Text

Forwards Requested Relief from Inservice Insp Requirements for Class 1,2 & 3 Components & Requested Relief from Inservice Testing Requirements for pumps.W/29 Oversized Drawings
	ML18114A579
Person / Time
Site:	Surry
Issue date:	05/17/1979
From:	Stallings C; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Schwencer A; Office of Nuclear Reactor Regulation
References
	332B-111776, NUDOCS 7905220142
	Download: ML18114A579 (109)
	v • d • e

{{#Wiki_filter:*, VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGINIA 23261 May 17, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. A. Schwencer, Chief Serial No. 332B/111776 PO/KEB:scj Docket No. 50-280 License No. DPR-32 Light Water Reactors Branch No. 1 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 hereby submits its programs for inservice inspection and testing of pumps and valves during the last forty month period of the first ten year interval for Surry Power Station Unit 1. Per 10 CFR 50.55a(g)(4) the ASME Code and addenda "in effect" for this period have been determined to be the 1974 Edition of Section XI with Addenda thru the Summer of 1975.

Surry Unit 1 was not, however, designed to meet the detailed inservice inspection and testing requirements of the ASME Code, Section XI.

Therefore, pursuant to 10 CFR 50.55a(g)(6)(i), we request specific relief from ASME Code require-ments pertaining to inservice inspection and testing of pumps and valves as outlined in attachments A, Band C. Attachments A Very truly yours, ?J;.m.~~ C. M. Stallings Vice President-Power Supply and Production Operations Surry Unit 1, Requested Relief from the Inservice Inspection Requirements for Class 1, 2 and 3 components as set forth in Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition with Addenda through the *summer of 1975 (last 40 month period of the first 10 year interval). B Surry Unit 1, Requested Relief from the Inservice Testing ,{ Requirements for Pumps as set forth in Subsection IWP to .c e.i' 5 S Section XI of the ASME Boiler and Pressure Vessel Code, 1974 '1 J "'1't\\~ Edition with Addenda thru the Summer of 1975 (last 40 month. ~""a.' J. 0 period of the first 10 year interval). l)6{t * (J.. t l ! ~ s*" t*.. n i~~ ('0~ '. t,\\tt e. 79052201'12._ ,.. (be,

- - -- --~--=---~- = -* Mr. Harold R. Denton

2

. VIRGINIA ELECTRIC AND POWER COMPANY TO 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). D Surry Unit 1, Marked Up Flow Diagrams Showing ASME Code Class 1, 2 and 3 System Boundaries Relative to Inservice Inspection and Testing.

I I I i ! ' ! i I. l* j \\ } l l { ---= _ =~-~==-=--------- - --- -.---

UNITED STATES

£ NUCLEAR REGULATORY COMMIS-J WASHINGTON, D. C. 20556 MEMORANDUM FOR: TERA Corp. FROM: US NRC/TIDC/Distribution Services Branch

SUBJECT:

Special Document Handling Requirements (:)1. Please use the following special distribution list for the attached document. The attached document requires the following special considerations: D Do not send oversize enclosure to the NRC PDR. [:] Only one oversize enclosure was received - please return for Regulatory File storage. D Proprietary information - send affidavit only to the NRC PDR !J S'.d,., d D~ R..:.t Xl_ Other: (specif.y) ./? /2 _.. ~ -£ ~-.._!,,,._ 'Q, r ,-~ -4..._ ~#.. ~-. f1e4%~ A... -o ~~ .9,(~ --L cc: DSB Files .1

ATTACHMENT A SURRY UNIT 1 REQUESTED RELIEF FROM TJIE INSERVICE INSPECTION REQUIREMENTS FOR CLASS 1, 2 and 3 COMPONENTS AS SET FORTH IN SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA TRROUGH THE SUMHER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL) The enclosed tables provide a listing of the Class 1, 2 and 3 pressure-retaining components (and their supports) which are subject to the inspection requirements of Subsections IWB, IWC and IWD of Section XI of the ASHE 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 thes.e inspection requirements have been determined to be impractical. Where relief is requested, .specific information is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative. The following provide further clarification concerning the Clas.s 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 Conunittee and, as yet, are not available for use. Standards for examination evaluations as included in the 1974 Edition of Section XI with Addenda through the Summer, 1975, are. incomplete and "Acceptance Standards for Flaw Indications" as given in Article IWB-3000.of the 1977 Edition of Section XI will be utilized. (b). Articles IWA-4000, IWB-4000, IWC-4000 and IWD-4000 entitled "Repair Pro.ceduresll in the. 1977 Edition of Section XI with Addenda. thru.the Summer of 1978 provide additional guidelines for making repairs and will be used in lieu of those contained in the 1974 Edition of Section XI with Addenda thru the Summer of 1975.. (c) Requirements for the visual examination o.f 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 system will be retained at.the first valve. in the line. The portions of systems affected by this limitation are: (i) Cold leg injection from accumulators between check valves l-SI-109, 130 and 147 and l-SI-107, 129 and 147, test lines to valves HCV-1850B, D and F, RHR return to valves MOV..;1720A and B.

--- -------- - - - - - - - - - - - - ~ e 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). e (ii) Hot leg injection between check valves l-SI-88, 91 and*94 and* check valves l-SI-238, 239 and 2.40. These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11448-FM-89B). (iii) Cold le*g low head inje-ction 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 th_e only means of pressurizing the Class 2 system is through the Class 1 system or when the boundary between the two systems is a check valve arranged for flow from Class 2 to the Class 1 system. Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412(a) on those portions of the Class 2 systems identified below. Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal operating.pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system. (i) R. C. Pump seal bypass lines from the flow orifice to valve HCV-1307 : (refer to drawing 11448-FM-SSC) * * (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. )?ump seal injection line from check va:J.ve l-CH-323; 333 and 349 to manually operated valve l-CH-294, 297 and 300 (refer to drawings l 1~48-FM~88B.. and ~SC}. (iv) Excess letdown system from valve HCV-1201 to HCV~ll37 (refer to drawing 11448-FM-SSC).

(v) Letdown line from valve LCV-1460B to orifice outlet valves HCV-1200A, Band 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*corrtinuous operation during plant operation. The continuous functional operation serves to demonstrate the structural and leak-tight integrity of these systems. Visual examinations of these systems will be performed at normal operation pressures to verify leaktightness. (f) Ultrasonic examinations will be conducted in accordance with the provisions of Appendix I and Article 5 of Section Vas required by Paragraph IWA-2232. As an alternative to using Article. 5 of* Section V1. Appendix III of*

section XI of the 1974 Edition, Winter, 1975 Addenda of the ASME Boiler and Pressure Vessel Code will be used for ultrasonic examina-tion of piping systems.
--~~

It is recognized that Appendix III of Section XI was issued in the Winter, 1975, Addenda and, as such, has not been officially recog-nized by the NRC by reference in 10 CFR 50.. However, Ap*pendix III is the first guideline that has been published in the ASME Code for the ultrasonic examination of pipe welds and, as suc_h, *its us.e is essential. (g) As an alternative for I-3121 of Sectiop. XI: "Calibration blocks required for the examination of welds in ferritic vessels 2 1/2 inches thick and over will be fabricated from material of-the same

specification, product form, and heat treatment as one of the materials being joined as allowed by article T-434.1 in the Winter, 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code."

The* reason this alternative is requested is that the Code* req.u.ires that. calibrat:Lon blocks for the examination of welds in ferritic _vessels 2 l/2inches 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 fabricat,~ 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.

e For the components in Surry Unit 1, particularly the pressurizer and steam generators, it will be impossible to meet the requirements of alternatives I 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 tb.e examination of piping system circumferential buttwelds (Category B-J) when the welds occur at geometric discontinuities such as pipe to vessel welds; pipe to fitting welds or fitting to fitting welds. For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the . weld and pipe surfaces: Examination from the fitting side. would be dependent upon the geometric configuration. Where elbows or tees are concerned, examination can be performed from the fitting side except. where the intra.dos of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when i_t 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 perce.nt 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 I, Class 1 system which due to limitations, would require surface examinations are: (i) (ii) (iii) (iv) (v) (vi) (vii) (viii) (ix) Loop 1 Cold Leg Injection line; Welds 6 an°d 7. Loop 2 Charging line; weld 11. Loop 2 Cold Leg injection line; welds 4 and 5. Loop 1 RTD Return line; weld 7. 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 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 ~tressing the system. Certain Class 2 systems or portions of Class 2 systems and components are exempt from the examination requirements of the IWC-2520 by IWC-1220. A summary of these exemptions as applicable to.the Surry plant systems are as follows:

(i)

All CVCS piping equal to or less t_han four-inch nominal diameter and is exempted by IWC-1220(d).

e I~*- (ii) (iii) (iv) (v) (vi) (vii) (viii) 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-I220(c)~ The boron injection tank discharge piping is all equal to or less than four inch nominal diameter. 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 nJc-I220(c). 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 system fluid and the pump and associated suction piping would be exempt from examination by IWC-1220(c). The high head SIS piping equal to.or less than four inch nominal diameter is exempted by IWC-1220(d). The containment spray system and recirculation spray systems do not function during normal reactor operation and are exempt by IWC-1220(b). 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 ASME 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 perform 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 references as being applicable to construction of components in the attached tables are: IIIA IIIC ASME Boiler and Pressure Vessel *Code, Section*. III, Class A Nuclear Vessels ASME Boiler and Pressure Vessel Code, Section III, Class C Nuclear Vessels

~-* - VIII B 31.1 B 16.5 ASME Boiler and Pressure Vessel Code, Section VIII, Pressure Vessels USA Standard USAS B 31.1 Code for Pressure Piping USA Standard USAS B 16.5 Steel Pipe Flanges, Flanged Valves and Fittings

e SURRY UNIT 1 I.NSER\\ INSPECTION ASHE CODE C ASS 1 COMPONENTS e TJ\\DLE TABLE nrn-2soo EXAMINATION IWB-2600 EXAMINATION ITEM NO. CATETORY. REQUIREMENT Volumetric SYSTEM OR CODE APPLICABLE

*---- COMPO NP.NT.::... __

_:T:..:O_::.C.::.O.:.:.N:::.ST::.:R~'-U:...C:...T_I_O..::.N:.-____ 'A._RE_*_A_T_O_D_E_E_* XAM I_N_E_D _______ __,_ __ Reactor Vessel III-A Upper to intennediate shell course Bl.1 B-A B 1.1 B-A Bl.1 B-A Bl.1 B-A Bl. 2 B-A Bl.2 B-B Bl.3 B-C Bl. 3 B-C Bl.4 B-D Bl. 4 B-D ' Bl.5 B-E Bl. 6 .B-F 1-RC-R-1 circumferential weld 'Intermediate to lower shell course circumferential weld

Intermediate shell course longitu-dinal welds (2)

Lower shell course longitudinal welds (2) Lower head to shell circumferential weld Lower head ring to disc circumferen-tial weld Vessel to flange weld Closure head to flange weld Outlet nozzle to vessel welds (3)

Inlet Nozzle to vessel welds (3)

CRDM, Vent and In-Core Instrumen-tation penetrations and CRDM seal welds ':Outlet nozzle to safe-ends welds (3) Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volmetric Volmetric Volmetric Visual Volmetric & Surface SECTION XI . CODE -RELIEF REQUESTED No No No . No No No No No No No No No

i I I I ) I I e TABLE

IWB-2600 ITD1 NO, Bl. 6 Bl. 7 Bl. 8 Bl.9 Bl.10 Bl.11 Bl. 12 Bl.13 Bl.14 Bl. 15 Bl.16 Bl.17 TABLE,

nm-2soo EXAMINATION CATETORY B-F B-G-1 B-G-1 B-G-1 B-G-1 B-G-2 B-H B-I-1 B-I-1 B-N-1 B-N-2 B-_N-3. SYATEM OR COMPONENT RY UNIT 1 INSEI E INSPECTION ASME CODE CLASS 1 COMPONENTS CODE APPLICABLE TO CONSTRUCTION iREA TO BE EXAMINED Inlet*nozzle to safe-end welds (3) Closure Head Studs (In-Place) Closure Head Studs & Nuts Veqsel* flange ligaments Closure head Washers Conoseal Bolting Integrally Welded vessel supports Closure Head Cladding Vessel Cladding.

