Text

Change 3 to Rev 0 to Third Interval IST Program
	ML18151A642
Person / Time
Site:	Surry
Issue date:	08/01/1995
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18151A643	List: ML18151A642; ML18153A787;
References
	PROC-950801, NUDOCS 9510200253
	Download: ML18151A642 (87)
	v • d • e

ATTACHMENT 2

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 THIRD INTERVAL IST PROGRAM.

REVISION 0 CHANGE 3

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SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 Revision o of the Surry Power station Unit 1 Inservice Testing (IST) Program for the third IST interval was submitted to the NRC on October 19, 1993 (Serial No.93-658).

A NRC Safety Evaluation Report (SER) was issued by letter dated October 20, 1994 for the third interval IST program.

The SER identified several IST program anomalies that needed to be addressed by Virginia Power.

Some of these program anomalies resulted in changes to the IST program.

These changes along.with other changes that resulted from system configuration changes and system evaluations are included in this submittal.

The following is a section by section summary of all changes to Revision O, of the Surry Unit 1 IST program since the changes that were sent to the NRC by letter dated October 11, 1994.

The summary given below contains the changes sent to the NRC by letter dated March 7, 1995 which deleted the closure tests for the SI accumulator discharge check valves~

2.0 GENERAL PROGRAM DEVELOPMENT This section replaces Section 2.0 entitled "PROGRAM DESCRIPTION."

In the NRC SER, Anomaly 1, the NRC wanted a description of how the IST program was developed, how scope was determined and how the program is updated.

Section 2.0 now contains this information.

3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.5 Unit 1 Pump Number 1-SW-P-lA 1-SW-P-lB 1-SW-P-lC 1-VS-P-lA 1-VS-P-lB 1-VS-P-lC PUMP INSERVICE TEST TABLES Program Change The pump table was revised to indicate that discharge pressure will be measured for the emergency service water pumps.

This program change resulted from the Virginia Power response to Anomaly 5 in the NRC SER.

The pump table was revised to indicate that differential pressure and flow would be measured every quarter.

Relief Request P-16 is being withdrawn.

1

1-VS-P-lD 1-VS-P-lE 1-VS-P-2A 1-VS-P-2B 1-VS-P-2C 1-VS-P-2D 1-VS-P-2E 3.6 Unit,l Relief Request P-11 P-16

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 The pump table was revised to indicate that differential pressure will be measured directly instead of inlet and discharge pressure.

PUMP TEST PROGRAM RELIEF REQUESTS Program Change Reference to not measuring discharge pressure for the emergency service water pumps was deleted.

This program change resulted from the Virginia Power response to Anomaly 5 in the NRC SER

Relief request is being withdrawn.

Instrumentation has been installed for testing the service water side control room air conditioning pumps to the requirements of OM Part 6.

4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.4 VALVE INSERVICE TEST TABLES The definition for the relief valve test type (SP} was expanded to include power actuated relief valves.

Unit 1 Valve Number 1-MS-TV-109 1-MS-TV-110 Comment/Program Change An engineering evaluation concluded that these main steam high pressure drain isolation valves should be removed from the IST program because they are not required for containment integrity in the event of a LOCA.

Also, no credit is taken for mitigation of other accidents (MSLB or steam generator tube rupture) since redundant isolation is provided by.. manual valves which are 2

1-RH-100 1-RH-FCV-1605 1-RH-HCV-1758 1-SI-107 l-SI-109 l-SI-128 1-SI-130 1-SI-145 1-SI-147 1-SI-MOV-1865A 1-SI-MOV-1865B 1-SI-MOV-1865C 1-SW-108 1-SW-113 1-SW-262 l-SW-268

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 administratively kept closed.

Therefore, the valves serve no safety related function even though they receive a containment isolation signal.

Program change:

The valves were removed from the IST program.

Program change:

This valve is no longer a motor operated valve.

Therefore, the valve number was changed from 1-RH-MOV-100 to 1-RH-100.

An engineering evaluation concluded that the simultaneous failure of the RHR heat exchanger bypass and discharge.valves to go to their fail-safe positions on loss of instrument air will not create a safety concern for achieving safe shutdown.

Therefore, these valves need not be included in the IST program.

Program change:

The valves were removed from the IST Program.

The closure test requirement was deleted for the accumulator discharge check valves.

This change was submitted to the NRC by letter dated March 7, 1995 (Serial No.95-108).

Program Change:

The closure test requirement was deleted.

Program Change:

The test frequency was changed from quarterly to cold shutdown for the SI accumulator isolation valves.

Refer to Cold Shutdown Justification CSV-35.

A full flow acceptance criterion has been determined that will allow for quarterly testing of these charging pump service water pump discharge check valves.

Therefore, the valves no longer need to be disassembled and inspected.

Program Change:

Relief Request V-50 is being 3

1-SW-246 1-SW-248 1-SW-250 1-SW-252 1-SW-313 1-SW-323 2-SW-333 4.5 Unit 1 Relief Request V-26 V-27 V-41

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 withdrawn.

These check valves will be full flow tested every three months.

Program change:

These valves were upgraded from ASME non-Class to ASME Class 3.

Program change:

Relief Request V-46 is being withdrawn.

Flow instrumentation has been installed that will allow for full flow testing of the service water side control room air conditioning pump discharge check valves every three months.

VALVE TEST PROGRAM RELIEF REQUESTS Program Change This relief request was revised to change the grouping of the SI accumulator check valves from valves 1-SI-130 and 147 in one group, and valves 1-SI-107, 109, 128 and 145 in the other group, to valves 1-SI-109, 130 and 147 in one group, and valves 1-SI-107, 128 and 145 in the other group.

This change resulted from Anomaly 11 in the NRC SER.

Reference to inspection was deleted from the alternative testing section as a form of corrective action and the phrase "declared inoperable" was added.

This change resulted from Anomaly 12.

Reference to disassembly and inspection of the auxiliary feedwater pump recirculation and oil cooler check valves during plant operation was deleted as a result of Anomaly 13.

We will continue to disassemble these valves during refueling outages.

The use of nonintrusive techniques will be investigated as an alternative to disassembly.

This commitment is a result of Anomaly 3.

4

V-42 V-46 V-47 V-50

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 Reference to disassembly and inspection of the main steam supply to turbine driven auxiliary feedwater pump check valves during plant operation was deleted as a result of Anomaly 13.

We will continue to disassemble these valves during refueling outages.

The use of. nonintrusive techniques will be investigated as an alternative to disassembly.

This commitment is a result of Anomaly 3.

Relief request is being withdrawn.

Instrumentation has been installed to measure flow through the service water side control room air conditioning pump discharge check valves every three months.

Valves 1-RH-FCV-1605 and 1-RH-HCV-1758 were removed from the IST program and from this relief request.

Relief request is being withdrawn.

The basis for not full flow testing the charging pump service water pump discharge check valves was that a full flow acceptance criterion had not yet been determined.

This acceptance criterion is now available.

4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS Unit 1 cs Just Program Change CSV-35 This cold shutdown justification was added.

In accordance with Technical Specification 3.3.A.10, the accumulator discharge isolation valves l-SI-MOV-1865A, Band C shall be blocked open by de-energizing the valve motor operators when the reactor coolant system pressure is greater than 1000 psig.

These valves could be called upon to close when the reactor coolant system pressure is less than 1000 psig.

If these valves were stroked during power operation and failed in the closed position, the corresponding accumulator would be 5

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM REVISION O, CHANGE 3 rendered inoperable and thus decrease plant safety.

Also, the valve controllers do not allow for a part-stroke exercise test.

4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Unit 1 Refuel Just Program Change RRV-4 The use of a sampling plan was added for the nonintrusive testing performed on the cold leg injection valves 1-SI-79, 82, 85, 241, 242 and 243.

The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.

According to NUREG-1482, relief from Code requirements is not needed if the recommended alternative testing method is followed.

6

SURRY POWER STATION UNIT 1 REPLACEMENT PAGES

TABLE OF CONTENTS INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES

1.0 INTRODUCTION

2.0 GENERAL PROGRAM DEVELOPMENT 2.1 Program Scope 2.2 Program Update 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 4.2 4.3 4.4 4.5 4.6 4.7 4.8 Program Development Philosophy Program Implementation Program Administration Valve Inservice Test Table Valve Test Program Relief Requests Valve Test Program Cold Shutdown Justifications Valve Test Program Reactor Refueling Justifications 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 ii S1PVI3RO Revision o August 1, 1995

2.0 GENERAL PROGRAM DEVELOPMENT S1PVI3RO ASME B&P Code,Section XI (hereby referred to as 'the Code')

requires that the owner of each nuclear power plant prepare and submit a "plan" for testing and inspection of systems and components under the jurisdiction of the Code and in compliance with Title 10, Part 50 of the Code of Federal Regulations (Para. 50.55a).

