ML18139A900
| ML18139A900 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/15/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 945, NUDOCS 8012170454 | |
| Download: ML18139A900 (75) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINLA. 23261 e
December 15, 1980 Mr. Harold R. Denton, Director Serial No. 945 Office of Nuclear Reactor Regulation PO/ATV:mmf Attn: Mr. Steven A. Varga, Chief Docket No.: 50-280 Operating Reactors Branch 1 License No.: DPR-32 Division of Licensing 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. 1 Pursuant to 10 CFR 50. 55a (g), the Virginia Electric and Power Company submitted 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 1 on*May 17, 1979. After reviewing the program for inservice inspection and testing of pumps and valves following the NRC working group meeting held April 15, 16, 17, 1980, we hereby resubmit our program with the detailed specific relief we require from ASME Code requirements pertaining*
to inservice inspection and testing of pumps and valves as
- outlined in attachments A, B, and C.
Very truly yours, f<~~*
Manager-Nuclear Operations and Maintenance t"
C,
DOCKET NO. 50-280 SURRY #1 REQUESTED RELIEH'FROM INS ERV ICE. INSPECTION AND TESTING REQUIREMENTS .
LTR DTD 12/15/80 (8012170454)
NOTICE -
THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN
- CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
DEADLINE RETURN DATE RECORDS FACILITY BRANCH
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 HlB, 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 inspect ion requirements have been determined to be impractical. Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for thip 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, 19 75, are incomplete and "Acceptance Standards for Flaw Indications" as given in Article IWB-3000 of the 1977 Edition of Section XI will be utilized.
Articles IWA-4000, illB-4000, IWC-4000 and Hffi-4000 entitled "Repair Procedures" in the 19 77 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.
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-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 sys tern will be retained at the first valve in the line. The portions of sys terns affected by this 1 imi ta ti on are:
(i) Cold leg injection from accumulators be tween check valves l-
- SI-109, 130 and 147 and l-SI-107, 129 and 147, test lines to valves HCV-1850B, D and F, RHR re turn to valves MOV-l 720A and B.
(
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 11448-FM-87A and 89B).
(ii) Hot leg injection between check valves l-SI-88, 91 and 94 and check valves l-SI-238, 239 and 240. These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11448-FM-89B).
(iii) Cold leg low head injection line between check valves l-SI-79, 82 and 85 and check valves l-SI-241, 242 and 243; and high head and.boron injection to check valves l-SI-235, 236 and 237 (refer to drawing 11448-FM-89B).
(iv) RHR take-off line between normally closed (with pressure interlock) valves MOV-1700 and 1701. 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 11448-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 Glass 2 system is through the Class 1 sys*tem or when the boundary be tween the two sys terns 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 Glass 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-1307 (refer to drawing 11448-FM-88C).
(ii) Hot leg injection between check valves l-SI-88, 91 and 94 and check'valves l-SI-238, 239 and 240. These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11448-FM-89B).
(iii) R. C. Pump seal injection line from check valve l-CH-323, 333 and 349 to manually operated valve l-CH-294, 297 and 300 (refer to drawings 11448-FM-88B and 88G).
(iv) Excess letdown system from valve HCV-1201 to HCV-1137 (refer to drawing 11448-FM-88C).
(v) Letdown line from valve LCV-1460B to orifice outlet valves HCY-1200A, B and C (refer to drawing 11448-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 leakage 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, spent fuel pit cooling, and boric acid transfer and recirculation, which are in continuous operationduring 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 V as required b~
Paragraph. IWA-2232.
As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 19 74 Edition, Winter, 19 75 Addenda of the ASME Boiler and Pressure Vessel Code will be used for ultrasonic examina-tion of piping systems with the following changes:
(1) Non-geometric indications.SO% of DAC or greater shall be recorded.
(2) An indication 100% of DAC or greater shall be investigated by a Level II or Level III examiner to the ext.en t necessary to de-termine the size, shape, identity and location of the reflector and evaluated in accordance with the acceptance requirements of Section XI.
(3) Any non-geometric indication, 20% of DAG or greater, discovered during the ultrasonic (UT) examination shall be evaluated by a Level II or Level III examiner to the extent necessary to determine the shape, identity and location of the reflector.
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 NRG.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 ASXE 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 l, 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 and attenuations in the unclad component.
Limitations may occur for the examination of piping system circumferential but twelds (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 1, Class 1 system which due to limitations, would require surface examinations are:
(i) Loop 1 Cold Leg Injection line; Welds 6 and 7.
(ii) Loop 2 Charging line; weld 11.
(iii) Loop 2 Cold Leg injection line; welds 4 and 5.
(iv) Loop 1 RTD return line; weld 7.
(v) Loop 2 RTD return line; weld 7.
(vi) Loop 3 RTD return line; weld 7.
(vii) Loop 3 Cold leg injection line; welds 3 and 4.
(viii) Pressurizer safety valve lines welds 7 and 8.
(ix) Pressurizer Relief line; welds 4 and 8 Welds in the Surry Unit 1, Class 2 system with limitations at geometric discontinuities are:
(i) Loop 1 Mainsteam By-Pass; welds 1,7,13,20 (ii) Loop 2 Mainsteam Relief line; welds 12,13,16,18,20,22,29,31 (iii) Loop 2 Mainsteam By-Pass; welds 1,7,13,20 (iv) Loop 2 SIS Hot Leg; weld 15 (v) 14" RHR; welds 1, 10, 15, 22, 27 (vi) 8 11 , 10", 12" RHR; welds 2,3,4,ll,15,14,13,38,36,45 (vii) 12", 10", RHR; welds 1, 7, 20, 27, 15 (viii) 12", 10", 611 RHR; weld 10 (ix) 10" SIS; weld 9 (x) 10" 6 11 SIS welds 6 and 14 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 eves piping equal to or less than four-inch nominal diameter and is exempted by rne-1220(d).
(ii) During plant operation, the boric acid solution will be constantly recirculated through the boron injection tank by the transfer pump system. Samples would normally be taken on a regular basis and the component and associated piping would be exempt from examination by IWC-1220(c).
(iii) The boron injection tank discharge piping is all equal to or less than four inch nominal diameter.
(iv) During plant operation, the contents of the SIS accumulators are normally sampled on a regular basis and this component and associated piping would also be exempted by IWC-1220(c).
(v) During plant operation, the low head SIS injection pumps are run on a periodic basis to recirculate flow and from the RWST. Samples taken on a regular basis from the RWST would verify the chemistry of the sys tern fluid and the pump and associated suction piping would be exempt from examination by IWC-1220(c) .
(vi) The high head SIS piping.equal to or less than four inch nominal diameter is exempted by IWC-1220(d).
(vii) The containment spray system and recirculation spray systems do not function during normal reactor operation and are exempt by IWC-1220(b).
(viii) The RWST, CAT and associated piping have design pressures and temperature less than 275 psig and 200°F and are exempt by IWC-1220(a).
The inservice inspection programs outlined in the attached tabulations have been developed as a result of a design review. Should certain ASHE Section XI Code requirements be discovered to be impractical due to unforeseen reasons during the process of performing inspections or tests, relief will be requested from the specific Section XI Code require-ment at that time.
Radiation levels in certain areas or of certain components may be found to prohibit the access for operators or inspectors to perfonn the inspec-tions or tests described in this program. If source strengths cannot be reduced and access is still restricted by considerations of compliance with the requirements of Regulatory Guides 8.8 and 8. 10, relief will be requested from the specific Section XI Code requirements and alternative examination or test requirements be proposed.
Codes refere*nces as being applicable to construction of components in the attached tables are:
IIIA ASME Boiler and Pressure Vessel Code,Section III, Class A Nuclear Vessels IIIC ASME Boiler and Pressure Vessel Code,Section III, Class C Nuclear Vessels VIII ASME Boiler and Pressure Vessel Code,Section VIII, Pressure Vessels B 31. 1 USA Standard USAS B 31.1 Code for Pressure Piping B 16.5 USA Standard USAS B 16.5 Steel Pipe Flanges, Flanged Valves and Fit tings
TABLE
- IWB-2600 TABLE nm-2soo EXAMINATION . SYSTEM OR IN SERVI CODE APPLICABLE TIT 1 SPECTION ASME CODE CLASS ]. COMPONENTS EXAMINATION SECTION Xi CODE RELIEF CATE TORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED ITEM NO.
