Text

Rev 0,Change 1 to Surry Unit 1 Third Interval IST Program
	ML18151A614
Person / Time
Site:	Surry
Issue date:	08/04/1994
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18151A617	List: ML18151A614; ML18153B100; ML20076F834;
References
	PROC-940804, NUDOCS 9410180167
	Download: ML18151A614 (81)
	v • d • e

1,,.---------

9410180167 941011

~DR ADDCK 05000280 PDR ATTACHMENT 1 CHANGES TO SURRY UNIT 1 THIRD INTERVAL INSERVICE TESTING PROGRAM REVISION 0 CHANGE 1

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM The following is a section by section summary of changes for Revision o, Change 1 of the Surry Power Station Unit 1 Inservice Testing {IST) Program for the third IST interval.

Revision o for the third IST interval was submitted on October 19, 1993 {Serial No.93-658).

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.5 Unit 1 Pump Number 1-cc-P~.2A 1-CC-P-2B 1-VS-P-lA 1-VS-P-lB 1-VS-P-lC 1-VS-P-lD 1-VS-P-lE 1-VS-P-2D 1-VS-P-2E 3.6 Unit 1 Relief Request P-16 P-17 PUMP INSERVICE TEST TABLES Program Change Relief Request P-22 was added for the suction pressure instrumentation.

Relief Request P-16 was extended per letter NRC dated June 2, 1994 (Serial No.94-324).

and inlet pressure instrumentation have not successfully installed.

to the Flow been These pumps were added to the control room air conditioning system as part of a system upgrade and will be tested every quarter.

PUMP TEST PROGRAM RELIEF REQUESTS Program Change This relief request was extended to the end of the next Unit 1 refueling outage because.flow and inlet pressure instrumentation were not successfully installed.

The next Unit 1 refueling outage is currently scheduled for the third quarter of 1995.

Refer to the letter to the NRC dated June 2, 1994.

Pumps 1-VS-P-2D and E were added.

Like the other pumps in this relief request, the total flow for 2

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM 1-VS-P-2D and E must be determined by summing the recorded flows from instruments placed downstream of the air handling units.

Therefore, throttling to a reference flow is not practical.

A straight line approximation of a small portion of the pump curve will be used to establish the acceptance criteria.

The basis for the original relief request was approved by the NRC SER dated June 26, 1992 (TAC Nos. M80297 and M80298).

P-22 This relief request is being added to the IST Program for the component cooling water pumps 1-cc-P-2A and B.

Recently installed inlet pressure gauges have a full scale range of o to 3.5 psig.

Readings from these inlet pressure gauges over the past year indicate that the dynamic pressures fall within the bottom third of full scale.

However, the difference in the error between the o to 3.5 psig gauges and gauges that would meet the ASME Section XI three times full-scale rule are so small that the Oto 3.5 psig gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.

Therefore, inlet pressure will be measured with gauges that have a full-scale of Oto 3.5 psig.

3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Unit 1 Non-Code Alternative Test PNC-1 Program Change Reference to the frequency response range of the vibration transducers was added.

The minimum pump shaft rotational speed for the diesel fuel oil pumps is 690 rpm.

To meet the one-third shaft speed requirement, the low end of the frequency response range would have to be 3.8 hz.

The transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz.

These transducers are capable of detecting vibrations at frequencies of at least one times the rotational speed of the pump, which is adequate for detecting degradation in positive 3

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM displacement pumps.

A note indicating that OM Part 6 does not require the measurement of suction pressure for positive displacement pumps was added.

4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.4 VALVE INSERVICE TEST TABLES Unit 1 Valve Number Comment/Program Change 1-MS-~V-lOlA 1-MS-NRV-lOlB 1-MS-NRV-lOlC 1-MS-TV-109 1-MS-TV-110 1-CH-LCV-lllSB 1-CH-LCV-1115D l-SI-25 l-SI-MOV-1885A 1-SI-MOV-1885B 1-SI-MOV-1885C 1-SI-MOV-1885D l-SI-25 Program Change:

The ASME Code Classification was changed from Class 2 to non-Code Class.

These isolation valves prevent leakage of contaminated containment sump water to the refueling water storage tank from the discharge side of the low head safety injection pumps during the recirculation mode transfer phase of safety injection.

Relief Request V-52 is being added to the IST program and states that in addition to replacement and repair as corrective actions, an evaluation can be performed.

Relief Request V-52 was sent to the NRC by letter dated April 26, 1994 (Serial No.94-223) and is being included in the IST Program through Change 1 to Revision o.

Program Change:

Relief Request V-52 is being added for the leak test.

The test method to verify valve closure was changed from disassembly and inspection to back seat testing every reactor refueling.

Refer to Reactor Refueling Justification RRV-

5.

Program Change:

Reactor Refueling 4

l-SI-107 1-SI-109 l-SI-128 1-SI-130 1-SI-145 1-SI-147 1-sw-12 l-SW-130 1-SW-313 1-SW-323 1-SW-333 1-SW-773 1-SW-778 l=SW-839 1-SW-840 ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM Justification RRV-5 was revised.

These accumulator discharge check valves will be tested as pairs to the closed position.

Refer to Relief Request V-26.

Program Change:

Relief Request V-26 was revised to indicate that valves l-SI-107 and 109, and 1-SI-128 and 130, and 1-SI-145 and 147 will be tested as pairs of valves in series to the closed position.

Also, Cold Shutdown Justification CSV-29 is no longer necessary for valves l-SI-109, 130 and 147, and was deleted from the program.

This manual valve is being added to the IST program to be tested closed.

This valve is closed to ensure an adequate service water inventory is available for the component cooling heat exchangers.

Program Change:

Valve was added to the program to be tested to the closed position every cold shutdown.

Refer to Cold Shutdown Justification CSV-34.

The internal parts were removed from this check valve.

Program Change:

The valve was removed from the IST program.

Program Change:

Relief Request V-46 was extended for these valves per letter to the NRC dated June 2, 1994.

These control room condenser water system pump discharge check valves were added as part of a system upgrade.

Program Change:

Valves were added to be full*

stroke exercised every three months.

These control room condenser water system discharge check valves were added as part of a system upgrade.

5

1-SW-PCV-lOOD,E l-SW-PCV-101D,E l-VS-286 l-VS-571 l-VS-641 l-VS-645 l-VS-672 ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM Program Change:

Valves were added to be partial stroke exercised every three months and disassembled and inspected on a reactor refueling frequency.

Refer to Relief Request V-53.