With respect to the elements of that plan related to the testing of pumps and valves,Section XI, Subsections IWP and IWV direct each licensee to comply with the applicable portions of ASME/ANSI OM Parts 6 and 10.

The NRC directed via the Federal Register, Vol. 57, No. 152 dated August 6, 1992 that pump and valve testing should be performed in accordance with ASME/ANSI OM-1987 including OMa-1988 Addenda.

Specifically, Part 1 of OM-1987 and Paragraphs 1.1 of OMa-1988 Addenda, Parts 6 and 10, establish the IST program scope with the provision that the rules apply only to ISI Classes 1, 2 and 3 as stated by the NRC in the Federal Register, Vol. 56, No. 21 dated January 31, 1991.

In accordance with ASME/ANSI OM-1987 and OMa-1988 Addenda, the following are required to be included in the testing program:

1)

Centrifugal and positive displacement pumps that are provided with an emergency power source and required to perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences qf an accident.

2)

Active or passive valves (and their actuating and position indicating systems) which are required to perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.

3)

Pressure relief devices that protect systems or portions of systems which perform a required function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.

In addition to the general Code requirements outlined above, there are other interpretations and positions that have come about as a result of past regulatory and licensee actions including Generic Letter 89-04 and NUREG-1482.

Other than these guides, there is no specific guidance for developing the IST Program scope of testing.

Therefore, a set of rules was established by which the scope of the Surry ASME Section XI IST Program is determined including components that are to be included and the extent and type of testing required 2-1 Revision o August 1, 1995

SlPVI3RO for each.

Based on these rules, the philosophy and assumptions used in determining the test requirements for selected pumps an~ valves were documented.

2.1 PROGRAM SCOPE In the course of developing the Program scope, each of the significant safety systems included within the ISI Class boundaries and certain safety systems outside of the ISI Class boundaries (such as the emergency diesel fuel oil transfer system) were evaluated with respect to the function of each component and the need for its operability as it relates to the scope of Section XI.

Supporting documents used include, Final Safety Analysis Report (FSAR),

Technical Specifications, Past program correspondence, Operating Procedures (normal, emergency and abnormal) and Plant System Descriptions.

The sequence followed during the development effort was as follows:

1) Each of the plant systems was subjected to an overview to determine any potential active safety function as described in the scope statement.

Those systems with no obvious safety functions were then excluded from further consideration.

Plant documents as well as operating staff comments were utilized in this phase.

2) For the remaining systems, flow diagrams were studied and any component that could possibly have an active or passive safety function (other than simply maintaining the pressure boundary) were identified for further evaluation.

3) The function of each component identified from the flow diagrams was determined.based on available documentation, staff review or general experience of the evaluator.

Testing requirements were derived based on the component function(s) and the applicable rule(s).

4) Available documents were reviewed and specific or implied component operational requirements were compared to the component functions.

5) The results of the steps described above were reviewed by several knowledgeable members of the plant 2-2 Revision o August 1, 1995

2.2 S1PVI3RO staff and evaluated for accuracy and consistency, and compiled in an IST basis document.

Based on this review, the final program scope was derived and the IST Program Plan developed.

PROGRAM UPDATE During the third 10-year interval it is expected that the scope of the Program will occasionally be modified in response to unrelated activities including, but not limited to:

1) Plant design changes,

2) Changes in operating conditions (e.g. normal valve lineup) and

3) Changes in accident mitigating procedures philosophy.

As a result, it is expected that the IST Program may be revised to ensure continued compliance with the Code requirements relating to the scope of the test program.

The supervisor responsible for maintaining the IST.

Program is provided copies of all plant modifications*

that are designated by Engineering to have a potential*

IST/ISI impact.

Should a change require a Program revision, the IST Coordinator would then implement the change to the Program Plan and the appropriate test procedure(s) in a timely manner.

2-3 Revision o August 1, 1995

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-lA 3

VAR 0

0 0

NA 0

1,19 1-CC-P-lB 3

VAR 0

0 0

NA 0

1, 19 l-CH-P-2A 2

VAR 0

0 0

NA NA 1,21 l-CH-P-2B 2

VAR 0

0 0

NA NA 1,21 1-CC-P-2A 3

VAR 0

0 0

NA NA 1,22 l-CC-P-2B 3

VAR 0

0 0

NA NA 1,22 1-SW-P-lOA 3

VAR 0

0 0

NA NA 1

1-SW-P-lOB 3

VAR 0

0 0

NA NA 1

1-SW-P-lA 3

FIX 0

0 0

1, 11 1-SW-P-lB 3

FIX 0

0 0

1, 11 1-SW-P-lC 3

FIX 0

0 0

1, 11 1-EE-P-lA NC FIX NA 0

NA 0

0 NA NA 1,PNC-1 1-EE-P-lC NC FIX NA 0

NA 0

0 NA NA 1,PNC-1 1-EE-P-lD NC FIX NA 0

NA 0

0 NA NA 1,PNC-1 1-EE-P-lF NC FIX NA Q

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 0 S1PVI3RO August 1, 1995

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

Class Resist Press Press Press Rate Vibration s12eed LevelLPressure Regyest 1-VS-P-lA 3

VAR NA1 NA1 0

0 0

NA NA 1

1-VS-P-lB 3

VAR NA1 NA1 0

0 0

NA NA 1

1-VS-P-lC 3

VAR NA1 NA1 0

0 0

NA NA 1

1-VS-P-lD 3

VAR NA1 NA1 0

0 0

NA NA 1

1-VS-P-lE 3

VAR NA1 NA1 0

0 0

NA NA 1

1-VS-P-2A 3

VAR NA1 NA1 0

0 0

NA NA 1.11 1-VS-P-2B 3

VAR NA1 NA1 0

0 0

NA NA 1.11 1-VS-P-2C 3

VAR NA1 NA1 0

0 0

NA NA L17 1-VS-P-2D 3

VAR NA1 NA1 0

0 0

NA NA 1.11 1-VS-P-2E 3

VAR NA1 NA1 0

0 0

NA NA L17 Note 1:

According to OM Part 6, Paragraph 4.6.2.2, differential pressure can be measured using a differential pressure gauge or the difference between the discharge pressure and the inlet pressure.

measuring inlet pressure S1PVI3RO These pumps use a differential pressure gauge, is not applicable.

3-10 therefore, Revision o August 1, 1995

RELIEF REQUEST P-11 System:

Pump{s):

Class Service Water 1-SW-P-lA 1-SW-P-lB 1-SW-P-lC 3

OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph 4.3 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 The emergency service water pumps take suction from the James river and discharge into the intake canal.

The James river near the plant is subject to a tide level variation of approximately five feet.

Therefore, the total static head for the system can vary from test to test.

There are no valves in the lines to throttle flow and to _compensate for the change in system static head.

The only way to duplicate flow and differential pressure from test to test is to perform the test at the same tide level each time.

Trying to perform this test within a small enough tide level range to produce repeatable results has proven impractical.

To compensate for the change in total system nead, a pump reference curve will be prepared based on test results taken at different tide levels.

Tests will be conducted within the tide level limits of the curve, and results will be compared to acceptance criteria based on the reference curve and the ranges given in OM Part 6, Table 3b.

Inlet pressure will be calculated from tide level.

Alternate Testing Proposed The flow is dependent upon tide level.

Tests will be conducted within the tide level limits of the pump reference curve, and flow will be compared to acceptance criteria based on the reference curve and the ranges given in OM Part 6, Table 3b.

