Text

Forwards Surry Power Station Units 1 & 2 IST Program Plan for Pumps & Valves Third Insp Interval 940510-040510, Rev 0
	ML18151A276
Person / Time
Site:	Surry
Issue date:	10/19/1993
From:	Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A277	List: ML18151A276; ML18151A278;
References
	93-658, NUDOCS 9310250219
	Download: ML18151A276 (218)
	v • d • e

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 e

October 19, 1993 United States Nuclear Regulatory Commission Serial No.93-658 Attention: Document Control Desk SPS/ETS R Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 THIRD TEN YEAR INSERVICE TESTING PROGRAM In accordance with 10 CFR 50.55a(f), Virginia Electric and Power Company submits the third ten-year interval. inservice testing program for Surry Units 1 and 2. Surry Power Station Units 1 and 2 lnservice Testing (1ST) Program Plans for Pumps and Valves have been revised to comply with the requirements of the 1989 Edition of the Code for the third interval. The third interval begins on May 10, 1994 for both units. The programs are included as Attachments 1 and 2 to this letter.

Included with the programs is a description of the changes between the second and third interval programs for Surry Power Station Units 1 and 2. There are three pump relief requests (P-1, 11, and 21 ), and three valve relief requests (V-26, 47, and 51) that require approval prior to use for Unit 1. Similarly, there are two pump relief requests (P-1 and 18), and three valve relief requests (V-26, 47, and 51), which require approval prior to use for Unit 2. Accordingly, we request your review of these relief requests prior to the start of the third interval.

Approximately 200 test procedures require revision to implement the third interval inservice testing program. The revision and implementation of this large number of procedures will have to be phased in over a period of several months. Therefore,*

certain third interval test procedures will be revised and performed prior to the start of the third interval.

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The Surry Power Station Units 1 and 2 third interval inservice testing programs and the relief requests contained therein have been reviewed by the Station Nuclear Safety and Operating Committee.

If you have questions regarding this information, please contact us.

Very truly yours, LJ~-j\

W. L. Stewart '

Senior Vice President - Nuclear Attachments

1. Unit 1 lnservice Testing Program Plan

2. Unit 2 lnservice Testing Program Plan cc:

w/out attachments U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 '

I.

INSERVICE TESTING PROGRAM PLAN

,,,I FOR PUMPS AND VALVES THIRD INSPECTION INTERVAL

'I MAY 10, 1994 - MAY 10, 2004

'.- i REVISION 0

' I

_._ __ ___,_..__ . ~ - - _-' ** ___ _

-NOTICE-

/*

THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION &

REPORTS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RE-CORDS & ARCHIVES SERVICES SEC-TION P1-22 WHITE FLINT. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE($) FROM DOCUMENT FOR REPRODUCTION MUST BE RE-FERRED TO FILE PERSONNEL.

-NOTICE-

/ l) / ; -r-/cr3#1JIPZ5e>211

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 THIRD INTERVAL 1ST PROGRAM REVISION 0

'*1*'

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM The following summary describes the changes from Revision 3 of the Surry Power Station Unit 2 Inservice Testing (IST) Program for the second IST interval to Revision O for the third IST interval. In addition to describing the changes to the program, the summary gives the approval mechanism for each relief request given in Sections 3.6 and 4.6.

Revision 3 for the second IST interval was submitted on July 24, 1992 (Serial No.92-286). The NRC issued a Safety Evaluation Report (SER) for Revision 3, by letter dated March 22, 1993.

Changes to Revision 3 were issued to the NRC by letters dated October 8, 1992 (Serial No.92-610) and May 6, 1993 (Serial No.93-046). The summary given below presents all changes to the IST Program from Revision 3 dated July 24, 1993, and identifies the corresponding letter if the change had been subsequently submitted. Changes to the IST Program Plans are highlighted by a revision bar in the right margin.

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

1.0 INTRODUCTION

The introduction was expanded to describe the transition from the second to the third IST interval, and the approval by the NRC of the 1989 Edition of Section XI *

. ** 2~0. PROGRAM DESCR:.CPTi.ui*r.,.**c 0 Reference to Section XI, the 1980 Edition through the Winter 1980 Addendum was replaced by reference to addenda through the 1988 Addenda and editions through the 1989 Edition.

3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.1 PROGRAM DEVELOPMENT PHILOSOPHY References to Section XI, the 1980 Edition through the Winter 1980 Addendum were replaced by references to addenda through the 1988 Addenda and editions through the 1989 Edition and ASME/ANSI Edition OM-87, Part 6, Addenda OMa-1988.

3.2 PROGRAM IMPLEMENTATION Verb tense changed from future tense to present tense *

2

ATTACHMENT 2

3.3

SUMMARY

OF CHANGES TO THE SURRY UHI'l' 2 IST PROGRAM PROGRAM ADMINISTRATION Reference to updating the IST Program a minimum of at least once every 40 months was deleted. Updating the program periodically is addressed in an internal administrative procedure.

3.5 PUMP INSERVICE TEST TABLES OM Part 6 does not require the measurement of bearing temperature. Therefore, references to bearing temperature were deleted.

Unit 2 PUMP NUMBER COMMENT/PROGRAM CHANGE 2-RS-P-2A Withdrew Relief Request P-4. Refer to the 2-RS-P-2B discussion in Section 3.6.

2-RS-P-lA 2-RS-P-lB 2-RH-P-lA 2-RH-P-lB Withdrew Relief Requests P-5 and P15.

to the discussion in Section 3.6.

Refer Program Change: Measurements of inlet and discharge pressures were deleted.

Differential pressure is measured directly.

Also, Relief Request P-15 was withdrawn.

1-EE-P-lC Program change: Diesel fuel oil transfer pump 1-EE-P-lC was moved from the Unit 2 IST Program to the Unit 1 IST Program.

3.6 PUMP TEST PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 3. It also contains a description of the approval mechanism for each relief request. That is, the summary indicates whether the approval is:

1) through a position in Generic Letter 89-04,

2) through a previously issued NRC SER or

3) obtained using a relief request that will need 3

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM approval by the NRC. Relief requests requiring NRC approval are marked with an asterisk*

Unit 2 Relief Request Change P-0 This relief request number is no longer active.

P-1* Reference to using vibration velocity (in/sec) instead of vibration displacement (mils) was deleted because vibration velocity is allowed by OM Part 6. The Revision 3 version of P-1 contained a note describing the use of a minimum value (0.5 in/sec) for vibration reference values.

Reference to this minimum reference was retained in the current version. Surry Power Station was given a three year period ending in August, 1993 to use the minimum reference value. Surry Power

Station requested by letter dated June 29, 1993 (Serial No.93-206) that the use of a minimum value be extended for a period of three years.

Use of a minimum vibration reference value was recently granted to North Anna Power station in the NRC SER received in September of 1993(TAC NOS.

M86645 & M86646). No period restrictions were placed on North Anna.

P-2 to These relief request numbers are no longer active.

P-3 P-4 Relief request is being withdrawn. The Revision 3 version of P-4 dealt with the outside recirculation spray pumps and requested relief for:

1) testing every 24 months instead of quarterly testing,

2) waiting two minutes instead of five minutes before measuring test quantities and

3) calculating inlet pressure.

4

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SORRY UHJ:T 2 IST PROGRAM For Item 1, the recirculation spray pumps are deep draft pumps that are maintained dry. OM Part 6, Paragraph 5.5 allows a 24 month test frequency for this type of pump. For Item 2, OM Part 6, Paragraph 5.6 only requires a two minute run time before measuring the test quantities. For Item 3, the NRC concluded in the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166) for P-4 that calculating the inlet pressure from the surface level is in accordance with the provisions of the Code, and therefore, relief is not required.

P-5 Relief request is being withdrawn. The Revision 3 version of P-5 dealt with the inside recirculation spray pumps and requested relief for:

1) testing every 24 months instead of quarterly testing and

2) measuring inlet and differential pressure

For Item 1, the recirculation spray pumps are deep draft pumps that are maintained dry. OM Part 6, Paragraph 5.5 allows a 24 month test frequency for this type of pump. For Item 2, the NRC concluded in the NRC SER dated March 22, 1993 (TAC Nos.

M84333, M84334, M83165, and M83166) for P-5 that calculating the inlet pressure from the surface level is in accordance with the provisions of the Code, and therefore, relief is not required.

P-6 This relief request number is no longer active.

P-7 The request to stop measuring inlet pressure was deleted for the residual heat removal pumps. OM-6 does not require measuring inlet pressure if differential pressure is measured directly. The NRC SER dated August 27, 1990 (TAC Nos. 655555 and 65556) granted approval for the extended cold shutdown testing frequency.

. P-8 to These relief request numbers are no longer active

P-14

5

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UlU::T 2 IST PROGRAM P-15 Interim Relief request is being withdrawn.

Testing on the inside recirculation spray pumps and the residual heat removal pumps was performed during the last Unit 2 refueling outage using instrumentation that met Code accuracy requirements.

P-16 The acceptance criteria were changed to reflect the criteria in OM Part 6, Table 3b. The basis for this relief request was approved by the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166).

P-17 Relief request is being withdrawn. Relief Request P-20 requested relief from measuring the static inlet pressure on a pump that is already in operation. This relief request is being withdrawn because OM Part 6 does not require measuring static inlet pressure.

Calibrating the inlet pressure instruments for the boric acid transfer pumps to an accuracy within+

2% has proven difficult and may be impractical in the future with the current instruments.

Calibrating the inlet pressure instruments to an accuracy within+ 3% would be practical. However, with the current o to 15 psig inlet pressure gauges calibrated to+/- 3%, a differential pressure can be determined that exceeds the accuracy requirements for differential pressure if the discharge pressure gauge is calibrated to an accuracy within+/- 1.75%.

Relief for going to the+ 3% is new to this relief request. The remainder of the relief request was approved by the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166) *

6

ATTACHMENT 2

3.6

SUMMARY

OF CHANGES TO THE SURRY OBIT 2 IST PROGRAM ALTERNATIVE TESTING FOR NON-CODE PUMPS This section describes why certain non-Code components that are included in the IST Program are not tested to the provisions of the Code and describes the alternative tests. The non-Code alternative tests are not relief requests and do not require approval by the NRC.

Unit 2 Non-Code Alternative Test Change PNC-1 The Revision 3 version of PNC-1 dealt with the diesel fuel oil pumps and described the following deviations from the Code:

1) measuring test quantities when the pump automatically starts on a low tank level signal instead of waiting five minutes,

2) measuring vibration velocity instead of vibration displacement and bearing temperature and

3) measuring inlet and differential pressure.

The waiting period in Item 1 was changed from five minutes to two minutes. The alternative test is still necessary even with the waiting period reduced to two minutes by OM Part 6.

Item 2 was deleted because OM Part 6 allows the use of vibration velocity and does not require bearing temperature measurement. Item J was also deleted because OM Part 6 does not require the measurement of inlet and differential pressure for positive displacement pumps such as the diesel fuel oil transfer pumps. Only discharge pressure need be measured.

Also, pump 1-EE-P-lC was moved from the Unit 2 IST Program to the Unit 1 IST Program and deleted from PNC-1 *

7

- ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.1 PROGRAM DEVELOPMENT PHILOSOPHY References to Section XI, the 1980 Edition through the Winter 1980 Addendum were replaced by references to addenda through the 1988 Addenda and editions through the 1989 Edition and ASME/ANS! Edition OM-87, Part 10, Addenda OMa-1988.

4.2 PROGRAM IMPLEMENTATION Verb tense changed from future tense to present tense.

References to Section XI were replaced by references to OM Part lOe 4.3 PROGRAM ADMINISTRATION Reference to updating the IST Program a minimum of at least once every 40 months was deleted

Updating the program periodically is addressed in an internal administrative procedure.

4.4 VALVE INSERVICE TEST TABLES References to Section Xi were replaced by references to*

OM Part 10 in the description of the valve tables.

Valves that were added to the program are identified by an asterisk *.

Unit 2 Valve Number Comment 2-BD-TV-200A to Program Change: Relief Request V-34 was 2-BD-TV-200F withdrawn.

2-CC-94, 95, Program Change: Relief Request V-45 was 2-CC-555, 556, replaced by Reactor Refueling Justification 2-CC-557, 592 RRV-7.

8

ATTACHMENT 2

2-CC-LCV-201

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM Program Change: Relief Request V-47 was revised to reflect the changes in the new Code.

2-CC-RV-212A to C, Program Change: Relief Request V-1 was 2-CC-RV-219A & B, withdrawn.

2-CC-RV-224, 2-CC-RV-238A & B 2-CC-RV-250 This relief valve was removed from the system.

Program Change: Valve was deleted from the IST Program.

2-CC-TV-207 This trip valve was removed from the system.

Program Change: Valve was deleted from the IST Program.

2-CC-TV-240A* & s* These trip valves were added to the system to replace 2-CC-TV-207. They must close to isolate the RCP thermal barrier cooling piping inside containment.

Program Change: Valves were added to the IST Program to be tested to the closed position every cold shutdown. Refer to Cold Shutdown Justification CSV-27.

2-CH-230 Following an accident, this volume control tank (VCT) discharge check valve must close after recirculation mode transfer to prevent contaminated sump water from entering the VCT via the seal water heat exchanger relief valve 2-CH-RV-2382B.

Program Change: The valve category was changed from C to A, and a closure test and leakage test were added. The closure test will be performed every reactor refueling as discussed in Reactor Refueling Justification RRV-8 .

9

ATTACHMENT 2

2-CH-258

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM Program Change: Relief Request V-14 was 2-CH-267 replaced by Reactor Refueling Justification 2-CH-276 RRV-1.

2-CH-309 Program Change: This valve was moved from Cold Shutdown Justification csv-20 to Reactor Refueling Justification RRV-6 and the test frequency was changed from cold shutdown to reactor refueling.

2-CH-FCV-2113B, It was determined that the failure of these 2-CH-FCV-2114B valves to close will not reduce the operator's ability to manually use the emergency boration system.

Program Change: Valves were deleted from the IST Program~

2-CH-LCV-2115B & D Following an accident, these valves isolate the reactor water storage tank (RWST) to prevent contaminated sump water from entering the RWST after recirculation mode transfer.

Program Change: The valve category was changed from B to A, and a leakage test was added.

2-CH-MOV-2267A These valves are passive. They do not have 2-CH-MOV-2269A to change position to fulfill their safety 2-CH-MOV-2270A functions.

Program Change: The exercise test was deleted.

2-CH-RV-2203 Program Change: Relief Request V-1 was 2-CH-RV-2382A & B withdrawn.

2-CH-TV-2204B Program Change: Relief Request V-34 was withdrawn.

2-CS-MOV-201A to D Program Change: Relief Request V-39 was withdrawn.

2-CV-TV-250A to D Program Change: Relief Request V-34 was withdrawn *

10

ATTACHMENT 2

2-CW-117

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM At one time, this normally closed manual valve would be opened following initiation of an event to reduce the flowrate through the essential heat exchangers and thus conserve the cooling water inventory in the intake canal. However, it has been determined that this vent valve is no longer required for canal water inventory concerns.

Program Change: Valve was deleted from the IST Program.

2-DA-TV-200A & B Program Change: Relief Request V-34 was 2-DA-TV-203A & B withdrawn.

2=DG-TV~208B Program Change: Relief Request V-34 was withdrawn.

1-EE-19 Program Change: These valves were moved from 1-EE-RV-105 the Unit 2 IST Program to the Unit 2 IST 1-EE-SOV-104 Program.

1-EE-RV-104 Program Change: Relief Request V-1 was 1-EE-RV-107 withdrawn.

1-EE-SOV-102 Program Change: Relief Request V-36 was 1-EE-SOV-103 replaced by Non-Code Alternative Testing VNC-4.

2-EG-S0V-200A & B Program Change: Relief Request V-37 was replaced by Non-Code Alternative Testing VNC-3.

2-GW-TV-200 to Program Change: Relief Request V-34 was 2-GW-TV-207, withdrawn.

2-GW-TV-211A & B 2-IA-381 & 384, These instrument air valves must open to allow bottled air to valve 2-RC-PCV-2456.

Program Change: The closure test was changed to an open test and the leakage test was deleted.

2-IA-395 & 396 These instrument air valves must close to ensure that bottled air is supplied to valve 11

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UIUT 2 IST PROGRAM 2-RC-PCV-2456.

Program Change: The open test was changed to a closure test and the leakage test was added.

2-IA-704 Program Change: Relief Request V-39 was withdrawn.

2-IA-864, 868 Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6.

2-IA-RV-211 Program Change: Relief Request V-1 was withdrawn.

2-IA-TV-200 Program Change: Relief Requests V-34 and 39 were withdrawn.

2-IA-TV-201B Program Change: Relief Request V-34 was withdrawn

2-LM-TV-200A to H Program Change: Relief Requests V-34 and 39 were withdrawn.

2-MS-NRV-201A to B Program Change: Relief Request V-48 was replaced by Cold Shutdown Justification csv-32.

2-MS-RV-201A to C Program Change: Relief Request V-47 was revised to reflect the changes in the new Code.

2-MS-SV-201A to C, Program Change: Relief Request V-1 was 2-MS-SV-202A to C, withdrawn.

2-MS-SV-203A to C, 2-MS-SV-204A to C, 2-MS-SV-205A to C 2-MS-TV-220 This valve is a mechanical trip device valve that is normally open. It trips closed to protect the turbine on the auxiliary feedwater pump from over speed conditions and has to be locally reset. The valve is passive in the open position and need not be tested

12

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UN:IT 2 IST PROGRAM Program Change: Valve was deleted from the IST Program.

2-RC-160 Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6.

2-RC-PCV-2455C These power operated relief valves need to 2-RC-PCV-2456 open on setpoint to protect the reactor coolant system from overpressurization when the reactor vessel is cooled down to less than 275 °F.

Program Change: A setpoint test was added and Relief Request V-34 was withdrawn.

2-RC-SOV-200Al & 2 Program Change: Relief Request V-31 was 2-RC-SOV-200Bl & 2 replaced by Cold Shutdown Justification CSV-33 and Relief Request V-34 was withdrawn.

2-RC-RV-2551A to C Program Change: Relief Request V-1 was withdrawn.

2-RH-FCV-2605 Program Change: Relief Request V-47 was 2-RH-HCV-2758 revised to reflect the changes in the new Code.

2-RH-RV-2721 Program Change: Relief Request V-1 was withdrawn.

2-RL-3 & 5 Program Change: Relief Request V-39 was withdrawn.

2-RM-3 Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6.

2-RM-TV-200A to C Program Change: Relief Request V-34 was withdrawn.

2-RS-46 & 53 Program Change: Relief Request V-39 was withdrawn.

2-RS-MOV-255A & B Program Change: Relief Request V-39 was withdrawn *

13

ATTACHMENT 2

2-SI-25

SUMMARY

OF CHANGES TO THE SURRY UN:IT 2 IST PROGRAM Following an accident, this valve isolates the reactor water storage tank (RWST) to prevent contaminated sump water from entering the RWST after recirculation mode transfer.

Program Change: The valve category was changed from C to A, a leakage test were added and Relief Request V-28 was replaced by Reactor Refueling Justification RRV-5.

2-SI-46A & B Program Change: Relief Request v-21 was 2-SI-50 & 327 replaced by Reactor Refueling Justification RRV-2.

2-SI-79, 82, 85, Program Change: Relief Request V-27 was 2-SI-88, 91, 94, revised to reference only back seat testing 2-SI-224, 225, of valves 2-SI-88 and 238, and 2-SI-91 and 2-SI-226, 227, 239, and 2-SI-94 and 240 in pairs. The 2-SI-228, 229, reference to test frequency was removed from 2-SI-235, 236, V-27 for all valves and replaced by Reactor 2-SI-237, 238, Refueling Justification RRV-4.

2-SI-239, 240, 2-SI-241, 242, 243 2-SI-107, 109, Program Change: Relief Request V-26 was 2-SI-128, 130, replaced by Reactor Refueling Justification 2-SI;....145, 147 RRV-3.

2-SI-150 & 174 Program Change: Relief Request V-39 was withdrawn.

2-SI-201 & 209 These check valves are on a 3/4 inch supply line from the RWST to the LHSI pump seals.

This line has been permanently isolated.

Therefore, the valves no longer have a safety function.

Program Change: Valves were deleted from the IST Program.

2-SI-304 Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6.

2-SI-321 & 322 Program Change: Relief Request V-39 was withdrawn

14

ATTACHMENT 2

2-SI-400

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM Program Change: Relief Request V-28 was replaced by Reactor Refueling Justification RRV-5.

2-SI-MOV-2860A & B Program Change: Relief Request V-39 was withdrawn.

2-SI-MOV-2867C & D Program Change: Relief Request V-39 was 2-SI-MOV-2869A withdrawn.

2-SI-MOV-2885A to Following an accident, these valves isolate 2-SI-MOV-2885D the reactor water storage tank (RWST) to prevent contaminated sump water from entering the RWST after recirculation mode transfer.

Program Change~ The valve category was changed from B to A, and a leakage test was added.

2-SI-RV-2845A to c Program Change: Relief Request V-1 was withdrawn

2-SI-TV-200 Program Change: Relief Request V-34 was 2-SI-TV-201B withdrawn.

2-SS-TV-200A & B, Program Change: Relief Request V-34 was 2-SS-TV-201A &'B, withdrawn.

2-SS-TV-202A & B, 2-SS-TV-204A & B, 2-SS-TV-206A &B 2-SW-108 The design basis for the charging pump 2-SW-113 service water system is being reevaluated. A 2-SW-130 full flow acceptance criteria will not be 2-SW-442 available until this evaluation is complete.

2-SW-445 In the mean time, these valves will be disassembled and inspected.

Program Change: The valves will be d~sassembled and inspected. Refer to Relief Request V-50. Also, the ASME Class for valve 2-SW-130 was changed from Class 3 to non-Class.

2-SW-TCV-208A to Program Change: Relief Request V-47 was 2-SW-TCV-208C revised to reflect the changes in the new 15

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE Code.

SURRY UNIT 2 IST PROGRAM 2-VG-TV-209A & B Program Change: Relief Request V-34 was withdrawn.

2-VP-12 Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-60 2-VS-MOV-200A to Program Change: Relief Request V-39 was 2-VS-MOV-200D, withdrawn.

2-VS-MOV-201 & 202 4.5 VALVE TEST PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 3. It also contains a description of the approval mechanism for each relief request. That is, the summary indicates whether the approval is:

1) 2)

3) through a position in Generic Letter 89-04, through a previously issued NRC SER or obtained using a relief request that will need approval by the NRC. Relief requests requiring NRC approval are marked with an asterisk*.

Unit 2 Relief Request Change V-1 Relief request is being withdrawn. The Revision 3 version of V-1 requested relief from testing safety and relief valves in accordance with PTC-25.3-1976 and to use OM Part 1 instead. OM Part 10 references OM Part 1 for safety and relief valve testing.

V-2 to These relief request numbers are no longer active.

V-4

16

ATTACHMENT 2

V-5

SUMMARY

OF CHANGES TO THE SURRY tm:IT 2 IST PROGRAM The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in v-s (2-FW-10, 41 and 72) must be disassembled every refueling outage. V-5 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

V-6 to These relief request numbers are no longer active.

V-13 V-14 Relief request is being withdrawn. Relief Request V-14 was replaced by Reactor Refueling Justification RRV-1. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

According to OM Part 10, Section 6.2, the test.

plan must justify the deferral of stroke testing.

V-15 to These relief request numbers are no longer active.

V-19 v-20 The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-20 {2-SI-47 and 56) must be disassembled every refueling outage. v-20 describes the disassembly and inspection of one valve from a group of two valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

v-21 Relief request is being withdrawn. Relief Request V-21 was replaced by Reactor Refueling

Justification RRV-2. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal 17

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM operation and cold shutdown is impractical.

v-22 to These relief request numbers are no longer active.

V-25 Relief Request V-26 was revised to describe a sampling program for non-intrusive techniques used in testing the SI accumulator discharge check valves. The sampling program is as follows.

During the first refueling outage where non-intrusive techniques are used, all valves in the group will be tested to verify that the techniques verify valve obturator movement. During subsequent refueling outages, flow testing will be performed on all valves in the group, but the non-intrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified. In this case, all valves in the group will be subjected to the non-intrusive techniques. The sampling program is in accordance with Generic Letter 89-04, position 2. A similar non-intrusive technique sampling program was approved for use by North Anna Power Station in the NRC SER received in September of 1993(TAC NOS. M86645 & M86646).

The justification for going to a reactor refueling frequency was moved to RRV-3. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical. The alternative test method was changed from disassembly and inspection to using non-intrusive techniques to verify that the check valves go to the full open position.

V-27 The portion of Relief Request V-27 which dealt with test frequency was replaced by Reactor Refueling Justification RRV-4. RRV-4 deals with the cold leg and hot leg SI check valves. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical. The portion of Relief Request V-27 which dealt with check valve pairs 2-SI-88 and

18

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SORRY UHXT 2 IST PROGRAM 238, 2-SI-91 and 239, and 2-SI-94 and 240 remains.

V-28 Relief request is being withdrawn. Relief Request V-28 was replaced by Reactor Refueling Justification RRV~S. RRV-5 deals with the SI cross tie check valves (2-SI-25 and 400). OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical. The Revision 3 version of V-28 indicated that 2-SI-25 would be disassembled and inspected every other outage. Reference to the disassembly and inspection every other outage was deleted from RRV-5. The test method and frequency are in accordance with OM Part 10, Paragraph 4.3.2.4(c).

V-29 & These relief request numbers are no longer active.

V-30 V-31 Relief request is being withdrawn. Relief Request V-31 was replaced by Cold Shutdown Justification CSV-33. CSV-33 deals with the head vent isolation valves and was originally a relief request because there could exist plant conditions during some cold shutdowns that prevent testing of these valves. Because OM Part 10 allows for a testing frequency as long as a reactor refueling frequency, relief from Code requirements is no longer necessary. As shown by the test frequency description, the appropriate test plan justification is a cold shutdown justification and not a reactor refueling justification.

V-32 & These relief request numbers are no longer active.

V-33 V-34 Relief request is being withdrawn. The Revision 3 version of Relief Request V-34 requested relief from applying an alert range acceptance criteria for stroke time to rapid acting valves (i.e.,

valves that stroke in less than two seconds). OM Part 10, Paragraph 4.2.1.S(e) addresses rapid acting valves. Therefore, relief from Code requirements is no longer necessary *

19

ATTACHMENT 2

V-35

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM This relief request number is no longer active.

V-36 Relief request is being withdrawn. Relief Request V-36 was replaced by Non-Code Alternative Testing VNC-4. The valve.s in VNC-4 (1-EE-SOV-102 and 103) are non-Code valves. According to the Minutes of Public Meetings on Generic Letter 89-04, "If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a

'request for relief' to be submitted to the staff.

Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." The non-Code alternative testing given in Section 4.8 documents the method for showing continued operability for these valves *

V-37 Relief request is being withdrawn. The non-Code air start solenoid valves were transferred to Non-Code Alternative Testing VNC-3. For the reasons given above, a 'request for relief' is not necessary.

V-38 This relief request number is no longer active.

V-39 Relief request is being withdrawn. The Revision 3 version of Relief Request V-39 requested relief from individually leak testing containment isolation valves and allowing groups of valves to be tested together. OM Part 10, Paragraphs 4.2.2.J(e) and (f) allow for the testing of valve combinations. Therefore, relief from Code requirements is no longer necessary.

V-40 This relief request number is no longer active.

V-41 The Code requirement reference was changed from Section XI, IWV to OM Part lOo OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the 20

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UN:IT 2 IST PROGRAM groups given in V-41 (2-FW-144, 159 and 174 in one group and 2-FW-148, 163 and 178 in another group) must be disassembled every refueling outage. v-41 describes the disassembly and inspection of one valve from each group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

These check valves can be disassembled while the plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

Also, reference to part stroke exercising every three months was deleted. There is no flow instrumentation or other means to detect partial flow.