*vessel Interior Surfaces and Inte'rnals Interior Attachments and Core Support Structuras

_:; Core Support Structures* SECTION XI EXAMINATION CODE-RELIE! REQUIREMENT REQUESTED Volumetric & No Surface Not No-Applicable Note 1 Volumetric & No Surface Volumetric No Visual No Visual No Not No-Applicable Note 2 Surface & No-Visµal or Note 3 Volumetric Visual No Visual No Not No - Applicable Note 4 Visual No

TABLE TABLE I\\lB-2500 UNIT 1 INSPECTI01~ ASME CODE LASS 1 COMPONENTS

IWB-2600 EXAMINATION SYS'l'EM OR CODE APPLICABLE EXJ\\MI NATION ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION ~REA TO BE EXAHINED REQUIREMENT

,----------*----*-----..:..:.:.;.:..:.::_ __ _;_;;__::_ _________ ~------*----------

Bl. 18 B-0 Control Rod Drive Housings Volumetric Bl.19 B2.l B2.1 B2.2 B2.3 B2.4 B2,5 B2. 6 B,2, 7 B2.8 B2.9 B2,10 B2. ll BJ,i B-P B-B B-B -B-D B-E B-F B-G-1 B-G-1 B-G-1 B-H B-:I-2 B-P B-G-2 B-B Pressurizer l~RC-E-2 Steam Generators . (3). Prima_ry Side* III-A III-A Exempted Components Longitudinal Shell welds (6) Circumferential shell welds (7) Nozfle to vessel welds (6). Heater Penetrations Nozzle t*o safe-end welds (6) Pressure Retaining Bolting (in place) Pressure ~etain:!.ng Bolting when removed Pressure Retaining Bolting . Integrally Welded Vessel Supports

*vessel cladd_ing Exempted Component_s *.

Manway Bolting Channel Head to tubesheet .Weld (3) Visual Volumetric Volumetric Not Applicable Visual Volumetric & Surface Not Applicable Not Applicable Not Applicable Volumetric Visual Visual Visual Volumetric SECTION XI CODE.R.ELIEF REQUESTED No No No Yes - Note 17 No - Note 5 No No No - Note 6 No - Note 6 No - Note 6 No No No No No

SURRY UNIT 1 e INSERV INSPECTION ASHE CODE.C ASS l COMPONENTS TABLE TAnLI~ nrn-2so6 SE_CTION XI IWB-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITE~l NO, CATETORY 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 Pressure Retaining Bolting Not No - (in place) Applicable Note 6 B3.5 . B-G-1 ~ressure 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 welded supports Not No - Applicable Note 6 B3.8 B-I-2 Vessel Cladding Visual No B3.9 B-P Exempted Components Visual No B3.10 B-G-2 -Mammy Bolting. Visual No Piping* Pressure No - .B4.l B-F Safe end to pipe welds Not Boundary Applicable . Note 6 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 !I B4.5 B-J Circumferential and Volumetric Yes - Longitudinal Pipe Welds Notes 9 and 10

e TAnLE TAnLE nm-2500 SURRY UNITl INSEH.V-INSPECTION ASME CODE CLASS 1 COMPONENTS

IWD-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION ITEM NO, CATETORY COMPONirnT TO CONSTRUCTION A.REA TO BE EXAMINED REQUIREMENT

-=----__;._ _________________ ::'..'.;~:_--~~~:::..:.:::.:::..:::.::..:::..=..:~---_;._.=~~_;.----...;.._------- B4.6 B4.7 B4.8 B4.9 B4.10 B4. ll B4.12 BS.l BS.1 BS.2 BS.2 BS.3 B5.3 B5.4 B-J B-J B-J

B-K-1 B-K-1 B-P B-G-2 B-G-1 B-G-1 B-G-1 B-G-1 B-G-1 B-G-1

~-K-1 Reactor Coolant Pumps (3) 1-RC-P-lA 1-RC-P-lB 1-RC-J:l-lC II* III-A *

i:

Branch Pipe connection welds exc~ed_ing 6" diameter *. Branch Pipe Connections Weld 6" diameter and smaller Soc,k.et Welds Integrally Welded Supports Support Components Exempted Components Pressure Retaining Bolt_ing Main Flange Bolting (in place) Seal Housing Bolting (in place) Main Flange Bolting when removed Seal Housing Bolting when' removed Main Flang_e Bolting Seal Housing Bolting Integrally Welded Supports Volumetric Surface Surface Volumetric Visual Visual Visual Volumetric Volumetric Volumetric Surface Volumetric Surface Visual Visual Volumetric SECTION XI CODE R-EL IEF REQUESTED Yes - Note 11 No No Yes - Note 12 No No No No Yes - Note 13

No Note 14 No Note 14 No No Yes -

Note 1 c;

e SU.RRY UNIT 1 INSE@e INSPECTION ASME CODE CLASS 1 COMPONENTS e TATILE SECTION XI TABLE IUB-2500

IWE-2600 EXAMINATION SYST!~M OR CODE APPLICABLE EXAMINATION CODE RELIEF nEQUIRE~lFNT RE(1UESTED

_I_T_D_l_N_O_. ___ c_A_TE_?T_O_Tl_\\.Y ____ (~_c_~-~:~~)_Nl*~N1_:T!:_ __ _:T~O~C~O.::.N.::..ST:::.:R:':'.U:.::C~T=-=I:.::O'..=.:N:__ ___ _;A..::.RE:::::*:.:.A:._:T~O-=B=E-E=*XAf:.::..:*..:.:!I:..:N.:.::JE::..::D _______ !\\_"__, __ \\_~1_*, --- BS.S BS.6 BS.7 BS.8 BS.9 B6.1 B6.2 B6.3 B6.4 B6.5 B6.6 B6.7 B6.8 B6.9 B-K-2 B-L-1 B-L-2 B-P B-G-2 B-G-1 B-G-1 B-G-1 B-K-1 B-K-2 B-M-1 B-M-2 B-P B-G-2 Valve Pressure Boundary Support Components Pump Casing Weld Pump Casings Exempted Components Pressure Retaining Bolting Pressure Retaining Bolting (in place) Pressure Retaining Bolting when removed Pressure Retaining Bolting Integrally welded supports Support Components Valve Body Welds

**valve Bodies*

Exempted Components Pressure Retaining Bolting Visual Volumetric Visual Visual Not Applicable Volumetric Volumetric & Surface Visual Not Applicable Visual Not Applicable Visual Visual Visual No No - Note 16 No No No - Note 6 No No No No - Note 6 No No - Note 6 No No No

SURRY UNIT 1 INSERVICE INSPECTION ASME CODE CLASS l COHPONENTS 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-250.0 by Category B-H.

3.

Radiation levels beneath the closure head may affect the allowable dosage of personnel doing surface and visual examination. The pres-ence of the cladding material is not considered when performing the stress analysis of the vessel such that failure of the cladding would not affect the integrity of the vessel. Tne closure head cladding will be volumetrically examined concurrent with the exam-inations performed on the closure head to flange weld.

4.

This requirement is applicable only to Boiling Water Type Reactors.

5.

The pressurizer nozzles are integrally cast with the vessel head and therefore*there are no welds.requiring *examination in accordance with the requirement IWB-2600.

6.

There are no items in this category on this component in the Surry Unit I Class 1 Systems.

7.

The steam generator nozzles are. integrally cast with the *channel head and therefore are no welds in this category.

8.

Examinations of the steam generator primary nozzle to safe-end and safe-end to pipe weld is limited both by the nozzle geometry and surface condition and the limited surface preparation,on the pipe side of the weld. The surface on the pipe side of the.weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic examination is limited to this from the edge of the weld. Examinations can be per-formed on the surface of the weld but are severely limited from the ~ nozzle side by the rough, as cast surface. Surface examination can be performed on one hundred percent of the weld and the base metal on the pipe side. The configuration is shown in Figure 1.

9.

Limitations may occur from the examination of piping system cir-cumferential butt welds (Category B-J) when the welds occur at geometric discontinuties such as pipe to vessel welds, pipe to fitting welds or fitting to fitting welds. For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe sur-faces. Examinations from the fitting side would be dependent upon

the geometric configuration. Where elbows or tees are concerned, examination can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases one hundred percent of the weld material can be examined. In instances where welds occur at fit-ting to fitting, access restrictions as outlined above occur on both sides of the weld. In instances where ultrasortic examinations cannot be performed on one hundred percent of the volume of the weld and head affected zone, surface examinations will be performed to supplement the limited volumetric examination.

10.

The ninety degrees elbqws 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 t'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? substitute for volumetric.

11.

The configuration of the reactor coolant branch nozzle connecti.on 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 nrn-2600, Item BS.l. Both the main flange and seal housing bolting will be examined as required by IWB-2600, Item B5.2 whenever a pump is disassembled for maintenance at the end of the ten-year interval when a pump will be disassembled for the performance required by Category B-L-1.

e e

15.

The structure and nature of the material of integrally welded pump supports are such that it is opaque to ultrasonic transmis-sion. Surface and visual examination will be performed as a substi-tute for volumetric.

16.

The reactor coolant pump casings in Surry Unit 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 it is op/1.que to ultrasonic trans-mission. Volumetric examination as required by TI?B-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 exten_t of examination that can be performed.

17.

Two of the pressurizer circumferential shell welds are not accessible for examination by volumetric or surface method due floor penetration and support structure interference. They will be subject to visual examination for evidence of leakage during system pressure-tests.

~.