Bl. 1 B-A Reactor Vessel III-A Upper to intermediate shell course Volumetric No 1-RC-R-l circumferential weld B 1. 1 B-A Intermediate to lower shell course. *volumetric No circumferential weld Bl. 1 B-A Intermediate shell course longitu- Volumetric No dinal welds (2)° Bl. 1 B-A Lower shell course longitudinal Volumetric No welds (2)
Bl. 2 B-A Lower head to shell circumferential .Volumetric No weld Bl. 2 B-B Lower head ring to disc circumferen- Volumetric No tial weld Bl. 3 B-C Vessel to flange weld Volumetric No Bl. 3 B-C Closure head to flange weld Volmetric No Bl. 4 B-D Ou*tlet nozzle to vessel welds (3) Volmetric No Bl. 4 B-D Inlet Nozzle to vessel welds (3) Vol metric No Bl. 5 B-E CRDM, Vent *and In-: Core Ins trumen- Visual No ta i:lon penetrations and CRDM seal welds Bl. 6 B-F Outlet nozzle to safe-ends welds (~) Volmetric & No Surface
TAI3LE SECTION X*l TABLE I\IB-2500 CODE APPLICABLE EXAMINATION CODE RELIEF
- *IWB-2600 EXAMINATION SYSTEM OR TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED ITE~i NO. CATETORY COMPONENT*
Bl. 6 B-F Inlet nozzle to safe-end welds (3) Volumetric & No Surface Bl. 7 B-G-1 Closure Head Studs (In-Place) Not No-Applicable Note 1 Bl. 8 B-G-1 Closure Head Studs & Nuts Volumetric & No Surface Bl.9 B-G-1 V~ssel flange ligaments Volumetric No Bl.10 B-G-1 Closure."head Wash.ers Visual No Bl. 11 B-G-2 Conoseal Bolting Visual No Bl. 12 B-H Int~grally Welded vessel supports Not No-Applicable Note 2 Bl. 13
- B-I-1 Closure Head Cladding Surface & No-Visual or Note 3 Volumetric Bl.14 B-I-1 . Vessel Cladding Visual No Bl.15 B-N-1 Vessel Interi<;>r Surfaces and Visual No Internals
. B1. 16 B-N-2 Interior Attachments and Core Not i No -
Support Structures Applicable Note 4 Bl. 17 B-N-3 Core Support Structures Visual No
TABLE
- ::n-18-2600 TABLE HIB-2500 EXAMINATION SYSTEM OR INS ERV CODE APPLICABLE IT 1 JSPEC!ION ASME CODE CLASS l. COMPONENTS EXAMINATION SECTION X:-1 CODE RELIEF ITE!-1 NO. CATETORY COMPONENT TO CONSTRUCTION ~REA TO BE EXAMINED REQUIREMENT REQUESTED Bl. 18 B-0 Control. Rod Drive Housings Volumetric No Bl. 19 B-P . Exempted Componen.ts Visual No B2. 1 B-B Pressurizer III-A Longitudinal Shell welds ( 6) Volumetric No l-RC-E-2 B2. 1 B-B Circumferentiai shell welds (7) Volume tiic Yes -
Note 17 B2.2 B-D Nozzle to vessel welds (6) Not No -
Applicable Note 5 B2.3 B-E Heater Penetrations Visual No B2.4 B-F Nozzle to safe-end welds (6) Volumetric & No Surf ace B2.5 B-G-1
- Pressure Retaining Bolting Not No -
(in place) Applicable Note 6 B2.6 B-G-1 Pressure Retaining Bolting Not No -
when removed Applicable Note 6 B2.7 B-G-1 Pressure Retaining Bolting Not *No -
Applicable Note 6 B2.8 B-H ~ntegrally Welded Vessel Supports Volumetric No B2.9 B-I-2 Vessel cladding Visual No B2.10 B-P Exempted Components Visual No B2. 11 B-G-2 Manway Bolting Visual No B3.l B-B Steam Generators III-A Channel Head to tubesheet Volumetric No (3) Primary Side Weld (3)
TABLE
- *IWB-2600 TABLE nrn-2soo EXAMINATION .. SYSTEM OR I.NSERV CODE APPLICABLE NIT 1 NSPECTION ASME CODE CLASS 1 COMPONENTS EXAMINATION SECTION XI CODE RELIEF ITE~f NO. CATE TORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED B3.2 B-D 1-RC-E-lA Nozzle to Vessel welds (6) Not No-1-RC-E-lB _Applicable Note 7 1-RC-E-lC B3.3 B-F Nozzle to safe-end welds (6) Volumetric & Yes -
Surface Note 8 B3.4 B-G-1 Pre*ssure Retaining Bolting Not No -
(in place) Applicable Note 6 B3.5 B-G-1 Pressure Retaining Bolting, Not No -
when removed *Applicable Note 6 B3.6 B-G-1 Pressure Retaining Bolting Not No - .
Applicable Note 6 B3. 7 B-H Integrally wel*ded supports Not No -
Applicable Note 6 B3.8 B-I-2 Vessel Clad.ding Visual No B3.9 B-P Exempted Components Visual No B3.10 B-G-2 Manway Bolting Visual. No B4.l B-F Piping Pressure Safe end to pipe welds Not No Boundary Appli(;!able Note 6 I
B4.2 B-G-1 Pressure Retaining. Bolts Not No -
(in place) Applicable Note 6 B4.3 B-G-1 Pressure Retaining Bolts Not No -
when removed
- Applicable Note 6 B4.4 B-G-1 Pressure Retaining Bolting Not No -
- Applicable Note 6 B4.5 B-J Circumferential and Volumetric Yes -
Longitudinal Pipe Welds Notes 9 and
TAB.LE
- *IWB-2600 TABLE nrn-2soo EXAMINATION SYSTEM OR INS ERV CODE APPLICABLE IT 1 NS PE CT ION ASME CODE CLASS 1 COMPONENTS EXAMINATION SECTION XI CODE RELIEF ITEN NO. CATE TORY COMPONENT TO CONSTRUCTION .. AR.EA TO BE EXAMINED REQUIREMENT REQUESTED B4.6 B-J Branch Pipe connection welds Volumetric Yes -
exceeding 6" diameter. Note 11 B4. 7 B-J ~ranch .Pipe Connec ti.ons Weld 6" Surface No diameter and smaller B4.8 B-J Socket Welds Surface No B4.9 B-K-1 Integrally Welded Supports Volumetric Yes -
Note 12 B4.10 B-K-1 Support Components Visual No B4. 11 B-P Exempted Components Visual No B4.12' B-G-2 Pressure Retaining Bolting Visual No BS.I B-G-1 Reactor Coolant III-A Main Flange.Bolting (in place) Volumetric No Pumps (3)
B5. l B-G-1 1-RC-P-lA Seal Housing Bolting (in place) Volumetric Yes -
1-RC-P-lB Note 1-RC-P-°IC 13 B5.2 B-G-1 Main Flange Bolting when removed I
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 Main Flange Bolting Visual No BS.3 B-G-1 Seal Housing Bolting Visual No*
BS.4 B-K-1 Integrally Welded Supports Volumetric Yes Note
TABLE
-IWB-2600 TAilLE I\IB-2500 EXAMINATION SYSTEM OR INS ERV CODE APPLICABLE
'IT 1 SPECTION ASME CODE CLASS 1 COMPONENTS EXAMINATION SECTION Xi*
CODE RELIEF ITE}1 NO. CATE TORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED B5.5 B-K-2 Support Components 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. . Exempted Components Visual No B5.9 B. . . G-2 Presi;;ure Retaining Boiting Not* No 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 B6.3 B-G-1 Pressure Retaining Bolting Visual No B6.4 B-*K-1 Integrally welded supports Not No --
Applicable Note 6 B6.5 B-K-2 Support Components Visual No B6.6 B-M-1 Valve Body Welds Not No Applicable Note 6 B6.7 B-M-2 Valve Bodies Visua!l. No B6.8 B-P . Exempted Components Visual No B6.9 B-G-2 Pressure Retaining Bolting Visual No
\
SURRY UNIT 1 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. Relief is requested from volumetric examination of the reactor vessel head cladding. Ultrasonic examination of the meridional and cir-cumferential head welds from the O. D. will cover sufficient clad-metal interface area to" provide assurance of closure head s true tural integrity.
- 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. However, the inner radiused sections of the integrally cast nozzles will be ultrasonic examined from the outside and the area will be visual examined to the extent practical as this is a high radiation area (20 to 30R).
- 6. There are no items in this category on this component in the Surry Unit 1 Class 1 Systems.
- 7. The steam generator nozzles are integrally cast with the channel head and therefore are no welds in this category. However, the inner radiused sections of the integrally cost nozzles will be ultrasonic examined from the outside and the area will be visual examined to the extent practical as this is a high radiation area (20 to 30R).
- 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 el bow, 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. Welds in the Surry Unit 1, Class 1 system which due to limitations would require surface examinations are:
(i) Loop 1 cold leg injection line; weld 6 and 7.
(ii) Loop 2 charging line; weld 11.
(iii) Loop 2 cold leg injection line; welds 4 and 5.
(iv) Loop 1 RTD return line; weld 7.
- 10.
(v)
(vi)
(vii)
(viii)
(ix)
Loop 2 RTD return line; weld 7.
Loop 3 RTD return line; weld 7.
Loop 3 cold leg injection line; welds 3 and 4.
Pressurizer safety valve lines welds 7 and 8.
Pressurizer relief line; welds 4 and 8.
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 BS. 1. Both the main flange and seal housing bolting will be examined as required by IWB-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.
lS. 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 subs ti-tute for volumetric *
- 16. The reactor coolant pump casings in Surry Unit 1 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 i t is opaque to ultrasonic trans-mission.
Volumetric examination as required by IWB-2600 will be attempted utilizing radiographic techniques. The success of these examina-tions 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 (C-S and C-7) 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.
\VESTINGHOUSE ELECTRIC CORPORATION FIGURE 1 STEAM GENERATOR PRIW\RY NOZZLE SAFE-mo TO PIPE \-/ELD CONFIGURATION STEAM GENERATOR NOZZLE INTEGRALLY CAST WITH HEAD "BUTTERED" . .:._-
SAFE-END REACTOR COOLANT PIPE ,
I
- ~
I WELD DEPOSITED CLADDING
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\-VESTINGHOUSE ELECTRIC CORPOf?ATION FIGURE 2 ID v
v.