V-42 The Code requirement reference was cha~ged from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.J.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-42 (2-MS-176, 178 and 182) must be disassembled every refueling outage. V-42 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

These check valves can be disassembled while the plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

V-43 The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the 21

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM groups given in V-43 (2-CS-104 and 105 in one group, 2-CS-13 and 24 in another group and 2-RS-11 and 17 in another group) must be disassembled every refueling outage. V-43 describes the disassembly and inspection of one valve from each group of two valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

V-44 Relief request is being withdrawn. Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. RRV-6 deals with certain containment isolation valves located inside containment that are subject to leakage testing.

The Revision J version of V-44 requested relief from performing a back seat test every cold shutdown. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

V-45 Relief request is being withdrawn. Relief Request V-45 was replaced by Reactor Refueling Justification RRV-7. RRV-7 deals with the RCP thermal barrier isolation check valves located inside containment that are subject to back seat testing. The Revision J version of V-45 requested relief from'performing a back seat test every cold shutdown. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

V-46 The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.J.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-46 (2-SW-247, 249, 251 and 2-SW-253) must be disassembled every refueling outage.

V-46 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2.

These check valves can be disassembled while the

22

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY lJNJ:T 2 IST PROGRAM plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

The Revision 3 version of V-47 submitted on July 24, 1992, requested relief from determining the alert status as required by the ;old Code. In the NRC SER received in March of 1993, the NRC reviewer determined that V-47 was not necessary because OM Part 10 does not require the determination of the alert acceptance criteria.

However, due to the data scatter displayed by the valves in V-47, relief from the requirements of OM 10, Paragraphs 4.3.1.S(b) and (d) is necessary.

Also, relief from measuring the full-stroke time from the initiation of the actuating signal was added.

V-48 Relief request is being withdrawn. Interim Relief Request V-48 was replaced by Cold-Shutdown Justification CSV-32. The Revision 3 version of V-48 requested an interim period from testing the main steam non-return valves until an alternative test method could be developed. This alternative method was developed during the Surry Unit 2 1993 refueling outage and is described in CSV-32. csv-32 was sent to the NRC by letter dated May 6, 1993 (Serial No.93-046).

V-49 Relief request is being withdrawn. The Revision 3 version of V-49 requested relief from IWV-3427(b) which required trending of leakages for Category A valves larger than six inches. OM-Part 10 does not have a similar requirement. Therefore, relief from Code requirements is no longer necessary.

V-50 These relief request is being added for check valves 2-SW-108, 113, 130, 442 and 445. The design basis for the charging pump service water system is being reevaluated. A full flow acceptance criteria will not be available until this evaluation is complete. In the mean time, these valves will be disassembled and inspected.

The test frequency is in accordance with Generic

23

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UN:IT 2 IST PROGRAM Letter 89-04, Position 2.

These check valves can be disassembled while the plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outagese v-s1* This relief request is being added and applies to containment isolation valves subject to Appendix J*, Type c leak testing. For cases where a valve has exceeded its permissible leakage rate but the overall containment leakage is below 0.6La, and the repair or replacement of the valve will have an adverse impact on plant startup and/or continued operation, an evaluation can be used as corrective action. A similar relief request was approved for use by North Anna Power Station in the NRC SER received in September of 1993(TAC NOS.

M86645 & M86646) .

4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS References to IWV were replaced with references to OM Part

10. Also, a section was added to each justification which gives a summary of the testing frequency. The following summarizes the changes to cold shutdown justifications since Revision 3.

Unit 2 Cold Shutdown Just Change CSV-1 Added test frequency summary.*

CSV-2 and These cold shutdown justification numbers are CSV-3 no longer active.

CSV-4 Reference to full flow testing check valves 2-FW-142, 157 and 172 was added. Also, a test frequency summary was added *

24

ATTACHMENT 2

CSV-5

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM Added test frequency summary.

CSV-6 Added the phrase "when the reactor coolant pumps are secured" and a test frequency summary.

CSV-7 to Added test frequency summaries.

CSV-9 CSV-10 The relief valve setting was changed from 700 psig to 600 psig. Also, a test frequency summary was added.

CSV-11 Added test frequency summary.

CSV-12 This cold shutdown justification number is no longer active.

CVS-13 Added the phrase "when the reactor coolant pumps are secured" and a test frequency summary

csv~14 to Added test frequency summaries.

CSV-18 CSV-19 Deleted reference to partial stroke testing of check valves 2-CH-225, 227 and 229. These valves will be full stroke tested every quarter when the boric acid concentration is above 100

.ppm. Also, a test frequency summary was added.

CSV-20 Replaced by Reactor Refueling Justification RRV-6.

CSV-21 Added test frequency summary.

CSV-22 to These cold shutdown justification numbers are CSV-24 no longer active.

CSV-25 & Added test frequency summaries.

CSV-26 CSV-27 Deleted valve 2-cc-TV-207 and added valves 2-CC-TV-240A and B. Also, a test frequency summary was added *

25

ATTACHMENT 2

CSV-28

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM Deleted reference to part stroke testing the main feedwater bypass valves every three months and added an explanation as to why this testing is not necessary. Also, a test frequency summary was added.

CSV-29 to Added test frequency summaries.

CSV-31 CSV-32 Cold Shutdown Justification CSV-32 was added to the IST Program to replace Interim Relief Request V-48. The Revision 3 version of V-48 requested an interim period from testing the main steam non-return valves until an alternative test method could be developed.

This alternative method was developed during the Surry Unit 2 1993 refueling outage and is described in CSV-32. CSV-32 was sent to the NRC by letter dated May 6, 1993 (Serial No.93-046) *

CSV-33 Cold Shutdown Justification CSV-33 was added to the IST Program to replace Relief Request V-31.

CSV-33 deals with the head vent isolation valves and was originally a relief request because there could exist plant conditions

during some cold shutdowns that prevent testing of these valves. Because OM Part 10 allows for a testing frequency as long as a reactor refueling frequency, relief from Code requirements is no longer necessary. As shown by the test frequency description, the appropriate test plan justification is a cold shutdown justification and not a reactor refueling justification.

4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Section 4e7 was added to the IST Program and the Revision 3 Section 4.7 was renumbered to Section 4.8.

OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during reactor refueling (but not more frequently than every three months) if the valves cannot be exercised during normal operation or cold shutdown. IWV allowed testing to be

26

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE

~URRY UNIT 2 IST PROGRAM deferred only to cold shutdowns. Therefore, no request for relief for testing every reactor refueling is necessary. A number of relief requests were replaced by reactor refueling justifications.

Unit 2 Reactor Refuel Just Change RRV-1 Reactor Refueling Justification RRV-1 was added to the IST Program to replace Relief Request V-14.

No other changes were made to the justification.

RRV-2 Reactor Refueling Justification RRV-2 was added to the IST Program to replace Relief Request v-21.

No other changes were made to the justification.

RRV-3 The justification for going to a reactor refueling frequency was moved from V-26 to RRV-3 for the SI accumulator discharge check valves. The alternative test method was changed from disassembly and inspection to using non-intrusive techniques to verify that the check valves go to the full open position. A sampling program will be *applied to the *non-intrusive techniques as**

described in Relief Request V-26.

RRV-4 ~eactor Refueling Justification RRV-4 was added to the IST Program to replace the test frequency descriptions previously found in Relief Request v-27 for the hot leg, cold leg and HHSI check valves.

RRV-5 Reactor Refueling Justification RRV-5 was added to the IST Program to replace Relief Request V-28.

The Revision 3 version of V-28 indicated that 2-SI-25 would be disassembled and inspected every other outage. Reference to the disassembly and inspection every other outage was deleted from RRV-5. The test method and frequency are in accordance with OM Part 10, Paragraph 4.3.2.4(c).

RRV-6 Reactor Refueling Justification RRV-6 was added to the IST Program to replace Relief Request V-44

27

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM No other changes were made to the justification.

RRV-7 Reactor Refueling Justification RRV-7 was added to the IST Program to replace Relief Request V-45 and Cold Shutdown Justification csv-20.

RRV-8 Reactor Refueling Justification RRV-8 was added to the IST Program to present the basis for testing the VCT discharge check valve 2-CH-230 closed every reactor refueling.

4.8 ALTERNATIVE TESTING FOR NON-CODE VALVES The Revision 3 Section 4.7 was renumbered to Section 4a8o Unit 2 Non-Code Alternative Test Change VNC-1 There is no change to VNC-1.

VNC-2 Non-Code alternative testing is being withd:cawn. VNC~2 dealt with valve 2-CW-117 which was deleted from the IST Program.

VNC-3 The air start system solenoid valves 2-EG-SOV-200A and B were added to VNC-3. These valves were covered by Relief Request V-37 in Revision J.

VNC-4 Non-Code Alternative Testing VNC-4 was added to the IST Program to replace Relief Request V-36. Also, valve 1-EE-SOV-104 was moved from the Unit 2 IST Program to the Unit 1 IST Program and deleted from VNC-4 *

28

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 PUMP INSERVICE TESTING PROGRAM References to IWP were. replaced with references to OM Part 6, Sections 7.1 to 7.4.

5.2 VALVE INSERVICE TESTING PROGRAM References to IWV were replaced with references to OM Part 10, Sections 6.1 to 6.4 *

29

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES THIRD INSPECTION INTERVAL MAY 10, 1994 - MAY 10, 2004 REVISION 0 ADDRESSES:

VIRGINIA ELECTRIC AND POWER COMPANY P.O. BOX 26666 RICHMOND, VIRGINIA 23261 SURRY POWER STATION P.O. BOX 315 SURRY, VIRGINIA 23883

TABLE OF CONTENTS

INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES

1.0 INTRODUCTION

2.0 PROGRAM DESCRIPTION 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Pump Test Program Relief Requests 3.7 Alternative Testing for Non-Code Pumps 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.1 Program Development Philosophy 4.2 Program Implementation 4.3 Program Administration 4.4 Valve Inservice Test Table 4.5 Valve Test Program Relief Requests 4.6 Valve Test Program Cold Shutdown Justifications 4.7 Valve Test Program Reactor Refueling Justifications 4.8 Alternative Testing for Non-Code Valves 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 Pump Inservice Test Program 5.2 Valve Inservice Test Program 6.0 QUALITY ASSURANCE PROGRAM

S2PVI3RO ii Revi:;ion o November 10, 1993

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

1.0 INTRODUCTION

This Pump and Valve Inservice Test (IST) Program Plan is applicable to the Surry Power Station Unit 2 which began commercial operation on May 1, 1973. The IST Program Plan is comprised of two independent subprograms - the Pump Inservice Test Program and the Valve Inservice Test Program.

The development, implementation and administration of these two programs are detailed in subsequent sections.

This IST Program Plan applies to the third 10-year IST interval for Surry Power Station Unit 2. The third interval starts on May 10, 1994 and ends by May 10, 2004.

The Code of Federal Register 10CFR50.55a(f) (4) (ii) states in part that the 10-year IST interval "must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month interval." As described in paragraph (b)(2) of 10 CFR 50.55a that was approved for use on September 8, 1992 by the Federal Register, Vol. 57, No. 152, "references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Division 1, and include addenda through the 1988 Addenda and editions through the 1989 Edition." The IST Program Plan for the third 10-year interval for Surry Unit 2 complies with these addenda and edition *

S2PVI3RO 1-1 Revision o November 10, 1993

2.0 PROGRAM DESCRIPTION

This Inservice Testing Program for ISI Class 1, 2, 3 and NC pumps and valves meets the requirements of Subsections IWP and IWV of Section XI of the ASME Boiler and Pressure Vessel Code, addenda through the 1988 Addenda and editions through the 1989 Edition. Where these requirements are determined to be impractical, specific requests for relief have been written and included in the program plan attached .

S2PVI3RO 2-1 Rev~pion O Noveinber 10, 1993

3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.1 PROGRAM DEVELOPMENT PHILOSOPHY Highly reliable safety-grade equipment is a vital consideration in the operation of a nuclear generating station. To help assure operability, the Surry Power Station Unit 2 Pump Inservice Test Program was developed.

The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operating parameters of vital pumps and to initiate corrective action when necessary. As described in Section 2, the Program must meet the:requirements of Subsection IWP, of Section XI of the ASME Boiler and Pressure Vessel Code. Subsection IWP, addenda through the 1988 Addenda and editions through the 1989 Edition, references Part 6, Edition OM-87, ASME/ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988. Therefore, the Program is based on the requirements of Part 6, along with NRC Staff guidelines provided in Generic Letter 89-04 for complying with certain provisions of 10CFR50.55a(f}.

The Nuclear Regulatory Commission and Code Committee recognized that design differences among plants may render impractical certain Code requirements. Where such impracticalities exist, they have been sub~tantiated as exceptions as allowed by the Code.

Alternate testing requirements have been proposed when warranted.

3.2 PROGRAM IMPLEMENTATION Surveillance testing is performed to detect equipment malfunction or degradation and to initiate corrective action. Since the safeguards pumps are normally in standby mode, periodic testing of this equipment is especially important. The Surry Power Station Unit 2 Inservice Test Program provides a schedule for testing safety-grade pumps and is implemented as part of normal periodic surveillance testing.

Reference data is gathered during initial surveillance tests. In most cases, test parameters are measured with normal plant instrumentation. This approach simplifies the test program and promotes timely completion of periodic surveillance testing. When permanently installed instrumentation is not available, portable instrumentation is used to record the required parameters

3-1 Revi~ion o S2PVI3RO November 10, 1993

During subsequent surveillance tests, flow rate is normally selected as the independent test parameter and is set to match the reference flow rate. Other hydraulic and mechanical performance parameters are measured and evaluated against the appropriate reference values. The results of such evaluations determine whether or not corrective action is warranted.

Each pump in the Pump Inservice Test Program is tested according to a detailed test procedure. The procedure include, as minimum:

1)

References:

This section identifies references applicable to Technical Specifications and other necessary material as drawings.

2)

Purpose:

This section identifies test objectives.

3) Initial Conditions: Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use.

4) Precautions: Precautions should be established to alert the individual performing the task to those situations in which important measures should be taken early or where extreme care should be used to protect equipment and personnel. Cautionary notes applicable to specific steps in the procedure should be included in the main body of the procedure as appropriate and should be identified as such.

5) Instructions: The main body of a procedure should contain step by step instructions in the degree of detail necessary for performing a required test.

6) Acceptance Criteria: The ranges within which test data are considered acceptable are established and included in the test procedure. In the event that data fall outside the acceptable range, operator action is governed by approved station procedures.

Finally, it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.

Additional testing is performed, as required, after pump maintenance or as determined necessary by personnel at Surry Power station *

S2PVI3RO 3-2 Revi~ion o November 10, 1993

3.3 PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Pump Inservice Test Program. The third 10-year interval IST Program will be officially implemented on May 10, 1994 and governs pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a(f) (4).

3.4 PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES".

2-CH-P-1A 2-CH-P-1B 2-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for the Safety Injection System and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11548-CBM-SSB, Sheet 2 .

2-SI-P-1A 2-SI-P-1B Low Head Safety Injection Pumps provides low pressure safety injection to the core for long term cooling and as a backup to accumulators. See drawing 11548-CBM-89A, Sheet 1.

2-CS-P-1A 2-CS-P-lB Containment Spray Pumps provide a cooled, chemically treated, borated spray to reduce containment pressure following a loss of coolant accident. See drawing 11548-CBM-84A, Sheet 2.

2-RS-P-2A 2-RS-P-2B Outside Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-CBM-84B, Sheet 2 .

S2PVI3RO 3-3 Rev.:!-.sion o November 10, 1993

2-RS-P-lA 2-RS-P-lB Inside Recirculation Spray Pumps aid the containment spray system in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-CBM-84B, Sheet 1.

2-FW-P-JA 2-FW-P-JB 2-FW-P-2 Auxiliary Feedwater Pumps supply the steam generator with feedwater in the event of a complete loss of normal feedwater. See drawing 11548-CBM-GSA, Sheet 3.

2..:RH-P-lA 2-RH-P-lB The function of Residual Heat Removal Pumps is to remove heat energy from the core when the Reactor Coolant system is below 350°F. See drawing 11548-CBM-87A, Sheet 1.

1-cc-P-1c 1-CC-P-lD

Component Cooling Water Pumps are used to supply water to remove heat from the Residual Heat Removal System.

See drawing 11448-CBM-72D, Sheet 1.

1-CH-P-2C 1-CH-P-2D Boric Acid Transfer Pumps supply boric acid to suction of charging pumps via normal coolant boration and emergency makeup. See drawing 11448-CBM-SSA, Sheet 1.

2-CC-P-2A 2-CC-P-2B Charging Pump Cooling Water Pumps provide water to transfer heat from the charging pump mechanical seals.

See drawing 11548-CBM-71B, Sheet 2.

2-SW-P-lOA 2-SW-P-lOB Charging Pump Service Water Pumps provide cooling water for Charging Pump Cooling Water Systems. See drawing 11548-CBM-71B, Sheet 1 .

S2PVI3RO 3-4 Rev,t~ion o Noveinber 10, 1993

1-EE-P-1B

1-EE-P-1E Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank. See drawing 11448-CBB-38A, Sheet 2 *

S2PVI3RO 3-5 Revision o Nov~mber 10, 1993

3.5 PUMP INSERVICE TEST TABLES This tabulation identifies the pumps to be tested, code classes, required test quantities and frequencies.

Relief from test requirements is requested in cases where test requirements have been determined to be impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable.

For non-Code pumps, a request for relief is not necessary when provisions of the Code cannot be met.

Section 3.7 contains a discussion of the testing requirements for non-Code pumps and descriptions of alternative testing in cases where the provisions of the Code cannot be met.

To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the table headings and abbreviations are provided below.

1) Pump Number - Each pump in the plant has a unique "tag" number which identifies the system to which the pump belongs.

2) Code Class - ASME Code Class of each pump as per

10CFR50.55a and Regulatory Guide 1.26

Note: NC is for non-Code pumps. These pumps are important to safety but are not in systems that are classified ASME Class 1, 2 or 3.

3) System Resist - Either FIX for a test loop with a fixed system resistance or VAR for a test loop with a system resistance that can be varied.

4) The required Section XI test quantities of Inlet Pressure, Differential Pressure (Discharge Pressure is not a required test quantity but is listed for clarity), Flow Rate, Vibration, Pump Speed and Lubrication Level/Pressure are given as column headings. The following abbreviations are used to describe the test status:

Q - the test will be performed on a quarterly basis CSD - the test will be performed every cold shutdown. A relief request explains the need for deviating from Section XI test frequency requirements

S2PVI3RO 3-6 Revision o November 10, 1993

NA - the test is not applicable, see corresponding

relief request RR - the test will be performed every reactor refueling. A relief request explains the need for deviating from Section XI test frequency requirements.

2Y - the test will be performed every 24 months Under pump speed, NA applies to constant speed pumps which do not require the measurement of speed. Therefore, no relief is necessary.

Under Lubrication Level/Pressure, NA applies to pumps that have a lubrication system with no level or pressure indication. No relief is necessary .

S2PVI3RO 3-7 Revision o November 10, 1993

PUMP IN SERVICE TEST TABLE Pump ASME System Inlet Disch Diff Flow Pump Lubrication Relief Ident. Class Resist Press Press Press Rate Vibration Speed Level/Pressure Request 2-CH-P-lA 2 VAR 0 0 0 0 0 NA 0 1 2-CH-P-lB 2 VAR 0 0 0 0 0 NA 0 1 2-CH-P-lC 2 VAR 0 0 0 0 0 NA 0 1 2-SI-P-lA 2 FIX 0 0 0 0 0 NA NA 1 2-SI-P-lB 2 FIX 0 0 0 0 0 NA NA 1 2-CS-P-lA 2 FIX 0 0 0 0 0 NA 0 1 2-CS-P-lB 2 FIX 0 0 0 0 0 NA 0 1 2-RS-P-2A 2 FIX 2Y 2Y 2Y 2Y 2Y NA NA 1 2-RS-P-2B 2 FIX 2Y 2Y 2Y 2Y 2Y NA NA 1 2-RS-P-lA 2 VAR RR RR RR RR ' RR NA NA 1 2-RS-P-lB 2 VAR RR RR RR RR RR NA NA 1 2-FW-P-3A 3 VAR 0 0 0 0 0 NA 0 1 2-FW-P-3B 3 VAR 0 0 0 0 0 NA 0 1 2-FW-P-2 3 VAR 0 0 0 0 0 0 0 1 2-RH-P-lA 2 VAR NA NA CSD CSD CSD NA NA 1, 7 2-RH-P-lB 2 VAR NA NA CSD CSD CSD NA NA 1.1 3-8 Revision o S2PVI3RO November 10, 1993

PUMP INSERVICE TEST TABLE Pump ASME System Inlet Disch Diff Flow Pump Lubrication Relief

!dent. Class Resist Press Press Press Rate Vibration Speed Level/Pressure Request 1-CC-P-lC 3 VAR 0 0 0 0 0 NA 0 1.16 l-CC-P-1D 3 VAR 0 0 0 0 0 NA 0 1.16 l-CH-P-2C 2 VAR 0 0 0 0 0 NA NA 1.18 1-CH-P-2D 2 VAR 0 0 0 0 0 NA NA 1.18 2-CC-P-2A 3 VAR 0 0 0 0 0 NA NA 1 2-CC-P-2B 3 VAR 0 0 0 0 0 NA NA 1 2-SW-P-lOA 3 VAR 0 0 0 0 0 NA NA 1 2-SW-P-lOB 3 VAR 0 0 0 0 0 NA NA 1 1-EE-P-1B NC FIX NA 0 NA 0 0 NA NA 1,PNC-1 1-EE-P-lE NC FIX NA 0 NA 0 0 NA NA 1,PNC-1 Note: PNC-1 is not a request for relief but a description of alternative testing for non-Code pumps. Refer to Section 3.7.

3-9 Revision O S2PVI3RO November 10, 1993

3.6 PUMP TEST PROGRAM RELIEF REQUESTS Relief Requests identify code requirements which are impractical for Surry Unit 2 and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed *

S2PVI3RO 3-10 Revision o Noveinber 10, 1993

RELIEF REQUEST P-0 Relief Request Withdrawn

S2PVI3RO 3-11 Revi::;ion o Nov~:inber 10, 1993

RELIEF REQUEST P-1

*Systems:

Pump{s):

Various IWP Program Pumps. See PUMP INSERVICE TEST TABLE.

Class OM Part 6 Code Requirements For Which Relief Is Requested section 4.3 Reference Values Reference vaiues shall be determined from the results of preservice testing or from the results of the first inservice test.

This request applies only to vibration testing.

Basis For Request Small reference values for vibration (Vr) will produce small acceptable ranges for pump operation. Based on a small acceptable range, an adequately and smoothly running pump could be subject to corrective action. To avoid this situation, a minimum value for Vr of 0.05 in/sec has been established for velocity measurements.

Alternate Testing Proposed Pumps with a measured reference value below 0.05 in/sec shall have subsequent test results compared to an acceptable range based on 0.05 in/sec .

S2PVI3RO 3-12 Revi::don o November 10, 1993

INTERIM RELIEF REQUEST P-2 Relief Request Withdrawn RELIEF REQUEST P-3 Relief Request Withdrawn RELIEF REQUEST P-4 Relief Request Withdrawn RELIEF REQUEST P-5 Relief Request Withdrawn

RELIEF REQUEST P-6 Relief Request Withdrawn

S2PVI3RO 3-13 Revi~ion o November 10, 1993

RELIEF REQUEST P-7

System:

Pump(s):

Residual Heat Removal 2-RH-P-1A 2-RH-P-1B Class 2 OM Part 6 Code Requirements For Which Relief Is Requested Frequency of Pump Test.

Basis For Request The low pressure RHR pumps take suction from and discharge to the reactor coolant system which operates nominally at 2235 psig.

This is well above the operating pressure for the RHR pumps.

Therefore, testing during normal operation is not possible.

Alternate Testing Proposed Pumps will be tested each cold shutdown (but not more frequently than every three months) *

S2PVI3RO 3-14 Revision o Noveinber 10, 1993

RELIEF REQUEST P-8

Relief Request Withdrawn INTERIM RELIEF REQUEST P-9 Relief Request Withdrawn RELIEF REQUEST P-10 Relief Request Withdrawn RELIEF REQUEST P-11 Relief Request Withdrawn RELIEF REQUEST P-12 Relief Request Withdrawn RELIEF REQUEST P-13 Relief Request Withdrawn RELIEF REQUEST P-14 Relief Request Withdrawn RELIEF REQUEST P-15 Relief Request Withdrawn

S2PVI3RO 3-15 Revision o November 10, 1993

RELIEF REQUEST P-16

-system: Component Cooling Pump(s): 1-CC-P-1C 1-CC-P-1D Class 3 OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph 4o3 requires reference values to be points of operation readily duplicated during subsequent tests. All subsequent test results shall be compared to these initial reference values.

Basis For Request During testing of the component cooling water pumps, flow is adjusted to the reference flow rate using an 18 inch butterfly valve. The butterfly valve is a crude throttling device and does not provide the fine tuning that is required to duplicate the reference flow rate from test to test. Consequently, throttling to the same reference flow rate during each test is not

practical

Alternate Testing Proposed Two reference points of flow versus differential pressure will be established from the reference test for each pump. A straight line approximation will be used to determine differential pressure reference points as a function of flow between the two test points. By keeping the difference between two test points small, the straight line is a good approximation of the pump curve within the two test points.

During the subsequent tests, test flow will be throttled as close as practical to the reference flow value. The test flow must fall between the two reference points used to establish the straight line approximation. The test flow and the corresponding differential pressure will be compared to either graphical and/or tabular acceptance criteria based on the straight line approximation of the reference pump curve .

S2PVI3RO 3-16 Revision o November 10, 1993

RELIEF REQUEST P-16 (Cont.)

*For example, given the straight line equation determined from the two reference points for flow and differential pressure:

Prdiff =a+ b*Q where Prdiff = the reference differential pressure based on the test value for flow (Q) recorded during subsequent tests and, a and bare constants, the acceptance criteria for the flow (Q) would be as follows:

Upper Required Action= 1.l*Prdiff Lower Required Action= 0.90*Prdiff The multipliers on Prdiff are taken from Table Jb in OM Part 6. The actual recorded.differential pressure (Padiff) will then be compared to the acceptance criteria determined from Prdiff. Also, the tests results can be trended from test to test by normalizing Padiff to Prdiff. For acceptable operation, the ratio of Padiff/Prdiff must fall between 0.9 and 1.1. A decrease in the ratio from test to test would indicate a steady degradation in pump performance *

S2PVI3RO 3-17 Revi~ion o Nov~:mber 10, 1993

RELIEF REQUEST P-17

Relief Request Withdrawn S2PVI3RO 3-18 Revision o November 10, 1993

RELIEF REQUEST P-18

*system :

Pump{s):

Chemical and Volume Control 1-CH-P-2C 1-CH-P-2D Class 2 OM Part 6 Code Requirements For Which Relief Is Requested The pressure instrument accuracy shall be within+ 2% (OM Part 6, Paragraph 4.6.1.1)

The full-scale range of each instrument shall be three times the reference value or less (OM Part 6, Paragraph 4.6.1.2).

Basis For Request Calibrating the inlet pressure instruments for the boric acid transfer pumps to an accuracy within+/- 2% has proven difficult and may be impractical in the future with the current instruments. Calibrating the inlet pressure instruments to an accuracy within+ 3% would be practical *

Also, the 15 psig.

pressures the three pressures inlet pressure gauges have a full scale range of Oto These instruments were sized by evaluating the static present at the suction side of the pumps and applying times rule of OM Part 6, Paragraph 4.6.1.2. The static range from 6 to 7 psig.

When the pumps are started, the pressure at the suction side of the pumps drops to approximately 2 psig; therefore, the inlet pressure gauges do not meet the three times rule for dynamic inlet pressure.