I WESTINGHOUSE ELECiRIC CORPORATION FIGURE 1

STEAM GENERATOR PRIMARY NOZZLE SAFE~END TO PIPE WELD CONFIGURATION STEAM GENERATOR NOZZLE INTEGRALLY

. CAST WITH HEAD 11 BUTTEREDII SAFE-END WELD DEPOSITED CLADDING REACTOR COOLANT PIPE I

~ co '¢

i:

. a: 0 LL WESTINGHOUSE ELECTRIC CORPORATION - BRANCH NOZZLE CONNECTION WELD CENTERLHIE NOZZLE FIGURE 2 NOZZLE FORGING - REACTOR COOLANT PIPE .* I i

e TABLE IWC-2600 ITEM NO. Cl. 1 C 1. 1 Cl. l Cl. l Cl. l Cl. l Cl. 2 Cl.3 Cl.4 Cl. l Cl. l Cl. 2 Cl.3 Cl..4 Cl. l TABLE rnc-2s20 EXAMINATION CATETORY C-A-2 C-A C-A C-A C-A C-B C-B c-c C-D C-A C-A C-B C-C C-D C-A SYSTEM OR COMPONENT Steam Genera-rators (3) (Shell Side) 1-RC-E-lA 1-RC-E-lB 1-RC-E-lC Residual Heat

Exchangers (2)

(Tube Side) 1-RH-E-lA 1-RH-E-lB Regenerative T'T....,...,1,, 't:i'..,..... -1.-...... _........ -

~NIT 1 INSE~E INSPECTION ASME CODE CLASS 2 COMPONENTS CODE APPLICABLE TO CONSTRUCTION IIIA IIIC III-C AREA TO BE EXAMINED Upper Head to Shell Weld Upper Shell to Transition Weld Transition to lower shell weld Lower Shell to Stub barrel weld Stub barrel to tubesheet weld Steam Outlet Nozzle to shell weld Feedwater Inlet Nozzle to shell weld Integrally Welded Supports Manway Bolting Head to Shell Welds Shell to flange welds Nozzle to vessel welds Integrally Welded Supports Tubesheet Flange Bolting Head to shell welds (6)

EXAMINATION REQUIREMENT Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Not Applicable Visual and Volumetric Volumetric Volumetric Volumetric Surface Visual and Volumetric Volumetric SECTION XI CODE. RELIEF REQUESTED No No No No No No No No - Note 1 No No No Yes - Note 2 No No Yes -

suRRY UNIT 1 e

INSE.E INSPECTION ASME CODE CLASS 2 COMPONENTS

TABLE, TABLE IhD-2520 SECTION XI Iwd-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE-RELIEF ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED Cl.! 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. l C-A Excess Letdown III-C Head to shell weld Volumetric No Heat Exchanger (Tube side) Cl. l 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 - App_licable 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. l 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 I Cl. 3 C-C Integrally welded supports Surface No Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric

e ~NITl INS INSPECTION ASME CODE. CLASS 2 COMPONENTS TABLE . TABLE IhC-2520 SECTION XI rne'-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODI:: RELIE: ITEM NO. CATETORY 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) C 1. 1 C-A 1-CH-E-l 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. l C-A Volume Control III-C Upper Head to shell weld Volumetric No Tank c1.1

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 1-CH-FL-4A Head to shell weld Volumetric No 1-CH-FL-4B Cl. 2 C-B Nozzle to vessel welds Not No - Applicable Note 9 'J Cl.3 C-C Integrally Welded Supports Surface No Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric

e TABLE IWC-2600 ITEM NO. Cl. l Cl. l Cl. 2 Cl.3

Cl. 4 Cl. l Cl. l Cl.2 Cl.3

,Cl. 4 C2. l C2.2 C2.3 C2,4 TABliE n..D-2520 URRY UNIT 1 IN 1ICE INSPECTION ASME CODE CLASS 2 COMPONENTS EXAMINATION SYSTEM OR CODE APPLICABLE e EXAMINATION REQUIREMENT CATETORY cm::ilP:...'.:O::.N::E'...::N'...::T:__ _ __;T:_:O~C:::O~N:.::'.S~T::::RU.:::.:::.CT.:_:l:::.:O:::N::__ ___ _;A:.::RE=. :.:' A.:.....::T:..:O~B=E_;E=* X:.::AM:.=.:.:I:.::N~E:..::D:__ _______ _.::.. __ _ C-A Reactor Cool-ant Filter C-A C-B C-C C-D C-A C-A C-B C-C C-D C-F;C-G C-F* C-G C-F; C-G C-D 1-CH-FL-2 Seal Water Return Filter 1-CH-FL-3 Piping Systems III-C III-C Cover Weldment to shell weld Head to shell weld Nozzle to vessel welds

- Integrally Welded Supports Pressure Retaining Bolting Cover Weldment to shell weld Head to shell weld Nozzle to vessel welds Integrally welded supports Pressure Retaining Bolting Circumferential Butt Welds Longitudinal weld joints in fittings Branch Pipe to Pipe Welds Pressure Retaining Bolting Volinetric Volumetric Not Applicable Surface Not Applicable Volumetric Volumetric Not Applicable Surface Not Applicable Volumetric Volumetric Volumetric Visual and Volumetric SECTION X1 COUE RELIT REQUESTEI Yes -

Note 10 Yes - Note 10 No - Note 10 No No Note 10 Yes - Note 10 Yes - Note 10 No - Note 10 No No - Note 10 Yes - Note 11 No Yes - Note 12 No

TJRRY UNIT 1 IN UICE INSPECTION ASME CODE CLASS 2 COMPONENTS TABLE TAilLE I\\iC-2520 SECTION XJ rwe'-2600 EX.AMI NATION SYSTEM OR CODE APPLICABLE l*'.XM\\l. NATION CODE !{ELI[ ITEM NO. CATETORY COMPONENT TO CONSTRUCTION AREA TO rm EXAMINED REQUIH.EMENT EEQUESTEI 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 - Remov;;tl Pumps (2) Applicable Note 1~ 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 1~ C3.4 C-E-2 Support Components Visual No C3.. l C-D Charging Pumps (3) Pump Casing Welds Not No - Applicable Note 1~ C3.2 C-D 1-CH-P-lA Pressure Retaining Bolting Visual and No 1-CH-P-lB Volumetric 1-CH-P-lC C3.3 C-E-1 Integrally Welded Supports Not No - Applicable Note 1~ C3.4 C-E-2 Support Components Visual No C4.l C-F; 9-G Valves Valve Body Welds Not No - Applicable Note 1~ C4.2 C-D Pressure Retaining Bolting. Visual and* No Volumetric C4.3 C-E-1 Integrally Welded Supports .Not No - ii Applicable Note 1~ C4.4 C-E-2 Support Components Visual No

SURRY UNIT 1 INSERVICE INSPECTION ASHE CODE CLASS 2 COHPONENTS 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 II 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 11 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 ~xcessive 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 11 and 2 11 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 11 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 11 diameter and therefore requires no examination under this category.

7.

Seal Water Heat Exchanger nozzle to vessel welds are 4 11 diameter and the pres*sure retaining bolting is.75 11

diameter therefore they require no examination.under this category.

8.

Volume Control Tank nozzle to vessel welds are 4 11 and 3 11 diameter therefore require no examination under this category.

e

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 Return Filter nozzle to vessel welds are 3" diameter and the bolting is.75" diameter therefore no examination is required under these categories. The thickness of the materials (0.188" thick) used for the construction of these filters is such that meaningful results could not be expected with ultrasonic examination as required by IWC-2600. Surface and visual examination of these welds (Cover weld.ment 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 ai all locations. For pipe to fitti~g or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be dependent upon the geometric configura-tion. Where elbows or tees are concerned, examination can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examination can be performed from the fitting side when it is a valve or a flange. In all cases one hundred percent of the weld material can be examined. In instances where welds occur at fitting. to fitting acce.ss restric-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.

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. '¢ ~ c,: 0

u.

e WESTINGHOUSE ELECTRIC CORPORATION FIGURE 3 RESIDUAL HEAT REMOVAL HEAT EXCHANGER NOZZLE TO VESSEL CONFIGU8AILOJl.

,.....--._..-+-r-r,,/. CHANNEL HEAD FLANGE NOZZLE TO VESSEL WELD

~ 111 THICK REINFORCEMPH PAD ~ NOZZLE. 1 O" SCH 40S (TYPICAL OF THO) .875 11 THICK SHELL AND HEAD

IC 0 LL .*.. ~ WESTINGHOUSE ELECTRIC C RPORATIO BRANCH NOZZLE CONNECTION WELD CENTERLINE* NOZZLE Figure 4 NOZZLE FORGING

r.

PIPE

e -~** ~.-.* SURR_1-IT 1

INs Em*c~sPECTrnN ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE

_S_Y_S_TE_* M ______ D_E_S_C_R_I_PTION / lDEN.:.:..T:..:I::.::r;__;, I::..:. C:.:.A:.::T:.:.I:.:.O.::.;,N ______ c_oN_ST_R_U_C_T_I_O __ N _______ EXAf ll_N_A_T_I_O_N _______ R_E_L_I_E_F_RE_* Q-"-U_E_S_T_E_D Chemical and Boric Acid Tank 1-CH-TK-lA Volume Control Main Steam to Turbine Driven Auxiliary Feedwater Pump Auxiliary Feedwater Boric Acid Tank 1-CH-TK-lB Boric Acid Transfer Pump l-CH-P-2A Boric Acid Transfer Pump l-CH-P-2B Boric Acid Filter l-CH-FL-1 Boric Acid Blender l-CH-BL-1 Piping Supports and Hang~rs Piping Supports & Hangers Auxiliary Feed Pump l-FW-P-2 (rurbine Driven) Auxiliary Feed Pump l-FW~P-3A (Motor Driven) Auxiliary Feed Pump l-FW-P-3B (Motor Driven) I Auxiliary Feed Pump l-FW-P-2 Oil Cooler VIII Visual/Operating VIII IIIC Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating

Pressure Visual/Operating Pressure Visual/Operating Pressure

SYSTEM Auxiliary Feedwater Circulating and Service Water SURR.NIT 1 INSER'v:i:c/~NSPECTION ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT DESCRIPTION/IDENTIFICATION APPLICABLE TO CONSTRUCTION Auxiliary Feed Pump l-FW-P-3A Oil Cooler Auxiliary Feed Pump l-FW-P-3B Oil Cooler Condensate Storage Tank 1-CN-TK-lA

Piping Supports and Hangers Recirculation Spray Heat Exchanger 1-RS-E-lA (tube side)

Recirculation Spray Heat Exchanger 1-RS-E-lB (tube side) Recirculation Spray Heat Exchanger 1-RS-E-lC (tube side) Recirculation Spray Heat Exchanger 1-RS-E-lD (tube side) Component Cooling Water Heat Exchanger 1-CC-E-lA (tube side) Component Cooling Water Heat Exchanger 1-CC-E-lB (tube side) Emergency Service Water Pump 1-SW-P~lA METHOD OF EXAMINATION Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual /Oper_a ting Pressure Visual/Operating Pressure SECTION XI CODE RELIEF ~EQUESTED

SYSTEM Circulating and Service Water SlJRR~IT 1 INSERVrcZJSPECTION ~~~ ASHE CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE DESCRIPTION/IDEN~T~I~F_I_C_A_T_I_ON~~~~~~CO_N_S_T_R_U_C_T_I_O_N~~~~~~-E-~XAlv~_II_N_A_T_I_O_N~~~~~~~R_E_L_I_E_F_R_E_~Q~U_E_S_T_E_D Emergency Service Water Pump 1-SW-P-lB Emergency Service.Water Pump 1-SW-P-lC

Charging Pump 1-CH-E-SA Lubricating Oil Cooler Charging Pump 1-CH-E-SB Lubricating Oil Cooler Charging Pump 1-CH-E-SC Lubricating Oil Cooler Charging Pump l-CH-E-7A Seal Cooler Charging Pump 1-CH-E-7B Seal Cooler Charging Pump l-CH-E-7C Seal Cooler Charging Pump 1-CH-E-7D Seal Cooler Charging Pump 1-CH-E-7E Seal Cooler Charging Pump l-CH-E-7F Seal Cooler Charging Pump Seal Cooling Surge
Tank l-CC-TK-3 Charging Pump Cooling Water Pump 1.:..cc-P-2A

,I Charging Pump Cooling Water Pump l-CC-P-2B Visual/Operating Pressure Visual/Operating Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Visual/Operating .Pr:essure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure

~m':..&l'Ll. .