These control room condenser water system pressure control valves were added as part of a system upgrade.

Program Change:

Valves were added to be full stroke exercised every three months.

Also, these valves were added to Relief Request v-47 because of limitations on obtaining repeatable stroke times.

The normal position for this valve was changed from closed to open.

It now provides alignment of the control room chilled water system B pump to the C chilled water loop without having to be manipulated.

Therefore, the valve is passive.

Program Change:

The valve was removed from the IST program.

This control room chilled water system manual isolation valve was added as part of a system upgrade.

Program Change:

Valve was added to be exercised every three months.

These control room chilled water system pump discharge check valves were added as part of a system upgrade.

Program Change:

Valves were added to be full stroke exercised every three months.

Valves 1-VS-641 and 645 will be exercised to the open and closed positions and valve 1-VS-672 will be exercised to the open position.

6

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM 4.5 VALVE TEST PROGRAM RELIEF REQUESTS Unit 1 Relief Request V-26 V-46 V-47 Program Change This relief request was revised to indicate that the accumulator discharge check valves will be tested as pairs of valves to the closed position.

Valves 1-SI-107 and 109, 1-SI-128 and 130, and 1-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system.

The downstream valves, 1-SI-109, 130 and 147 were previously chosen as the isolation valves and were subject to back seat tests while the other valves were considered as backup valves and were not subject to back seat tests.

The other set of valves cannot be individually back seated with the current piping configuration.

Testing experience has shown that a severe water hammer can be produced by attempting to individually test the downstream isolation valve.

Treating the check valves as a pair of isolation valves would eliminate the possibility of creating a water hammer event through testing.

The accumulators have level indicators and high/low tank level alarms in the control room.

Therefore, during normal operation the accumulator level is constantly monitored to ensure that one out of two check valves is seated properly to prevent in leakage from the reactor coolant system.

This relief request was extended to the end of the next Unit 1 refueling outage because flow and inlet pressure instrumentation were not successfully installed.

The next Unit 1 refueling outage is currently scheduled for the third quarter of 1995~

Refer to the letter to the NRC dated June 2, 1994.

Valves 1-SW-PCV-lOOD and E, and 1-SW-PCV-101D and E are being added.

These valves have no remote indication or manual remote control.

The valve position is manipulated by venting the actuator 7

V-50 V-52 V-53 ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM 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.

Interim approval to use the original relief request was granted by NRC letter dated February 17, 1994.

Valve 1-SW-130 was removed from the relief request.

This relief request is being added to the IST program for the RWST isolation valves.

The RWST isolation valves prevent leakage of contaminated containment sump water to the refueling water storage tank from the discharge side of the low head safety injection pumps during the recirculation mode transfer phase of safety injection.

Relief Request V-52 states that in addition to replacement and repair as corrective actions, an evaluation can be performed.

Relief Request V-52 was sent to the NRC by letter dated April 26, 1994 (Serial No.94-223) and is being included in the IST Program through Change 1 to Revision o.

This relief request is being added for control room condenser system discharge check valves 1-SW-839 and 840.

The check valves are downstream from the recirculation loops for two of the five trains in the control room condenser water system.

These two trains were added to the control room air conditioning system in 1994 and were designed to operate with a service water temperature of at least 95 °F.

These two trains have such a large cooling capacity that one of the two trains can absorb the heating load of the entire control room air conditioning system.

To maintain this high temperature, these trains must be operated with most of the service water flow diverted to the recirculation lines.

If the flow was diverted to the discharge check 8

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM valves for the purpose of achieving full design flow through the check valves, the service water temperature would drop and the condenser system would trip off line on low condenser suction pressure.

Also, the system heat load balance would be upset.

Therefore, full flowing these check valves while the unit is operating is not practical.

The Surry control room is common to both units.

Performing the full flow test is not practical when either unit is operating.

As an alternate test, these valves will be disassembled and inspected.

These check valves can be disassembled while the plant is operating.

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. The test frequency is in accordance with Generic Letter 89-04, Position 2.

4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS Unit 1 Cold Shutdown Just CSV-29 CSV-34 Program Change This cold shutdown justification is being deleted from the IST program.

The accumulator discharge check valves will be tested as pairs to the closed position per Relief Request V-26.

This cold shutdown justification is being added to the IST program.

The 10 inch manual isolation valve 1-sw-12 isolates service water to the plant chilled water system condensers.

A full stroke test of 1-sw-12 may require that the condensers be secured.

The chilled water system supplies cooling water to the containment coolers for each unit.

The chilled water system is needed during much of the year while the plant is operating to ensure that the containment coolers have enough added capacity to maintain the containment air 9

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM partial pressure within the acceptable operation range as described in Technical Specification Section 3.8, Figure 3.8-1.

Therefore, service water flow should not be interrupted to the chilled water system while the plant is operating.

4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Unit 1 Reactor Refuel Just RRV-3 RRV-5 Program Change Justification was added for not performing a partial stroke test on the accumulator discharge check valves during cold shutdowns.

Reactor Refueling Justification RRV-5 was revised to indicate that l-SI-25 will be back seat/leak tested to verify closure every reactor refueling instead of disassembled and inspected.

10

SURRY POWER STATION UNIT 1 REPLACEMENT PAGES

SlPVIJRO l-SW-P-lA l-SW-P-1B 1-SW-P-lC Emergency Service Water Pumps supply the required service water to the canal to provide for minimum safeguards operation in the unlikely event of a loss of site power coincident with a OBA.

See drawing 11448-CBM-71A, Sheet 1.

1-EE-P-lA 1-EE-P-lC 1-EE-P-1D 1-EE-P-lF Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank.

See drawing 11448-CBB-JSA, Sheet 2.

1-VS-P-1A 1-vs-P-lB 1-vs-P-1c 1-vs-P-10 1-vs-P-lE Main Control Room Air Conditioning System condenser side pumps provide service water to the main control room air conditioning system chillers.

See drawing 11448-CBM-71D, Sheets land 2.

1-VS-P-2A l-VS-P-2B l-VS-P-2C l-VS-P-2D l-VS-P-2E Main Control Room Air Conditioning System chiller side pumps circulated chilled water to the main control room and switch gear room air handling units.

See drawing 11448-CBB-41A, Sheets 2 and 3.

3-5 Revision o August 4, 1994

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 Q

Q Q

NA Q

1,19 1-CC-P-lB 3

VAR Q

Q Q

NA Q

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

VAR Q

Q 0

0 Q

NA NA 1.21 l-CH-P-2B 2

VAR 0

0 Q

Q Q

NA NA 1.21 l-CC-P-2A 3

VAR 0

0 0

NA NA 1._22

~.