Using a lower range pressure gauge (i.e. Oto 5 psig) would meet the three times rule for dynamic inlet pressure; however, the lower range gauge would be repeatedly exposed to an overrange condition (static pressures in excess of 5 psig) which would damage the instruments.

Using a lower range temporary gauge on a quarterly basis presents a hardship because the process fluid contains boric acid and is contaminated. If contaminated, the temporary instruments would probably become waste material.

However, with the current o to 15 psig inlet pressure gauges calibrated to+/- 3%, a differential pressure can be determined that exceeds the accuracy requirements for differential pressure

3-19 Rev1;,sion o S2PVI3RO November 10, 1993

RELIEF REQUEST P-18 (Cont.)

Each boric acid transfer pump discharge pressure gauge (Oto 150 psig range) has an instrument loop accuracy of 1.59%. computing the maximum error for differential pressure using the current instrument configuration and an inlet pressure gauge accuracy of

+/- 3%, yields an error of 2.85 psid.

Computing the Code allowed error for differential pressure for an inlet pressure gauge with a 2% accuracy and a o to 5 psig range and a discharge pressure instrument with a 2% accuracy and a o to 150 psig range yields an error of 3.1 psid. With the current instrument configuration, the loop accuracy of each discharge pressure instrument could be as high as 1.75%, which equates to a 3.075 psid error, and still be within the Code allowed error of 3.1 psid for differential pressure. Therefore, for purposes of trending pump degradation using differential pressure and flow, the current instrument is adequate as long as the discharge pressure instrument loop accuracies remain at or below 1.75%.

Alternate Testing Proposed The *inlet pressure gauges with a full scale range of Oto 15 psig and calibrated to an accuracy within+ 3%, will be used to measure dynamic inlet pressures. Also, the loop accuracies for the discharge pressure gauges will be maintained at or below an accuracy of 1.75% to ensure that the differential pressure error is below the differential pressure error allowed by the Code *

S2PVI3RO 3-20 Revision O November 10, 1993

3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the minutes of public meeting on Generic Letter 89-04, "Paragraph (g) of 10 CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. Paragraph (g) has been replaced by Paragraph (f) in the currently approved 10 CFR 50.55a. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state.that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program. (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a 'request for relief' to be submitted to the staff.

Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3 *

Surry Power Station has elected to include certain non-Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site.

As indicated in the minutes of public meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not

'requests for relief' but are provided for information .

S2PVI3RO 3-21 Revi~ion o Nove~ber 10, 1993

NON-CODE ALTERNATIVE TESTING PNC-1

-system: Fuel Oil Pump(s): 1-EE-P-1B 1-EE-P-1E Class : NC OM Part 6 Code Requirements Which cannot Be Met Measure test quantities after the pump has been running for at least two minutes (OM Part 6, Paragraph 5.6).

Basis For Alternate Testing The pump op~rating time is limited due to operational restraints.

While the diesels are running, these pumps start automatically when the fuel oil level in the day tank reaches the low level switch, and stop when the level reaches the high level switch.

The pump run time can vary depending upon the diesel load and the resulting fuel consumption rate. If the pumps are allowed to run for five minutes prior to measuring the test quantities and the fuel consumption'rate is low, not enough time is available to

gather all of the required Section XI test data

Alternate Testing The measurement of Section XI quantities will begin when the pump automatically starts on a low tank level signal *

S2PVI3RO 3-22 Rev~sion o November 10, 1993

4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION

4.1 PROGRAM DEVELOPMENT PHILOSOPHY Surry Power Station Unit 2 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The Code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity. The Surry Unit 2 Valve Inservice Test Program satisfies these requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. Subsection IWV, addenda through the 1988 Addenda and editions through the 1989 Edition, references Part 10, Edition OM-87, ASME/ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988. Therefore, the Program is based on the requirements of Part 10, along with NRC Staff guidelines provided in Generic Letter 89-04 for complying with certain provisions of 10 CFR 50.55a(f).

This program includes valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident." It is important to note that the scope of ASME Section XI and the Surry Inservice Testing Program for its implementation includes many valves which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specifications. In these cases, the requirements of Section XI, OM Part 10 shall be met except where relief has been granted.

To generate the Surry Unit 2 Valve Program, ASME Class 1, 2 and 3 valves were analyzed to determine their required type and frequency of testing. The valves to be tested under OM Part 10 commitments are listed by system and drawing in the Valve Test Tables.

Surry Unit 2 is committed to meeting the leak rate testing requirements of:

1) 10CFR50, Appendix J for containment isolation valves and

2) OM Part 10 for other valves for which seat leakage is limited to a specific maximum amount (i.e. pressure isolation valves) unless relief is specifically requested from OM Part 10 4-1 Revision o S2PVI3RO Nove:fuber 10, 1993

requirements *

Valves subject to leak testing per Appendix J will be tested to the requirements of OM Part 10, Paragraphs 4.2.2.3(e) and 4.2.2.3(f) as required by 10 CFR 50.55a(b) (2) (vii). Appendix J satisfies the testing requirements of OM Part 10, Paragraph 4.2.2.2.

The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.

The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted (refer to Section 4.5).

The Surry Unit 2 Valve Inservice Test Program complies with the intent of the applicable codes, regulations and guidelines and makes a positive contribution to the safe operation of the plant.

4.2 PROGRAM IMPLEMENTATION The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Three types of tests are conducted as part of the Valve Test Program:

1) Valve Exercise Tests,

2) Valve Leakage Tests and

3) Safety Valve Tests The Exercise Tests verify that:

1) the valve strokes properly,

2) the valve responds to control commands,

3) the valve stroke time is within specific limits and

4) remote position indication accurately reflects the observed valve position. Remote valve position indication will be verified every two years.

Fail safe valves are tested by observing the valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.

Those valves which are scheduled to be exercised during cold shutdown are subject to the requirements of OM Part 10, Paragraph 4.2.1.2(g) which states that:

"valve exercising during cold shutdown shall commence within 48 hr of achieving cold 4-2 Revision o S2PVI3RO Noveinber 10, 1993

shutdown, and continue until all testing is

complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr provided all valves required to be tested during cold shutdown will be tested prior to plant startup.

However, it is not the intent of this Part to keep the plant in cold shutdown in order to complete cold shutdown testing."

Valve Leakage Tests verify that valves are leak tight in accordance with Appendix J or ASME Section XI.

Relief and Safety valves are required to be tested to the requirements of OM Part 1.

Certain valves cannot be full stroke exercised during normal operation following maintenance. These valves are described in the cold shutdown justifications (refer to Section 4.6) and reactor refueling justifications (refer to Section 4.7). If maintenance cannot be deferred to a shutdown condition, then an engineering evaluation must be performed prior to the maintenance to determine the effect of the maintenance on valve performance. If the evaluation shows that performance will not be affected, then no post maintenance testing is required. A partial stroke test will be performed if possible

To test check valves to the full open position, the maximum required accident condition flow must be measured through the valve. In certain cases, this flow cannot be practically established or verified.

According to Generic Letter 89-04, disassembly and inspection of the check valves on a sampling basis is an acceptable alternative testing method.

As described in Generic Letter 89-04, the sample disassembly and inspection program involves grouping similar valves and testing one valve in each group during each refueling outage. The sampling technique requires that each valve in the group be the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation. The group size cannot exceed four valves.

Additionally, at each disassembly it must be verified that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound. Also, to verify the full stroke capability of the valve, the disk should be manually exercised *

S2PVI3RO 4-3 Revision O Noveinber 10, 1993

A different valve of each group is required to be

disassembled, inspected, and manually full stroked exercised at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised or there is binding or failure of valve internals, the remaining valves in that group must be disassembled, inspected, and manually full stroked exercised during the same outage.

4.3 PROGRAM ADMINISTRATION*.

The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test. Program. The program will be officially implemented on May 10, 1994.

The program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.SSa(f) (4) for subsequent 120 month IST intervals.

4.4 VALVE. INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet OM Part 10 requirements. The tables reflect the positions taken in support of the relief requests. To aid the reader in the interpretation of the tables, brief explanations of the table headings and abbreviations are provided.

For non-Code valves, a request for relief is not necessary when provisions of the Code cannot be met.

Section 4.8 contains a discussion of the testing

.,,:.,'.'-,, ...,"*,:regui:i::*eme:.:its for non~Code valves* and descriptions**of* *-*-'*.,

alternative testing in cases where the provisions of the Code cannot be met.

1) Valve Number - Each valve in the plant has a unique "tag" number which identifies the system to which the equipment belongs and type of equipment.

2) Drawing Location - The specific coordinates of each valve are supplied to facilitate location of the valves on the flow diagrams provided.

3) Function - A brief description of the function of the valve.

4) Code Class - ASME code Class of each valve as per 10 CFR so.ssa and Regulatory Guide 1.26.

NOTE: NC is for non-Code valves. These valves are important to safety but are not in systems that are 4-4 Revision o S2PVI3RO Noveibber 10, 1993

classified ASME Class 1, 2 or 3 *

5) category - Categories are defined by OM Part 10, Section 1.4. Each valve has specific testing requirements which are determined by the category to which it belongs. Valves marked with an "E" are passive valves.

6) Size - Nominal pipe diameter to which valve connects is given in inches.

7) Valve Type - A brief description of the actuator and valve type.

The following abbreviations are used to describe actuator types. Valves may be actuated in more than one way.

MO - Motor Operated AO - Pneumatic (Air Operated)

MAN - Manually Operated SO - Electronic solenoid Operated Valves

8) Isolation Valve Type - Valves that are assigned a maximum leakage. The following abbreviations are used to describe the main isolation valve types:

CIV - Containment Isolation Valve subject to Appendix J leakage testing.

PIV - Pressure Isolation Valve which protects low pressure safety related piping from RCS pressure.

Technical Specification Section 3.1.C specifies the pressure isolation valves that are tested in accordance with this program.

9) Test Position - The following abbreviations are used to describe normal valve positions to which the valves are tested (including the valve safety position):

o - Open C - Closed OC - Open and Closed

10) Test Required - Testing requirements identified for the valves are identified here.

ST - Stroke times shall be measured per OM Part 10, Paragraph 4.2.1.4 or as modified by a specific relief request *

S2PVI3RO 4-5 Revision o November 10, 1993

EV - Exercise valve for operability at least once

every 3 months per OM Part 10, Paragraph 4.2.1.4 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, Section 4.2.1.2.

LT - Leak test shall be performed per OM Part 10, Section 4.2.2 or as modified by specific relief request.

CV - Check valves shall be exercised at least once every 3 months per OM Part 10, Paragraph 4.3.2.1 or as modified by a specific cold shutdown or reactor refueling justification which is all9wed by OM Part 10, Section 4.2.2.2.

VP - Valve position indication shall be verified per OM Part 10, Paragraph 4.1 or as modified by a specific relief request.

SP - Set points of safety and relief valves shall be tested per OM Part 1 or as modified by a specific relief request.

FS - Valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of the actuator power at least once every 3 months per OM Part 10, Paragraph-4.2.1.6 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, section 4.2.1.2 *

S2PVI3RO 4-6 Revision O Noveinber 10, 1993

VIRGINIA POWER COMPANY PAGE: 1 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE .

0VALVE NUMBER 2*BD*TV-200A DRA"ING NUMBER 11548*CBM*124A SHEET DR"G VALVE NUMBER COOR TYPE 1 OF 4 C-7 AO GATE 3.000 2 B ISO VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE EV FS ST C

C C

REL CS RR ALT POS V* CSV* RRV- VCN-21 21 21 NC TEST REQ JUST JUST TEST VP oc 11A11 STEAM GENERATOR BLOWDOYN, INSIDE CON*

TAINMENT ISOLATION VALVE 2*BD*TV-200B 11548*CBM*124A 1 OF 4 C-6 AO GATE 3.000 2 B EV C

--- 21---- ---- ----

FS C 21 ST C 21 VP oc 11A11 STEAM GENERATOR BLOWDOYN, OUTSIDE CON*

TAINMENT ISOLATION VALVE 2*BD*TV-200C 11548*CBM*124A 2 OF 4 C-7 AO GATE 3.000 2 B EV C 21 FS C 21 ST C 21 VP oc 11 B11 STEAM GENERATOR BLOWDOIIN, INSIDE CON*

TAINMENT ISOLATION VALVE 2*BD*TV*200D 11548*CBM*124A 2 OF 4 C-6 AO GATE 3.000 2 B EV C 21 FS C 21 ST C 21 oc VP 11 B11 STEAM GENERATOR BLOWDOYN, OUTSIDE CON*

TAINMENT ISOLATION VALVE 2*BD*TV*200E 11548*CBM*124A 3 OF 4 C-7 AO GATE 3.000 2 B EV C 21 FS C 21 ST C 21 VP oc 11 C11 STEAM GENERATOR BLOWDOYN, INSIDE CON*

TAINMENT ISOLATION VALVE 2*BD*TV*200F 11548*CBM*124A 3 OF 4 C*6 AO GATE 3.000 2 B EV C 21 FS C 21 ST C 21 VP oc 11 C11 STEAM GENERATOR BLOWDOYN, OUTSIDE CON*

TAINMENT ISOLATION VALVE

VIRGINIA PCllER COMPANY PAGE: 2 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 1-CC-569 DRAWING NUMBER 11448-CBM-0720 SHEET DRWG VALVE NUMBER COOR TYPE 1 OF 5 B-5 CHECK VALVE 18.000 3 C ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE CV 0

REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN-C 11 D11 COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 1-CC-578 11448-CBM-0720 1 OF 5 B-5 CHECK VALVE 18.000 3 C CV C 0

11 C" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 2-CC-001 11548-CBM-072A 2 OF 7 F-7 CHECK VALVE 6.000 3 C CV C 6 CC SUPPLY TO 11A" RC PUMP LO, STATOR SHROUD &

THERM BARRIER COOLERS, ISOL CHECK VLV 2-CC-058 11548-CBM-072A 3 OF 7 F-7 CHECK VALVE 6.000 3 C CV C 6 CC SUPPLY TO 11 811 RC PUMP LO, STATOR SHROUD &

THERM BARRIER COOLERS, ISOL CHECK VLV 2-CC-059 11548-CBM-072A 4 OF 7 F-7 CHECK VALVE 6.000 3 C CV C 6 CC SUPPLY TO 11 C11 RC PUMP LO, STATOR SHROUD &

THERM BARRIER COOLERS, ISOL CHECK VLV 2-CC-094 11548-CBM-072A 2 OF 7 C-6 CHECK VALVE 2.000 3 C CV C 7

2-CC-095 COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11548-CBM-072A 3 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2.000 3 C CV C 7 2-CC-176 11548-CBM-072A 1 OF 7 F-7 CHECK VALVE 18.000 3 C CV C 5 0 5 CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE 2-CC-177 11548-CBM-072A 1 OF 7 F-7 CHECK VALVE 18.000 3 C CV C 5 0 5 CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE 2-CC-181 11548-CBM-072A 1 OF 7 E-2 MANUAL BFLY 18.000 3 B EV C 26 0 26 CC RETURN FROM RHR HEAT EXCHANGER MANUAL ISOLATION VALVE 2-CC-185 11548-CBM-072A 1 OF 7 C-2 MANUAL BFLY 18.000 3 B EV C 26 0 26 CC RETURN FROM RHR HEAT EXCHANGER MANUAL ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 3 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASHE IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NlllBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-CC-224 11548-CBM-0728 1 OF 3 D-2 CHECK VALVE 6.000 3 C CV C 5 CC SUPPLY TO 11 C11 RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-233 11548-CBM-0728 1 OF 3 D-6 CHECK VALVE 6.000 3 C CV C 5 CC SUPPLY TO 11811 RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-242 11548-CBM-0728 1 OF 3 D-8 CHECK VALVE 6.000 3 C CV C 5 CC SUPPLY TO 11A11 RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-CC-329 11548-CBM-0718 2 OF 2 D-3 CHECK VALVE 2.000 3 C CV C 0

CHARGING PUMP COOLING IJATER PUMP DISCHARGE CHECK VALVE 2-CC-555 11548-CBM-072A 2 OF 7 C-6 CHECK VALVE 2.000 3 C CV C 7 COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2-CC-556 11548-CBM-072A 3 OF 7 C-6 CHECK VALVE 2.000 3 C CV C 7

2-CC-557 COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11548-CBM-072A 4 OF 7 C-6 CHECK VALVE COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2.000 3 C CV C 7 2-CC-592 11548-CBM-072A 4 OF 7 C-6 CHECK VALVE 2.000 3 C CV C 7 COMPONENT COOLING IJATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 2-CC-764 11548-CBM-0718 2 OF 2 C-7 CHECK VALVE 2.000 3 C CV C 0

CHARGING PUMP COOLING IJATER PUMP DISCHARGE CHECK VALVE 2-CC-806 11448-CBM-072E 1 OF 2 C-5 CHECK VALVE 1.000 3 C CV 0 30 CHARGING PUMP SEAL COOLING SURGE TANK MAKEUP CHECK VALVE

----- --- --- 31---- ---- ----

2-CC-LCV-201 11548-CBM-0718 2 OF 2 D-5 AO GATE 1.000 3 B EV C 0 31 FS C 31 ST C 47 31 0 47 31 CHARGING PUMP SEAL COOLING SURGE TANK LEVEL CONTROL/ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 4 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VAtVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*CC*RV-212A 11548*CBM-072B 1 OF 3 C-7 RELIEF VALVE .750 3 C SP 0 REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 2*CC*RV*212B 11548*CBM*072B 1 OF 3 C-5 RELIEF VALVE .750 3 C SP 0 REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 2*CC*RV-212C 1t548*CBM*072B 1 OF 3 C-3 RELIEF VALVE .750 3 C SP 0 REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 2*CC*RV-219A 11548*CBM*072A 1 OF 7 E-3 RELIEF VALVE 1.500 3 C SP 0 A RHR HEAT EXCHANGER COMPONENT COOLING 11 11 RELIEF VALVE 2*CC*RV*219B 11548*CBM-072A, 1 OF 7 D-3 RELIEF VALVE 1.500 3 C SP 0 11 8 11 RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 2-CC*RV-224 11548*CBM*072A 5 OF 7 F-6 RELIEF VALVE .750 3 C SP 0 COMPONENT COOLING PIPING RELIEF 2*CC*RV-238A 11548*CBM*072A 2 OF 7 F-6 RELIEF VALVE .750 3 C SP 0 REACTOR SHROULD COOLING COIL RELIEF VALVE 2*CC*RV*238B 11548*CBM*072A 3 OF 7 F-6 RELIEF VALVE .750 3 C SP 0 REACTOR SHROULD COOLING COIL RELIEF VALVE 2*CC*RV-238C 11548*CBM*072A 4 OF 7 F-6 RELIEF VALVE .750 3 C SP 0 REACTOR SHROULD COOLING COIL RELIEF VALVE 2-CC*TV*205A 11548*CBM*072A 2 OF 7 B-4 AO BALL 6.000 3 B EV C 6 FS C 6 ST C 6 VP oc CC RETURN FROM "A" RC PUMP LO,STATOR &SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV-205B 11548*CBM*072A 3 OF 7 B-4 AO BALL 6.000 3 B EV C 6 FS C 6 ST C 6 VP oc CC RETURN FROM 8 RC PUMP LO,STATOR &SHROll>

11 11 COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 5 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*CC*TV*205C 11548*CBM*072A 4 OF 7 B-4 AO BALL 6.000 3 B EV C 6 FS C 6 ST C 6 VP oc CC RETURN FROM 11 C11 RC PUMP LO,STATOR &SHROUD COOLERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*209A 11548*CBM*072A 1 OF 7 B-7 AO BFLY 18.000 3 B EV C 0

FS C ST C 0

VP oc CC RETURN FROM A RHR HEAT EXCHANGER, OUT*

11 11 SIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*209B 11548*CBM*072A 1 OF 7 C-7 AO BFLY 18.000 3 B EV C 0

FS C ST C 0

VP oc CC RETURN FROM 11 B11 RHR HEAT EXCHANGER, OUT*

SIDE CONTAINMENT ISOLATION VALVE

2*CC*TV*210A 11548*CBM*072B 1 OF 3 E-7 AO BFLY 6.000 3 B EV C FS C ST C VP oc CC RETURN FROM 11A11 RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*210B 11548*CBM*072B 1 OF 3 E-5 AO BFLY 6.000 3 B EV C FS C ST C VP oc CC RETURN FROM 11 B11 RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*210C 11548*CBM*072B 1 OF 3 E-4 AO BFLY 6.000 3 B EV C FS C ST C VP oc CC RETURN FROM 11 C11 RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV*220A 11548*CBM*072A 2 OF 7 C-5 AO GATE 1.500 3 B EV C 27 FS C 27 ST C 27 VP oc CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 2-CC*TV*220B 11548*CBM*072A 3 OF 7 C-5 AO GATE 1.500 3 B EV C 27

VIRGINIA POWER COMPANY PAGE: 6 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT

.,VALVE DRA"ING SHEET DR"G VALVE VALVE ASHE IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2*CC*TV-220B 11548*CBM-072A 3 OF 7 C-5 AD GATE 1.500 3 B FS C 27 ST C 27 VP DC CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 2*CC*TV-220C 11548*CBM-072A 4 OF 7 C-5 AD GATE 1.500 3 B EV C

--- 27---- ---- ----

FS C 27 ST C 27 VP oc CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARR I ER I SOLATl ON VAL VE

--- 27 2*CC-TV-240A 11548-CBM-072A 1 OF 7 D-7 AD GLOBE 3.000 3 B EV C FS C 27 ST C 27 VP DC CC RETURN FROM COOLANT PUMP THERMAL BARRIERS, INSIDE CONTAINMENT ISOLATION VALVE 2*CC*TV-240B 11548-CBM*072A 1 OF 7 D-7 AD GLOBE 3.000 3 B EV C

--- 27---- ---- ----

FS C 27 ST C 27 VP DC

CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE

\

VIRGINIA P~R COMPANY PAGE: 7 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 1-CH-109 DRAWING NUMBER 1t448-CBM-088A SHEET DRWG VALVE NUMBER COOR TYPE 1 OF 4 C-5 CHECK VALVE 11 C11 BORIC ACID TRANSFER PUMP DISCHARGE CHECK 2.000 2 C ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE CV REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN*

0 VALVE 1-CH-116 11448-CBM-OBBA 1 OF 4 C-4 CHECK VALVE 2.000 2 C CV 0 "D" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 2-CH-225 11548-CBM-0888 1 OF 2 D-3 CHECK VALVE 1.000 2 C CV 0 19 MANUAL EMERGENCY BORATION PATH CHECK VALVE 2-CH-227 11548-CBM-0888 1 OF 2 B-5 CHECK VALVE 2.000 2 C CV 0 19 MAIN EMERGENCY BORATION LINE TO CHARGING PUMP SUCTION CHECK VALVE 2-CH-228 11548-CBM-0888 1 OF 2 B-4 MANUAL GATE 1.000 2 B EV 0 19 MANUAL EMERGENCY BORATION PATH MANUAL VALVE 2-CH-229 11548-CBM-088B 1 OF 2 B-4 CHECK VALVE 1.000 2 C CV 0 19 MANUAL EMERGENCY BORATION PATH CHECK VALVE

2-CH-230 11548-CBM-OBSB 1 OF 3 C-6 CHECK VALVE CHARGING PUMP SUPPLY FROM VOLUME CONTROL TANK DISCHARGE CHECK VALVE 4.000 2 AC CV LT C

0 C

8 2-CH-256 11548-CBM-0888 2 OF 2 D-7 CHECK VALVE 2.000 2 C CV 0 "A" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE :

2-CH-258 11548-CBM-0888 2 OF 2 D-7 CHECK VALVE 3.000 2 C CV C 0

"A" CHARGING PUMP DISCHARGE CHECK VALVE 2-CH-265 11548-CBM-0888 2 OF 2 D-6 CHECK VALVE 2.000 2 C CV 0 "B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 2-CH-267 11548-CBM-0888 2 OF 2 D-6 CHECK VALVE 3.000 2 C CV C 0

"B" CHARGING PUMP DISCHARGE CHECK VALVE 2-CH-274 11548-CBM-0888 2 OF 2 D-4 CHECK VALVE 2.000 2 C CV 0

VIRGINIA POWER COMPANY PAGE: 8 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV- RRV* VCN*

11 C11 CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 2-CH-276 11548-CBM-0888 2 OF 2 D-4 CHECK VALVE 3.000 2 C CV C 0

"C" CHARGING PUMP DISCHARGE CHECK VALVE 2-CH-309 11548-CBM-088C 1 OF 2 D-4 CHECK VALVE 3.000 2 AC CIV CV C 6 LT C MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN*

MENT ISOLATION CHECK VALVE 2-CH-FCV*2113A 11548-CBM-0888 1 OF 2 C-3 AO GLOBE 1.000 2 B

EV 0 FS 0 ST 0 VP oc

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

MANUAL EMERGENCY BORATION PATH FLOW CONTROL VALVE 2*CH-FCV*2114A 11548-CBM-0888 1 OF 2 D-4 AO GLOBE 2.000 2 B EV C FS C ST C VP oc PRIMARY GRADE WATER SUPPLY TO BORIC ACID BLENDER ISOLATION VALVE 2-CH-FCV-2160 11548*CBM-088C 1 OF 2 B-4 AO GLOBE 2.000 1 AE CIV LT C VP oc CHARGING FLOW CONTROL TO LOOP FILL.HF.ADER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CH-LCV-2115B 11548-CBM-0888 2 OF 2 B-8 MO GATE 8.000 2 A EV C 0

LT C ST C 0

VP oc CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 2-CH*LCV*2115C 11548-CBM-0888 1 OF 2 C-6 MO GATE 4.000 2 B EV C 11 ST C 11 VP oc CHARGING PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK 2*CH-LCV-2115D 11548-CBM-0888 2 OF 2 C-8 MO GATE 8.000 2 A EV C 0

LT C ST C 0

VP oc

VIRGINIA POWER COMPANY PAGE: 9 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRA"'ING SHEET DR"'G VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING "'ATER STORAGE TANK 2*CH*LCV*2115E 11548-CBM-0888 1 OF 2 C-6 MO GATE 4.000 2 B EV C 11 ST C 11 VP oc CHARGING PUMP SUPPLY ISOLATION VALVE FROM VOLUME CONTROL TANK 2-CH*LCV-2460A 11548-CBM*OSSC 1 OF 2 F-7 AO GLOBE

----- B---

2.000 1 EV C 15 FS C 15 ST C 15 VP oc NORMAL LETDo.iN TO REGENERATIVE HEAT EXCHANGER ISOLATION VALVE 2*CH*LCV-2460B 11548-CBM*OSSC 1 OF 2 F-7 AO GLOBE 2.000 1 'B EV C 15 FS C 15 ST C 15 VP oc NORMAL LETDO\IN TO REGENERATIVE HEAT EXCHANGER ISOLATION VALVE 2*CH*MOV*2267A 11548-CBM-0888 2 OF 3 C-7 MO GATE 6.000 2 E VP oc CHARGING PUMP SUCTION ISOLATION VALVE FROM R"'5T, VCT AND LHSI PUMP 2-CH*MOV-22678 11548-CBM-0888 2 OF 3 B-7 MO GATE 6.000 2 E VP oc L°"' HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 2*CH*MOV*2269A 11548-CBM-0888 2 OF 3 C-5 MO GATE 6.000 2 E VP oc CHARGING PUMP SUCTION ISOLATION VALVE FROM R"'ST, VCT AND LHSI PUMP 2-CH*MOV-22698 11548-CBM-0888 2 OF 3 B-5 MO GATE 6.000 2 E VP oc L°"' HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 2*CH*MOV*2270A 11548-CBM-0888 2 OF 3 C-3 MO GATE 6.000 2 E VP oc CHARGING PUMP SUCTION ISOLATION VALVE FROM R"'ST, VCT AND LHSI PUMP 2-CH*MOV-22708 11548-CBM-0888 2 OF 3 B-3 MO GATE 6.000 2 E VP oc L°"' HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 2*CH*MOV*2275A 11548-CBM-0888 2 OF 2 D-7 MO GATE 2.000 2 B EV C 0