INSERVIC:f ~'i?i~CTION _

ASME COD!~ CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI Cc5DE SYSTEM DESCRIPTION/IDENTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED

--------------------------------------------~----

Circulating Charging Pump Intermediate Seal Cooler Visual/Operating and Service 1-SW-E-lA Pressure Water Component Cooling Water Charging Pump Intermediate Seal Cooler 1-SW-E-lB Charging Pump Service Water Pump 1-SW-P-lOA Charging Pump Service Water Pump

1-sw-P-lOB Recirculation Spray Hx Radiation Monitori-ing Sample Pump l-SW-P-5A Recirculation Spray Hx Radiation Monitro-ing Sample Pump 1-SW-P-5B Recirculation Srpay Hx Ra4iation Monitor-ing Sample Pump 1-SW-P-5C Recirculation Spray Hx Radiation Monitor-ing Sample Pump 1-SW-P-SD Piping Supports and Hangers Reactor Coolant Pump 1-RC-P-lA Oil Cooler Reactor Coolant Pump 1-RC-P~lB Oil Cooler

i Reactor Coolant Pump 1-RC-P-lC Oil Cooler Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure

SURRY_&!T l INSERVI~CI~~PECTION ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT APPLICABLE TO METHOD OF SECTION XI CODE _S_Y_S_T_E1'_1 ______ D_E_S_CR_IP_. T_IO N / IDE N-=T-=I=-F-=I..:.C:.:AT::::.-=..IO.:.:N::.;__ ____ __:C...:;O.:..N...:;S...;.T_;.;R_U_CT-=-I-=-O~N:_:__ _______ E_XAlv_l_IN_A_T_I_O_N _________ I_rn_, L_I-:-E_P_R_E_Q,_U_E_S1_'I_m Component Cooling Water Reactor Coolant Pump 1-RC-P-lA Shroud Cooling Coil l-VS-E-6A Reactor Coolant Pump 1-RC-P-lB Shroud Cooling Coil l-VS-E-6B Reactor Coolant Pump 1-RC-P-lC Cooling Coil l-VS-E-6C Excess Letdown Heat Exchanger l-CH-E-4 (shell side) Residual Heat Removal Pump Seal Cooler l-RH-E-2A Residual Heat Removal Pump Seal Cooler l-RH-E-2B Residual Heat Removal Heat Exchanger 1-RH-E-lA (shell side) Residual Heat Removal Heat* Exchanger l~RH-E-lB (shell side) Reactor Containment Air Recirculation Cooler l-VS-E-2-A Reactor Containment Air Recirculation Cooler l-VS-E-2~B Reactor Containment Air Recirculation Cooler l-VS-E-2-C Fuel Pit Cooler 1-FC-E-lA (shell side)

/

Fuel Pit Cooler 1-Fc.:..E-lB (shell side) VIII VIII VIII Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Op.era ting Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating* Pressure Visual/Operating Pressure

SYSTEM Component Cooling Water Fuel Pit Cooling SURRY-IT 1. INSERVJ:.cE4!sPECTI0N ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT DESCRIPTION/IDENTIFICATION APPLICABLE TO CONSTRUCTION Non Regenerative Heat Exchanger l-CH-E-2 (shell side) Seal Water Heat Exchanger 1-CH-E-l (shell side) Component Cooling Surge Tank 1-CH-TK-1 . Component Cooling Pump 1-CC-P-lA Component Cooling Pump 1-CC-P-lB Component ~oo1tng Water Heat Exchanger 1-CC-E-lA (shell side) Component Cooling Water Heat Exchanger 1-CC-E-lB (shell *side) Piping Support and Hangers Spent Fuel Pit Pump 1-FC-P-lA Spent Fuel Pit Pump 1-FC~P~lB Spent Fuel Pit Cooler 1-FC-E-lA (tube side) VIII VIII METHOD OF EXAMINATION Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual Visual/Operating Pressure* Visual/Operating Pressure Visual/Opera~ing Pressure SECTION XI CODE IH:LIEF IrnQUESTED

e SURR *. NIT 1 INSERVIC .NSPF.CTION ASME CODI~ *CT.,i\\SS 3 COMPONENTS CODE COMPONENT APPLICABLE. TO METHOD OF SECTION XI CODE DESCRIPTION/lDf.NTIFICATION CONSTRUCTION EXAMINATION RELIEF REQUESTED --~-----'-------

'-----'----------------------------o.__ __

SYSTEM .Fuel Pit Cooling Spent Fuel Pit Cooler 1-FC-E-lB (tube side) Piping Support and Hang*ers Visual/Operating Pressure Visual/Operating Pressure Visual

e ATTACHMENT B SURRY UNIT 1 REQUESTED RELIEF FRON THE INSERVI CE TESTING REQUIREMENTS FOR PUHPS AS SET FORTH IN SUBSECTION IWP TO SECTION XI OF THE ASHE BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THROUGH THE Sill'fr1ER 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 AS1"1E Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975. This tabulation identifies the pumps to be tested, code class, test flow path system resistance, and required test quantities and frequencies. Relief from test requirements is requested in cases where their test requirements have been determined to be impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable.

e PUMP HARK PUMP CODE NUMBER. DESCRIPTION CLASS 1-CH-P-.lA High Head 2 1-rn-r-rn Safety Injection 1-CH-P-JC (Charging) (Dwg. No. 11448-FM-88B) 1-SI-P-lA Low Head 2 1-SI-P-lB I Safety Injection (Dwg. No. 11448-I FM-89A) 1-CS-P-lA Containment Spray 2 1-CS-P-lB (Dwg. No. 11448-FM-84A) 1-RS-P-2A Outside Recirc-2 1-RS-P""2B ulation Spray (Dwg. No. 11448-FM-84A)

1 SURR~IT 1 INSERVIi!'TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS SYSTEM RESIS-TANCE TEST QUANTITIES Speed (if variable)

FIXED o VARIABLl~ Inlet Pressure (Pi) (NOTE 2 Differential Pressure (t,P) Flow Rate (Q) Vibration Amplitude (V) Bearing T~mperature (Tb) Lubricant Level or Pressure FIXED Speed (if variable) Inlet Pressure (Pi) Differential Pressure (tiP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure FIXED Speed (if variable) Inlet Pressure (Pi) Differential Pressure (AP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tl1) Lubricant Level or Pressure

FIXED.

Speed (if variable) Inlet Pressure (Pi) D~fferential Pressure (t, 11) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure TEST RELIEF FREQUENCY REQUESTED REMARKS NA CONSTANT Monthly YES-NOTE 1 Monthly Monthly NOTE 2 Monthly Yearly Monthly NA CONSTANT Monthly YES-NOTE 3 NA Monthly Monthly NA NOTE 4 NA NOTE 4 NA CONSTANT Monthly NA Monthly Monthly Yearly Monthly NA CONSTANT NA Yes-Note 5 .. Monthly* NA Monthly NA Note 4 NA Note 4

PU}!P MAl,\\K PUMP CODE NUNBRR hESCRIPTION r.LASS 1-RS-.P-IA Inside Recircu-2 l-RS-P-ll3 lation Spray (Dwg. No. 11448-FM-84A) 1-FW-P.-3A Auxiliary 3 1-FW-P-3B Feedwater l-FW-P-2 (Dwg. No. 11448-F11-68A) 1-RH-P:* lA Residual Heat 2 1-RH-P-IB Removal (Dwg. 11448-FM-87 A) 1-CC-P-:-lA Component Cooling 3 1-cc-P~ IB (Dwg. No. 11448-FM-72D)

j SURRY8IT 1 INSERVI~TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS SYSTEM RESIS-TANCE TEST QUANTITIES FIXED Speed (if variable)

Inlet Pressure (Pi) Differential Pressure (6P) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant 'Level or Pressure FIXED Speed (if variable) Inlet Pressure (Pi) Differential Pressure (LIP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure FIXED o* Speed (if variable) VARIABL, Inlet Pressure (Pi) (Note 8 Differential Pressure (Id'). Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level*or Pressure VARIABL*: Speed.(if ~ariable) Inlet Pressure (Pi) Differential Pressure (iP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure TEST RELIEF FREQUENCY REQUESTED RE1'fARKS NA CONSTANT NA Yes-Note 6 NA NA Yes-Note 6 NA Yes-Note 6 NA Note 4 NA Note 4 NA CONSTANT Monthly Monthly NA Monthly Yearly Honthly NA CONSTANT Refueling Yes-Note 7

~efueling Yes-Note 7

- ** Refueling Yes-Note 7 Note 8 ~efueling Yes-Note 7 NA Note 4 NA Note 4 NA CONSTANT Monthly Yes-Note 9 Monthly Yes-Note 9 i"1onthly Yes-Note 9 Monthly Yea,rly Monthly

e SURR)i.NIT l . INS ERV c

TESTING.

ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RESIS-TEST RELIEF NUl'IBER DESCRIPTION CLASS TANCE TEST QUANTITIES .FREQUENCY REQUESTED REMARKS 1-CH-P-2A Boric Acid 3 FIXED Speed (if variable) NA CONSTANT . l-CH-P-2B Transfer Inlet Pressure (Pi) rlonthly Yes-Note 10 (Dwg. No. 11448-Differential Pressure (LIP) Monthly FM-88A) FlC?W 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 CONSTANT 1-CC-P-2B Cooling Water Inlet Pressure (Pi) NA Yes-Note 11 (Dwg. No. 11488-Differential Pressure ( tiP) NA FM-71B) Flow Rate (Q) Monthly Vibration Amplitude (V) Monthly 1 I Bearing Temperature (Tb) NA Note 12 Lubricant Level or Pressure NA Note 12 1-SW-P-lOA Charging Pump 3 VARIABLl Speed (if variable) NA CONSTANT 1-SW-P-lOB Service Water Inlet Pressure (Pi) NA

Yes-*Note 13 (Dwg. No. 11448-D~fferential Pressure (AP)

NA Yes-Note 13 FM-71B) Flow Rate (Q) Monthly Vibration Amplitude (V) Honthly I Bearing Temperature (Tb) NA Note 12 Lubri~ant Level or Pressure NA Note 12 I 1-SW-P:-lA E~ergency Service 3 FIXED Speed (if variable) Monthly Variable 1-S,,FP:-1B Water (Dwg. No. Inlet Pressure (Pi) Monthly Yes~Note 14* 1-sw-P~1c 11448-FM-71A) Differential Pressure (6P) Monthly Flow Rate (Q) NA Vibration Amplitude (V)

}fonthly Bearing Temperature (Tb)

NA Note 15

I Lubricant Level or Pressure Mon.thly Yes-Note 15

) e SURRY.IT 1 P~g-INSERVI TESTING ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM

MARK PUMP CODE RESIS-TEST RELIEF NUHJ3ER nr.s C:RIPTION C:LASS T/\\NCE TEST QUANTITIES FREQUENCY REQUESTED.