0 IC 0 BRAUCH NOZZLE cor~NECTION HELD u.
CENTERLINE NOZZLE NOZZLE FORGING REACTOR COOLANT PIPE
TABLE IWe-2600 TABLE HiD -2520 EXAMINATION SYSTEM OR CODE APPLICABLE IN SE RV ASME CODE CLASS 2 COMPONENTS NIT 1 NSPECTION EXAMINATION SECTION Xl CODE RELIEF
_I_T_EM_N_O....:_._ _ _
CA__T_E_T_O_R_Y_ _ _c_*o.MPONENT:__ __:T_::::O_:'. .CO::::N:::.:S:::.:T:..::R:.::U:..::C:..:T..::I:::..O::.N_ _ _ _.:.:A::.:RE=*A;.:_T=-:0::__.:B:..:E;__E.:..XAM.;__IN....:..E_D_ _ _ _ _ _ _R_E_,Q~U-I_RE_*M_E_N_T_ _ _
RE_Q..:_U_E_S_T_E_D Cl. 1 C-A-2 Stearn Genera- IIIA Upper Head to Shell Weld Volumetric No rators (3)
(Shell Side}
Cl. 1 C-A 1-RC-E-lA Upper Shell to Transition Weld Volumetric No 1-RC-E-lB 1-RC-E-lC c 1. 1 C-A Transition to lower shell weld Volumetric No Cl. 1 C-A Lower Shell to Stub barrel weld Volumetric No Cl. 1 C-A Stub barrel to tubeshee t 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 weld Cl. 3 C-C Integrally Welded Supports Not No -
Applicable Note 1 Cl. 4 C-D Manway Bolting Visual and No Volumetric Cl. 1 C-A Residual Heat IIIC Head to Shel 1 Welds Volumetric No Exchangers (2)
(Tube Side) c 1. 1 C-A 1-RH-E-lA Shell to flange welds Volumetric No 1-RH-E-lB Cl. 2 C-B Nozzle to vessel welds Volumetric Yes -
Note 2 Cl. 3 C-C Integrally Welded Supports Surf ace No Cl. 4 C-D Tube sheet Flange Bolting Visual and No Volumetric Cl. 1 C-A Regenerative III-C Head to shell welds (6) Volumetric Yes -
- Heat Exchanger Note 3
TABLE rwe-2600 TABLE rnc-2s20 EXAMINATION SYSrnM OR INSE" CODE APPLICABLE UNIT 1 INSPECTION ASME CODE CLASS 2 COMPONENTS EXAMINATION SECTION -xr CODE RELIEF ITEM NO. CATE TORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED Cl. 1 C-A l-CH-E-3 Shell to tubesheet welds ( 6) Volumetric Yes -
Note 3 Cl. 2 C-B Nozzle to vessel welds (12) Not No -
Applicable Note 4 Cl. 3 C-C Integrally welded supports Not No -
Applicable Note 4 Cl. 4 C-D Pressure Retaning Bolting Not No -
Applicable Note 4 Cl. 1 C-A Excess Letdown III-C Head to shell weld Volumetric No Heat Exchanger (Tube side) c 1. 1 C-A l-CH-E-4 Shell to flange weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 5 Cl. 3 C-C Integrally welded supports Not No -
Applicable Note 5 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. 1 C-A l-CH-E-2 Shell to flange weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 6 Cl. 3 C-C Integrally welded supports Surface No Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric
.:t TABLE rwe-2600 TABLE HiC-2520 EXAMINATION SYSTEM OR CODE APPLICABLE UNIT 1 INSPECTION ASME CODE CLASS 2 COMPONENTS EXAMINATION SECTION XI CODE RELIEF ITEM NO. CATE TORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED Cl. 1 C-A Seal Water III-C Head to shell welds Volumetric No Heat Exchanger (Tube Side)
Cl. 1 C-A l-CH-E-1 Shell to flange welds Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 7 Cl. 3 C-C Integrally welded supports Surface No Cl. 4 C-D Pressure Retaining Bolting Not No -
Applicable Note 7 Cl. 1 C-A Volume Control III-C Upper Head to shell weld Volumetric No Tank Cl. 1 C-A l-CH-TK-2 Lower head to shell weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 8 Cl. 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 Shell to flange weld Volumetric No Injection Filters (2) c 1. 1 C-A l-CH-FL-4A Head to shell weld Volume tr le No l-CH-FL-4B Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 9 Cl. 3 C-C Integrally Welded Supports Surface No Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric
TABLE rwe-2600 TABLE I'\\-C-2520 EXAMINATION SYSTEM OR CODE APPLICABLE INSE ASME CODE CLASS :lCOMPONENTS INSPECTION EXAMINATION
- SECTION *xr CODE RELIEF ITEM NO. CATETORY COMl'ON-.:.:I:.:.:m~T::___ _. :.T: :. .O_C=:.;O:.:N:.:.:S:.:T:.:R.:.:U-=C-=T.: .I.:. ON::.:________ A_RE_A_:__T_O:__B...;::E_E_XAM_I_N_E_D_ _ _ _ _ _ _REQUIREMENT REQUESTED Cl. 1 C-A Reactor Cool- III-C Cover Weldment to shell weld Vol metric Yes -
ant Filter Note 10 c 1. 1 C-A l-CH-FL-2 Head to shell weld Volumetr.ic Yes -
Note 10 Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 10 Cl. 3 C-C Integrally Welded Supports Surface No Cl. 4 C-D Pressure Retaining Bolting Not No -
Applicable Note 10 Cl. 1 C-A Seal Water III-C Cover Weldment to shell weld Volumetric Yes -
Re turn Filter Note 10 Cl. 1 C-A l-CH-FL-3 Head to shell weld Volumetric Yes -
Note 10 Cl. 2 C-B Nozzle to vessel welds Not No -
Applicable Note 10 Cl. 3 C-C Integrally welded supports Surface No Cl. 4 C-D Pressure Retaining Bolting Not No -
Applicable Note 10 C2. l C-F;C-G Piping Systems C.ircumferential Butt Welds Volumetric Yes -
Note 11 C2. 2 C-F;C-G Longitudinal weld joints in Volumetric No fittings C2.3 C-F;C-G Branch .Pipe to Pipe Welds Volumetric Yes -
Note 12 C2.4 C-D Pressure Retaining Bolting Visual and No Volumetric
UNIT 1 INSPECTION ASME CODE CLASS 2 COMPONENTS TABLE TABLE n;G-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.l C-F Residual Heat Pump Casing Welds Not No -
Removal Pumps (2) Applicable Note 13 C3. 2 C-D 1-RH-P-lA Pressure Retaining Bolting Visual and No 1-RH-P-lB Volumetric C3. 3 C-E-1 Integrally Welded Supports Not No -
Applicable Note 13 C3.4 C-E-2 Support Components Visual No C3.l C-D Charging Pumps (3) Pump Casing Welds Not No -
Applicable Note 13 C3.2 C-D 1-CH-P-lA Pressure Retaining Bolting Visual and No 1-CH-P-IB Volumetric 1-CH-P-lC C3. 3 C-E-1 Integrally Welded Supports Not No -
Applicable Note 13 C3.4 C-E-2 Support Components Visual No C4.l C-F;C-G Valves Valve Body Welds Not No -
Applicable Note 14 C4.2 C-D Pressure Retaining Bolting Visual and No Volumetric C4.3 C-E-1 Integrally Welded Supports Not No -
Applicable Note 14 C4.4 C-E-2 Support Components Visual No
SURRY UNIT 1 INSERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS NOTES
- 1. There are no items in this category on this component in the Surry Unit 1 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. 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 this category, personnel involved could be subjected to a total accumulated dose of up to fifty-six man rem.
It is felt that potential personnel exposure to complete these examinations is excessive particularly when the examination is to establish the continued integrity of a vessel in a system in which all the piping welds are exempt from examination by IWC-1220(d).
Efforts will be made to examine 10% of one weld volumetrically when practical however, examination of this vessel for evidence of leakage during the performance of pressure tests will provide the same assurance of continued integrity as for the piping system with which it is associated.
- 4. Regenerative heat exchanger nozzles are 3" and 2" diameter, there are no integrally welded supports and pressure retaining bolting on this vessel therefore no examination is required under these categories.
- 5. 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.
- 6. Non Regenerative Letdown Heat Exchanger nozzle to vessel welds are 2" diameter and therefore requires no examination under this category.
- 7. 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.
- 8. Volume Control Tank nozzle to vessel welds are 4" and 3" diameter therefore require no examination under this category .
- 9. Seal Water Injection Filters nozzle to vessel welds are 2" diameter, therefore require no examination under this category.
- 10. Reactor Coolant Filter and Seal Water Re turn 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.
- 11. 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 i t 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 res tric-tions 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 effected zone, surface examinations may be performed to supplement the limited volumetric examination. Welds in the Surry Unit l, Class 2 system with limi-tations at geometric discontinuities are:
(i) Loop 1 Mainsteam By-Pass; Welds 1, 7, 13, 20 (ii) Loop 2 Mainsteam Relief line welds 12, 13, 16, 18, 20, 22, 29, 31 (iii) Loop 2 Mainsteam By-Pass; welds 1, 7, 13, 20 (iv) 1 Loop 2 SIS Hotleg; weld 15 (v) 14" RHR; welds 1, 10, 15, 22, 27 (vi) 8", 10", 12" RHR; welds 2, 3, 4, 11, 13, 14, 15, 36, 38, 45 (vii) 12", 10" RHR; welds 1, 7, 15, 20, 27 (viii) 12", 10", 6" RHR weld 10 (ix) 10" SIS; weld 9 (x) 10", 6" SIS welds 6 and 14
- 12. The configuration of typical branch pipe welds is shown in Figure
- 4. Ultrasonic examinations cannot be performed on the surface of the weld. Examinations will be performed to the extent practical from the pipe and nozzle surfaces adjacent to the weld. Surface examination of the weld will be performed to supplement the volumetric examination.
- 13. The residual heat removal pumps and charging pumps do not have any pump casing*welds or integrally welded supports.
- 14. There are no valve body welds or integrally welded supports on the valves in Surry Unit 1.
\VESTINGHOUSE ELECTRIC CORPORATION F!t;URE 3 RESIDUAL HEAT: REMO\/Al HEAT EXCHAf\JGER c::
0 NOZZLE *TO VESSEL CONFIG\JRAT!Oll.
IL
---~~........ /*CHANNEL HEAD FLANGE 111* THICK REINFORCEME~H PAD NOZZLE TO VESSEL HELD
~ NOZZLCJ O" SCH 405
(.TYPICAL OF THO)
-~ .
. .875" THICK SHELL AND HEAD
- ------------------------------------------~--------J
~
i:
Figure 4 0 BRANCH NOZZLE COiitlECTION WELD IL CENTERLINE NOZZLE NOZZLE FORGrnG PIPE I
f
'-----------------~-------_i.:
- COMPONENT S"URRY*u INSERVICE IN CODE APPLICABLE TO ION ASME CODE *CLASS 3 COMPONENTS METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRU.,TION EXAMINATION RELIEF REQUESTED Chemical and Boric Acid Tank 1-CH-TK-lA . VIII Visual/Operating Volume Control Pressure Boric Acid Tank 1-CH-TK-lB VIII" Visual/Operating .