~

l-CC-P-2B 3

VAR 0

0 0

Q 0

NA NA 1,22

~

1-SW-P-lOA 3

VAR 0

0 0

Q 0

NA NA 1

1-SW-P-lOB 3

VAR Q

Q Q

Q 0

NA NA 1

1-SW-P-lA 3

FIX 0

NA 0

0 0

Q 0

1.11 1-SW-P-lB 3

FIX Q

NA 0

0 Q

0 0

1, 11 1-SW-P-lC 3

FIX 0

NA 0

Q Q

0 Q

1.11 1-EE-P-lA NC FIX NA 0

NA Q

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

NA 0

Q NA NA 1.PNC-1 1-EE-P-lD NC FIX NA 0

NA Q

0 NA NA 1,PNC-1 1-EE.:.P-lF NC FIX NA 0

NA Q

0 NA NA 1,PNC-1 Note:

PNC-1 is not a request for relief but a description of alternative testing for non-code pumps.

Refer to section 3.7.

3-9 Revision o SlPVIJRO August 4, 1994

Pump ASME System Inlet Disch

!dent.

Class Resist Press Press 1-VS-P-lA 3

VAR NA Q

1-VS-P-lB 3

VAR NA Q

1-VS-P-lC 3

VAR NA Q

1-VS-P-lD 3

VAR Q

Q 1-VS-P-lE 3

VAR Q

Q 1-VS-P-2A 3

VAR Q

Q 1-VS-P-2B 3

VAR Q

Q 1-VS-P-2C 3

VAR Q

Q l-VS-P-2D 3

VAR Q

Q 1-VS-P-2E 3

VAR Q

Q S1PVIJRO PUMP INSERVICE TEST TABLE Diff Flow

.Pump Press Rate Vibration Speed NA NA Q

NA NA NA Q

NA Q

Q Q

NA Q

Q Q

NA Q

Q Q

NA Q

Q Q

NA Q

Q Q

NA Q

Q Q

NA Q

Q Q

NA 3-10 Lubrication Relief Level/Pressure Request NA 1.16 NA 1.16 NA 1.16 NA 1

NA 1

NA 1.17 NA 1.17 NA 1.11 NA 1117 NA 1.11 Revision O August 4, 1994

~

I <

\\J

....i 1

~

'-.I

RELIEF REQUEST P-17 System:

Main Control Room Air Conditioning Pump(s):

l-VS-P-2A 1-VS-P-2B 1-VS-P-2C 1-VS-P-2D 1-vs-P-2E Class 3

OM Part 6 Code Requirements For Which Relief Is Reguested 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 Reguest The chilled water circulating pumps for the main control room air conditioning system service two trains each with of four air handling units connected in a parallel configuration.

Total flow for each pump is determined by summing the recorded flows from flow instruments placed downstream of the four air handling units in one of the trains.

Test flow is controlled by throttling a gate valve near each air handling unit, which has proven to be a crude flow control method.

Having to throttle to a specific reference flow using the sum of flows from four instruments with a gate valve that is not suited for fine flow control is not very practical.

Alternate Testing Proposed Two reference points of total flow versus differential pressure will be established from the reference test for each pump.

A straight line approximation will be used to determine differential pressure reference points as a function of flow between the two test points.

By keeping the difference between two test points small (a difference of 30 gpm compared to a nominal reference value of 270 gpm), the straight line is a good approximation of the pump.curve within the two test points.

During the subsequent tests, flow will be throttled *in each parallel path as close as practical to a reference flow value for that path.

The total flow must fall between the two reference points used to establish the straight line approximation.

The total flow and the corresponding differential pressure will be 3-24 S1PVI3RO Revision O August 4, 1994

~

I

'RELIEF REQUEST P-22 system:

Component Cooling Water Pump(s):

l-CC-P-2A l-CC-P-2B Class 3

OM Part 6 Code Requirements For Which Relief Is Requested The full-scale range of each instrument shall be three times the reference value or less -(OM Part 6, Paragraph 4. 6.1. 2)

Basis For Request Recently installed inlet pressure gauges have a full scale range of o to 3.5 psig.

Readings from these.inlet pressure gauges over the past year indicate that the dynamic pressures fall within the*

bottom third of full scale.

However, the difference in the *error between the Oto 3.5 psig gauges and gauges that would meet the three times full-scale rule are so small that the Oto 3.5 psig gauges can be considered *to be equivalent in terms of accuracy for determining differential pressure.

For example, the lowest recorded inlet pressure for pump 1-cc-P-2B is o.s psig.

A gauge that meets the three times full-scale rule would have a full scale of 2.4 psig or less.

A 2% accuracy for the 2.4 psig gauge translates to an error of 0.05 psig.

A 2%

accuracy for the 3.5 psig gauge translates to an error of 0.07 psig.

The difference in error of 0.02 psig is insignificant when determining the differential pressures for these pumps which range between 50 and 60 psig.

Therefore, the two gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.

Alternate Testing Proposed Inlet pressure will be measured with gauges that have a full-scale of o to 3.5 psig.

3-3la S1PVI3RO Revision o August 4, 1994

NON-CODE ALTERNATIVE TESTING PNC-1 system:

Pwnp(s):

Class Fuel Oil 1-EE-P-lA 1-EE-P-lC 1-EE-P-1D 1-EE-P-lF NC OM Part 6 Code Requirements Which cannot Be Met Measure test quantities after the pump has been running for at least two minutes (OM Part 6, Paragraph 5.6).

The frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimwn pump shaft rotational speed to at least 1000 HZ (OM Part 6, Paragraph 4.6.1.6).

Basis For Alternate Testing The pump operating time is limited due to operational restraints.

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

The pump run time can vary depending upon the diesel load and the resulting fuel conswnption rate. If the pumps are allowed to run for two minutes prior to measuring the test quantities and the fuel consumption rate is low, not enough time is available to gather all of the required Section XI test data.

The minimum pump shaft rotational speed for these pumps is 690 rpm.

To meet the one-third shaft speed requirement, the low end of the frequency response range would have to be 3.8 hz.

The transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz.

These transducers are capable of detecting vibrations at frequencies of at least one times the rotational speed of the pump, which is adequate for detecting degradation in positive displacement pumps.

Alternate Testing The measurement of Section XI quantities will begin when the pump.

automatically starts on a low tank level signal.