REMARKS 1-SW-P-SA Recirculation 3 FIXED Speed (if variable) NA CONSTANT 1-SW-P-SB Spray Hx Radia-Inlet Pressure. (Pi) NA Yes-Note 16 1-SW-,P-SC tion Monitoring Diff e-rential Pressure (LIP) NA Yes-Note 16* 1-SW-P-SD Sainple Flow Rate (Q) NA Vibration Amplitude (V) NA Yes-Note 16 NA Yes-Note 16

Bearing Te_mperature (Tb)

NA Yes-Note 16 Lubricant Level or Pressure Speed (if variable) Inlet Pressure (Pi) Differential Pressure (tiP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure Speed (if variable) Inlet Pressure (Pi) Differential Pressure (AP) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) Lubricant Level or Pressure Speed (if variable) Inlet Pressure (Pi) Differential Pressure (ti P) Flow Rate (Q) Vibration Amplitude (V) Bearing Temperature (Tb) ,I Lubricant Level or Pressure I

e SURRY UNIT 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 and 3 PUMPS NOTE

1.

Suction pressure instrumentation is not installed nor required.. There pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure is nominally 15 to 20 psig. Therefore, the L1P 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 obser.ve VCT pressure using control room indication to assure repeated initial conditions for testing the pumps. This indication is approximately 4% accurate.

2.

When the nonoperating pump is tested on recirculation flow, the

3.

flow path is a fixed resistance system and it is required to measure L\\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 L\\P and Q. 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 shall be dry tested quarterly as required by proposed T.S. 4.5.A.2 (Change No. 66). Since these pumps take suction from the containment sump and discharge thru the spray headers, it is not practical to perform periodic flow testing.

7.

It is considered impracticle to make a containment eritry on a monthly basis in order to test these pumps. These pumps are not Engineered Safety Feature pumps. Operability during use can be determined by monitoring reactor coolant system temperature. Testing as required by subsection IWP will be performed during each refueling outage.

8.

When the pump is tested on recirculation flow, the path is a fixed resistance system and it is required to measure L\\P or Q, not both (Table IWP-3100-1). When the pump is tested while pumping through the Reactor Coolant System, the flow path is a variable resistance system and it is required to measure both L\\P and Q.

e SURRY UNIT 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 and 3 PlfrlPS NOTES cont'd.

9.

Flow rates from these pumps vary 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 for 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 bearing~ are carried in the driver motor and are grease lubricated.

13.

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.

14.

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 piessure 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.

16.

The flow path of these pumps is normally dry due to a commitment of not introducing service water to the recirculation spray heat exchangers. Also no pressure measuring instrumentation is provided. During each refueling the pumps will be started to verify shaft rotation.

. e ATTACHMENT C SURRY UNIT 1 REQUESTED RELIEF FRON THE INSERVICE TESTING REQUIREHENTS FOR VALVES AS SET FORTH IN SUBSECTION IWV TO SECTION XI OF THE ASHE BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THRU THE SUHHER OF 1975 (LAST flO 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 ASHE Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975. This tabulation identifies the valve to be tested, drawing location; function, code class, category, size, valve type, actuator type, normal position a_nd test requirements. Relief from test requirements is requested in cases where these test requirements have be~n 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 ASHE Section XI subsub-article IWV-3420. There are no testable Category D valves in Surry Unit 1 Systems. Any inspection requirements identified as impractical during the course of the inspection period will be noted and included in the inspection program at the time of the next revision. When one valve in a redundant safety related system is found inoperable during testing, nonredundant valves in the remaining train will not be cycled as procedures require but will be cycled after the first inoperable valve in the system is returned to service. This valve testing program addresses those valves for which demonstration of operability is necessary to assure safe shutdown of the unit *or mitigation of the consequences of an accident. The program has been reviewed to assure-that testing the valves at the intervals specified will not place the plant in an unsafe condition. Where practical, valves will be cycled at 3 month test intervals. When a commitment is made to test valves during hot or cold shutdown it is not intent to shutdown the unit solely for the purpose of valve testing nor to perform the testing more often than once per 92 days due to more frequent shutdowns. The following clarification shall apply to those valves which are scheduled to be exercised during cold shutdown: "Valve testing shall commence not later than 48 hours after reaching cold shutdown and continue until complete or unit is ready to return to power. Completion of all valve testing is not a prerequisite to return to power."

e TEST REQUIREMENTS SURRY UNIT 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 Ai'ID 3 VALVES LEGEND SP - SETPOINTS of safety and relief valves shall be tested per Section XI subsubarticle IWV-3510 or as modified by specific relief request. VP - VALVE POSITION shall be verified per Section XI subarticle IWV-3700 or as modified by specific relief request. CV - CHECK VALVES shall be exercised at least once every (3) months per Section XI subsubarticle IWV-3520 or as modified by specific relief request. LT - LEAK TESTS shall be performed per Section XI subsubarticle 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 TINES shall be measured per Section XI subsubarticle IWV-3410 or as modified by specific relief request. VALVE POSITIONS 0-0pen C-Closed QC-Open or Closed T-Throttled VALVE TYPES CK-Check RE-Relief SF-Safety BA-Ball GL-Globe GA-Gate BU-Butterfly SCK-Stop Check PL-Plug ACTUATOR TYPES SA-Self Actuating t10-Motor PN-Pneumatic HW-Handwheel

e

suRRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:..._ ____

MA_I_NS_T_E_A_M ________ _ DRAW. NO. _____ 1_1_4_4_8_-F_M_-_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 ITYPE TION SV-MSI01A, B, C B-3,B-4,B-6 Main Steam Safety Valves 2 C 4 SF SA C SP NO SV-HSI02A,B,C C-3,C-4,C-6 Main Steam Safety Valves 2 C 6 SF SA C SP NO SV-MS103A,B,C B-3,B-4,B-6 SV-MSI04A,B, C B-3.B-4.B-6 SV-l'-18105A, B, C C-3,C-4,C-6 TV-:-MS101A,B,C D-3,D-5,D-7 Main Steam Line Trip Valves 2 B 30 CK PN 0 EV YES ST (1) PCV-MSI02 F-8 Main Steam to Turbine Driven 3 B 3 GL PN C EV NO Auxiliary Feedwater Pump ST MOV-MSI02 G-8 Main Steam to Turbine Driven 3 B 3 GA MO C EV NO Auxiliary Feedwater Pump ST 1-MS-17 6, 178, F-8,F-8,F-8 Main Steam to Turbine Driven 3 C 3 CK SA C CV NO 1.82 Auxiliary Feedwater Pump Check Valves NRV-MS102A,B,C D-3,D-S,D-6 Main Steam Non-Return Valves 2 C 30 SCK no 0 CV YES (1) TV-MS109 F-7 Main Steam Drain to B 3 GA PN 0 CV. NO Condenser ST TV-MSllO E-7 Main Steam Drain to .B 2 GA PN 0 CV NO Blowdown ST I

e SURRY. 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME AUX. STEAM & AIR REMOVAL DRAW. NO, VALVE DR.t.1.W, CODE CATE-NUHBER

LOCN, FUNCTION CLASS GORY TV-SVI02 L-2 Air Removal Divert A

to Reactor Containment 1-VP-12 L-1 Air Removal Divert AC to Reactor Continment .i I I 11448-FM-66A SIZE VALVE ACTUA-NORJvlAL (IN I) TYPE TOR POSI-IllL-.. JJ..QJ;!_, 6 GA PN C 6 CK SA C e TES REQ PAGrf ~ Rf.LIEF , I 1ZEQUES1 ~...,.~~ L E s L C T NO V T T V NO

SYSTEM NAME FEED WATER VALVE DRAW. NUMBER LOCN. 1-FW-27,58,89 C-2,B-4,B-5 l-FW-10,12, c-2,c-2 41,43, C-4,C-4, 72, 74 C-5,C-5 MOV-FW151A,B,C, B-6,B-6, D,E,F B-6,B-6, C-6,C-6 l-FW-131,133, C-6,C-6, 136,138 C-6,C-6 l-FW-142,157, D-7,E-7 172 F-7 SURRY.T 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES DRAW.NO. CODE CATE-FUNCTION CLASS GORY Auxiliary Feedwater Header 2 C Check Valves at Main Feedwater Header Main Feedwater Check Valves 2 C at Containment Penetrations Auxiliary Feedwater to 3 B Steam Generators Auxiliary Feedwater Header 3 C Check Valves at Containment Penetration Auxiliary Feedwater Pump 3 C Discharge Check Valves 1 i I 11448 FM 68A PA Gt 3 -- SIZE VALVE ACTUA-NORMAL TEST RELIEF (IN.) TYPE TOR POST-REQ. REQUES1 TYPE ,TIQN....,.,. L,k~- 3 CK SA C CV* YES (2) 14 CK SA 0 CV YES (3) 3 GL MO 0 EV NO ST 6 CK SA C CV YES (2) 6 CK SA C CV YES (2) l i

SURRY. l INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CROSS-CONNECTS FOR AUXILIARY FEED VALVE NUMBER HOV-FW160A,B 1-FW-272,273 l-FW-309,310 DRAW.

LOCN, J-5 J-6 I-7,I-7 H-7,H-7 FUNCTION Cross-Connects for Unit No.. 1 Aux. Feed from Unit No. 2 Cross-Connect for Unit No. 1 Aux. Feed from Unit No. 2 Check Valves at Cont. Penet.

Cross-Connect for Unit No. 1 Aux. Feed from Unit No. 2 Check Valves

DRAW. NO, CODE CATE-CLASS GORY 3

B 3 C 3 C SIZE (IN.) 6 6 6 e 11448-FM-68B PAGrf VALVE ACTUA-NORMAL RELIEF TEST TYPE TOR POSI-REQ.

REQUES1 mJL._.J:.lQf.......,

... *-* ~ff'O:~ GL MO C EV NO ST CK SA C CV YES (2) CK SA C CV YES (2).*

SYSTEM NAME SERVICE WATER L V/\\.LVE

DRAW, NUMDER LOCN.

MOV-CWI06A,B, E-4,E-4, C,D F-4,F-4 HOV-SW102A,B E-6,F-6 HOV-SW103A,B, B-6,B-6 C,D D-6,E-6 HOV-SW104A,B, A-2,B-2,C-2, C,D C-2,A-2,A-2, HOV-SWI05A,B, B-2,C-2 C,D MOV-SW106A,B D-4,D-4 HOV-SWIOIA,B B-4C-4

I Tr.

