ML18139A906

Forwards Requested Relief from Inservice Insp & Testing Requirements.Program W/Detailed Specific Relief Required from ASME Code Requirements Per Inservice Insp & Testing of Pumps & Valves Outlined in Attachments A,B & C

ML18139A906
Person / Time
Site:	Surry
Issue date:	12/15/1980
From:	Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Denton S, Varga S Office of Nuclear Reactor Regulation
References
944, NUDOCS 8012170659
Download: ML18139A906 (73)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICH.MOND,VJ:HGIN.IA 23261 December 15, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Denton:

REQUESTED RELIEF FROM INSERVICE INSPECTION AND TESTING REQUIREMENTS SURRY POWER STATION UNIT NO. 2 Serial No.

944 PO/ATV:mmf Docket No.: 50-281 License No.: DPR-37 Pursuant to 10 CFR 50. 55a (g), the Virginia Electric and Power Company submitted its programs for inservice inspection and testing of pumps and valves during the last forty month period of the first ten year interval for Surry Power Station Unit 2 on September 28, 1979.

After reviewing the pro-gram for inservice inspection and testing of pumps and valves following the NRC working group meeting held April 15, 16, 17, 1980, we hereby resubmit our program with the detailed specific relief we require from ASME Code require-ments pertaining to inservice inspection and testing of pumps and valves as outlined in attachments A, B, and C.

.-.:-i l.!

8012170659 Very truly yours, N~tL B. R.~;ia Manager-Nuclear Operations and Maintenance

ATTACHMENT A SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE INSPECTION REQUIREMENTS FOR CLASS 1, 2 and 3 COMPONENTS AS SET FORTH IN SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THROUGH THE SUMMER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)

The enclosed tables provide a listing of the Class 1, 2 and 3 pressure-retaining components (and their supports) which are subject. to the inspection requirements of Subsections IWB, IWC and IWD of Section XI of the ASME Boiler and Pressure Vessel Code 19 74 Edition with Addenda thru the Summer of 1975.

These tabulations identify the components to be inspected, the components safety class, the applicable code to which the component was built, and the method of examination.

Relief from the -inspection requirements of each Subsection is requested in cases where these inspection requirements have been determined to be impractical.

Where relief is requested, specific information is provided which identifies the applicable code requirement, justification for the relief request, and the inspection method to be used as an alternative.

The following provide further clarification concerning the Class 1, 2 and 3 system inspection programs.

(a)

Articles IWC-3000 and IWD-3000 entitled, "Evaluation of Examination Results" are in the course of preparation by the Code Committee and, as yet, are not available for use.

Standards for examination evaluations as included in the 1974-Edition of Section XI with Addenda through the Summer, 1975, are incomplete and "Acceptance Standards for Flaw Indications" as given in Article IWB-3000 of the 19 77 Edition of Section XI will be utilized.

(b)

Articles IWA-4000, IWB-4000, IWC-4000 and IWD-4000 entitled "Repair

-Procedures" in the 1977 Edition of Section XI with Addenda thru the Summer of 1978 provide additional guidelines for making repairs and wil 1 be used in lieu of those contained in the 19 7 4 Edition of Section XI with Addenda thru the Summer of 19 7 5.

(c)

Requirements for the visual examination, of Class 1 systems and com-ponents for evidence of leakage during the performance of a system pressure test following each refueling are identified by IWB-5200.

Exception is taken to the implementation of these requirements on those portions of Class 1 systems which are contained between two check valves or two normally closed valves, where pressure applied to the reactor coolant system will be retained at the first valve in the line.

The portions of systems affected by this limitation are:

(i)

Cold leg injection from accumulators between check valves 2-SI-109, 130 and 147 and 2-SI-107, 128 and 145, test lines to valves HCV-2850B, D and F, RHR return to valves MOV-2720B and check valve 2-RH-47.

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 11548-FM-8 7A and 89B).

(ii) Hot leg injection between check valves 2-SI-88, 91 and 94 and check valves 2-SI-238, 239 and 240 and check valves 2-SI-226, 227.

These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11548-FM-89B).

(iii) Cold leg low head injection line between check valves 2-SI-79, 82 and 85 and check valves 2-SI-241, 242 and 243; and high head and boron injection to check valves 2-SI-235, 236 and 237 (refer to drawing 11548-FM-89 B).

(iv) RHR take-off line be tween normally closed (with pressure interlock) valves MOV-2700 and 2701.

This portion of the system will be pressurized whenever the system is put into operation during plant shutdown when the reactor coolant system is cooled to 350°F and depressurized to 450 psig (refer to drawing 11548-FM-87A).

(d)

Subsections IWB and IWC contain differing requirements for the hydrostatic testing of Class 1 and Class 2 systems and components.

The implementation of these requirements is impractical when the only means of pressurizing the Class 2 system is through the Class 1 system or when the boundary between the two systems is a check valve arranged for flow from Class 2 to the Class 1 system.

Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412(a) on those portions of the Class 2 systems identified below.

Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal ope rating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system.

(i)

R. C. Pump seal bypass lines from the flow orifice to valve HCV-2307 (refer to drawing 11548-FM-88C).

(ii)

Hot leg injection between check valves 2-SI-88, 91 and 94 and check valves 2-SI-238, 239 and 240 and check valves 2-SI-226,

• ,~._

227.

These portions of systems are filled and vented but not pressurized during normal operation (refer to drawing 11548-FM-89B).

(iii)

R. C. Pump seal injection line from check valve 2-CH-323, 333 and 349 to manually operated valve 2-CH-29 4, 29 7 and 300 (refer to drawings l 1548-FM-88B and 88C).

(iv)

Excess letdown system from valve HCV-2201 to HCV-2137 (refer to drawing l 1548-FM-88C).

e (v)

Letdown line from valve LCV-2460B to orifice outlet valves HCV-2200A, Band C (refer to drawing 11548-FM-88C).

(e)

The examination requirements for Class 3 systems and components as given in the enclosed tabulation are in accordance with IWD-2410(c) which specifies that 100 percent of the components be examined as required by IWA-5240 and IWD-2600 either during normal operation or during system inservi_ce 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, and boric acid transfer and recirculation, which are in continuous operation during plant operation.

The continuous functional operation serves to demonstrate the structural and leak-tight integrity of these systems.

Visual examinations of these systems will be performed at normal operation pressures to verify leaktightness.

(f)

Ultrasonic examinations will be conducted in accordance with the provisions of Appendix I and Article 5 of Section Vas required by Paragraph IWA-2232.

As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 1974 Edition, Winter, 1975 Addenda of the ASME Boiler and Pressure Vessel Code will be used for ultrasonic examina-tion of piping systems with the following changes:

(1)

Non-geometric indications 50% of DAG or greater shall be recorded.

(2)

An indication 100% of DAG or greater shall be investigated by a Level II or Level III examiner to the extent necessary to determine the size, shape, identity and location of the re-flector and evaluated in accordance with the.acceptance requirements of Section XI.

(3)

Any non-geometric indication, 20% of DAG or greater, dis-covered during the ultrasonic (UT) examination shall be evaluated by a Level II or Level III examiner to the extent necessary to determine the shape, identity and location of the reflector.

It is recognized that Appendix III of Section XI was issued in the Winter, 1975, Addenda and, as such, has not been officially recog-nized by the NRG by reference in 10 CFR 50.

However, Appendix III is the first guideline that has been published in the ASME Code for the ultrasonic examination of pipe welds and, as such, its use is essential.

(g)

As an alternative for I-3121 of Section XI:

"Calibration blocks required for the examination of welds in ferritic vessels 2 1/2 inches thick and over will be fabricated from material of the same specification, product form, and heat treatment as one of the materials being joined as allowed by article T-434.1 in the Winter, 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code."

. w The reason this alternative is requested is that the Code requires that calibration blocks for the examination of welds in ferritic vessels 2 1/2 inches thick and greater be fabricated from material taken from the component nozzle drop out or material from the component prolongation.

As a third alternative, when it is not possible to fabricate the block from material taken from the component, the block may be fabricated from a material of a specification included in the applicable examination volumes of the component.

It is required that the acoustic velocity and attenuation of such a block be demonstrated to fall within the range of straight beam longitudinal wave velocity and attenuation found in the unclad components.

For the components in Surry Unit 2, particularly the pressurizer and steam generators, it will be impossible to meet the requirements of alternatives 1 or 2.

Materials of the specification are readily available, but because all the components involved are clad on the inner surfaces, it would be impossible to obtain a comparison of sound beam velocities and attenuations in the unclad component.

Limitations may occur for the 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 intrados of the fitting prevents adequate ultrasonic coupling.

No examinations can be performed from the fitting side when it is a valve or a flange.

In most cases one hundred percent of the weld material can be examined.

In instances where welds occur at fitting to fitting, access restrictions as outlined above occur on both sides of the weld.

In instances where ultrasonic examinations cannot be performed on one hundred percent of the volume of the weld and heat affected zone, surface examinations may be performed to supplement the limited volumetric examination.

Welds in the Surry Unit 2, Class 1 system which due to limitations, would require surface examinations are:

(i)

Loop 1 Cold Leg Injection line; Welds 7.

(ii)

Loop 2 Cold Leg injection line; welds 5 and 7.

(iii)

Loop 3 RTD re turn line; weld 9.

(iv)

Loop 3 Cold leg injection line; welds 3 and 4.

(v)

Pressurizer safety valve lines welds 7 and 8.

(vi)

Pressurizer Relief line; welds 4 and 19.

Welds in the Surry Unit 2, Class 2 system with limitation at geometric discontinuities are:

(i)

Loop 1 Mains team; welds 20, 18, 15, 11, 2, 4, 6, 8 (ii)

Loop 1 Mains team; By-Pass welds 12, 7, 19 1 (iii)

Loop 2 Mains team; By-Pass; welds 7, 12, 19, 1 (iv)

Loop 3 Mains team; welds 2, 4, 6, 8, 11, 12, 18, 20 (v)

Loop 3 Mainsteam; By-Pass welds 7, 12, 19, 1 (vi) 10" RHR; weld 14 (vii)

Loop 2 Mainsteam; welds 2, 4, 6, 8, 11, 12, 18, 20

e 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 wi.thout unduly stressing the system.

Certain Class 2 systems or portions of Class 2 systems and components are exempt from the examination requirements of the IWC-2520 by IWC-1220.

A summary of these exemptions as applicable to the Surry plant systems are as follows:

(i)

(ii)

(iii)

(iv)

(v)

(vi)

(vii)

(viii)

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

During plant operation, the boric acid solution will be constantly recirculated through the boron injection tank by the transfer pump sys tern.

Samples would normally be taken on a regular basis and the component and associated piping would be exempt from examination by IWC-1220(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 IWC-1220(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 sys tern 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 inse rvice 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 ASME Boiler and Pressure Vessel Code,Section III, Class A Nuclear Vessels IIIC ASME Boiler and Pressure Vessel Code,Section III, Class C Nuclear Vessels VIII 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 Fi t tings

I TABLE

• -lWB-2600 ITEM NO.

Bl. 1 B 1. 1

• Bl. l Bl. 1 Bl. 2 Bl. 2 Bl. 3 Bl. 3 Bl: 4 I B.1.4 Bl. 5 Bl. 6

• TABLE Ilffi-2500 EXAMINATION SYSTEM OR CATETORY COMPONENT B-A Reactor Vessel 2-RC-R-l B-A B-A B-A B-A B-B B-C B-C B-D B-E B-F

.!.!!:~!lV UNl'l' i INSERVI~K INSPECTION ASME COL)£ ! C.* ASS :L COMPONENTS

• CODE.APPLICABLE TO CONSTRUCTION III-A

' t*.

~REA TO BE EXAMINED tlpper to. intermediate shell course I

~ircumferential weld I

Intermediate to lower shell course circumferential weld I

I J:ntermediate shell course longitu-dinal welds (2)

I Lower shell course longitudinal welds (2)

Lower head to shell circumferential

':'eld Lower head ring to disc circumferen-tiai weld*

Vessel to fl~nge weld'

• . Closure head to flqnge weld Outlet nozzle to.vessel welds (3)

Inlet Nozzle to vessel welds* (3) i CRDM,.Vent *and In-:-Core Instrumen-tation penetrations anci CRDM seal

• ¥elds

• ?utlet no~zle" to safe-ends.welds (3)

• EXAMINATION REQUIREMENT Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric Visual*

Volumetric &

Surface SECTION XI CODE RELIEF REQUESTED No No No Noe No No.