Pressure Boric Acid Transfer Pump 1-CH-P-2A Visual/Operating Pressure Boric Acid Transfer Pump l-CH-P-2B Visual/Operating Pr~ssure Boric Acid Filter 1-CH-FL-1 IIIC Visual/Operating Pr.essure Boric Acid Blender l-CH-BL-1 Visual/Operating Pressure Piping Visual/Operating Pressure Supports and Hangers Visual
- Main Steam to Piping Visual/Operating
'Turbine Driven Pressure Auxiliary Feedwater Pump* Supports & Hangers Visual Auxiliary Auxiliary Feed Pump l-FW-P-2 (Turbine Visual/Operating Feedwater Driven) Pressure Auxiliary Feed Pump l-FW-P-3A (Motor Visual/Operating Driven) Pressure Auxiliar.y Feed Pump l-FW-P-3B (Motor Visual/Operating Driven) Pressure Auxiliary Feed Pump l-FW-P-2 Oil Cooler Visual/Operating Pressure
SURRY ut-A
.INSERVI~~~ION_
ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRUl.TION EXAMINATION RELIEF REQUESTED Auxiliary Auxiliary Feed Pump l-FW-P-3A Oil Cooler Visual/Operating Feedwater Pressure Auxiliary Feed Pump l-FW-P-3B Oil Cooler Visual/Operating Pressure Condensate Storage Tank 1-CN-TK-lA Visual/Operating Pressure Piping Visual/Operating Pressure Supports and Hangers Visual Circulating Recirculation Spray Heat Exchanger Visual/Operating and Service 1-RS-E-lA (tube side) Pressure Water Recirculation Spray Heat Exchanger Visual/Ope rating 1-RS-E-lB (tube side) Pressure Recirculation Spray Heat Exchanger Visual/Operating 1-RS-E-lC (tube side) Pressure Recirculation Spray Heat Exchanger Visual/Operating 1-RS-E-lD (tube side) Pressure Component Cooling Water Heat Exchange.r Visual/Ope rating 1-CC-E-lA (tube side) Pressure Component Cooling Water Heat Exchanger Visual/Operating 1-CC-E-lB (tube side) Pressure Emergency Service Water Pump 1-SW-P-lA Visual/Operating Pressure
COMPONENT SURRY UN
--~--
INSERVICE INS ON ASME CODE *CLASS 3 COMPONENTS CODE APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED Circulating Emergency Service Water Pump 1-SW-P-lB Visual /Ope rating and Service Pressure Water Emergency Service Water Pump 1-SW-P- lC Visual /Ope ratlng
.Charging Pump 1-CH-E-SA Lubricating Visual/Operating Oil Cooler Pressure Charging Pump 1-CH-E-SB Lubricating Visual/Operating Oil Cooler Pressure Charging Pump 1-CH-E-SC Lubricating Visual/Operating Oil Cooler Pressure Charging Pump 1-CH-E-7A Seal Cooler Visual/Operating Pressure Charging Pump 1-CH-E-7B Seal Cooler Visual/Operating Charging Pump 1-CH-E-7C Seal Cooler Visual/Operating Pressure Charging Pump 1-CH-E-7D Seal Cooler Visual/Operating Pressure Charging Pump. 1-CH-E- 7E Seal Cooler Visual/Operating Pressure Charging Pump 1-CH-E-7F Seal Cooler Visual/Operating Pressure Charging Pump Seal Cooling Surge Visual/Operating Tank l-CC-TK-3 Pressure Charging Pump Cooling Water Pump 1-CC-P-2A Visual/Operating Pressure Charging Pump Cooling Water Pump 1-CC-P-2B Visual/Operating Pressure
SURRY U~
TNSERVICE I!i_~
ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/ IDE.NTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED Circulating Charging Pump Intermediate Seal Cooler Visual/Operating and Service 1-SW-E-lA Pressure Water Charging Pump Intermediate Seal Cooler Visual/Opera ting 1-SW-E-lB Pressure Charging Pump Service Water Pump Vi sua 1 /Opera ting 1-SW-P-lOA Pressure Charging Pump Service Water Pump Visual/Operating 1-SW-P-lOB Pressure Recirculation Spray Hx Radiation Monitori- Visual/Opetating ing Sample Pump 1-SW-P-SA Pressure Recirculation Spray Hx Radiation Monitro- Visual/Operating ing Sample Pump 1-SW-P-SB Pressure Recirculation Srpay Hx Radiation Monitor- Visual/Operating ing Sample Pump 1-SW-P-SC Pressure Recirculation Spray Hx Radiation Monitor- Visual/Operating ing Sample Pump 1-SW-P-SD Pressure Piping Visual/Operating Pressure Supports and Hangers Visual Component Reactor Coolant Pump 1-RC-P-lA Oil Visual/Operating Cooling Cooler Pressure Water Reactor Coolant Pump 1-RC-P-lB Oil Visual/Operating Cooler Pressure Reactor Coolant Pump 1-RC-P-lC Oil Visual/Operating Cooler Pressure
- COMPONENT SURRY Ul<a
-INSERVIC~ION ASME CODE *CLASS 3 COMPONENTS CODE APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRU ... TION EXAMINATION RELIEF REQUESTED Component Reactor Coolant Pump 1-RC-P-lA Shroud Visual/Operating Cooling Cooling Coil l-VS-E-6A Pressure Water Reactor Coolant Pump _l-RC-P-lB Shroud Visual/Operating Cooling Coil l-VS-E-6B Pressure Reactor Coolant Pump 1-RC-P-lC Visual/Operating Cooling Coil l-VS-E-6C Pressure Excess Letdown Heat Exchanger l-CH-E-4 VIII Visual/Operating (shell side) Pressure Residual Heat Removal Pump Seal Cooler Visual/Operating 1-RH-E-2A Pressure Residual Heat Removal Pump Seal Cooler Visual/Operating l-RH-E-2B Pressure Residual Heat Removal Heat Exchanger VIII Visual/Operating 1-RH-E-lA (shell side) Pressure Residual Heat Removal Heat Exchanger VIII Visual/Operating 1-RH-E-lB (shell side) Pressure Reactor Containment* Air Recirculation Visual/Operating Cooler 1-VS-E-2-A Pressure Reactor Containment Air Recirculation Visual/Operating Cooler l-VS-E-2~B Pressure Reactor Containment Air Recirculation Visual/Operating Cooler 1-VS-E-2-C Pressure Fuel Pit Cooler 1-FC-E-lA (shell side) Visual/Operating Pressure Fuel Pit Cooler 1-FC-E-lB (shell side) Visual/Operating Pressure
SURRY INSERVICE IN ASME CODE *CLASS 3 CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED Component Non Regenerative Heat Exchanger VIII Visual/Operating Cooling l-CH-E-2 (shell side) Pressure Water Seal Water Heat Exchanger l-CH-E-1 VIII Visual/Operating (shell side) Pressure Component Cooling Surge Tank 1-CH-TK-l Visual/Operating Pressure Component Cooling Pump 1-CC-P-lA Visual/Operating Pressure Component Cooling Pump 1-CC-P-lB Visual/Operating Pressure Component Cooling Water Heat Exchanger Visual/Operating 1-CC-E-lA (shell side) Pressure Component Cooling Water Heat Exchanger Visual/Operating 1-CC-E-lB (shell side) Pressure Piping Visual/Operating Pressure Support and Hangers Visual
- Fuel Pit Spent Fuel Pit Pump 1-FC-P-lA Visual/Operating Cooling Pressure Spent Fuel Pit Pump 1-FC-P-IB Visual/Operating Pressure Spent Fuel Pit Cooler 1-FC-E-lA Visual/Operating (tube side) Pressure
SDRRY UN INSERVICE IN ION ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED Fuel Pit Spent Fuel Pit Cooler 1-FC-E-lB Visual/Operating Cooling (tube side) Pressure Piping Visual/Operating Pressure Support and Hangers Visual
ATTACHMENT B SURRY UNIT 1 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, 19 74 Edi ti on,
- 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 de terrnined to be impractical. Where* relief is requested, technical justification is provided along with alternative test methods when applicable
- SURRY u9 INSERVICE TESTING Page 1 ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK* PUMP CODE RES IS- TEST RELIEF NUMBER nESr.RTPTION CLASS TANCE TEST QUANTITtES FREQUENCY REQUESTED REMARKS 1-CH-P-lA High Head 2 FIXED or Speed (if variable) NA CONSTANT 1-CH-P-lB Safety Injection VARIABLE Inlet Pressure. (Pi) Monthly YES-NOTE 1 1-CH-P-lC (Charging) (NOTE 2) Differential Pressure (t.P) Monthly (Dwg. No. 11448- 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 lnjec tion Inlet Pressure (Pi) Monthly~ YES-NOTE 3 (Dwg. No. 11448- Differential Pressure (t.P) NA FM-89A) Flow Rate (Q) Monthly Vibration Amplitude (V) Monthly BLdring Temperature (Tb) t-lA NOTE 4 Lubricant Level or Pressure l-lA NOTE 4 1-CS-P-lA Containment Spray 2 FIXED Speed (if variable) AA CONSTANT 1-CS-P-lB (Dwg. No. U448- Inlet Pressure (Pi) lionthly FM-84A) Differential Pressure (AP) ~A Flow Rate (Q) lionthly Vibration Amplitude (V) 11onthly Bearing Temperature (Tb) lrearly LubricRnt Level or Pressure lionthly :
l-RS-P-2A Outside Recirc- 2 FIXED Speed (if variable) ~A CONSTANT l-RS-P-2B ulation Spray Inlet Pressure (Pi) ~A . Yes-Note S (Dwg. No. 11448- Differential Pressure (t. '.r) 1onthly FM-84A) Flow Rate (Q) ~A Vibration Amplitude (V) ~onthly Bearing Temperature (Tb) ~A Note 4 Lubricant Level or Pressure ~A Note 4
Page 2 SURRY INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RES IS- TEST RELIEF NUMBER nESr.RIPTION CLASS TAN CE TEST QUANTITIES FREOUENCY REQUESTED REMARKS 1-RS-P-lA Inside Recircu- 2 FIXED Speed (if variable) NA CONSTANT 1-RS-P-lB lation Spray Inlet Pressure (Pi) INA Yes-Note 6 (Dwg. No. 11448- Differential Pressure (AP) INA FM-84A) Flow Rate (Q) INA Yes-Note 6 Vibration Amplitude (V) !NA Yes-Note 6 Bearing Temperature (Tb) INA Note 4 Lubricant Level or Pressure NA Note 4 1-FW-P-3A Auxiliary 3 FIXED Speed (if variable) Monthly Note 8 1-FW-P-3B Feed water Inlet Pressure (Pi)
- Monthly '. I l-FW-P-2 (Dwg. No. 11448- Differential Pressure (AP) M:onthly FM-68A) Flow Rate (Q) NA Vibration Amplitude (V) f1onthly Bearing Temperature (Tb) l'iearly Lubricant Level or Pressure ffonthly 1-RH-P-lA Residual Heat 2 FIXED Speed (if variable) ~A CONSTANT 1-RH-P-lB Removal (Dwg. Inlet Pressure (Pi) Cold Shutdc wn Yes-Note 7 11448-FM-87A) Differential Pressure (ilP) Cold Shutdc wn Yes-Note 7 Flow Rate (Q) Cold Shutdc wn Yes-Note 7 Vibration Amplitude (V) Cold Shutdc wn Yes-Note 7 Bearing Temperature (Tb) NA Note 4 Lubricant Level or Pressure NA Note 4 1-CC-P-lA Component Cooling 3 VARIABLE Speed (if variable) ~A CONSTANT 1-CC-P-lB (Dwg. No. 11448- Inlet Pressure (Pi) ~onthly Yes-Note 9 .i FM-72D) D~fferential Pressure (AP) 1onthly rt'es-Note 9 Flow Rate (Q) 1onthly !Yes-Note 9 Vibration Amplitude (V) onthly Bearing Temperature (Tb) early Lubricant Level or Pressure. ,' onthly
Page 3 SURRY INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RES IS- TEST RELIEF NUMBER DESCRIPTION CLASS TANCE TEST QUANTITIES FREQUENCY REQUESTED REMARKS 1-CH-P-2A Boric Acid 3 FIXED Speed (if variable) NA CONSTANT 1-CH-P-2B Transfer Inlet Pressure (Pi) Monthly Yes-Note 10 (Dwg. No. 11448- Differential Pressure (AP) Monthly FM-88A) Flow Rate (Q) NA Vibration Amplitude (V) NA Yes-Note 10 Bearing Temperature (Tb) NA Yes-Note 10 Lubricant Level or Pressure NA Note 10 1-CC-P-2A Charging Pump 3 FIXED Speed (if variable) NA Inlet l'ressure (Pi) \ CONSTANT l-CC-P-2B Cooling Water iJA Yes-Note 11 (Dwg. No. 11488- Differential Pressure (~P) iJA FM-71B) Flow Rate (Q) ~onthly Vibration Anlplitude (V) fionthly Bearing Temperature (Tb) NA Note 12 Lubricant Level or Pressure f'lA . Note 12 1-SW-P-lOA Charging Pump 3 VARIABLE Speed (if variable) iJA CONSTANT 1-SW-P-lOB Service Water Inlet Pressure (Pi) ~A Yes-Note 13 (Dwg. No. 11448- Differential Pressure (AP) NA Yes-Note 13 FM-71B) Flow Rate (Q) llonthly Vibration Amplitude (V) ~onthly Bearing Temperature (Tb) IJA Note 12 Lubricant Level or Pressure ~A Note 12 1-SW-P-lA Emergency Service 3 FIXED Speed (if variable) onthly Var lab le 1-SW-P-lB Water (Dwg. No. Inlet Pressure (Pi) onthly rtes-No te 14 1-SW-P-lC 11448-FM-71A) Differential Pressure (~P) onthly Flow Rate (Q) JTA Vibration Amplitude (V) l onthly Bearing Temperature (Tb) l A Lubricant Level or Pressure1 onthly Note IS Y'es-Note 15 I
SURRY UNIT 1 INSERVICE TESTING AS.ME CODE CLASS 1, 2 and 3 Put1PS 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 6.P 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 Oroom 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 6.P 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 6.P 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 for each test (head of water with casing filled) and thus will not be measured.