'l'he transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz versus the 3.8 hz required by the Code for a pump running at 690 rpm.

3-33 S1PVI3RO Revision O August 4, 1994

NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)

Note:

The diesel oil transfer pumps are positive displacement pumps.

According to OM Part 6, Table 2, only discharge pressure need be measured for positive displacement pumps.

3-34 S1PVI3RO Revision o August 4, 1994

VIRGINIA POWER C04PANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NLl4BER DRA\\IING NLl4BER SHEET DR\\IG VALVE NL14BER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE

c* CHARGING PUMP DISCHARGE RECIRC LINE CHEC(

VALVE 1-CH-276 11448-CBM-0888 2 OF 3 D-4 CHEC( VALVE

c* CHARGING PUMP DISCHARGE CHEC( VALVE 1*CH-309 11448*CBM*D88C 1 OF 2 D*4 CHECK VALVE MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN-MENT ISOLATION CHECK VALVE 1*CH-FCV*1113A 11448-CBM-0888 1 OF 3 C-3 AO GLOBE MANUAL EMERGENCY &ORATION PATH FLCI\\I CONTROL VALVE 3-000 2 3.000 2 1.000 2 1*CH*FCV-1114A 11448-CBM-0888 1 OF 3 C-4 AO GLOBE 2.000 2 PRIMARY GRADE WATER SUPPLY TO BORIC ACID BLENDER ISOLATION VALVE 1-CH*FCV-1160 11448*CBM*D88C 1 OF 2 B*4 AO GLOBE CHARGING FLCI\\I CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CH-LCV-11151 11448-CBM-0888 2 OF 3 B-8 NO GATE CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING YATER STmlAGE TANK 1-CH-LCV-1115C 11448-CBM-0888 1 OF 3 C*6 NO GATE CHARGING PUMP SUPPLY I SOLA Tl ON FROM VOLlJIE CONTROL TANK 1-CH-LCV-1115D 11448-CBM-0888 2 OF 3 C-8 NO GATE 2.000 1 8.000 2 4.000 2 8.000 2 C

CV AC CIV CV LT B

B EV FS ST VP EV FS ST VP AE CIV LT VP A

B A

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

8 OF 70 REVI SIOlil: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C C

0 0

0 oc C

C C

oc C

0 C

C 0

oc C

C oc C

0 C

C 0

oc 52 52 11 11 6

1 tj I <

<:J

~

\\ <

"-.]

VIRGINIA POMER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE VALVE NUMBER 1-MS-087 1*MS-120 1-MS-158 1*MS*176 1-MS-178 1-MS-182 DRAIJING NUMBER SHEET DRIJG VALVE NUMBER COOR TYPE 11448*CBM*064A 1 OF 6 C-6 MANUAL GATE MAIN STE.AM LINE TO TURBINE DRIVEN AUXILARY FEEDWATER PUMP.ISOLATION VALVE 11448*C8M*064A 2 OF 6 C-6 MANUAL GATE MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ISOLATION VALVE 11448*C8M*064A 3 OF 6 C-6 MANUAL GATE MAIN STE.AM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ISOLATION VALVE 11448*C8M*064A 4 OF 6 C-7 CHECK VALVE

Au MAIN STE.AM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER IUIP 11448*C8M*064A 4 OF 6 Da7 CHECK VALVE us* MAIN STEAM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 11448*C8M*064A 4 OF 6 D*7 CHECK VALVE

c* MAIN STE.AM HEADER SUPPLY CHECK VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 4.000 2 B

EV 4.000 2 B

EV 3.000 2 C

CV 3.000 2 C

CV 1*MS*NRV*101A 11448*CBM*064A 1 OF 6 E-4 NO STOP CHECK 30.000 NC C

CV VP

A* MAIN STE.AM HEADER NON-RETURN VALVE 1-MS*NRV-1018 11448*CBM*064A 2 OF 6 D-3 NO STOP CHECK 30.000 NC C

a* MAIN STE.AM HEADER NON-RETURN VALVE 1*MS*NRV*101C 11448*CBM*064A 3 OF 6 D-3 NO STOP CHECK

c* MAIN STE.AM HEADER NON-RETURN VALVE 1*MS*PCV*102A 11448*CBM*064A 4 OF 6 C-4 AO GATE MAIN STEAM SUPPLY TRIP VALVE TO TURBIWE DRIVEN AUXILIARY FEEDIJATER IUIP 30.000 NC C

3.000 2 B

CV VP CV VP EV FS ST VP PAGE:

34 OF 70 REVISIOII: 00 DATE: 08/04/94 NC REL CS AR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV-VCN-C C

C C

0 C

0 42 42 C

32 DC C

DC C

0 C

C 0

DC 32

VALVE NIMBER 1*MS*TV-101B DRAIIING NLMBER VIRGINIA POWER CCJ4PANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRIIG VALVE NLMBER COOR TYPE ISO VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448*C8M*D64A 2 OF 6 C*4 AO CHECK VALVE 30.000 2 B

EV ST VP

a* MAIN STEAM HEADER TRIP VALVE 1*MS*TV*101C 11448*C8M*064A 3 OF 6 C-4 AO CHECK VALVE 30.000 2 B

c* MAIN.STEAM HEADER TRIP VALVE 1*MS*TV*109 1*MS*TV*110_

11448*CBM*064A 4 OF 6 F-5 AO GATE MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO CONDENSER 11448*CBM-064A 4 OF 6 F-7 AO GATE MAIN STEAM HIGH PRESSURE DRAIN ISOLATic>>i TO STEAM GENERATOR BLCl.llOIJN SYSTEM 3.000 NC B

2.000 NC B

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

37 OF 70 REV! Slc>>i: DO DA TE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VCN*

C C

oc C

C oc C

C C

oc C

C C

oc

,,-1 I z

<....)