No No No

.No No No

TABLE TABLE nm-2soo

• • ?WB-2600

• EXAMINATION ITEM NO.

. CATETORY Bl. 6 B-F Bl. 7 B-G-1 Bl. 8 B-G-1 Bl.9 B-:-G-1 Bl.10 B-G-1 Bl.11 B.:..G-2 Bl. 12 B-H Bl.13

' B-I-1 Bl~14 B-I-1 B\\i. 15 B:-N-1

\\

'.Bl. 16 B-N-2 BL 17 B-N-J*

I SYSTEM OR*

COMPONENT 8UR'lY UNIT ~

INSERY!.*~J,; INSPECTION ASME CODE; c*,ASS l. COMPONENTS CODE.APPLICABLE TO CONSTRUCTION iREA TO BE EXAMINED 0

t*

Inlet nozzle to safe-end welds (3)

C1osure: Head Studs (In-Place)

• Closure: Head Studs.&

• Nut~

Vesse.l flange*. ligaments Clo*s~~e ~h~ad Washers Conoseal.Bolting Int7grally Welded vessel support~

• 91osure. Head. c'ladding

• Vessel Gladding t~ssel Interior Surfaces Jnternals I

Interior.Attach~ents and

• support Structures ior.e Supp9rt Structures i I.

I

' i' I

and' Core

~

SECTION' XI EXAMINATION CODE RELIEF REQUIREMENT REQUESTED Volumetric &

No Surface

• Not No-Appl:i,.cable Note 1 Volumetric &

No Surface

• Volumet.ric *

• No e Visual

• No

• Visual No Not No-Applicable Note 2 Surface &

No-Visual or Note 3 Volumetric Visual No Visual No e No't.

No Applicable.

• Note 4 Visual No

U~ll l'i' UNI'l' i INSEllVY.!g 1N8PEC'1'ION ASME COUE C.ASS l. COMPONENTS TABLE

~itcTroN* xi TABLE Ilffi-2500

• *lWB-2600 EXAMINATION SYSTEM OR CODE.APPLICABLE kXAMINATION CODE RELIEF ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION

~REA TO BE EXAMINED REQUIREMENT REQUESTED Bl. 18 B-0 Control* *Rod Drive Housings Volumetric No I

Bl. 19 B-P

~xempted* Components Visual No B2. 1 B-B Pressurizer III:-A Longitudinal Shell welds (6)

Volumetric No 2-RC-E-2 I

B2. l B-B Gircu,mfe rent ial sheli welds (7)

Volumetric Yes -

Note 17 e B2.2 B-D Nozzle to vessel welds (6)

Not No Applicable*

Note 5 B2.3 B-E

'eater Penetrations Visual No B2.4 B-F tisozzle to safe-end welds (6)

Volumetric &

No I

Surface l

B2.5 B-G-1

. res sure Retaining Bolting Not No

• in place)

Applicable Note 6 B2.. 6 B-G-1 tryssui::~ Re'taining Bolting Not No -

. Jh.en removed

• Applicable Note 6

\\

'. t, B2.7 B-G-1 Pressure Retaining Bolting Not No -

• Applicable Note B2. 8 B-H

~ntegrally Welded Vessel Supports Volumetric.

No B2.9 B-I-2 Vessel cladding Visual No i

B2.10 B-P

}l:xernpted Components Visual N'o B2.ll B-G-2

}1qnway Bolting Visual No B3.l B-B Steam Generators...

• III-A Channel Head to tubesheet

• Volumetric No (3)*Primary Side Weld (3)

I

i BURlY UNIT ~

INSERV'fi~g INSPJrnTION ASME COUE 1 CLASS l. COMPONENTS TABLE TABLE IUB-2500 SECTION-XI

'-!WB-2600 EXAMINATION SYSTEM OR CODE.APPLICABLE EXAMINATION CODE RELIEF ITE}f NO.

CATETORY COMPONENT TO CONSTRUCTION iREA TO BE EXAMINED REQUIREMENT REQUESTED '

I i I

l l I

B3.2 B-D 2-RC-E-lA Jozzle to Vessel welds (6)

Not No-2-,RC-E-lB Applicable Note 7 I

2-RC-E-lC I

• B3. 3 B-F t>lozzle to safe-end welds (6)*

Volumetric &

Yes -

I Surface**

Note 8 I

i t B3.4 B-G-1 Pressure. Reta:i.hing Bolting Not No -

. (in_piace)

Applicable Note-B3.5 B-G-1

. Pres*sur~* Re t~ining Bolting~,-

Not No -

when removed Applicable Note 6 B3.6 B-G-1.

Pressure Retaining Bolting Not No -

_Appiicable

. Note* 6 B3.7 B-H Int~grally wel1Ied supports Not No -

Applicable Note 6 B3.8 B-I-2

.Vessel Cl~d~in*g Visual No B3.9 B-P Exempted Compone,nts Visual No

.i Bb. 10 B-G..:.2

. l' Manway B()ltiI"J.~ '

Visual No

!33. 1 B-B Regenerative r'n~c.

Head to she°ll weld.s (6)

Vo1umetric Yes '

Heat Exchanger 19 2-CH-E-3.

B3.1 B-B Shell to tubesheer:* welds (6).

Volumetric Yes-Note 19

SL' R l\\' UNlT ~

INSEfil 1 :g INSPirnTIOH ASME CODE c*.ASS l. COMPONENTS TABLE TABLE HIB-2500 SECTION XI

, *lWB-2600 EXAMINATION SYSTEM OR CODE.APPLICABLE EXAMINATION CODE RELIEF TTE}t NO.

CATETORY COMPONENT TO CONSTRUCTION

'.AREA TO BE EXAMINED REQUIREMENT REQUESTED B3.2 B-D Nozzle to head welds ( 12)

Volumetric Yes-Note 18 B3.3 B-F Nozzle to safe end welds Not No-Note 6 Applicable B3.4 B-G-1 Pressure Retaining Bolting (in place)

Not No-Note 6 Applicable B3.S B-G-1 Pressure! Retaining Bolting (when Not No-N-6 removed)

Applicable B3.6 B-G-1 Pressure Retaining Bolting Not No-Note 6 Applicable B3.7 B-H Integrally Welded Supports Not No-Note 6 Applicable B3.8

' B-I-2

• Vessel Cladding*

Not No-Note 6 I

Applicable B3.9 B-P

~:x:empt~d Co~ponents Visual No B3.10 B-G-2 Pressure Retaining Bolting Not No-Note 6

\\

. t, Applicable B4.1 B-F Piping Pressure Safe end to pipi,= welds Not N.o --

Bou_ndary AppHcable Note 6 B4.2 B-G--:1 fressure-Retaining Bolls

• Not No -

• (in place)

Applicable Note 6 B4.3 B-G-1 Pressure Retaining Bolts Not No -

• when removed Applicable Note 6 I

\\

j TABLE

• '-lWB-2600 ITE}f NO.

B4.4 B4.5 B4.6

'B4.7 B4.8 B4.9 B4.-10 B~.11

\\

B4.12 BS.l BS. 1 TABLE nm-2soo EXAMINATION SYSTEM OR CATETORY COMPONENT B-G-1 B-J B-J B-J B-J B-K-1 B-K-1 B-P B-G-2 B-G-1 B-G-1 Reactor Coolf-mt

.Pumps (3) 2-RC-P-lA 2-RC-P-lB 2-RC-P-lC B~R:lY UNIT i 1NSERV'fcg lNSPgCTION ASME COl)J~; C'.ASS l COMPONENTS CODE.APPLICABLE TO CONSTRUCTION iREA TO BE EXAMINED

.. l*

III-A Pressure. Retaining Bolting i

Circumferential and.

Longitud.inal Pipe Welds

• i Branch Pipe connection welds

. exceeding 6" diameter~

~ranch Pipe Connections Weld 6" diameter and smaller.

Socket Welds Integrally Welded Supports *

• Support. Components Exemp_ted Components..

Pressure Re.taining Boltin.g Main Flange Bolting (in place)

Seal Housing Bolting (in place)

EXAMINATION REQUIREMENT Not Applicable Volumetric Volumetric Surface Surface Volumetric Visual Visual Visual

'vohime tric Volumetric

~

SECTION' XI CODE RELIEF REQUESTED No -

Note 6 Yes -

Notes 9 and 10 Yes-*.

Note No No Yes -

Note 12 No No No e No Yes -

Note 13

\\

l TABLE TABLE IY.B-2500 B~R:tY UNIT i INSEitVf,.:g INSPECTION ASME CODE C.*,ASS l. COMPONENTS

• -?WB-2600 EXAMINATION SYSTEM OR CODE APPLICABLE ITEM NO.

CATETORY COMPONENT

. TO CONSTRUCTION

~REA TO BE EXAMINED

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

BS.2 BS.2 BS.3 BS.3-BS.4 BS.5 BS.6 ns:1 B\\s. 8 BS.9 B6.l B6.2 B-G-1

. B-G-1 B.,-G-1 B-G-1 B-K-1 B-:K-2 B-L-1 B-L-2 B-:P B-G-2 B-G-1 B-G-,l t,

• Valve Pressure Boundary Main Flange Bolting when removed Seal Housing Bolting when removed:

Main -Fl~nge Bal ting Seal Ho~sing_ Bolting*

Integrally Welded Supports Support Compori.~nts Pump Casing Weld Pump Cas.ings.

Exempted Components l?ressure Retaining Bolting fressure Retaini'ng Bolting*

• (in place).

. J?re'ssu:re Retaining BCllting when removed *

• ~

SECTION-XI EXAMINATION.

CODE RELIEF REQUIREMENT REQUESTED Volumetric &

No -

Surface Note 14 Volumetric &

No -

Surface**

Note 14 Visual No e Visual No Volumetric.

Yes Note 15 Visual No Volumetric No

• . Note 16 Visual No.

Visual No Not No e Applicable*.

Note 6 Volume*tric No

. Volumetric &

No Surface

TABLE TABLE Ilffi-2500

'*?WB-2600 EXAMINATION SYSTEM OR ITEM NO.

CATETORY COMPONENT

-B6. 3 B-G-1 B6.4 B-K-1 B6.5 B-K;._2 B6.6 B-M-1 B6.7 B-M-2 B6.8 B"'."'P B6.9 B-G-2

\\

I St: R lY UNIT i INSEfilf,:g lNSPIWTION ASME COl)J~. C!'.ASS l. COMPONENTS CODE.APPLICABLE TO CONSTRUCTION

~REA TO BE EXAMINED

.. t*

Pressure Retaining Bolting I

J;ntegrally welded supports Support:Components Valve Body Welds

.I I.

I Valve Bodies i ~xempted Components Pressure Retaining Bolting I

I I

SECTION XI EXAMINATION CODE RELIEF REQUIREMENT REQUESTED Visual No Not No -

• Applicable Note 6 Visual No Not No-

,A.pplicable Note.

Visual No Visual No Visual No

SURRY UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 1 COMPONENTS NOTES

1.

The Reactor Vessel Closure Head Studs are removed during each refueling and there will be no need for examination in place as required by IWB-2600.

2.

The reactor vessel is supported on pads integral with the inlet and outlet nozzles and therefore are excluded from examination requirements of IWB-2500 by Category B-H.

3.

Radiation levels beneath the closure head may affect the allowable dosage of personnel doing surface and visual examination.

Relief is requested from volumetric examination of the reactor vessel head cladding ultrasonic examination of the meridional and circumferential head welds from the O.D. will cover sufficient clad-metal interface area to provide assurance of closure head structural integrity.

4.

This requirement is applicable only to Boiling Water Type Reactors.

5.

The pressurizer nozzles are integrally cast with the vessel head and therefore there are no welds requiring examination in accordance with the requirement IWB-2600. However, the inner radiused sections of the integrally cast nozzles will be ultrasonic examined from the outside and the area will be visual examined to the extent practical as this is a high radiation area (20 to 30 R).

6.

There are no items in this category on this component in the Surry Unit 2 Class 1 Systems.

7.

The steam generator nozzles are integrally cast with the channel head and therefore are no welds in this category. However, the inner radiused sections of the integrally cast nozzles will be ultrasonic examined from the outside and the area will be visual examined to the extent practical as this is a high radiation area (20 to 30R).

8.

Examinations of the steam-generator primary nozzle to safe-end and safe-end to pipe weld is limited both by the nozzle geometry and surface condition and the limited surface preparation on the pipe side of the weld.