ST C 0

VIRGINIA POWER COMPANY PAGE: 10 OF 66 SURRY .UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE* CLASS CAT TYPE TYPE POS V- CSV- RRV* VCN-2*CH*MOV*2275A 11548-CBM-0888 2 OF 2 D-7 MO GATE 2.000 2 B VP OC A CHARGING PUMP MINIMUM RECIRCULATION ISO*

11 11 LATION VALVE 2*CH*MOV*2275B 11548-CBM-0888 2 OF 2 D-5 MO GATE 2.000 2 B EV C 0

ST C 0

VP oc 11 B11 CHARGING PUMP MINIMUM RECIRCULATION ISO*

LATION VALVE 2*CH*MOV*2275C 11548-CBM-0888 2 OF 2 D-3 MO GATE

----- B---

2.000 2 EV C 0

ST C 0

VP oc "C" CHARGING PUMP MINIMUM RECIRCULATION ISO*

LATION VALVE 2*CH*MOV*22S6A 11548-CBM-0888 2 OF 2 E-7 MO GATE 3.000 2 B EV C 0

ST C 0

oc VP CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2*CH*MOV*2286B 11548-CBM*OSSB 2 OF 2 E-6 MO GATE 3.000 2 B EV C 0

ST C 0

VP oc CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2*CH*MOV*22S6C 11548-CBM-0888 2 OF 2 E-4 MO GATE 3.000 2 B EV C 0

ST C 0

VP oc CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH*MOV*2287A 11548-CBM-0888 2 OF 2 D-7 MO GATE 3.000 2 B EV C 0

ST C 0

VP oc CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH*MOV-22878 11548-CBM-0888 2 OF 2 D-6 MO GATE 3.000 2 B EV C 0

VIRGINIA POWER COMPANY PAGE: 11 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER DRAWING NUMBER 2-CH*MOV-22878 11548-CBM-0888 SHEET DRWG VALVE NUMBER COOR TYPE 2 OF 2 D-6 MO GATE 3.000 2 B ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE ST VP C

0 oc REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV* VCN-CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH*MOV-2287C 11548-CBM-0888 2 OF 2 D-4 MO GATE 3.000 2 B EV C 0

ST C 0

VP oc CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 2-CH*MOV-2289A 11548-CBM-OBSC 1 OF 2 B-4 MO GATE 3.000 2 A CIV EV C 16 LT C ST C 16 VP oc MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CH*MOV-22898 11548-CBM*OSSC 1 OF 2 8*3 MO GATE 3.000 2 B EV C 16 ST C 16 VP oc

MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT 2-CH-MOV-2350 11548-CBM-0888 1 OF 2 B-5 MO GATE 2.000 2 B EV 0 19 ST 0 19 VP oc EMERGENCY &ORATION TO CHARGING PUMP SUCTION 2-CH-MOV-2373 11548-CBM-0888 2 OF 2 E-7 MO GATE 3.000 2 B VP oc CHARGING PUMP RECIRCULATION HEADER ISOLATION VALVE 2-CH*MOV-2381 11548-CBM-0888 1 OF 2 C-8 MO GATE 3.000 2 A CIV EV C 13 LT C ST C 13 VP oc REACTOR COOLANT PUMP SEAL WATER RETURN, OUT-SIDE CONTAINMENT ISOLATION VALVE 2-CH-RV-2203 11548-CBM*OBSC 1 OF 2 F-4 RELIEF VALVE 2.000 2 C SP 0 LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2*CH*RV-2382A 11548-CBM-OBSC 2 OF 2 F-5 RELIEF VALVE 2.000 2 C SP 0 REACTOR COOLANT PUMP SEAL WATER RELIEF VALVE, RV DISCHARGE TO PRESSURIZER RELIEF TANK

VIRGINIA POWER COMPANY PAGE: 12 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 2-CH-RV-2382B DRAWING NUMBER 11548-CBM-0888 SHEET DRWG VALVE NUMBER COOR TYPE 1 OF 2 C-7 RELIEF VALVE SEAL WATER HEAT EXCHANGER RELIEF VALVE, RV 2.000 2 C ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE SP REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN*

0 DISCHARGE TO VOLUME CONTROL TANK

2-CH-TV-2204A 11548-CBM-OBSC 1 OF 2 D-3 AO GATE

----- B--- CIV 2.000 2 EV C 15 FS C 15 LT C ST C 15 VP oc LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 2*CH-TV-2204B 11548-CBM-OBBA 4 OF 4 D-3 AO GATE

----- B--- CIV 2.000 2 EV C 15 FS C 15 LT C ST C 15 VP oc LETDOWN CONTROL FROM REGEN HX, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA PCJIER COMPANY PAGE: 13 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 2-CS-013 DRAWING NUMBER 11548-CBM-084A SHEET DRWG VALVE NUMBER COOR TYPE 2 OF 3 F-4 CHECK VALVE 8.000 2 ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE AC CIV CV LT C

0 C

REL CS RR ALT 43 43 NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN-11 A11 CONT SPRAY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 2-CS-024 11548-CBM-084A 2 OF 3 E-4 CHECK VALVE . 8.000 2 AC CIV CV C 43 0 43 LT C 11911 CONT SPii.AY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 2-CS-104 11548-CBM-084A 2 OF 3 F-3 CHECK VALVE 8.000 2 C CV C 43 0 43 CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE

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

2-CS-105 11548-CBM-084A *2 OF 3 E-3 CHECK VALVE

----- C---

8.000 2 CV C 43 0 43 CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE 2-CS-MOV-200A 11548-CBM-084A 2 OF 3 B-7 MO GATE 12.000 2 B EV 0 ST 0 VP oc CONTAINMENT SPRAY PUMP SUCTION ISOLATION VALVE 2-CS-MOV-200B 11548-CBM-084A 2 OF 3 A-7 MO GATE 12.000 2 B EV 0 ST 0 VP oc CONTAINMENT SPRAY PUMP SUCTION ISOLATION VALVE 2-CS-MOV-201A 11548-CBM-084A 2 OF 3 F-5 MO GATE 8.000 2 A CIV EV C 0

LT C ST C 0

VP oc 11 A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CS-MOV-201B 11548-CBM-084A 2 OF 3 F-5 MO GATE 8.000 2 A CIV EV C 0

LT C ST C 0

VP oc "A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CS-MOV-201C 11548-CBM-084A 2 OF 3 E-5 MO GATE 8.000 2 A CIV EV C

VIRGINIA POWER COMPANY PAGE: 14 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-CS-MOV-201C 11548-CBM-084A 2 OF 3 E-5 MO GATE 8.000 2 A CIV EV 0 LT C ST C 0

VP oc "B" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CS-MOV-201D 11548-CBM-084A 2 OF 3 E-5 MO GATE 8.000 2 A CIV EV C 0

LT C ST C 0

VP oc "B" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CS-MOV-202A 11548-CBM-084A 3 OF 3 C-6 MO GATE 6.000 2 B EV 0 ST 0 VP oc CHEMICAL ADDITION TANK DISCHARGE TO RWST ISOLATION VALVE 2-CS-MOV-202B 11548-CBM-084A 3 OF 3 B-6 MO GATE 6.000 2 B EV 0 ST 0 VP oc CHEMICAL ADDITION TANK DISCHARGE TO RWST IS.OLATION VALVE

VIRGINIA PO\IER COMPANY PAGE: 15 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN*

2-cv-002 11548-CBM-OSSA 1 OF 2 D-4 MAN GATE 8.000 2 AE CIV LT C CONTAINMENT VACUUM EJECTOR SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV*HCV-200 11548-CBM-OSSA 1 OF 2 D-3 AO GATE 8.000 2 AE CIV LT C VP QC CONTAINMENT VACUUM EJECTOR, INSIDE CONTAIN-MENT ISOLATION VALVE 2*CV*TV-250A 11548-CBM-OSSA 2 OF 2 E-4 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP QC "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*CV-TV-250B 11548-CBM*OBSA 2 OF 2 E-5 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP QC "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV-TV-250C 11548-CBM-OBSA 2 OF 2 D-4 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc "B" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-CV-TV-250D 11548-CBM-OBSA 2 OF 2 D-5 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc 8 CONTAINMENT VACUUM PUMP SUCTION ISOLATION 11 11 VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 16 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 2-CW-MOV-200A DRAWING NUMBER 11548-CBM-071A SHEET DRWG VALVE NUMBER COOR TYPE 2 OF 3 F-7 MO BFLY 96.000 NC B ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE EV ST VP C

C oc REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN-CONDENSER DISCHARGE ISOLATION VALVE 2-CW-MOV-200B 11548-CBM-071A 2 OF 3 F-7 MO BFLY 96.000 NC B EV C ST C VP DC CONDENSER DISCAHRGE ISOLATION VALVE 2-CW-MOV-200C 11548-CBM-071A 2 OF 3 F-6 MO BFLY 96.000 NC B EV C ST C VP DC CONDENSER DISCHARGE ISOLATION VALVE 2-CW-MOV-2000 11548-CBM-071A 2 OF 3 F-5 MO BFLY 96.000 NC B EV C ST C VP DC CONDENSER DISCHARGE ISOLATION VALVE 2-CW-MOV-206A 11548-CBM-071A 2 OF 3 D-7 MO BFLY 96.000 3 B EV C ST C VP DC CONDENSER INLET ISOLATION VALVE 2-CW-MOV-206B 11548-CBM-071A 2 OF 3 D-7 MO BFLY 96.000 3 B EV C ST C VP DC CONDENSER INLET ISOLATION VALVE 2-CW-MOV-206C 11548-CBM-071A 2 OF 3 D-5 MO BFLY 96.000 3 B EV C ST C VP DC CONDENSER INLET ISOLATION VALVE 2-CW-MOV-2060 11548-CBM-071A 2 OF 3 D-5 MO BFLY 96.000 3 B EV C ST C VP DC CONDENSER INLET ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 17 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NLIIBER NLIIBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-DA-TV-200A 11548-CBM-083B 3 OF 3 B-3 AO GATE . 2.000 2 A CIV EV C FS C LT C ST c.

VP oc REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMENT ISOLATION VALVE .

2-DA-TV-200B 11548-CBM-083A 1 OF 2 E-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 2-DA-TV-203A 11548-CBM-083B 3 OF 3 E-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT ISOLATION VALVE 2-DA-TV-203B 11548-CBM-083B 3 OF 3 E-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT TRIP VALVE

VIRGINIA POWER COMPANY PAGE: 18 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-DG-TV-208A 11548-CBM-083B 1 OF 3 B-2 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 2-DG-TV-208B 11548-CBM-083A 2 OF 2 C-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, OUT-SIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 19 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

1*EE*013 11448-FB *038A 2 OF 3 D-7 CHECK VALVE 1.500 NC C CV 0 DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 1-EE-031 11448-FB *038A 2 OF 3 D-6 CHECK VALVE 1.500 NC C CV 0 DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 1-EE*RV-104 11448-FB *038A 2 OF 3 D-7 RELIEF VALVE .500 NC C SP 0

--- .... ---- .... I DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 1-EE*RV-107 11448-FB *038A 2 OF 3 D-6 RELIEF VALVE .500 NC C SP 0

... ---- **-- ---- I DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 1-EE*SOV-102 11448-FB *038A 2 OF 3 D-4 SO GATE 1.000 NC B EV 0 4 DIESEL FUEL OIL PUMP DISCHARGE VALVE 1-EE*SOV-103 11448-FB *038A 2 OF 3 D-4 SO GATE 1.000 NC B EV 0 4 DIESEL FUEL OIL PUMP DISCHARGE VALVE

VIRGINIA POWER COMPANY PAGE: 20 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIIING SHEET DRIIG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-EG-040 11448-FB -046B 1 OF 3 B-8 CHECK VALVE .750 NC AC CV C LT C DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 2-EG-042 11448-FB -046B 1 OF 3 B-4 CHECK VALVE .750 NC AC CV C LT C DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 2-EG-043 11448-FB -0468 1 OF 3 E-7 AIR PILOT NC B EV 0 ST 0 3 EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 2-EG-044 11448-FB -046B 1 OF 3 E-3 AIR PILOT NC B EV 0 ST 0 3 EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 2-EG-045 11448-FB -046B 1 OF 3 E-7 CHECK VALVE NC C CV C 3 0 3 EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 2-EG-046 11448-FB -046B 1 OF 3 E-4 CHECK VALVE NC C CV C 3 0 3 EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 2-EG-SOV-200A 11448-FB -046B 1 OF 3 D-7 SO GATE 1.000 NC B EV 0 ST 0 3 DIESEL AIR START SYSTEM SOLENOID VALVE 2-EG-SOV-200B 11448-FB -046B 1 OF 3 D-4 SO GATE 1.000 NC B EV 0 ST 0 3 DIESEL AIR START SYSTEM SOLENOID VALVE

VIRGINIA POWER COMPANY PAGE: 21 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-FP-151 11548-CBB-0478 1 OF 1 D-6 MAN BALL 4.000 2 AE CIV LT C FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-FP-152 11548-CBB-0478 1 OF 1 D-7 MAN BALL 4.000 2 AE CIV LT C FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 22 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-FW-010 11548-CBM-068A 1 OF 4 E-6 CHECK VALVE 14.000 2 C CV C 5 11A11 MAIN FEEDWATER SUPPLY, INSIDE CONTAINMENT PENETRATION CHECK VALVE 2-FW-027 11548-CBM*068A 1 OF 4 E-6 CHECK VALVE 3.000 2 C CV 0 4 11A11 AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 2-FW-041 11548-CBM-068A 1 OF 4 D-6 CHECK VALVE 14.000 2 C CV C 5 11 811 MAIN FEEDWATER HEADER SUPPLY, INSIDE CONTAINMENT PENETRATION CHECK VALVE 2-FW-058 11548-CBM-068A 1 OF 4 C-6 CHECK VALVE 3.000 2 C CV 0 4 11 8 11 AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 2-FW-072 11548-CBM-068A 1 OF 4 C-6 CHECK VALVE 14.000 2 C CV C 5 11 C11 MAIN FEEDWATER SUPPLY, INSIDE CONTAINMENT PENETRATION CHECK VALVE 2-FW-089 11548-CBM-068A 1 OF 4 B-7 CHECK VALVE 3.000 2 C CV 0 4 11 C11 AUXILIARY FEEDWATER HEADER CHECK VALVE AT MAIN FEEDWATER HEADER 2-Fll-131 11548-CBM-068A 1 OF 4 B-4 CHECK VALVE 6.000 2 C CV 0 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION - INSIDE 2-FW-133 11548-CBM-068A 1 OF 4 B-4 CHECK VALVE 6.000 2 C CV 0 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION - OUTSIDE 2-FW-136 11548-CBM-068A 1 OF 4 A-4 CHECK VALVE 6.000 2 C CV 0 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION - INSIDE 2-FW-138 11548-CBM-068A 1 OF 4 A-4 CHECK VALVE 6.000 2 C CV . 0 4 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION - OUTSIDE 2-FW-142 11548-CBM-068A 3 OF 4 D-8 CHECK VALVE 6.000 3 C CV C 4 0

TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2-FW-144 11548-CBM-068A 3 OF 4 D-7 CHECK VALVE 1.000 3 C CV 0 41 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE

VIRGINIA POWER COMPANY PAGE: 23 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NlMBER NlMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2-FW-148 11548*CBM*068A 3 OF 4 E-7 CHECK VALVE 1.000 3 C CV 0 41 AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 2-FW-157 11548*CBM*068A 3 OF 4 D-6 CHECK VALVE 6.000 3 C CV C 4 0

11A11 MOTOR DRIVEN AUXILIARY FEEDWATER PIMP DISCHARGE CHECK VALVE 2-FW-159 11548-CBM-068A 3 OF 4 D*6 CHECK VALVE 1.000 3 C CV 0 41 "A" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 2-FW-163 11548*CBM*068A 3 OF 4 E-6 CHECK VALVE 1.000 3 C CV 0 41 AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 2-FW-172

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

11548*CBM*068A 3 OF 4 D*S CHECK VALVE 6.000 3 C CV C 4 0

"B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 2-FW-174 11548-CBM*068A 3 OF 4 D*S CHECK VALVE 1.000 3 C CV 0 41 "B" MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 2-FW-178 11548*CBM*068A 3 OF 4 E-4 CHECK VALVE 1.000 3 C CV 0 41 AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 2-FW-272 11548-CBM*068A 1 OF 4 A-8 CHECK VALVE 6.000 2 C CV 0 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW-273 11548*CBM*068A 1 OF 4 A-7 CHECK VALVE 6.000 2 C CV 0 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW-305 11548-CBM*068A 1 OF 4 A*S CHECK VALVE 6.000 2 C CV 0 4 CHECK VALVE AT CONT PENE (CROSS* CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW-306 11548-CBM-068A 1 OF 4 A-5 CHECK VALVE 6.000 2 C CV 0 4 CHECK VALVE AT CONT PENE (CROSS - CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 2-FW*FCV-2478 11548*CBM*068A 1 OF 4 E-4 AO GATE 14.000 NC B EV C

--- 28 FS C 28 ST C 28 VP DC

VIRGINIA POWER COMPANY PAGE: 24 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME HIV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-MAIN FEEDWATER REGULATING VALVE 2-FW-FCV-2488 11548-CBM-068A 1 OF 4 D-4 AO GATE 14.000 NC B EV C 28 FS C 28 ST C 28 VP oc MAIN FEEDWATER REGULATING VALVE 2-FW-FCV-2498 11548-CBM-068A 1 OF 4 B-4 AO GATE 14.000 NC B EV C 28 FS C 28 ST C 28 VP oc MAIN FEEDWATER REGULATING VALVE 2-FW-HCV-255A 11548-CBM-068A 1 OF 4 F-3 AO GATE 4.000 NC B EV C 28 FS C 28 ST C 28 VP oc MAIN FEEDWATER REGULATING VALVE BYPASS VALVE

2-FW-HCV-255B 11548-CBM-068A 1 OF 4 D-3 AO GATE MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 4.000 NC B EV FS ST VP C

C C

oc 28 28 28 2-FW-HCV-255C 11548-CBM-068A 1 OF 4 C-3 AO GATE 4.000 NC B EV C 28 FS C 28 ST C 28 VP oc MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 2-FW-MOV-251A 11548-CBM-068A 1 OF 4 B-7 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP oc NORMAL AUXILIARY FEEDWATER SUPPLY TO C11 11 STEAM GENERATOR 2-FW-MOV-251B 11548-CBM-068A 1 OF 4 B-7 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP QC

VIRGINIA POWER COMPANY PAGE: 25 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT

VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV- RRV- VCN-STANDBY AUXILIARY FEEDWATER SUPPLY TO "C" STEAM GENERATOR 2*FW*MOV*251C 11548*CBM*068A 1 OF 4 B-6 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP oc STANDBY AUXILIARY FEEDWATER SUPPLY TO 111 11 STEAM GENERATOR 2*FW-MOV*251D 11548*CBM*068A 1 OF 4 B-6 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP oc NORMAL AUXILIARY FEEDWATER SUPPLY TO 11111 STEAM GENERATOR 2*FW*MOV-251E 11548-CBM*068A 1 OF 4 B-6 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP oc STANDBY AUXILIARY FEEDWATER SUPPLY TO 11A11 STEAM GENERATOR 2*FW*MOV-251F 11548-CBM*068A 1 OF 4 B-5 MO GLOBE 3.000 2 B EV C 0

ST C 0

VP oc STANDBY AUXILIARY FEEDWATER SUPPLY TO 11A11 STEAM GENERATOR 2*FW*MOV-260A 11448-CBM-068A 3 OF 4 F-7 MO GLOBE 6.000 3 B EV 0 ST 0 VP oc CROSS - CONNECT FOR UNIT 1 AUXILIARY FEED-WATER FROM UNIT 2 2*FW*MOV-260B 11448*CBM-068A 3 OF 4 F-7 MO GLOBE 6.000 3 B EV 0 ST 0 VP oc CROSS - CONNECT FOR UNIT 1 AUXILIARY FEED-WATER FROM UNIT 2

VIRGINIA POWER COMPANY PAGE: 26 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE

VALVE NUMBER 2-GW*TV-200 DRAWING NIIIBER 11448*CBM*090C SHEET DRWG VALVE NIIIBER COOR TYPE 1 OF 1 C-4 SO GATE .375 2 A ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE CIV EV FS LT C

C C

REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV* RRV- VCN-ST C VP DC SUCTION LINE TO HYDROGEN ANALYZER* UNIT 1 2-GW*TV-201 11448-CBM*090C 1 OF 1 C-4 SO GATE .375 2 A CIV EV C FS C LT C ST C VP DC SUCTION LINE TO HYDROGEN ANALYZER* UNIT 1 2-GW*TV-202 11448*CBM*090C 1 OF 1 B-4 SO GATE .375 2 A CIV EV C FS C LT C ST C VP DC DISCHARGE LINE TO HYDROGEN ANALYZER* UNIT 1

----- A--- CIV 2-GW-TV-203 11448*CBM*090C 1 OF 1 B-4 SO GATE .375 2 EV C FS C LT C ST C VP DC DISCHARGE LINE TO HYDROGEN ANALYZER* UNIT 1 2-GW*TV-204 11448*CBM*090C 1 OF 1 E-4 SO GATE .375 2 A CIV EV C FS C LT C ST- C VP DC SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-GW*TV-205 11448*CBM*090C 1 OF 1 E-4 SO GATE .375 2 A CIV EV C FS C LT C ST C VP DC SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-GW*TV-206 11448*CBM-090C 1 OF 1 D-4 SO GATE .375 2 A CIV EV C FS C LT C ST C VP DC

VIRGINIA POWER COMPANY PAGE: 27 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-GW-TV-207 11448-CBM-090C 1 OF 1 D-4 SO GATE .375 2 A CIV EV C FS C LT C ST C VP oc RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-GW-TV-211A 11448-CBM-090C 1 OF 1 F-3 SO GATE

.375 2 A CIV EV C FS C LT C ST C VP oc UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 2-GW-TV-211B 11448-CBM-090C 1 OF 1 F-3 SO GATE .375 2 A CIV EV C FS C LT C ST C VP oc

UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POIJER COMPANY PAGE: 28 OF 66

SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAI.IING SHEET DRI.IG VALVE VALVE ASME II.IV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-IA-381 11548-CBM-075C 2 OF 2 B-6 CHECK VALVE -750 NC C CV 0 BOTTLED AIR SUPPLY TO 2-RC-PCV-2456 SUPPLY CHECK VALVE 2-IA-384 11548-CBM-075C 2 OF 2 B-5 CHECK VALVE .750 NC C CV 0 BOTTLED AIR SUPPLY TO 2-RC-PCV-2455C SUPPLY CHECK VALVE 2-IA-395 11548-CBM-075C 2 OF 2 B-6 CHECK VALVE .750 NC AC CV C LT C BOTTLED AIR SUPPLY TO 2-RC-PCV-2456 ISOLATION CHECK VALVE 2-IA-396 11548-CBM-075C 2 OF 2 B-5 CHECK VALVE .750 NC AC CV C LT C BOTTLED .AIR.SUPPLY TO 2-RC-PCV-2455C ISOLATION CHECK VALVE 2-IA-446 11448-CBM-075C 1 OF 5 D-7 MAN GATE 2.000 2 AE CIV LT C BACKUP INSTRUMENT AIR TO CONTAINMENT FROM UNIT 2 2-IA-704 11548-CBM-075B 2 OF 2 C-3 MAN GATE 2.000 2 AE CIV LT C BACKUP INSTRUMENT AIR TO CONTAINMENT FROM UNIT 2 2-IA-864 11548-CBM-075C 1 OF 2 E-3 CHECK VALVE 2.000 2 AC CIV CV C 6 LT C INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-IA-868 11548-CBM-075C 1 OF 2 E-3 CHECK VALVE 2.000 2 AC CIV CV C 6 LT C INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-IA-947 11548-FM -075D 1 OF 1 B-7 CHECK VALVE .500 NC AC CV C LT C BOTTLED AIR SUPPLY TO 2-MS-SOV-202A,B ISOLATION CHECK VALVE 2-IA-948 11548-FM -075D 1 OF 1 B-8 CHECK VALVE .500 NC C CV 0 BOTTLED AIR SUPPLY TO 2-MS-SOV-202A,B SUPPLY CHECK VALVE 2-IA-RV-210 11548-CBM-075C 2 OF 2 B-6 RELIEF VALVE NC C SP 0 BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE 2-IA-RV-211 115.48-CBM-075C 2 OF 2 B-5 RELIEF VALVE NC SP C 0

VIRGINIA POWER COMPANY PAGE: 29 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE 2-IA-TV-200 11548-CBM-075B 2 OF 2 B-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc INSTRUMENT AIR SUPPLY TO CONT~INMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-IA-TV-201A 11548*CBM-075J 1 OF 1 A-3 AO GATE 3.000 2 A CIV EV C FS C LT C ST C VP oc INSTRUMENT AIR SUCTION FROH CONTAINMENT 2-IA-TV-201B 11548-CBH-075J 1 OF 1 A-3 AO GATE 3.000 2 A CIV EV C FS C LT C ST C VP oc

INSTRUMENT AIR SUCTION FROM CONTAINMENT

VIRGINIA POWER COMPANY PAGE: 30 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2*LM*TV-200A 11548-CBM-OSSA 1 OF 2 B-6 AO GATE .375 2 A CIV EV C FS C LT C ST C VP QC CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-2008 11548-CBM-OSSA 1 OF 2 B-6 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2*LM-TV-200C 11548-CBM-OSSA 1 OF 2 B-5 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200D 11548-CBM-OSSA 1 OF 2 B-5 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200E 11548-CBM*OSSA 1 OF 2 B-4 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200F 11548-CBM*OSSA 1 OF 2 B-5 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2-LM-TV-200G 11548-CBM*OSSA 1 OF 2 B-6 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc

VIRGINIA POWER COMPANY PAGE: 31 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2*LM-TV*200H 11548*CBM*085A 1 OF 2 B-7 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA ~R COMPANY PAGE: 32 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE

** VALVE NUMBER 2*MS*087 DRAWING NUMBER 11548*CBM*064A SHEET DRWG VALVE NUMBER COOR TYPE 1 OF 6 C-6 MANUAL GATE MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY 4.000 2 B ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE EV C REL CS RR ALT NC TEST REQ JUST JUST TEST POS V* CSV* RRV- VCN*

FEEDWATER PUMP ISOLATION VALVE 2-MS-120 11548-CBM-064A 2 OF 6*c-6 MANUAL GATE 4.000 2 B EV C MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ISOLATION VALVE 2-MS-158 11548*CBM*064A 3 OF 6 C*6 MANUAL GATE 4.000 2 B EV C MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ISOLATION VALVE 2-MS-176 11548*CBM*064A 4 OF 6 C-7 CHECK VALVE 3.000 2 C CV C 42 0 42 11A11 MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2-MS-178 11548*CBM*064A 4 OF 6 D-7 CHECK VALVE 3.000 2 C CV C 42 0 42 11 8 11 MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2-MS-182 11548*CBM*064A 4 OF 6 D-7 CHECK VALVE 3.000 2 C CV C 42 0 42 11 C MAIN STEAM HEADER SUPPLY CHECK VALVE TO 11 TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2*MS*NRV*201A 11548*CBM*064A 1 OF 6 E-4 MO STOP CHECK 30.000 2 C CV C 32 VP oc A MAIN STEAM HEADER NON-RETURN VALVE 11 11 2*MS*NRV*201B 11548*CBM*064A 2 OF 6 D-3 MO STOP CHECK 30.000 2 C CV C 32 VP oc "BIi MAIN STEAM HEADER NOH-RETURN VALVE 2*MS*NRV*201C 11548*CBM~064A 3 OF 6 D-3 MO STOP CHECK 30.000 2 C CV C 32 VP oc 11 C11 MAIN STEAM HEADER NON-RETURN VALVE 2*MS*PCV-202A 11548*CBM*064A 4 OF 6 C-4 AO GATE 3.000 2 B EV C 0