- 6. These pumps cannot be tested to code requirements as the test would require filling the sump and spraying water on components in the containment. Pump current is the only pump parameter measured, this test is performed monthly. This system is always dry which prevents longer pump run time (30 second max.) and prevents performing periodic flow testing.
- 7. It is considered impractical 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 cold shutdown provided that containment is accessible.
- 8. The turbine-driven auxiliary feed pump speed will be measured monthly.
The motor driven auxiliary feed pumps are not required to have the speed measured.
SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 and 3 PUMPS NOTES cont'd.
- 9. Flow rates from these pumps va-ry to meet the unit heat load require-ments. Instead of varying the system resistance (as required by IWP-3100) to establish a reference flow, sets of reference values will be established to cover the range of system flow rates.
- 10. No inlet pressure instrumentation is installed for these pumps.
These pumps take suction from the Boric Acid Storage Tanks. Tanks level will be observed from the control room to establish initial conditions for testing. The pumps are totally encased in insulation making vibration and bearing temperature impractical to measure.
Lubricant is provided by pump flow.
- 11. No inlet pressure instrumentation is installed fo:t these pumps.
The charging pump seal cooling surge tank maintians a constant suction head for these pumps therefore it is not considered necessary to measure inlet pressure.
- 12. Pump bearings are carried in the driver motor and are grease lubricated .
- 13.
14.
No inlet or outlet pressure instrumentation is installed for these pumps. Flow rate and vibration amplitude will be measured to assure adequate pump performance. Also a system low pressure alarm is provided to alert the operator of inadequate system flow.
No inlet pressure instrumentation is installed for these pumps.
These pumps take suction from the James River. The river water level will be used to establish initial conditions for testing.
- 15. The service water pumps are open line shaft pumps that depend primarily of the liquid being pumped for the lubrication of the .
pump and lineshaft bearings. The bearing lubricating water flow can be verified by sight glass and pressure can be monitored. All pump bearings are submerged and lubricant is allowed to leak off into the sump and is not piped back, such that bearing or lubricant outlet. temperature cannot be monitored.
ATTACHMENT C SURRY UNIT 1 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 IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 19 74 Edition, with Addenda thru the Summer of 19 75.
This tabulation identifies thevalve 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 10CFRSO in lieu of ASME Section XI subsub-article IWV-3420.
There are no testable Category D valves in Surry Unit 1 Systems.
Any inspection requirements identified as impr;actical during the course of the inspection period will be noted and included. in the inspection program at the time of the next revision.
Any valve which when exercised could put the plant in an unsafe condition will not be tested. Below are some examples of the types of valves specifically excluded from exercising tests during plant operation:
(i) All valves whose failure in a non-conservative position during the cycling that would cause a loss of system function will not be exercised. Valves in this category would typically include all non-redundant valves in lines. Some valves may fall into this category under certain system configurations or plant operating modes.
(ii) All valves whose failure to close during a cycling test would result in a loss of.containment integrity. Valves in this cate-gory would typically include all valves in containment pene-trations where the redundant valve is open and inoperable.
(iii) All valves, which when cycled, could subject a system to pressure in excess of their design pressures. It is assumed for the purpose of a cycling test, that one or more of the upstream check valves has failed unless positive methods are available for determining the pressure or lack thereof on the high pressure side of the valve to be cycled.
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."
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 tq the required position will be achieved by observing that normal required flows are established in the systems.
The stroke times of solenoid control led, air operated valves is both extremely rapid and subject to considerable variation: Exception is taken to complying with stroke variations defined by Article IWV-3410(c)
(3). The valve stroke timing tolerance specified is based on a reference valve. This will not exceed the maximum stroke time.
A review of containment isolation valves is being conducted to ensure compliance to Appendix J of 10 CFR 50. At the completion of this review some valves may be added to this program .
SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES LEGEND TEST REQUIREMENTS 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 IWV-3420 or as modified by specific relief request.
EV - EXERCISE VALVE for operability at least once every (3) months per Section XI subsubarticle IWV-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 VALVE TYPES ACTUATOR TYPES 0-0pen CK-Check SA-Self Actuating C-Closed RE-Relief *MO-Motor OC-Open or Closed SF-Safety PN-Pneumatic T-Throttled BA-Ball HW-Handwheel GL-Globe GA-Gate BU-Butterfly SCK-Stop Check PL-Plug DA - Diaphram
e SURRY UNIT 1 INSERVICE TESTING
. ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME_____M=-=A~I==Nc:___;:;S;.::T.:::EAM~--------- DRAW. NO *----~l:..::.l....:...44.:....:8:._;-:..::.FM=---=6:._;4=A'----- PAGE 1 VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES1 ITYPF. TION SV-MS 10 lA, B, C B-3,B-4,B-6 Main Steam Safety Valves 2 c 4 SF SA c SP YES
( 1)
SV-MS102A,B,C C-3,C-4,C-6 Main Steam Safety Valves 2 c 6 SF SA c SP YES SV-MS103A,B,C B-3,B-4,B-6 (1)
SV-MS 104A, B, C B-3. B-4. B-6 SV-MS 105A, B,c C-3,C-4,C-6 TV-MSlOlA, B,C D-3,D-5,D-7 Main Steam Line Trip Valves 2 B 30 CK PN 0 EV YES ST (1)
PCV-MS102 F...,.8 Main Steam to Turbine Driven 3 B 3 GL PN c EV NO Auxiliary Feedwa ter Pump ST MOV-MS102 G-8 Main Steam to Turbine Driven 3 B 3 GA MO c EV NO Auxiliary Feedwater Pump ST l-MS-176, 178, F-8,F-8,F-8 Main Steam to Turbine Driven 3 c 3 CK SA c CV NO 182 Auxiliary Feedwate r Pump Check Valves NRV-MS lOlA, B,C D-3,D-5,D-6 Main Steam Non-Return Valves 2 c 30 SCK MO 0 CV YES (1)
TV-MS109 F-7 Main Steam Drain to - B 3 GA PN 0 EV NO Condenser ST TV-MSllO E-7 Main Steam Drain to - B 2 GA PN 0 EV NO Blowdown ST NRV-MS102A,B,C C-2,C-4,C-6 Decay Heat Release Non-Return 2 c 3 SCK HW c CV NO Valves
SURRY UNIT l
. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME AUX. STEAM & AIR REMOVAL
~~~~~~~~~~~~~--'--'--=~~- PAGE-z--
VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES1
'l'YPR 1'ION TV-SV102 L-2 Air Removal Divert to Reactor Containment
- A 6 GA PN c LT NO EV ST TV-SV103 L-2 Air Removal Divert to Atmosphere - B 6 GA PN c LT No EV ST l-VP-12 L-1 Air Removal Divert to Reactor Continment
- AC 6 CK:' SA c LT Yes CV (26) i
SYSTEM NAHE._ _ _ _ _F_E_ED_W_A_T_E_R_________
. ASME CODE CLASS 1, 2 AND 3 VALVES Dr~w. NO. 11448 FM 68A
- Pi\GE-:t-1--;,ALVE DRAW,
- I CODE CATE- SIZE VALVE IACTUA-1 NO~-'IAL TEST R"-~~E::-
l i~1- ~-F-W-:-:-:-:-~-8-,8-9--~C---:-~-:-:-~-.-~-5-1,~--~-:-:-!-~-~-:-r-:-;-:-~-~-n-H_e_~_e_r--f~~~)--~~-1~~~!~
l-FW-10, 12, 41, 43, C-2,C-2 I Feedwater Header Main Feedwater Check Valves I
~
- 2 C l
- 1
! 14 CK SA l 0 CV 72, 74 C-4,C-4, C-.5,C-5 1.
I at Containment Penetrations 1* YES (3)
MOV-FW151A,B,C, B-6,B-6, II . Auxiliary Feedwa ter to 1
1 3 B 3 GL MO I D,E,F B-6, B-6, C-6, C-6 Steam Generators 1 0 EV ST NO I
l l-FW-131, 133, 136,138 C-6,C-6, C-6,C-6 Auxiliary Feedwater Header Check Valves at Containment I f 3 c 6 CK SA c CV YES l! Penetration l I I! I !l (2)
- 1 l-FW-142, 15 7, 172 D-7 ,E-7 F-7 Auxiliary Feedwater Pump Discharge Check Valves l 3 c 6 CK l SA c ICV I
I YES I
i l-FW-144, 159, 174 D-7, F-7 G-7 Auxiliary Feedwater Pump Recirculation Check Valves II I 3 c 1 l CK l! SA l 0 l' CV (2)
No I*
I I I I I I I !