The surface on the pipe side of the weld, which is a cast el bow, is machined for a distance of approximately three inches from the edge of the weld.

Ultrasonic examination is limited to this from the edge of the weld.

Examinations can be per formed on the surface of the weld but are severely limited from the nozzle side by the rough, as cast surface.

Surface examination can be performed on one hundred percent of the weld and the base metal on the pipe side.

The configuration is shown in Figure 1.

9.

Limitations may occur from the examination of piping system cir-cumferential butt welds (Category B-J) when the welds occur at geometric discontinuties such as pipe to vessel welds, pipe to

13.

The reactor coolant pump seal housing bolts are of the socket head type and the configuration is such that ultrasonic examinations as required by IWB-2600 cannot be performed when the bolting is in place.

Examinations will be performed to the extent required by IWB-2600 when the seal housing is disassembled for maintenance.

14.

The reactor coolant pump main flange bolting is ultrasonically examined, in place in accordance with the requirements of IWB-2600, Item BS. 1.

Both the main flange and seal housing bolting will be examined as required by IWB-2600, Item BS. 2 whenever a pump is disassembled for maintenance at the end of the ten-year interval when a pump will be disassembled for the performance required by Category B-1-1.

15.

The structure and nature of the material of integrally welded pump supports are such that it is opaque to ultrasonic transmis-sion.

Surface and visual examination will be performed as a substi-tute for volumetric.

16.

The reactor coolant pump casings in Surry Unit 2 are fabricated from two heavy wall austenitic steel castings joined together by a weld formed by the electroslag process.

The structure and nature of this material are such that it is opaque to ultrasonic trans-mission.

Volumetric examination as required by IWB-2600 will be attempted utilizing radiographic techniques.

The success of these examinations will be dependent upon the availability of high energy gamma sources and the level of background radiation.

Internal fittings in the pump may also provide restriction to the extent of examination that can be performed.

17.

Two of the pressurizer circumferential shell welds (C-5 and C-7) are not accessible for examination by volumetric or surface method due floor penetration and support structure interference.

They will be subject to visual examination for evidence of leakage during system pressure tests.

18.

Due to joint configuration of the nozzle to shell welds volumetric examination is impractical.

Surface examination will be done as a substitute.

19.

The regenerative heat exchanger is a three pass vessel, having a total of six head to shell welds and six shell to tubesheet welds.

Radiation levels adjacent to this heat exchanger are between six and seven R/hr.

The total time required for erection of scaffolding, removal of all insulation covering welds, cleaning, performing examinations and restoration of insulation could take a total of three to four hours for the examination of a 1/2" long portion of each of twelve welds in category B3.l, such that personnel involved could be subjected to a total accumulated dose of up to five-six man rem.

I C

0 *

• 0

• 0)_***.,

• • ~-,

I TINGHOUSE ELECTRIC CORP ATION

)-. -------~

FIGURE 1 STEAM GENERATOR PRIMARY NOZZLE SAFE-END TO PIPE WELD CONFIGURATION STEAM GENERATOR NOZZLE INTEGRALLY

• CAST WITH HEAD "BUTTERED" SAFE-END

. REACTOR COOLANT PIPE I

WELD DEPOSITED CLADDING

• ."T n------------------------------,c-=::,,u }:

.:;;~

tt*k

-::1\\

.,7.,

.. :~

'=*v***,

• }

.,... ______.STING HOUSE ELECTRIC COR._A_r_ro_N _________ l FIGURE 2 I

BRANCH NOZZLE CONNECTION WELD CENTERLINE.

NOZZLE NOZZLE FORGING REACTOR COOLANT PIPE

! f TABLE IWe-2600 ITEM NO.

Cl. 1 Cl. 1 Cl. 1 Cl. l Cl. 1 Cl. l Cl.2 Cl. 3 CL4

\\

\\

Cl. 1 C 1. 1 Cl. 2 Cl. 3 Cl. 4 TABLE U\\C-25:ZO EXAMINATION CATETORY C-A 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 SYSTf;M OR COMPONENT Steam Genera-ra tors (3)

(Shell Side) 2-.RC-E-lA 2-RC-E-lB 2;..RC-E-lC Residual Heat Exchangers (2)

(Tube Side) 2-RH-E-lA 2-RH-E-lB 81 H tY UNl'l' l lNSERlI ::JI INSPECTIOH ASME CODE C~ASS 2 COMPONENTS CODE APPLICABLE TO CONSTRUCTION IIIA

~

IIIC AREA TO BE EXAMINED Upper Head to Shell Weld Upper Shell to Transition Weld

• Tn~nsition to lower shell weld Lower Shell to Stub barrel weld Stub barrel to tubesheet weld Steam Outlet Nozzie to shell weld Feedwater Inlet Nozzle to shell weld

. Integrally Welded Supports

-Manway Bolting Head

• to Shell Welds Shell to flap.ge welds Nozzle to vessel welds Integrally Welded Supports Tubesheet Flange Bolting EXAMINATION REQUIREMENT Volumetric Volumetric Volumetric Volumetric Volumetric Volumetric**

Volumetric Not Applicable Visual and Volumetric

• Volumetric Volumetric Volumetric Surface Visual and Volumetric SECTION'* XI CODE RELIEF REQUESTED No No No No No No e

. No -

Note 1 No

• No No Yes -

Note 2 No No

fJI IUV IIN 1'1' 2' lNSElt\\'l..'.:I~ INSPECTION

,T ASME CODE CLASS 2 COMPONENTS TABLE TABLE I~-25:ZO SECTION.XI IWe-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED Cl. 1 C-A Excess Letdown III-C Head to shell weld Volumetric No Heat Exchanger (Tube side)

Cl. 1 C-A 2-CH-E-4 Shell to flange weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -

Applicable Note 3 Cl. 3 C-C Integrally welded supports Not No-,

Applicable Note Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric Cl. 1 C-A Non Regenera-III-C tive Letdown Head to shell weld Volumetric No Heat Exchanger (Tube Side) c 1. 1 C-A 2-CH-E-2 Shell ~o flange weld Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -

\\

Applicable Note 4 Cl. 3 C-C Integrally welded supports Surface No -~

\\

Cl. 4 C-D Pressure Retaining Bolting Visual and

- No Volumetric Cl. 1 C-A Seal Water III-C Head to sheli welds Volumetric No Heat Exchanger (Tube Side)

C 1. 1 C-A 2-CH-E-l Shel 1 to flange welds Volumetric No Cl. 2 C-B Nozzle to vessel welds Not No -

Applicable Note 5 l

i Bl n,1y UNI'l' !'

I I

INSER\\ 1 ~E INSPECTION ASME CODE C~ASS 2 COMPONENTS I

I TABLE I I TABLE Il\\U-25~0 SECTION XI IWe-2600 EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED CI.3 C-C Integrally welded supports Surface*

No Cl. 4 C-D Pressure Retaining Bolting Not No -

Applicable Note 5 Cl. I C-A Volume Control III-C Upper Head to shell weld Volumetric No Tank Cl. I C-A 2-CH-TK-2 Lower' head to shell weld Volumetric No e Cl. 2 C-B Nozzle to vessel welds Not No -

0 Applicable Note 6 I

CI.3 C-C Integrally. Weld~d Supports Surface No I i Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric I I Cl. I C-A Seal Water III-C Shell to flange weld Volumetric

• • No Injection l

Filters (2) cL I C-A 2-CH-FL-4A Head to shell weld Volume trlc..

No 2-CH-FL-4B

\\

t, ci. 2 C-B Nozz.le to vessel welds Not No --

Applicable Note

\\

CI.3 C-C Integrally Welded Supports Surface No Cl. 4 C-D Pressure Retaining Bolting Visual and No Volumetric Cl. I C-A Reactor Cool-III-C Cover Weldment to shell weld Volmetric Yes -

and Filter Note 8 Cl. I C-A 2-CH-FL-2 Head to.. shell weld Volumetric Yes -

Note 8 I

• 1

I TABLE IWe-2600 ITEM NO.

Cl. 2 Cl. 3 Cl. 4 Cl. 1 Cl. l Cl. 2 Cl. 3 Cl. 4 C2.1

\\

C2.2 C2.3 C2.4 TABLE I00-25~0 EXAMINATION CATETORY C-B C-C C-D C-A C-A C-B C-C C-D SYSTEM OR COMPONENT Seal Water Return Filter 2-CH-FL-3 C-E;C-G

.. Piping Systems C-F;C-G C-F;C-G C-D 8111 ;lY UNl'l' !*

INSEfil 'i ::E INSPECTION ASME CODE CLASS 2 COMPONENTS CODE APPLICABLE TO CONSTRUCTION III-C AREA TO BE EXAMINED Nozzle to vessel welds Integrally Welded Supports Pressure Retaining Bolting

• Cover Weldment to shell weld Head to shell weld Nozzle to vessel welds Integrally welded supports Pressure Retaining Bolting

• Circumferential Rµtt Welds Longitudinal weld joints in fit tings Branch Pipe to Pipe Welds Pressur1r Retaining Bolting EXAMINATION REQUIREMENT Not Applicable Surface Not Applicable Volumetric Volumetric Not Applicable Surface Not Applicable Volumetric Volumetric Volumetric Visual and Volumetric SECTION XI CODE RELIEF REQUESTED No -

Note 8 No

• *No -

Note 8

, Yes*-

Note 8 Yes -

Note 8 No -

Note 8

• No No Note 8 Yes -

Note 9 No e" Yes -

Note 10 No

fll 'IHl'l UNl'l' l!

INSER\\'ICI<~ INSPl~CTION ASME CODE CLASS 2 COMPONENTS TABLE TABLE I~-2sio SECTION* XI IWe-2600

• EXAMINATION SYSTEM OR CODE APPLICABLE EXAMINATION CODE RELIEF ITEM NO.

CATETORY COMPONENT TO CONSTRUCTION AREA TO BE EXAMINED REQUIREMENT REQUESTED C2.5 C-E-1 Integrally Welded Supports Surface No C2.6 C-E-2 Support Components Visual No C3.1 C-F Residual Heat Pump Casing Welds Not No -

Removal Pumps (2)

Applicable Note 11 C3. 2 C-D 2-RH-P-lA Pressure Retaining Bolting Visual and No e 2-RH:...P-lB Volumetric C3. 3 C-E-1 Integrally Welded Supports Not No -

Applicable

_Note 11 C3.4 C-E-2 Support Components Visual No C3.1 C-D.

Charging Pumps (3)

Pump Casing Welds

.Not

. No Applicable Note 11 C3.2 C-D 2-CH-P-lA Pressure Retaining Bolting Visual and No 2-CH-P-lB Volumetric 2-CH-P-lC C3. 3 C-E-1 Integrally Welded Supports Not No -

\\

t, Applicable Notej C3.4 C-E-2 Support Components Visual No

\\

C4.1 C-F; C-G Valves Valve Body Welds Not No Applicable Note 12 C4.2 C-D Pressure Retaining Bolting Visual and No Volumetric*

C4.3 C-E-1 Integrally Welded Supports Not No -

Applicable Note 12 j

C4.4 C-E-2 Support Components.

Visual No

SURRY UNIT 2 INSERVICE INSPECTION ASME CODE CLASS 2 COMPONENTS NOTES

1.

There are no i terns in this category on this component in the Surry Unit 2 Class 2 systems.

2.

. The nozzle to vessel welds of the residual heat exchangers are covered by l" thick by 3" wide reinforcement pad as shown in Figure

3.

These welds are not accessible for examination by volumetric or surface methods.

The area will be subject to visua:l examination for evidence of leakage during system pressure tests.

3.

Excess Letdown Heat Exchanger nozzles are 2" diameter.

There are not any integrally welded supports on this vessel.

Therefore no examination is required under these categories.

4.

Non Regenerative Letdown Heat Exchanger nozzle to vessel welds are 2" diameter and therefore requires no examination under this category.

5.

Seal Water Heat Exchanger nozzle to vessel welds are 4" diameter and the pressure retaining bolting is.75" diameter therefore they require no examination under this category.

6.

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

7.

Seal Water Injection Filters nozzle to vessel welds are 2" diameter, therefore require no examination under this category.

8.

Reactor Coolant Filter and Seal Water Return Filter nozzle to vessel welds are 3" diameter and the bolting is. 75" diameter therefore no examination is required under these categories.