FS C ST C 0

VP oc MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

VIRGINIA POWER COMPANY PAGE: 33 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN*

2-MS-PCV-202B 11548-CBM-064A 4 OF 6 D-5 AO GATE 3.000 2 B EV C 0

FS C ST C 0

VP QC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 2-MS-RV-201A 11548-CBM-064A 1 OF 6 E-5 AO ANGLE 4.000 2 B EV C 0

FS C ST C 47 0 47 VP oc 11A11 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-RV-201B 11548-CBM-064A 2 OF 6 E-6 AO ANGLE 4.000 2 B EV C 0

FS C ST C 47 0 47 VP oc 11 8 11 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-RV-201C 11548-CBM-064A 3 OF 6 E-5 AO ANGLE 4.000 2 B EV C 0

FS C ST C 47 0 47

'IP oc 11 C11 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 2-MS-SV-201A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 4.000 2 C SP 0 A MAIN STEAM HEADER SAFETY VALVE, SV 11 11 DISCHARGE TO ATMOS 2-MS-SV-201B 11548-CBM-064A 2 OF 6 0-6 SAFETY VALVE 4.000 2 C SP 0 11 B11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-201C 11548-CBM-064A 3 OF 6 D-6 SAFETY VALVE 4.000 2 C SP 0 11 C11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-202A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 6.000 2 C SP 0 11A11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-202B 11548-CBM-064A 2 OF 6 D-5 SAFETY VALVE 6.000 2 C SP 0

VIRGINIA POIJER COMPANY PAGE: 34 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-11 911 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-202C 11548-CBM-064A 3 OF 6 D-6 SAFETY VALVE 6.000 2 C SP 0 11 C11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-SV-203A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 6.000

C 2 SP 0 "A11 MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-2038 11548-CBM-064A 2 OF 6 D-6 SAFETY VALVE 6.000 2 C SP 0 l 11811 MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGEE TO ATMOS 2-MS-SV-203C 11548-CBM-064A 3 OF 6 D-6 SAFETY VALVE 6.000

C 2 SP 0 "C" MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-204A 11548-CBM-064A 1 OF 6 E-6 SAFETY VALVE 6.000

C 2 SP 0 11A" MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-2048 11548-CBM-064A 2 OF 6 D-6 SAFETY VALVE 6.000 2 C SP 0 "8" MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-204C 11548-CBM-064A 3 OF 6 D-6 SAFETY VALVE 6.000

C 2 SP 0

**----~**

"C" MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-205A 11548-CBM-064A 1 OF 6 E-5 SAFETY VALVE

6.000 ----- C 2 SP 0 "A" MAIN STEAM HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-2058 11548-CBM-064A 2 OF 6 D-5 SAFETY VALVE 6.000 2 C SP 0 "B" MAIN STEAi4 HEADER SAFETY VALVE, sv DISCHARGE TO ATMOS 2-MS-SV-205C 11548-CBM-064A 3 OF 6 D-5 SAFETY VALVE 6.000 2 C SP 0 "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 2-MS-TV-201A 11548-CBM-064A 1 OF 6 D-4 AO CHECK VALVE 30.000 2 B EV C ST C VP oc 11 A MAIN STEAM HEADER TRIP VALVE 11

VIRGINIA POWER COMPANY PAGE: 35 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVJCE TESTING INTERVAL DATE: 11/10/93 JNSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME JWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN-2*MS*TV*201B 11548*CBM*064A 2 OF 6 C-4 AO CHECK VALVE 30.000 2 B EV C ST C VP oc "B" MAIN STEAM HEADER TRIP VALVE 2*MS*TV*201C 11548*CBM*064A 3 OF 6 C-4 AO CHECK VALVE 30.000 2 B EV C ST C VP oc "C" MAIN STEAM HEADER TRIP VALVE 2-MS*TV-209 11548*CBM*064A 4 OF 6 F-5 AO GATE 3.000 2 B EV C FS C ST C VP oc MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO CONDENSER 2-MS*TV-210 11548*CBM*064A 4 OF 6 F-7 AO GATE 2.000 2 B EV C FS C ST C VP oc MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO STEAM GENERATOR BLOWDOWN SYSTEM

VIRGINIA POWER COMPANY PAGE: 36 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV- RRV- VCN-2-RC-16D 11548*CBM-0S6B 2 OF 3 D-7 CHECK VALVE 3.000 2 AC CIV CV C 6 LT C PRIMARY GRADE WATER SUPPLY TO PRESSURIZER RELIEF TANK 2*RC*HCV-2556A 11548*CBM*0S6A 1 OF 3 E-8 AO PLUG 2.000 1 E VP oc LOOP FILL BOUNDARY VALVE 2-RC-HCV-25568 11548-CBM*OS6A 2 OF 3 D-8 AO PLUG 2.000 1 E VP oc LOOP FILL BOUNDARY VALVE 2*RC*HCV*2556C 11548*CBM-0S6A 3 OF 3 D-3 AO PLUG 2.000 1 E VP oc LOOP FILL BOUNDARY VALVE 2-RC*MOV-2535 11548-CBM-0868 1 OF 3 E-4 MO GATE 3.000 1 B EV C 0

ST C 0

VP oc BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 2-RC*MOV-2536 11548-CBM*OS6B 1 OF 3 D-4 MO GATE 3.000 1 B EV C 0

ST C 0

VP oc BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 2-RC-PCV-2455C 11548-CBM-086B 1 OF 3 D-3 AO PLUG

----- BC---

3.000 1 EV C 7

0 7 FS C 7 SP 0 ST C 7 0 7 VP oc PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 2-RC-PCV-2456 11548-CBM-086B 1 OF 3 E-3 AO PLUG 3.000 1 BC EV C 7 0 7 FS C 7 SP 0 ST C 7 0 7 VP oc PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK

VIRGINIA POWER COMPANY PAGE: 37 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN-2*RC*SOV*200A1 11548*CBM-086A 3 OF 3 B-5 SO GATE

----- B--- ----- EV----

1.000 1 C 33 0 33 FS C 33 ST C 33 0 33 VP oc REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2*RC*SOV*200A2 11548*CBM*086A 3 OF 3 A-5 SO GATE 1.000 1 B EV C

--- 33---- ---- ----

0 33 FS C 33 ST C 33 0 33 VP oc REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2*RC*SOV*200B1 11548*CBM-086A 3 OF 3 B-5 SO GATE 1.000 1 B EV C

--- 33---- ---- ----

0 33 FS C 33 ST C 33 0 33 VP oc REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2-RC*SOV-200B2 11548*CBM*086A 3 OF 3 A-5 SO GATE

----- B---

1.000 1 EV C

--- 33---- ---- ----

0 33 FS C 33 ST C 33 0 33 VP oc REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 2-RC*Sl/*2551A 11548-CBM-0868 1 OF 3 E-6 SAFETY VALVE. 6.000 1 C SP 0 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 2-RC*SV*2551B 11548-CBM-0868 1 OF 3 E-5 SAFETY VALVE 6.000 1 C SP 0 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 2*RC*SV-2551C 11548-CBM-0868 1 OF 3 E-5 SAFETY VALVE 6.000 1 C SP 0 PRESSURIZER SAFETY VALVE, SV DISCHARGE TO PRESSURIZER RELIEF TANK 2-RC*TV*2519A 11548-CBM-0868 2 OF 3 D-7 AO GATE 3.000 2 A CIV EV C FS C LT C ST C VP oc

VIRGINIA POWER COMPANY PAGE: 38 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT

VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-PRIMARY GRADE WATER SUPPLY TO PRT-#2 RCP SEAL STANDPIPES & FLUSH CONNECT, OUT CONT ISO VLV

VIRGINIA POWER COMPANY PAGE: 39 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VAL:VE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NIJIBER NIJIBER NIJIBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV* RRV- VCN-2-RH-005 11548*CBM*0S7A 1 OF 2 E-5 CHECK VALVE 10.000 2 C CV C 8 0 8 "B" RHR PUMP DISCHARGE CHECK VALVE 2-RH-011 11548-CBM-087A 1 OF 2 E-7 CHECK VALVE 10.000 2 C CV C 8 0 8 A RHR PUMP DISCHARGE CHECK VALVE 11 11 2-RH-047 11548-CBM-087A 2 OF 2 C-3 CHECK VALVE

-- 10.000 ----- C---

1 CV 0 8 RHR DISCHARGE TO LOOP 2 COLD LEG CHECK VALVE 2-RH*FCV-2605 11548-CBM-087A . 2 OF 2 C-7 AO BFLY 12.000 2 B EV C 14 FS C 14 ST C 47 14 RHR HEAT EXCHANGERS BYPASS FLOW CONTROL VALVE 2-RH*HCV-2758 1154S*CBM-087A 2 OF 2 C-5 AO BFLY 12.000 2 B EV 0 14 FS 0 14 ST 0 47 14

2-RH*MOV-200 RHR HEAT EXCHANGERS DISCHARGE FLOW CONTROL VALVE 1154S-CBM-087A 2 OF 2 E-3 MO GATE RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 6.000 2 AE CIV LT C

--- 9---- ---- ----

2-RH*MOV-2700 11548-CBM-087A 1 OF 2 A-5 MO GATE 14.000 1 B EV C 0 9 ST C 9 0 9 VP oc RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2-RH-MOV-2701 11548-CBM-087A 1 OF 2 A-4 MO GATE

----- B---

14.000 1 EV C

--- 9---- ---- ----

0 9 ST C 9 0 9 VP oc RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2-RH-MOV*2720A 11548-CBM-087A 2 OF 2 C-3 MO GATE 10.000 1 B EV C 10 0 10 ST C 10 0 10 VP oc

VIRGINIA P~R COMPANY PAGE: 40 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-RHR RETURN ISOLATION TO 11 8 11 ACCUMULATOR DISCHARGE LINE 2-RH-MOV-27209 11548-CBM-087A 2 OF 2 B-3 MO GATE 10.000 1 B EV C 10 0 10 ST C 10 0 10 VP oc RHR RETURN ISOLATION TO 11C11 ACCUMULATOR DISCHARGE LI NE 2-RH-RV-2721 11548-CBM-087A 2 OF 2 D-4 RELIEF VALVE 3.000 2 C SP 0 RHR SYSTEM RELIEF VALVE

VIRGINIA POWER COMPANY PAGE: 41 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE IWV VALVE TEST TEST REQ JUST JUST TEST NIMBER NIMBER NIMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-RL-003 11448-CBM-118A 3 OF 3 D-7 MAN DIAPHRAGM 3.000 2 AE CIV LT C REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, OUTSIDE CONT ISOLATION VALVE 2-RL-005 11448-CBM-118A 3 OF 3 D-6 MAN DIAPHRAGM 3.000 2 AE CIV LT C REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, INSIDE CONT ISOLATION VALVE 2-RL-013 11448-CBM-118A 3 OF 3 B-7 MAN DIAPHRAGM 3.000 2 AE CIV LT C REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, INSIDE CONT ISOLATION VALVE 2-RL-015 11448-CBM-118A 3 OF 3 B-7 MAN DIAPHRAGM 3.000 2 AE CIV LT C REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, OUTSIDE CONT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 42 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAlolING SHEET DRlolG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-RM-003 11548-CBP-014B 1 OF 1 B-5 CHECK VALVE .750 2 AC CIV CV C 6 LT C RETURN TO CONTAINMENT FROM RADIATION MONITOR-ING CABINET, INSIDE CONT ISOL CHECK VALVE 2-RM-TV-200A 11548-CBP-014B 1 OF 1 B-4 AO GATE .750 2 A CIV EV C FS C LT C ST C VP oc RETURN ISOLATION FROM AIR RADIATION MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE 2-RM-TV-200B 11548-CBP-014B 1 OF 1 F-8 AO GATE .750 2 A CIV EV C FS C LT C ST C VP oc SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE 2-RM-TV-200C 11548-CBP-014B 1 OF 1 E-8 AO GATE .750 2 A CIV EV C FS C LT C ST C VP oc SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN-MENT VENT DUCT, INSIDE CONT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 43 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-RS-011 11548-CBM*084B 2 OF 2 E-5 CHECK VALVE 10.000 2 AC CIV CV C 43 0 43 LT C 11 9 11 OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-RS-017 11548-CBM-084B 2 OF 2 D-5 CHECK VALVE. 10.000 2 AC CIV CV C 43 0 43 LT C 11A11 OUTSIDE RECJRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-RS-046 11548-CBM*084B 2 OF 2 A-6 MAN GATE 2 AE CIV LT C OUTSIDE RECIRC SPRAY PUMP SUCTION BYPASS LINE ISOLATION VALVE 2-RS-053 11548-CBM-084B 2 OF 2 B-6 MAN GATE 2 AE CIV LT C OUTSIDE RECIRC SPRAY PUMP SUCTION BYPASS LINE ISOLATION VALVE 2*RS*MOV-255A 11548-CBM*D84B 2 OF 2 B-6 MO PLUG 12.000 2 A CIV EV C 0

LT C ST C 0

VP oc 11A11 OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP 2-RS-MOV-255B 11548-CBM-084B 2 OF 2 B-6 MO PLUG 12.000 2 A CIV EV C 0

LT C ST C 0

VP oc 11 8 11 OUTSIDE RECJRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP 2-RS*MOV-256A 11548-CBM-084B 2 OF 2 D-6 MO BFLY 10.000 2 A CIV EV C 0

LT C ST C 0

VP oc "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO*

LATION, OUTSIDE CONTAINMENT ISOLATION VALVE 2-RS*MOV-256B 11548-CBM-084B 2 OF 2 E-6 MO BFLY 10.000 2 A CIV EV C 0

LT C ST C 0

VP QC

VIRGINIA POWER COMPANY PAGE: 44 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-11 A11 OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO-LATION, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 45 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT

. *VALVE DRAWING SHEET DRWG VALVE VALVE ASME [WV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV- VCN-2-RT-02 11548*CBM-124A 1 OF 4 E-7 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-06 11548-CBM*124A 1 OF 4 E-6 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 2-RT-21 11548*CBM*124A 2 OF 4 E-7 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-25 11548*CBM*124A 2 OF 4 E-6 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 2-RT-40 11548*CBM*124A 3 OF 4 E-7 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 2-RT-44 11548*CBM-124A 3 OF 4 E-6 MANUAL GLOBE 3.000 2 AE LT C STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 46 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NIMBER NIMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-SA-081 11548-CBM-075E 1 OF 1 B-6 MAN GATE 2.000 2 AE CIV LT C SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, INSIDE CONTAINMENT ISOLATION VALVE 2-SA-082 11548-CBM-075E 1 OF 1 B-6 MAN GATE 2.000 2 AE CIV LT C SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 47 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 JNSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME JW VALVE TEST TEST REQ JUST JUST TEST NIIIBER NIIIBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-Sl-025 11548-CBM-089A 1 OF 3 E-5 CHECK VALVE 8.000 2 C CV C 5 0 5 RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER 2-Sl-032 11548-CBM-089B 1 OF 4 E-3 MAN GLOBE 1.000 2 AE CIV LT C ACCUMULATOR MAKEUP LINE,* OUTSIDE CONTAINMENT ISOLATION VALVE 2-S1-046A 11548-CBM-089A 1 OF 3 A-3 CHECK VALVE 12.000 2 C CV 0 2 RWST SUPPLY CHECK VALVE TO 11A11 LOW HEAD SI PUMP SUCTION 2-SI-0468 11548-CBM-089A 1 OF 3 B-3 CHECK VALVE 12.000 2 C CV 0 2 RWST SUPPLY CHECK VALVE TO 118 11 LOW HEAD SJ PUMP SUCTION 2-SI-047 11548-CBM-089A 1 OF.3 B-5 CHECK VALVE 12.000 2 C CV 0 20 11911 LOW HEAD SJ PIIIP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 2-SI-050 11548-CBM-089A 1 OF 3 C-4 CHECK VALVE 10.000 2 C CV C 2 0 2 118 11 LOW HEAD SJ PUMP DISCHARGE CHECK VALVE 2-SI-053 11548-CBM-089A 2 OF 3 B-4 CHECK VALVE 2.000 2 C CV 0 11 8 11 LOW HEAD SJ PUMP MINIMUM FLOW/TEST LINE DISCHA~GE CHECK VALVE 2-SI-056 11548-CBM-089A 1 OF 3 B-7 CHECK VALVE 12.000 2 C CV 0 20 A LOW HEAD SJ PUMP SUCTION CHECK VALVE 11 11 FROM CONTAINMENT SUMP 2-SI ~061 11548-CBM-089A 2 OF 3*9-5 CHECK VALVE 2.000 2 C CV 0 11A11 LOW HEAD SJ PUMP MINIMUM FLOW/TEST LINE DISCHARGE CHECK VALVE 2-SI-073 11548-CBM-089A 2 OF 3 E-7 MAN GLOBE .750 2 AE CIV LT C ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-079 11548-CBM-089B 4 OF 4 F-7 CHECK VALVE 6.000 1 AC PJV CV C 4 0 4 LT C RCS COLD LEG SJ ADMISSION CHECK VALVE 2-SI-082 11548-CBM-089B 4 OF 4 E-7 CHECK VALVE 6.000 1 AC PJV CV C 4 0 4

VIRGINIA POWER COMPANY PAGE: 48 OF 66 SURRY UNIT 2 REVISION: DD THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*Sl*D82 11548*CBM*089B 4 OF 4 E*7 CHECK VALVE 6.000 1 AC PIV LT C RCS COLD LEG SI ADMISSION CHECK VALVE 2-Sl-085 11548*CBM*089B 4 OF 4 D-7 CHECK VALVE 6.000 1 AC PIV CV C 4 0 4 LT C RCS COLD LEG SI ADMISSION CHECK VALVE 2-Sl-088 11548*CBM*089B 4 OF 4 D-7 CHECK VALVE 6.000 1 C CV C 27 4 0 4 RCS HOT LEG SI ADMISSION CHECK VALVE 2-Sl-091 11548-CBM*089B 4 OF 4 C-7 CHECK VALVE 6.000 1 C CV C 27 4 0 4 RCS HOT LEG SJ ADMISSION CHECK VALVE 2-Sl-094 11548*CBM*089B 4 OF 4 B-7 CHECK VALVE 6.000 1 C CV C 27 4 0 4 RCS HOT LEG SI ADMISSION CHECK VALVE 2-Sl-107 11548*CBM*089B 1 OF 4 B-7 CHECK VALVE 12.000 1 C CV 0 26 3 A ACCUMULATOR DISCHARGE CHECK VALVE 11 11 2-Sl-109 11548-CBA*0898 1 OF 4 B-8 CHECK VALVE 12.000 1 C CV C 29 0 26 3 "A" ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 2-Sl-128 11548*CBM*089B 2 OF 4 B-6 CHECK VALVE 12.000 1 C CV 0 26 3 B ACCUMULATOR DISCHARGE CHECK VALVE 11 11 2-Sl

130 11548*CBM*089B 2 OF 4 B-7 CHECK VALVE 12.000 1 C CV C 29 0 26 3 11 B11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 2-Sl-145 11548*CBM*089B 3 OF 4 B-5 CHECK VALVE 12.000 1 C CV 0 26 3 C ACCUMULATOR DISCHARGE CHECK VALVE 11 11 2-Sl-147 11548*CBM*089B 3 OF 4 B-7 CHECK VALVE 12.000 1 C CV C 29 0 26 3

VIRGINIA P~R COMPANY PAGE: 49 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER DRAYING NUMBER SHEET DRYG VALVE NUMBER COOR TYPE 11c11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV* VCN-2-Sl-150 11548-CBM*089A 3 OF 3 F-6 MAN GLOBE .750 2 AE CIV LT C BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG 2-Sl-174 11548-CBM-089A 3 OF 3 D-6 MAN GLOBE .750 2 AE CIV LT C HIGH HEAD SAFETY INJECTION YO RCS*

2-Sl-224 11548-CBM-0898 4 OF 4 F-3 CHECK VALVE

3.000 2 C CV 0 4 HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 2-Sl-225 11548-CBM-089B 4 OF 4 E-3 CHECK VALVE 3.000 2 C CV 0 4 HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 2-Sl-226 11548-CBM-089B 4 OF 4 C-3 CHECK VALVE 3.000 2 C CV 0 4 HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE

2-Sl-227 2-Sl-228 11548*CBM*089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11548-CBM-089B 4 OF 4 B-3 CHECK VALVE 3.000 2 6.000 2 C

C CV CV 0

0 4

4 LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2-SI-229 11548-CBM-089B 4 OF 4 B-3 CHECK VALVE 6.000 2 C CV 0 4 LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2-SI-235 11548-CBM*089B 4 OF 4 F-7 CHECK VALVE . 2.000 1 C CV C 4 0 4 HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 2-SI-236 11548-CBM-089B 4 OF 4 E-7 CHECK VALVE 2.000 1 C CV C 4 0 4 HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 2-SI-237 11548-CBM*089B 4 OF 4 D-7 CHECK VALVE 2.000 1 C CV C 4 0 4

VIRGINIA POWER COMPANY PAGE: 50 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVJCE TESTING INTERVAL DATE: 11/10/93 JNSERVJCE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER DRAWING NIMBER SHEET DRWG VALVE NUMBER COOR TYPE HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV* VCN*

2-SI-238 11548-CBM-0898 4 OF 4 D-7 CHECK VALVE 6.000 1 C CV C 27 4 0 4 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG 2-SI-239 11548-CBM-0898 4 OF 4 C-7 CHECK VALVE 6.000 1 C CV C 27 4 0 4 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG 2-SI-240 11548-CBM-0898 4 OF 4 B-7 CHECK VALVE 6.000 1 C .CV C 27 4 0 4 LOW HEAD SAFETY INJECTION SUPPLY CHECK VALVE TO RCS HOT LEG 2-SI-241 11548-CBM-089B 4 OF 4 F-7 CHECK VALVE 6.000 1 AC PIV CV C 4 0 4 LT C LOW HEAD SJ TO RCS COLD LEG ISOLATION CHECK VALVE

2-SI-242 11548-CBM-0898 4 OF 4 E-7 CHECK VALVE LOW HEAD SI TO RCS COLD LEG ISOLATION CHECK VALVE 6.000 1 AC PIV

---* -------------------------------------- ****4**-----~------- ----- ----- --- ----

2-SI-243 11548-CBM-089B 4 OF 4 D-7 CHECK VALVE 6.000 1 AC PIV CV LT CV C

0 C

C 4

4 4

0 4 LT C LOW HEAD SI TO RCS COLD LEG ISOLATION CHECK VALVE 2-SI-304 11548-CBM-089B 1 OF 4 F-3 CHECK VALVE 1.000 2 AC CIV CV C 6 LT C NITROGEN SUPPLY TO ACCUMULATORS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 2-SJ-321 11548-CBM-089A 1 OF 3 A-5 MAN GLOBE .750 2 AE CIV LT C LOW HEAD SJ FROM CHARGING HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 2-SI-322 11548-CBM-089A 1 OF 3 B-7 MAN GLOBE .750 2 AE CIV LT C LOW HEAD SI FROM CHARGING HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 2-Sl-327 11548-CBM*089A 1 OF 3 C-6 CHECK VALVE 10.000 2 C CV C 2 0 2

VIRGINIA POIJER COMPANY PAGE: 51 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-11 A11 LOW HEAD SI PUMP DISCHARGE CHECK VALVE 2-SI-400 11548-CBH-089A 1 OF 3 E-4 CHECK VALVE 10.000 2 C CV 0 5 RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER 2-SI-MOV-2842 11548-CBH-089A 3 OF 3 D-7 MO GATE

----- A---

3.000 2 CIV EV C 25 0 25 LT C ST C 25 0 25 VP oc HIGH HEAD SI FROM CHARGING HEADER TO RCS COLO LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2860A 11548-CBH-089A 1 OF 3 B-7 MO GATE 12.000 2 A CIV EV 0 LT C ST 0 VP oc 11 A11 LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 2-SI-MOV-2860B 11548-CBM-089A 1 OF 3 B-5 MO GATE 12.000 2 A CIV EV 0 LT C ST 0 VP oc 11 8 11 LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 2-SI-MOV-2862A 11548-COM-089A 1 OF 3 A-3 MO GATE 12.000 2 B EV C ST C VP oc 11 A11 LOW HEAD SI PUMP SUCTION FROM RWST 2-SI-MOV-2862B 11548-CBM-089A 1 OF 3 B-3 MO GATE 12.000 2 B EV C ST C VP oc 11 811 LOW HEAD SI PUMP SUCTION FROM RWST 2-SI-MOV-2863A 11548-CBM-089A 2 OF 3 C-5 MO GATE 8.000 2 B EV C 0

ST C 0

VP oc 11 A LOW HEAD SAFETY INJECTION PUMP SUPPLY 11 ISOLATION TO CHARGING PUMPS 2-SI-MOV-28638 11548-CBM-089A 2 OF 3 0-3 MO GATE 8.000 2 B EV C 0

ST C

VIRGINIA POWER COMPANY PAGE: 52 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME. IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV* RRV- VCN-2-Sl*MOV-28638 11548-CBM-089A 2 OF 3 D-3 MO GATE 8.000 2 B ST 0 VP QC 8 LOW HEAD SAFETY INJECTION PUMP SUPPLY 11 11 ISOLATION TO CHARGING PUMPS 2*Sl*MOV-2864A 11548-CBM-089A 2 OF 3 D-6 MO GATE 10.000 2 B EV C 0

ST C 0

VP QC 11A11 LOW HEAD SI PlllP COLD LEG DISCHARGE $TOP VALVE 2-Sl*MOV-28648 11548*CBM*089A 2 OF 3 D-4 MO GATE 10.000 2 B EV C 0

ST C 0

VP OC 8 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP 11 11 VALVE 2*SI*MOV-2865A 11548-CBM-0898 1 OF 4 C-7 MO GATE 12.000 2 B EV C 0

ST C 0

VP QC 11A11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-SI-MOV-28658 11548-CBM-0898 2 OF 4 C-6 MO GATE 12.000 2 B EV C 0

ST C 0

VP QC 11 B11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD.LEG 2-SI*MOV-2865C 11548-CBM-0898 3 OF 4 C-5 MO GATE 12.000 2 B EV C 0

ST C 0

VP QC 11 C11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-Sl-MOV-2867C 11548-~BM-089A 3 OF 3 F-6 MO GATE 3.000 2 A CIV EV C 18 0 18 LT C ST C 18 0 18 VP QC BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 53 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-SI-MOV-2867D 11548-CBM-089A 3 OF 3 E-6 MO GATE 3_000 2 A CIV EV C 18 0 18 LT C ST C 18 0 18 VP oc BORON INJECTION TANK OUTLET TO RCS COLD.LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2869A 11548-CBM-089A 3 OF 3 C-7 MO GATE 3_000 2 A CIV EV C 25 0 25 LT C ST C 25 0 25 VP oc HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2869B 11548-CBM-089A 3 OF 3 E-4 MO GATE 3.000 2 A CIV EV C 25 0 25 LT C ST C 25 0 25 VP oc HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2885A 11548-CBM-089A 2 OF 3 B-5 MO GATE 2.000 2 A EV C LT C ST C VP oc "A" LOW HEAD SI PlJiliP MINIMUM FLOIJ/TEST LINE ISOLATION 2-SI-MOV-2885B 11548-CBM-089A 2 OF 3 B-4 MO GATE 2.000 2 A EV C LT C ST C VP oc 11 811 LOW HEAD SI PUMP MINIMUM FLOIJ/TEST LINE ISOLATION 2-SI-MOV-2885C 11548-C8M-089A 2 OF 3 8-4 MO GATE 2.000 2 A EV C LT C ST C VP oc 8 LOW HEAD SI PUMP MINIMUM FLOIJ/TEST LINE 11 11 ISOLATION .