3-17 S1PVI3RO Revision o August 1, 1995

S1PVI3RO THIS PAGE IS INTENTIONALLY BLANK 3-18 Revision o August 1, 1995

S1PVI3RO RELIEF REQUEST P-16 Relief Request Withdrawn 3-20 Revision o August 1, 1995

SlPVIJRO THIS PAGE IS INTENTIONALLY BLANK 3-21 Revision o August 1, 1995

S1PVI3RO THIS PAGE IS INTENTIONALLY BLANK 3-22 Revision o August 1, 1995

S1PVI3RO THIS PAGE IS INTENTIONALLY BLANK 3-23 Revision O August 1, 1995

VALVE NUMBER 1-MS-TV-1018 1-MS-TV-101C VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-064A 2 OF 6 C-4 AO CHECK VALVE 30.000 2 11811 MAIN STEAM HEADER TRIP VALVE 11448-CBM-064A 3 OF 6 C-4 AO CHECK VALVE 30.000 2 11C11 MAIN STEAM HEADER TRIP VALVE B

B EV ST VP EV ST VP PAGE:

37 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

QC C

C oc

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-RH-005 1-RH-011 1-RH-100 11448-CBM-087A 1 OF 2 E-5 CHECK VALVE 11811 RHR PUMP DISCHARGE CHECK VALVE 11448-CBM-087A 1 OF 2 E-7 CHECK VALVE 11A11 RHR PUMP DISCHARGE CHECK VALVE 11448-CBM-087A 2 OF 2 E-3 MANUAL GATE RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RH-MOV-1700 11448-CBM-087A 1 OF 2 A-5 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 1-RH-MOV-1701 11448-CBM-087A 1 OF 2 A-4 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 1-RH-MOV-1720A 11448-CBM-087A 2 OF 2 C-3 MO GATE RHR RETURN ISOLATION TO 11811 ACCUMULATOR DISCHARGE LINE 1-RH-MOV-17208 11448-CBM-087A 2 OF 2 B-3 MO GATE 1-RH-RV-1721 RHR RETURN ISOLATION TO 11C11 ACCUMULATOR DISCHARGE LI NE 11448-CBM-087A 2 OF 2 D-4 RELIEF VALVE RHR SYSTEM RELIEF VALVE 10.000 2 C

CV 10.000 2 C

CV 6.000 2 AE CIV LT 14.000 1 B

EV ST VP 14.000 1 B

EV ST VP 10.000 1 B

EV ST VP 3.000 2 C

SP PAGE:

41 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS

RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C 0

oc 0

C 0

oc 0

C 0

oc 0

C 0

OC 0

8 8

9 9

10 10 10 10

VALVE NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL iNSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE THIS PAGE IS INTENTIONALLY BLANK

PAGE:

42 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV--RRV-VCN-

VALVE NUMBER 1-SI-079 1-Sl-082 1-Sl-085 1-Sl-088 1-Sl-091 1-Sl-094 VIRGINIA PO'JER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-089B 4 OF 4 F-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 11448-CBM-089B 4 OF 4 E-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 11448-CBM-089B 4 OF 4 D-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 11448-CBM-089B 4 OF 4 D-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11448-CBM-089B 4 OF 4 C-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11448-CBM-089B 4 OF 4 B-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 6.000 1 6.000 1 6.000 1 6.000 1 6.000 1 6.000 1 AC PIV LT AC PIV CV LT AC PIV CV LT C

CV C

CV 1-Sl-107 11448-CBM-089B 1 OF 4 B-7 CHECK VALVE 12.000 1 C

"A11 ACCUMULATOR DISCHARGE CHECK VALVE 1-Sl-109 1-Sl-128 1-Sl-130 11448-CBM-089B 1 OF 4 B-8 CHECK VALVE 11A11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11448-CBM-089B 2 OF 4 B-6 CHECK VALVE 11B11 ACCUMULATOR DISCHARGE CHECK VALVE 11448-CBM-089B 2 OF 4 B-7 CHECK VALVE 11B11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 12.000 1 C

12.000 1 C

CV CV CV CV PAGE:

50 OF 70 REVISION: 00 DATE: 02/24/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

0 C

C 0

C C

27 0

C 0

0 0

27 27 26 26 26 26 4

4 4

4 3

3 3

3 I

VALVE NUMBER 1-SI-145 1-SI-147 1-SI-150 1-SI-174 1-SI-224 1-SI-225 1-SI-226 1-SI-227 1-SI-228 1-SI-229 1-SI-234 1-SI-235 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-089B 3 OF-4 B-5 CHECK VALVE "C" ACCUMULATOR DISCHARGE CHECK VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 12.000 1 C

CV 11448-CBM-089B 3 OF 4 B-7 CHECK VALVE

12.000 1 C

11C11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11448-CBM-089A 3 OF 3 F-6 MAN GLOBE BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG 11448-CBM-089A 3 OF 3 D-6 MAN GLOBE HIGH HEAD SAFETY INJECTION TO RCS 11448-CBM-089B 4 QF 4 F-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE

.750 2

.750 2 3.000 2 11448-CBM-089B 4 OF 4 E-3 CHECK VALVE 3.000 2 HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUM_PS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 1 OF 4 F-3 CHECK VALVE NITROGEN SUPPLY TO ACCUMULATORS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-089B 4 OF 4 F-7 CHECK VALVE 3.000 2 3.000 2 6.000 2 6.000 2 1.000 2 2.000 1 CV AE CIV LT AE CIV LT C

CV C

CV AC CIV CV LT C

CV PAGE:

51 OF 70 REVISION: 00 DATE: 02/24/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0

C C

0 0

C C

C 0

26 26 3

3 4

4 4

4 6

4 4

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 1-SI-MOV-18638 11448-CBM-089A 2 OF 3 D-3 MO GATE 11811 LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1-SI-MOV-1864A 11448-CBM-089A 2 OF 3 D-6 MO GATE "A" LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 1-SI-MOV-18648 11448-CBM-089A 2 OF 3 D-4 MO GATE 11811 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 1-SI-MOV-1865A 11448-CBM-0898 1 OF 4 C-7 MO GATE "A" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1-SI-MOV-18658 11448-CBM-0898 2 OF 4 C-6 MO GATE 11811 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 8.000 2 B

10.000 2 B

12.000 2 B

ST VP EV ST VP EV ST VP EV ST VP EV ST VP 1-SI-MOV-1865C 11448-CBM-0898, 3 OF 4 C-5 MO GATE "C" ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1-SI-MOV-1867C 11448-CBM-089A 3 OF 3 E-6 MO GATE HIGH HEAD SAFETY INJECTION TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 12.000 2 3.000 2 B

EV ST VP A

CIV EV LT ST VP PAGE:

54 OF 70 REVISION: 00 DATE: 02/24/95 NC REL CS RR

.ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

C 0

oc 35 35 35 35 35 35 35*

35 35 35 35 35 18 18 18 18

VALVE NUMBER 1-sw-012 1-SW-108 1-SW-113 1-SW-206 1-SW-208 1-SW-246 1-SW-247 1-SW-248 1-SW-249 1-SW-250 1-SW-251 1-SW-252 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-071A 2 OF 4 C-4 BUTTERFLY SERVICE WATER SUPLY HEADER TO CHILLED WATER SYSTEM MANUAL ISOLATION VALVE 10.000 3 11448-CBM-071B 1 OF 2 B-4 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11448-CBM-071B 1 OF 2 B-7 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11448-CBM-071A 3 OF 4 E-8 MAN GATE CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 11448-CBM-071A 3 OF 4 E-8 MAN GATE CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 2.000 3 2.000 3 2.000 2 2.000 2 11448-CBM-071A 3 OF 4 C-8 CHECK VALVE 3.000 3 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBH-071A 3 OF 4 D-7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071A 3 OF 4 C-7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-071A 3 OF 4 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071A 3 OF 4 C-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-071A 3 OF 4 D-5 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071A 3 OF 4 C-5 CHECK VALVE 3.000 3 3.000 3 3.000 3 3.000 3 3.000 3 3.000 3 B

EV C

CV C

CV AE CIV LT AE CIV LT C \\

CV C

CV PAGE:

61 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

0 C

C 0

0 0

34

VALVE NUMBER 1-SW-253 1-SW-262 1-SW-264 1-SW-265 1-SW-268 1-SW-313 1-SW-323 1-sw-m 1-SW-778 1-SW-839 1-SW-840 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-071A 3 OF 4 D-4 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071B 1 OF 2 B-4 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 11448-CBM-071D 1 OF 1 C-5 MANUAL BFLY CONTROL ROOM CONDENSER WATER TO BACKUP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-071D 1 OF 1 C-7 MANUAL BFLY CONTROL ROOM CONDENSER WATER TO BACKUP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-071B 1 OF 2 B-6 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 11448-CBM-071D 1 OF 1 F-7 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 11448-CBM-071D 1 OF 1 F-5 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 11448-FM-071D 2 OF 2 C-5 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 11448-FM-071D 2 OF 2 C-4 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE VALVE 11448-FM-071D 2 OF 2 F-5 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM DISCHARGE CHECK VALVE 11448-FM-071D 2 OF 2 F-4 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM DISCHARE CHECK VALVE 3_000 3 C

