCV-2307 (refer to drawing 11548-FM-SSC).
(ii)
Hot leg injection between check valves 2-SI-88, 91 and 94 and check valves 2-SI-238, 239 and 240 and check valves 2-SI-226, 227.
These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11548-FM-89B).
(iii)
R. C. Pump seal injection line from check valve 2-CH-323, 333 and 349 to manually operated valve 2-CH-294, 297 and 300 (refer to drawings 11548-FM-SSB and SSC).
(iv)
Excess letdown system from valve HCV-2201 to HCV-2137 (refer to drawing 11548-FH-SSC).
(v)
Letdown line from valve LCV-2460B to orifice outlet valves HCV-2200A, Band C (refer to drawing 11548-FM-88C).
(e)
The examination requirements for Class 3 systems and components as given in the enclosed tabulation are in accordance with IWD-2410(c) which specifies that 100 percent of the components be examined as required by IWA-5240 and IWD-2600 either during normal operation or during system inservice testing.
An additional requirement of IWD-2410(b) is the examination of Class 3 systems and components for evidence of leak.age during the performance of a system pressure test in accordance with IWD-5000.
It should be noted, that these system pressure tests when required are impractical in those portions of systems, such as component cooling, service water, and boric acid transfer and recirculation, which are in continuous operation during plant operation.
The continuous functional operation serves to demonstrate the structural and leak-tight integrity of these systems.
Visual examinations of these systems will be performed at normal operation pressures to verify leaktightness.
(f)
Ultrasonic examinations will be conducted in accordance with the provisions of Appendix I and Article 5 of Section Vas 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 ultrasonic examina-tion 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 recog-nized by the NRC by reference in 10 CFR 50.
However, Appendix III is the first guideline that has been published in the ASME Code 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 fabricate the block from material taken from the component, the block may be fabricated from a material of a specification 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 straight beam longitudinal wave velocity and attenuation found in the unclad components.
For the components in Surry Unit 2, particularly the pressurizer and steam generators, it will be impossible to meet the requirements of alternatives 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 impossible to obtain a comparison of sound beam velocities arid attenuations in the unclad component.
Limitations may occur for the examination of p1p1ng system circumferential buttwelds (Category B-J) 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 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 most cases one hundred percent of the weld material can be examined.
In instances where welds occur at fitting to fitting, access restrictions 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.
Welds in the Surry Unit 2, Class 1 system which due to limitations, would require surface examinations are:
(i)
Loop 1 Cold Leg Injection line; Welds 7.
(ii)
Loop 2 Cold Leg injection line; welds 5 and 7.
(iii)
Loop 3 RTD return line; weld 9.
(iv)
Loop 3 Cold leg injection line; welds 3 and 4.
(v)
Pressurizer safety valve lines welds 7 and 8.
(vi)
Pressurizer Relief line; welds 4 and 19.
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.
Certain Class 2 systems or portions of Class 2 systems and components are exempt from the examination requirements of the IWC-2520 by IWC-1220.
A summary of these exemptions as applicable to the Surry plant systems are as follows:
(i)
All CVCS piping equal to or less than four-inch nominal diameter and is exempted by IWC-1220(d).
e VIII B 31.1 B 16.5 ASME Boiler and Pressure Vessel Code,Section VIII, Pressure Vessels USA Standard USAS B 31.1 Code for Pressure Piping USA Standard USAS B 16.5 Steel Pipe Flanges, Flanged Valves and Fittings
TABLE TABLE nrn-2soo
- -lWB'--2600 EXAMINATION SYSTEM OR.
- ITEM NO.
CATETORY COMPONENT Bl. l B-A Reactor Vess.el 2-RC-R-l Bl. l B-A Bl. l B-A Bl. l B-A
-Bl. 2 B-A Bl.2 B-B Bl. 3 B-C Bl.3 B-C Bl.4 B-D
~'i. 4 B-D
\\
JH.5 B-E Bl. 6 B-F
.lttv UNI'l' i IN SER\\/ r,:r~ INSPECTION ASME CODE c°".ASS 1 COMPONENTS CODE APPLICABLE TO CONSTRUCTION III-A 0
t*
~REA TO BE EXAMINED Upper to intermediate shell course circumferential weld
- Intermediate to lower shell course circumferential weld Intermediate shell course longitu-dinal wel_ds (2)
Lower shell course longitudin~l welds (2)
Lower head to shell circumferential weld Lower head ring to disc circumferen~
tial weld Vessel to flange weld
.Closure hea_d to flange weld Outlet nozzle to vessel welds (3)
Inlet Nozzl_e to. vessel welds (3)
CROM, Vent* and In-Core Instrumen.-
tation penetrations and CRD~ seal welds Outlet nozzle to safe-ends *welds (3)
EXAMINATION REQUIREMENT Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumet:r;ic Volumetric Volumetric Volumetric Visual Volumetric &.
Surface SECTION XI, CODE RELIEF REQUESTED' No No No No No No No
. No No No No No
e TABLE TABLE I\\IB-2500
- *IWB-2600 EXAMINATION ITEM NO, CATETORY Bl. 6 B-F Bl. 7 B-G-1 Bl.8 B-G-1 Bl.9 B-G-1 Bl.10 B-G-1 Bl.11 B-G-2 Bl.12 B-H Bl.13 B-I-1 Bl.14 B-I-1
\\
Bl.15 B-N-1 Bl.16 B-N-2 BL 17 B-N-3 j
SYSTEM OR COMPONENT lY UNI'l' i J.NSE~i,~g INSPECTION ASME COUB Ci.ASS l COMPONENTS CODE APPLICABLE TO CONSTRUCTION
~REA TO BE EXAMINED l*
Inlet nozzle to safe-end welds (3)
~losure Head Studs (In-Place)
Closure Head Studs & Nuts
.. I Vessel flange ligaments Closure*head Washers Conoseal*Bolting Integrally Welded vessel supports Closure Head Cladding Vessel Cladding Vessel Int~rior Surfaces and Internals Interior Attachments and Core Support Structures Core Support Structures SECTION XI*
EXAMINATION CODE RELIEF REQUIREMENT REQUESTED Volumetric &
No Surface Not No-Applicable Note 1 Volumetric &
No Surface Volumetric No Visual No Visual No Not No-Applicable Note 2 Surface &
No-Visual or Note 3 Volumetric Visual No Visual No Not No -
Applicable Note 4 Visual No
TABLE
- -lWB-2600 ITE~t NO.
Bl. 18 Bl.19 B2.l B2. l B2.2 B2.3 B2.4 B2.5 B2*.6 B2.7 B2. 8 B2.9
. B2.10 B2.ll B3.l TABLE I\\IB-2500 EXAMINATION CATETORY B-0 B-P B-B B-B B-D B-E B-F
- B-G-1 B-G-1 B-G-1 B-H B-I-2 B-P B-G-2 B-B SYSTEM OR COMPONENT Pressurizer 2-RC-E-2 Steam Generators (3) Primary Side I
tw.tV UNI'l' ~
J.NSEffii f. !I~ l NSPECTION ASME COl)J~ C*,ASS l COMPONENTS CODE APPLICABLE TO CONSTRUCTION III-A
. I*
III-A
~REA TO BE EXAMINED Control-Rod Drive Housings Exempted Components Longitudinal Shell welds (6)
Circumferential shell welds (7)
Nozzle to vessel welds (6)
Heater Penetrations Nozzle to ~afe-end welds (6)
Pressure Retaining Bolting (in. place)
Pressure Retaining Bolting when removed Pressure Retaining Bolting Integrally Welded Ve~sel Suppqrts
- Vessel cladd:Lng Exempted Components Manway Bolting Channel Head to tubesheet Weld (3) e EXAMINATION REQUIREMENT Volumetric Visual Volumetric Volumetric Not Applicable Visual Volumetric &
Surface Not Applicable Not Applicable Not Applicable Volumetric Visual Visual Visual V9lumetric SECTION XI
- CODE RELIEf REQUESTED No No No Yes -
Note 17 No -
Note 5 No No No -
Note 6 No -
Note 6 No -
Note 6 No No No No No
_a.tv UNI't' i INSEltV r,~g INSPECTION ASME CODE C,ASS l. COMPONENTS TAllLE TABLE I\\JB-2500 SECTION XI *
- *IWB-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAM! NATION CODE RELIEF ITE~t NO.
CATETORY COMPONENT TO CONSTRUCTION
~REA TO BE EXAMINED REQUIREMENT REQUESTED' B3.2 B-D 2-RC-E-lA Nozzle to Vessel welds (6)
Not No-2-RC-E-lB Applicable 2-RC-E-lC Note 7 B3.3 B-F Nozzle to safe-end welds (6)
Volumetric &
Yes -
- Surface, Note 8 B3.4 B-G-1 Pressure Retaining Bolting Not No -
(in place)
Applicable Note 6 B3.5.
B-G-1 Pressur~ Retaining Bolting, Not No -
when removed Applicable Note 6 B3.6 B-G-1 Pressure Retaining Bal ting Not No -
Applicable Note* 6 B3.7 B-H Int~grally welded supports Not No -
Applicable Note 6 B3.8 B-I-2 Vessel Cladding Visual No B3:9 B-P Exempted Components Visual No B.3.10 B-G-2 l*
Manway Bal ting Visual No B3.'l B-B Regenerative III-C Head to shell welds (6)
Volumetric Yes-Note
\\
Heat Exchanger 2-CH-E-3 19 B3.l B-B
. Shell to tubesheet welds (6)
Volumetric Yes-Note 19
\\
j TABLE
- -lWB-2600 ITEM NO.
B3.2 B3.3 B3.4 B3.5 B3.6 B3.7 B3.8 B3.9 B3.10 B4.1 B4.2 B4.3 TADLE IUB-2500 EXAMINATION CATETORY B-D B-F B-G-1 B-G-1 B-G-1 _
B-H B-I-2 B-P B-G-2 B-F B-G-1 B-G-1 SYSTEM OR COMPONENT Piping Pressure
- Boundary
-lV UNI'l' i J.NSElt\\, I Jg lNSPIWTION ASMErJouiC£,A!:i8 l t:OMPONlrnTS CODE.APPLICABLE
. TO CONSTRUCTION
~REA TO BE EXAMINED Nozzle.to head welds (12)
. Nozzle to safe end welds Pressure Retaining Bolting (in place)
Pressure Retaining Bolting.(when I*
removed)'
Pressure* Retaining Bolting Integrally Welded Supports Vessel Cladding Exempted Components Pressure Retaining Bolting Safe end to pipe welds Pressur~ Retaining Bolts
. '(in place)
Pressure Retaining Bolts when.removed SECTION XI
- EXAMINATION CODE RELIEF
- REQUIREMENT REQUESTED" Volumetric Yes-Note 18
- Not No-Note 6 Applicable Not No-Note 6 Applicable Not No-Note 6 Applic.able Not No-Note 6 Applicable Not No'.""Note 6 Applicable Not No--:Note 6 Applicable Visual.
- No Not No-Note 6 Applicable Not No -
Applicable Note"6 Not No -
Applicable Note 6 Not No -.
Applicable Note 6
I
- l.
r i I
I I
TABLE
- -lWB-2600 ITEM NO.
B4.4 B4.5 B4.6
. B4. 7 B4.8 B4.9 B4.10 B4.ll B4.12 BS.l BS. l TABLE nm-2soo EXAMINATION CATETORY B-G-1 B-J B-J B-J B-J B-K-1 B-K-1 B-P B-G-2 B-G-1 B-G-1 SYSTEM OR COMPONENT Reactor Coolant Pumps (3) 2-RC-P-lA 2-RC-P-lB 2-RC-P-lC aw UNI'!'~
INSimv 1,:g INSPECTION ASHE COl)J~ C,ASS 1 COMPONENTS CODE APPLICABLE TO CONSTRUCTION III-A
~REA TO BE EXAMINED Pressure Retaining Bolting Circumferential and Longitudinal Pipe Welds Branch Pipe connection weld$
exceeding 6" diameter.