2-S1-MOV-2885D 11548-C8M-089A 2 OF 3 8-5 MO GATE 2.000 2 A EV C LT C ST C VP oc

VIRGINIA POWER COMPANY PAGE: 54 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-

"A" LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 2-SI-MOV-2890A 11548-CBM-089A 2 OF 3 C-7 MO GATE 10.000 2 A CIV EV C 0

LT C ST C 0

VP oc "A" LOW HEAD SI PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2890B 11548-CBM-089A 2 OF 3 E-7 MO GATE 10.000 2 A CIV EV C 0

LT C ST C 0

VP oc "B" LOW HEAD SI PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-MOV-2890C 11548-CBM-089A 2 OF 3 D-7 MO GATE

----- A--- CIV 10.000 2 EV C 17 0 17 LT C ST C 17 0 17 VP oc LOW HEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-RV-2845A 11548-CBM-089A 2 OF 3 E-6 RELIEF VALVE 1.000 2 C SP 0 11A11 LOW HEAD SI PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2-SI-RV-2845B 11548-CBM-089A 2 OF 3 E-5 RELIEF VALVE 1.000 2 C SP 0 LOW HEAD SI HEADER TO COLD LEG RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2-SI-RV-2845C 11548-CBM-089A 2 OF 3 E-5 RELIEF VALVE 1.000 2 C SP 0 "B" LOW HEAD SI PUHP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 2-SI-TV-200 11548-CBM-089A 3 OF 3 B-7 AO GATE 1.000 2 A CIV EV C FS C LT C ST C VP oc NITROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SI-TV-201A 11548-CBM-089B 1 OF 4 C-3 AO GATE 1.000 2 A CIV EV C FS C LT C

VIRGINIA POYER COMPANY PAGE: 55 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT

'VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*Sl*TV*201A 11548-CBM-0898 1 OF 4 C-3 AO GATE 1.000 2 A CIV ST C VP oc ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, INSIDE CONTAINMENT ISOLATION VALVE 2*Sl*TV*201B 11548*CBM*089B 1 OF 4 B-2 AO GATE 1.000 2 A CIV EV C FS C LT C ST C VP oc ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*Sl*TV*202A 11548*CBM*089A 1 OF 3 E-7 AO GATE 8.000 2 B EV 0 FS 0 ST 0 VP oc UNIT 1 RWST TO UNIT 2 RWST CROSS TIE 2*SI*TV*202B 11548*CBM*089A 1 OF 3 E-7 AO GATE 8.000 2 B EV 0 FS 0 ST 0 VP oc

UNIT 1 RWST TO UNIT 2 RWST CROSS TIE

VIRG-INIA PMR Cl>>4PANY PAGE: 56 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2*SS*TV-200A 11548-CBM-082A 2 OF 3 F-7 SO GATE .375 1 A CIV EV C FS C LT C ST C VP oc PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 2*SS*TV*200B 11548*CBM-082A 2 OF 3 F-6 AO GATE .375 1 A CIV EV C FS C LT C ST C VP oc PRESSURIZER LIQUID SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SS*TV*201A 11548-CBM*082A 2 OF 3 E-7 SO GATE .375 1 A CIV EV C FS C LT C ST C VP oc PRESSURIZER VAPOR SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 2*SS-TV-201B 11548-CBM-082A 2 OF 3 E-6 AO GATE .375 1 A CIV EV C FS C LT C ST C VP oc PRESSURIZER VAPOR SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2*SS-TV-202A 11548-CBM-082A 2 OF 3 D-7 SO GATE .375 1 A CIV EV C FS C LT C ST C VP oc REACTOR COOLANT COLD LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 2*SS*TV-202B 11548-CBM-082A 2 OF 3 D-6 SO GATE .375 1 A CIV EV C FS .c LT C ST C VP oc REACTOR COOLANT COLD LEGS SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SS-TV-203A 11548-CBM-082A 2 OF 3 F-7 SO GATE .375 2 AE CIV LT C VP oc RHR SAMPLE HEADER, INSIDE CONTAINMENT ISOLA-TION VALVE 2*SS*TV-203B 11548-CBM-082A 2 OF 3 F-6 SO GATE .375 2 AE CIV LT C

I j

VIRGINIA POWER COMPANY PAGE: 57 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET. DRWG VALVE

VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-SS-TV-203B 11548-CBM-082A 2 OF 3 F-6 SO GATE .375 2 AE CIV VP OC RHR SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLA-TION VALVE 2-SS-TV-204A 11548-CBM-082A 2 OF 3 D-7 SO GATE .375 2 A CIV EV C FS C LT C ST C VP oc PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 2-SS-TV-204B 11548-CBM-D82A 2 OF 3 C-6 AO GATE .375 2 A CIV EV C FS C LT C ST C VP oc PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 2-SS-TV-206A 11548-CBM-082A 2 OF 3 E-7 SO GATE .375 1 A CIV EV C FS C LT C ST C oc VP REACTOR COOLANT HOT LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 2-SS-TV-206B 11548-CBM--082A 2 OF 3 E-6 SO GATE .375 1 A CIV EV C FS C LT C ST C VP oc REACTOR COOLANT HOT LEGS SAMPLE HEADER, OUT-

.SIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 58 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*SV*TV-202A 11548*CBM-066A 2 OF 3 E-4 AO GATE 6.000 2 A CIV EV C FS C LT C ST C VP QC CONDENSER AIR REMOVAL DISCHARGE TO CONTAIN*

MENT, OUTSIDE CONTAINMENT ISOLATION VALVE

VIRGINIA POWER C<J!PANY PAGE: 59 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM* VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASHE IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN*

2*SW*108 11548*CBM*071B 1 OF 2 B-4 CHECK VALVE 2.000 3 C CV C 0 50 CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 2*SW*113 11548*CBM*071B 1 OF 2 B-7 CHECK VALVE 2.000 3 C CV C 0 50 CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 2-SW-130 11548*CBM*071B 1 OF 2 D-7 CHECK VALVE 2.000 NC C CV 0 so CIRCULATING WATER TO DISCHARGE TUNNEL CHECK VALVE 2-SW-206 11548*CBM-071A 3 OF 3 E*S MAN GATE 2.000 2 AE CIV LT C CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 2-SW-208 11548*CBM*071A 3 OF 3 E-8 MAN GATE 2.000 2 AE CIV LT C CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 2-SW-246 11548*CBM*071A 3 OF 3 D-8 CHECK VALVE 3.000 NC C CV 0 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 2-SW-247 11548*CBM*071A 3 OF 3 D-7 CHECK VALVE 3.000 3 C CV 0 46 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2-SW-248 11548*CBM*071A 3 OF 3 D-7 CHECK VALVE 3.000 NC C CV 0 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 2-SW-249 11548*CBM*071A 3 OF 3 D-6 CHECK VALVE 3.000 3 C CV 0 46 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2-SW-250 11548*CBM*071A 3 OF 3 D-6 CHECK VALVE 3.000 NC C CV 0 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 2-SW-251 11548*CBM*071A 3 OF 3 D-6 CHECK VALVE 3.000 3 C CV 0 46 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2-SW-252 11548*CBM*071A 3 OF 3 D-5 CHECK VALVE 3.000 NC C CV 0

VIRGINIA POWER COMPANY PAGE: 60 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 2-SW-2S3 11S48-CBM-071A 3 OF 3 0-S CHECK VALVE 3.000 3 C CV 0 46 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE .

2-SW-442 11S48-CBM-071B 1 OF 2 B-4 CHECK VALVE 2.000 3 C CV 0 so CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2-SW-44S 11S48-CBM-071B 1 OF 2 B-6 CHECK VALVE 2.000 3 C CV 0 so CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2-SW-MOV-201A 11S48-CBM-071A 3 OF 3 B-4 MO BFLY 36.000 3 B EV C ST C VP oc BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2-SW-MOV-201B 11S48-CBM-071A 3 OF 3 B-4 MO BFLY 36.000 3 B EV C ST C VP oc BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2-SW-MOV-202A 11S48-CBM-071A 2 OF 3 D-6 MO BFLY 42.000 3 B EV C ST C VP oc SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2-SW-MOV-202B 11S48-CBM-071A 2 OF 3 D-S MO BFLY 42.000 3 B EV C ST C VP oc SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2-SW-MOV-203A 11S48-CBM-071A 3 OF 3 B-8 MO BFLY 30.000 3 B EV 0 ST 0 VP oc SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV-203B 11548-CBM-071A 3 OF 3 B-8 MO BFLY 30.000 3 B EV 0 ST 0 VP oc SERVICE WATER HEADER SUPPLY ISOLATION To*

RECIRC SPRAY HEAT EXCHANGERS

VIRGINIA POWER COMPANY PAGE: 61 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE

VALVE NUMBER 2-SW-MOV-203C DRAWING NUMBER 11548-CBM-071A SHEET DRWG VALVE NUMBER COOR TYPE 3 OF 3 B-3 MO BFLY 30.000 3 B ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE EV ST VP 0

0 oc REL CS RR ALT NC TEST REQ JUST JUST TEST POS V- CSV- RRV- VCN-SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV-2030 11548*CBM-071A 3 OF 3 B*2 MO BFLY 30.000 3 B EV 0 ST 0 VP oc SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SW-MOV-204A 11548-CBM-071A 3 OF 3 D-7 MO BFLY 24.000 3 B EV C 0

ST C 0

VP oc SERVICE WATER SUPPLY TO 11A11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-204B 11548*CBM*071A 3 OF 3 D-6 MO BFLY 24.000 3 B EV C 0

ST C 0

oc VP SERVICE WATER SUPPLY TO 11 B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-204C 11548-CBM-071A 3 OF 3 D-5 MO BFLY 24.000 3 B EV C 0

ST ' C 0

VP OC SERVICE WATER SUPPLY TO 11 C11 RECIRC SPRAY.HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-204D 11548-CBM-071A 3 OF 3 D*4 MO BFLY 24.000 3 B EV C 0

ST C 0

VP oc SERVICE WATER SUPPLY TO D RECIRC SPRAY HEAT 11 11 EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-205A 11548-CBM*071A 3 OF 3 D-8 MO BFLY 24.000 3 B EV C 0

ST C 0

VP oc SERVICE WATER RETURN FROM 11A11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW-MOV-2058 11548-CBM-071A 3 OF 3 D*7 MO BFLY 24.000 3 B EV C 0

VIRGINIA POIJER COMPANY PAGE: 62 OF 66 SURRY UNIT 2 REVISION: 00 THIRD JNSERVJCE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME JW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV* RRV- VCN*

2-SW*MOV*205B 11548-CBM*071A 3 OF 3 D-7 MO BFLY 24.000 3 B ST C 0

VP oc SERVICE WATER RETURN FROM 11 B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-SW*MOV*205C 11548-CBM-071A 3 OF 3 D-6 MO BFLY 24.000 3 B EV C 0

ST C 0

VP OC SERVICE WATER RETURN FROM "C11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2*SW*MOV-205D 11548*CBM-071A 3 OF 3 D-5 MO BFLY 24.000 3 B EV C 0

ST C 0

VP oc SERVICE WATER RETURN FROM 11 D11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2*SW-TCV-208A 11548*CBM*071B 1 OF 2 E-7 AO GATE 1.500 3 B EV 0 FS 0 ST 0 47 SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 2-SW*TCV*208B 11548-CBM*071B 1 OF 2 E-5 AO GATE 1.500 3 B EV 0 FS 0 ST 0 47 SERVICE WATER TO CHARGING PUMP LUSE OIL COOLER TEMPERATURE CONTROL VALVE 2-SW-TCV-208C 11548*CBM*071B 1 OF 2 E-4 AO GATE 1.500 3 B EV 0 FS 0 ST 0 47 SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE

VIRGINIA POWER COMPANY PAGE: 63 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV- RRV- VCN-2-VA-001 11548-CBM-0838 3 OF 3 F-3 MAN GATE 2.000 2 AE CIV LT C VENT LINE FROM PRIMARY VENT POT, OUTSIDE CONTAINMENT ISOLATION VALVE 2-VA-009 11548-CBM-083B 3 OF 3 F-4 MAN GATE 2.000 2 AE CIV LT C VENT LINE FROM PRIMARY VENT POT, INSIDE .

CONTAINMENT ISOLATION VALVE

VIRGINIA POWER COMPANY PAGE: 64 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAWING SHEET DRWG VALVE VALVE ASME IWV VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV* RRV* VCN-2*VG*TV*209A 11548-CBM-083B 1 OF 3 E-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, INSIDE CONT ISOL *vLV 2-VG*TV-2098 11548*CBM*083A 2 OF 2 F-3 AO GATE 2.000 2 A CIV EV C FS C LT C ST C VP oc VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT ISOL VLV

VIRGINIA POWER COMPANY PAGE: 65 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAI.IING SHEET DRI.IG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V- CSV* RRV- VCN-2-VP-12 11548-CBM-066A 2 OF 3 F-4 CHECK VALVE 6.000 2 AC CIV CV C 6 LT C CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE

VIRGINIA POIJER COMPANY PAGE: 66 OF 66 SURRY UNIT 2 REVISION: 00 THIRD INSERVICE TESTING INTERVAL DATE: 11/10/93 INSERVICE TESTING PROGRAM - VALVE TABLE NC ISO REL CS RR ALT VALVE DRAIJING SHEET DRIJG VALVE VALVE ASME IW VALVE TEST TEST REQ JUST JUST TEST NUMBER NUMBER NUMBER COOR TYPE SIZE CLASS CAT TYPE TYPE POS V* CSV* RRV* VCN-2*VS*MOV*200A 11548-CBB*006A 1 OF 2 C-7 MO BFLY 36.000 2 AE CIV LT C VP oc CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT ISOLATION VALVE 2*VS*MOV-200B 11548*CBB-006A 1 OF 2 C-8 MO BFLY 36.000 2 AE CIV LT C VP oc CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 2*VS*MOV*200C 11548-CBB*006A 1 OF 2 D-7 MO BFLY 36.000 2 AE CIV LT C VP oc CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLATION VALVE 2-VS*MOV-2000 11548-CBB*006A 1 OF 2 D-8 MO BFLY 36.000 2 AE CIV LT C VP oc CONTAINMENT PURGE EXHAUST, OUTSIDE CONTAIN*

MENT ISOLATION VALVE 2-VS*MOV-201 11548-CBB-006A 1 OF 2 D-7 MO BFLY 8.000 2 AE CIV LT C VP oc CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT ISOLATION VALVE 2-VS*MOV-202 1154S*CBB*006A 1 OF 2 C-7 MO BFLY 18.000 2 AE CIV LT C VP oc CONTAINMENT VACUUM BREAKER

4.5 VALVE TEST PROGRAM RELIEF REQUESTS

Relief Requests identify code requirements which are impractical for Surry Unit 2 and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of code requirements is proposed *

S2PVI3RO 4-7 Revision o November 10, 1993

RELIEF REQUEST V-1 Relief Request Withdrawn RELIEF REQUEST V-2 Replaced by Cold Shutdown Justification csv-1 RELIEF REQUEST V-3 Replaced by Cold Shutdown Justification CSV-2 RELIEF REQUEST V-4 Replaced by Cold Shutdown Justification CSV-4

S2PVI3RO 4-8 Revipion o November 10, 1993

RELIEF REQUEST V-5

system Valve(s):

Feedwater 2-FW-10 2-FW-41 2-FW-72 Category: C Class : 2 Function: Main Feedwater check valves at Contain_ment Penetrations.

OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used. e, This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Request Closure of these valves during power operation would require securing feedwater which would result in reactor trip. Cold shutdown testing of valves using flow to verify closure is inconclusive due to the inability to establish adequate differential pressure across the valve disc.

- - . '/',;

A *te::se*was**curnlucted in an t:ffort i.:o verify whether closure* of these valves can be determined using flow. Because there is no isolation boundary between the steam generators and the valves, the test volume must include the steam generators. A steam generator was pressurized with a nitrogen blanket to approximately 5 psig. The 0.75 inch drain valve just upstream of the check valve was opened and flow was observed~ The 14 inch check valve did not stop the back flow through the vent. It was concluded that the flow was inadequate to seat the check valve completely. Just a small gap between the disc and the seat was sufficient to create a flow area equal to or greater than the flow area through the drain. Therefore, the pressure differential associated with the back flow is being created across the drain valve and not the disc of the check valve.

The above test proved to be inconclusive because of the inability to establish a sufficient differential pressure across the disc.

The only way to increase the differential pressure is to increase the flow area from the test volume. However, this is not achievable for the existing configuration. Immediately upstream 4-9 Revision O S2PVI3RO November 10, 1993

RELIEF REQUEST V-5 (Cont.)

of the drain valve is another 14 inch check valve, so the only available flow area from the test volume is the drain valve.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled every reactor refueling. A different valve will be disassembled every reactor refueling. This test frequency is in accordance with Generic Letter 89-04, Position 2 .

S2PVI3RO 4-10 Revision o November 10, 1993

RELIEF REQUEST V-6

Relief Request Withdrawn RELIEF REQUEST V-7 Replaced by Cold Shutdown CSV-5 RELIEF REQUEST V-8 Replaced by Cold Shutdown Justification CSV-6 RELIEF REQUEST V-9 Replaced by Cold Shutdown Justification CSV-20 RELIEF REQUEST V-10 Replaced by Cold Shutdown Justification CSV-23 RELIEF REQUEST V-11 Replaced by Cold Shutdown Justification CSV-8 RELIEF REQUEST V-12 Replaced by Cold Shutdown Justification CSV-9 RELIEF REQUEST V-13 Replaced by Cold Shutdown Justification csv-10 RELIEF REQUEST V-14 Replaced by Reactor Refueling Justification RRV-1

S2PVI3RO 4-11 Revi~ion o November 10, 1993

RELIEF REQUEST V-15

Replaced by Cold Shutdown Justification csv-11 RELIEF REQUEST V-16 Replaced by Cold Shutdown Justification csv-12 RELIEF REQUEST V-17 Replaced by Cold Shutdown Justification CSV-13 RELIEF REQUEST V-18 Replaced by Cold Shutdown Justification CSV-15 RELIEF REQUEST V-19 Replaced by Cold Shutdown Justification CSV-16

S2PVI3RO 4-12 Revision o November 10, 1993

RELIEF REQUEST V-20

system Valve(s):

Safety Injection 2-SI-47 2-SI-56 category: c Class : 2 Function: Low Head Safety Injection Pump Suction from Containment Sump Check Valve OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) .reads in part that, "disassembly every refueling outage to verify operability*of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Request To partial or full flow test these valves requires taking suction from the reactor containment sump which contains untreated water

This water should not be introduced into the system.

Alternate Testing Proposed These valves will be grouped together and one valve from this g:cuup -~ill

be a.isai'a..lt~Ifil.Jl~d

and inspectiad every reactor. refueling.'.' ...*

A different valve will be disassembled every reactor re!ueling.

This test frequency is in accordance with Generic Letter 89-04, Position.2 .

S2PVI3RO 4-13 Revision o Noveinber 10, 1993

RELIEF REQUEST V-21

Replaced by Reactor Refueling Justification RRV-2 RELIEF REQUEST V-22 Replaced by Cold Shutdown Justification CSV-17 RELIEF REQUEST V-23 Replaced by Cold Shutdown Justification CSV-25 RELIEF REQUEST V-24 Replaced by Cold Shutdown Justification CSV-18 RELIEF REQUEST V-25 Relief Request Withdrawn

S2PVI3RO 4-14 Rev~~ion o November 10, 1993

RELIEF REQUEST V-26

System Valve(s):

Safety Injection 2-SI-107 2-SI-128 2-SI-145 2-SI-109 2-SI-130 2-SI-147 Category: C Class 1 Function: Accumulator Discharge Check OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.4(a) - This section states in part that, "The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its function, as specified in para. 1.1, or both. Observation may be by observing a direct indicator such as a position indicating device, or by other indicator(s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means." This section implies that the techniques used to verify obturator movement be applied to every valve on a test frequency that is practical.

Basis For Request Non-intrusive techniques are used to verify obturator movement for the SI accumulator discharge check valves. These techniques provide a "positive means" for verifying obturator movement, however, due to the burden of applying these techniques in the field, a sampling program will be used as described below.

Alternate Testing Proposed During the first refueling outage where non-intrusive techniques are used, all valves in the group will be tested to verify that the techniques verify valve obturator movement. During subsequent refueling outages, flow testing will be performed on all valves in the group, but the non-intrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified. In this case, all valves in the group will be subjected to the non-intrusive techniques. The test frequency is in accordance with Generic Letter 89-04, Position 2 *

S2PVI3RO 4-15 Revision o Novelilber 10, 1993

RELIEF REQUEST V-26 (Cont.)

Valves 2-SI-130 and 147 are in one group and valves 2-SI-107, 109, 128 and 145 are in the other group. Because 2-SI-130 and 147 are downstream from where RHR connects to the SI line, they experience different service conditions than the other valves.

The justification for testing these valves during reactor refuelings was moved to Reactor Refueling Justification RRV-3

S2PVIJRO 4-16 Revision O November 10, 1993

RELIEF REQUEST V-27

System Valve(s):

.. Safety Injection 2-SI-88 2-SI-91 2-SI-238 2-SI-239 2-SI-94 2-SI-240 Category: C Class 1 Function: Safety Injection to RCS Hot Legs Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.2 - Each check valve shall be exercised.

Basis For Request Individual valve closure cannot be verified for valves 2-SI-88, 91, 94, 238, 239 and 240. There are no drains between the valve pairs 2-SI-88 and 2-SI-238, 2-SI-91 and 2-SI-239, and 2-SI-94 and 2-SI-240

Alternate Testing Proposed A leakage test will be performed on each of the three pairs of valves and the leakage of each pair will be compared to a limit.

If* i:.;he' 1*eaka.ge: liDtit,* is exceeded, Luth valves* in the pair will be subject to inspection, repair or replacement. Note that there is no specified permissible accident leakage limit for these valves.

Therefore, these valves are Category c *

S2PVI3RO 4-17 Revi.sion o November 10, 1993

RELIEF REQUEST V-28

Replaced by Reactor Refueling Justification RRV-5 RELIEF REQUEST V-29 Replaced by Cold Shutdown Justification CSV-21 RELIEF REQUEST V-30 Relief Request Withdrawn RELIEF REQUEST V-31 Replaced by Cold Shutdown Justification CSV-33 RELIEF REQUEST V-32 Replaced by Cold Shutdown Justification CSV-22

RELIEF REQUEST V-33 Relief Request Withdrawn RELIEF REQUEST V-34 Relief Request Withdrawn RELIEF REQUEST V-35 Replaced by Cold Shutdown Justification CVS-7 RELIEF REQUEST V-36 Replaced by Non-Code Alternative Testing VNC-4

S2PVI3RO 4-18 Revj...sion o November 10, 1993

RELIEF REQUEST V-37

Replaced by Non-Code Alternative Testing VNC-3 RELIEF REQUEST V-38 Relief Request Withdrawn RELIEF REQUEST V-39 Relief Request Withdrawn RELIEF REQUEST V-40 Relief Request Withdrawn

S2PVIJRO 4-19 Revision o November 10, 1993

RELIEF REQUEST V-41

System Valve(s)

FW 2-FW-144 2-FW-148 2-FW-159 2-FW-163 2-FW-174 2-FW-178 Category . C Class .. 3 Function .. Auxiliary Feedwater Pwnp Recirc Line and Pwnp Oil Cooler Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Relief These check valves cannot be partial or full flow tested because instrwnentation is not installed to measure flow or differential pressure. There is no other indirect means to verify full flow for these valves with the current configuration.

These check valves can be disassembled while the plant is operating. To allow for flexibility in planning for refueling

,*/: 01::'.*>* ._,,.:,.::'outagesai1J. *>;i:i*t:.t-11?' m~~t'~tn~'-'i11tf:\hc"* u£** O:iYi'**part:*. 10/*** the -- val ves~"-will-...- ...

be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

Alternate Testing Proposed Valves 2-FW-144, 159, and 174 will be grouped together; valves 2-FW-148, 163, and 178 will be grouped together and one valve from each group will be disassembled and inspected on a reactor ,

refueling frequency. A different valve from each group will be t disassembled for each inspection. If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected. This test frequency is in accordance with Generic Letter 89-04, Position 2 *

S2PVI3RO 4-20 Reviidon O November 10, 1993

RELIEF REQUEST V-42

System Valve(s) :

MS 2-MS-176 2-MS-178 2-MS-182 Category: C Class : 2 Function: Main Steam Header Supply Check Valves To Turbine Driven Auxiliary Feedwater Pump OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used. 01 This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Relief These check valves cannot be back seat tested with flow during normal operation because this test would require the venting of process steam while verifying the closed position. Venting of process steam would endanger the test personnel.

However, these check valves can be isolated and disassembled

-while t:ht! plarrt-*i~ op'=rati:i:ig :,*.*Tu*- allow for' flexibility.- in *** * * * --':*,**

planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected on a reactor refueling frequency. A different valve will be disassembled for each inspection. If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected. This test frequency is in accordance with Generic Letter 89-04, Position 2.

The valves will be full flow tested every three months *

S2PVI3RO 4-21 Revision o Novelilber 10, 1993

RELIEF REQUEST V-43

System Valve(s):

containment Spray 2-CS-104 2-CS-105 2-CS-13 2-CS-24 2-RS-11 2-RS-17 Category: AC (2-CS-13,24 and 2-RS-11,17) and C(2-CS-104,105)

Class : 2 Function: containment Spray Pwnp Discharge Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Relief These check valves cannot be partial or full flow exercised during normal operation because this test would introduce containment spray to containment. These valves cannot be locally exercised during normal operation because they are located inside containment.

These valves are located upstream of the spray nozzles. For valves 2-CS-13 and 24, and 2-RS-11 and 17, the only way to

. ~-": :. : **, **perforw,, u,.test.*(pa.l'i:.ial*,,,,op~:t1***0:&:.~' t::losed)',*'*is'*to ,*install"'ca' blci.:Cik: ,.,,,,,:~{.: 1 flange downstream and locally perform an partial open and close test using air. The small increase in safety gained by performing this test every cold shutdown does not justify the burden of installing the blank flange and locally back seat testing the valves at the increased cold shutdown test frequency.

There are no blank flanges installed downstream for valves 2-cs-104 and 105. Therefore, a back seat test or a partial open test cannot be performed on these valves with the current piping configuration. These valves have no external lever arms. The only means to exercise valves 2-CS-104 and 105 to the open and closed positions is by disassembly *

S2PVI3RO 4-22 Revision o Novelhber 10, 1993

RELIEF REQUEST V-43 (Cont.}

.Valves 2-CS-13 and 24, and 2-RS-11 and 17 do have weight-loaded lever arms, however, the weight position and lever arm angle are subject to adjustment to ensure that the valves open when a pressure differential using air is applied every 18 months as required by T. s. 4.5.C. Therefore, torque measurements would not be repeatable.

Alternate Testing Proposed For testing to the open and closed positions, valves 2-CS-104 and 105 will be grouped together and one valve from the group will be disassembled and inspected every reactor refueling. A different valve will be disassembled every reactor refueling. A partial open test cannot be performed on valves 2-cs-104 and 105 with the current piping configuration. This test frequency is in accordance with Generic Letter 89-04, Position 2.

For testing to the full open position; valves 2-cs-13 and 24 will be grouped together; and valves 2-RS-11 and 17 will be grouped together and one valve from each group will be disassembled and inspected every reactor refueling. A different valve from each group will be disassembled every reactor refueling. This test frequency is in accordance with Generic Letter 89-04, Position 2 *

Technical Specifications Paragraph 4.5.C. requires verification that valves 2-CS-13 and 24, and 2-RS-11 and 17 open when the discharge line of the pump is*pressurized with air and seat when a vacuum is applied. This test partially strokes the valves open. Valves 2-CS-13 and 24, and 2-RS-11 and 17 are containment i::!lolc:1c.iOii "ValVeS"" and'i are~* b:l~"Cad*~-t,:r'" the "i;:lOSed* posi*tion"' each ./:i~;, "'"i':;f:;.,;,r,:jj,.