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SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM :'\ANE._ _ _ _ _c_R_o_s_s-_c_o_N_N_E_C:_'f_S_F_O_RA_u_x_I_L_I_A_R_Y_FEED DRAW. NO *-----=ll,,__4._4._..8'--.....
FM .....-_,6..,8_B.____ _ PAGE VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF NlJ'}mER LOCN. FUNCTION CLASS GORY (IN.)
- TYPE TOR POSI- REQ. REQUES1 11'YP( TTON MOV-FW160A,B .T-5,J-6 Cross-Connects for Unit* No. 1 3 B 6 GL MO c EV Aux. Feed from Unit No. 2 NO ST l-FW-272, 273 I-7,I-7 *Cross-Connect for Unit No. 1 3 c 6 CK SA c CV YES Aux. Feed from Unit No. 2 Check Valves at Cont
- Penet. (2) l-FW-309, 310 H-7,H-7 Cross-Connect for Unit No. 1 Aux. Feed from Unit No. 2
~ c 6 CK SA c CV YES Check Valves (2)
SURRY UNIT 1 INSERVICE ~ESTING ASME CODE .CLASS 1, 2 AND 3 VALV~S SYSTEM NAf!E._____s_E_R_v_r_c_E_W_A_T_E_R_ _ _ _ _ __ DRAW.N0. ______1_14_4_8_-_FM_-_7~1_A___~ PAGE 5 VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF
!li'IDIBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUE~S1 1'YPF. TION MOV-CW106A,B, E-4,E-4, Condenser Inlet 3 B 96 BU MO 0 EV NO C,D F-4,F-4 Isolation Valves ST MOV-SW102A,B E-6,F-6 Service Water to Component 3 . B 42 BU MO 0 EV NO Cooling Wat~r Heat Exchangers ST MOV-SW103A,B, B-6,B-6 Service Water to Recircula-. 3 B C,D D-6,E-6 tion Spray Heat E~changers 30 BU MO c EV YES
. ST (4)
MOV-SW104A,B, A-2, B-2, C-2, Recirculation Spray Heat 3 B C,D 24 BU MO 0 EV NO C-2 ,A-2,A-2, Exchange~s Isolation Valves MOV-SWlOSA, B, c,n B-2,C-2 ST MOV-SW106A,B D-4,D-4 Recirculation Spray Heat 3 B 36 BU MO 0 EV NO Exchangers Cross Connect ST
... Valves MOV-$W101A,B B-4C-4 Bearing Cooling Water 3 B 36 BU MO EV Heat Exchanger Isolation . 0 ST NO*
Valves t
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SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CIRCULATING & SERVICE WATER 11448-FM-71B PAGE 6 VALVE DRAW. CODE CATE.,- SIZE VALVE ACTUA- NOR.'1AL TEST° RELIEF.
NIDIBER LOCN. FUNCTION CLASS *GORY (IN.) TYPE TOR POSI- REQ. REQUES1 ITYP'R TION l-CC-764,752 D-6,G-6 Charging Pump Cooling Water 3 c 2 CK SA oc. CV NO Pump Discharge Check Valve l-SW-113, 108 D-8,G-8 Charging Pump Service Water 3 c Pump Check VAlve 2 CK SA oc CV NO I
i I
I I
0 i
SURRY U N -
INSERVICE TESTING ASME CODE c::.,/\.SS 1, 2 AND 3 VALVES SYSTEN NAffE:___ _ _ _c_o_M_P_O_N_EN_T_c_o_O_L_I_N_G_W_A_T_E_R_ DRAW. NO. 11448-FM-Z?A Pt.GE_]__
VAtVE DRAW. *----T-conE I CATE_!! SIZE I VALVE IAcruA- NOfillAL I TEST --;ELIEF F~N~~I~~- t~~~~J-~~~~~L~ cr:~I~~~~~-~J~~~E~~-.l~;~~. ~.,~,~~.~.,~, !,~~-~~~~~
Nl;}!EER LOCN.
---+--------r*-----
- j I I RV-CC119A~B L-2, L-3 I Component Cooling from RHR Heat Exchanger Relief Valve 1
j 3 ) C l
l-CC-176, 177 '!1 . i I I
I B-1,B-l I* I. YES i Component Cooling to RHR Beat Exchanger Check Valves l' 3 C !i 18 CK l
11 SA OC CV (5) l-CC-1,58,59 A-2,A-2,A-2
!! Component Cooling to Reactor Coolan,t Pumps I i 3 C i; 6 CK j SA II 0 CV YES
( 6)
TV-CC105A,B ,C D-8, D-8, E-8 'I Component Cooling from Reactor Coolant Pumps lj 3 I
B lI 6 BA j PN O EV ST YES (6) lI TV-CC107 D-8 !
i Component Cooling from I i 3 *!
- B lI 2~ GL 1
I1' PN 0 EV ! YES I TV-CC109A,B F-8,F-9 ;I l
Reactor Coolant Pumps component coo 1.ing RHR Heat Exchangers f rom 3 1
1 1
I B
1 1
NO ST II I, I lI I 1
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SUimY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES COMPONENT COOLING. 11448-FM-72R PAGE B
\'AL\'E DRAW. CODE CATE- SIZE VALVE ACTUA- NOR!>!AL TEST RELIEF Nl;}H3ER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQlJES1 TYPR TI0111 l-CC-24 2
- 23 3, C-4,E-4,I-4 Component Cooling to 3 c 6 CK SA 0 CV YES 224 Reactor* Containment *(7)
Air Recirculation Coolers TV-CCl lOA,B .c ~3,F-3,H-3 Component Cooling from 3 B 6 BU PN 0 EV NO Reactor Containment Air ST Recirculation Coolers 0
RV-CC112A,B,C E-5,F-5,G-5 Component Cooling rrom 3* c 3/4 RE SA c SP NO Reactor Containment Air Recirc. Coolers Relief*
I
SURRY UN-INS ERVI CE TESTING
. ASJ:IB CODE CLASS l, 2 AND 3 VALVES SYSTE~f NAHE ,_ _ _ _C_OM_P_O_N_E_NT_C..cc.O~OL~I=N.:...:::G_ _ _ __
DRAW. NO *-----.1l.-.1.l.L1-4""'48~-"-"FM-1'1-71-r2t;.4..C--- PACE-9--
V1\LVE NUNTI2R DRAW.
LOCN.
l.
i.
FUNCTION I CODE I CATE-! SIZE I CLASS I GORY j (IN.)
VALVE l.l\cTuA-TYPE l~~R, NOP-..}IAL
~*os~- REQ.
TEST jizi::~*IEF I REQUES'l 1--------1------~L-*---*-~*--*---~-*--,.-~---*----**-~-i-----~--1.----~*w**--~.l.'.Li.I'. E.~-,. _IX9L ... .,..~...=~~*~*"*'*****. ""********-~*-
RV-CClllA,B 1 !
3 I I ;
C j~
! I i
I-3, I-4 I c I
Component Cooling to Fuel Pit Coolers Relief Valves I
)
I \
3/ 4 RE j SA i SP NO I . I I 1 i I I I I I I ' i I
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- c * * :~
SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE}f NANE COMPONENT COOLING DRAW* NO. _ _ _ _ _11448-FM-72D
- ----------------~ PAGE lO VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NOR..'.i.AL TEST RELIEF NU'}ffiER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES1 l'l'YPF. 'rION l-CC-55 7, 563 *c-2,C-2 *component Cooling Pump 3 c 18 CK SA oc CV NO Discharge Check I
SURRY UN~
INSERVICE TESTING ASME CODE CLASS 1 ~ 2 AJ'.-U) 3 VALVES SYSTEM NAME,_ _ _ _ _S_AM_P_L_I_N_G_ _ _ _ _ _ _ _ _~
DRAW. NO
- _ _ _ ___JJ__._J~41"-40:8=.JFM~:.(;8h-'2...QB---- P/\.GE-H-VALVE t*.!'1..'.i.'1EER DRAT*].
I LOCN. FUNCTIO;':'!
- Ij CODE CLASS CATE-GORY I SIZE l
I (IN.)
VALVE TYPE ACTUA-TOR NORHAL POSI-TEST REQ.
I RE~*IEFl REQUES1l t----------.J-------,'----------- *-----1----- -~-~*--_J-~--*--1.TYJ;.K~--.J].Cl~L~~'""***=~~*~'-r u**=~~-
TV-SS103 E-1 Residual Heat Removal System Sample 1 2 A I 3/8 GA I PN oc ~; NO TV-SSlOOA,B D-1,E-l Pressurizer Liquid Space Sample Il . 1 A Il* 3/ 8 GA I. PN oc LT EV NO TV-SSlOlA,B D-1,E-1 Pressurizer Vapor Space Sample I!
I 1 A II 3/8 GA I I PN oc ST LT EV ST TV-SS106A,B D-2,E-2 Primary Coolant Hot A 3/8 GA PN oc LT NO I Leg Samples l
EV ST TV-SS102A,B D-2,E-2 I
Primary Coolant Cold Leg Samples ;
A I 3/8 GA
. PN
! oc I LT NO I
i l l\
EV ST TV-SS104A,B D-2, E-2 I1 Pressurizer Relief Tank Gas Space Sample A 3/8 GA I PN oc LT NO I! I Il
- EV ST I l l I
I I
j I I
.I II l I
- t i
I I I' I '
INSERVICE TESTING
... ASME CODE CLASS 1, 2 AND 3 VALVES s-ISTEN NAHE_ _ _ _ _V_E_N_T_S_&_D_R_A_IN_S_ _ _ _ _ __ DRAW. NO. J J 448 FM 83A PAGE-1-1---
VALVE DRAW. I i-CODE 1Az;.UA-1 NORNAL I l\li'l'IBER LOCN.
I FUNCTION I CLASS CATE-I SIZE GORY VALVE TEST RELIEF L~IN.) .,,...~~~I.I~~~~ . -~~c~~~ ~* R~.:.:.~..,.*.~~~~EST i----------:-------,*c------~--~-------;*
I TV-DAlOOB A-8 R. C. Sump Pump A 2 GA I. PN oc LT NO Discharge Isolation f Il
~~
TV-DG108B A-3 Pr. Dr. Transfer Pump A 2 GA PN oc LT NO Disch. Isolation EV ST TV-VG109B A-1 'Gas Vent Hdr. Isolation A 2 GA PN 0 LT NO EV ST l-VA-1, 6 A-3 I Containment Isolation AE 2 GA ! HW c VP (YES)
I (26)
I I 1, I I l.
I I i,.