SURRY -T 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 AND 3 VALVES DRAW NO CODE ', CATE-* FUNCTION CLASS GORY Condenser Inlet 3 B Isolation Valves Service Water to Component 3 B Cooling Water Heat Exchangers Service Water to Recircula-3 B tion Spray Heat Exchangers Recirculation Spray Heat 3

B Exchangers Isolation Valves Recirculation Spray Heat 3

B Exchangers Cross Connect. Valves Bearing Cooling Water 3 B Heat Exchanger Isolation Valves 11448-FM-71A 'T SIZE V/\\.LVE ACTUA-NORMAL TEST RELIEF (IN,) TYPE TOR POSI-

REQ, REQUES1

.r..xl.:L-.. Jl.Q] =- 96 BU MO 0 EV NO ST 42 BU 110 0 EV. NO ST 30 'BU MO C EV YES ST (4) 24 BU MO 0 EV NO ST 36 .BU. MO 0 EV NO ST 36 BU HO 0 EV NO ST I I

,':f,. SURRY eT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME ----------------~- CIRCULATING & SERVICE WATER

DRAW. NO, VALVE

DRAW, CODE

'* CATE-NUNBER

LOCN, FUNCTION CLASS GORY 1-CC-764,752 D-6 G-6 Charging Pump Cooling Water_

3.

C Pump Discharge Check Valve 1-SW-113, 108 D-8,G-8 Charging Pump Service Water 3 C Pump Check VAlve

I 11448-FM-71B SIZE VALVE ACTUA-NORMAL (IN.)

TYPE TOR P.OSI-I~ ..J:l.Qlt.- 2 CK SA oc 2 CK SA oc TEST REQ. CV CV 6 PAGE RELIEF REQUES1 ~; NO NO (

I SURRY-T 1, INSERV!CE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SY STEM N AME ____ Gh'IO-lt'HwPttQ},,.,ffil',,f'}tttT-G01-1tO-r1-L..+I.;,i.NM"G -.\\lf+l*lA..... 'f....,ER---- DRAW. NO *-----l-1-ilfo'-4,..;.4-l',-8-iF<.f'M.-....-72.,L,i,A,....l ~- VALVE

DRAW, CODE CATE-SIZE VALVE i\\CTUA-NOH.,>vfAL NUNI3ER

LOCN, FUNCTION CLASS GORY (IN,)

TYPE TOR POSI-

-~..

......u~*t 1111i,e,t,ee,..,.......... TDX-. ... 'LI;Q.IL. RV-CC119A,B L-2,L-3 Component Cooling from RHR 3 C 1\\ RE SA C Heat Exchanger Relief Valve 1-CC-176,177 B-1,B-1 Component Cooling to RHR Heat 3 C 18 CK SA oc Exchanger Check.Valves 1-CC-1,58,59 A-2,A-2,A-2 Component Cooling to REactor 3 C 6 CK SA 0 Coolant Pumps TV-CC105A,B,C D-8,D-8,E-8 Component Cooling from

3.

B 6 BA PN 0 Reactor Coolant Pumps TV-CC107 D-8 Component Cooling from 3 B 2\\ GL PN 0 Reactor Coolant Pumps TV-CC109A,B F-8,F-9 Component Cooling from 3 .B 18 BU PN 0 RHR Heat Exchangers

i PAGE-+--

TEST RELIEF REQ. 1ZEQUES1 ~ .. tK'ft'wllJl:l:rr... '11A'I\\.~ SP NO. CV YES (5) CV YES (6) EV YES ST (6)

EV YES ST (6)

EV NO ST

e SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:__ ____ co_l"._IP_O_NE_NT_c_o_o_L_IN_G _____ _ DRAW. NO. -------------'---- 11448-FM-72B r VALVE

DRAW, CODE CATE-SIZE VALVE ACTUA-NORMAL Nl]}1BER LOCN.

FUNCTION CLASS GORY (IN.) TYPE TOR POSI-T.YPF. TION 1-CC-242,233, C-4,E-4,I-4 Component Cooling to 3 C 6 CK SA 0 224 Reactor Containment Air Recirculation Coolers TV-CCllQA,B,C D-3,F-3,H-3 Component Cooling from 3 B 6 BU PN 0 Reactor Containment Air Recirculation Coolers RV-CC112A,B, C E-5,F-S;G-5 Component Cooling from 3 C 3/4 RE SA C Reactor Containment Air Recirc. Coolers Relief

j P i\\GE 8 TEST RELIEF REQ.

REQUES1 CV YES (7) EV NO ST SP NO I I

SYSTEM NAME COMPONENT COOLING SURRY..1 INSERVICE TESTING ASME CODE CLASS 1,, 2 AND 3 VALVES

DRAW. NO, VALVE DRAW.

CODE CATE-NUN13ER

LOCN, FUNCTION CLASS GORY RV-CClllA,B I-3,1-4 Component Cooling to Fuel 3

C Pit Coolers RElief Valves

I 11448-FM-72C SIZE VALVE ACTUA-NOH.NAL TEST Rf.LIEF (IN.)

TYPE TOR POSI-

REQ, REQUES1 I.XU__..J:1.QN 3/4 RE SA C

SP NO

I SYSTEM NAME COMPONENT COOLING SURRY. 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES DRAW. NO, VALVE DR.Ahl, CODE CATE-NUNBER

LOCN, FUNCTION CLASS GORY 1-CC-557,563 C-2,C-2 Component Cooling Pump 3

C Discharge Check 11448-FM-72D SIZE VALVE ACTUA-NORMAL (IN,) TYPE TOR ):'O~I-I.W..i.......-..J;J,QJL *..., 18 CK SA oc TES REQ 10 PAtE T RELIEF REQUES1 C V NO

e SURRY UN,1 e INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SPENT FUEL PIT COOLING 11448-FM-81A . 11 SYSTEM NAME DRAW.NO. P/1..CE -- VALVE

DRAW, CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEI<'

NUMBER

LOCN, FUNCTION CLASS GORY*

(IN.) TYPE TOR POSI-REQ. REQUES'1 ~ TION h--==,11'1'.J 1-"J*c-~, 11 U-7,E-/ Spent..11uel.l:'it CooTing 3 C l:Z. CK . UC *=-=rv, Pump Discharge Check I

SURRY UN.1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SAMPLING 11448-FM-82B SYSTEM NAME ---------------- DRAW. NO. ____________ _ VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL Nill1BER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-TYP"R TION TV-SS103 E-1 Residual Heat Removal 2 A 3/8 Gl PN oc System Sample TV-SSlOOA, B D-1,E-1 Pressurizer Liquid 1 A 3/8 GA PN oc Space Sample TV-SS101A,B D-1,E-1 Pressurizer Vapor 1 A 3/8 GA PN oc Space Sample TV-SS106A,B D-2,E-2 Primary Coolant Hot 1 Leg Samples A 3/8. GA

PN oc TV-SS102A,B D-2,E-2 Primary Coolant Cold 1

Leg Samples A 3/8 GA PN oc TV-SS104A,B D~2 E-2 Pressurizer Relief Tank A 3/8 GA PN oc Gas Space Sample ,j TEST REQ. LT EV ST LT EV ST LT EV ST LT EV ST LT EV ST LT EV . 1.2 PAGE RELIEF REQUES'I NO NO NO NO NO NO

.SURRY A1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM,NAME 5lENTS & DRAINS DRAW.NO. JlM8-EH-83i\\ Pi\\GE --1-3-- VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES1 T..Yl'..L-. IION '..Ai =-ivm~ TV-DAlOOB A-8 R. C. Sump Pump A 2 GA PN oc LT NO Discharge Isolation EV ST 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 I

VENTS & DRAINS SURRY. 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME ________________ _ 11448-FM-83B DRAW. NO*-----'---------- VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL NillfBER LOCN. FUNCTION CLASS GORY (IN,) TYPE TOR POSI-lYP.]. * *, TION TV-DAlOOA I-8 R. C. Sump Pump A 2 Gl PN oc Discharge Isolation TV-DG108A L-5 Pr. Dr. Transfer Pump A 2 GA PN oc Disch. Isolation TV-VG109A L-2 Gas Vent Hdr. Isolation A 2 GA PN 0 ) TEST RELIEF REQ. REQUES1 LT NO EV ST. LT NO EV ST LT NO EV ST

SURRY. 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CONTAINMENT & RECIRCULATION SPRAY SYSTEM NAME. _________________ _ 11448-FM-84A DRAW. NO. _____________ _ VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL NlTMBER LOCN. FUNCTION CLASS GORY (IN,) TYPE TOR POSI-

rypr,:

TIOL'l MOV-RS155A,B f-8,F-8 Recirculation Spray Pump 2 A 12 PL MO 0 Suction from Containment Sump MOV-RS156A,B F-6 F-6 Recirculation Spray 2 A 10 GA MO 0 Pump Discharge l-RS-11, 17 F-6,F-6 Recirculation Spray Pump 2 AC 10 CK SA C Discharge Check Valves

noV-CSlOlA,B, F-2,F-2, Containment Spray Pump 2

A 8 GA MO C C,D F-1,F-1 Discharge 1-CS-13 24 E-2,E-1 Containment Spray PUmp 2 AC 8 CK SA C Discharge Check Valves MOV-CS'l02A,B J-3,K-3 Chemical Addition Tank 2 B 6 GA MO C to RWST Isolation Valve L PACE lS TEST RELIEF REQ. REQUES1 LT NO EV ST LT NO EV ST CV YES LT (8) LT NO EV ST CV YES LT (8) EV NO ST

. SU~RY lllil 1 INSERVICE TESTING ASME CODE CLASS 1, 2.AND 3 VALVES SYSTEM NAME _____________ __;_ __ _ CONT. VACUUM & LEAKAGE MONITORING DRAW. NO*-----------~- 11448-FM-85A VALVE

DRAW, CODE CATE-SIZE VALVE ACTUA-NORMAL NU1'fJ3ER LOCN.

FUNCTION CLASS GORY (IN,) TYPE TOR POSI-lY~-* J:ION TV-LMIOOA,B E-3,E-3,E-3, Open Pressure System A 3/8 GA PN C C,D,E,f,G,H E-3,E-3,E-3, Isolation D-3,E-3 TV-LHIOIA,B H-4,I-4 Closed Pressure System A 3/8 GA PN C Isolation HCV-CVIOO J-5 Cont. Vacuum Air Ejector A 8 GA PN C Isolation TV-CV-ISOA,B, H-7,H-7, Cont. Vacuum Pump A 2 GA PN 0 C,D H-8,H-8 Suction Isolation i

. 16.