The thickness of the materials (0. 188" thick) used for the cons true tion of these filters is such that meaningful results could not be expected with ultrasonic examination as required by IWC-2600.

Surface and visual examination of these welds (Cover weldment to shell and head to shell) will be performed as an alternative method.

9, Examination of Class 2 piping sys terns is limited to those occurring at geometric discontinuities such that some limitations may be expected at all locations.

For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces.

Examination from the fitting side would be dependent upon the geometric configura-tion.

Where elbows or tees are concerned, examination can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling.

No examination can be performed from the fit ting side when it is a valve or a flange.

In all cases one hundred percent of the weld material can be examined.

In instances where welds occur at fitting to fitting access 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.

Welds in the Surry Unit 2, Class 2 system with limi-tations at geometric discontinuities are:

(i)

Loop 1 Mainsteam; welds 20, 18, 15, 11, 2, 4, 6, 8 (ii)

Loop 1 Mainsteam By-Pass; welds 12, 7, 19, 1 (iii)

Loop 2 Mainsteam; welds 2, 4, 6, 8, 11, 12, 18, 20 (iv)

Loop 2 Mainsteam By-Pass; welds 7, 12, 19, 1 (v)

Loop 3 Mainsteam; welds 2, 4, 6, 8, 11, 12, 18, 20 (vi)

Loop 3 Mainsteam By-Pass; welds 7, 12, 19, 1 (vii) 10" RHR; welds 14

10.

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.

11.

The residual heat removal pumps and charging pumps do not have any pump casing welds or integrally welded supports.

12.

There are no valve body welds or integrally welded supports on the valves in Surry Unit 2.

~

C 0..

~-

. __.,U ESTINGHOUSE ELEC1RIC CO RATION FI'1URE-3 RESIDUAL -HEAT REMOVAl HEAT EXCHANGER

---~--....i.

........ /'CHANNEL HEAD FLANGE

- NOZZLE TO VESSEL WELD 1

1

' THICK. REINFORCEMENT PAD

-~

NOZZLE.10" SCH 40S

{.TYPICAL OF TWO)

.875~ THICK SHELL AND HEAD fi I

---

~

.. **~-

• ..JJ

).}"

-~.,

ESTINGHOUSE' ELECTRIC COR RATION

... - -- -**--* ~-...

BRANCH NOZZLE CONNECTION WELD CENTERLINE NOZZLE Figure 4 NOZZLE FORGING PIPE I

I i

SYSTEM Chemical and Volume Control Main Steam to Turbine Driven Auxiliary Feedwater Pump Auxiliary Feed water SURRY UNIT t'Z::

INSERVICE -INSPECTION ASME CODE *CLASE 3 COMPONENTS COMPONENT DESCRIPTION/IDENTIFICATION Boric Acid Tank 1-CH-TK-lC Boric Acid Transfer Pump l-CH-P-2C Boric Acid Transfer Pump l-CH-P-2D Boric Acid Filter 2-CH-FL-l.

. Boric Acid Blender 2-CH-BL-l Piping Supports and Hangers Piping Supports & Hangers Auxiliary Feed Pump 2-FW-P-2 (Turbine Driven)

Auxiliary Feed Pump 2-FW-P-3A (Motor Driven)

Auxiliary Feed Pump 2-FW-P-3B (Motor Driven)

COI:-E APPLICAELE TO CONSTRUCTION VIII IIIC Auxiliary Feed Pump 2-FW-P-2 Oil Cooler METHOD OF EXAMINAT:tON 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 /Ope rating Pressure Visual /Ope rating Pressure t

SECTION XI CODE RELIEF REQUESTED

SYSTEM Auxiliary Feedwater Circulating and Service Water SURRY UNIT ti::

-INSERVICE INSPECTION ASME CODE *CLASS 3 COMPONENTS COMPONENT DESCRIPTION/IDENTIFICATION CODE APPLICABLE TO CONSTRUCTION Auxiliary Feed Pump 2-FW-P-3A Oil Cooler Auxiliary Feed Pump 2-FW-P-3B Oil Cooler Condensate Storage Tank Z.:-CN-TK-1 Piping Supports and Hangers Recirculation Spray Heat Exchanger 2-RS-E-lA (tube. side)

Reclrculaton Spray He_at Exchanger 2-RS-E-lB (tube side)

Recirculation Spray Heat Exchanger*

2-RS-E-lC (tube side)

Recirculation Spray Heat Exchanger 2-RS-E-lD (tube side)

Component Cooling Water Heat Exchanger 1-CC-E-lC (tube side)

Component Cooling Water Heat Exchanger 1-CC-E-lD (tube side)

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/Opera ting Pressure SECTION XI CODE RELIEF REQUESTED

SYSTEM Circulating and Service Water SURRY UNIT (l.;

-INSERVICE. INSPECTION ASME CODE *CLASS 3 COMPONENTS COMPONENT DESCRIPTION/IDENTIFICATION.

Charging Pump 2-CH-E-5A Lubricating Oil Cooler Charging Pump 2-CH-E-5B Lubricating Oil Cooler Charging Pump 2-CH-E-5C Lubricating Oil Cooler Charging Pump 2-CH-E-7A Seal Cooler Charging Pump 2-CH-E-7B Seal Cooler*

Charging Pump 2-CH-E-7C Seal Cooler Charging Pump 2~CH-E-7D Seal Cooler Charging Pump 2-CH-E-7E Seal Cooler Charging Pump 2-CH-E-7F Seal Cooler Charging Pump Seal Cooling Surge Tank 2-CC-TK-3 CODE APPLICABLE TO CONSTRUCTION Charging Pump Cooling Water Pump 2-CC-P-2A Charging Pump Cooling Water Pump 2-CC-P-2B METHOD OF EXAMINATION Visual/Operating Pressure Visual/Operating Pressure

• Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Visual/Operating Pressure Visual/Operating Pressure Visual/Operating

.Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure SECTION XI CODE RELIEF REQUESTED

SYSTEM Circulating and Service Water Component Cooling Water SURRY UNIT ti.:

-INSERVICE..J NSPECTION ASME CODE *CLASS 3 COMPONENTS CODE COMPONENT DESCRIPTION/IDENTIFICATION APPLICAP.LE TO CONSTRUCTION Charging Pump Intermediate Seal Cooler 2-SW-E-lA Charging Pump Intermediate Seal Cooler 2-SW-E-lB Charging Pump Service Water Pump 2-SW-P-lOA Charging

• Pump Service Water Pump 2-SW-P-lOB Recirculation Spray Hx Radiation Monitori-ing Sample Pump 2-SW-P-5A Recirculation Spray Hx Radiation Monitro..,.

ing Sample Pump 2-SW-P-SB Recirculation Srpay Hx Radiation Monitor-ing Sample Pump 2-SW-P-5C Recirculation Spray Hx Radiation Monitor-ing Sample Pump 2-SW-P-SD Piping Supports and Hangers Reactor Coolant Pump 2-RC-P-lA Oil Cooler Reactor Coolant Pump 2-Rc....:P-lB Oil Cooler Reactor Coolant Pump 2-RC-P-lC Oil Cooler METHOD OF EXAMINATION Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure Visuai/Operating Pressure Visu.al/Operating Pressure Visual/Operating Pressure Visual Visual /Ope rating Pressure Visual/Operating Pressure Visual/Operating Pressure SECTION XI CODE RELIEF REQUESTED

SYSTEM Component Cooling Water SURRY UNIT (i.:

,!NSERVICE,INSPECTION ASME CODE *CLASS 3 COMPONENTS COMPONENT DESCRIPTION/IDENTIFICATION Reactor Coolant Pump 2-RC-P-lA Shroud Cooling Coil 2-VS-E-6A Reactor Coolant Pump 2-RC-P-lB Shroud Cooling Coil 2-VS-E-6B Reactor Coolant Pump 2-RC-P-lC Cooling Coil 2-VS-E-6C Excess Letdown Heat Exchanger 2-CH-E-4 (shell side)

Residual Heat Removal Pump Seal Cooler 2-RH-E-2A Residual Heat Removal Pump Seal Cooler 2-RH-E-2B Residual Heat Removal Heat Exchanger 2-RH-E-lA (shell side)

Residual Heat Removal Heat Exchanger 2-RH-E-lB (shell side)

Reactor Containment Air Recirculation Cooler 2-VS-E-2-A Reactor Containment Air Recircula tlon Cooler 2-VS-E-2-B Reactor Containment Air Recircula-tion Cooler 2-VS-E-2-C CODE APPLICABLE TO CONSTRUCTION VIII 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/Operating Pressure Visual/Operating Pressure Visual/Operating Pressure SECTION XI CODE RELIEF REQUESTED r,

SYSTEM Component Cooling Water SURRY UNIT (l:;

.INSERVICE -INSPECTION ASME CODE *CLASS 3 COMPONENTS COMPONENT DESCRIPTION/IDENTIFICATION Non Regenerative Heat Exchanger 2-CH-E-2 (shell side)

Seal Water Heat Exchanger 2-CH-E-l (shell side)

Component Cooling Pump 1-CC-P-lC Component Cooling Pump 1-CC-P-lD Component Cooling Water Heat Exchanger 1-CC-E-lC (shell side)

• Component Cooling Water Heat Exchanger 1-CC-E-lD (shell. side)

Piping Support and Hangers CODE APPLICABLE TO CONSTRUCTION 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 SECTION XI CODE RELIEF REQUESTED

• ,i, ATTACHMENT B SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE TESTING REQUIREMENTS FOR PUMPS AS SET FORTH IN SUBSECTION IWP TO SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THROUGH THE S"ill'1MER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)

The enclosed tabulations provide a listing of the Class 1, 2, and 3 pumps which are subject to the testing requirements of Subsections IWP of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Addenda thru the Summer of 1975.

This tabulation identifies the pumps to be tested, code class, test flow path system resistance, and required test quantities and frequencies.

Relief from test requirements is requested in cases where their test requirements have been determined to be impractical.

Where relief is requested, technical justification is provided along with alternative test methods when applicable.

SURRY UN!T 2.

Page 1 INSERVICE TESTING

. ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP I I

SYSTEM MARK PUMP CODE RESIS-TEST RELIEF I

NUNBER nFSC:RIP'l'ION CLASS TANCE TEST QUANTITIES FREQUENCY REQUESTED REMARKS r--:-

l 2-CH-P-lA High Head 2

FIXED or Speed (if variable)

NA CONSTANT 2-CH-P-lB Safety Injection

• VARIABLE Inlet Pressure (Pi)

Monthly YES-NOTE 1 2-CH-P-lC (Charging)

(NOTE 2) Differential Pressure (AP)

Monthly (Dwg. No. 11548-

'Flow Rate (Q)

Monthly NOTE 2 FM-88B)

Vibration Amplitude (V)

Monthly Bearing Temperature (Tb)

Yearly Lubricant Level or Pressure Monthly 1-SI-P-lA Low Head 2

FIXED Speed (if variable)

NA CONSTANT a-sI-P-lB Safety Injection Inlet Pressure (Pi)

Monthly YES-NOTE 3 (Dwg. No. 11648-Differential Pressure (AP)

NA FM-89A)

Flow Rate (Q)

Monthly Vibration Amplitude (V)

Monthly Bearing Temperature (Tb)

NA NOTE 4 Lubricant Level or Pressure NA NOTE 4 2-CS-P-lA Containment Spray 2

FIXED Speed (if variable)

NA CONSTANT 2-CS-P-lB (Dwg. No. 11548-Inlet ~)ressure (Pi)

Monthly I

FM-84A)

Differential Pressure (.AP)

NA Flow Rt1te (Q)

• Monthly e

Vibrat:Lon Amplitude (V)

Monthly Bearing Temperature (Tb)

Yearly Lubricant Level or Pressure Mont.hly i

b 2-RS-P-2A Outside Recirc-2 FIXED Speed (if variable)

NA CONSTANT I 2-RS-P-2B ulatlon Spray Inlet Pr.essure (Pi)

NA Yes-Note 5 I

(Dwg. No. 11548-Differential Pressure (AP)

Monthly FM-84A)

Flow Rate (Q)

NA Vibration Amplitude (V)

Monthly I

Bearin3 Temperature (Tb)

NA Note 4

I Lubricant Level or Pressure i I 1

I

Page 2 SURRY UNIT 2.

INSERVICE TESTING

• ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RESIS-TEST.