-I I <

'-..I

VALVE NI.MBER 1-Sl-025 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NI.MBER SHEET DRWG VALVE NI.MBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-D89A 1 OF 3 F-5 CHECK VALVE 8.000 2 RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER AC CV LT 1-Sl-032 11448-CBM-D89A 1 OF 3 E-7 NAN GLOBE ACCUIJLATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 1.000 2 AE CIV LT 1-SI-046A 1-SI-0468 1-SI-047 1-Sl-050 1-SI-053 1-SI-056 1-SI-058 1-Sl-061 1-Sl-073 1-SI-079 11448-CBM-089A 1 OF 3 A-3 CHECK VALVE RWST SUPPLY CHECK VALVE TO *A* LOW HEAD SI PlMP SUCTION 11448-CBM-D89A 1 OF 3 B-3 CHECK VALVE RWST SUPPLY CHECK VALVE TO *e* LOW HEAD SI PUMP SUCTION 11448-CBM-089A 1 OF 3 B-5 CHECK VALVE 12.000 2 12.000 2 12.000 2

e11 LOW HEAD SI FUIP SUCTION CHECK VALVE FROM CONTAINMENT Sl.MP 11448-CBM-089A 1 OF 3 C-4 CHECK VALVE "B" LOW HEAD SI PlMP DISCHARGE CHECK VALVE 11448-CBM-089A 2 OF 3 B-4 CHECK VALVE

e* LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE DISCHARGE CHECIC VALVE 11448-CBN-089A 1 OF 3 B-7 CHECK VALVE "A" LOW HEAD SJ PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 11448-CBM-089A 1 OF 3 C-6 CHECK VALVE

A" LOW HEAD SJ PlMP DISCHARGE CHECK VALVE 11448-CBN-089A 2 OF 3 B-6 CHECK VALVE

A11 LOW HEAD SJ PUMP NJNIMlJC FLOW/TEST LINE DISCHARGE CHECK VALVE 11448-CBN-089A 2 OF 3 F-7 NAN GLOBE ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-089B 4 OF 4 F-7 CHECK VALVE 10.000 2 2.000 2 12.000 2 10.000 2 2.000 2

.750 2 6.000 1 C

CV C

CV AE CIV LT AC PIV CV PAGE:

49 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C C

0 0

0 C

0 0

0 C

0 0

C C

0 52 20 20 5

5 2

2 2

2 4

4 c.J

VALVE NLMBER 1-SI-079 DRAIJING IUCSER VIRGINIA P<IIER COMPANY SURRY UNIT 1 THIRD JNSERVICE TESTING INTERVAL JNSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRIJG VALVE NLMBER COOR TYPE ISO VAL VE ASME UN VAL VE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-0898 4 OF 4 F-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 6.000 1 AC PIV LT 1-SI-082 11448-CBM-0898 4 OF 4 E-7 CHECK VALVE RCS COLD LEG SI ADMISSION CHECK VALVE 6-000 1 AC PIV CV LT 1-SJ-085 11448-CBM-0898 4 OF 4 D-7 CHECK VALVE RCS COLD LEG SJ ADMISSION CHECK VALVE 6.000 1 AC PJV CV LT 1-SJ-088 1-SI-091 1-SI-094 1-SI-107 1-SI-109 1-51-128 1-SI-130 11448-CBM-0898 4 OF 4 D-7 CHECIC VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11448-CBM-0898 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 11448-CBM-089B 1 OF 4 B-7 CHECK VALVE "A" ACCUMULATOR DISCHARGE CHECK VALVE 11448-CBM-0898 1 OF 4 B-8 CHECK VALVE

A* ACClKILATOR COLD LEG ADMISSION CHECK VALVE 11448-CBM-089B 2 OF 4 B-6 CHECIC VALVE

e* ACCUMULATOR DISCHARGE CHECK VALVE 11448-CBM-0898 2 OF 4 B-7 CHECK VALVE

s* ACCUMULAT~ COLD LEG h!>MISS!ON CHECK VALVE 6.000 1 C

CV 6.000 1 C

CV 12.000 1 C

CV PACE:

50 OF 70 REVISIOII: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV* VCN*

C C

0 C

C 0

C C

0 C

0 27 27 27 26 26 26 26 26 4

4 4

4 3

3 26 3

26 26 3

VALVE NLMSER 1-Sl-145 DRAIIING NlMBER VIRGINIA P<IIER COMPANY SURRY UHIT 1 THIRD INSERVICf TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRIIG VALVE NUMBER COOR TYPE ISO VALVE ASME IW VALVE TEST SIZE ClASS CAT TYPE TYPE 11448-CBM-0898 3 OF 4 B-5 CHECK VALVE 12.000 1 C

CY

c* ACCUMULATOR DISCHARGE CHECK VALVE 1*Sl*147 11448-CBM-0898 3 OF 4 B-7 CHECK VALVE

c* ACCUNJLATDR COLD LEG ADMISSION CHECK VALVE 12.000 1 C

CV 1*Sl*150 11448*CBM*D89A 3 OF 3 F-6 NAIi GLOBE BORON INJECTION TANK BYPASS LINE JSOlATJON VALVE - TD RCS COLD LEG

.750 2 AE CIV LT 1*Sl*174 1-Sl *224 1*Sl*225 1-Sl-226 1-Sl-227 1*Sl*228 1-Sl-229 1-Sl-234 1-Sl-235 11448*CBM*D89A 3 OF 3 D-6 NAN GLOBE HIGH HEAD SAFETY INJECTION TO RCS 11448*CBM*D89B 4 OF 4 F-3 CHECK VALVE HIGH HEAD SJ FRCII CHARGING PlJ4PS TO RCS COLD LEGS, JIISJDE CONT CHECK VALVE 11448-CBM-0898 4 OF 4 E-3 CHECK VALVE HIGH HEAD SI FRCII CHARGING PlJ4PS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 11448-CBM-0898 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FRCII CHARGING PlJIPS TO RCS HOT LEGS, JNSJDE_CONT CHECK VALVE 11448*C8M*D89B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SI FRCII CHARGING PlJCPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448*CBM-089B 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FRCII LHSI PlJ4P TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 11448-CBM-0898 4 OF 4 B-3 CHECK VALVE LOW HEAD SI FRCII LHSI PlJ4P TD RCS HOT LEGS, JNSJDE CONT CHECK VALVE 11448-CBM-0898 1 OF 4 F-3 CHECK VALVE NITROGEN SUPPLY TO ACClMULATDRS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 1144S*CB14*089S 4 OF 4 F-7 CHECIC VAL\\'!:

.750 2 3.000 2 3.000 2 3.000 2 3.000 2 6.000 2 6.000 2 1.000 2 2.000 1 AE CIV LT C

CV C

CY C

CV C

CY C

CV C

CV AC CIV CV LT C

CY PAGE:

51 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VOi-C 0

C 0

C C

0 0

C C

C 0

26 26 26 26 3

3 4

4 4

4 6

4 4

cJ

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE VALVE NUMBER DRAYING NUMBER SHEET DRYG VALVE NUMBER COOR TYPE 1-SJ-MOV-18671>