I i
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- VENTS & DRAINS SURRY U N -
INSERVICE TESTING
- .ASME CODE CLASS l , 2 Ai'Jl) 3 VALVES
- (
DRAW. NO *_ _ _ __,l._.l._...4-=4~8-~FM~-~8~3B~- PACE--13--
I I VALVE RE~-J:EF-.l
/ALVE J'I:-!E.ER DRAW.
LOCN.
I FUNCTION j CODE CLASS CATE-! SIZE GORY (IN.) TYPE jACTUA-p:oR l NOTu-lAL POSI-TEST REQ. RCQtJ;;:S'i I
- ~~~~~r~~~~~~-~~~~~
I
. -*-!-------~* _L_.:\:Y.f}'----. .II'lli.-.1-*-*r**----I TV-DAlOOA I-8 R. C. Sump Pump Discharge Isolation A I 2 GA PN oc LT EV NO l I I TV-DG108A L-5 Pr. Dr. Transfer Pump Disch. Isolation Al 2 OA PN OC ~~ NO TV-VG109A L-2 Gas Vent Hdr. Isolation A 2 GA PN 0 LT NO EV ST I1*
I I
l I
I I
I II I
I
I SURRY UNIT 1
- . INSERVICE TESTING ASME- CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CONTAINMENT & RECIRCULATION SPRAY PAGE-- VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES1
- 'T'YP'R TION MOVRS155A,B F8,F8 Recirculation Spray Pump 2 A 12 PL MO 0 LT NO Suction from Containment Sump EV ST MOVRS156A,B F6,F6 Recirculation Spray 2 A 10 GA MO 0 LT NO Pump Discharge EV ST lRSll, 17 F6,F6 Recirculation Spray Pump 2 AC Discharge Check Valves 10 CK . SA c CV LT YES (8)
MOV-CSlOO,A,B I-4, I-4 Containment Spray Pump 2 B 12 GA MO 0 EV NO Suction from RWST ST MOVCS 10 IA, B, F2,F2, Containment Spray Pump 2 A 8 GA MO c LT NO C,D Fl, Fl Discharge EV ST 1CS13,24 E2, El Containment Spray PUmp 2 AC 8 CK SA c CV YES Discharge Check Valves LT (8)
MOVCS102A,B J3,K3 Chemical Addition Tank 2 B to RWST Isolation Valve 6 GA MO c EV NO ST lCS 25 J-3 RWST to LHSI 2 !
E 16 GA HW 0 VP NO MOV RH-100 K-3 RHR to RWST
, - A 6 GA MO 0 EV YES ST (26)
SYSTEM* NAME SURRY UNIT l INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CONT. VACUUM & LEAKAGE MONITORING PAGE~
VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES'l TYPF. 'T'ION TV-LMlOOA,B E-3
- E-3, E-3, Open Pressure System -
C,D,E,F,G,H A 3/8 GA PN c LT NO E-3,E-3,E-3, Isolation EV D-3,E-3 ST TV-LM101A,B H-4, I-4 Closed Pressure System - A 3/8 GA PN c LT NO Isolation EV ST HCV-CVlOO J-5 Cont. Vacuum A:ir Ejector - A 8 GA PN c LT YES Isolation \
EV (26)
ST TV-CV-150A,B, H-7,H-7, Cont. Vacuum Pump - A 2 GA PN 0 LT NO C,D H-8,H-8 Suction Isolation EV ST 1-CV-2 ' I-5 Coll't. Vacuum Air Ejector - AE 8 GA HW c VP YES Isolation EV (26)
I .
I
SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CONT. VACUUM & LEAKAGE MONITORING DRAW. NO *_____1ull..!:l4t..::t4cu.8=-FM=::..:i9cuO'°'A_ _
VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NOl{iYi.AL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES1
.. ITYP"F'. '!'ION l-GW-166, 175 B-3, A-3 Gaseous Waste Disposal - A 2 DA HW c VP Yes Isolation LT (26)
EV l-GW-174, 183 A-2, B-2 Gaseous Waste Disposal Isolation
EV I '
SURRY UN' INSERVICE TESTING ASHE CODE CLASS 1, 2 AND 3 VALVES SYSTEN NA.i~E._____R_E_A_C_T_O_R~CO~O~LA-"'-N~T:..___ _ _ _ _~ DRAH. NO . _____l.._.l"-"4=4~8'--FM....u::-_,_8,_,_6LUB_ _ __ Pf\.GE-1.6-I VAT-VE NUNBER DRAW.
LOCN. FU~CTION CODE CLASS CATE-GORY SIZE (IN.)
I VALVE L\CTU/\.- NORNAL TEST RELIEF I -- -----t I TYPE TOR
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SV-1551A,B,C F-4,G-4,H-4 Pressurizer Safety Valves TV-1519A A-6 Primary Grade Water to 1
c A
6 SF SA c SP I NO 3 GA PN c LT NO PRZ Relief Tank l EV ST l
l-RC-160 D-6 Primary Grade Water to PRZ Relief Tank I - AC , 3 CK SA c LT CV YES (27)
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. ASME CODE CLASS 1, 2 AND 3 VALVES S'.(S TEN N l 0 f E _ C_H...EM_*.r...c~A~L~~AN=D:____!._V.':'.'._O~LUM=E~C~O~N""T'-"R""O""'L,___ DRAW. NO *-----!l-ll-4-44-488--lH<M-£rtJ8rH8rHB----
VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NORrL'.\L TEST Ri::LIEF NFHBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. REQUES'i
- - - - - f - ~-!'*-- TYPF.
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I l-CH-258, 26 7, D-6,F-6 Charging Pump Discharge 276 G-6 2 c 3 CK SA oc CV YES I Check Valve (17)
I LCV-1115B,D C-9,C-9 Charging Pump Suction from 2 B 8 GA MO c EV NO Refueling Water Storage Tank ST LCV-l 115C,E H-3, H-3 Charging Pump Suction from 2 B 4 GA MO 0 EV Volume Control Tank YES ST (12)
MOV-1275A,B,C D-6,F-6,H-6 Charging Pump Recirculation 2 B 2 GA MO 0 EV Flow Path Isolation YES ST (17)
MOV-1373 F-5 Charging Pump Recirculation 2 B 3 GA MO 0 EV Header Stop Valve YES ST (13)
MOV-1381 A-3 Reactor Coolant Pump Seal 2 A 3 GA MO 0 LT Water Return YES EV (14)
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SURRY UN-INS ERVI CE TESTING
.. ASME CODE CLASS 1, 2 AT'*fD 3 VALVES SYSTEM NA.~E'~--~~~C~H~EM==I~C~AL=-.;A~N~D~V~O~L~I~lM~E.._,,C~O~N~T~R-OI~*- DRAW. NO . --lr:l!:-.14rit4~8,_.FJFJ>lf-f-t8tt8!fi-------
- PACE
-rs-I VALVE
~WMBER DRAW.
LOCN. FUNCTION CODE CLASS CATE-GORY SIZE (IN.)
VALVE TYPE ACTUA-TOR NORHAL POSI-TEST REQ.
RELIEF REQUES11 i
- ...TYPF.
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TV-1204 A-3 Reactor Coolant System 2 A 2 GA PN 0 LT YES Letdown Isolation Trip Valve EV (15)
ST RV-1209 F-1 Reactor Coolant System 2 c 2 RE SA c SP NO Letdown Relief Valve RV-1257 H-1 Volume Control Tank Relief 2 c 3 RE SA c SP NO Valve MOV-1289A & B B-5 Normal Charging Header 2 A 4 GA MO 0 LT Isolation YES EV (16)
ST FCV-1160 A-3 RCS Loop Fill Header 1 A 2 GL PN c LT Isolation YES EV (26)
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CHEMICAL AND VOLUME CONTROL SURRY UN
.INSERVICE TESTING
.. ASME CODE CLASS 1, 2 AND 3 VALVES DRAW. NO . _ _.._1.l.J14.,...4+.118~EM~-.e8.e8C1..--------
- PAGE-t9--
VALVE DRAW. CODE CATE- SIZE VALVE ACTUA- NOfillAL TEST RELIE11 NUNTIER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI- REQ. 17.EQUESTj
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-*~---l RV-1203 H-1 Letdown Header Relief 2 c 2 CK SA c SP NO I
HCV-l 200A, B, C H-2, H-2,
! H-2 Letdown Orifice Isolation 2 A 2 GA PN oc LT EV NO I '
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INSERVICE TESTING
.. - ASHE CODE CLASS 1, 2 AND 3 VALVES SYSTEN NAi~E*~~---~SA~F~E=T~Y'-"'I=N=J=EC~T~I=O~N,___ _~-~ DRAW. NO' ---:11:-+/-l-'t-44'48~H'Mi~897i.Ar------
VALVE DRAW. CUDE CATE- SIZE VALVE ACTUA- NORNAL TEST R NUNBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR
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POSI-TION....
REQ.
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MOV-1860A,B B-8, E-8 Low Head Safety Injection 2 A 12 GA MO c LT N Pump Suction from Contain-ment Sump EV ST l-SI-56,47 C-8, F-8 Low Head Safety Injection 2 c 12 CK SA c CV YES Pump Suction from Contain-ment smµp Check ( 18)
MOV-1862A, B G-9, G-8 Low Head Safety Injection 2 B 12 GA MO 0 EV NO Pump Suction from Refueling Water Storage Tank* ST l-SI-46A, B G-9' G-8 Low Head Safety Injection 2 c 12 CK SA c CV Y.ES I Pump Suction from Refueling Water Storage Tank Check ( 28) 1 I l-SI-58, 50 D-7' G-7 Low Head Safety Injection 2 c 10 CK Pump Discharge Check SA c CV YES
( 28)
MOV-1863A, B E-6, G-6 Low Head Safety Injection 2 B 8 GA MO c EV NO Pump Dischrge to High Head '
Safety Injection P~mp Suction ST MOV-1885A, B, C-7, G-6, Low Head Safety Injection c, 2 B 2 GA MO 0 EV NO D G-6, C-7 Pump Rec 1 rcula ti on to ST Refueling Water Storage Tank . I lI I l-SI-61, 53 C-6, G-6 Low Head Safety Injection I
2 c 2 CK SA c CV NO i Pump Recirculation to I
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SURRY INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES
- PAG~
VALVE DRAW. C'JDE CATE-I SIZE VALVE ACTUA- NORNAL TEST RELIEF
}<u'MBER LOCN. Fl?NCTION CLASS GORY f (IN.) . TYPE TOR POSI- REQ
- REQUES1 MOV-1864A, B D-6, G-5
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- 2 B 10 GA MO 0 EV Pump Dischrge to Reactor NO
~ ST Coolant System Cold Legs t 1*
RV-1845A, B, c C-6, D-5 Low Head Safety Injection 2 c 1 .RE
MOV-1890A, B B-6, B-5 Low Head Safety Injec I; ion 2 AE. 10 GA MO c LT NO to Reactor Coolan.t System Hot Legs EV ST VP MOV-1890C B-6
- Low Head Safety Injection 2 AE 10 GA MO 0 LT YES to Reactor Coolant System EV (19)
I MOV-1869A, B, 1842 A-3, I-3, A-1 High Head Safety *Injection to Reactor Coolant Sys.