Branch Pipe Connections Weld 6" diameter and smaller Socket Welds Integrally Welded Supports Support Components Exempted Components Pressure Retaining Bolting Main Flange Bolting (in place)
Seal Hous1ng Bolting (in place).
EXAMINATION REQUIREMENT Not Applicable Volumetric Volumetric Surface Surface Volumetric Visual Visual Visual Volumetric Volumetric SECTION XI,
CODE RELIEF REQUESTED*
No -
Note 6 Yes -
Notes.
9 and 10 Yes -
Note 11 No No Yes -
Note 12 No No No No Yes -
Note 13
l'l UNI'!' ~
r.wm ITCTNrw1rnrr10N ASMEtromr c ~-1 COMPOtfENTS TABLE TABLE nm-2soo SECTION XI.
- -lWB-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITE~f NO.
CATETORY COMPONENT TO CONSTRUCTION
~REA TO BE EXAMINED REQUIREMENT REQUESTED*
BS.2 B-G-1 Main Flange Bolting when removed Volumetric &
No -
Surface Note 14 BS.2 B-G-1 Seal Housing Bolting when Volumetric &
No -
removed*
Surface.
Note 14 BS.3 B-G-1 t-lain. Flange Bolting Visual No BS.3 B-G-1 Seal Housing Bolting Visual No B5.4 B-K-1 Integrally Welded Supports Volumetric Yes -
Note 15 BS.S B-K-2 Support Compo~ents Visual No B5.6 B-L-1
- Pump Casing Weld Volumetric No Note 16 B5~7 B-L-2 Pump Casings Visual No B5.8 B-P I*
Exempted Components Visual No BS.9 B-G-2 Pressure Retaining Bolting Not No I \\
Applicable Note *6 B6.l B-G-1
- Valve Pressure Pressure Retaining Bolting Volumetric No Boundary
. '(in place)
B6.2 B-G-1 Pressure Retaining Bolting Volumetric &
No when removed Surface
I I
I I
- I I
- j j
i i
TABLE
- *IWB-2600 ITE!-1 NO.
B6.4 B6.5 B6.6 B6.7 B6.8 B6.9 TADLE I\\IB-2500 EXAMINATION SYSTEM OR CATETORY COMPONENT
-l't' UNI'!' ~
INSEIB.if,:g INSPECTION ASME COUE C1,AS8 1 COMPONENTS CODE APPLICABLE TO CONSTRUCTION
~REA TO BE EXAMINED
--.------------------.Pressure Retaining Bolting B-K-1 B-K-2 B-M-1 B-M-2 B-P B-G-2
. t*
Integrally welded supports Support Components Valve Body Welc;ls
- Valve Bodies Exempted Components Pressure.Retaining Bolting SECTION XI.
EXAMINATION CODE RELIEF REQUIREMENT REQUESTED*
Visual No Not No -
Applicable Note 6 Visual No Not No Applicable Note 6 Visual No Visual No Visual No
SURRY UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENTS NOTES
- 1.
The Reactor Vessel Closure Head Studs are removed during each refueling and there will be no need for examination in place as required by IWB-2600.
- 2.
The reactor vessel is supported on pads integral with the inlet and outlet nozzles and therefore are excluded from examination requirements of IWB-2500 by Category B-H.
- 3.
Radiation levels beneath the closure head may affect the allowable dosage of personnel doing surface and visual examination.
The pres-ence of the cladding material is not considered when performing the stress analysis of the vessel such that failure of the cladding would not affect the integrity of the vessel.
The closure head cladding will be volumetrically examined concurrent with the exam-inations performed on the closure head to flange weld.
4, This requirement is applicable only to Boiling Water Type Reactors.
- 5.
The pressurizer nozzles are integrally cast with the vessel head and therefore there are no welds requiring examination in accordance with the requirement IWB-2600.
- 6.
There are no items in this category on this component in the Surry Unit 2 Class 1 Systems.
7, The steam generator nozzles are integrally cast with the channel head and therefore are no welds in this category.
- 8.
Examinations of the steam generator primary nozzle to safe-end and safe-end to pipe weld is limited both by the nozzle geometry and surface condition and the limited surface preparation on the pipe side of the weld.
The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld.
Ultrasonic examination is limited to this from the edge of the weld.
Examinations can be per formed on the surface of the weld but are severely limited from the nozzle side by the rough, as cast surface.
Surface examination can be performed on one hundred percent of the weld and the base metal on the pipe side.
The configuration is shown in Figure 1.
- 9.
Limitations may occur from the examination of piping system cir-cumferential butt welds (Category B-J) when the welds occur at geometric discontinuties 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 sur-faces.
Examinations from the fitting side would be dependent 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 fit-ting to fitting, access restrictions 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 head affected zone, surface examinations will be performed to supplement the limited volumetric examination.
- 10.
The ninety degrees elbows on the crossover leg of the reactor coolant system are fabricated in two halves from austenitic stain-less steel castings welded together by the electroslag process.
The structure and nature of the electroslag weld in the cast austeni-tic ninety degree elbows is such that the material is opaque to ultrasonic transmissions utilizing currently available techniques.
Radiography is the only other available technique for volumetric examination. It is not possible to obtain code acceptable radiographs with double wall "shots" on these components which are approximately thirty-eight inches diameter, 3.5 inches wall thickness, containing a two-inch thick splitter plate and having radiation levels of up to three hundred mr/hr on contact.
Surface examination will be performed as a substitute for volumetric.
- 11.
The configuration of the reactor coolant branch nozzle connection welds is as shown in Figure 2.
Ultrasonic examinations cannot be performed on the surface of the weld.
Examinations will be performed to the extent practical from the pipe and nozzle adjacent to the weld.
Surface examination will be performed to.supplement this volumetric examination.
- 12.
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 examinations.
- 13.
The reactor coolant pump seal housing bolts are of the socket head type and the configuration is such that ultrasonic examinations as required by IWB-2600 cannot be performed when the bolting is in place.
Examinations will be performed to the extent required by IWB-2600 when the seal housing is disassembled for maintenance.
- 14.
The reactor coolant pump main flange bolting is ultrasonically examined, in place in accordance with the requirements of IWB-2600, Item B5.l.
Both the main flange and seal housing bolting will be examined as required by rdB-2600, Item BS.2 whenever a pump is disassembled for maintenance at the end of the ten-year interval when a pump will be disassembled for the performance required by Category B-L-1.
e
- 15.
The structure and nature of the material of integrally welded pump supports are such that it is opaque to ultrasonic transmis-sion.
Surface and visual examination will be performed as a substi-tute for volumetric.
- 16.
The reactor coolant pump casings in Surry Unit 2 are fabricated from two heavy wall austenitic steel castings joined together by a weld formed by the electroslag process.
The structure and nature of this material are such that it is opaque to ultrasonic trans-mission.
Volumetric examination as required by IWB-2600 will be attempted utilizing radiographic techniques.
The success of these examinations will be dependent upon the availability of high energy gamma sources and the level of background radiation.
Internal fittings in the pump may also provide restriction to the extent of examination that can be performed.
- 17.
Two of the pressurizer circumferential shell welds are not accessible for examination by volumetric or surface method due floor penetration and support structure interference.
They will be subject to visual examination for evidence of leakage during system pressure tests.
- 18.
Due to joint configuration of the nozzle to shell welds volumetric examination is impractical.
Surface examination will be done as a substitute.
- 19.
The regenerative heat exchanger is a three pass vessel, having a total of six head to shell welds and six shell to tubesheet welds.
Radiation levels adjacent to this heat exchanger are between six and seven R/hr.
The total time required for erection of scaffolding, removal of all insulation covering welds, cleaning, performing examinations and restoration of insulation could take a total of three to four hours for the examination of a 1/2" long portion of each of twelve welds in category B3.l, such that personnel involved could be subjected to a total accumulated dose of up to five-six man rem.
'.~~*---*---**** e
-1'{
I UNI'l' 2' e
INSER\\ I*~E INSPECTION ASME COUE C~ASS 2 COMPONENTS TABLE SECTION XI IWJ-2520 TABLE EXAMINATION CODE RELIEF rwe-2600 EXAMINATION SYSTEM OR CODE APPLICABLE ITEM NO.
CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED Cl. l C-A Steam Genera-IIIA Upper Head to Shell Weld Volumetric No rators (3)
(Shell Side)
Cl. l C-A 2-RC-E-lA Upper Shell to Transition Weld Volumetric No 2-RC-E-lB 2-RC-E-lC C 1. 1 C-A Transition to lower shell weld Volumetric No Cl. l C-A Lower Shell to Stub barrel weld Volumetric No Cl. l C-A Stub barrel to tubesheet weld Volumetric No Cl. l C-B Steam Outlet Nozzle to shell weld Volumetric No Cl. 2 C-B Feed water Inlet Nozzle to shell Volumetric No I
- I Cl.3 C-C Integrally Welded Supports Not No -
Applicable Note 1 Cl.4 C-D Manway Bolting Visual and No Volumetric t*
c1.1 C-A Residual Heat IIIC Head to Shell Welds Volumetric No Exchangers (2)
(Tube Side)
Cl. l C-A 2-RH-E-lA Shell to flange welds Volumetric No 2-RH-E-lB C 1. 2 C-B Nozzle to vessel welds Volumetric Yes -
Note 2 Cl. 3 C-C Integrally Welded Supports Surface No Cl. 4 C-D Tubesheet Flange Bolting Visual and No Volumetric
- l11lY UNl'J.':?
INS Yer~ INSPECTION ASME COUE CLASS 2 COMPONENTS TABLE TABLE IW:i-25~0 SECTION xr rwe-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITEM NO.
CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED -
Cl. l C-A Excess Letdown III-C Head to shell weld Volumetric No Heat Exchanger (Tube side)
Cl. l C-A 2-CH-E-4 Shell to flange weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 3 Cl. 3 C-C Integrally welded supports Not No -
Applicable Note 3 Cl.4 C-D Pressure Retaining Bolting Visual and No Volumetric Cl. l C-A Non Regenera-III-C Head to shell weld Volumetric No tive Letdown Heat Exchanger (Tube Side)
Cl. l C~A 2-CH-E-2 Shell to flange weld Volumetric No Cl.2 C-B Nozzle to vessel welds Not No -
Applicable Note 4
\\
l*
c1.3 C-C Integrally welded supports Surface No
\\
Cl.4 C-D Pressure Retaining Bolting Visual and No Volumetric Cl. l C-A Seal Water III-C Head to shell welds Volumetric No Heat Exchanger (Tube Side)
Cl. l C-A 2-CH-E-l Shell t:o flange welds Volumetric No Cl. 2 C-B Nozzle to. ves.sel welds Not No -
Applicable Note 5
TABLE rwe-2600 ITEM NO.
Cl. 3 Cl.4 Cl. l Cl. l Cl. 2 Cl. 3 Cl. 4 Cl. l C 1. l
\\
c*1. 2 Cl. 3 Cl.4 Cl. l Cl. l TABLE IWJ-25~0 EXAMINATION CATETORY C-C C-D C-A C-A C-B C-C C-D C-A C-A C-B C-C C-D C-A C-A SYSTEM OR COMPONENT Volume Control Tank 2-CH-TK-2 Seal Water Injection Filters (2) 2-CH-FL-4A 2-CH-FL-4B Reactor Cool-and Filter 2-CH-FL-2 A
ll*tV UN l'I' l!
rnflat1*JE INSPEc'irION ASME CODE CLASS 2 COMPONENTS CODE APPLICABLE TO CONSTRUCTION AREA TO BE EXAMINED III-C III-C III-C Integrally welded supports Pressure Retaining Bolting Upper Head to shell weld Lower head to shell weld Nozzle to vessel welds Integrally Welded Supports Pressure Retaining Bolting Shell to flange weld Head to shell weld Nozzle to vessel welds Integrally Welded Supports Pressure Retaining Bolting Cover Weldment to shell weld Head to shell weld EXAMINATION REQUIREMENT Surface Not Applicable Volumetric Volumetric Not Applicable Surface Visual and Volumetric Volumetric Volumetric Not Applicable Surface Visual and Volumetric Volmetric Volumetric SECTION XI CODE RELIEF REQUESTED_
No No -
Note 5 No No No -
Note 6 No No No No No -
Note 7 No No Yes -
Note 8 Yes -
Note 8
TABLE rwe-2600 ITEM NO.