RELIEF Nm*ffiER n"RSCRIPTION rr ASS TANCE TEST QUANTITIES FREQUENCY REQUESTED REMARKS NA CONSTANT I 2-RS-P-lA Inside Recircu-2 FIXED Speed (if variable)

NA Yes-Note 6 2-RS-P-lB lation Spray Inlet Pressure (Pi)

NA (Dwg. No. 11548-Differential Pressure (AP)

NA Yes-Note 6 FM-84A)

Flow Rate (Q)

NA Yes-Note 6 Vibration Amplitude (V)

NA Note 4 Bearing Temperature (Tb)

NA Note 4 Lubric,mt Level or Pressure Monthly Note 8 2-FW-P-3A Auxiliary 3

FIXED Speed (if variable)

Monthly 2-FW-P-3B Feed water Inlet Pressure (Pi)

Monthly.

2-FW-P-2 (Dwg. No. 11548-Differential Pressure (AP)

NA FM-~8A)

Flow Rate (Q)

Monthly Vibration Amplitude (V)

-Yearly Bearing Temperature (Tb)

Monthly Lubricant Level or Pressure NA CONSTANT 2-RH-P-lA Residual Heat 2

FIXED

$peed (if variable)

Cold Shutd Yes-Note.

own 2-RH-P-lB Removal (Dwg.

Inlet Pressure (Pi)

Cold Shutd JWO Yes-Note,

11548-FM-87A)

Differential Pressure (AP)

Cold Shutd awn Yes-Note,

Flow Rate (Q)

Cold Shutd own Yes-Note,

Vibration Amplitude (V)

NA Note 4 Bearing Temperature (Tb)

NA Note 4 Lubricant Level or Pressure NA CONSTANT 1-CC-P-lC Component Cooling 3

VARIABLI Speed (if variable)

Monthly Yes-Note 9 1-CC-P-lD (Dwg. No. 11448-Inlet Pressure (Pi)

Monthly Yes-Note 9 FM-72D)

Differential Pressure (AP)

Monthly Yes-Note 9 Flow Rate (Q)

Monthly Vibration Amplitude (V)

Yearly Bearing Temperature (Tb)

Monthly Lubricant Level or Pressure I

l

(

I r

I

SURRY UNIT 2.

• Page 3 INSERVIC3 TESTING

. ASME CODE CLASS 1, 2 AND 3 PUMPS PUMP SYSTEM MARK PUMP CODE RESIS-TEST..

RELIEF NlThmER nFSCRIPTION l"T ASS TANCE TEST OUANTITIES FREQUENCY REQUESTED REMARKS l-CH-P-2C Boric Acid 3

FIXED Speed (if variable)

NA CONSTANT 1-CH-P-2D Transfer Inlet Pressure {Pi)

Monthly Yes-Note 10 (Dwg. No. 11448-Differential Pressure (AP)

Monthly FM-88A Flow Rate (Q)

NA Vibration Amplitude (V)

NA Yes-Note 10 Bearing Temperature (Tb)

NA Yes-Note 10 Lubricant Level or Pressure NA Note 10 2-CC-P-2A Charging Pump 3

FIXED Speed (if variable)

NA CONSTANT 2-CC-P-2B Cooling Water Inlet Pressure (Pi)

NA Yes-Note 11 (Dwg. No. 11548-Differential Pressure (AP)

NA FM-:7IB)

Flow Rate (Q)

Monthly Vibration Amplitude (V)

Monthly Bearing Temperature (Tb)

NA Note 12 Lubricant Level or Pressure 2-SW-P-lOA Charging Pump 3

VARIABLl Speed (if variable)

NA CONSTANT 2-SW-P-IOB Service Water Inlet Pressure (Pi)

NA Yes-Note 13 (Dwg. No. 11548 Differential Pressure (AP)

NA Yes-Note 13 FM-7IB)

Flow Rate (Q)

Monthly Vibration Amplitude (V)

Monthly Bearing Temperature (Tb)

NA Note 12 Lubricant Level or Pressure NA Note 12 I

Speed (if variable)

Inlet Pressure (Pi)

Differential Pressure (AP)

Flow Rate (Q)

Vibration Amplitude (V)

Bearin1 Temperature (Tb)

Lubricant Level or Pressure I

SURRY UNIT 2 INSERVICE TESTING 8

ASME CODE CLASS 1, 2 and 3 PUMPS NOTE

1.

Suction pressure instrumentation is not installed nor required.

There pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure is nominally 15 to 20 psig.

Therefore, the~ developed by the pump is more than 100 times the suction pressure and a gage for suction pressure would not provide significant data.

We propose to observe VCT pressure using control room indication to assure repeated initial conditions for testing the pumps.

This indication is approximately 4% accurate.

2.

When the nonoperating pump is tested on recirculation flow, the flow path is a fixed resistance system and it is required to measure

~ 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~ and Q.

3.

No inlet pressure instrumentation is installed for these pumps.

These pumps take suction from the RWST for performance testing.

This tank has a minimum level required by the Technical Specifica-tions which is observed from the Control Room.

Tank level will be used to establish initial conditions for testing.

4.

Proper lubricant level or pressure cannot be observed since bearings are in main flow path.

Reference is made to IWP-4310 which establishes exception to Tb for bearings within the main flow path.

5.

These pumps are flow tested at shut of head as required by T.S.

4.5.A.3 by filling pump casings with water and running on recircula-tion flow path.

Suction pressure is the same for each test (head of water with casing filled) and thus will not be measured.

6.

These pumps cannot be tested to code requirements as the test would require filling the sump and spraying water on components in the containment.

Pump current is the only pump parameter measured, this*

test is performed monthly.

This system is always dry which prevents longer pump run time, (30 seconds max) and prevents performing periodic flow testing.

7.

It is considered impractical to make a containment entry on a monthly basis in order to test these pumps.

These pumps are not Engineered Safety Feature pumps.

Operability during use can be determined by monitoring reactor coolant system temperature.

Testing as required by subsection IWP will be performed during cold shutdown provided that containment is accessable.

8.

The turbine-driven auxiliary feed pump speed will be measured monthly.

The motor-driven auxiliary feed pumps are not required to have the speed measured.

ATTACHMENT C SURRY UNIT 2 REQUESTED RELIEF FROM THE INSERVICE TESTING REQUIREMENTS FOR VALVES AS SET FORTH IN SUBSECTION IWV TO SECTION XI OF THE ASME BOILER AND PRESSURE VESSEL CODE, 1974 EDITION WITH ADDENDA THRU THE SUMMER OF 1975 (LAST 40 MONTH PERIOD OF THE FIRST 10 YEAR INTERVAL)

The enclosed tabulation provides a listing of the Class 1, 2 and 3 valves which are subject to the testing requirements of Subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, with Mdenda thru the Summer of 1975.

This tabulation identifies the valve to be tested, drawing location, function, code class, category, size, valve type, actuator type, normal position and test requirements.

Relief from test requirements is requested in cases where these test requirements have been determined to be impractical.

Where relief is requested, technical justification is provided along with alternative test methods when applicable.

Leak testing of containment isolation valves shall be performed in accordance with Appendix J of 10CFR50 in lieu of ASME Section XI subsub-article IWV-3420.

There are no testable Category D valves in Surry Unit 2 Systems.

Any inspection requirements identified as impractical during the course of the inspection period will be noted and included in the inspection program at the time of the next revision.

Any valve which when exercised could put the plant in an unsafe condition will not be tested.

Below are some examples of the types of valves specifically excluded from exercising tests during plant operation:

(i)

All valves whose failure in a non-conservative position during the cycling test would cause a loss of system function will not be exercised.

Valves in this category would typically include all non-redundant valves in lines.

Some valves may fall into this category under certain system configurations or plant opera ting modes.

(ii) All valves, whose failure to close during a cycling test would result in a loss of containment integrity.

Valves in this category would typically include all valves in containment penetrations where the redundant valve is open and inoperable.

(iii) All valves, which when cycled, could subject a system to pressures in excess of their design pressures.

It is assumed for the purpose of a cycling test, that one or more of the upstream check valves has failed unless positive methods are available for determining the pressure or lack thereof on the high pressure side of the valve to be cycled.

e This valve testing program addresses those valves for which demonstration of operability is necessary to assure safe shutdown of the unit or mitigation of the consequences of an accident.

The program has been reviewed to assure that testing the valves at the intervals specified will not place the plant in an unsafe condition.

Where practical, valves will be cycled at 3 month test intervals.

When a commitment is made to test valves during hot or cold shutdown it is not intent to shutdown the unit solely for the purpose of valve testing nor to perform the testing more often than once per 92 days due to more frequent shutdowns.

The following clarification shall apply to those valves which are scheduled to be exercised during cold shutdown:

"Valve testing shall commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown and continue until complete or unit is ready to return to power.

Completion of all valve testing is not a prerequisite to return to power."

Reactor coolant Class land Class 2 pressure boundary valves have not been included in the test program.

The reactor coolant pressure boundary is subject to pressure tests and adequately monitored for leakage following each refueling in accordance with the requirements of Article IWB-5000.

Gross leakage test requirements for check valves providing Class 1 to Class pressure boundaries are defined in 4.5.B.2(c) and (d) of the Surry technical specification.

Article IWV-3520(b) requires that check valves be exercised to the position required to fulfill their function.

Check valves at Surry are not equipped with position indicating devices and verification of operation to the required position will be achieved by observing that normal required flows are established in the systems.

The stroke times of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation.

Exception is taken to complying with stroke time variations defined by Article IWV-3410(c) (3).

The valve stroke timing tolerance specified is based on a reference valve.

This will not exceed the maximum stroke time.

A review of containment isolation valves is being conducted to ensure compliance to Appendix J of 10CFRSO.

At the completion of this review some valves may be added to this program.

'~ '

e TEST REQUIREMENTS SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES LEGEND SP - SETPOINTS of safety and relief valves shall be tested per Section XI subsubarticle IWV-3510 or as modified by specific relief request.

VP - VALVE POSITION shall be verified per Section XI subarticle IWV-3700 or as modified by specific relief request.

CV -

CHECK VALVES shall be exercised at least once every (3) months per Section XI subsubarticle IWV-3520 or as modified by specific relief request.

LT - LEAK TESTS shall be performed per Section XI subsubarticle IWV-3420 or as modified by specific relief request.

EV - EXERCISE VALVE for operability at least once every (3) months per Section XI subsubarticle IWV-3410 or as modified by specific relief request.

ST - STROKE TIMES shall be measured per Section XI subsubarticle IWV-3410 or as modified by specific relief request.

VALVE POSITIONS 0-0pen C-Closed OC-Open or Closed T-Throttled VALVE TYPES CK-Check RE-Relief SF-Safety BA-Ball GL-Globe GA-Gate BU-Butterfly SCK-Stop Check PL-Plug DA-Diaphram ACTUATOR TYPES SA-Self Actuating MO-Motor PN-Pneumatic HW-Handwheel

SURRY UNIT 2.

INSERVICE TESTING

.*

• ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE,f N~-IBc-....-----J¥:1..A1a1..I.LJN.11-.S~Tu:E~AU!IM'-----'--------

DRAW.NO. ----------------

11548-FM-64A PAGE 1 --

I

'VAL'VE DRAW.

CODE CATE-SIZE VALVE ACTUA-NORHAL TEST RELIEF NlJZEER LOCN.

FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-REQ.

REQUES1 a:ce..e._ 'l'I0N SV-MS201A,B,C B-3,B-4,B-6 Main Steam Safety Valves 2

C 4

SF I SA C

SP YES i

~

(1)

SV-MS202A,B,C C-3,C-4,C-6 Main Steam Safety Valves 2

C 6

-SF SA C

SP YES (1)

SV-MS203A,B,C B-3,B-4,B-6 SV-MS204A,B,C B-3. B-4. B-6 SV-MS205A,B,C C-3,C--4,C-6

. TV-MS201A,B,C D-3,D-:-5,D-7 Main Steam Line Trip Valves 2

B 30 CK PN 0

EV YES ST

( 1)

PCV-MS2Q2 F-8 Main Steam to Turbine *Driven 3

B 3

GL PN C

EV NO Auxiliary Feedwater Pump ST MOV-MS202.

G-8 Main Steam. to Turbine Driven 3

B 3

GA MO C

EV NO j

Auxiliary Feedwater Pump ST 1

I l 2-MS-176, 178, F-8,F-8,F-8 Main Steam.to Turbine Driven 3

c.