CV 2.000 3 C

CV 6.000 3 B

EV 6.000 3 B

EV 2.000 3 C

CV 3.000 3 C

CV 4.000 3 C

CV 3.000 3 C

CV 1-SW-MOV-101A 11448-CBM-071A 3 OF 4 B-4 MO BFLY 36.000 3 B

EV ST PAGE:

62 OF 70 REVISION: 00 DATE: 08/01/95 NC

. REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0

0 0

0 C

C 53 53

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SW-MOV-101A 11448-CBM-071A 3 OF 4 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 1-SW-MOV-101B 11448-CBM-071A 3 OF 4 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 1-SW-MOV-102A 11448-CBM-071A 2 OF 4 D,6 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SW-MOV-102B 11448-CBM-071A 2 OF 4 D-5 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1*SW-MOV-103A 11448-CBM*071A 3 OF 4 B-8 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-103B 11448-CBM-071A 3 OF 4 B-8 MO BFLY SERVICE WATER HEADER SUPPLY iSOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-103C 11448-CBM-071A 3 OF 4 B-3 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-103D 11448-CBM-071A 3 OF 4 8-2 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-104A 11448-CBM-071A 3 OF 4 D-7 MO BFLY 36.000 3 36.000 3 42.000 3 42.000 3 30.000 3 30.000 3 30.000 3 30.000 3 24.000 3 B

B B

VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST PAGE:

63 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN*

oc C

C oc C

0 C

0 oc C

0 C

0 oc 0

0 oc C

0 C

VIRG.INIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SW-MOV-104A 11448-CBM-071A 3 OF 4 D-7 MO BFLY 24.000 3 SERVICE WATER SUPPLY TO "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-104B 11448-CBM-071A 3 OF 4 D-6 MO BFLY 24.000 3 SERVICE WATER SUPPLY TO "B" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-104C 11448-CBM-071A 3 OF 4 D-5 MO BFLY 24.000 3 SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE. CONT ISOLATION VALVE 1-SW-MOV-104D 11448-CBM-071A 3 OF 4 D-4 MO BFLY 24.000 3 SERVICE WATER SUPPLY TO 11D11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT-ISOLATION VALVE 1*SW-MOV-105A 11448-CBM-071A 3 OF 4 D-8 MO BFLY SERVICE WATER RETURN FROM "A" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV*105B 11448-CBM-071A 3 OF 4 D-7 MO BFLY SERVICE WATER RETURN FROM 11B11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-105C 11448-CBM-071A 3 OF 4 D-6 MO BFLY SERVICE WATER RETURN FROM "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-105D 11448-CBM-071A 3 OF 4 D-5 MO BFLY 24.000 3 24.000 3 24.000 3 24.000 3 B

B B

B ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV PAGE:

64 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ _JUST JUST TEST POS V-CSV-RRV-VCN-0 QC C

0 C

0 QC C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

0 C

0 oc C

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SW-MOV-105D 11448-CBM-071A 3 OF 4 D-5 MO BFLY SERVICE WATER RETURN FROM 11D11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-PCV-100A 11448-CBM-071D 1 OF 1 F-7 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-100B, 11448-CBM-071D 1 OF 1 F-5 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-100C 11448-CBM-071D 1 OF 1 F-3 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-100D 11448-FM-071D 2 OF 2 F-5 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV*100E 11448-FM-071D 2 OF 2 F-4 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV*101A 11448-CBM-071D 1 OF 1 E-8 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV*101B 11448-CBM-071D 1 OF 1 E-6 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*SW-PCV-101C 11448-CBM-071D 1 OF 1 E-4 AO GATE 24.000 3 B

3.000 3 B

EV ST VP EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST PAGE:

65 OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 C

0 oc 0

0 0

C C

C 47 47 47 47 47 47 47 47

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-101D 11448-FM-071D 2 OF 2 D-5 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-101E 11448-FM-071D 2 OF 2 D-3 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE.

CONROL VALVE 1-SW-TCV-108A 11448-CBM-071B 1 OF 2 E-7 AO GATE SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1-SW-TCV-108B 11448-CBM-071B 1 OF. 2 E-5 AO GATE SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1-SW-TCV-108C 11448-CBM-071B 1 OF 2 E-4 AO GATE 2-SW-333 SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 11448-CBM-071D 1 OF 1 F-3 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 3.000 3 3.000 3 1.500 3 1.500 3 1.500 3 3.000 3 B

B B

C EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST CV PAGE:

65A OF 70 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

C C

0 0

47 47 47 47 47

S1PVI3RO 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 allowed by OM Part 10, Section 4.i.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, 1987 Edition or as modified by a specific relief request.

In the case of power actuated relief valves, testing consists of determining the operability of the pressure sensing and valve actuation equipment per the requirements of OM Part 1, Section 7.3.1.2.

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.

4-6 Revision o August 1, 1995

RELIEF REQUEST V-26 system Safety Injection Valve{s):

1-SI-107 1-SI-128 1-SI-145 category:

c Class 1

1--SI-109 1-SI-130 1-SI-147 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 in the alternate testing section.

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.

4-15 S1PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-26 (Cont.)

Valves 1-SI-109, 130 and 147 are closest to the reactor coolant system and are in one group, and valves 1-SI-107, 128 and 145 are in the other group.

The justification for testing these valves during reactor refuelings is described in Reactor Refueling Justification RRV-3

4-16 S1PVI3RO Revision O August 1, 1995

RELIEF REQUEST V-27 system Safety Injection Valve(s):

1-SI-88 1-SI-91 1-SI-94 Category:

C Class 1

1-SI-238 1-SI-239 1-SI-240 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 l-SI-88, 91, 94, 238, 239 and 240.

There are no drains between the valve pairs 1-SI-88 and 1-SI-238, 1-SI-91 and 1-SI-239, and 1-SI-94 arid 1-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 the leakage limit is exceeded, both valves in the pair will be declared inoperable and subject to repair or replacement.

Note that there is no specified permissible accident leakage limit for these valves.

Therefore, these valves are Category C.

S1PVI3RO Revision O August 1, 1995

RELIEF REQUEST V-41 System Valve(s)..

Category..

Class FW 1-FW-144 1-FW-148 C

3 1-FW-159 1-FW-163 1-FW-174 1-FW-'178 Function.. Auxiliary Feedwater Pump Recirc Line and Pump 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 instrumentation 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.

Alternate Testing Proposed I

Valves 1-FW-144, 159, and 174 will be grouped together; valves 1-FW-148, 163, and 178 will be grouped together and one valve from each group will be disassembled and inspected every reactor r.

refueling.

A different valve from each group will be disassembled for each inspection.

If a valve fails its inspection, t~e remaining valves in the group will be disassembled and inspected

4-20 S1PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-42 System MS Valve(s) :

1-MS-176 1-MS-178 1-MS-182 Category:

C 2

Class 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."

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.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling.

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.

The valves will be full flow tested every three months.

4-21 S1PVI3RO Revision o August 1, 1995

S1PVI3RO INTERIM RELIEF REQUEST V-46 Relief Request Withdrawn 4-25 Revision o August 1, 1995

SlPVI3RO THIS PAGE IS INTENTIONALLY BLANK 4-26 Revision O August 1, 1995

RELIEF REQUEST V-47 System.. Various Valve(s):

Valves affected by this relief request are identified Category:

Class Function:

by Table V-47.

OM Part 10 Code Requirements For Which 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 (4.2.1.8(b)) and +/-50% for power-operated valves with reference stroke times less than or equal to 10 seconds (4.2.1.8(d)).

Basis For Relief The valves listed in Table V-47 either have no remote indication and no remote control, or no remote open/close control, or the 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 4.2.1.8(b) and (d).

Therefore, timing the full-stroke from the initiation of the actuating signal and applying the acceptance criteria of Paragraphs 4.2.1.8(b) and (d) are not practical.

Valve 1-CC-LCV-101 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 1-MS-RV-lOlA, Band C is controlled by a potentiometer.

Although the valves have remote position 4-27 S1PVI3RO Revision o August 1, 1995

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 1-SW-PCV-lOOA, B, C, D and E, and 1-SW-PCV-lOlA, B, C, D and E have no remote indication or manual remote control.