11448-CBM-D89A 3 OF 3 F-6 MO GATE HIGH HEAD SAFETY INJECTION TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1869A 11448-CBM-D89A 3 OF 3 D-7 MO GATE HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-NOV*18698 11448-CBM-D89A 3 OF 3 E-4 MO GATE HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1885A 11448-CBM*D89A 2 OF 3 8*6 MO GATE

A* LOIJ HEAD SI PUMP MINIMUM FLOIJ/TEST LINE ISOLATION 1-Sl*MOV-1885&

11448-CBM*D89A 2 OF 3 8*4 NO GATE

e* LOIJ HEAD SI PUMP MINIMUM FLOIJ/TEST LINE ISOLATION 1-SI-MOV-1885C 11448-CBM*D89A 2 OF 3 8*4 NO GATE

e* LOIJ HEAD SI PUMP MINltlJN FLOIJ/TEST LINE ISOLATION 1-SI-MOV-1885D 11448*CBM*D89A 2 OF 3 8*6 NO GATE ISO VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 A

3.000 2 A

2.000 2 A

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

55 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN*

C 0

C C

0 oc C

0 C

C 0

oc C

0 C

C 0

oc C

C 52 C

DC C

C C

oc C

52 C

oc C

C 52 C

oc 18 18 18 18 25 25 25 25 25 25 25 25

~

I

<..J

~

CJ

VALVE NlMBER 1-SW-012 VIRGINIA PaJER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NlMBER SHEET DRWG VALVE NlMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-C8'4-071A 2 OF 4 C-4 MANUAL BFLY SERVICE WATER SUPPLY HEADER TD CHILLED WATER SYSTEM MANUAL ISOLATION VALVE 10.000 3 B

EV 1-SW-108 11448*C8'4*071B 1 OF 2 B-4 CHECK VALVE 2.000 3 C

CV CHARGING PlllP SERVICE WATER PI.IIP CHECK VALVE 1-SW-113 11448*CBM-071B 1 OF 2 B-7 CHECK VALVE 2.000 3 C

CV CHARGING PlllP SERVICE WATER PlJ4P CHECK VALVE 1-SW-206 1-SW-208 11448-CSM-071A 3 OF 4 E-8 NAN GATE CONTAINMENT ISOLATIDN VALVE FDR SERVICE WATER DRAINS TO HEAT EXCHANGER 11448-CBM-071A 3 OF 4 E-8 NAN GATE CONTAINMENT ISOLATION VALVE FDR SERVICE WATER DRAINS TO HEAT EXCHANGER 2.000 2 Af CIV LT 2.000 2 Af CIV LT PAGE:

61 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCM-C C

0 C

D C

C 34 50 50 1-SW-246 11448-C8'4-071A 3 OF 4 C-8 CHECK VALVE 3.000 NC C

CV.

0 1-SW-247 1-SW-248 1-SW-249 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-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*C8'4-071A 3 OF 4 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 3.000 3 C

3.000 NC C

3.000 3 C

- - ---------------) ---------------------------------------- ----- ----- ---

1 *SY-250 1-SW-251 1-SW-252 11448-C8'4-071A 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 NC C

3.000 3 C

3.000 NC C

CV D

CV 0

CV D

VIRGINIA POl,IER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL JNSERVJCE TESTING PROGRAM - VALVE TABLE ISO VALVE NIMBER DRAWING NIMBER SHEET DRWG VALVE NIMBER COOR TYPE VALVE ASHE JWV VALVE TEST SIZE CLASS CAT TYPE TYPE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 1-SW-253 11448-Clll4-071A 3 OF 4 D-4 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 3.000 3 C

1-SW-262 11448-Clll4-071B 1 OF 2 8*4 CHECK VALVE CHARGING PllCP SERVICE WATER PllCP DISCHARGE CHECK VALVE 2.000 3 C

1-SW-263 1-SW-264 1-SW-265 11448*Clll4*071D 1 OF 1 C*7 AD GATE CONTROL ROCJI CONDENSER WATER SELF CLEANING STRAINER ISOLATION VALVE 11448*CBM*071D 1 OF 1 C*S MANUAL &FLY CONTROL ROCJI CONDENSER WATER TO BACKUP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-0710 1 OF 1 C*7 MANUAL &FLY 6.000 3 E

6.000 3 B

1-SW-268 1-SW-313 1 *SW-323 1-sw-m CONTROL ROCJI CONDENSER WATER TO BAcnJP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-0718 1 OF 2 8*6 CHECK VALVE CHARGING PllCP SERVICE WATER PllCP DISCHARGE CHECK VALVE 11448-CBM-0710 1 OF 1 F-7 CHECK VALVE CONTROL ROCJI CONDENSER WATER SYSTEM PlJIIP DISCHARGE CHECK VALVE 11448*CBM*071D 1 OF 1 F*S CHECK VALVE CONTROL ROCJI CONDENSER WATER SYSTEM PlJCP DISCHARGE CHECK VALVE 11448-FM *071D 2 OF 2 C*S CHECK VALVE CONTROL ROCJI CONDENSER ~ATER SYSTEM PlJCP DISCHARGE CHECK VALVE 1-sw-ns 11448-FM -0710 2 OF 2 C-4 CHECK VALVE CONTROL ROCJI CONDENSER WATER SYSTEM PlJIIP DISCHARGE CHECK VALVE 1-SW-839 11448-FM *071D 2 OF 2 F-5 CHECK VALVE CONTROL ROCJI CONDENSER WATER SYSTEM DISCHARGE CHECK VALVE

D*aa*~--------------------

1-SW-840 1144B*FM *071D 2 OF 2 F-4 CHECK VALVE 2.000 3 C

3.000 3 C

4.000 3 C

3.000 3 C

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

62 OF 70 REVISIOli: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS v-csv-RRV-vc~-

0 0

50 oc 0

0 0

50 0

46 0

0 0

53 0

53

VIRGINIA Pa.lER COMPANY SURRY UNIT 1 THIRD INSERVICE.TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO VALVE NLJIBER DRAIJING NIMBER SHEET DRIJG VALVE NLJIBER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE CONTROL ROOM CONDENSER WATER SYSTEM DISCHARGE CHECK VALVE 1*S1J*M0V*101A 11448*CBM-071A 3 OF 4 B-4 NO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 36.000 3 B

1-SIJ*MOV*101B 11448*CBM-071A 3 OF 4 B-4 NO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 36.000 3 B