3 CK SA C

CV NO 182 Auxi 1 ia ry Feed water Pump a*

Check Valves NRV-MS201A,B,C D-3, D-5, D-6 Main Steam Non-Return Valves 2

C

• 30 SCK MO 0

CV YES (1)

TV-MS209 F-7 Main Steam Drain to

• B 3

GA PN 0

EV NO I

Condenser ST I

TV-MS210 E-7 Main Steam Drain B

2 GA PN 0

EV NO I

to I

Blowdown

• ST I

j NRV-MS-202 A,B,C C-2,C-4,C-6 Decay. Heat Release Non-Return 2

C 3

SCK HW C

CV NO I I I Valve I

t i

I

~

l I

~

I I

I I

l I

I I

SURRY UNIT t.

lNSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME~~~~~A~U~X_._s_T_E_AM~~&_A_I~R __

R_FM_O_V~A~L ____ _

DRAW,N0.~--~~.....:;,.;11~5_4~8_-~FM_-_6~6=A~~---

VALVE DRAW.

CODE CATE-SIZE VALVE ACTUA-NORMAL NUMBER LOCN.

FUNCTION

. CLASS GORY (IN.)

TYPE TOR POSI-i'T'YPF TION

• TV-SV202 L-2 Air Removal*Divert A

6 GA PN C

to Reactor Containment TV-SV203 L-2 Air Removal Divert. to B

6 GA PN 0

Atmosphere 2-VP-12

.L-1 Air Removal Divert AC I.

6 CK SA C

to Reactor Continment I

I

(

i I I I

~

I PAGE_L_

TEST RELIEF REQ.

REQUES1 LT NO EV ST LT NO EV ST LT Yes CV (26) r

SURRY UNIT 2.

INSERVICE TESTING

.. ASI1E CODE CLASS 1, 2 A..."ID 3 VALVES SYSTEH NA.'fE~ _____

F_E_E_D_W_A_T_E_R ________ _

DRAW. NO.

11548-FM-68A PAGE._L_

~---V-AL-\\-1E-*---,---D-RA-W-.--.r1-*---------------

1 r,-C-O_D_E~-C-A-T-E-,J SIZE VALVE

'ACTUA-NORMAL TEST RELI~

~u"l*3ER LOCN.

FUNCTION CLASS G07..Y (IN.)

TYPE !TOR POST-

REQ, REQUES ~1

)TYPf.'

'T'l()N I

--*-------!'-- ---*~ ~--t.-'-'~-.....:',--,..c~-,,s.,--.~--.,,~ rnmo.-,,,.,_,_,

A

• 11 F a H *d 2

c 1*.

3 I CK SA c

cv YES 2-FW-27, 58, 89 2-FW-10, 12, 41, 43, 72, 74 MOV-FW251A, B, C, D,E,F 2-FW-131, 133, 13§, 138 2-FW-142, 157, 172 2-FW-144, 159 174 C-2,B-4,~-5 C-2, C-2 C-4,C-4, C-5,C-5 B-6, B-6, B-6,B-6, C-6,C-6 C-6,C-6, C-6,C-6 D-7,E-7 F-7 D-7,E-7,F-7 ux1

• ary ee water ea er Check Valves at Main (2)

Feedwater Header Main Feedwa ter Check Valves at Containment Penetrations Auxili<;try Feedwa ter to Steam Generators Auxiliary Feedwater Header Check Valves at Containment Penetration Auxiliary feedwater Pump Discharge Check Valves Auxiliary Feedwater Pump Recirculation Check Valves 2 I 3

3 3

3 C

14 B

3 C

6 C

6 C

1 I

1 CK SA 0

GL MO 0

CK SA C

CK SA C

CK SA 0

CV EV ST CV CV CV YE~

(3).1 NO YES (2)

YES (2)

NO -

SURRY UNIT 2.

INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME-__~~~CR=O=S=S~-~C~Q~N=N=EC=T~S......,F~O~R......_.A~UX~I~J~,I-A~R~Y_._F_EE....,D PAGE-4._

VALVE DRAW.

CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.

FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-REQ.

REQUES1 l1'YPF.

TION MOV-FW260A,B J-5,J-6 Cross-Connects for Unit No. 2 i 3

B r 6 GL MO C

EV NO Aux. Feed from Unit No. 1 i

ST 2-FW-272, 273 I-7, I-7 Cross-Connect for Unit No. 2 3

• C 6

• CK SA C

CV YES Aux. Feed from Unit No. 1 c2>9 Check Valves at Cont. Penet.

i

~

I r

2-FW-305, 306 H-7,H-7 Cross-Connect for Unit No. 2 3

.C I 6

CK SA C

CV YES I

Aux. Feed from Unit No. 1 (2)

Check Valves I I I

(

I

SURRY UNIT 2.

INSERVICE 'fESTING

.... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME _________ s_E_R_v_rc_E __

W_A_T_E_R __________ ~

DRAW, NO *. ____

_.;;..11.;.:5:....;4;.;;;8_-,;;;,.:FM;.:.-...;7.;.:l;.:.A:;__ __ _

PAGE 5 VALVE DRAW.

CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER

LOCN, FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-REQ.

REQUES'l i'T'YPF.

TIOl\\T

~

MOV-CW206A,B, E-4,E-4, Condenser Inlet 3

B ;

96 BU MO 0

EV NO C,D F-4,F-4 Isolation Valves ST MOV-SW202A,B E-'6,F-6 Service Water to 3

B 42 BU MO

• o EV NO Service Water Pumps ST -

MOV-SW203A,B, B-6,B-6 Service Water to Recircula-3 B

30 BU MO C

EV YES C,D D-6,E-6 tion Spray Heat Exchangers ST (4)

MOV-,-SW204A, B, A-2, B-2, C-2, Recirculation Spray Heat 3

B 24*

BU MO 0

EV NO C,D C-2,A-2,A-2, Exchangers Isolation. Valves ST MOV-SW205A,B, B-2,C-2.

f C,D MOV-SW206A,B D-4,D-4 Recirculation Spray Heat

3.

B 36 BU MO 0

EV NO Exchangers Cross Connect ST Valves MOV-SW201A,B B-4C-4 Bearing Cooling Water 3

B 36 BU MO 0

EV NO Heat Exchanger Isolation ST Valves I

I I I I

i I

I I

I l

/ !

1~

I i I

l I

l I I

I SYST:::}f NA}IB VALVE 11.Jl-1:BER 2-CC-764, 329 2-SW-113, 108 SURRY UNIT 2.

INSERVICE TESTING

.... ASME CODE CLASS 1, 2 AND 3 VALVES CIRCULATING & SERVICE WATER DRAW.

CGJE LOCN.

N..:7CTION CLASS r

D-6,G-_6 Charging Pump Cooling Water 3

Pump Discharge Check Valve D-8, G-8 Charging Pump Service Water 3

Pump Check Valve I l J

DRAW. NO

• _____

1...,1._5,...4~8==...,.,FM""""'"7~lwl3----

PAGE-6--

ACTUA-NORMAL TEST RELIE~

TOR POSI-

-~-R,...E...,,*Q...,,. ___ "'.:~.t:Q**-~-~~-11

~- TJ.. mL_..,_

No SA QC CV I

i SIZE VALVE CATE-I GORY I (IN.)

TYPE

• I C

2 CK C

2

. CK SA oc CV

• NO e1 I

I I

~. 1*'**....... *,"~**.. **'*;,*.-':,.*.';lo- '*

SURRY UNI'.~ 2:

INSERVICE T' rnTING ASHE CODE CLASS 1* l AND 3 VALVES SYSTEM NAHE. ____

c_o_M_P_O_N_E_N'_r _c_o_o_L_I_N_G_\\_-lA_T_E_R __

PAGE -

VALVE DRAW.

CODE CATE-SIZS VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.

FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-REQ.

REQUES1 TYPE TION RV-CC2l9A.B

.-2, L-3 Component Cooling from RHR

• 3 C

1~

RE SA C

SP NO I

Heat Exchanger Relief Valve I I I I 2-CC-17 6, 177 l-1,B-l

.Component Cooling to RHR lleat 3

C 18 CK SA oc CV YES I

Exchanger Che~k Valves

, I (5) 2-CC-l, 58, 59

1.-2,A-2,A-2 Component.Cooling to Reactor 3

.c 6

CK SA 0

CV YES Coolant Pumps (6)

' I I

I t l

\\

l*

I I

~

SURRY UNIT 2°_

INSERVICE TESTING AS:ME CODE CLASS 1, 2 AND 3 VALVES S"l"ST:21 NPJ-fE _______

C_OM_P_O_N_E_N_T_C_O_O_L_I_N_G ____ _

DRAW.N0. _______

1_1_54_8_-_FM_-_7_2_B ___ _

l

~CTUA-VAL'.7E DRAW.

I CODE CATE-SIZE VALVE NORMAL I I NlfBER LOCN. FUNCTION GORY (IN.) TYPE TOR POSI-I CLASS l.J.l.Q~ YrlL_. 2-CC-242, 233, C-2 D-2 E-2 Component Cooling to 3 C 6 CK i SA 0 224 Reactor Containment Air Recirculation Coolers I RV-CC212A,B,C D-3, E-3, F-3 Component Cooling.from 3 C 3/4 RE SA C Reactor Containment Air I Reclrc. Coolers Relief I I I i I I I I I I J I l I I i I l i i I f ~ TEST REQ. CV SP ~ I ti. PAGE 8 I n-, ~*LIEF i',~ -~ R* EQUES. y ( N ES

7) 0

SURRY UNIT 2. INSERVICE TESTING ... *. ASME CODE CLASS 1, 2 AND 3 VALVES S1ST21 NA,.'1E:.._ _____ C..:;.om~p~o;;.;;n....;e..;;.n;..;;t~C..:;.oo..:;.l::.;i:;.:n.:i::g2.-..,;,;W;.;:;a...::t.=.e.::..r __ PAGE--2A, I CODE l VALVE DRAW. CATE-SIZE VALVE ~CTUA-NORMAL TEST RELI I NL'}3ER LOCN. FUNCTION I CLASS GORY (IN.) TYPE TOR POSI-REQ. REQU .,YDi,_ ~lL.. PCUWU!l;;a:I,~ - *-~ l-CC-569, 578 C-2 Component Cooling Water 3 C l 18 CK I 3A oc CK NO I Discharge Check Valves i I ~;J ES' - I I ' I I I i l I I i I I e I I I t I ! l I l ! I ( I l I i l f I f l I l I t l I

SURRY UNIT 2: INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYST:i:}f NAf1E COMPONENT COOLING ' I 11 ii

I VA

..,VE NUl*~BER TV-CC205A,B,C TV-CC207 TV-CC209A,B TV-CC210A,B,C DRAW.

LOCN. A-1, B-1, G-1 A-1 E-4,E-3 D-2,'D-2,C-2 FUNCTION Component Cooling from* Reactor Coolant Pumps Component Cooling from Reactor Coolant'Pumps Component Cooling from RHR Heat Exchangers Component Cooling from Reactor Containment Air Recirculation Coolers I DRAW, NO. 11448-FM-72F

---

=-'-'-'"'--'-=--',..;:..;..._ __ _

CODE CATE-SIZE VALVE ACTUA-NORHAL CLASS GORY (IN.) TYPE TOR POSI-i.m..E~. !-I.l.911 3 B 6 BA PN 0 3 B 2~

• GL PN 0

3 B 18 BU PN 0 3 B 6 BU PN 0 I I 1 PAGEL_ TEST RELIE}' REQ. REQUES1 - ~~--* EV YES ST (6) EV YES ST (6) EV NO ST EV NO ST 1 i j

SURRY UNIT 2. INSERVICE TESTING ..... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE1 Ni>.. }fE:.......-____ .a:.SAM=P....,L=I.... N'""G __________ _ DRAW. NO *-----li,.,li,.;;5~~f-e!J-FM-.8~2:Hl:Jr---- PAGE~ VALVE DRAW. C(;JE CATE-SIZE VALVE 'ACTUA-NOR}1AL TEST !RELIEF NlTXBER LOCN. FU::;CTION CLASS GORY (IN.) TYPE TOR POSI- ~~ hxr.ll-!-,I.lQJL I PN TV-SS203 E-1 Residual Heat Removal 2 A 3/8 GA oc LT NO System Sample EV ST TV-SS200A,B D-1,E-l Pressurizer Liquid 1 A 3/8 GA* PN

• oc
• LT NO Space Sample I

EV ST TV-SS201A,B D-1,E-1 Pressurizer Vapor 1 A 3/8 . GA PN oc LT NO Space Sample EV ST TV-SS206A,B D-2,E-2 Primary Coolant Hot 1 A 3/8 GA PN oc LT NO Leg Samples* EV ST TV-SS202A,B D-2,E-2 Primary Coolant Cold 1. A

• 3/8 1 GA PN oc LT NO Leg Samples
• EV ST TV-SS204A,B D-:2,E-2 Pressurizer Relief Tank A

3/8 GA PN oc LT NO e Gas Space Sample .EV ST i i I I i f 1 I I l

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME"'--~~--V_E_NT_s_&_D_R_A_I_N_s _______ ~ DRAW. NO *-----,lHl,..;,5~4-A8-H-{-,8~3~t....., --- PAGE--tt-VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER

LOCN, FUNCTION CLASS GORY (IN,)

TYPE TOR POSI-

REQ, REQUES'J ITYPF.