The valve position is manipulated by venting the actuator diaphragm and the stroke time is measured by observing the movement of the local position indicator.

Differences in the speed at which the petcock is opened to vent the diaphragm and in interpreting when the position indicator starts and stops affect the repeatability of the stroke time measurements.

Valves 1-SW-TCV-lOSA, 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 4.2.1.9(a).

However, the ranges described in Paragraphs 4.2.1.S(b) and {d) will not be applied

4-28 S1PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-47 (Cont.)

TABLE V-47 Valve 1-CC-LCV-101 category Class Function 1-MS-RV-101A,B,C 1-SW-PCV-lOOA,B,C 1-SW-PCV-lOOD,E 1-SW-PCV-101A,B,C 1-SW-PCV-101D,E 1-SW-TCV-lOSA,B,C SlPVIJRO B

3 B

B B

B 2

3 3

3 4-29 Charging Pump Seal Cooling Surge Tanlc Level Control Main Steam Header

.Discharge to Atmosphere PORV Control Room Condenser Water System Pressure Control Valves Service Water to Charging Pump Lube Oil Cooler Temperature Control Valves Revision O August 1, 1995

S1PVI3RO RELIEF REQUEST V-50 Relief Request Withdrawn 4-31 Revision O August 1, 1995

COLD SHUTDOWN JUSTIFICATION CSV-35 System Safety Injection Valve(s):

1-SI-MOV-1865A l-SI-MOV-1865B l-SI-MOV-1865C category:

B Class 2

Function:

Accumulator Discharge Isolation Valves to RCS Cold Leg Cold Shutdown Justification In accordance with Technical Specification 3.3.A.10, 'the accumulator discharge isolation valves 1-SI-MOV-1865A, Band c shall be blocked open by de-energizing the valve motor operators when the reactor coolant system pressure is greater than 1000 psig.

These valves could be called upon to close when the reactor coolant system pressure is less than 1000 psig. If these valves were stroked during power operation and failed in the closed position, the corresponding accumulator would be rendered inoperable and thus decrease plant safety.

Also, the valve controllers do not allow for a part-stroke exercise test.

Testing Frequency These valves will be full stroke exercised to the open and closed positions every cold shutdown but not more frequently than once every three months.

4-67b SlPVI3RO Revision O February 24, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 System Safety Injection Valve{s):

Valves affected by this request are identified in Category:

Class Function:

Table RRV-4.

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 injection path valves during cold shutdowns when 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 1-SI-79. 82, 85. 241. 242 and 243 To individually verify closure for valves 1-SI-79, 82, 85, 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.

Therefore, it is impractical to perform a closure test. every quarter.

4-73 S1PVI3RO Revision o August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

These valves are designated as pressure isolation valves.

Technical Specification Table 4.1-2A 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 4.2.1.2(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 co~tinue 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 respect, the Technical Specification frequency is more 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.

Close Test Discussion for l-SI-88. 91. 94, 238, 239 and 240 Individual valve closure cannot be verified for valves l-SI-88, 91, 94, 238, 239 and 240.

There are no drains between the valve pairs 1-SI-88 and 1-SI-238, l-SI-91 and 1-SI-239, and 1-SI-94 and 1-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

4-74 S1PVI3RO Revision o August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

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 l-SI-235, 236 and 237 To verify closure for valves 1-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 every cold shutdown, a leakage test 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.

Testing Frequency Testing Frequency To the Open Position There is no installed instrumentation that can measure individual flow rates for valves 1-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 1-SI-88, 91, 94, 238, 239 and 240 each reactor refueling.

With low head pump flow, the cold leg injection valves 1-SI-79, 82, 85, 241, 242 and 243 will be acoustically monitored using a sampling plan 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.

4-75 SlPVI3RO Revision o August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.

The valves will be placed into two groups with valves 1-SI-79, 82 and 85 in one group, and valves 1-SI-241, 242 and 243 in the other group.

During initial testing using nonintrusive techniques, each valve in the group will be nonintrusively verified as operable.

During subsequent testing, nonintrusive verification will be performed for only one valve of the group on a rotating schedule each time the testing is performed, and the balance of the group will be flow tested.

If problems are found with the sample valve that are determined to affect the operational readiness of the valve, all valves in the group must be tested using nonintrusive techniques during the same outage.

The remaining valves 1-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 1-SI-79, 82, 85, 241, 242 and 243 will be tested to the closed position per the requirements of Technical Specification Table 4.1-2A.

The valve pairs 1-SI-88 and l-SI-238, and 1-SI-91 and 1-SI-239, and 1-SI-94 and 1-SI-240 will be tested for leakage to confirm that the valve pairs provide isolation for the three hot leg injection paths.

The leakage tests will be performed 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 1-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 l-SI-224, 225, 226, 227, 228 and 229 need only to open to perform their safety function.

No credit is taken for valves l-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.

4-76 SlPVI3RO Revision o August 1, *1995

Valve 1-SI-88, 1-SI-94, 1-SI-239, 1-SI-235 1-SI-236 1-SI-237 1-SI-241 1-SI-242 1-SI-243 1-SI-224, 1-SI-226, 1-SI-228, 1-SI-79, S1PVI3RO REACTOR REFUELING JUSTIFICATION RRV-4 (cont.)

category 91 C

238 240 C

AC 225 C

227 229 C

82, 85 AC TABLE RRV-4 Class 1

1 1

2 2

1 4-77 Function Safety Injection to RCS Hot Legs High Head Safety Injection to RCS Cold Legs Low Head Safety Injection to RCS Cold Legs High Head Safety Injection Check Valve at Containment Penetrations Low Head Safety Injection Check Valves at Containment Penetrations Safety Injection to RCS Cold Legs Revision o August 1, 1995

ATTACHMENT 3

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 THIRD INTERVAL 1ST PROGRAM REVISION 0 CHANGE 3

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM REVISION O, CHANGE 3 Revision O of the Surry Power Station Unit 2 Inservice Testing (IST) Program for the third IST interval was submitted to the NRC on October 19, 1993 (Serial No.93-658).

A NRC Safety Evaluation Report (SER) was issued by letter dated October 20, 1994 for the third interval IST program.

The SER identified several IST program anomalies that needed to be addressed by Virginia Power.

Some of these program anomalies resulted in changes to the IST program.

These changes along with other changes that resulted from system configuration changes and system evaluations are included in this submittal.

The following is a section by section summary of all changes to Revision o, of the Surry Unit 1 IST program since the changes that were sent to the NRC by letter dated October 11, 1994.

The summary given below contains the changes sent to the NRC by letter dated March 7, 1995 which deleted the closure tests for the SI accumulator discharge check valves.

2.0 4.0 GENERAL PROGRAM DEVELOPMENT This section replaces Section 2.0 entitled "PROGRAM DESCRIPTION."

In the NRC SER, Anomaly 1, the NRC wanted a description of how the IST program was developed, how scope was determined and how the program is updated.

Section 2.0 now contains this information.

VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.4 VALVE INSERVICE TEST TABLES The definition for the relief valve test type (SP) was expanded to include power actuated relief valves.

Unit 2 Valve Number Comment/Program Change 2-MS-TV-209 2-MS-TV-210 An engineering evaluation concluded that these main steam high pressure drain isolation valves should be removed from the IST program because they are not required for containment integrity in the event of a LOCA.

Also, no credit is taken for mitigation of other accidents (MSLB or steam generator tube rupture) since redundant isolation is 1

2-RH-200 2-RH-FCV-2605 2-RH-HCV-2758 2-RH-MOV-2720A 2-RT-2 2-RT-6 2-RT-21 2-RT-25 2-RT-40 2-RT-44 2-SI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 2-SI-147

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM REVISION O, CHANGE 3 provided by manual valves which are administratively kept closed.

Therefore, the valves serve no safety related function even though they receive a containment isolation signal.

Program change:

The valves were removed from the IST program.

Program change:

This valve is no longer a motor operated valve.

Therefore, the valve number was changed from 2-RH-MOV-200 to 2-RH-200.

An engineering evaluation concluded that the simultaneous failure of the RHR heat exchanger bypass and discharge valves to go to their fail-safe positions on loss of instrument air will not create a safety concern for achieving safe shutdown

Therefore, these valves need not be included*

in the IST program.

Program change:

The valves were removed from the IST Program.

Program change:

The ASME Class was changed from 1 to 2.