Cl. 2 Cl.3 Cl.4 Cl. l Cl. l Cl. 2 Cl. 3 Cl.4 C2.l
\\
C2. 2 C2.3 C2.4 TABLE I\\ol'l-2570 EXAMINATION CATETORY C-B C-C C-D C-A C-A C-B C-C C-D C-F;C-G C-F;C-G C-F;C-G C-D SYSTEM OR COMPONENT Seal Water Return Filter 2-CH-FL-3 Piping Systems AllltV UNl'l' 2 INS-1GE INSPECTION ASME CODE CLASS 2 COMPONENTS CODE APPLICABLE TO CONSTRUCTION III-C t*
AREA TO BE EXAMINED Nozzle to vessel welds Integrally Welded Supports Pressure Retaining Bolting Cover Weldment to shell weld Head to shell weld Nozzle to vessel welds Integrally welded supports Pressure Retaining Bolting Circumferential Butt Welds Longitudinal weld joints in fittings Branch Pipe to Pipe Welds Pressure Retaining Bolting EXAMINATION REQUIREMENT Not Applicable Surface Not Applicable Volumetric Volumetric.
Not Applicable Surface Not Applicable Volumetric Volumetric Volumetric Visual and Volumetric SECTION XI CODE RELIEF REQUESTED_
No -
Note 8 No No -
Note 8 Yes -
Note 8 Yes -
Note 8 No -
Note 8 No No Note 8 Yes -
Note 9 No Yes -
Note 10 No
- u*w UNI'l' 2 INS T:m INSPECTION e
ASME CODE CLASS 2 COMPONENTS TABLE TABLE I\\..U-2520 SECTION XI rwe-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITEM NO.
CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED.
C2.5 C-E-1 Integrally Welded Supports Surface No C2.6 C-E-2 Support Components Visual No C3.1 C-F Residual Heat Pump Casing Welds Not No -
Removal Pumps (2)
Applicable Note 11 C3. 2 C-D' 2-RH-P-lA Pressure Retaining Bolting Visual and No 2-RH-P-lB Volumetric C3. 3 C-E-1 Integrally Welded Supports Not No -
Applicable Note 11 C3.4 C-E-2 Support Components Visual No C3.l C-D*
Charging Pumps (3)
Pump Casing Welds Not No -
Applicable Note 11 C3.2 C-D 2-CH-P-lA Pressure Retaining Bolting Visual and No 2-CH-P-lB Volumetric 2-CH-P-lC C3. 3 C-E-1 Integrally Welded Supports Not No -
l*
Applicable Note 11 C3.4 C-E-2 Support Components Visual No C4.1 C-F;C-G Valves Valve Body Welds Not No -
Applicable Note 12 C4.2 C-D Pressure Retaining Bolting Visual and No Volumetric C4.3 C-E-1 Integrally Welded Supports Not No -
Applicable Note 12 C4.4 C-E-2 Support Components Visual No
SURRY UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS NOTES
- 1.
There are no items in this category on this component in the Surry Unit 2 Class 2 systems.
- 2.
The nozzle to vessel welds of the residual heat exchangers are covered by l" thick by 3" wide reinforcement pad as shown in Figure
- 3.
These welds are not accessible for examination by volumetric or surface methods.
The area will be subject to visual examination for evidence of leakage during system pressure tests.
- 3.
Excess Letdown Heat Exchanger nozzles are 2" diameter.
There are not any integrally welded supports on this vessel.
Therefore no examination is required under these categories.
- 4.
Non Regenerative Letdown Heat Exchanger nozzle to vessel welds are 2" diameter and *therefore requires no examination under this category.
- 5.
Seal Water Heat Exchanger nozzle to vessel welds are 4" diameter and the pressure retaining bolting is.75" diameter therefore they require no examination under this category.
- 6.
Volume Control Tank nozzle to vessel welds are 4" and 3" diameter therefore require no examination under this category.
7, Seal Water Injection Filters nozzle to vessel welds are 2" diameter, therefore require no examination under this category.
- 8.
Reactor Coolant Filter and Seal Water Return Filter nozzle to vessel welds are 3" diameter and the bolting is.75" diameter therefore no examination is required under these categories.
The thickness of the materials (0. 188" thick) used for the construction of these filters is such that meaningful results could not be expected with ultrasonic examination as required by IWC-2600.
Surface and visual examination of these welds (Cover weldment to shell and head to shell) will be performed as an alternative method.
- 9.
Examination of Class 2 piping systems is limited to those occurring at geometric discontinuities such that some limitations may be expected at all locations.
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 configura-tion.
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 examination 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.
\\
e SURRY At l'l.i INSRRVU~rrmTT.ON ASME CODI~ *CLASS ] COMPONENTS com:
COMPONENT APPLICABl,E TO METHOD OF SECTION XI CODE SYSTEM.
DESCRIPTION/ IDENTIFICATION CONSTRUC:T::.10::::N::._ _____
--=E.;;,::XAM::.=.::.;IN....:A..:..T_I_O_N _______
RE_L_I_E_F_RE Q_UE_S_T_E_D
- ....::....:::::~'-------=..:::.;:,.::.:.:;~:..::..:.~~~------------
Chemical and Volume Control Main Steam to Turbine Driven Auxiliary Boric Acid Tank 1-CH-TK-lC Boric Acid Transfer Pump l-CH-P-2C Boric Acid Transfer Pump l-CH-P-2D Boric Acid Filter 2-CH-,FL-l Boric Acid Blender 2-CH-BL-l Piping
'Supports and Hangers Piping Feedwater Pump Supports & Hangers
\\
Auxiliary Feed water Auxiliary Feed Pump 2-FW-P-2 (Turbine Driven)
Auxiliary Feed Pump 2-FW-P-3A (Motor Driven)
Auxiliary Feed Pump 2-FW-P-3B (Motor Driven)
Auxiliary Feed Pump 2-FW-P-2 Oil Cooler VIII IIIC Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual /Operating Pressure Visual Visual/Operating Pressure Visual Visual /Opera ting Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure
\\
e SYSTEM Auxiliary Feed water Circulating and Service Water
\\
SURRY er.__&_
INSERVICF. Il!S !'EC1'ION ASME CODE *CLASS 3 COMPONENTS com:
COMPONENT DESCRIPTION/IDENTIFICATION APPLICABLE TO METHOD OF SECTION XI CODE CONSTRUCT ::..:IO:::.:N::.._ _____
-=E::XAM=.:.I::.:N:..:.:A.:.:T:..:I:..:O..:.;N _______
RE_L_I_E_F_RE__._QU_E_S_T...;.E_D Auxiliary Feed Pump 2-FW-P-3A Oil Cooler Auxiliary Feed Pump 2-FW-P-3B Oil Cooler Condensate Storage Tank 2~CN-TK-l Piping Supports and Hangers Recirculation Spray Heat Exchanger 2-RS-E-lA (tube side)
Recirculation Spray Heat Exchanger 2-RS-E-lB (tube side)
Recirculation Spray Heat Exchanger 2-RS-E-lC (tube side) t*
Recirculation Spray Heat Exchanger 2-RS-E-lD (tube side).
Component Cooling Water Heat Exchanger 1-CC-E-lC (tube side)
Component Cooling Water Heat Exchanger 1-CC-E-lD (tube side)
Visual/ Opera ting Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressur~
Visual/Operating Pressur.e Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure
, I I
! l I I
I
\\
11 I
SYSTEM Circulating and Service Water
\\
SURRY-~
INSERVICR llfSPECTION
.ASME CODE *CLASS 3 COMPONENTS com:
e COMPONENT DESCRIPTION/IDENTIFICATION APPLICABJ,E TO METHOD OF SECTION XI CODE CONSTRUCT =-IO:..:N:.:__ ______
E.;...XAM_I_N_A_T_I_O_N _______
RE_L_I_E_F_RE~QU_E_S_T_E_D Charging Pump 2-CH-E-5A Lubricating Oil Cooler Charging Pump 2-CH-E-5B Lubricating Oil Cooler Charging Pump 2-CH-E-5C Lubricating Oil Cooler Charging Pump 2-CH-E-7A Seal Cooler Charging Pump 2-CH-E-7B Seal Cooler Charging *Pump 2-CH-E-7C Seal Cooler
- Charging Pump 2-CH-E-7D Seal Cooler Charging Pump 2-CH-E-7E Seal Cooler Charging Pump 2-CH-E-7F Seal Cool!'r Charging Pump Seal Cooling Surge Tank 2-CC-TK-3 Charging Pump Cooling Water Pump 2-CC-P-2A Charging Pump Cooling Water Pump 2-CC-P-2B Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure
i
- I I I I
'! ' i I
'i i I
I l i !
i I I I J
'I i
'1 l I i
i
, I I.
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I,
. SURRY-!:..~
INSERVICF. ms l'EC'l'ION ASME CODI~ *CLASS 3 COMPONENTS com:
COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE
~S_Y_ST_E_M ______
D_E_S_C_R_I_P_T_IO_N_/c_I_D_E_N_T_I_F_I_CA_T_I_O_N--,-_____
c_o_N_S_T_RU_C'I ::..IO:..;N~ ______
E_XAM_I_N_A_T_I_O_N _______
RE_L_I_E_F_R_E...,_QU_E_S_T_E_D Circulating and Service Water Component Cooling Water Charging Pump Intermediate Seal Cooler
. 2-SW-E-lA Charging Pump Intermediate Seal Cooler 2-SW-E-lB Charging Pump Service Water Pump 2-SW-P-lOA Charging Pump Service Water Pump 2-SW-P-lOB Recirculation Spray Hx Radiation Monitori-ing Sample Pump 2-SW-P-SA Recirculation Spray Hx Radiation Monitro-ing Sample Pump 2-SW-P-SB Recirculation Srpay Hx Radiation Monitor-ing Sample Pump 2-SW-P-SC Recirculation Spray Hx Radiation Monitor-ing Sample Pump 2-SW-P-SD I*
Piping Supports and Hangers Reactor Coolant Pump 2-RC-P-lA Oil Cooler Reactor Coolant Pump 2-RC-P-lB Oil Cooler Reactor Coolant Pump 2-RC-P-lC Oil Cooler i
I
- I Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual /Opera ting Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating Pressure Visual/Operating.