1'ION I I I I TV-DA200B H-8 R. c. Sµmp Pump ~ A 2 GA PN oc LT NO Discharge Isolation EV ST TV-DG208B H-4 Pr. Dr. Transfer Pump A 2 GA PN oc LT NO Disch. Isolation EV ST TV-VG209B H-1 Gas Ven.t Hdr.

• Isolation A

2 GA PN 0 LT NO EV ST 2-VA-l I-5 Containment Isolation AE 2 GA HW C VP YES (26) i ' I J I i I I I j I

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES DRAW,N0.~~~~_.._11~5~4~8~-~EM~--6~3~B..._~~~ PAGE-1.2_ VALVE

DRAW, CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN.

FUNCTION CLASS GORY (IN,) TYPE TOR POSI-REQ. REQUES'l 'l'YP"P. 'l'ION TV-DA200A I-8 R. c. Sump Pump A 2 GA PN oc LT NO Discharge Isolation EV l ST i TV-DG208A L-4 Pr. Dr. Transfer Pump A 2 GA PN oc LT NO Disch. Isolation EV . ST TV-VG209A L-2 Gas Vent Hdr. Isolation A 2 GA PN 0 LT NO EV ST 2-VA-9 L-4 Containment Isolation AE 2 GA HW 0 VP YES. (26)

i.,

I I I l I

f. I I

I I I

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME ______ c_o_N_T_A_INM_E_NT __ &_R_E_c_r_R_c_uLA_T_r_o_N_SPRAY DRAW. NO

• ____

...;1:.;.1~5....;.4.;;,.8-_FM....;...-..;..8..;..4A~--- PAGE--11._ VALVE DRAW. CODE CATE-1 SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES'J 1'YPF. 'l'ImJ I MOVRS255A,B F8,F8 Recirculation Spray Pump 2 A 12 PL MO 0 LT NO Suction from Containment Sump EV ST MOVRS256A,B F6,F6 Recirculation Spray 2 A 10 GA MO 0 LT NO Pump Discharge EV ST 2RS11, 17 F6,F6 -Recircuiation Spray Pump 2 AC 10 CK SA C CV YES Discharge Check Valves LT (8) MOV-CS200,A,B I-4, I-4 Containment Spray Pump 2 B 12 GA MO 0 EV NO Suction from RWST ST MOVCS201A,B, F2,F2, Containment Spray Pump 2 A 8 GA. MO C LT NO C,D Fl,Fl Discharge EV ST 2CS13,24 E2,El Containment Spray PUmp 2 AC 8 CK SA C CV YES Discharge Check Valves LT (8) MOVCS202A,B J3,K3 Chemical Addition Tank 2 B 6 GA MO C EV NO to RWST Isolation Valve ST 2-CS-204,205 D-1,D-2 Containment Spray 2 AC 8 CK SA C CV YES Check Valves LT (8) 2-CS-25 J-4 RWST* to LMST 2 E 16 GA HW 0 VP NO MO.V-RH-200 K-3 RHR to* RWST 2 A 6 GA MO 0 EV YES ST (26) 1

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES

• SYSTEM NAME CONT VACTTTJM & LEAKAGE MQNITOBING DRAW. NO *-----J"""Ji..5L<ilJ.Qa8==-FM~."""s~5.,.,.A----

PAGE--1 VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES1 'l'YPF. 'T'!()l\\J TV-LM200A,B E-3, E-3, E-3, Open Pressure System A 3/8 GA PN

• C LT NO C,D,E,F,G,H E-3, E-3, E-3, Isolation EV D-3, E-3 ST TV-LM201A,B H-4, I-4 Closed Pressure System A

3/8 GA PN C LT NO Isolation EV ST HCV-CV200 J-5 Cont. Vacuum Air Ejector A 8 GA PN C LT YES Isolation EV (26) ST TV-CV-250A,B, H-7,H-7, Cont. Vacuum Pump A 2 GA PN 0 LT NO

• C,D H-8,H-8 Suction Isolation EV ST 2-CV-2 1-5.

Containment Vacuum Air AE 8 GA HW C VP YES Ejector Isolation EV (26) e I I I I I i I i I I

SURRY UNIT 2*. INSERVICE TESTING .... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE:1 NAHE ------------------ CONT. VACUUM & LEAKAGE MONITORING DRAW. N0. _____ .._11....,4'""4.... 8=EM=9 ..... 0 ...... A~--- 2-G lACTUA- V/1.L,.1.lE DRAW. CODE CATE-SIZE VALVE NORH.AL 1'.u1*;1:.ER LOCN. FUNCTION CLASS GORY (IN.) TYPE hoR POSI-I cr,1.l;JL_ ~L. I I I i W-166,175 E-3,C-3 Gaseous Waste Disposal A 2 DA HW I / __ Isolation W-174-183 C-2, D-2 Gaseous Waste Disposal AEI 2 DA HW Isolation i 2-G i I I i ! ' I I I I I '.i J I TEST REQ. VP LT EV VP LT EV PAGE-J..4.A RET 1-::-r.-l RE* QUES1 ,ir.r*~ n-.a~...,..... I I y ES

26)

( y ( ES

26)

SURRY UNJT 2: INSERVICE 'fESTING .. ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:.,._ ___ ~R~E~A~C~T~OR~C~O~O~LA~N~T=-------- DRAW. NO, ______ 11._5.r.=4.... 8=...EM .......... S... 6 ..... B...._ __ _ PAGE---15.... VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) .TYPE TOR POSI-REQ. REQUES'1 l,'T'YPF. '!'ION SV-2551A,B,C F-4,G-4,H-4 Pressurizer Safety Valves 1 C 6 SF SA C SP NO TV-2519A A-6 Primary Grade Water to A 3 GA PN C LT NO PRZ Relief Tank EV ST 2-RC-160 B-7 Primary Grade water to AC 3 CK SA C LT. YES PRZ Relief Tank CV (27) ( 11448-FM-79D) I l I I

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME CHEMICAL AND. VOLUME CONTROL DRAW,NO.~~~~....J..11~5~t~1S>-,ll;~ll4-.g~g~gs--~~- VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES1 ITYPR TJ()N 2-CH-258, 26 7, D-6,F-6 Charging Pump Discharge 2 C ~ 3 CK SA oc CV YES 276 G-6 Check Valve 1, (17) LCV-2115B,D C-9,C-9 Charging Pump Suction from 2 B 8 GA MO C EV NO Refueling Water Storage Tank ST LCV-2115C,E H-3,H-3 Charging Pump Suction from 2 B 4 GA MO 0 EV YES Volume Control Tank ST (12) MOV-2275A,B,C D-6, F-6, H-1 Charging Pump Recirculation 2 B 2 GA MO 0 EV YES Flow Path Isolation ST ( 17) MOV-2373 F-5 Charging Pump Recirculation 2 B 3 GA MO 0 EV YES Head~r Stop Valve ST (13) MOV-2381 A-3 Reactor Coolant Pump Seal 2 A 3 GA MO 0 LT YES Water Return EV (14) ST I

SURRY UNIT 2. INSERVICE TESTING .. ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME __ ~-~-C_H_EM_I~C_A_L_AN_D~V_O..;.L_UM __ E_C_O_N_T_R_O~L-DRAW. NO. _ __;;l~l-S-'-48~*-..,;;FMc;;..;_-.... 88_B~----- PAGE_!L VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.)

• TYPE TOR POSI-REQ.

REQUES1 11'YPF. 'T'ION I TV-2204 A-3 Reactor Coolant System 2 A 2 GA PN 0 LT YES Letdown Iso_lation Trip Valve EV (15) ST "RV-2209 F-1 Reactor Coolant System 2 C i 2 RE SA C SP NO Letdown Relief Valve RV-2257 H-1 Volume Control Tank Relief 2 C 3 RE SA C SP NO Valve MOV-22894. & B B-5 Normal Charging Header 2 A 4 GA MO 0 LT YES Isolation EV (16) ST FCV-2160 A-3 RCS Loop Fill Header 1 A 2 GL PN C LT YES Isolation EV (26) ST I I I

SURRY UNIT 2: INSERVICE TESTING . ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAJ1E _____ ___;C_H_EM_I;;;;.C....;.A..;;;L;;..._AN....;.D_V....;.O....;.L_UM_E_C.;;..O_N_T ____ R""'"O=L-DRAW, NO._---al:a..l::.:5:;;:4~8-_FM~-~8..,.8~C------ PAGE_ia_ VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF . NUMBER LOCN

• FUNCTION CLASS GORY (IN,)

TYPE TOR POSI-REQ. REQUES1 l'T'YPR 'fION RV-2203 H-1 Letdown Header Relief 2 C 2 CK SA C SP NO HCV-2200A,B,C H-2, H-2, Letdown Orifice Isolatioh 2 A 2 GA PN QC LT NO H-2 EV ST l I I l p I I

SURRY UNIT 2: INSERVICE TESTING ASME CODE CLAS~ 1, 2 AND 3 VALVES SYSTEM NAME':.-___ __:.S~A::.F.:a:.ET~Y::......-:I:.:;N::::::J.:a:.E,:;:,.CT~I~O::..:,.N:..-.----- DRAW. NO

• __

la!..al!a.a5~4~8;;:;.-FM=~81.,1,9,J;JA _____ _ PAGE___19_ VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUN.BER

LOCN, FUNCTION CLASS GORY (IN.)

TYPE TOR POSI-REQ. REQUES1 i'l'YPR TION MOV-2860A,B B-8, E-8 Low Head Safety Injection 2 A ~ 12 GA MO C LT NO Pump Suction from Contain-EV ment Sump ST 2-SI-56, 47 C-8, F-8 Low Head Safety Injection 2 C 12 CK SA C CV YES Pump Suction from Contain-(18) ment Sump Check l>JOV-2862A, B G-9. G-8 Low Head Safety Injection 2 B 12 GA MO 0 EV NO Pump Suction from Refueling ST. Water Storage Tank 2-SI-46A, B G-9. G-8 Low Head Safety Injection 2 C 12 CK SA C CV YES Pump Suction from Refueling (28) Water Storage Tank Check 2-SI-43, 50 D-7, G-7 Low Head Safety Injection 2 C 10 CK SA C CV YES Pump Discharge Check (28 \\ MOV-2863A, B E-6, G-6 Low Head Safety Injection 2 B 8 GA MO C EV NO Pump Dischrge to High Head ST Safety Injection Pump Suction MOV-2885A, B, C-7, G-6, Low Head Safety Injection 2 B 2 GA MO 0 EV NO C, D G-6, C-7 Pump Recirculation to I ST Refueling Water Storage Tank I 2-SI-61, 53 C-6, G-6 Low Head Safety Injection 2 C 1 2 CK SA C CV NO

• l Pump Recirculation to j

Refueling Water Stol'.'age l I I

SURRY UNIT 2: INSERVICE TESTING .... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME. ____ ---'S'-A_F_E_TY_I"'""N_J_E_C_T_IO.....;N _______ _ PAGE_2!L VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN*) TYPE TOR POSI-REQ. REQUES'l l'l'V'P'R Trm1 MOV-2864A, B D-6, G-5 Low Head Safety Injection. 2 B ~ 10 GA MO 0 EV NO ~ Pump Dischrge to Reactor ~ ST Coolant System Cold Legs I . RV-2845A, B, C C-6, D-5 Low Head ,, Safety Injection 2 C l 1 RE SA C SP NO C-5 Flow Path Relief MOV-2890A, B . B-6, B-5 Low Head Safety Injection 2 AE 10 GA MO C LT NO to Reactor Coolant System EV Hot Legs ST VP MOV-2890C B-6 Low Head Safety Injection 2 AE 10 GA MO 0 LT YES to Reactor Coolant System EV (19) Cold Legs ST VP MOV-2869A, B, A-3, I-3 High Head Safety Injection 2 AE 3 GA MO

• c LT YES 2842.