Program change:

The isolation valve type "CIV" was added under the appropriate column.

This designation was erroneously omitted in previous versions and the addition of it to the tables does not imply additional testing requirements.

The closure test requirement was deleted for the accumulator discharge check valves.

This change was submitted to the NRC by letter dated March 7, 1995 (Serial No.95-108).

Program Change:

The closure test requirement was deleted.

2

2-SI-MOV-2865A 2-SI-MOV-2865B 2-SI-MOV-2865C 2-SW-108 2-SW-113 2-SW-442 2-SW-445 2-SW-246 2-SW-248 2-SW-250 2-SW-252 2-SW-247 2-SW-249 2-SW-251 2-SW-253

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM REVISION O, CHANGE 3 Program Change:

The test frequency was changed from quarterly to cold shutdown for the SI accumulator isolation valves.

Refer to Cold Shutdown Justification CSV-34.

A full flow acceptance criterion has been determined that will allow for quarterly testing of these charging pump service water pump discharge check valves.

Therefore, the valves no longer need to be disassembled and inspected.

Program Change:

Relief Request V-50 is being withdrawn.

These check valves will be full flow tested every three months.

Program change:

These valves were upgraded from ASME non-Class to ASME Class 3.

Program change:

Reference to disassembly and inspection of the recirculation spray heat exchanger service water vent check valves during plant operation was deleted as a result of Anomaly 13.

4.5 VALVE TEST PROGRAM RELIEF REQUESTS Unit 2 Relief Request V-26 V-27 Program Change This relief request was revised to change the grouping of the SI accumulator check valves from valves 2-SI-130 and 147 in one group, and valves 2-SI-107, 109, 128 and 145 in the other group, to valves 2-SI-109, 130 and 147 in one group, and valves 2-SI-107, 128 and 145 in the other group.

This change resulted from Anomaly 11 in the NRC SER.

Reference to inspection was deleted from the alternative testing section as a form of corrective action and the phrase "declared 3

I~

V-41 V-42 V-46

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM REVISION O, CHANGE 3 inoperable" was added.

This change resulted from Anomaly 12.

Reference to disassembly and inspection of the auxiliary feedwater pump recirculation and oil cooler check valves during plant operation was deleted as a result of Anomaly-13.

The use of nonintrusive techniques will be investigated as an alternative to disassembly.

This commitment is a result of Anomaly 3.

Reference to disassembly and inspection of the main steam supply to turbine driven auxiliary feedwater pump check valves during plant operation was deleted as a result of Anomaly 13.

The use of nonintrusive techniques will be investigated -as an alternative to disassembly.

This commitment is a result of Anomaly 3.

Reference to disassembly and inspection of the recirculation spray heat exchanger service water vent check valves during plant operation was deleted as a result of Anomaly 13.

V-47 Valves 2-RH-FCV-2605 and 2-RH-HCV-2758 were removed from the IST program and from this relief request.

V-50 Relief request is being withdrawn.

The basis for not full flow testing the charging pump service water pump discharge check valves was that a full

_flow acceptance criterion had not yet been determined.

This acceptance criterion is now available.

4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS Unit 2 cs Just Program Change CSV-34 This cold shutdown justification was added.

In accordance with Technical Specification 3.3.A.10, the accumulator discharge isolation valves 2-SI-MOV-2865A, Band C shall be blocked open by de-4

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM.

REVISION O, CHANGE 3 energizing the valve motor operators when the reactor coolant system pressure is greater than 1000 psig.

These valves could be called upon to close when the reactor coolant system pressure is less than 1000 psig.

If these valves were stroked during power operation and failed in the closed position, the corresponding accumulator would be rendered inoperable and thus decrease plant safety.

Also, the valve controllers do not allow for a part-stroke exercise test.

4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Unit 2 Refuel Just Program Change RRV-4 The use of a sampling plan was added for the nonintrusive testing performed on the cold leg injection valves 2-SI-79, 82, 85, 241, 242 and 243.

The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.

According to NUREG-1482, relief from Code requirements is not needed if the recommended alternative testing method is followed

5

SURRY POWER STATION UNIT2 REPLACEMENT PAGES

TABLE OF CONTENTS INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES

1.0 INTRODUCTION

2.0 GENERAL PROGRAM DEVELOPMENT 2.1 Program Scope 2.2 Program Update 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 4.2 4.3 4.4 4.5 4.6 4.7 4.8 Program Development Philosophy Program Implementation Program Administration Valve Inservice Test Table Valve Test Program Relief Requests Valve Test Program Cold Shutdown Justifications Valve Test Program Reactor Refueling Justifications 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 ii S2PVI3RO Revision o August 1, 1995

2.0 GENERAL PROGRAM DEVELOPMENT S2PVI3RO ASME B&P Code,Section XI (hereby referred to as 'the Code')

requires that the owner of each nuclear power plant prepare and submit a "plan" for testing and inspection of systems and components under the jurisdiction of the Code and in compliance with Title 10, Part 50 of the Code of Federal Regulations (Para.. 50.55a).

With respect to the elements of that plan related to the testing of pumps and valves, section XI, Subsections IWP and IWV direct each licensee to comply with the applicable portions of ASME/ANSI OM Parts 6 and 10.

The NRC directed via the Federal Register, Vol. 57, No. 152 dated August 6,' 1992 that pump and valve testing should be performed in accordance with ASME/ANSI OM-1987 including OMa-1988 Addenda.

Specifically, Part 1 of OM-1987 and Paragraphs 1.1 of OMa-1988 Addenda, Parts 6 and 10, establish the IST program scope with the provision that the rules apply only to ISI Classes 1, 2 and 3 as stated by the NRC in the Federal Register, Vol. 56, No. 21 dated January 31, 1991.

In accordance with ASME/ANSI OM-1987 and OMa-1988 Addenda, the following are required to be included in the testing program:

1)

Centrifugal and positive displacement pumps that are provided with an emergency power source and required to

perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.

2)

Active or passive valves (and their actuating and position indicating systems) which are required to perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.

3)

Pressure relief devices that protect systems or portions of systems which perform a required function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or mitigating the consequences of an accident.

In addition to the general Code requirements outlined above, there are other interpretations and positions that have come about as a result of past regulatory and licensee actions including Generic Letter 89-04 and NUREG-1482.

Other than these guides, there is no specific guidance for developing the IST Program scope of testing.

Therefore, a set of rules was established by which the scope of the Surry ASME Section XI IST Program is determined including components that are to be included and the extent and type of testing required 2-1 Revision o August 1, 1995

S2PVI3RO for each.

Based on these rules, the philosophy and assumptions used in determining the test requirements for selected pumps and valves were documented.

2.1 PROGRAM SCOPE In the course of developing the Program scope, each of the significant safety systems included within the ISI Class boundaries and certain safety systems outside of the ISI Class boundaries (such as the emergency diesel fuel oil transfer system) were evaluated with respect to the function of each component and the need for its operability as -it relates to the scope of Section XI.

Supporting documents used include, Final Safety Analysis Report (FSAR),

Technical Specifications, Past program correspondence, Operating Procedures (normal, emergency and abnormal) and Plant System Descriptions.

The sequence followed during the development effort was as follows:

1) Each of the plant systems was subjected to an overview to determine any potential active safety function as described in the scope statement.

Those systems with no obvious safety functions were then excluded from further consideration. Plant documents as well as operating staff comments were utilized in this phase.

2) For the remaining systems, flow diagrams were studied and any component that could possibly have an active or passive safety function (other than simply maintaining the pressure boundary) were identified for further evaluation.

3) The function of each component identified from the flow diagrams was determined based on available documentation, staff review or general experience of the evaluator.

Testing requirements were derived based on the component function(s) and the applicable rule(s).

4) Available documents were reviewed and specific or implied component operational requirements were compared to the component functions.

5) The results of the steps described above were reviewed by several knowledgeable members of the plant 2-2 Revision o August 1, 1995

2.2 S2PVI3RO staff and evaluated for accuracy and consistency, and compiled in an IST basis document.

Based on this review, the final program scope was derived and the IST Program Plan developed.

PROGRAM UPDATE During the third 10-year interval it is expected that the scope of the Program will occasionally be modified in response to unrelated activities including, but not limited to:

1) Plant design changes,

2) Changes in operating conditions (e.g. normal valve lineup) and

3) Changes in accident mitigating procedures philosophy.