Pressure
\\
SYSTEM Component Cooling Water SURRY -
r a.:
INS ERVHm rns {>f:CTION ASME CODI~ *CLASS.] COM110NEN'l'S CODI:
COMPONENT DESCRIPTION/IDENTIFICATION APPLICABLE TO METHOD OF SECTION XI CODE Reactor Coolant Pump 2-RC-P-lA Shroud Cooling Coil 2-VS-E-6A Reactor Coolant Pump 2-RC-P-lB Shroud Cooling Coil 2-VS-E-6B Reac,tor Coolant Pump 2-RC-P-lC Cooling Coil 2-VS-E-6C Excess Letdown Heat Exchanger 2-CH-E-4 (shell side)
Residual Heat Removal Pump Seal Cooler 2-RH-E-2A Residual Heat Removal Pump Seal Cooler
'2-RH-E-2B Residual Heat Removal Heat* Exchanger 2-RH-E-lA (shell side)
Residual Heat Removal Heat *Exclrnnfer 2-RH-E-lB (shell side)
Reactor Containment Air Recirculation Cooler 2-VS-E-2-A Reactor Containment Air Recirculation Cooler 2-VS-E-2-B Reactor Containment Air Recirculation Cooler 2-VS-E-2-C CONSTRU<:T=I.::.ON::.:__ _____
__:E..:..XAM=-=.:.::.IN;_A..:..T_I_O_N ________
RE_L_I_E_F_RE___,Q._U_E-:-ST_E_D VIII VIII VIII Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure
\\
e SYSTEM Component Cooling Water SURRY I'r t'Z.:
INS~RVICF. _ l!?ECTION ASME CODE *CLASS 3 COMPONENTS com:
e COMPONENT DESCRIPTION/IDENTIFICATION APPLICABJ,E TO METHOD OF SECTION XI CODE Non Regenerative Heat Exchanger 2-CH-E-2 (shell side)
Seal Water Heat Exchanger 2-CH-E-l (shell side)
Component Cooling Pump 1-CC-P-lC Component Cooling Pump 1-CC-P-lD Component Cooling Water Heat Exchanger 1-CC-E-lC (shell side)
Component Cooling Water Heat Exchanger 1-CC-E-lD (shell side)
Piping Support and Hangers CONSTRU< :1 =-IO'"""N.;__ ______
E_XAM_I_N_A_T_I_O_N _______
RE_L_I_E_F_R_EQ~U-E_S_T_E_D VIII Visual/Operating VIII Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual
ATTACHMENT B SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE TESTING REQUIREMENTS FOR PUMPS AS SET FORTH IN SUBSECTION IWP TO SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THROUGH THE SUMMER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)
The enclosed tabulations provide a listing of the Class 1, 2 and 3 pumps which are subject to the testing requirements of Subsections IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975.
This tabulation identifies the pumps to be tested, code class, test flow path system resistance, and required test quantities and frequencies.
Relief from test requirements is requested in cases where their test requirements have been determined to be impractical.
Where relief is requested, technical justification is provided along with alternative test methods when applicable.
SURR.IT 2.
Page-INSERVICE TESTING ASME CODE CLASS l; 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RESIS-TEST RELIEF NllHEER nESC:RIPTION r.LASS TANCE TEST QUANTITIES FREQUENCY REQUESTED REMARKS 2-CH-P-lA High Head 2
FIXED 01 Speed (if variable)
NA CONSTANT 2-CH-P-lB Safety Injection VARIABLI Inlet Pressure (Pi)
Monthly YES-NOTE 1 2-CH-P-lC (Charging)
(NOTE 2 Differential Pressure (!iP)
Monthly (Dwg. No. 11548-Flow Rate (Q)
Monthly NOTE 2 FM-88B)
Vibration Amplitude (V)
Monthly Bearing Temperature (Tb)
Yearly Lubricant Level or Pressure Monthly 1-SI-P-lA Low Head 2
FIXED Speed (if variable)
NA CONSTANT 1-SI-P-lB Safety Injection Inlet Pressure (Pi)
Monthly YES-NOTE 3 (Dwg. No. 11448-Differential Pressure (AP)
NA FM-89A)
Flow Rate (Q)
Monthly Vibration Amplitude (V)
Monthly Bearing Temperature (Tb)
NA NOTE 4 Lubricant Level or Pressure NA NOTE 4 2-CS-P-lA Containment Spray 2
FIXED Speed (if variable)
NA CONSTANT 2-CS-P-lB (Dwg. No. 11548-I Inlet Pressure (Pi)
Monthly FM-84A)
Differential Pressure (AP)
NA Flow Rate (Q)
Monthly Vibration Amplitude (V)
Monthly Bearing Temperature (Tb)
Yearly Lubricant Level or Pressure Monthly I
I 2-RS-P-2A Outside Recirc-2 FIXED Speed (if variable)
NA CONSTANT 2-RS-P-2B ulation Spray Inlet Pressure (Pi)
NA Yes-Note 5 (Dwg. No. 11548-Differential Pressure (AP)
Monthly l
i FM-84A)
Flow Rate (Q)
NA I
I Vibrat:ion Amplitude (V)
Monthly i I I
Bearing Temperature (Tb)
NA Note 4 l
i Lubricant Level or Pressure l
I I
I
!.1 j
I 1
' I l ;
i I:
I !
j
- 1 e
PUMP MARK NlTMBER 2-RS-P-lA 2-RS-P-lB 2-FW-P-JA 2-FW-P-3B 2-FW-P-2 2-RH-P-lA 2-RH-P-lB I
1-CC-P-lC 1-CC-P-lD PUMP CODE nF.Sr.RIP'l'ION C.T ASS Inside Recircu-2 la tion Spray (Dwg. No. 11548-FM-84A)
Auxiliary 3
Feed water (Dwg. No. 11548-FM-68A)
Residual Heat 2
Removal (Dwg.
11548-FM-87A)
Component Cooling 3
(Dwg. No. 11448-FM-72D) smm&11r 2.
INSERVIC1~ TESTING
. ASME CODE CLASS l*, 2 AND 3 PUMPS SYSTEM RESIS-TANCE FIXED FIXED FIXED or VARIABLE (Notf 8)
VARIABLE I
I I rF ST QUANTITIES I
Speed
- f variable)
Inlet : essure (Pi)
Differ. tial Pressure (AP)
Flow~ lt Le, e (Q)
Vibrat; Beari~
Lubric I
Speed Inlet Differ Flow E Vibrat Bearir Lubric Speed Inlet Differ Flow F Vibrat Bearin:
Lubrid I
i I Speed*
Inlet Differ Flow R Vibrat Beariq Lubric n Amplitude (V)
Temperature (Tb)
- .t Level or Pressure 1r
(:I
>1
~r' lt Le f variable) essure (Pi).
tial Pressure (AP) e (Q) n Amplitude (V)
Temperature (Tb) 11.t Level or Pressure lt Le 11 f variable) essure (Pi)
,tial Pressure (AP) e (Q)
,n Amplitude (V)
Temperature (Tb) t Level or Pressure
(:.
£>1
.f variable)
- essure (Pi)
~I
- l I i,
g
- 11
,tial Pressure (AP)
- e (Q) in Amplitude * (V)
Temperature (Tb) it Level or Pressure Page.
TEST RELIEF FREQUENCY REQUESTED REMARKS NA CONSTANT NA Yes-Note 6 NA NA Yes-Note 6 NA Yes-Note 6 NA Note 4 NA Note 4 NA CONSTANT Monthly Monthly NA Monthly Yearly Monthly NA CONSTANT Refueling Yes-Note 7 Refueling Yes-Note 7 Refueling Yes-Note 7 Note 8 Refueling Yes-Note 7 NA Note 4 NA Note 4 NA CONSTANT
!Monthly Yes-Note 9 Monthly Yes-Note 9 Monthly Yes-Note 9 Monthly Yearly Monthly
SURR.IT 2.
Page-INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM RELIEF I
RESIS-TEST MARK PUMP CODE REQUESTED REMARKS I
TEST QUANTITIES FREQUENCY l
NlTI-fBER nESCRIPTION QLASS TANCE
- I.
i CONSTANT NA l-CH-P-2C Boric Acid 3
FIXED Speed (if variable)
!Monthly Yes-Note 10 l-CH-P-2D Transfer Inlet Pressure (Pi)
(Monthly I
(Dwg. No. 11448-Differential Pressure (AP)
NA j
FM-88A Flow Rate (Q)
NA Yes-Note 10 Vibration Amplitude (V)
NA Yes-Note 10 Bearing Temperature (Tb)
Note 10 l
Lubricant Level or Pressure NA I
NA CONSTANT 2-CC-P-2A Charging Pump 3
FIXED Speed (if variable)
Yes-Note 11 NA 2-CC-P-2B Cooling Water Inlet Pressure (Pi)
NA (Dwg. No. 11588-Differential Pressure (AP)
Monthly FM-71B)
Flow Rate (Q)
!Monthly Vibration Amplitude (V)
NA Note 12 Bearing Temperature (Tb)
Lubricant Level or Pressure i
I NA CONSTANT 3
VARIABLE 2-SW-P-lOA Charging Pump Speed (if variable)
NA Yes-Note 13 2-SW-P-lOB Service Water Inlet ?ressure (Pi)
NA Yes-Note 13 I
(Dwg. No. 11548 Differ~ntial Pressure (~P)
Monthly F,
' Flow Rate (Q)
Monthly Vibration Amplitude (V)
NA Note 12 Bearin;~ Temperature (Tb)
NA Note 12 I
Lubricant Level or Pressure I
I I
NA CONSTANT
,1 l
3 FIXED
' 2-SW-P-5A Recirculation Speed (if variable)
Yes-Note 15
\\
NA
~ 2-SW-P-5B Spray Hx Radia-I Inlet Pressure (Pi)
NA Yes-Note 15 I 2-SW-P-5C ti.on Monitoring Differential Pressure (AP) 1 NA
\\ 2-SW-P-5D Sample j
Flow Rate (Q)
NA Yes-Note 15 I Dwg. No. (11448-F~-
I Vibration Amplitude (V)
Yes-Note 15 NA i
71A)
{
! Bearin3 Temperature (Tb)
Yes~Note 15 i
NA j
I
~
I
\\
l Lubricant Level or Pressure I {
- f.
I I
\\
I I I
' I.
SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 and*3 PUMPS NOTE
- 1.
Suction pressure instrumentation is not installed nor required.
There pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure is nominally 15 to 20 psig.
Therefore, the 6P developed by the pump is more than 100 times the suction pressure and a gage for suction pressure would not provide significant data.
We propose to observe VCT pressure using control room indication to assure repeated initial conditions for testing the pumps.
This indication is approximately 4% accurate.
- 2.
When the nonoperating pump is tested on recirculation flow, the flow path is a fixed resistance system and it is required to measure 6P or Q, not both (Table IWP-3100-1).
When the operating pump is tested, the flow path is a variable resistance system and it is required to measure both 6P and Q.
- 3.
No inlet pressure instrumentation is installed for these pumps.
These pumps take suction from the RWST for performance testing.
This tank has a minimum level required by the Technical Specifica-tions which is observed from the Control Room.
Tank level will be used to establish initial conditions for testing.
- 4.
Proper lubricant level or pressure cannot be observed since bearings are in main flow path.
Reference is made to IWP-4310 which establishes exception to Tb for bearings within the main flow path.
- 5.
These pumps are flow tested at shut of head as required by T.S.
4.5.A.3 by filling pump casings with water and running on recircula-tion flow path.
Suction pressure is the same fo{ each test (head of water with casing filled) and thus will not be measured.
- 6.
These pumps shall be dry tested quarterly as required by proposed T.S. 4.5.A.2 (Change No. 66).
Since these pumps take suction from the containment sump and discharge thru the spray headers, it is not practical to perform periodic flow testing.
- 7.
It is considered impracticle to make a containment entry on a monthly basis in order to test these pumps.
These pumps are not Engineered Safety Feature pumps.
Operability during use can be determined by monitoring reactor coolant system temperature.
Testing as required by subsection IWP will be performed during each refueling outage.
- 8.
When the pump is tested on recirculation flow, the path is a fixed resistance system and it is required to measure 6P or Q, not both (Table IWP-3100-1).
When the pump is tested while pumping through the Reactor Coolant System, the flow path is a variable resistance system and it is required to measure both 6P and Q.
ATTACHMENT C SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE TESTING REQUIREMENTS FOR VALVES AS SET FORTH IN SUBSECTION IWV TO SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THRU THE SUMMER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)
The enclosed tabulation provides a listing of the Class 1, 2 and 3 valves which are subject to the testing requirements of Subsection DilV of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975.
This tabulation identifies the valve to be tested, drawing location, function, code class, category, size, valve type, actuator type, normal position and test requirements.
Relief from test requirements is requested in cases where these test requirements have been determined to be impractical.
Where relief is requested, technical justification is provided along with alternative test methods when applicable.
Leak testing of containment isolation valves shall be performed in accordance with Appendix J of 10CFR50 in lieu of ASME Section XI subsub-article IWV-3420.
There are no testable Category D valves in Surry Unit 2 Systems.