A-1 to Reactor Coolant Sys. EV (20) ST VP MOV-2867C, D B-1, B-2 Boron Injection Tank 2 A 3 GA MO C LT YES Outlet 'Isolation EV (21) ST MOV-286 7A, B I-2, I-2 Boron Injection Tank 2 B 3 GA MO C EV YES Inlet Isolation ST (21) I

SURRY UN'IT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 Al\\TD 3 VALVES SYSTE}I NA!-fE;,._ ____ -.:aS=A;;..F..;;;E.. T..... Y-=IN"-J--'E... C""'T"""I...... 0..... N _______ _ I 1-- 1 T VJ...LVE DRAW. I CC:.JE CATE-1 SIZE VALVE IACTUA-NOR.HAL TEST lREUEF mn*IBER LOCN. Flf.*;CTION CLASS GORY (IN.) TYPE 'TOR FOSI-REQ; REQUES1 iJ.JJ'J;.._ ~QtL ~~.~.:i;~- ~ B I V-2884A H-1 Boron Injection Tank 2 1 GA I PN 0 EV NO Recirculation ST DRAW. NO._...JJwJi...;5i.w4.o8=EM=--""'8~9~.A.__ _____ _ PAGE~ . I I V-2884B, C H-1, G-2 Boron Injection Tank 3 B 1 GA PN 0 EV NO Recirculation ST T V-2857B D-1 Boron Injection Tank 2 C 3/4 RE SA C SP NO Relief R T V-SI201) B-4 Nitrogen Accumulators A 1 GA PN 0 LT NO 3/J EV ST -SI-73 A-5 Accumulator Isolation AE GL HW C EV YES 2 LT (26) -SI-32 A-5 Accumulator Isolation AE 1 GL HW C EV YES- .LT (26 2 -SI-150 C-1 . Bo_ron Injection Tank A 1 GL HW 0 EV YES 2 LT (26) -SI-174 B-2 High Head Safety I~jection A I 3/4 GA HW C EV YES to il. C. System LT (26) 2 I I I l I J { I I J I

SURRY UNIT 2. INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEM NAME:.__ ________ s_A_F_E_T_Y_I_N_J_E_C_T_IO_N __________ _ DRAW.N0.~---1~15~4~8_-_FM_-_8~9_B __________ ~ PAGE 22 VALVE DRAW. CODE CATE-SIZE VALVE ACTUA-NORMAL TEST RELIEF NUMBER LOCN. FUNCTION CLASS GORY (IN.) TYPE TOR POSI-REQ. REQUES'l l'l'VPF 'T'ION RV-2858A, B, C C-4,G-5,°C-7 Accumulator Tank Relief. 2 C 1 RE SA C SP NO 2-SI-107, 109 C-5, A-5, Accumulator Discharge Check 1 C

• 12 CK SA C

CV YES 128, 130, G-7, A-7, (22) 145, 147 C-8, A-9 MOV-2865A, B, C C-S~G-6,C-8 Accumulator Discharge 2 BE 12 GA MO 0 EV NO ST VP 2-SI-88, 91, 94, A..:.2, A-2, Safety Injection to 1 C 6 CK SA C CV YES 238, 239_, 240 A-3, B-2 RCS Hot Legs (23) B-2, A-3 2-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 (24). 2-SI-241, 242, B-1, B-1, .Low Head Safety Injection 1 C 6 CK SA C CV YES 243 B-2 to RCS Cold Legs (30) 2-SI-224, 225, J-1, J-1, High Head Safety Injection 1,2 C 3 CK SA C CV YES 226, 227 J-2, J-3 Check Valves at Containment (24) Pene tra'tions ' 2-SI-228, 229 J-3, J-3 Low Head Safety Injection 2 C 6 CK SA C CV YES Check Valves at Containment (30) Penetrations I

i i f I I I I I I I I i I I i SURRY UNIT 2. INSERVICE TESTING .... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE1 NAHE ~----------------- SAFETY INJECTION DRAW. NO

• __.....1,l...i.l...1..5~48.i=EM.:.u=:.l.JSu.9.uB------

PAGE-.;u_ ...-,---------...-------.----------------il----r---~---T----,----,----,----.-----, I' VALVE DRAW. CCJE CATE-SIZE VALVE ACTUA-NORNAL TEST RELIEF N1JY...BER LOCN. FU:"ICTION CLASS GORY (IN,) TYPE TOR POSI-REQ. REQUES1 1---------~-------+--------*-------'*r ---;----r----ci----~IX.t'JL.....,_TIQ],:..-...,.,,.,........,...,..,.,_!***""""""""*- 2-SI-337,341 339,336 338,340 2-SI-79, 82, 85 TV-SI201A, B 2-SI-234 E-3, E-2, E-2, E-2 E-1, E-1 A-:1, A-1, A-2 J-5, J-5 J-4 Cold & Hot Leg Safety Injection Line Throttle Valve Safety Injection to RCS

• cold Legs Accumulator Nitrogen Relief Line Isolation

. Nitrogen Accumulators I 1 E 2 2 C 6 A 1 I I i AC . 1 I 1 f I J HW T CK SA C GA P.N 0 CK SA C l ~ l VP CV LT EV ST CV LT I I I NO YES (23) NO YES (29) e I I I ,1 ~ I

SURRY UNIT 2. INSERVICE TESTING ... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTEX NP..xE R.W.S.T. CROSS TIE DRAW.NO. 11448 EMnl06C PAGE~ 1- \\11!.L~lE lfil{SER DRAW. LOGN. .,--C_O_D_E-,,_C_A_T_E---,,.--S-I-ZE~-r-\\-7 A-LVE 1~.;;=--l NOR}1A.L TEST R~LIE:-'1 CLASS GORY (IN.) TYPE JTOR POSI-REQ. REQUES~ ---i r~.!J.illL.... _____. FUNCTION TV-SI202A, B 2-SI-25 2-SI-400 i 1 D-3, D-3 C-3 B-3 Unit No. 1 RWST to Unit No. 2 RWST Cross Tie Charging Pump Suction from RWST Check Valve Charging Pump Suction from RWST Check Valve 2. B I 8 GA ~ PN C EV NO ST 2 C 8 CK 2 C 10 CK SA C SA C CV CV. YES (12) YES (12)

6 SURRY UNIT 2: INSERVICE TESTING .... ASME CODE CLASS 1, 2 AND 3 VALVES SYSTE::1 N1u'ffi _______ S_T_E_AM_G_E_N_E_RA_T_OR_B_L_O_W_D_O_WN __ DPJ\\W.N0.~-~1~1~4~4~8-_FM~-~1~2~4wA.__ ____ _ PAGE.2.6__ VALVE DRAW. CODE CATE-SIZE VALVE IACTUA-NOfil1AL TEST RELI N1_;~{33R LOCN. FUNCTION CLASS GO~Y (IN.) TYPE \\TOR POST-REQ. ?,EQU* --(['Y}:.J.t...,_Jl.QJi._ *'IIU.'W.$"... \\l?:'~-:in-.,~~:-,u.... J GAi TV-BD200A,B,C C-2, C-2, C- ~. Steam Generator. Blowdown 2 3 PN 0 EV YES D,E,F C-4,C-5,C- ~ Trip Valves ~ ST (25 I ) I J I ' l I i I I l I j ! I 1 I I sj :SP/119 I I I I i I I

<I SURRY UNIT 2 INSERVICE TESTING ASME CODE CLASS 1, 2 AND 3 VALVES RELIEF REQUESTS (1) A full stroke or partial stroke exercise of these valves during power operation could result in a turbine and reactor trip. As an alternative, they will be exercised during cold shutdown. (2) Opening these valves during power operation would introduce cold and out of chemistry specifications auxiliary feed water 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) Opening these valves would result in the introduction of service water into the Recirculation Spray Heat Exchanger and cause fouling of the heat exchanger tubing. As an alternative, these valves will be tested during cold shutdown. (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 cold shutdown. (8) These valves are located inside the containment and not accessible during power operation. Using flow to exercise these valves would result in spraying water in the containment and manual exercising requires building scaffolding. To build scaffolding containment entry would be necessary thereby requiring leak testing of both doors prior to establishing subatmospheric containment pressure and plant startup. As an alternative these valves will be manually full stroke exercised during re fueling outages.

(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) This valve cannot be shut down when the RC system is above atmos-pheric pressure or when the RC system is being filled. Closure of this valve would cause loss of RCP seal flow resulting in pump seal damage. As an alternative, this valve will be tested during refueling outages. (15) Exercising this valve closed during power operation loss of RC inventory and pressurizer level control. be exercised during cold shutdowns. could result in a This valve wil 1 (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 coolan-t inventory. This valve will be exercised during cold shutdown. (17) With the present plant design, these valves can only be partial stroke exercised during power operation. The charging pumps cannot achieve design accident flow when pumping into the RC system at operating pressure and the only available flow path to test these valves is into the RC system. During cold shutdown, full stroke exercising of the valves could result in an over-pressurization of the RC system and could force a safety system (PORV's) to function. These valves will be full stroke exercised during refueling outages when the vessel head is removed providing an adequate expansion volume. '/ ) IJ (18) This normally closed check valve cannot be exercised without isola suction to the LHSI pump and draining a portion of the system. This valve will be part-stroke exercised during each refueling outage using the leakage monitoring test connections. (19) This valve will not be exercised during power operation because failure in the closed position would render the low head safety injection to the cold leg inoperable. This valve will be full stroke exercised during cold shutdowns. (20) These valves cannot be exercised during power operation because opening these valves would allow charging flow into the RC system thermally shocking the HHSI nozzles an causing reactivity transients. During cold shutdowns the charging (HHSI) flow could cause an over-pressurization of the RC system and could force a safety system (PORV's) to function. These valves will be full stroke exercised during refueling outages. (21) Opening these valves during power operation would allow concentrated boric acid to flow into the piping systems that are not heat traced and a boron building could crystalize and block system flow. These valves are full stroke exercised during cold shutdowns. (22) These valves cannot be exercised during power operation because accumulator pressure cannot overcome RCS pressure. The 3/4" test line will not partial stroke these valves. These valves cannot be exercised during cold shutdown because an over-pressurization accident could occur. These valves are partial stroke exercised during refueling outages. (23) These valves cannot be exercised during power operation, HHSI flow through these valves would thermal shock the injection nozzles. During cold shutdown the RCS pressure is greater than accident pressure and full design flow cannot be achieved. These valves are full stroke exercised during refueling outages when the vessel head is removed. (24) These valves cannot be exercised during power operation exercising these valves requires flow into the RCS, thermal shocking the in-jection nozzles. Exercising these valves during cold shutdown could result in an overpressurization of the RCS and force a safety system (PORV's) to function. These valves are full stroke exercised during refueling outages when the vessel head is removed. (25) Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves are reopened a flow surge occurs which automatically isolates the inner valves due to high flow. Then a containment entry is necessary to reset these valves and upon reopening the process may occur again. As an alternative these valves will be exercised during cold shutdown. ~. r, ') e (26) These are passive valves and are not required to change position to perform their safety related function. As an alternative these valves will be tested during each refueling outage. (27) Plant design does not permit verification of valve position during power operation or cold shutdown. The only way to verify its safety position is during leak rate testing at refueling outages. (28) These valves cannot be full stroke exercised during power operation, the only full flow path is into the RCS and the LHSI pumps cannot overcome RCS operating pressure. This valve is partial stroke exercised quarterly through the pump recirculation line. During cold shutdown the RCS pressure is greater than design accident pressure and the LHSI pump cannot achieve design flow. These valves are full stroke exercised during refueling outages with the vessel head removed which provides minimum RCS back pressure which allows full LHSI flow. (29) This valve cannot be verified shut (its safety related position) during power operation or cold shutdown. The only method to verify valve closure is during a leak rate test at refueling outages. (30) These valves cannot be exercised during power operation as the only full flow path into the RCS and the LHSI pumps cannot be full stroke exercised because RCS pressure is greater than accident pressure. These valves are full stroke exercised during refueling outages with the vessel head removed. }}