1-SW-MOV-102.A 11448*CBH*071A 2 OF 4 D-6 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1*SW*M0V*102B 11448*CBH*071A 2 OF 4 D*S NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1*SIJ*MOV*103A 11448*CBH*071A 3 OF 4 B-8 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1*S1J*MOV*103B 11448*CBH*071A 3 OF 4 B-8 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1*SW*NOV*103C 11448*CBH*071A 3 OF 4 B-3 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1*SW*NOV*103D 11448*CBH*071A 3 OF 4 B-2 NO BFLY 42.000 3 B

42.000 3 B

30.000 3 B

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

63 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VCN*

C C

DC C

C DC C

0 C

0 DC C

0 C

0 DC 0

0 DC

VIRGINIA POJER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NIMBER DRAWING NIMBER SHEET DR\\IG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-NOV-104A 11448-CBM-071A 3 OF 4 D-7 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *A* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE B

1-S\\I-NOV-104B 11448-CBM-071A 3 OF 4 D-6 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *a* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-S\\I-MOV-104C 11448-CBM-071A 3 OF 4 D-5 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *c* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-NOV-104D 11448-CBM-071A 3 OF 4 D-4 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *D* 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* RECJRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1*SW-MOV-105B 11448*CBM-071A 3 OF 4 D-7 NO BFLY 24.000 3 24.000 3 SERVICE WATER RETURN FROM *s*:'RECJRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV*105C 11448-CBM*071A 3 OF 4 D-6 MO BFLY 24.000 3 B

B B

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

64 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN-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

0 oc C

0 C

VIRGINIA PCIIER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE VALVE NlMBER DRAIJING NlMBER SHEET DRIJG VALVE NLMBER COOR TYPE 1*SW*NOV-105C 1144S*CBM*071A 3 OF 4 D-6 NO BFLY SERVICE WATER RETURN FRc:>>4 *c* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 24.000 3 B

ST VP 1*S1J*NOV*105D 1144S*CBM*071A 3 OF 4 D*S NO BFLY SERVICE WATER RETURN FRc:>>4 "I)* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 24.000 3 B

1*S1J*PCV*100A 1144S*CBM*071D 1 OF 1 F-7 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SIJ*PCV*100B 1144S*CBM*071D 1 OF 1 F*S AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*S1J*PCV-100C 1144S*CBM*071D 1 OF 1 F*3 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SIJ-PCV-1000 11448-FM -071D 2 OF 2 F*S AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*SIJ*PCV-100E 11448-FM -071D 2 OF 2 F*4 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*SIJ-PCV-101A 1144S*CBM-071D 1 OF 1 E*S AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*SIJ-PCV-101B 1144S*CBM-071D 1 OF 1 E-6 AO GATE 3.000 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 PAGE:

65 OF 70 REVISlc>>I: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV-RRV-VCN-0 oc:

C 0

oc:

0 0

O*

0 0

C C

47 47 47 47 47 47 47

~

~-

(.J

---~~---~ -

VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE VALVE NUMBER DRAIJING NIJMBER SHEET DRIJG VALVE NIJMBER COOR TYPE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE ISO VALVE ASME II.IV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-S1J-PCV*101C 11448-CBH-071D 1 OF 1 E-4 NJ GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1*S1J*PCV*101D 11448-FM *071D 2 OF 2 D-5 NJ GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-101E 11448-FM *071D 2 OF 2 D-3 NJ GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 3.000 3 3.000 3 3.000 3 1-SW-TCV-108A 11448-CBH-071B 1 OF 2 E-7 NJ GATE 1.500 3 SERVICE WATER TO CHARGING PlllP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1-SIJ*TCV-1088 11448*C1111*071B 1 OF 2 E*S NJ GATE SERVICE 1./ATER TO CHARGING PlllP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1*SW*TCV*10SC 11448-CBM-071B 1 OF 2 E-4 NJ GATE 2*SW*333 SERVICE WATER TO CHARGING PlllP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 11448-CBM-071D 1 OF 1 F-3 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECIC VALVE 1.500 3 1.500 3 3.000 3 B

B B

B C

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

65A OF 70 REVISIOH: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VCN*

C C

C 0

0 0

47 47 47 47 0

47 0

0 0

47 D

46

,:2 C,.)

VALVE NUMBER 1-VS-285 VIRGINIA P<l'o'ER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZf CLASS CAT TYPE TYPE 11448-FB *041A 2 OF 2 C-6 MANUAL GATE CONTROL ROOM CHILLED WATER CROSS TIE ISOLATION VALVE 3.000 3 B

EV 1-VS-288 11448-FB *041A 2 OF 2 B-7 CHECI( VALVE CONTROL ROOM CHILLED WATER PUMP DISCHARGE CHECI( VALVE 2.000 3 1-VS-292 11448-FB *041A 2 OF 2 B-5 CHECI( VALVE CONTROL ROOM CHILLED WATER PUMP DISCHARGE CHECIC VALVE 2.000 3 1-VS-296 11448-FB *041A 2 OF 2 B-4 CHECI( VALVE CONTROL ROOM CHILLED WATER PU4P DISCHARGE CHECK VALVE 2.000 3 C

CV C

CV 1-VS-571 11448-FM *041A 2 OF 3 C-7 MAN GATE CONTROL ROOM CHILLED WATER SYSTEM HEADER CROSS CONNECT ISOLATION VALVE 3.000 3 B

EV 1-VS-641 11448-FM *041A 3 OF 3 D-6 CHECK VALVE 4.000 3 C

CV 1-VS-645 1-VS-672 CONTROL ROOM CHILLED WATER SYSTEM PU4P DISCHARGE CHECI( VALVE 11448-FM *041A 3 OF 3 D-5 CHECI( VALVE CONTROL ROOM CHILLED WATER SYSTEM PUMP DISCHARGE CHECK VALVE 11448-FM *041A 3 OF 3 F-6 CHECK VALVE CONTROL ROOM CHILLED WATER SYSTEM DISCHARGE HEADER CHECI( VALVE 1*VS-MOV-100A 11448-CBB-OD6A 1 OF 2 C-4 NO BFLY CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT ISOLATION VALVE 1*VS*MOV-100B 11448-CBB*OD6A 1 OF 2 C-3 MO BFLY 4.000 3 4.000 3 36.000 2 36.000 2 CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE.

1-VS*MOV-100C 11448*CBB*0D6A 1 OF 2 D-4 NO BFLY 36.000 2 C

CV C

CV AE CIV LT VP AE CIV LT VP AE CIV LT VP.

PAGE:

69 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST P0S V*

CSV* RRV-VCN-C 0

C 0

0 C

oc C

DC C

oc

""4

~

I;,.)