1 refueling outage as part of the Appendix J leak testing program *

S2PVI3RO 4-23

. Revision O Novelilber 10, 1993

RELIEF REQUEST V-44

Replaced by Reactor Refueling Justification RRV-6 RELIEF REQUEST V-45 Replaced by Reactor Refueling Justification RRV-7

S2PVI3RO 4-24 Revi~ion O November 10, 1993

RELIEF REQUEST V-46

System Valve(s):

Service Water 2-SW-247 2-SW-249 2-SW-251 2-SW-253 category: c Class : 3 Function: Recirculation Spray Heat Exchanger Service Water supply Vent Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Relief These check valves must open to provide an effective vent path to ensure that the service water headers are filled and flow through the recirculation spray heat exchangers is quickly established.

There is no instrumentation to measure flow or differentail pressure across the valves. The valves are inaccessible and cannot be manually manipulated without disassembly. The valves

* -'- :...,:,.,_

carr be'* pa:c:-~ial :-sLr"'k:ed*-- opeir*unly**-wherf*s~rvice water,.. fs<sent *- * *"' ,\:,,,,

0 through the recirculation spray heat exchangers. The recirculation spray heat exchangers are maintained dry to avoid fouling. With the current piping configuration, there is no means to partial stroke test these valves without fouling the heat exchangers.

These check valves can be disassembled while the plant is operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected on a reactor refueling frequency. A different valve will be disassembled for each inspection. If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected *

S2PVI3RO 4-25 Revi_sion o November 10, 1993

RELIEF REQUEST V-47

System Valve(s):

Category:

Various Valves affected by this relief request are identified by Table V-47.

Class Function:

OM Part 10 Code Requirements For Wnich Relief Is Requested Paragraph 1.3, definition of full-stroke time - the time interval from initiation of the actuating signal to the indication of the end of the operating stroke.

Paragraph 4.2.1.9(b) which states in part that "Valves with measured stroke times which do not meet the acceptance criteria of para. 4.2.1.8 shall be immediately retested or declared inoperable." Paragraph 4.2.1.8 presents acceptance criteria of

+25% for power-operated valves with reference stroke times greater than 10 seconds (4.2.1.S(b)) and +/-50% for power-operated valves with reference stroke -times less than or equal to 10 seconds (4.2.1.S(d)).

Basis For Relief The valves listed in Table V-47 either have no remote indication

,,>' .* . :a*.,. ** ', and**nO' remote** cont.cul',' ;*Cii:.' 'no*--r~mut:e **upt:::11/wluli:ie **cus1t:i:*ol',**' or: the'** *.:*L, '..-

test requires that the power source be interrupted at the valve and not at the switch. Also, these valves typically exhibit stroke time data scatter from test to test that can exceed the 25% and 50% required by Paragraphs 4.2.1.S(b) and (d).

Therefore, timing the full-stroke from the initiation of the actuating signal and applying the acceptance criteria of Paragraphs 4.2.1.S(b) and (d) are not practical.

Valve 2-cc-Lcv-201 maintains the water level in the seal cooling water tank for component cooling to charging pump cooling system.

This valve has no remote indication or manual position switch.

The valve is exercised by manipulating the tank level signal and isolating the power source, and timed by locally observing stem movement. Differences in interpreting when the valve stem starts and stops will affect the repeatability of the stroke time measurements.

The position of valves 2-MS-RV-201A, Band C is controlled by a potentiometer. Although the valves have remote position

S2PVI3RO 4-26 ReviJ;ion o November 10, 1993

RELIEF REQUEST V-47 (Cont.)

indication, there is no open/closed switch. The speed at which the valve goes open or closed depends upon the speed at which the operator turns the potentiometer knob, which in turn affects the repeatability of the stroke time measurements.

Valves 2-RH-FCV-2605 and 2-RH-HCV-2758 are controlled by a potentiometer and have no remote indication. The stroke time is measured by locally observing stem movement. Differences in interpreting when the valve stem starts and stops affect the repeatability of the stroke time measurements.

Valves 2-SW-TCV-208A, Band C control the flow -of service water to the charging pump lube oil coolers. There is no remote indication or manual position switch. Valve position is controlled by lube oil temperature. The valves are locally manipulated by isolating the power source, and timed by observing stem movement. Differences in interpreting when the valve stem starts and stops affect the repeatability of the stroke time measurements.

Alternate Testing Proposed The full-stroke will be measured by locally observing stem movement and not from the initiation of the actuating signal

Also, maximum stroke times will be established in accordance with Paragraph 4.2.l.9(a). However, the ranges described in Paragraphs 4.2.1.S(b) and (d) will not be applied *

S2PVI3RO 4-27

Rev~sion o November 10, 1993

RELIEF REQUEST V-47 (Cont.)

Valve Category TABLE V-47 Class Function 2-CC-LCV-201 B 3 Charging Pump Seal Cooling Surge TanJc Level Control 2-MS-RV-201A,B,C B 2 Main steam Header Discharge to Atmosphere PORV 2-RH-FCV-2605 B 2 RHR Heat Exchanger Bypass Flow control Valve 2-RH-HCV-2758 B 2 RHR Heat Exchanger Discharge Flow Control Valve 2-SW-TCV-208A,B,C B 3 Service Water to Charging Pump Lube Oil Cooler Temperature Control Valves

S2PVI3RO 4-28 Revision O Noveinber 10, 1993

INTERIM RELIEF REQUEST V-48

Replaced by Cold Shutdown Justification CVS-32 RELIEF REQUEST V-49 Relief Request Withdrawn

S2PVI3RO 4-29 Revision o Nov~mber 10, 1993

RELIEF REQUEST V-50

System Valve(s):

Service Water 2-SW-108 2-SW-113 2-SW-130 2-SW-442 2-SW-445 category: c Class 3 (2-SW-108,113,442,445)

NC (2-SW-130)

Function: Charging Pump Service Water Pump discharge Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Request

The design basis for the charging pump service water system is currently undergoing reevaluation. A full flow acceptance criteria will not be avaliable until this reevaluation is complete .

. . . .*.,-, These' chedk-* val V{;::J ca:a *b~ .. ui~~:;i:jf:ifuilil<ilu* wilile the plant ***is * **. i""'.*"" 1 operating. To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages.

Alternate Testing Proposed These valves will be placed into two groups and one valve from each group will be disassembled and inspected on a reactor refueling frequency. A different valve will be disassembled for each inspection. Valves 2-SW-108, 113 and 130 will be in one group, and valves 1-SW-442 and 445 will be in the other group.

If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected. The check valves will be partial stroke tested every three months. This test frequency is in accordance with Generic Letter 89-04, Position 2 *

S2PVI3RO 4-30 Revision o November 10, 1993

RELIEF REQUEST V-51 system Various Valve(s): All Containment Isolation Valves Subject to Appendix J Testing - These valves are identified by the abbreviation "CIV" under the Isolation Valve Type Column in the Valve Table.

category: A and AC Class ..

Function: Provide Containment Isolation OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.3(f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.

Basis For Request

Permissible valve leakage rates are based on each valve's possible contribution to the total leakage rate for the containment system. The total containment leakage rate must be less than 0.6La as defined in Technical Specification 4.4.C.

Exceeding an individual valve's permissible leakage rate may have no affect on the containment's ability to maintain an overall leakage rate less than 0.6LA.

Also, there may be plant conditions, or schedule constraints, that preclude repair or replacement of a valve when the individual leakage limit is exceeded, but the overall leakage limits for the Type c-tested valves is met. In these cases, imposing the Code requirements of repair or replacement would create an undue burden with no compensating benefit to quality and safety when the bases for leakage limits is met for the overall limit necessary to ensure containment integrity.

Alternate Testing Proposed In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall containment leakage rate will be maintained below 0.6La until the next Type C tests. No repair or replacement is necessary if the evaluation is performed. However, when the plant conditions are

S2PVI3RO 4-31 Revision o November 10, 1993

RELIEF REQUEST V-51 (Cont.)

not such that a repair or replacement would adversely impact plant startup and/or continued operations, an evaluation is not appropriate *

S2PVI3RO 4-32 Revision o November 10, 1993

VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS

OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during Cold Shutdown (but not more frequently than every three months) if the valves cannot be exercised during normal operation.

Therefore, no request for relief from testing every three months is necessary.

However, OM Part 10, Section 6.2 does require that these valves be specifically identified by the owner.

The cold shutdown justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation *

S2PVI3RO 4-33 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-1

System Valve(s):

Main Steam 2-MS-TV-201A 2-MS-TV-201B 2-MS-TV-201C Category: B Class 2 Function: Main Steam Line Trip Valves Cold Shutdown Justification Full stroke or part stroke exercising of these valves during power operation could result in a turbine and reactor trip.

Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months.

Note: The technical specification acceptance criteria are more limiting than the standard Section XI test criteria because the technical specification requires the measurement of elapsed time from the manual initiation of steam line isolation to initiation of main trip valve motion (must be less than or equal to 4.0 seconds) and the measurement of elapsed time from full open to full closed (must be less than vi.'* equal*to* 5.0 *secoHds). If either of the limiting times are exceeded, the valve fails the test.

Section XI requires the measurement of elapsed time from initiation of steam line isolation to full valve closure, which is a less conservative test *

S2PVI3RO 4-34 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-2

Replaced by Interim Relief Request V-48 COLD SHUTDOWN JUSTIFICATION CSV-3 Cold Shutdown Justification Withdrawn

S2PVI3RO 4-35 Rev~sion O November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-4

System Valve(s):

Auxiliary Feedwater Valves affected by this justification are identified by Table CSV-4.

category:

Class Function:

Cold Shutdown Justification Except for valves 2-FW-142, 157 and 172, partial or full opening the valves in Table CSV-4 during power operation would introduce cold auxiliary feedwater to the steam generators resulting in thermal stress and possible steam generator tube degradation.

Valves 2-FW-142, 157 and 172 can be full stroke tested every three months.

To test valves 2-FW-142, 157 and 172 to the closed position, flow must be established to the steam generators in order to back seat the valves on the discharge side of the non-running pumps. This test would also introduce cold auxiliary feedwater to the steam generators if performed during normal operatione Testing Frequency Except for valves 2-FW-142, 157 and 172, the valves in Table csv-4 will be full stroke exercised every coldshutdownbuc not more frequently than once every three months. Valves 2-FW-142, 157 and 172 will be full stroke tested once every three months and tested in the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-36 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-4 (Cont.)

TABLE CSV-4 Valve Category Class Function 2-FW-27 C 2 Auxiliary Feedwater Header 2-FW-58 Check at Main Feedwater 2-FW-89 Header Valves 2-FW-131 C 2 Auxiliary Feedwater Header 2-FW-133 Check Valves at 2-FW-136 Containment Penetration 2-FW-138 2-FW-142 c 3 Auxiliary Feedwater Pump 2-FW-157 Discharge Check Valves 2-FW-172 2-FW-272 C 2 Check Valves at 2-FW-273 Containment Penetration (Cross-connect for Unit 1 Aux. Feed. from Unit 2) 2-FW-305 C 2 Check Valves at 2-FW-306 Containment Penetration (Cross-Connect for Unit 1 Aux. Feed. from Unit 2)

S2PVI3RO 4-37 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-5

*system Valve(s):

. component Cooling Valves affected by this justification are identified by Table csv-s Category:

Class .

Function:

Cold Shutdown Justification These 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 are necessary to test these valves to either the open or closed position. This is considered impractical during power operation.

Testing Frequency The valves in Table csv-s will be tested in the closed position every cold shutdown but not more frequently than once every three months. Valves 2-CC-176 and 177 will be full stroke exercised every cold shutdown but not more frequently than once every three months.

TABLE CSV-5 Valve *Category Class Function 2-CC-176 C 3 Component Cooling to RHR 2-CC-177 Heat Exchanger Check Valves 2-CC-242 C 3 Component Cooling to 2-CC-233 Reactor containment Air 2-CC-224 Recirculation Coolers

S2PVI3RO 4-38

'Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-6

system Valve(s):

.. Component Cooling Valves affected by this justification are identified by Table CSV-6.

Category:

Class ..

Function:

Cold Shutdown Justification To perform an operability or a fail-safe test, the component cooling lines must be isolated, thereby stopping the flow of cooling water to the Reactor Coolant Pumps. Loss of cooling water to these pumps can be damaging, even for short periods of time.

Testing Frequency The valves in Table CSV-6 will be tested in the closed position every cold shutdown when the reactor coolant pumps are secured but not more frequently than once every three months

TABLE CSV-6 Valve Category Class Function 2-cc-1 C 3 Component Cooling to 2-CC-58 Reactor Coolant Pumps 2-CC-59 2-CC-TV-205A B 3 Component Cooling from 2-CC-TV-205B Reactor Coolant Pumps 2-CC-TV-205C

S2PVI3RO 4-39 Revision O November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-7

system Valve(s):

Reactor Coolant 2-RC-PCV-2456 2-RC-PCV-2455C category: BC Class 1 Function: Pressurizer Power Operated Relief Valves Cold Shutdown Justification These pressurizer power operated relief valves have shown a high probability of sticking open while being exercised during power operation. Also, these valves are not required for overpressure protection unless the primary system temperature is under 350 °F per Technical Specification Paragraph 3.1.G.1.b(3).

Testing Frequency These valves will be tested on approach to Cold Shutdown and testing shall not be deferred *

S2PVI3RO 4-40

Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-8

system Valve(s):

Residual Heat Removal 2-RH-5 2-RH-11 2-RH-47 category: c Class 1 (2-RH-47), 2 (2-RH-5 and 11)

Function: RHR Pump Discharge Check Valve Cold Shutdown Justification These valves can only be partial or full stroke exercised to the open position and verified closed during the testing of RHR pumps 2-RH-P-lA and lB (refer to Relief Request P-7). The low pressure pumps take suction from and discharge to the reactor coolant system which operates at 2235 psig. This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible.

Testing Frequency

These valves will be tested to the full open position and the closed position d~ing the testing of the RHR pumps (refer to Relief Request P-7) *

S2PVI3RO 4-41 Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-9

System ..

Valve(s):

Residual Heat Removal 2-RH-MOV-2700 2-RH-MOV-2701 Category: B Class : 1 Function: RHR Suction form Reactor Coolant System Cold Shutdown Justification These valves are interlocked with Reactor Coolant System pressure such that the valves cannot be opened at elevated reactor coolant system pressure. Overpressurization of the suction line may cause a LOCA. The interlocks cannot be bypassed with normal control circuitsQ Testing Frequency These valves will be tested to the full open position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-42 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION csv-10

--system Valve(s):

Residual Heat Removal 2-RH-MOV-2720A 2-RH-MOV-2720B Category: B Class : 1 Function: RHR Discharge to Reactor Coolant System Cold Shutdown Justification With the MOV shut and if its respective check valve is leaking, there is no way to determine whether or not an overpressure condition exists before opening the MOV.

If the MOV was opened and an overpressure condition did exist between the MOV and the RCS, the primary pressure of 2235 psig will be released on the Residual Heat Removal System with a relief valve setting of 600 psig. This would be an unnecessary challenge to the Residual Heat Removal System.

Since the MOV is also part of the discharge piping of an accumulator, there is a possibility of discharging an accumulator into the RHR system and disabling it. The accumulators are maintained at pressure above the normal operating or shutdown pressure of the Residual Heat Removal System. Opening of these valves would dump accumulator water into the Residual Heat Re:anoval ::,y~teJ.G.

This wi11* dilute the boron concentration oi: ,the**-

accumulator as well as lower its level and pressure, which is a violation of Technical Specifications.

Testing Frequency These valves will be tested to the full open position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-43 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION csv-11

System Valve(s):

Chemical and Volume Control 2-CH-LCV-2115C 2-CH-LCV-2115E Category: B Class 2 Function: Charging Pump Suction from Volume Control Tanks Cold Shutdown Justification Partial or full stroke exercising these valves 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 Reactor Coolant System boron inventory, which would cause a plant transient.

Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-44 Revision o November 10, 1993

l COLD SHUTDOWN JUSTIFICATION CSV-12

Cold Shutdown Justification Withdrawn

S2PVIJRO 4-45 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-13

*system Valve(s):

Chemical and Volume Control 2-CH-MOV-2381 Category: A Class : 2 Function: Reactor Coolant Pump Seal Water Return Cold Shutdown Justification:

Closure of this valve with Reactor Coolant Pumps in operation will cause a loss of seal flow resulting in possible pump seal damage.

Testing Frequency This valve will be tested to the closed position every cold shutdown when the reactor coolant pumps are secured but not more frequently than once every three months *

S2PVIJRO 4-46 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-14

System Valve(s):

Residual Heat Removal 2-RH-FCV-2605 2-RH-HCV-2758 Category: B Class 2 Function: Residual Heat Removal Exchanger flow control Cold Shutdown Justification These valves have no remote position indication and are located inside containment. The valves can only be exercised (partial or full stroke) and timed by locally observing stem movement.

Because a containment entry is required to perform the exercise and fail-safe tests, it will be conducted every cold shutdown.

Testing Frequency Valve 2-RH-FCV-2605 will be tested to the closed position, and valve 2-RH-HCV-2758 will be tested to the full open position every cold shutdown but not more frequently than once every three months .

S2PVI3RO 4-47 Revi_sion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-15

System Valve(s):

Chemical and Volume Control 2-CH-TV-2204A 2-CH-TV-2204B 2-CH-LCV-2460A 2-CH-LCV-2460B category: A (2-CH-TV-2204A, B) and B (2-CH-LCV-2460A, B)

Class 1 (2-CH-LCV-2460A, B) and 2 (2-CH-TV-2204A, B)

Function: Reactor Coolant System Letdown Isolation Trip and Level Control Valves Cold Shutdown Justification Exercising these valves during power operation interrupts letdown flow from the reactor coolant system (RCS) to the volume control tank. If the valves should fail closed, reactor coolant inventory control would be lost.

The pressurizer level control program controls reactor coolant inventory 'by regulating the operation of the charging flow control val_ve so that the charging input flow to the RCS and reactor coolant pump seal injection flow into the RCS matches letdown flow

Also, exercising these valves during normal operation will interrupt letdown flow through the regenerative heat exchanger.

This flow interruption would allow a slug of relatively cool charging water to thermal shock the nozzle connecting the 3" charging line to the 27 11 loop 2 cold leg injection line.

The valve controllers do not allow for a part stroke exercise test.

Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-48 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-16

system Valve(s):

Chemical and Volume Control 2-CH-MOV-2289A 2-CH-MOV-2289B

category: A (2-CH-MOV-2289A) and B (2-CH-MOV-2289B)

Class : 2 Function: Normal Charging Header Isolation Cold Shutdown Justification Failure of these valves in the closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory.

Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-49 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-17

*system Valve(s):

Safety Injection 2-SI-MOV-2890C Category: A Class . 2 Function: Low Head Safety Injection to Reactor Coolant System Cold Legs Cold Shutdown Justification In accordance with Technical Specification 3.3.A.8, during power operation, the A.C. power shall be removed from 2-SI-MOV-2890C with the valve in the open position. If this valve was stroked during power operation and failed in the closed position, the Low Head Safety Injection System would be rendered inoperable.

Testing Frequency This valve will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-50 Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-18

System Valve(s):

. Safety Injection 2-SI-MOV-2867C 2-SI-MOV-28670 Category: A Class : 2 Function: High Head Safety Injection Isolation Cold Shutdown Justification These valves cannot be partial or full stroke exercised during power operation. Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient.

Testing Frequency These valves will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months *

S2PVIJRO 4-51 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-19

system Valve(s):

Chemical and Volume Control 2-CH-225 2-CH-227 2-CH-228 2-CH-229 2-CH-MOV-2350 Category: B (2-CH-MOV-2350, 2-CH-228) and C (2-CH-225,227,229)

Class 2 Function: Emergency and Manual Emergency Boration Line Isolation Valves Cold Shutdown Justification To achieve full flow through Check valves 2-CH-225, 227 and 229, the boric acid transfer pumps must be set at high speed, which could inject enough boric acid into the reactor coolant system to cause a reactor power transient. Under normal plant operating conditions or when the plant is shutdown, valve 2-CH-MOV-2350 can be full stroke exercised and valves 2-CH-225, 227 and 229 can be part stroked exercised with the boric acid transfer pumps set on low speed to minimize the amount of boric acid injected into the reactor coolant system. However, during power operation when the concentration of boric acid in the reactor coolant system is low, the addition of boric acid will produce an undesirable transient in reactor power. Low concentrations of boric acid occur near the end of the fuel cycle.

Testing Frequency Valve 2-CH-MOV-2350 will be full stroke exercised and check valves 2-CH-225, 227 and 229 will be full stroked exercised every quarter during normal operation when the reactor coolant boric acid concentration is above 100 ppm.

Manual valve 2-CH-228 will be stroked open when the other valves in the alternate boration path are exercised. The increased level of safety gained be exercising this valve every quarter does not justify the added burden of performing a separate test just for the manual valve .

S2PVI3RO 4-52 Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-20

Replaced by Reactor Refueling Justification RRV-6

S2PVI3RO 4-53 Revision O November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-21

System Valve(s):

Steam Generator Blowdown 2-BD-TV-200A 2-BD-TV-200B 2-BD-TV-200D 2-BD-TV-200E 2-BD-TV-200C 2-BD-TV-200F Category: B Class : 2 Function: Steam Generator Blowdown Isolation Cold Shutdown Justification Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves reopen, a flow surge could occur 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.

T~sting Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-54 Revi.sion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-22

Cold Shutdown Justification Withdrawn COLD SHUTDOWN JUSTIFICATION CSV-23 Replaced by Relief Request V-43 COLD SHUTDOWN JUSTIFICATION CSV-24 Cold Shutdown Justification Withdrawn

S2PVI3RO 4-55 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-25

System Valve(s):

Safety Injection 2-SI-MOV-2842 2-SI-MOV-2869A 2-SI-MOV-2869B

~t~ocy: A Class : 2 Function: High Head Safety Injection to reactor Coolant system Cold Shutdown Justification These valves cannot be partial or full stroke exercised during power operation. Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient and possible thermal shock to the High Head Safety Injection System.

Also, according to Technical Specification 3.3.A.9, A. c. power shall be removed with the valves in the closed position during power operation.

Testing Frequency These valves will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months .

S2PVI3RO 4-56 Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-26

system Valve(s):

.. Component Cooling 2-CC-181 2-CC-185 category: B (manual)

Class . 3 Function: Component Cooling Supply/Return to/from RHR Heat Exchanger Isolation Valves Cold Shutdown Justification A containment entry is required to exercise these manual butterfly valves. Therefore, they will be exercised every cold shutdown.

Testing Frequency These valves will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-57 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-27

System Valve(s):

Component Cooling 2-CC-TV-220A 2-CC-TV-220B 2-CC-TV-240A 2-CC-TV-240B 2-CC-TV-220C category: B Class : 3 Function: Component Cooling Return from Reactor Coolant Pump Thermal Barrier Isolation Valves Cold Shutdown Justification Exercising these valves during normal operation would isolate component cooling water to the reactor coolant pump thermal barriers" Cooling water must be available to the reactor coolant pump thermal barriers when the reactor coolant system temperature is above 200 °F. Cold shutdown is entered when the reactor coolant system temperature drops below 200 °F. The valve controllers do not allow for a part stroke exercise test.

Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months .

S2PVI3RO 4-58 Rev.j..sion O November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-28

*system Valve(s):

Feedwater 2-FW-FCV-2478 2-FW-FCV-2488 2-FW-FCV-255A 2-FW-FCV-255B 2-FW-FCV-2498 2-FW-FCV-255C Category: B Class : NC Function: Main Feedwater Regulating and Regulating Bypass Isolation Valves Cold Shutdown Justification These valves are in positions required to sustain power operation. Full stroke exercising the valves would result in a reactor trip. The main feedwater regulating valves 2-FW-FCV-2478i 2488 and 2498 move during normal operation as they perform their regulating function.

The bypass valves 2-FW-FCV-255A, Band Care used only during plant startup. During this startup period, their safety function is to close. During normal operation, these valves remain closed and, thus are passive in the closed position. Therefore, the bypass valves do not need to be partial stroke tested every three months.

Testi:ng,Freguency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months. The main feedwater regulating valves will be part stroke exercised every three months during the turbine inlet valve movement test *

S2PVI3RO 4-59 Rev~ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-29

System Valve(s):

Safety Injection 2-SI-109 2-SI-130 2-SI-147 Category: c Class 1 Function: SI Accumulator Discharge Isolation Check Valve Cold Shutdown Justif,ication These check valves are located inside containment and are back seat tested using the installed sampling system. To ensure that all of the leakage that could pass by the check valves is collected, the accumulator discharge motor operated valves (2-SI-MOV-2865A, Band C) must be closed. However, these motor operated valves must be apen and de-energized when the reactor coolant system pressure is above 1000 psig according to Technical Specification Paragraph 3.3.A.10.

Testing Frequency The accumulator check valves will be tested to the closed position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-60 Revision o November 10, 1993

COLO SHUTDOWN JUSTIFICATION CSV-30

**,,c,system Valve(s):

Category:

Component Cooling 2-cc-aos C

Class : 3 Function: Charging Pump Seal Cooling Surge TanJc Makeup Valve Cold Shutdown Justification This valve must open to provide a flow path from the component cooling water system to the charging pump seal water surge tank as a supply of makeup water to the surge tanJc. There is no flow instrumentation to verify partial or full flow for the check valve.

There is level instrumentation on the surge tanJc *. The surge tanJc can be isolated, drained down and refilled. However, the surge tanJc provides the NPSH for the charging pump cooling water pumps and it should not be isolated from the system during normal operation when component cooling water for the charging pumps is required

Testing Frequency This valve will be tested to the full open position every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-61 ReviJ;ion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-31

*system Valve(s):

Component Cooling 2-CC-LCV-201 Category: B Class : 3 Function: Charging Pump Seal Cooling Surge Tank Level Control Valve Cold Shutdown Justification This valve must open to maintain the level in the charging pump seal water surge tank and must close to prevent overflowing the surge tank and potentially draining the surge tank through the over flow line. The valve fails closed on lose of operating air.

Valve position is determined solely from tank level. In order to manipulate the valve for testing, the surge tank must be isolated. However, the surge tank provides the NPSH for the charging pump cooling water pumps and it should not be isolated from the system during normal operation when component cooling water for the charging pumps is required

Testing Frequency This valve will be exercise to the open and closed positions every cold shutdown but not more frequently than once every three months *

S2PVI3RO 4-62 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-32

System Valve(s):

.. Main Steam 2-MS-NRV-201A 2-MS-NRV-201B 2-MS-NRV-201C Category: C Class : 2 Function: Main Steam Non-Return Valves Cold Shutdown Justification Valve Description The main steam non-return valves (NRVs) at Surry Power Station are located in the main steam valve house and are a globe type stop check designo The valves measure approximately 16 feet from the bottom of the valve body to the top of the hand wheel and weigh almost 18,000 lbs. The disk is welded to a hollow piston and the whole assembly is free to move about 25 vertical inches within the valve body cylinder. The disk measures 25.5 inches across and the disk and piston assembly weighs approximately 1,200 lbs. When the main steam system is not inservice, a motor operator is used to run the valve stem down onto the disk to secure the main steam line.

The valves open to allow steam to the turbine. For accident

conditians, the* nun-retu:t'd valves*"in conjunction with*. the *main * ,_., **

steam trip valves prevent the blowdown of more than one steam generator for any break location, even if one valve fails to close. For example, for a break upstream of the trip valve in one line, the closure of either the non-return valve in that line or the trip valves in the other lines prevents the blowdown of the other steam generators.