Any inspection requirements identified as impractical during the course of the inspection period will be noted and included in the inspection program at the time of the next revision.
When one valve in a redundant safety related system is found inoperable during testing, nonredundant valves in the remaining train will not be cycled as procedures require but will be cycled after the first inoperable valve in the system is returned to service.
This valve testing program addresses those valves for which demonstration of operability is necessary to assure safe shutdown of the unit or mitigation of the consequences of an accident.
The program has been reviewed to assure that testing the valves at the intervals specified will not place the plant in an unsafe condition.
Where practical, valves will be cycled at 3 month test intervals.
When a commitment is made to test valves during hot or cold shutdown it is not intent to shutdown the unit solely for the purpose of valve testing nor to perform the testing more often than once per 92 days due to more frequent shutdowns.
The following clarification shall apply to those valves which are scheduled to be exercised during cold shutdown:
"Valve testing shall commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown and continue until complete or unit is ready to return to power.
Completion of all valve testing is not a prerequisite to return to power."
e Reactor coolant Class 1 and Class 2 pressure boundary valves have not been included in the test program.
The reactor coolant pressure boundary is subject to pressure tests and adequately monitored for leakage following each refueling in accordance with the requirements of Article IWB-5000.
Gross leakage test requirements for check valves providing Class 1 to Class pressure boundaries are defined in 4.5.B.2(c) and (d) of the Surry
, technical specification; Article IWV-3520(b) requires that check valves be exercised to the position required to fulfill their function.
Check valves at Surry are not equipped with position indicating devices and verification of operation to the required position will be achieved by observing that normal required flows are established in the systems.
The stroke times of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation.
Exception is taken to complying with stroke time variations defined by Article IWV-3410(c) (3).
TEST REQUIREMENTS SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES LEGEND SP -
SETPOINTS of safety and relief valves shall be tested per Section XI subsubarticle IWV-3510 or as modified by specific relief request.
VP -
VALVE POSITION shall be verified per Section XI subarticle IWV-3700 or as modified by specific relief request.
CV -
CHECK VALVES shall be exercised at least once every (3) months per Section XI subsubarticle IWV-3520 or as modified by specific relief request.
LT -
LEAK TESTS shall be performed per Section XI subsubarticle D?V-3420 or as modified by specific relief request.
EV -
EXERCISE VALVE for operability at least once every (3) months per Section XI subsubarticle D?V-3410 or as modified by specific relief request.
ST -
STROKE TIMES shall be measured per Section XI subsubarticle IWV-3410 or as modified by specific relief request.
VALVE POSITIONS 0-0pen C-Closed OC-Open or Closed T-Throttled VALVE TYPES CK-Check RE-Relief SF-Safety BA-Ball GL-Globe GA-Gate BU-Butterfly SCK-Stop Check PL-Plug ACTUATOR TYPES SA-Self Actuating MO-Motor PN-Pneuma tic HW-Handwheel
i e
I l 1
.-i i
I SYSTEM NAME I
VALVE I
NUMBER I
i I SV-MS201A,B,C I
SV-MS202A,B,C t
SV-MS203A, B,C SV-MS204A,B,C 1
SV-MS205A,B,C TV-MS201A,B,C PCV-MS202 IMOV-MS202 2-MS-176, 178, 182 NRV-MS20 IA, B, C
\\
TV-MS209 ITV-MS210 d
I
\\
t SURRY IDi I' ~ 2.
INSERVICE T~STING ASME CODE CLASS 1 1 AND 3 VALVES MAIN STEAM DRAW. NO
- ___
___;l:.;:1~5...:.;48;;...-....;;,F.;.:;M-_6;;...4=A;;__---
DRAW.
LOCN.
-3,B-4,B-6
,h-3,C-4,C-6
-3,B-4,B-6
~-3.B-4.B-6 1 -3,C-4,C-6 1-),D-5,D-7 l-8 ic-8
-8,F-8,F-8
)o-3,D-5,D-6
-7
- -7 FUNCTION Main Stearn Safety Valves
- Main Stearn Safety Valves Main Steam Line Trip Valves Main Stearn.to Turbine Driven Auxiliary Feedwater Pump Main Steam to Turbine Driven Auxiliary Feedwater lump Main Steam to Turbine Driven Auxiliary Feedwater Pump Check Valves Main Stearn Non-heturn Valves
. Main Stearn Drain to Condenser Main Stearn Drain to Blowdown CODE CATE-CLASS GORY 2
C 2
C 2
B 3
B 3
B 3
C 2
C B
B SIZE VALVE ACTUA-NORMAL (IN*)
TYPE TOR POSI-
'T'YPF
'l'ION.
4 SF SA C
6 SF SA C
30 CK PN 0
3 GL PN C
3 GA MO
- c 3
CK SA C
30 SCK MO 0
3 GA PN 0
2 GA PN 0
PAGE_l_
TEST RELIEF REQ *.
REQUES1 SP NO SP NO EV YES ST (1)
EV NO ST EV NO ST CV NO CV YES (1)
\\
e SURRY mrr 2:
INSERVICE T~STING ASME CODE CLASS 1 1 ? AND 3 VALVES AUX. STEAM & AIR REMOVAL SYSTEM NAME -------------------
VALVE NUMBER TV-SV202 2-VP-12
- i,-l DRAW.
LOCN.
FUNCTION Air Removal Divert to Reactor Containment Air Removal Divert to Reactor Continment CODE CLASS DRAW.NO, 11548-FM-66A CATE-I SIZE VALVE ACTUA-NORMAL GORY (IN.)
TYPE TOR POSI-T'YPF.
T'ION A
6 GA PN C
AC 6
CK SA C
1 PAGE 2 TEST RELIEF REQ.
REQUES1 LT NO EV ST LT Yes CV (26)
[ i I I
'-l
,1 I
I I
l l
I i I
I i
' I
\\
SURRY ill! r 2:
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME
- FEEDWATER VALVE DRAW.
NUMBER LOCN.
FUNCTION 1-----------+-------1--------------~
2-FW-27, 58, 89 2-FW-10, 12, 41,43, 72, 74 MOV-FW251A, B,C, D,E,F 2-FW-131, i33, 136,138 2-FW-142,157, 172
\\
C-:-2, B-4, B--'S
'::-2,C-2
~-4,C-4, C-5, C-5
~-6, B-6,
~-6, B-6,
~-6, C-6
'-6,C-6, i,-6,C-6 r;}--7,E-7 1,_7 Auxiliary Feedwater Header Check Valves at Main Feedwater Header Main Feedwater Check Valves at Containment Penetrations Auxiliary Feedwater to Steam Generators Auxiliary Feedwater Header Check Valves at Containment Penetration Auxiliary Feedwa.ter Pump Discharge Check Valves CODE CLASS 2
2 3
3 3
DRAW. NO
- ____
..;;;1=1 __
54~8 __ -..;;;F __
M'"""----6=8A ______ _
CATE-SIZE VALVE ACTUA-NORMAL GORY (IN.)
TYPE TOR POSI-1'YPF.
1'ION C
3 CK SA C
C 14 CK SA 0
B 3
GL MO 0
C 6
CK SA C
C 6
CK SA C
P AGE_3_* _
TEST RELI.EF REQ.
REQUES'J CV YES (2)
CV YES (3)
EV NO ST CV YES.
(2)
CV YES (2)
I*
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME. __
_...;C1..1.BwQ""'SJ.J.S=.i..C~au..JN.uN.a.:.EC1..1.'.1...JfS.l-..lE;,.l,QWB.__a.A.uIT....
XT~J~* Tu;AuBuY-+,f.i.:.E.......
ED DRAW *. NO, ____
__._)..... 1 5.u4u8=-"E""'M~6,..,8B..._ __ _
VALVE DRAII.
I CODE
._M_O_V---F-:-~-'6-0-:-~-B---i---J---5-~ J_o_-:-* --1:......-C_r_o_s_s---C-on-n-~-~-:-~-T-:*-~N-r_U_n_1_* t-N-o-.~21 CLA:S 2-FW-272, 273 I-7,I-7 2-FW-305, 306 H-7,H-7 Aux. Feed from Unit No. 1 I. I Cross-Connect for Unit No. 2 Aux. Feed from Unit No. 1 Check Valves at Cont. Penet.
Cross-Connect for Unit No. 2 Aux. Feed from Unit No. 1 Check Valves I
l ! I I
~
f 3
3
' ! I I 1 I CATE-GORY I
1 l
j SIZE (IN.)
6 6
6 VALVE ACTUA-NORMAL TEST TYPE TOR POSI-REQ.
GL CK CK I
TYPF.
TION MO SA SA C
ST C
C EV CV CV PAGE..:.A_
RELIEF REQUES1 NO YES (2)
YES (2)
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME.~-~-~S~E_R~V~IC~F.-~_W~A~T~E~R--------~--~
VALVE NUMBER DRAW *.
LOCN.
FUNCTION CODE CLASS DRAW. NO
- ______.......... 11.... 5~4,..,..8.._-,;:;;FM..._-...... 7..._.l..._A,__ __ _
CATE-GORY SIZE (IN.)
VALVE TYPE ACTUA-NORMAL TEST TOR POSI-REQ.
PAGE~
RELIEF REQUEST 1--------------1-------:---------------;*-* -------*--------1:..J.Y..:.PeJ.L~... *.,._....
1*~:to.:.iN.:....-i.----~---1 I
3
- I:
B !
96 BU 1'
MO MOV-CW206A,B, C,D MOV-SW202A,B MOV-SW203A,B, C,D MOV-SW204A,B, C,D MOV-SW025A,B, C,D MOV-SW206A,B
- MOV-SW201A,B E-4, E-4, F-4,F-4 E-6, F-6 B-6,B-6 D-6,E-6 A-2, B-2, C-2, C-2,A-2,A-2, B-2,C-2 D-4,D-4 B-4C-4 Condenser Inlet Isolation Valves Service Water to Service Water Pumps Service Water to Recircula-tion Spray Heat Exchangers Recirculation Spray Heat Exchangers Isolation Valves Recirculation Spray Heat Exchangers Cross Connect Valves Bearing Cooling Water Heat Exchanger Isolation Valves I
I I
3 B I 42 BU ij 3
B I 30 BU I
3 B I 24 BU I
3 B
i
. 36 i
BU 3
B 36 BU I
~ I I
I.
i i
I I
I I I
l i
I I
i I I j
I I
0 MO 0
MO C
MO MO 0
MO 0
EV ST EV ST EV ST EV ST EV ST EV ST NO NO YES (4)
NO NO NO
! I i
j
-1
\\
I I
1 I i
1 I I
I l
I I
I I
SYSTEM NAME CIRCULATING &
VALVE DRAW.
NUMBER LOCN.
2-CC-764,752 D-6, G-6 2-SW-113, 108 D-.8,G-8 SURRY lJli I'C 2:
INSERVICEIT~STING ASME CODE CLASS 1, l. AND 3 VALVES DRAW. NO.
11548-FM-71B
=--=:......:.-=--~_.__.-=-----
SERVICE WATER PAGE~
CODE CATE-SIZE VALVE ACTUA-NORMAL TE$T RELIEF FUNCTION CLASS GORY (IN~)
TYPE TOR POSI-REQ.
REQUES1 1'YPR 1'ION i
Charging Pump Cooling Waterl Pump Discharge Check Valve i 3
C 2
CK SA oc CV NO Charging Pump Service Water:
3 C
2 CK SA oc CV NO Pump Check VAlve
~
I_
SURRY UN I'} 2:
INSERVICE r* rnTING AsME CODE CLASS l; l AND 3 VALVES SYSTEM NAME~__:_~ __
c_o_M_PO_N_E_N_T___;co_o_L_I_N_G __
WA_T_E_R~--~
,.-------r-----------~-e-VALVE NIDIBER RV-CC219 A, B 2-CC-176, 177 2-CC-1,58,59
\\
DRAW.