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I AE 3 GA MO c .LT EV YES I I (20)
B-1, B-2 I I
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GA MO I c LT YES i I EV (21)
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Inlet Isolation l
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VALVE DRAW. CODE CATE-l SIZE VALVE ACTUA- NOR.HAL TEST RELIEF NUXEER LOCN. FUNCTION 'CLASS I
- ~~~~--<*------------}~~--I GORY I
(IN.)
l TYP~ eR POSI- REQ. REQUES TV-1884A H-1 Boron Injection Tank Recirculation 2 B j
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I ST NO TV--1884B, C H-1, G-2 Boron Injection Tank 3 B 1 GA PN 0 .EV NO Recirculation ST RV-1857 D-1 Boron Injection Tank 2 c Relief 3/4 RE SA c SP NO TV-SilOO_ B_;4 Nitrogen Accumulators A 1 GA PN 0 LT NO EV ST l-SI-73
- A-5 Accumulator I~;olation AE *3/4 GL c EV YES LT (26) l-SI-32 A-5* Accumulator Isolation AE 1 GL HW c EV YES LT (26) l-SI-150 E-1 Boron Injection Tank - A 1 GL HW I EV YES 0
I LT (26) t l-SI-174 C-2 High Head Safety Injection to Reactor Coolant System I I A l 3/4 GA HW c EV YES I I II LT (26)
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.SURRY-.
INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES
---~~~~~~-----------------------~~~-~ DRAW.N0*~--1~1~44~8~-~FM~--89~B=--~~~~~- PAGE.23__
VALVE DRAW. CODE CATE-I SIZE VALVE ACTUA- NORNAL TEST RELIEF NU11EER LOCN.
.I FUNCTION CLASS GORY r (IN.) TYPE TOR POSI- REQ. REQUES1
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RV-1858A, B, c C-4,G-5,C-7 Accumulator Tank Relief 2 c
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. *I C-5, A-5, Accumulator Discharge Check 1. c . 12 CK SA c 128, 130, G-7, A-7, CV YES 145, 147 C-8, A-9 (22)
MOV-1865A, B, c C-5,G-6,C-8 Accumulator. Discharge 2 BE 12 G./l MO EV 0 NO ST VP I -
l-SI-88, 91, 94, A-2, A-2, Safety Injection to 1 c 'SA 238, 239. 240 A-3, B-2 6 CK c CV YES
. RCS Hot Legs I B-2, A-.3 (23) 1-SI-235, 236, ~1. B-1 High Head Safety. Injection 1 c 2 CK SA* c CV YES 237 B-2 to RCS Cold Legs I . (24)
II 1-SI-241, 242, 243 B-1, B-1, B:....2 Low Head Safety Injection to RCS Cold Legs 1 c I 6 CK SA c CV YES (30) l-SI-224, 225, I
I J-1, J-1, High Head Safety Injection 2 c
! 3 CK SA c CV I Il 226, 227 J-2, J-3 YES Check Valves at Containment (24)
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1-SI-228, 229 J-3, J-3 Low Head Safety Injection i 2 c .~ 6 CK SA c CV YES l Check Valves at Containment Penetrations l
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- . SURRY .u9 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:_.._ _ ____,S~A~F.....,.E,...T.&.Y.....I""-lN.,.,.J....,E.,.C""T....,IO"'"N....__ _ _ __
DRAW. NO *--...Jlul~4..Q4.t:J;8:.EMl:.J!l.::~8.;;i.9.o.B_ _ _ _ __ PAGE Q~
ALVE c ER DRAW.
LOCN. f FUNCTION C:.JDE CLASS I CATE-I SIZE GORY r (IN.)
VALVE IACTUA-TYPE !TOR NOfil!AL POSI-TEST REQ.
RELIEF REQUES1 I i I J.YJ'..] TIQN I I g *~-._
MOV-18 66A, B, D, E, F c, E-3, E-2, E--2, E-2 Cold & Hot Leg Safety Injection Line Throttle Valve 2 I
- ij E ,,~~ 2 GL I
HW T VP NO l-SI-7 9, 82, 85 E-1, E-1 .
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I A-.1, A-1, Safety Injection to RCS 2 c i* *6 CK SA c CV YES A-2 Cold Legs (23)
TV-Sil OlA, .B J-5, J-5 Accumulator Nitrogen - A 1 GA PN 0 LT NO Re.1 ie f Line Isolation EV ST l-SI-2 34 J-4 Nitrogen Accumulators - AC 1 CK SA c CV YES LT (29)
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INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES DRAW. NO *----=l-=.1. .:. 44..:. :8::.. -. .::FM..:;:_..-:--=.l.::<.;06:;:..;C::.. -_ _ _ __
- PAGZ_5_
VALVE NUM3ER DRAW.
LOCN. FUNCTION CODE CLASS I CATE--, SIZE GORY r (IN.)
VALVE IACTUA-TYPE .TOR NORNAL POSI-TEST REQ.
RELIEF REQUES1 i---1 ,.
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- ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME._ _ _ ___;;:S~T;;:.:EAM=-...:;;G=.E;:.;;NE::.::RA=Tc.::.O~R....:B:;.:L:..::0;..:..:WD==-OWN='---
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LOCN.
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FUNCTION CODE CLASS DRAW. NO *_ _....l_...1.i44:Ll8~-_...FM.....__-~12""'4..,.A.___ _ _ __
CATE-I SIZE GORY i (IN.)
VALVE TYPE ACTUA-TOR NORNAL POSI-TEST REQ.
EE PAGE2fL_
REQUE I TV-BDlOOA,B,C D,E,F C-2,C-2,C-4 . Stearn Generator Blowdown C-4,C-5,C-5 Trip Valves II 2 I
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SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES RELIEF REQUESTS (1) A full stroke or partial stroke exercise of these valves during power operation could result in a turbine and reactor trip. As an alternative, they will be full stroke exercised during cold 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 feedwa ter (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) Opening these valves would result in the introduction of service water into the recirculation spray heat exchangers and cause fouling of the heat exchanger tubing. As an alternative, these
- (5) valves will be tested during cold shutdown.
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 cold shutdown.
(8) These valves are located inside the containment and not accessible during power operation, using flow to exercise these valves would result in spraying the containment, manual exercising requires building scaffolding that requires venting the containment that in turn requires leak testing both doors prior to plant startup to establish subatmospheric containment pressure. As an alterna-tive, these valves will be manually full stroke exercised during refueling outages. .
(9) Cycling of these RHR system valves during power operations would subject the RHR sys tern to full RCS pressure. These valves will be exercised when the RHR system is placed into operation during cooldown of the reactor coolant syscem.
(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 cold shutdown.
(14) This valve cannot be shut down when the RC system is above atmos-
- pheric pressure or when the RCS is being filled. Closure of this valve cause loss of RCP seal flow resulting in pump seal damage.
As an alternative, this valve will be tested at refueling outages.
(15) Exercising this valve shut dueing power operation could result in a loss of RC inventory and pressurizer level control. This valve will be exercised during cold shutdowns.
(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. Tiiis valve will be exercised during cold shutdown.
(17) With the present plant design, these valves can only be partial stroke exercised during power operation and the charging pumps cannot achieve design accident flow when pumping into the RCS at operating pressure, the only available flow path to test these valves is into the RCS.
During cold shutdown, full stroke exercising these valves could result in an over-pressurization of the RC's and could force a safety system (PORV's) to function. These valves will be full stroke exercised during refueling outages when the vessel head is removed providing an adequate expansion volume
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(18) This normally closed check valve cannot be exercisea 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 will not be exercised during power operation if this valve failed in the closed position, LHSI to the cold leg would be rendered inoperable. This valve is full stroke exercised during cold shutdowns.
(20) These valves cannot be exercised during power operation, opening these valves would allow charging flow into the RCS thermally shocking the HHSI nozzles and causing reactivity transcients. During cold shutdown the charging (HHSI) flow could cause an over-pressuri-zation of the RCS an~ could force a safety system (PORV's) to function. These valves are full stroke exercised during refuling outages.
(21) Opening these valves during power operation would allow concentrated boric acid to flow into the piping systems that are not heat traced and a boron build-up could crystalize and block system flow. These valves are full stroke exercised during cold shutdowns.
(22) These valves cannot be exercised during power operation because accumulator pressure cannot overcome RCS pressure. The 3/ 4" test line will not partial stroke these valves. These valves cannot be exercised during cold shutdown because an overpressuri-za tion accident could occur. These valves are partial stroke exer-cised during refueling outages.
(23) These valves cannot be exercised during power operation, HHSI flow through these valves would thermal shock the injection nozzles.
During cold shutdown the RCS pressure is greater than accident pressure and full design flow cannot be achieved. These valves are full stroke exercised during refueling outages when the vessel head is removed.
(24) These valves cannot be exercised during power operation, exercising valves requires flow into the RCS, thermal shocking the injection nozzles. Exercising these valves during cold shutdown could result in an overpressurization of the RCS and force a safety system (PORV's) to function. These valves are full stroke exercised during refueling outages when the vessel head is removed.
(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 are passive valves and are not required to change position to perform their safety related function. As an alternative. these valves will be tested during each refueling outage.
(27) Plant design does not permit verification of valve position during power operation or cold shutdown. The only way to verify its safety position is during leak rate testing at refueling outages. *
(28) These valves cannot be full stroke exercised during power operation, the only full flow path is into the RCS and the LHSI pumps cannot overcome RCS operating pressure. This valve is partial stroke exercised quarterly through the pump recirculation line. During cold shutdown the RCS pressure is greater than design accident pressure and the LHSI pump cannot achieve design flow. These valves are full stroke exercised during refueling outages with the vessel head removed which provides minimum RCS back pressure which allows full LHSI flow.
(29) This valve cannot be verified shut (its safety related position) during power operation or cold shutdown. The only method to verify valve closure is during a leak rate test at refueling outages.
(30) These valves cannot be exercised during power operation as the only full flow path into the RCS and the LHSI pumps cannot be full stroke exercised because RCS pressure is greater than accident pressure.
These valves are full stroke exercised during refueling outages with the vessel head removed .