Method of Testing The piping downstream of each non-return valve leads to a common distribution manifold and cannot be isolated. Therefore, performing a back seat test using flow is not practical. Also, valve disassembly and inspection are not practical alternatives due to the size of the valve and the weight of the disk *

S2PVI3RO 4-63

- . Rev~_sion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-32 (Cont.)

However, an alternative exists to verify that the disk moved to the valve seat during reactor coolant system (RCS) cooldown.

When the RCS temperature is between 350 °F and 195 °F during the cooldown process, the main steam trip valves are closed. Then the main steam non-return valves close in response to the loss of steam flow.

After the main steam trip valve is closed, the Valve Operation Test and Evaluation System (VOTES) can be used to determine the position of the disk of the NRV. After the main steam trip valve is closed, the non-return valve stem is run down onto the disk after the disk returns to the seat. A change in the running force within the normal travel of the stem indicates a resistance to stem movement (i.e., a stuck disk). Verifying that the stem travels to the seated disk with nominal changes in the running force indicates that the disk is on the seat. The test requires that the cooldown process be delayed between one to two hours to setup the instrumentation and to perform the test on each of three valves" Virginia Power owns the VOTES equipment and has personnel trained* to use the equipment and interpret the results.

The VOTES consists of a force sensor permanently mounted on the valve yoke, valve switch current probes and a motor current probe. The force sensor detects the strain experienced by the yoke as the valve stem moves. Strain is converted to force. The valve switch probes determine the status of the torque and limit switches, and the open and closed bypass switches in the motor operator control circuit over the course of stem travel. To attach the switch and motor current probes, the power to the valve must*be intei:-:rupted.

Testing Frequency Discussion Full stroke or *part stroke exercising of these valves during power operation would result in a turbine and reactor trip.

Plant cooldown procedures require the trip valve to be closed, and then the NRV stem run down onto the disk to isolate the main steam system. The VOTES testing must be performed when the NRVs are initially closed during the cooldown to accurately assess the piston-disk assembly's as-found position. As indicated above, the VOTES test will delay the cooldown process from between one to two hours. Some cold shutdown outages are forced outages that result from exceeding a Technical Specification limit such as unidentified RCS leakage. The emphasis in a forced outage cooldown is to reach cold shutdown as rapidly as possible and to mitigate the cause of the forced outage. Stopping this process to perform the VOTES test would complicate the operators task to

S2PVI3RO 4-64 Revi_sion o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-32 (Cont.)

secure the plant and may reduce plant safety. However, during planned cold shutdowns where there are no mitigating circumstances, there is adequate time to notify the test personnel, carry the equipment into the field and perform the test.

There is no evidence in the valve history that a valve has stuck in the partial open position. The piston-disk assembly is not attached to any other internal part, the 1,200 lb piston-disk assembly is maintained parallel within the valve body cylinder and the main steam system is very clean. Consequently, there no mechanism to prevent the disk from dropping from the full open position to the valve seat.

Testing Frequency The VOTES test described above will be performed on each main steam non-return valve during the cooldown process going into each planned cold shutdowne This test will not be performed more often then once every three months *

S2PVI3RO 4-65 Revision o November 10, 1993

COLD SHUTDOWN JUSTIFICATION CSV-33

System Valve(s):

Reactor Coolant 2-RC-S0V-200A-l 2-RC-S0V-200A-2 2-RC-S0V-200B-1 2-RC-S0V-200B-2 Category: B Class .. 1 Function: Head Vent for Reactor Vessel Cold Shutdown Justification These valves isolate the reactor vessel from containment atmosphere. Partial or full stroke exercising the valves during normal operation or during cold shutdowns where the reactor coolant system is pressurized could result in the release of uncontrolled contamination to containment.

Testing Frequency This valve will be exercise to the open and closed positions during cold shutdowns when the reactor coolant system is not pressurized but not more frequently than once every three months *

S2PVI3RO 4-66 Revi.:;ion o November 10, 1993

4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS

OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during reactor refueling (but not more frequently than every three months) if the valves cannot be exercised during normal operation or cold shutdown. Therefore, no request for relief from testing every three months is necessary.

However, OM Part 10, Section 6.2 does require that these valves be specifically identified by the owner.

The reactor refueling justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation *

S2PVI3RO 4-67

Rev~ion o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-1

System Valve(s):

Chemical and Volume Control 2-CH-258 2-CH-267 2-CH-276 category: C Class . 2

Function: Charging Pump Discharge Check Valve Reactor Refueling Justification With present plant design, these valves can only be partial stroke exercised during power operation because the charging pumps cannot achieve design accident flow when pumping into the Reactor coolant System at operating pressure. The only available flow path to test these valves is into the reactor coolant system. During cold shutdown, stroke exercising these valves could result in an overpressurization of the Reactor Coolant System and could force a safety system to function.

Testing Frequency These valves will be partially stroked every three months and full flow tested each refueling *

S2PVI3RO 4-68 Revi.:;ion o November 10, 1993

REACTOR REFUELING JUSTIFICATION** RRV-2

system Valve(s):

Safety Injection Valves affected by this request are identified in Table RRV-2.

Category:

Class Function:*

Reactor Refueling Justification These valves cannot be full stroke exercised during plant power operation. The only full flow path is into the Reactor Coolant System and Low Head Safety Injection pumps cannot overcome Reactor Coolant System operating pressure. These valves will be partially stroked every three months through the pump recirculation line. During cold shutdown, the Reactor Coolant System pressure still prevents full flow testing of the check valve. During cold shutdown, the charging flow could cause an overpressurization condition.

Testing valves 2-SI-50 and 327 to the closed position requires isolating the suction lines to the low head safety injection pumps, venting on the upstream side of the valve being tested, starting the pump on the other path, checking for leakage and then repeating the process for the other valve. This test can take up to a hour to complete and places the unit into a LCO per

.reehuical* s~~'-if i1:;cd:io11*3. 3 if pe:cfu:cmed during' normal *.- **-' * -"~***

1 operation.

Testing Frequency These valves will be partially stroked every three months and full stroked every refueling.

Valves 2=SI=50 and 327 will be tested to the closed position every cold shutdown *

S2PVI3RO 4-69 Revj,,sion o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-2 (Cont.)

Valve 2-SI-46A c TABLE RRV-2 category Class 2

Function Low Head Safety Injection 2-SI-46B Pump Suction from Refueling Water Storage Tanlc Check 2-SI-50 C 2 Low Head Safety Injection 2-SI-327 Pump Discharge Check

S2PVI3RO 4-70 Rev.j..sion O November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-3

System Valve(s):

Safety Injection 2-SI-107 2-SI-128 2-SI-145 2-SI-109 2-SI-130 SI-147 Category: c Class : 1 Function: Accumulator Discharge Check Reactor Refueling Justification These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 to 650 psig) is below Reactor Coolant System pressure and the injection of borated water would upset the reactor coolant chemistry. During cold shutdown, the RCS pressure still prevents full flow testing.

To achieve full flow through the valves during reactor refueling, the accumulator would have to be discharged from an initial pressure of 600 psig. Discharging the accumulator from this pressure would stress the piping system and inject nitrogen into the RCS. Nitrogen in the RCS.has been linked to gas binding of the RHR pumps. However, the accumulator can be discharged from a lower pressure during reactor refuelings when the RCS is depressurized. At this pressure, full flow

*

conu.ii:ioni:1 will :not** be* "ei3tablishet..; **however,* eriough flow **wfll' *be**,~

developed to open the check valves to the full open position.

This event can be verified and documented using non-intrusive diagnostic techniques.

Testing Frequency Non-intrusive diagnostic techniques will be used to determine that the check valves open to the full open position. A sampling program will be applied to the non-intrusive techniques as described in Relief Request V-26 *

S2PVI3RO 4-71 Revtsion o Nove:inber 10, 1993

l REACTOR REFUELING JUSTIFICATION RRV-4

system Valve(s):

safety Injection Valves affected by this request are identified in Table RRV-4.

category:

Class Function:

Reactor Refueling Justification Open Test Discussion The valves on the high head injection paths cannot be partial or full stroke exercised to the open position during power operation because flow through these valves would thermal shock the injection system and cause unnecessary plant transients.

Flow cannot be established in the valves on the low head injection paths during power operation because the low head safety injection pumps do not develop sufficient head to overcome reactor coolant system pressure *

During cold shutdown, exercising the high head injection path valves with flow could cause a low temperature overpressurization of the reactor coolant system and force a safety system to function. Because of the large flow rate {3000 gpm) produced by the low head safety injection pumps, exercising.

the* low head inje~cio:irpdi:.il valves*during***cold shutdol.t(ns*--wheri"'******---.

the reactor head is bolted in place presents the risk of filling the pressuizer and overflowing through a pressure operated relief valve into the pressuizer relief tank. Therefore, it is impractical to exercise the high or the low head injection path valves with flow quarterly or during cold shutdowns. The valves listed in Table RRV-4 are on the high and/or the low head injection paths.

Close Test Discussion for 2-SI-79. 82. 85. 241. 242 and 243 To individually verify closure for valves 2-SI-79, 82, as, 241, 242 and 243, the piping must be vented upstream and a backseat test performed. These valves are located inside the containment and would require a subatmospheric containment entry to perform the backseat test if the reactor is above 200°F *

S2PVI3RO 4-72 Revi_sion o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

Therefore, it is impractical to perform a closure test every quarter.

These valves are designated as pressure isolation valves.

Technical Specification Table 4.l-2A requires that periodic leakage testing on each of these valves be accomplished prior to entering power operation condition after each time the plant is placed in the cold shutdown condition for refueling and after each time the plant is placed in cold shutdown condition for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months if testing has not been accomplished in the proceeding 9 months.

According to OM Part 10, Paragraph 4.2.l.2(f), "valves full-stroke exercised at cold shutdowns shall be exercised during each cold shutdown, except as specified in (g) below. Such exercise is not required if the time period since the previous full-stroke exercise is less than 3 months." Paragraph (g) states that "valve exercising during cold shutdown shall commence within 48 hr of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr provided all valves required to be tested during cold shutdown will be tested prior to startup. However, it is not the intent of this Part to keep the plant in cold shutdown to complete cold shutdown testing."

However, if that first cold shutdown came more than nine months after the last test, Technical Specifications would require that the test be completed regardless of the delay to plant statup *.

In* this 1.;*esp+E:,,;_.t, *the Technical°' Specification frequency* is :inore conservative than the IST Program required frequency. Also, a leakage test provides a better measure of the condition of the valve seats than does a standard backseat test. When compared to the Code requirements for a backseat test performed every cold shutdown, the combination of the Technical Specification required test frequency and leakage testing is an alternative that provides an acceptable level of quality and safety *

S2PVIJRO 4-73 Revision o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

Close Test Discussion for 2-SI-88. 91. 94. 238. 239 and 240 Individual valve closure cannot be verified for valves 2-SI-88, 91, 94, 238, 239 and 240. There are no drains between the valve pairs 2-SI-88 and 2-SI-238, 2-SI-91 and 2-SI-239, and 2-SI-94 and 2-SI-240. To verify closure for each pair of valves, a subatmospheric containment entry must be made and a backseat test performed if the reactor is above 200°F. Therefore, it is impractical to perform a closure test every quarter.

A leakage test will be performed on each of the three.pairs of valves * . This test will be performed on the same test frequency as the pressure isolation valves discussed above (i.e., per Technical Specification Table 4.1-2A). Note that there is no specified permissible accident leakage limit for these valves.

Therefore, these valves are Category c. When compared to a backseat test performed every cold shutdown, the combination of the test frequency described in Technical Specification Table 4.1-2A and leakage testing is an alternative that provides an acceptable level of quality and safety.

Close Test Discussion for 2-SI-235. 236 and 237 To verify closure for valves 2-SI-235, 236 and 237, a subatmospheric containment entry must be made and a backseat test performed if the reactor is above 200°F. Therefore, it is impractical to perform a closure test every quarter.

In lieu of performing a backseat test on each of these valves

, ,, *~*-**** --

ev~:cy cold" shutdown~*-* a* leakage* te:st' will be performed *on* each,*,'

valve and the leakage of each valve will be compared to a limit.

This test will be performed on the same test frequency as the pressure isolation valves discussed above (i.e., per Technical Specification Table 4.1-2A). Note that there is no specified permissible accident leakage limit for these valves. Therefore, these valves are Category c. When compared to a backseat test performed every cold shutdown, the combination of the test frequency described in Technical Specification Table 4.1-2A and leakage testing is an alternative that provides an acceptable level of quality and safety .

S2PVI3RO 4-74 Revision O November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

Testing Frequency Testing Frequency To the Open Position There is no installed instrumentation that can measure individual flow rates for valves 2-SI-79, 82, 85, 88, 91, 94, 238, 239, 240, 241, 242 and 243. Clamp on ultrasonic flow instrumentation will be used to verify full flow through the hot leg safety injection valves 2-SI-88, 91, 94, 238, 239 and 240 each reactor refueling.

Using low head pump flow, the cold leg injection valves 2-SI-79, 82, 85, 241, 242 and 243 will be acoustically monitored for the disk striking the back seat every reactor refueling. The data will be analyzed to show that the disk struck the back seat, which verifies that the disk stroked to the full open.position.

The remaining valves 2-SI-224, 225, 226, 227, 228, 229, 235, 236 and 237 will be full stroke exercised with flow every reactor refueling.

Testing Frequency To the Closed Position Valves 2-SI-79, 82, 85, 241, 242 and 243 will be tested to the closed position per the requirements of Technical Specification Table 4.l-2A.

The valve pairs 2-SI-88 and 2-SI-238, and 2-SI-91 and 2-SI-239, and 2-SI-94 and 2-SI-240 will be tested for leakage to confirm that the valve pairs provide isolation for the three hot leg

' ****"' ****'"*\* * * ** i:ttjection-- patJ1~.-*" Ti1t:i *'leakay-e *tebts *will'*be- pei:*formed at*. the,,. * .,,,,;*,* *,

frequency required by Technical Specification Table 4.1-2A.

Individual valve verification to the closed position is not possible with the current line configurations.

Valves 2-SI-235, 236 and 237 will be tested for leakage to confirm that the valves are in the closed position. The leakage tests will be performed at the frequency required by Technical Specification Table 4.1-2A.

The remaining valves 2-SI-224, 225, 226, 227, 228 and 229 need only to open to perform their safety function. No credit is taken for valves 2-SI-224, 225, 226, 227, 228 and 229 to close because isolation for the safety injection flow paths is provided by the upstream and downstream valves. For each of these valves, there are normally closed motor operated valves located upstream and two check valves in series located downstream. The upstream and downstream valves are tested for closure *

S2PVI3RO 4-75 Rev~ion o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

Valve 2-SI-88, 91 2-SI-94, 238 C

TABLE RRV-4 Category Class 1

Function Safety Injection to RCS Hot Legs 2-SI-239, 240 2-SI-235 C 1. High Head Safety Injection 2-SI-236 to RCS Cold Legs 2-SI-237 2-SI-241 AC 1 Low Head*safety Injection 2-SI-242 to RCS Cold Legs 2-SI-243 2-SI-224, 225 C 2 High Head Safety Injection 2-SI-226, 227 Check Valve at Containment Penetrations 2-SI-228, 229 C 2 Low Head Safety Injection Check Valves at Containment Penetrations 2-SI-79, 82, 85 AC 1 Safety Injection to RCS Cold Legs

S2PVI3RO 4-76

Rev.:j.sion o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-5

System Valve(s):

.. RWST Cross Tie 2-SI-25 2-SI-400 category: c Class .. 2 Function: Charging Pump Suction from RWST Cross Tie Reactor Refueling Justification Exercising these valves 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 reactor coolant boron inventory.

Full flow for the charging system can only be established during reactor refueling when the RCS is depressurized.

Valve 2-SI-25 must close to preserve inventory from the Unit 2 RWST when the cross tie lines are opened. There are no vents or pressure instrumentation upstream of the valve; therefore, the valve cannot be backseat tested with flow.

Testing Frequency These valves will partial flow tested during every cold shutdown and full flow tested during every reactor refueling.

Valve 2-SI-25 will be disassembled and inspected every refueling outage to verify closure *

S2PVI3RO 4-77 Revision o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-6

System Valve(s):

Various Valves affected by this justification are identified by Table RRV-6.

category:

Class Function:

Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety functions. The only way to verify closure is to perform a local leak rate/back pressure test. Since the valves are located inside containment, they cannot be tested quarterly.

These valves are containment isolation valves and are subject to leak testing every reactor refueling outage per the requirements of the Appendix J leak testing program and OM Part 10, Paragraphs 4.2.2.3(e) and (f). The leak tests not only verify that the valves close adequately* as does a normal back pressure test, but the tests also reveal the condition of the valve seating surfaces. As required by Paragraph 4.2.2.J(e), the leak tests include acceptance criteria for the maximum allowed leakage.

*

Perfo:i'.uliny *a :ilack s~a.t* te:si:* every* cold *shutdown does not provide enough increase in safety to justify the burden of back seat testing on a more frequent basis.

Testing Frequency Exercise to the closed position every reactor refueling *

S2PVI3RO 4-78 Revision o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-6 (Cont.)

Valve TABLE REACTOR RRV-6 Category Class Function 2-CH-309 AC 2 Normal Charging Isolation 2-IA-864 AC 2 Instrument Air Containment 2-IA-868 Isolation 2-RC-160 AC 2 Primary Grade Water to Pressurizer Relief TanJc 2-RM-3 AC 2 Isolation on Monitor Return Line 2-SI-304 AC 2 Nitrogen Accumulators N2 Supply 2-VP-12 AC 2 Condenser Air Removal Discharge to Containment

.,., ".:* :, *'* . ~***-c., . * ,'?* ., *

S2PVI3RO 4-79

Revision o November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-7

System Valve(s):

Component Cooling 2-CC-94 2-CC-95 2-CC-592 2-CC-555 2-CC-556 2-CC-557 category: c Class 3

. Function: Component Cooling Supply to RCP Thermal Barrier Isolation Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety function to prevent gross leakage. For the following reasons, it is not practical to test the thermal barrier check valves quarterly or at cold shutdown:

1) the valves are inside a locked radiation area located inside containment; therefore, they are not accessible during normal operation,

2) the valves are inaccessible for about 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after cold shutdown due to decontamination activities which must be performed before entry into the area,

3) the reactor cooling pump(s) may be running with the reactor

cool in~, sy~ i.::dut *t.~Mpe:t ~tu:c*a* 'le~sf't:ilaff 2 oo °F *if an** RHR *1oop* is*,., *---*: ,,.._,,

unavailable (in this case the valves and thus cooling to the thermal barriers would normally not be isolated) and

4) the valves have soft seats that are replaced every five years and using pressure to back seat these valves on the more frequent cold shutdown frequency may accelerate the degradation of the soft seats.

These valves will be exercised only during refueling outages because the small increase in safety gained by performing this test every cold shutdown does not justify the burden of performing a local back pressure test *

S2PVI3RO 4-80 Revision o Novsmber 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-7 (Cont.)

Testing Frequency Exercise to the closed position every reactor refueling *

S2PVI3RO 4-81 Revi:_sion O November 10, 1993

REACTOR REFUELING JUSTIFICATION RRV-8

system Valve(s):

Chemical and Volume Control 2-CH-230 Category: C Class . 2 Function: Charging Pump Supply from VCT Discharge Reactor Refueling Justification During normal operation, this valve cannot be isolated to perform a back pressure test because normal letdown and charging flow would be interrupted. Also, if the valve was isolated during normal operation, the charging pumps would have to be secured.

This valve is also subject to leak testing, which is performed every reactor refueling. Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify performing a leak rate test.

Testing Frequency Exercise to the closed position every reactor refueling.

4-82 Revi_sion o S2PVI3RO Nove:inber 10, 1993

4.8 ALTERNATIVE TESTING FOR NON-CODE VALVES

According to the minutes of public meeting on Generic Letter 89-04, "Paragraph (g) of 10CFR so.ssa requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.SSa) do not require a

'request for relief' to be submitted to the staff.

Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3.

Surry Power station has elected to include certain non-Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability. The alternate testing is described in this section. There may be other deviations from Code provisions that are not described

.,, - ,, ..... s.,,. * " -'*' ,.* in* *i;,i:.d.iiil *section*.'~

li'o.c these* uases, ducumentation *is*

available at the plant site.

As indicated in the minutes of public meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components. Therefore, the alternative tests described in this section are not

'requests for relief' but are provided for information *

S2PVI3RO 4-83 Revision o November 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-1

*System Valve(s):

Instrument Air 2-IA-381 2-IA-384 2-IA-396 2-IA-947 2-IA-385 2-IA-948 category: c Class NC Function: Bottled Air System Supply/Isolation Section XI Code Requirements Which Cannot Be Met Exercise valves every three months.

Basis For Alternate Testing Valves 2-IA-381, 384 and 947 must close to ensure that bottled air is available to actuate the main valves (2-RC-PCV-2455C, 2-RC-PCV-2456, and 2-MS-SOV-202A and B). Valves 2-IA-395, 396 and 948 must open to allow bottled air to reach the main valves.

There is no direct means to measure the flow of air through the check valves.

However, after the instrument air system is isolated and the lines vented, the stroke times of the main valves are measured and compared to acceptance criteria. Measuring the stroke times

p:t'OV'ideS' i:;.;.di:i:'t2ct*** t::..rideiiCe'- that: *valves IA-395, 396 and 948 'open, properly and that valves 2-IA-381, 384 and 947 close properly.

The performance of this test renders the main valves inoperable; therefore, the tests cannot be performed during normal operation.

After stroking the main valves with the air bottles, the air bottles must be replaced. The safety gained in testing the valves every cold shutdown versus every reactor refueling does not justify the burden of replacing the air bottles on the more frequent basis *

S2PVI3RO 4-84 Revµdon o November 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-1 (Cont.)

Alternative Testing Valves 2-IA-381, 384 and 947 will be tested closed and valves 2-IA-395, 396 and 948 will be tested open by isolating and venting the instrument air lines, and then stroking the main valves with the bottled air. The stroke times of the main valves will be measured and compared to acceptance criteria. This test will be performed every reactor refueling *

S2PVI3RO 4-85 Revision o November 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-2

Non-Code Alternative Testing Withdrawn

S2PVIJRO 4-86 Revision o November 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-3

system Valve{s):

Emergency Generator 2-EG-43 2-EG-44 2-EG-45 2-EG-46 2-EG-S0V-200A 2-EG-S0V-200B Category: B (2-EG-43,44, 2-EG-SOV-200A and B)

C (2-EG-45,46)

Class : NC Function: 2-EG-43,44 EOG Starting Air/Drive Air Control/Relay Valves 2-EG-45,46 EDG Air Start Pressure Equalizing Check Valves 2-EG-S0V-200A and B Air Start System Solenoid Valves OM Part 10 Code Requirements Which cannot Be Met For valves 2-EG-43,44, and 2-EG-SOV-200A, B, measure stroke time

For valves 2-EG-45,46, measure flow to verify full open Basis For Alternate Testing Valves, 2~EG-43 and 44 ai:-e' aL: pil~t valves that open to supply **

drive air to the EDG air starting motors. These valves along with the air start solenoid valves 2-EG-SOV-200A and B have actuation times considerably under a second and there is no visual reference on the valve to observe the stroke; therefore, the stroke time cannot be measured.

Valves 2-EG-45 and 46 are check valves that close to prevent opening the air start valves before the air motor pinion gears are fully engaged. They open to ensure that the air motor pinions remain*engaged (hold-in feature) when the air motors are operating. The only indication of the proper operation of the

S2PVI3RO 4-87 Rev~sion o Novsinber 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-3 (Cont.)

check valves is the proper operation of the pinion gears. The air pilot valves and the check valves work in concert with the air start solenoid valves to start the emergency diesels upon demand within the required time.

Alternative Testing These valves will be stroke tested quarterly by observing that the valves perform their intended function, which is to start the diesel engines. Adequate performance of the valves will be verified by recording the time it takes for the diesel engines to reach a predetermined RPM and comparing the time to an acceptance criterion.

Also, the failure of these valves to perform will promptly give a diesel engine trouble alarm. Further investigation would identify problems with the operability of these valves *

~

S2PVI3RO 4-88 Revision o Noveblber 10, 1993

NON-CODE ALTERNATIVE TESTING VNC-4

system Valve(s):

EE 1-EE-SOV-102 1-EE-SOV-103 category: B Class : NC Function: Diesel Fuel Oil Pump Discharge Valves OM Part 10 Code Requirements Which cannot Be Met Measure stroke time.

Basis For Alternate Testing These valves are small (li1 ) , fast acting solenoid operated gate valves with no position indication lights and no local visual means of determining stroke time. Valve operability can only be indirectly observed by verifying system operability.

Also, these valves are interlocked with the pumps to open and close upon pump startup and shutdown.

Alternate Testing Proposed These solenoid valves will be stroke tested quarterly by obDe~' vi:a'ig *thc:.:& t the* sole:aoid **valves *perform

their intended * * *

function (fuel oil is flowing to the day tank after the solenoid valve has been opened) *

S2PVI3RO 4-89 Revision o Noveinber 10, 1993

5.0 REPORTING OF INSERVICE TEST RESULTS

5.1 PUMP INSERVICE TESTING PROGRAM A record of each pump will be maintained in accordance with OM Part 6, Section 7.1 that includes the following:

1) the manufacturer and the manufacturer's model and serial or other identification number,

2) a copy or summary of the manufacturer' acceptance test report if available,

3) a copy of the pump manufacturer' operating limits.

A record of inservice test plans will be maintained in accordance with OM Part 6, Section 7.2 that includes the following:

1) the hydraulic circuit to be used,

2) the location and type of measurement for the required test parameters,

3) the reference values and

4) the method of determining reference values which are not directly measured by instrumentation.

A record of test results will be maintained in accordance with OM Part 6, Section 7.3 that includes

' the: f oll&Wi:ilyT -

1) pump identification,

2) date of test,

3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.),

4) values of measured parameters,

5) identification of instruments used,

S2PVI3RO 4-90 Revision o Nov~:mber 10, 1993

6) comparisons with allowable ranges of test values

7) 8)

and analysis of deviations, requirement for corrective action, evaluation and justification for changes to reference values and

9) signature of the person or persons responsible for conducting and analyzing the test.

A record of corrective action will be maintained in accordance with OM Part 6, Section 7.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results.

The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC .

S2PVI3RO 4-91 Revision o November 10, 1993

5.2 VALVE INSERVICE TESTING PROGRAM

A record of each valve will be maintained in accordance with OM Part 10, Section 6.1 that includes the following:

1) the manufacturer and the manufacturer's model and serial or other unique identification number,

2) a copy or summary of the manufacturer' acceptance test report if available,

3) preservice test results and

4) limiting value of full stroke time.

This IST Program Plan meets the requirements of OM Part 10, Section 6.2, Test Plans.

A record of test results will be maintained in accordance with OM Part 10, Section 6.3 that includes the following:

1) valve identification,

2) date of test,

3) 4)

reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.),

values of measured parameters,

5) identification of instruments used,

6) comparisons with allowable ranges of test values and analysis of deviations,

7) requirement for corrective action and

8) signature of the person or persons responsible for conducting and analyzing the test.

A record of corrective action will be maintained in accordance with OM Part 10, Section 6.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results.

The Valve Inservice Test Program, associated surveillance test procedures and results will be kept 4-92 Rev~sion o S2PVI3RO Noveinber 10, 1993

at Surry Power Station. They will be available for

audit by the Authorized Nuclear Inservice Inspector and the NRC .

S2PVI3RO 4-93 Revj.sion o November 10, 1993

6.0 QUALITY ASSURANCE PROGRAM The Pump and Valve Inservice Test Program activities will be conducted in accordance with the Nuclear Operations Department Standards Manual and Technical Specifications for Surry Power station *

S2PVIJRO 4-94 Revision o Nov~mber 10, 1993

ML18151A276

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ML18151A276

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1.0 INTRODUCTION

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