PAGE TEST RELIEF REQ,. REQUES1 LT NO EV ST LT NO EV ST LT NO EV ST LT NO EV ST

e REACTOR COOLANT SYSTmI. NAME ________ 'VALVE DRAW. NUMBER LOCN. SV-1551A,B,C F-4 G-4 H-4 TV-1519A A-6 l-RC-160 D-6 SURRY uAt1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CODE CATE-FUNCTION CLASS GORY Pressurizer Safety Valves 1 C Primary Grade Water to A PRZ Relief Tank Primary Grade Water to AC PRZ Relief Tank 11448-FM-86B SIZE VALVE ACTUA-NOR.HAL (IN.) TYPE TOR POSI- ~ TIO:N 6 SF SA C 3 GA PN C 3 CK* SA C TEST REQ. SP LT EV ST LT CV . 17 PACE RELIEY REQUES1 NO NO NO

RESIDUAL HEAT REMOVAL SURRY a 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME ------------------ VALVE DRAW. CODE CATE-NUNBER LOCN. FUNCTION CLASS GORY MOV-1700,1701 H-7,H-7 RHR Suction from Reactor 1 B I Coolant System MOV-1720A,B K-5,K-S' RHR Discharge to Reactor 1 B Coolant System RV-1721 I-4 RHR System Relief Valve 2 C l-RH-5., 11 D-6,B-6 RHR Pump Discharge Check 2 C Valve I 11448-FM-87A . 18 PAGE SIZE VALVE ACTUA-NORMAL TEST RELIEF (IN.) TYPE TOR POSI-REQ. REQUES'I ITYP ;,.,..._, ~ 14 GA MO C EV YES ST (9) 10 GA MO C EV YES ST (9) 3 RE SA C SP YES (10 ) 10 CK SA C CV YES (11)

SURRY m9 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME ------------- CHEMICAL AND VOLUME CONTROL DRAW. NO. VALVE DRAW. CODE CATE-NUMBER LOCN. FUNCTION CLASS GORY l-CH-76,92 C-7,D-7 Boric Acid Transfer Pump 3 C Discharge Check Valves 11448-FM-88A SIZE VALVE ACTUA-NORMAL (IN.) TYPE TOR POSI-l'T'YPE TJON 2 CK SA 0 e TEST REQ.

19 PAGE RELIEF REQUES1
-cv,~NO

e SURRY.UN.1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYS Tm! Ni\\NE. ____ .::'.;c1~m;!!:,,l'.!..:1I:c..:aC::!.cA~L!.....:2:AN!!cD~VDO~Lt~U'""M!.!=EC-S<C.lal.ONu.1,.,'R...,O.,.,L..__ . VALVE NUNBER DRAW

LOCN.

FUNCTION CODE CLASS DRAW, NO

____

......:..JJwJ...;14c=1LfcU8c:::-.i:.Fw.Mc::..-8°'80'JPL.l---- CATE-. SIZE VALVE ACTUA-NORMAL GORY (IN.) TYPE TOR POSI-e TEST REQ. PA~l(}__* RELIEF REQUES1 11----------1-~-----i---,.-------------..i-----1,----1-----1----1J.lUi--.. J.,l,~O~N_...et-....... =-=rt--*""""--i l-CH-258,267, 276 , LCV-1115B,D LCV-l 115C,E MOV-l.275A,B,C MOV-1373 MOV-1381 D-6,F-6 G-6 C-9,C-9 H-3,H-3 D-6,F-6,H-6 F-5 A-3 Charging Pump Discharge Check Valve Charging Pump Suction from Refueli~g Water Storage Tank Charging Pump Suction from Volume Control Tank Charging Pump Recirculation Flow Path Isolation Charging Pump Recirculation Header Stop Valve Reactor Coolant Pump Seal Water Return 2 C 3 2 B 8 2 B 4 2 B 2 2 B 3 2 A 3 CK SA oc GA MO C GA MO 0 GA MO 0 GA MO 0 GA MO 0 CV EV ST EV ST EV ST EV ST LT EV ST NO NO YES (12) NO YES (13) YES (14)

e SURRY UNIT 1 INSERVICE TESTING S SS 1 A 3 VA S A ME CODE CLA

2 ND LVE CHE~ICAL AND VOLUME CONTROL DRAW. NO.

11448-FM-88B 21 SYSTEM NAi"'1E PJ\\GE -- VJ\\LVE _ DRAW. CODE CATE-SIZE VALVE ACTUA-NOR!'!AL TEST RELIEF NUNBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUEST I TYPT<'. TION I TV-1204 A-3 Reactor Coolant System 2 A 2 Gi PN 0 LT YES I Letdown Isolation Trip Valve EV (15) ST RV-1209 F-1 Reactor Coolant System 2 C Letdown Relief Valve 2 RE SA C SP NO RV-1257 H-1 Volume Control Tank Relief 2 C 3 RE SA C SP NO Valve HOV-1289A B-5 Normal Charging Header 2 A 4 GA MO 0 LT YES Isolation EV (16) ST I MOV-1289B B-5 Normal Charging Header 2 B 4 GA MO 0 EV YES Isolation ST (16) FCV-1160 A-3 RCS Loop Fill Header 1 A 2 GL PN C LT YES Isolation EV (17) I I

SYSTE:!-f NAME I VALVE NUMBER RV-1203 HCV-1200A,B,C 1-CH-309 e SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES CHEMICAL AND VOLUtlE CONTROL DRAW. NO. DRAW. CODE CATE-LOCN. FUNCTION CLASS GORY H-1 Letdown Header Relief 2 C H-2, H-2, Letdown Orifice Isolation 2 A H-2 J-3 Normal Charging Header 2 AC Isolation ,I 11448-FM-88C PAGE 22 SIZE VALVE ACTUA-NORl*!AL TEST RELIEF (IN.) TYPE TOR POSI-REQ. REQUES1 TYPF TI.ON .. ~.... 2 Cr SA C SP NO 2 GA PN oc LT NO EV ST 3 CK SA 0 LT YES CV (16)

SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SAF~TY INJECTION SYSTEM NAME _________________ _ DRAW. NO*----------- 11448-H1-89A VALVE DRAW. CODE .CATE-SIZE VALVE ACTUA-NORMAL NUMBER LOCN. FUNCTION CLASS GORY (IN,) TYPE TOR POSI-TYPE TION MOV-1860A,B B-8, E-8 Low Head Safety Injection 2 A 12 Gl MO C Pump Suction from Contain-ment Sump 1-SI-56,47 C-8, F-8 Low Head Safety Injection 2 C 12 Cl SA C Pump Suction from Contain-ment Sump Check MOV-l862A, B G-9, G-8 Low Head Safety Injection 2 B 12 GA HO 0 Pump Suction from Refueling Water Storage Tank 1-SI-46A, B G-9, G-8 Low Head Safety Injection 2 C 12 CK SA C Pump Suction from Refueling Water Storage Tank Check 1-SI-58, 50 D-7, G-7 Low Head Safety Injection 2 C 10 CK SA C Pump Discharge Check MOV-1863A, B E-6 ' G-6 Low Head Safety Injection Pump Dischrge to High Head 2 B 8 GA MO C Safety Injection PU!l\\P Suction MOV-1885A, B, C-7, G-6, Low.Head Safety Injection 2 B - 2 GA MO 0 C, D G-6, C-7 Pump Recirculation to . Refueling Water St6rage Tank C-6.* G-6 ii 1-SI-61 53 Low Head Safety Injection 2 C 2 CK SA C Pump Recirculation to Refueling Water Storage PACE 23 TEST RELIEF REQ. REQUES1 LT NO EV ST CV YES (18) EV NO ST CV NO CV NO EV NO ST EV NO ST CV NO l

e I SYSTEM NAME I VALVE I NUMBER MOV-1864A, B RV-1845A, B, C MOV-1890A, B MOV-1890C MOV-'1869A, B, - 1842 MOV-1867C, D MOV-1867A, B e _SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SAFETY INJECTION ~ DRAW.NO. DRAW. CODE CATE-LOCN. FUNCTION CLASS GORY D-6 ' G-5 Low Head Safety Injection 2 B Pump Dischrge to Reactor Coolant System Cold Legs C-6, D-5 Low Head Safety Injection 2 C C-5 Flow Path Relief B-6, B-5 Low Head Safety Injection 2 AI to Reactor Coolant System Hot Legs B-6 Low Head Safety Injection 2 AE to Reactor Coolant System Cold Legs A-3, I-3, High Head Safety Injection 2 AE i\\-1 to Reactor Coolant Sys. B-1, B-2 Boron Injection Tank 2 A Outlet Isolation I-2, I-2 Boron Injection Tank 2 B Inlet Isolation 11448 FM-89A 24 PAGE SIZE VALVE ACTUA-NORMAL TEST RELIEF (IN.) TYPE TOR POS I-_ REQ. REQUEST T.YPJ~.;.,, TION 10 GP MO 0 EV NO ST 1 RE SA C SP _ NO 10 GA MO C LT NO EV ST VP 10 GA NO 0 LT YES EV (19) ST VP 3 GA MO C LT YES EV (20) ST VP 3 GA MO C LT YES EV (21) ST 3 GA MO C - EV YES ST (21)

e e e SURRY UNIT 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME SAFETY INJECTION DRAW.NO. 11448-FM-89A PAGE 25 VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NOR1'1AL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES1

r,YPE. *TION TV-1884A H-1 Boron Injection Tank 2

B 1 GP PN 0 EV NO Recirculation ST 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 3J,, RE SA C SP. NO TV-SI100 B-4 Nitrogen Accumulators A 1 GA PN 0 LT NO EV ST I

e e SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES y ~YSTEM NAME SAFETY INJECTION DRAW. NO. 11448-Fl:1-89B PAGE 26 VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUEST TYPF. TI.ON RV-1858A B, C C-4,G-5,C-7 Accumulator Tank Relief 2 C 1 RE SA C SP NO 1-SI-107, 109 C-5, A-5, Accumulator Discharge Check 1 C 12 0 SA C CV YES 128, 130, G-7, A-7, (22) 145, 147 C-8, A-9 J:10V-:-1865A, B, C C-5,G-6,C-8 Accumulator Discharge 2 BE 12 GA MO 0 EV NO ST VP l-SI-88, 91, 94, A-2, A-2, Safety Injection to 1 C 6 CK. SA C CV YES

238, 239, 240 A-3, B-2 RCS HotLegs (23)

B-2, A-3 1-SI-235, 236, B-1, B-1 High Head Safety Injection 1 C 2 CK SA C CV YES 237 B-2 to RCS Cold Legs (23) 1-SI-241, 242, B-1, B-1, Low Head Safety Injection 1 C 6 CK SA C CV YES 243 B-2 to RCS Cold Legs (27) 1-SI-224 225, J-1, J-1, High Head Safety Injection 2 C 3 CK SA C CV YES 226, 227 J-2, J-3 Check Valves at Containment* (23) Penetrations l-SI-228, 229 J-3, J-3 ,/ Low Head Safety Injection 2 C 6 CK SA C CV YES Check Valves at Containment (24) Penetrations I

e SYSTEM NAME VALVE NUNllER

MOV-1866A, B, C, D, E, F 1-SI-79, 82, 85 TV-SI101A, B 1-SI-234 e

SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES DRAW. NO. SAFETY INJECTION 11448-FM-89B DRAW.

CODE CATE-SIZE VALVE ACTUA-LOCN.