As a result, it is expected that the IST Program may be revised to ensure continued compliance with the Code requirements relating to the scope of the test program.

The supervisor responsible for maintaining the IST Program is provided copies of all plant modifications*

that are designated by Engineering to have a potential*

IST/ISI impact.

Should a change require a Program revision, the IST Coordinator would then implement the change to the Program Plan and the appropriate test procedure(s) in a timely manner.

2-3 Revision O August 1, 1995

S2PVI3RO 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 allowed 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, 1987 Edition or as modified by a specific relief request.

In the case of power actuated relief valves, testing consists of determining the operability of the pressure sensing and valve actuation equipment per the requirements of OM Part 1, Section 7.3.1.2.

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.

4-6 Revision o.

August 1, 1995

VALVE NUMBER 2-MS-TV-201B 2-MS-TV-201C VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NIMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11548-CBM-064A 2 OF 6 C-4 AO CHECK VALVE 30.000 2 11811 MAIN STEAM HEADER TRIP VALVE 11548-CBM-064A 3 OF 6 C-4 AO CHECK VALVE 30.000 2 11C11 MAIN STEAM HEADER TRIP VALVE B

B EV ST VP EV ST VP PAGE:

35 OF 66 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

oc C

C oc

VIRGINIA POWER COMPANY.

SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRA"ING NUMBER SHEET DR"G VALVE NUMBER COOR TYPE VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2-RH-005 2-RH-011 2-RH-047 2-RH-200 11548-CBM-087A 1 OF 2 E-5 CHECK VALVE 11B" RHR PUMP DISCHARGE CHECK VALVE 11548-CBM-087A 1 OF 2 E-7 CHECK VALVE "A" RHR PUMP DISCHARGE CHECK VALVE

.11548-CBM-087A 2 OF 2 C-3 CHECK VALVE RHR DISCHARGE TO LOOP 2 COLD LEG CHECK VALVE 11548-CBM-087A 2 OF 2 E-3 MANUAL GATE RHR SUPPLY ISOLATION TO REFUEL "ATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 2-RH-MOV-2700 11548-CBM-087A 1 OF 2 A-5 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2-RH-MOV-2701 11548-CBM-087A 1 OF 2 A-4 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 2-RH-MOV-2720A 11548-CBM-087A 2 OF 2 C-3 MO GATE RHR RETURN ISOLATION TO "B" ACCUMULATOR DISCHARGE LINE 2*RH-MOV-2720B 11548-CBM-087A 2 OF 2 B-3 MO GATE 2-RH-RV-2721 RHR RETURN ISOLATION TO 11C11 ACCUMULATOR DISCHARGE LINE 11548-CBM-087A 2 OF 2 D-4 RELIEF VALVE RHR SYSTEM RELIEF VALVE 10.000 2 10.000 2 10.000 1 6.000 2 14.000 1 C

CV C

CV AE CIV LT B

EV ST VP 14.000 1 B

EV ST VP 10.000 2 B

10.000 1 B

3.000 2 C

EV ST VP EV ST VP SP PAGE:

39 OF 66 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C 0

0 C

0 0

QC 0

0 QC 0

0 oc 0

8 8

8 9

9 9

9 10 10 10 10

VALVE

NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE THXS PAGE XS XNTENTXONALLY BLANK

PAGE:

40 OF 66 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV-RRV-VCN-

VALVE NUMBER 2-RT-02 2-RT-06 2-RT-21 2-RT-25 2-RT-40 2-RT-44 VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM*- VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11548-CBM-124A 1 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11548-CBM-124A 1 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 11548-CBM-124A 2 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11548-CBM-124A 2 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 11548-CBM-124A 3 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11548-CBM-124A 3 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT PAGE:

45 OF 66 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C

C C

C)

VALVE NUMBER 2-SI-082 2-SI-085 2-SI-088 2-SI-091 2-SI-094 2-SI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 VIRG.INIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11548-CBM-0898 4 OF 4 E-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 11548-CBM-0898 4 OF 4 D-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 11548-CBM-0898 4 OF 4 D-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11548-CBM-089B 4 OF 4 C-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11548-CBM-0898 4 OF 4 B-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11548-CBM-089B 1 OF 4 B-7 CHECK VALVE "A" ACCUMULATOR DISCHARGE CHECK VALVE 11548-CBM-089B 1 OF 4 B-8 CHECK VALVE 11A11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE' 11548-CBM-089B 2 OF 4 B-6 CHECK VALVE 11B11 ACCUMULATOR DISCHARGE CHECK VALVE 11548-CBM-089B 2 OF 4 B-7 CHECK VALVE 11B11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11548-CBM-089B 3 OF 4 B-5 CHECK VALVE 11C" ACCUMULATOR DISCHARGE CHECK VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 6.000 1 6.000 1 6.000 1 6.000 1 6.000 1 12.000 1 12.000 1 12.000 1 12.000 1 12.000 1 AC PIV CV LT AC PIV CV LT C

CV C

CV PAGE:

48 OF 66 REVISION: 00 DATE: 02/24/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 C

C 0

C C

27

o.

C 0

0 0

0 27 27 26 26 26 26 26 4

4 4

4

.4 4

4 4

4 3

3 3

VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2-SI-147 11548-CBM-089B 3 OF 4 B-7 CHECK VALVE 12.000 1 2-SI-150 2-Sl-174 11C11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11548-CBM-089A 3 OF 3 F-6 MAN GLOBE BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG 11548-CBM-089A 3 OF 3 D-6 MAN GLOBE HIGH HEAD SAFETY INJECTION TO RCS

.750 2

.750 2 2-Sl-224 11548-CBM-089B 4 OF 4 F-3 CHECK VALVE

'3.000 2 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 HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 2-SI-226 11548-CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2*Sl-227 11548-CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2*Sl*228 11548-CBM-089B 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 2*S1*229 2-Sl-235 2-Sl-236 2-SI-237 11548-CBM-089B 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11548-CBM-089B 4 OF 4 F-7 CHECK VALVE HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 11548-CBM-089B 4 OF 4 E-7 CHECK VALVE HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECK VALVE 11548-CBM-089B 4 OF 4 D-7 CHECK VALVE 3.000 2 3.000 2 3.000 2 6.000 2 6.000 2 2.000 1 2.000 1 2.000 1 C

CV AE CIV LT AE CIV LT C

CV C

CV PAGE:

49 OF 66 REVISION: DO DATE: 02/24/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 C

C 0

0 0

0 C

0 26 3

4 4

VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 2*SI-MOV-2863B 11548-CBM-089A 2 OF 3 D-3 MO GATE 11911 LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 2-SI-MOV-2864A 11548*CBM-089A 2 OF 3 D-6 MO GATE 11A11 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 2-SI-MOV-2864B 11548-CBM-089A 2 OF 3 D-4 MO GATE 11B11 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 2*SI-MOV-2865A 11548-CBM-089B 1 OF 4 C-7 MO GATE 11A11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-Sl*MOV-2865B 11548-CBM-089B 2 OF 4 C-6 MO GATE 11B11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2*SI-MOV-2865C 11548-CBM-089B 3 OF 4 C-5 MO GATE 11C11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 2-SI-MOV-2867C 11548-CBM-089A 3 OF 3 F-6 MO GATE BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 8.000 2 B

10.000 2 B

12.000 2 B

3.000 2 A

CIV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV LT ST VP PAGE:

52 OF 66 REVISION: 00 DATE: 02/24/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 QC C

0 C

0 OC C

0 C

0 OC C

0 C

0.

OC C

0 C

0 oc C

0 C

0 OC C

0 C

C 0

OC 34 34 34 34 34 34 34*

34 34 34 34 34 18 18 18 18

VALVE NUMBER 2-SW-108 2-SW-113 2-SW-206 2-SW-208 2-SW-246 2-SW-247 2-SW-248 2-SW-249 2-SW-250 2-SW-251 2-SW-252 2-SW-253 VIRGINIA POWER COMPANY.

SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL

. INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11548-CBM-071B 1 OF 2 B-4 CHECK VALVE 2.000 3 CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11548-CBM-0718 1 OF 2 B-7 CHECK VALVE 2.000 3 CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11548-CBM-071A 3 OF 3 E-8 MAN GATE 2.000 2 CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 11548-CBM-071A 3 OF 3 E-8 *MAN GATE 2.000 2 CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 11548-CBM-071A 3 OF 3 D-8 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 3.000 3 11548-CBM-071A 3 OF 3 D-7 CHECK VALVE 3.000 3 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11548-CBM-071A 3 OF 3 D-7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11548-CBM-071A 3 OF 3 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11548-CBM-071A 3 OF 3 D-5 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D-5 CHECK VALVE 3.000 3 3.000 3 3.000 3 3.000 3 3.000 3 3.000 3 C

CV C

CV AE CIV LT AE CIV LT C

CV C

CV PAGE:

59 OF 66 REVISION: 00 DATE: 08/01/95 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C 0

C C

0 0

46 46 46 46

VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE. TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2-SW-442 2-SW-445 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11548*CBM*071B 1 OF 2 B-4 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 11548*CBM*071B 1 OF 2 B-6 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2*SW*MOV*201A 11548*CBM*071A 3 OF 3 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2*SW*MOV*201B 11548*CBM*071A 3 OF 3 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2*SW*MOV*202A 11548*CBM*071A 2 OF 3 D-6 *MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2*SW*MOV*202B 11548*CBM*071A 2 OF 3 D-5 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2*SW-MOV*203A 11548*CBM*071A 3 OF 3 B-8 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2*SW*MOV*203B 11548*CBM*071A 3 OF 3 B-8 MO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2*SW*MOV*203C 11548*CBM*071A 3 OF 3 B-3 MO BFLY 2.000 3 C.

2.000 3 C

36.000 3 B

42.000 3 B

30.000 3 B

CV CV EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP PAGE:

60 OF 66 REVISION: 00 DATE: 08/01/95 NC

. REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV-VCN*

0 0

C C

oc C

C oc C

C oc 0

0 oc 0

0 oc

-~--.----

RELIEF REQUEST V-26 System Safety Injection Valve(s):

2-SI-107 2-SI-128 2-SI-145 category:

c Class 1

2-SI-109 2-SI-130 2-SI-147 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 in the alternate testing section.

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.

4-15 S2PVI3RO Revision O August 1, 1995

I RELIEF REQUEST V-26 (Cont.)

Valves 2-SI..-109, 130 and 147 are closest to the reactor coolant system and are in one group, and valves 2-SI-107, 128 and 145 are in the other group.

The justification for testing these valves*

during reactor refuelings is described in Reactor Refueling Justification RRV-3.

4-16 S2PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-27 system Safety Injection Valve(s):

2-SI-88 2-SI-91 2-SI-94 Category:

C Class 1

2-SI-238 2-SI-239 2-SI-240 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 the leakage limit is exceeded, both valves in the pair will be declared inoperable and subject to repair or replacement.

Note that there is no specified permissible accident leakage limit for these valves.

Therefore, these valves are Category C.

4-17 S2PVI3RO Revision o August 1, 1995

system Valve(s)..

Category..

Class Function..

FW 2-FW-144 2-FW-148 C

3 RELIEF REQUEST V-41 2-FW-159 2-FW-163 2-FW-174 2-FW-178 Auxiliary Feedwater Pump Recirc Line and Pump 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 instrumentation 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.

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 every reactor refueling.

A different valve from each group will be disassembled for each inspection.

If a valve fails its inspection, the remaining valves in the group will be disassembled and inspected

4-20 S2PVI3RO Revision O August 1, 1995

RELIEF REQUEST V-42 system Valve(s) :

category MS 2-MS-176 2-MS-178 2-MS-182 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."

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.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling.

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.

The valves will be full flow tested every three months

4-21 S2PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-46 System..

Service Water Valve(s):

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 r~circulation 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 can be partial stroked open only when service water is sent 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.

Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected every reactor refueling.

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.

4-25 S2PVI3RO Revision o August 1, 1995

RELIEF REQUEST V-47 System Various Valve(s):

Valves affected by this relief request are identified Category:

Class Function:

by Table V-47.

OM Part 10 Code Requirements For Which 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.l.8(b)) and +/-50% for power-operated valves with reference stroke times less than or equal to 10 seconds (4.2.1.8(d)).

Basis For Relief The valves listed in Table V-47 either have no remote indication and no remote control, or no remote open/close control, or the 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 4.2.1.8(b) and (d).

Therefore, timing the full-stroke from the initiation of the actuating signal and applying the acceptance criteria of Paragraphs 4.2.l.8(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 4-27 S2PVI3RO Revision o August 1, 1995

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-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

4-28 S2PVIJRO Revision o August 1, 1995

RELIEF REQUEST V-47 (Cont.)

TABLE V-47 Valve 2-CC-LCV-201 Category Class Function B

3 2-MS-RV-201A,B,C B

2 2-SW-TCV-208A,B,C B

3 S2PVIJRO 4-29 Charging Pump Seal Cooling Surge TanJc Level Control Main steam Header Discharge to Atmosphere PORV Service Water to Charging Pump Lube Oil Cooler Temperature Control Valves Revision o August 1, 1995

S2PVI3RO RELIEF REQUEST V-50 Relief Request Withdrawn 4-31 Revision O August 1, 1995

COLD SHUTDOWN JUSTIFICATION CSV-34 System Safety Injection Valve(s):

2-SI-MOV-2865A 2-SI-MOV-2865B 2-SI-MOV-2865C Category:

B Class 2

Function:

Accumulator Discharge Isolation Valves to RCS Cold Leg Cold Shutdown Justification In accordance with Technical Specification 3.3.A.10, the accumulator discharge isolation valves 2-SI-MOV-2865A, Band C shall be blocked open by de-energizing the valve motor operators when the reactor coolant system pressure is greater than 1000 psig.

These valves could be called upon to close when the reactor coolant system pressure is less than 1000 psig.

If these valves were stroked during power operation and failed in the closed position, the corresponding accumulator would be rendered inoperable and thus decrease plant safety.

Also, the valve controllers do not allow for a part-stroke exercise test.

Testing Frequency These valves will be full stroke exercised to the open and closed positions every cold shutdown but not more frequently than once every three months

4-66a S2PVI3RO Revision O February 24, 1995

System..

REACTOR REFUELING JUSTIFICATION RRV-4 Safety Injection Valve(s):

Valves affected by this request are identified in Category:

Class Function:

Table RRV-4.

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 injection path valves during cold shutdowns when 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, 85, 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.

Therefore, it is impractical to perform a closure test every quarter

4-72 S2PVI3RO Revision O August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

These valves are designated as pressure isolation valves.

Technical Specification Table 4.1-2A 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 4.2.1.2(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 respect, the Technical Specification frequency is more 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.

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.

4-73 S2PVI3RO Revision o August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

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.l-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.l-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 every cold shutdown, a leakage test 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.l-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.l-2A and leakage testing is an alternative that provides an acceptable level of quality and safety.

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.

With low head pump flow, the cold leg injection valves 2-SI-79, 82, 85, 241, 242 and 243 will be acoustically monitored using a sampling plan 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.

4-74 S2PVI3RO Revision o August 1, 1995

REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.)

The sampling plan will follow the recommended alternative testing method described in NUREG 1482, Section 4.1.2.

The valves will be placed into two groups with valves 2-SI-79, 82 and 85 in one group, and valves 2-SI-241, 242 and 243 in the other group.

During initial testing using nonintrusive techniques, each valve in the group will be nonintrusively verified as operable.

During subsequent testing, nonintrusive verification will be performed for only one valve of the group on a rotating schedule each time the testing is performed, and the balance of the group will be flow tested. If problems are found with the sample valve_that are determined to affect the operational readiness of the valve, all valves in the group must be tested using nonintrusive techniques during the same outage.

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 injection paths.

The leakage tests will be performed 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.

4-75 S2PVI3RO Revision o August 1, 1995

REACTOR Valve 2-SI-88, 91 2-SI-94, 238 2-SI-239, 240 2-SI-235 2-SI-236 2-SI-237 2-SI-241 2-SI-242 2-SI-243 2-SI-224, 225 2-SI-226, 227 2-SI-228, 229 2-SI-79, 82, 85 S2PVI3R0 REFUELING JUSTIFICATION RRV-4 (Cont.)

category C

C AC C

C AC TABLE RRV-4 Class 1

1 1

2 2

1 4-76 Function Safety Injection to RCS Hot Legs High Head Safety Injection to RCS Cold Legs Low Head Safety Injection to RCS Cold Legs High Head Safety Injection Check Valve at Containment Penetrations Low Head Safety Injection Check Valves at Containment Penetrations Safety Injection to RCS Cold Legs Revision o August 1, 1995

~J

ML18151A642

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