- LOCN, i...-2, L-3 B-1,B-l 1\\-2, A-2, A-2 FUNCTION Component Cooling from RHR Heat Exchanger Relief Valve Component Cooling to RHR Heat Exchanger Check Valves Component 0Cooling to Reactor Coolant Pumps CODE CLASS 3
3 3
DRAW,NO *. ~~~~__._I~Js~4u8=-i.:EM-=:.~7~2A..__~~~
CATE-SIZE VALVE ACTUA~
NORMAL GORY (IN~)
TYPE TOR POSI-l'l'YPR
'T'ION C
1~
RE SA C
C 18 CK SA oc C
6 CK SA 0
PAGE -
TEST RELIEF REQ.
REQUES1 SP NO CV YES (5)
CV YES (6)
i I
.J l
i i
SURRY UN I',~ 2:
INSERVICE T~STING ASME CODE CLASS 1, AND 3 VALVES SYSTEM NAME-__~~~c_oM_P_O_N_E_N_T~co_o_L_I_N_G~---~~
VALVE NUMBER 2-CC-242,233, 224 RV-CC212A,B,C
\\ '
DRAW.
LOCN.
C-4, E-4, I-4
~-5,F-5,G-5 FUNCTION Component Cooling to Reactor Containment Air Recirculation Coolers Component Cooling from Reactor Containment Air Recirc. Coolers Relief CODE CLASS 3
3 DRAW.NO.
11548-FM-72B
__._.----------=-'-'-------
CATE-SIZE VALVE ACTUA-NORMAL GORY (IN.)
TYPE TOR POSI-TYPE 1'ION C
6 CK SA 0
C 3/4 RE SA C
PAGE_a_
- TEST RELIEF REQ.
REQUES1 CV YES (7)
SP NO
I 1
I SYSTEM NAME 1
I I VALVE NUMBER l l TV-CC205A,B,C l
I I TV-CC207 1 l l I TV-CC209 A, B i
TV-CC210A,B,C
.J I SURRY UNI'~ 2:
INS~RVICE T~STING ASME CODE CLASS 1, :! AND 3 VALVES COMPONENT COOLING DRAW. NO
- _____ J...... J...,.4.,..4.._.8;;:..EM.......:...,J.... 2.... F---~
DRAW.
LOCN.
l!\\-1, B-1, C-1 E-4, E-3 D-2, D-2, C-2 FUNCTION Component Cooling from Reactor Coolant Pumps' Component Cooling from Reactor Coolant Pumps Component Cooling from RHR Heat Exchangers Component Cooling from Reactor Containment Air Recirculation Coole~s CODE CATE-CLASS GORY 3
B 3
B 3
B 3
B SIZE VALVE ACTUA-NORMAL (IN.)
TYPE TOR POSI-TYPF.
TION 6
BA PN 0
2~
GL PN 0
18 BU PN 0
6 BU PN 0
PAGE-9--
TEST RELIEF REQ.
REQUES'l EV YES ST (6)
EV YES ST (6)
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:.---. __
_;;;.S_AM_P_L_I_N_G ____ ~*~---~
DRAW.NO.
l 1548-FM-82B PAGE 10 VALVE DRAW.
CODE CATE..,.
- SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY (IN.)
TYPE TOR POSI-REQ.
REQUES'l 11'Y'PF TION
~
3/81 TV-SS203 E-1 Residual Heat Removal I
2 A
GA PN oc LT NO System Sample
~
EV i
~
TV-SS200A,B D-1, E-1 Pressurizer Liquid 1
A 3/8 GA PN oc LT NO Space Sample.
EV ST TV-SS201A,B D-,-l, E-1 Pressur.izer Vapor 1
A 3/8 GA PN oc LT NO Space Sample EV ST TV-SS206A,B D-2, E-2 Primary Coolant Hot I
A 3/8 GA PN oc LT NO Leg Samples EV ST TV-SS202A,B D-2, E-2 Primary Coolant Cold 1
A 3/8 GA PN oc LT NO Leg Samples I
EV I
ST I
TV-SS204A,B D-2, E-2 Pressurizer Relief Tank A
3/8 GA PN oc LT NO Gas Space Sample.
I EV ST i
I I
I I
~
l t
I l
I I
i I I
~
j I
~
l*
~
- I I I l
I
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME_~-~--VE_N_T_S_&_D_R_A_I_N_S ___ ~~--
DRAW. NO
- ____
_.;;lc..;;;l.;;;..5....;..48:;_-...;;F~M.... - __ 8.;;..3A=-----
PAGE_ll_
VALVE DRAW.
I CODE "I CATE-) SIZE VALVE. ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION f CLASS I GORY I (IN.)
TYPE TOR POSI-REQ.
REQUES1 ITYPF TION TV-DA200B A-8 R. C. Sump Pump I
I A i 2
GA PN oc LT NO Discharge Isolation I
EV I
ST Al M
TV-DG208B A-3 Pr. Dr. Transfer Pump 2
GA r PN oc L'l' NO Disch. Isolation I
I EV I
ST I
1 TV-VG209B A-1 Gas Vent Hdr. Is*oiation I I
2 GA PN
- l A I 0
LT NO I
EV ST I I I
I I
I I
l I I I
l l i
I i
I I
I*
I I
~
- 1
(
I I i
)
I I
I
e e
SURRY UNIT 2:
INSERVICE TESTING ASME CODE CLASS 1, 2*AND 3 VALVES SYSTEM NAME;___~ __
v_EN_T_S_&_._D_R_A_IN_s ______ ~
.DRAW. NO
- _____
1_15_4_8_-_FM_-_B..,3_B___;. __ _
PAGE 12 VALVE DRAW.
CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER
- LOCN, FUNCTION CLASS GORY (IN.)
TYPE TOR POSI-
- REQ, REQUES'l 11'YPl<'
'l'IOlll r-A ;
TV-DA200A I-8 R. C. Sump Pump 2
GA PN oc LT NO Discharge Isolation EV ST TV-DG208A L-5 Pr. Dr. Transfer Pump A
2 GA PN oc LT NO Disch. Isolation EV ST TV-VG209A L-2 Gas Vent Hdr. Isolation A
2 GA PN 0
LT NO EV ST i
I I
I I
I
?,
I I
µ I
SYSTEM NAME VALVE NUMBER MOVRS255A,B MOVRS256A,B 2RS11,17 MOV-CS200,A,B MOVCS201A,B, C,D 2CS13,24 MOVCS202A,B I
SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CONTAINMENT & RECIRCULATION SPRAY DRAW.NO.
- DRAW, CODE CATE-LOCN.
FUNCTION CLASS GORY F8,F8 Recirculation 2
i Spray Pump A I Suction from Containment Sump
~ l i
I F6,F6 Recirculation Spray 2
A Pump Discharge F6,F6 Recirculation Spray Pump 2
AC Discharge Check Valves I-4, I-4 Containment Spray Pump 2
B Suction from RWST F2,F2, Containment Spray Pump 2
A Fl, Fl Discharge E2,El Containment Spray PUmp 2
AC Discharge Check Valves J3,K3 Chemical Addition Tank 2
B to RWST Isolation Valve I
I I I I I l
i l
I I
l l
i 11548-FM-84A PAGE 13 SIZE VALVE ACTUA-:-
NORMAL TEST RELIEF (IN*)
TYPE TOR POSI-REQ.
REQUES1 iTYPR TION 12 PL MO 0
LT NO EV ST 10 GA MO 0
CV YES LT (8) 12 GA MO 0
EV NO ST 8
GA MO C
LT NO EV ST 8
CK SA C
CV YES LT (8) 6 GA MO C
EV NO ST I
I I
SYSTEM NAME VALVE NUMBER TV-LM200A,B C,D,E,F,G,H TV-LM201A,B HCV-CV200 TV-CV-250A,B,
.C,D I
SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CONT. VACUUM*& LEAKAGE MONITORING DRAW.NO.
11548-FM-85A
~a=._;c.a:,_.=,;a~=-----
DRAW.
CODE CATE-SIZE VALVE ACTUA-NORMAL LOCN.
FUNCTION CLASS GORY (IN.)
TYPE TOR POSI-TYPE
,TTON Open Pressure Sy~ ~I E-3, E-3, E-3, 3/8 GA PN C
~3,E-3,E-3, Isolation P-3, E-3 I
H-4, I-4 Closed Pressure System A I 3/8 GA PN C
Isolation J-5 Cont. Vacuum Air Ejector A
8 GA PN C
Isolation H-7, H-7, Cont. Vacuum Pump A
2 GA PN 0
H-8, H-8 Suction Isolation i
I I i I I
I
)
i I
I l I j
e PAGE_li__
TEST RELIEF REQ.
REQUES1 LT NO EV ST L'f NO EV ST LT YES EV (26)
e SURRY UNIT 2:
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:...._ __ ~~R~E~A~C~T~OR;;a._C~O~O~L~A~NT.::.-------
DRAW. NO
- ____
__.._1 _._1 5...,4..... 8=E.uM=8..... 6.... B..__ __ _
PAGE~
VALVE DRAW.
CODE CATE-t SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY (IN.)
TYPE TOR POSI-REQ.
REQUES1
!TYPE TION SV-2551A,B,C F-4, G-4, H-4 Pressurizer Safety Valves l
1 C
~
6 SF SA C
SP NO TV-2519A A-6 Primary Grade Water to A I.
3 GA PN C
LT NO PRZ Relief Tank EV ST 2-RC-160 B-7 Primary Grade water to AC 3
CK SA C
LT YES PRZ Relief Tank CV (26)
(11448-FM-79D)
I I
I I I I
~
f r;
- i.
I l
I I
~
l I
I
- I I '
I f
SURRY UNIT 2.
INSERVICE.TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME~~~----RE_S_I_D_U_A_L~H_EA_'_f_R_EM
__ o_v_A_L~----~
DRAW.N0, __ ~
____ --=..;11~5~4~8~-=FM=-~8~7=A;:..._ ____ _
PAGE-1.6_
VALVE DRAW.
CODE CATE-I SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY.I (IN.)
TYPE TOR POSI-
- REQ, REQUES1 TYPF'.
'J'l{)hl.
MOV-2700, 2701 H-7,H-7 RHR Suction from Reactor 1
B 14 GA MO C
EV YES Coolant System ST (9)
MOV-2720A,B K-5, K-5 RHR Discharge to Reactor 1,2 B
10 GA MO C
EV YES Coolant System ST (9)
RV--,2721 I-4 RHR System Relief Valve 2
C 3
RE SA C
SP YES (10) 2-RH-5, 11 D-6, B-6 RHR P1,1mp Discharge Chec*k 2
C 10 CK SA C
CV YES Valve (11) 2-RH-47 L-5 RHR System Discharge to 1
C 10 CK SA C
CV YES B RCS Loop (27)
I I
l I
I i
~
I i I I
j I
j I
I l \\ l I
I I I I
I
e SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CHEMICAL AND.VOLUME CONTROL DRAW.NO. -------------
11448-FM-88A
- PAGE 17 VALVE DRAW.
CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY (IN.)
. TYPE TOR POSI-REQ.
REQUES1 I
11'YP'R Tl()l\\T
!- I
~
l-CH-116, 109 G-7 Boric Acid Transfer Pump*
ij 3
C
?:
2 CK I SA 0
CV NO I I Discharge Check Valves i
I I
I l
I I
i I
i l
I I
I I
I I
1 I I
I b
I I
I I
j I
l j
i I
1
,1 I
l I
- [
l
.. I I
I
e SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME-:.._ ____
C_H_EM_I_C_A_L_A_N_D_VO_L_U_M_E_C_O_N_T_RO_L_
DRAW. NO
- ____
__:l~l:.::5...:4..::::8_-=..:FM~-...:8a:.:8a=.:B:__* ---
VALVE DRAW.
CODE CATE-SIZE VALVE ACTUA-NORMAL* TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY (IN.)
TYPE TOR.
POSI-REQ.