FUNCTION CLASS GORY (IN.) TYPE TOR TYPE E-3, E-2, Cold & Hot Leg Safety 2 E 2 GI HW E~2, E-2 Injection Line Throttle Valve E-1, E-1 A-1, A-1, Safety Injection to RCS 2 C 6 CK SA A-2 Cold Legs J-5, J-5 Accumulator Nitrogen A 1

GA PN Relief Line Isolation J-4 Nitrogen Accumulators AC 1

CK SA I PAGE 27 NORNAL TEST RELIEF POSI-REQ.* REQUES1 .TION_ ~*..i~ T VP NO C CV YES (26) 0 LT NO EV ST 0 CV NO LT I

I r e SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME. _____ R_. w_._s_. T_._c_Ro_s_s __ T_rn ___ _ 11448-FM-106C DRAW. NO'-----'"'--------- VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORHAL NUMBER LOCN. FUNCTION CLASS GORY (IN.) TY-:-E TOR POSI-TYPF', TION TV-SI102A, B D-3, D-3 Unit No. 1 RWST to Unit 2 B 8 GP PN C No. 2 RWST Cross Tie 1-SI-25 C-3 Charging Pump Suction 2 C 8 CI< SA* C from RWST Check Valve 1-SI-410 B-3 Charging Pump Suction 2 C 10 CK SA C from RWST Check Valve e PAGE 28 TEST RELIEF REQ.. REQUES1 EV NO ST CV YES (12) CV YES (12) I I i i

e SURRY UNIT 1 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES STE~H GENERATOR BLOWDOWN SYSTEM NM1E;__ ______________ 11448-FM-124A DRAW. NO. ____________ _ VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL NUMBER

LOCN, FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-ITYPE TION. TV-BD100A,B,C C-2, C-2, C-L,, Steam Generator Blowdowri 2 B 3 Gt PN 0 D,E,F C-4,C-5,C-5 Trip Valves . sj :SP/119 e 29 PAGE TEST RELIEF REQ.

P.::'.QUES1 EV YES ST (25)

I

e SURRY UNIT 1 INSERVICE TESTING ASHE CODE CLASS 1, 2 AND 3 VAL\\.7ES RELIEF REQUESTS (1) Closure of these valves during power operation will result in a turbine and reactor trip. As an alternative, they will be cycled during re*actor shutdown. (2) Opening these valves during power operation would introduce cold and out of chemistry specifications auxiliary feedwater to the steam generators resulting in thermal stress and possible degradation. As an alternative, they will be tested during cold shutdown. (3) Closure of these valves during power operation would require securing feedwater (resulting in a reactor trip) and initiation of auxiliary feedwater flow to back seat the disc. These valves will be tested during cold shutdown. ( 4) A commitment h_as been made prohibiting the introduction of service water into the Recirculation Spray Heat Exchangers. As an alterna-tive, these ~alves will be tested during each refueling outage. (5) These check valves are located in the containment and may be normally open or closed depending on system lineup.. A containment entry and manipulation of other system valves is necessary to test these valves. This is considered impractical during power operation and therefore they will be tested during cold shutdown. (6) Component cooling water flow to the reactor coolant pumps is required at all times the pumps are in operation. Failure of one of these valves in a closed position during cycling would result in a loss of the cooling flow to the pump. These valves will be tested during cold shutdown when the reactor coolant pumps are secured. (7) These valves remain open during normal plant operations. It is not practical to test for closure unless the containment air coolers are taken out of service. As an alternative, these valves will be tested during each refueling outage. (8) It is not possible to verify that this normally closed check valve opens without initiation of flow through the containment spray header or by visual observation inside the containment. As an alternative the valve shall be exercised during each refueling outage. (9) Cycling of these RHR system valves during power operations would subject the RHR system to full RCS pressure. These valves will be exercised when the RHR system is placed into operation during cooldown of the reactor coolant system.

(10) This relief valve cannot be tested unless the entire RHR system is removed from service and drained. The RHR system must be available during operation and refueling outages for core cooling capability. The valve will be tested whenever the RHR system is removed from service and drained for maintenance. (11) This valve can only be cycled when the RHR pumps are started. As an alternative to testing once per (3) months, they will be tested when the RHR pumps are tested in the pump testing program. (12) Exercising this valve during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in RCS boron inventory. It will be exercised during cold shutdown when the RCS* is borated to shutdown conditions. (13) This valve cannot be exercised without possible damage to the charging pumps. As an alternative, it will be exercised when the charging pumps are secured during each refueling outage. (14) To protect the reactor coolant pumps seals, flow is required at all times during power operation and cold shutdown. This valve will be exercised during each refueling shutdown. (15) This valve cannot be exercised when the charging and letdown systems are in operation due to increased risk of overpressurization of the letdown system. It will be exercised during cold shutdown. (16) Failure of this valve in a closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reaCtory coolant inventory. This valve will be exercised during cold shutdown. (17) This flow control valve is modulated open and closed by a ten turn pontentiometer located on the control board. Since the valve stroke time (ST) is dependent on operator response time in manipulat-ing the controller and the time const~nt of th~ control system, it will not provide useful information and therefore will not be measured. (18) This normally closed check valve cannot be exercised without isolating suction to the LHSI puinp and draining a portion of the system. This valve will be part-stroke exercised during each refueling outage using the leakage monitoring test connections. (19) This valve is required to be maintained in the indicated position with power to the operator removed during power operation. It will be cycled during cold shutdown. (20) This valve is directly attached to the charging pump discharge header. If this valve were exercised during power operation, hot or cold shutdown, uncontrolled flow to the RCS might cause overpressuri-zation. Additionally MOV-1869A and Bare required.to be maintained closed with power to the operator removed during power operation. As an alternative, this valve will be exerci3ed during each refuel-ing outage. (21) These valves were designed to be closed with no differential pressure accross the seats. Cycling during power operation causes the seats to leak when the valve is closed resulting in subsequent dilution of the boron injection tank. As an alternativer these valves will be tested during cold shutdown. (22) To exercise this normally closed check valve would require the simulation of a loss of coolant accident, i.e. loss RCS pressure~ This valve will be part-stroke exercised by initiating accumulator injection to the RCS while cooling down for a refueling outage. (23) The only way to verify that these normally closed check valves open is by initiating flow, using the charging pumps, into the reactor coolant system hot ind cold legs. If charging flow was directed to the reactor coolant system in this manner it could cause over-pressurization during cold shutdown or result in a loss in charging flow control during operation. As an alternate, these check valves will be exercised open during each refueling outage. (24) The only way to verify that these normally closed check valves can open is by initiating flow, using the low head safety injection pumps, into the reactor coolant system hot and cold legs. During operation or cold shutdown reactor coolant system pressure will be higher than the low head pump discharge pressure precluding flow into the vessel. As an alternate, these valves will be exercised open during each refueling outage. (25) Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to*steam. When the valves are reopened a flow surge occurs which automatically isolates the inner valves due to high flow. Then a containment entry is necessary to reset these valves and upon reopening the process may occur again. As an alternative these valves will be exercised during cold shutdown. ATTACHMENT D SURRY UNIT 1 Marked Up Flow Diagrams Showing ASME Code Class 1,2 and 3 System Boundaries Relative to Inservice Inspection and Testing The enclosed drawings are marked up to show the ASME Code Class 1, 2 and 3 system boundaries relative to inservice inspection and testing. I Drawings showing containment isolation valves that are not part of the boundaries are also included. The system boundaries are also described below: Drawing No. 11448-FM-64A 11448-FM-66A l 1448-FM-68A 11448-FM-68B 11448-P-1-7 lA 11448-FN-71B 11448-FM-72A Description Class 2 as marked except for steam generator primary side (class 1) and steam lines. from valves l-MS-87,. 379, 120, 378, 158 & 377 to the turbine drive for the auxiliary steam generator feed pump (class 3). Containment isolation valves The auxiliary feedwater system is class 3 as marked. The main feed-water system is class 2 as marked. The primary side of, the steam generator is class li Class 3 as marked Class 3 as marked except for sheLl side of the recirculation spray heat exchanges (class 2). Class 3. as marked Class 3 as marked except for the tube side of the excess letdown heat exchanger (class 2) and the tube side of the residual heat removal exchangers (class 2).

( I 11448-FM-72B 11448-FM-72C 11448-FM-72D 11448-FM-SlA 11448-FM-82B 11448-FM-83A l 1448-FM-83B 11448-FM-84A 11448-FM-SSA 11448-FM-86A 11448-FM-86B 11448-FM-87A 11448-FM-SBA 11448-FM-88B Class 3 as marked Class the 3 as marked tube side of except the for non-regenerative heat exchanger (class

2) and the tube side of the seal water heat ex-changer (clais 2).

Class 3 as marked Class 3 as marked Class 1 as marked except for lines 3/4"-RH-21, 22 to valve TV-SS-103 (Class 2). Containment isolation valves Containment isolation valves Class 2 as marked except for tube side of recirculation spray cooler (class 3). Containment isolation valves Class 1 as marked except for secondary side of steam. generators (class 2).and. portions of lines 2"-SI-74, 85 & 75 (class 2). Class 1 as marked Class 2 as marked except for RHR inlet from RCS to valve MOV-1701 (class 1), RHR discharge to RCS from valves MOV-1720A&B (class 1), com-ponent cooling (CC) to RHR-pumps (class

3) and shell side of the RHR heat exchanger (class 3).

Class 3 as marked except for eves letdown line 3"-CH-25 as marked (class 2).* Class 2 as boric acid piping to l-CH..:.206, marked except for transfer system valves FCV-1114B, l-CH-209, l-CH-227

11448-FM-SSC 11448-FM-89A 11448-FM-89B 11448-FM-106C 11448-FH-123A 11448-FM-124A 11448-FH-130A 11448-FB-4 lA and l-CH-229 (class 3), shel 1 side of nonregenerative exchanger (class 3) and side of seal water heat exchanger (class 3). Class 2 as marked except loop fill header (class loop drain header from to valve HCV-1201 (cl~ss letdown line from RCS to heat shell for 1)' RCS 1)' 1)' valve LCV-1460B (class charging line from RCS .to valve l-:-CH-312 (class 1), auxiliary spray line from RCS to valve l-CH-313 (class

1),

RCP seal leakoff lines to RO 10-RSB-l,2 & 3 (class 1), RCP seal leakoff lines l-CH-261 thru 266 (class 1), RCP seal injection lines from valves l-CH-323, 333 349 to RCP's (class 1) and shell side of excess let-down heat exchanger (class 3). Class 2 as marked except for lines 1"-SI-187 to valve TV-1884A * (class. 3) and line l "-CH-229 to.valve l-SI-3 (class 3). Class 2 as marked. except for. cold leg SI. lines from RC loops to valves l-SI-235, 241, 236, 242, 237 & Z43 (class 1), hot leg SI lines from RC loops to valves l-SI-238, 239 & 240 (class 1), and accumulator discharge lines from RC loops to valves HCV-1850B, D &. F, l-SI-207, 129 & 145 (class 1). Class 2 as marked Class 2 as marked Class 2 as marked Cl~ss 3 as marked Class 3 as marked

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Dear Mr. Denton:

SUBJECT:

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