REQUES1 i
i'T'YPF.
'T'ION l
~-,
I n
2-CH-258,267, D-6, F-6 Charging Pump Discharge*
2 C
3 CK SA oc CV NO 276 G-6 Check Valve LCV-2115B,D C-9,C-9 Charging Pump Suction from 2
B 8
GA MO C
EV NO Refueling Water *storage Tank ST LCV-2 l 15C, E H-3,H-3 Charging Pump Suction from 2
B 4
GA MO 0
EV YES Volume Control Tank ST (12)
MOV-2275A,B,C D-6,F-6,H-h Charging Pump Recirculation 2
B 2
GA MO 0
EV NO Flow Path Isolation ST MOV-2373 F-5 Charging Pump Recirculation 2
B 3
GA MO 0
EV YES Header Stop Valve ST (13)
MOV-2381 A-3 Reactor Coolant Pump Seal 2
A 3
GA MO 0
LT YES Water Return I
EV (14)
ST l !
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SURRY UNI'~ 2:
INSERVICE T'~STING ASME CODE CLASS 1, ! AND 3 VALVES SYSTEM NAME_~ ____
c_H_EM_r_cA_L __ A_N_D __
V_O_L_UM~E_*_c_o_N~T_R_O_L_
VALVE NUMBER TV-2204 RV-2209 RV-2257 MOV-2289A MOV-2289B
\\
FCV-2160 A-3 F-1 H-1 B-5 B-5 A-3 DRAW.
LOCN.
FUNCTION Reactor Coolant System Letdown Isolation Trip Valve Reactor Coolant System Letdown Relief Valve Volume Control Tank Relief Valve Normal Charging Header Isolation Normal Charging Header Isolation
~
RCS Loop Fill Header Isolation CODE CLASS
- 2 2
2 2
2 1
DRAW. NO
- ___
l...:;.1"'-54...,8.._-.aaF=M---=8 8=B"'--------,,--
CATE-SIZE VALVE ACTUA,-
NORMAL GORY (IN.)
TYPE TOR POSI-
'l'YPF TION A
2 GA PN 0
'l" t C
2 RE SA C
C 3
RE SA C
A 4
GA MO 0
B 4
GA MO 0
A 2
GL PN C
PAGE-19.
TEST RELIEF
- REQ.
REQUES1.
LT YES EV (15)
LT YES.
EV (17)
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME. ____
~C...,.H~EM..J..I...,,C~,Al;.!.Li.,....ilANu.D~Yu.Ou.L....,lJ..,.MuE _,C..,,,,.O.u;Nu.T.J.>R.,..,OI...,_, _
DRAW. NO
- _ __,lul_.5~4u:S ;;..Fu;M.1;;;-cuR.,_.8,.._C _______ _
VALVE NUMBER DRAW.
LOCN.
. ' CODE CATE-I SIZE VALVE ACTUA-NORMAL TEST FUNCTION PAGE --20...'._
RELIEF REQUES1 I
CLASS GORY 1 1
, (IN.)
TYPE TOR POSI-REQ.
TYPF
'l'ION 1-----------i--------'1:--------*------. '"-----:1----1:---+,---~----+-J"-=.t..,-+.---*l=----l RV-2203 H-1 l Letdown Header Relief i
2 !
C
~
2 CK SA C
SP NO I
I HCV-2200A,B,C H-2, H-2, Letdown Orifice Isolation i
2 I A J H-2 I
I 2-CH-309 J-3 Normal Charging Header Isolation I
I I
1 AC i i
I I
I I
I.
I I
I l
1 j
- 1
~
i l
I r f I l
1 I
I I
I I
2 GA PN 3
CK SA I
I oc 0
I LT EV ST LT CV NO YES (16)
- l l
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e SURRY UN I'~' 2:
INSERVICE TJSTING ASME CODE CLASS 1, '! AND 3 VALVES SYSTEM NAME SAFETY INJECTION VALVE NUMBER MOV-2860A,B 2-SI-56,47 MOV-2862A, B 2-SI-46A, B I
2-SI-43, 50 MOV-2863A, B MOV-2885A, B, C, D 2-SI-61, 53 DRAW.
LOCN.
B-8, E-8 C-8, F-8 G-9, G-8 G-9, G-8 D-7, G-7 E-6, G-6 C-7, G-6, G-6, C-7 C-6, G-6 FUNCTION Low Head Safety Injection*
Pump Suction from Contain-ment Sump Low Head Safety Injection Pump SuctiQn from Contain-ment Sump Check Low Head Safety Injection Pump Suction from Refueling Water Storage Tank Low Head Safety Injection Pump Suction from Refueling Water Storage Tank Check t*
Low Head Safety Injection Pump Discharge Check Low Head Safety Injection Pump Dischrge to High Head Safety Injection Pump Suction Low Head Safety Injection Pump Recirculation to Refueling Water Storage Tank Low Head Safety Injection Pump Recirculation to Refueling Water Storage CODE CLASS 2
2 2
2 2
2 2
2 DRAW. NO
- _ ___JI_.I...... 5'""4.uB~EM=.,8uc9cuA"--------
CATE-SIZE VALVE ACTUA-NORMAL GORY (IN.)
TYPE TOR POSI-TYPE TI0N A
12 GA MO C
C 12 CK SA C
B 12 GA MO 0
C 12 CK SA C
C 10 CK SA C
B 8
GA MO C
B*
2 GA MO 0
C 2
CK SA C
PAGE---2.l.
TEST RELIEF fEQ.
REQUES'l LT NO EV ST CV YES (18)
EV NO ST CV NO CV NO EV NO ST EV NO ST CV NO
i l
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SURRY UN I*~ 2; INSERVICE T*~STING ASME CODE CLASS 1,.~ AND 3 VALVES SYSTEM NAME_~~~~-S_A_F_E_T_Y~IN_J_E_C_T_r_o_N~~~~~-
VALVE NUMBER MOV-2864A, B RV-2845A, B, C MOV-2890A, B MOV-2890C
\\
MOV-2869A, B, 2842 MOV-2867C, D MOV-2867A, B DRAW.
LOCN.
D-6, G-5 C-6, D-5 C-5 B-6, B-5 B-6 A-3, I-3, A-1 B-1, B-2 1-2, I-2 FUNCTION Low Head Safety Injection*
Pump Dischrge to Reactor Coolant System Cold Legs Low Head Safety Injection Flow Path R~lief Low Head Safety Injection to Reactor.Coolant System Hot Legs Low Head Safety Injection to Reactor Coolant System Cold Legs t*
High Head Safety Injection to Reactor*Coolant Sys.
Boron Injection Tank Outlet Isolation Boron Injection Tank Inlet Isolation CODE CLASS 2
2 2
2 2
2 2
DRAW. NO. __
ll_S_4_8-_FM--_8_9A _____ _
CATE"'."'
SIZE VALVE ACTUA-NORMAL GORY (IN.)
TYPE TOR POSI-l'T'YPF.
TION B
10 GA MO 0
C 1
RE SA C
AE 10 GA MO C
AE 10 GA MO 0
AE 3
GA MO C
A 3
GA MO C
B 3
GA MO
. C e
PAGE 22*
TEST RELIEF REQ.
REQUES'l EV NO ST SP NO LT NO EV ST VP LT YES EV (19).
l I
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SURRY UN I':: 2:
INSERVICE T:~STING
. ASME CODE CLASS 1, '! AND 3 VALVES SYSTEM NAME~~~~-S_A_F_E_TY~I_N_J_E_C_T_I_O_N~~~~~~
VALVE NUMBER TV-2884A TV-2884B, C RV-2857 TV-SI200
\\
i, H-1 DRAW.
LOCN.
H-1, G-2 D-1 B-4 FUNCTION Boron Injection Tank Recirculation Boron Injection Tank Recirculation Boron Injection Tank Relief Nitrogen Accumulators DRAW. NO.
11548-FM-89A CODE CATE-SIZE VALVE CLASS GORY (IN.)
TYPE 2
B*
1 GA 3
B 1
GA 2
C 3/4 RE A
1 GA e
PAGE ---23__
ACTUA-NORMAL TEST RELIEF TOR POSI-REQ.
REQUES1 TY~E TION PN 0
EV NO ST PN 0
SP NO PN 0
LT NO EV ST i
e SURRY UN1T 2:
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME _____ __:;S~A~F~E~T~Y--=IN~J~E~~C~T~I~O=N----~~
DRAW. NO,_--'1~1'""5:..:!4~8=FM;..!:-....:.8"--'9:...!.B!__ _____ _
PAGE2..4__
VALVE
- DRAW, I
CODE CATE-I SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION CLASS GORY (IN.)
TYPE TOR POSI-REQ.
REQUES1 I
1
!TYPF.
TION I
I Ii RV-2858A, B, C C-4, G-5, C-7 Accumulator Tank Relief 2
C I 1
RE SA C
SP NO
~ I 2-SI-107, 109 C-5, A-5, Accumulator Discharge Check 1
C 12 CK SA C
CV YES 128, 130, G-7, A-7, (22) 145, 147 C-8, A-9 MOV-2865A, B, C C-5, G-6, C-8 Accumulator Discharge I
2 BE 12 GA MO 0
I I
2-SI-88, 91, 94, A-2, A-2, Safety Injection to 1
C 6
CK SA C
CV YES 238, 239, 240 A-3, B-2 RCS Hot Legs I
(23)
B-2, A-3 2-SI-235, 236, B-1, B-1 High Head Safety Injection 1
C I
2 CK SA C
CV YES 237 B-2 to RCS Cold Legs (23) 2-SI-241, 242, B-1, B-1, Low. Head Safety Injection 1
C !
6 CK SA C
CV YES 243 B-2 to RCS Cold Legs I
(24)
I I
I I
2-SI-224, 225, J-1, J-1, High Head Safety Injection i 1,2 C
I 3
CK SA C
CV YES i
226, 227 J-2, J-3 Check Valves at Containment I
f i
(23)
I Penetrations I
r I I
I 1
2-SI-228, 229 J-3, J-3 Low Head Safety Injection 2
C '
6 CK SA C
CV YES i
I Check Valves at Containment s
I 1
I (24) 1 Penetrations I
,j I
I
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SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:__~~~-l;!S~A~FE~T~Y::...-,I~N~J~E~C~T~IO~N~--~~~~
DRAW. NO '----=-1~1~54..:..;8~-..::.F.;:;;M'--;:;.,89::....:B=--------
PAGE..12_
VALVE DRAW.
CODE cATE-1 SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER
- LOCN, FUNCTION CLASS GORY
- (IN.)
TYPE TOR POSI-REQ,*
REQUES1 ITYPF.
TTON I
I
- f
~,.
I r,
2-SI-337, 341 E-3, E-2, Cold & Hot Leg Safety 1
E
~
2 GL HW T
VP NO I
l 339,336 E-2, E-2 Injection Line Throttle Valve I
i 338,340 E-1, E-1 2-SI-79, 82, 85 A-1, A-1, Safety Injection to RCS 2
C I 6 CK SA C
CV YES A-2 Cold Legs (23)
TV-SI201A, B J-5, J-5 Accumulator Nitrogen A
1 GA PN 0
LT NO Relief Line Isolation I
EV ST 2-SI-234 J-4 Nitrogen Accumulators AC 1
CK SA C
CV YES LT (26) t I
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- 1 i
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SYSTEM NAME VALVE NUMBER TV-SI202A, B 2-SI-25 2-SI-400
\\
e SURRY UN!': 2:
INSERVICE TilSTING
- ..
- ASME CODE CLASS 1,.! AND 3 VALVES R. W. S. T. CROSS TIE DRAW. NO
- ____ l=l_._4....
48"""---FM
....... ---=l.._0.._6C...__~---
DRAW.
LOCN.
D-3, D-3 C-3 B-3 FUNCTION Unit No. 1 RWST to Unit No. 2 RWST Cross Tie Charging Pump Suction from RWST Check Valve Charging. Pump Suction from RWST Check Valve CODE CATE-CLASS GORY 2
B*
2 C
2 C
SIZE VALVE ACTUA-NORMAL (IN.)
TYPE TOR POSI-TYPF.
TION 8
GA PN C
8 CK SA C
10 CK SA C
e PAGE--U-TEST RELIEF REQ.
REQUES'I EV NO ST CV YES (12)
CV YES (12)
e e
SURRY UNIT 2.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME STEAM GENERATOR BLOWDOWN
_____......;;....;..._-~-'----....;..;;;~.......;.=---
DRAW. NO.
11448-FM-124.A
---=-~:...;;;.....;;..;:..:.....:..=~-----'--
PAGE.u__
VALVE DRAW.
I CODE CATE-l SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.
FUNCTION I CLASS GORY. (IN:)
TYPE TOR POSI-REQ.
REQUES1 "i
~
iTYPF TION
- I *-*--
I j
~
- f.
TV-BD200A,B,C C-2,C-2,C-4, Steam Genera tor Blowdown I 2
B
~
3 GA PN 0
EV YES D,E,F C-4, C-5, C-5 Trip Valves.
~
ST (25) 1 I J
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e SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES RELIEF REQUESTS (1)
Closure of these valves during power operation will result in a turbine and reactor trip.
As an alternative, they will be cycled during reactor shutdown.
(2)
Opening these valves during power operation would introduce cold and out of chemistry specifications auxiliary feedwater to the steam generators resulting in thermal stress and possible degradation.
As an alternative, they will be tested during cold shutdown.
(3)
Closure of these valves during power operation would require securing feedwater (resulting in a reactor trip) and initiation of auxiliary feedwater flow to back seat the disc.
These valves will be tested during cold shutdown.
(4)
A commitment has been made prohibiting the introduction of service water into the Recirculation Spray Heat Exchangers.
As an alterna-tive, these valves will be tested during each refueling outage.
(5)
These check valves are located in the containment and may be normally open or closed depending on system lineup.
A containment entry and manipulation of other system valves is necessary to test these valves.
This is considered impractical during power operation and therefore they will be tested during cold shutdown.
(6)
Component cooling water flow to the reactor coolant pumps is required at all times the pumps are in operation.
Failure of one of these valves in a closed position during cycling would result in a loss of the cooling flow to the pump.
These valves will be tested during cold shutdown when the reactor coolant pumps are secured.
(7)
These valves remain open during normal plant operations.
It is not practical to test for closure unless the containment air coolers are taken out of service.
As an alternative, these valves will be tested during each refueling outage.
(8)
It is not possible to verify that this normally closed check valve opens without initiation of flow through the containment spray header or by visual observation inside the containment.
As an alternative the valve shall be exercised during each refueling outage.
(9)
Cycling of these RHR system valves during power operations would subject the RHR system to full RCS pressure.
These valves will be exercised when the RHR system is placed into operation during cooldown of the reactor coolant system.
e e
(10) This relief valve cannot be tested unless the entire RHR system is removed from service and drained.
The RHR system must be available during operation and refueling outages for core cooling capability.
The valve will be tested whenever the RHR system is removed from service and drained for maintenance.
(11) This valve can only be cycled when the RHR pumps are started.
As an alternative to testing once per (3) months, they will be tested when the RHR pumps are tested in the pump testing program.
(12) Exercising this valve during power operation would require the charging pump suctions to be aligned with the refueling water storage tank.
This would cause a sudden increase in RCS boron inventory.
It will be exercised during cold shutdown when the RCS is borated to shutdown conditions.
(13) This valve cannot be exercised without possible damage to the charging pumps.
As an alternative, it will be exercised when the charging pumps are secured during each refueling outage.
(14) To protect the reactor coolant pumps seals, flow is required at all times during power operation and cold shutdown.
This valve will be exercised during each refueling shutdown.
(15) This valve cannot be exercised when the charging and letdown systems are in operation due to increased risk of overpressurization of the letdown system.
It will be exercised during cold shutdown.
(16) Failure of this valve in a closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactory coolant inventory.
This valve will be exercised during cold shutdown.
(17) This flow control valve is modulated open and closed by a ten turn pontentiometer located on the control board.
Since the valve stroke time (ST) is dependent on operator response time in manipulat-ing the controller and the time constant of the control system, it will not provide useful information and therefore will not be measured.
(18) This normally closed check valve cannot be exercised without isolating suction to the LHSI pump and draining a portion of the system.
This valve will be part-stroke exercised during each refueling outage using the leakage monitoring test connections.
(19) This valve is required to be maintained in the indicated position with power to the operator removed during power operation.
It will be cycled during cold shutdown.
(20) This valve is directly attached to the charging pump discharge header.
If this valve were exercised during power operation, hot or cold shutdown, uncontrolled flow to the RCS might cause overpressuri-zation.
Additionally MOV-2869A and Bare required to be maintained closed with power to the operator removed during power operation.
As an alternative, this valve will be exercised during each refuel-ing outage.
(21) These valves were designed to be closed with no differential pressure accross the seats.
Cycling during power operation causes the seats to leak when the valve is closed resulting in subsequent dilution of the boron injection tank.
As an alternative, these valves will be tested during cold shutdown.
(22) To exercise this normally closed check valve would require the simulation of a loss of coolant accident, i.e. loss RCS pressure.
This valve will be part-stroke exercised by initiating accumulator injection to the RCS while cooling down for a refueling outage.
(23) The only way to verify that these normally closed check valves open is by initiating flow, using the charging pumps, into the reactor coolant system hot and cold legs.
If charging flow was directed to the reactor coolant system in this manner it could cause over-pressurization during cold shutdown or result in a loss in charging flow control during operation.
As an alternate, these check valves will be exercised open during each refueling outage.
(24) The only way to verify that these normally closed check valves can open is by initiating flow, using the low head safety injection pumps, into the reactor coolant system hot and cold legs.
During operation or cold shutdown reactor coolant system pressure will be higher than the low head pump discharge pressure precluding flow into the vessel.
As an alternate, these valves will be exercised open during each refueling outage.
(25) Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam.
When the valves are reopened a flow surge occurs which automatically isolates the inner valves due to high flow.
Then a containment entry is necessary to reset these valves and upon reopening the process may occur again.
As an alternative these valves will be exercised during cold shutdown.
(26) These valves are normally closed during reactor operation and are required to remain closed during an accident.
As an alternative these valves will be leak tested during each refueling outage.
(27) This check valve cannot be cycled unless RHR system is in service.
As an alternate this valve will be cycled at CSD and RHR is in service.
ATTACHMENT D SURRY UNIT 2 Marked Up Flow Diagrams Showing ASME Code Class 1,2 and 3 System Boundaries Relative to Inservice Inspection and Testing The enclosed drawings are marked up to show the ASME Code Class 1, 2 and 3 system boundaries relative to inservice inspection and testing.
Drawings showing containment isolation valves that are not part of the boundaries are also included.
The system boundaries are also described below:
Drawing No.
11548-FM-64A 11548-FM-66A 11548-FM-68A 11548-FM-71A 11548-FM-7 lB 11548-FM-72A Description Class 2 as marked except for steam generator primary side (class 1) and steam lines from valves 2-MS-87, 379, 120, 378, 158 & 3 77 to the turbine drive for the auxiliary steam generator feed pump (class 3).
Containment isolation valves The auxiliary feedwater system is class 3 as marked.
The main feed-water system is class 2 as marked.
The primary side of the steam generator is class 1.
Class 3 as marked except for shell side of the recirculation spray heat exchanges (class 2).
Class 3 as marked Class 3 as marked except for the tube side of the excess letdown heat exchanger (class 2) and the tube side of the residual heat removal exchangers (class 2).
11548-FM-72B 11448-FM-72E 11448-FM-72F 11548-FM-82A l 1548-FM-83A l 1548-FM-83B 11548-FM-84A 11548-FM-85A 11548-FM-86A 11548-FM-86B 11548-FM-8 7A l 1548-FM-88A 11548-FM-88B Class 3 as marked Class 3 as marked except for the tube side of the non-regenerative heat exchanger (class
- 2) and the tube side of the seal water heat ex-changer (class 2).
Class 3 as marked Class 1 as marked except for lines 3/4"-RH-112, 122 to valve TV-SS-103.
Containment isolation valves Containment isolation valves Class 2 as marked except for tube side of recirculation spray cooler (class 3).
Containment isolation valves Class 1 as marked except for secondary side of steam generators (class 2) and portions of lines 2"-SI-274, 285 & 275 (class 2).
Class 1 as marked Class 2 as marked except for RHR inlet from RCS to valve MOV-2701 (class 1), RHR discharge to RCS from valves MOV-2720B and check valve 2-RH-47 (class 1), com-ponent cooling (CC) to RHR pumps (class
- 3) and shell side of the RHR heat exchanger (class 3).
Class 2 as marked.
Class 2 as boric acid piping to 2-CH-206, marked except for transfer system valves FCV-2114B, 2-CH-209, 2-CH-227
11548-FM-88C 11548-FM-89A 11548-FM-89B 11548-FM-123A 2-CH-229 and 2-CH-237 (class 3),
shell side of nonregenerative heat exchanger (class 3) and shell side of seal water heat exchanger (class 3).
Class 2 as marked except loop fill header (class for
- 1) '
RCS loop drain header from to valve HCV-2201 (class letdown line from RCS to
- 1) '
- 1) '
valve LCV-2460B (class charging line from RCS to valve 2-CH-309 (class 1),
auxiliary spray line from RCS (class 1), auxiliary spray line from RCS 1),
RCP seal leakoff to RO 20-RSB-l,2
& 3 1),
RCP seal injection from valves 2-CH-323, 333 to RCP's (class 1) and (class lines (class lines
& 349 shell side of excess let-down heat exchanger (class 3).
RC lines 31"-RC-302, 305, 308 and 27~"-RC-303,
- 306, 309 class I).
Class 2 as marked except for lines 1"-SI-287 to valve TV-2884A (class
- 3) and line l "-CH-230 to valve 2-SI-3 (class 3).
Class 2 as marked except for cold leg SI 1 ines from RC loops to valves 2-SI-235, 241, 236, 242, 237 & 243 (class 1),
hot leg SI lines from RC loops to valves 2-SI-226 227 (class 1),
and accumulator discharge lines from RC loops to valves HCV-2850B, D
F, 2-SI-207, 128 & 145 (class 1).
Class 2 as marked The following list of drawings have not been enclosed as they may be found in our letter; serial no. 332B/111776, dated May 17, 1979.
11448-FM-l 06C 11448-FM-124A
APPENDIX E SURRY UNIT 1 Surry Unit 1, Revision to our letter serial No. 332C/111776 dated August 8, 1979.
Page 16 of Requested Relief from In-Service Testing Requirements of valves as set forth in Sub Section IWV to Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda thru the Summer of 1975 (last 40 month period of the first 10 year interval).
j SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CONT. VACUUM.& LEAKAGE MONITORING DRAW.NO.
VALVE DRAW.
CODE CATE-NUMBER LOCN.
FUNCTION CLASS GORY TV-LMlOOA,B E-3, E-3, E-3, Open Pressure System
- A C,D,E,F,G,H E-3, E-3,E-3, Isolation D-3, E-3 TV-LM101A,B H-4, 1-4 Closed Pressure System A
Isolation HCV-CVlOO J-5 Cont. Vacuum Air Ejector A
Isolation TV-CV-150A,B, H-7, H-7, Cont. Vacuum Pump A
-C,D H-8,H-8 Suction Isolation I
I SIZE (IN.)
3/8 3/8 8
2 11448-FM-85A VALVE TYPE GA GA GA GA 1 I ACTUA.:..
PN PN PN PN I.
NORMAL POSI-ION C
C C
0
~.**
- ~
y PAGE 16 TEST RELIEF REQ.
REQUES LT NO EV ST LT NO EV ST LT YES EV (26)
ST LT NO
.EV ST