VALVE NLJ4BER DRAWING 111.IIBER VIRGINIA POWER CCMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASMf IW VALVE TEST SIZE CLASS CAT TYPE TYPE CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLATION VALVE 1*VS*MOV*100D 11448*CBB*006A 1 OF 2 0*3 MO BFLY 36.000 2 AE CIV LT VP CONTAINMENT PURGE EXHAUST, OUTSIDE CONTAIN*

MENT ISOLATION VALVE 1-VS*MOV-101 1*VS*MOV*102 11448*CBB*D06A 1 OF 2 D-3 NO BFLY CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT ISOLATION VALVE 8.000 2 11448*CBB*006A 1 OF 2 C-3 MO BFLY 18.000 2 CONTAINMENT VAClAM BREAKER AE CIV LT VP AE CJV LT VP PAGE :

70 OF 70 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST P0S V*

CSV-RRV-VCN-C oc C

oc C

oc

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

l-SI-107 l-SI-128 l-SI-145 category:

c Class l

l-SI-109 l-SI-130 l-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 Exercise to the Open Position 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.

Exercise to the Closed Position Valves l-SI-107 and 109, l-SI-128 and 130, and l-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system.

The downstream valves, l-SI-109, 130 and 147 were previously chosen as the isolation valves and were subject to back seat tests while the other valves were 4-15 S1PVI3RO Revision o August 4, 1994

RELIEF REQUEST V-26 (Cont.)

considered as backup valves and were not subject to back seat tests.

The other set of valves cannot be individually back seated with the current piping configuration.

Testing experience has shown that a severe water hammer can be produced by attempting to individually test the downstream isolation valve.

To individually test these valves, a reactor coolant system pressure in excess of 1000 psi was needed to properly seat the valves.

The line upstream was then vented using a 3/4 inch sample line.

Flow in the sample line was monitored to verify that the check valve seated.

Also, the accumulator was isolated by the upstream motor operated isolation valve.

During one test, a steam bubble was created in the volume of pipe upstream of the check valve due to the initial high pressure and temperature in the line, and due to the subsequent venting of the line and the flashing of water to steam.

When the motor operated isolation valve was opened following the test to restore the accumulator to service, a severe water hammer was created by the collapsing steam bubble.

Although less severe hydraulic transients had been observed in previous tests, the potential for system damage became obvious after this test.

Other test methodologies were evaluated to determine if valve closure could be verified while reducing or eliminating the possibility of creating another water hammer event.

For example, testing at a lower reactor coolant temperature and pressure reduces the amount of water flashing to steam.

However, testing has shown that the check valves do not seat properly at reactor coolant system pressures less then 1000 psi. It was concluded that with the current system configuration, a test could not be designed that would meet these criteria.

Treating the check valves as a pair of isolation valves would eliminate the possibility of creating a water hammer event through testing.

The accumulators have level indicators and high/low tank level alarms in the control room.

Therefore, during normal operation the accumulator level is constantly monitored to ensure that one out of two check valves is seated properly to prevent in leakage from the reactor coolant system

4-16 S1PVI3RO Revision o August 4, 1994 I <

~

RELIEF REQUEST V-26 (Cont.)

Alternate Testing Proposed Exercise to the Open Position 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.

Valves l-SI-130 and 147 are in one group and valves l-SI-107, 109, 128 and 145 are in the other group.

Because 1-SI-130 and 147 are downstream from where RHR connects to the SI line, they experience different service conditions than the other valves.

The justification for testing these valves during reactor refuelings was moved to Reactor Refueling Justification RRV-3 Exercise to the Closed Position Valves 1-SI-107 and 109, 1-SI-128 and 130, and 1-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system.

Monitoring the accumulator level during normal operation will be an adequate demonstration that one out of two valves in series is seating properly.

If leakage past both valves in series to the accumulators becomes unacceptable for normal operation, both valves will be declared inoperable.

The check valves will not be individually tested to the closed position.

4-16a S1PVI3RO Revision O August 4, 1994

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-RH-FCV-1605 and 1-RH-HCV-1758 are controlled by a potentiometer and have no remote indication.

The stroke time is measured by locally observing stem movement.

Differences in interpreting when the valve stem starts and stops affect the repeatability of the stroke time measurements.

Valves 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, B and 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 4, 1994

RELIEF REQUEST V-47 (Cont.)

TABLE V-47 Valve l-CC-LCV-101 Category Class Function l-MS-RV-101A,B,C 1-RH-FCV-1605 l-RH-HCV-1758 1-SW-PCV-lOOA,B,C 1-SW-PCV-lOOD,E 1-SW-PCV-lOlA,B,C 1-SW-PCV-lOlD,E 1-SW-TCV-lOBA,B,C S1PVI3RO B

3 B

B B

B 2

2 2

3 3

3 4-29 Charging Pump Seal Cooling Surge Tanlc Level Control Main Steam Header Discharge to Atmosphere PORV rum Heat Exchanger Bypass Flow Control Valve RHR Heat Exchanger Discharge Flow Control Valve Control Room Condenser Water System Pressure Control Valves Service Water to Charging Pump Lube Oil Cooler Temperature Control Valves Revision O August 4, 1994

RELIEF REQUEST V-50 system Service Water Valve(s):

1-SW-108 1-SW-113 Category:

C 1-SW-262 1-SW-268 Class 3 (l-SW-108,113,262,268)

Function:

Charging Pump Service Water Pump discharge Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used."

This sentence implies that each valve in the group given above must be disassembled every refueling outage.

Basis For Request The design basis for the charging pump service water system is currently undergoing reevaluation.

A full flow acceptance criteria will not be avaliable until this reevaluation is complete.

These check valves can be disassembled while the plant is operating.

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

Alternate Testing Proposed These valves will be placed into two groups and one valve from each group will be disassembled and inspected on a reactor refueling frequency.

A different valve will be disassembled for each inspection.

Valves 1-SW-108 and 113 will be in one group, and valves 1-SW-262 and 268 will be in the other group.

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

The check valves will be partial stroke tested every three months.

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

4-31 S1PVI3RO Revision o August 4, 1994

RELIEF REQUEST V-52 System Chemical and Volume Control and Safety Injection Valve(s):

1-CH-LCV-lllSB 1-CH-LCV-lllSD 1-SI-25 Category:

A and A/C Class 2

1-SI-MOV-1885A 1-SI-MOV-1885B 1-SI-MOV-1885C 1-SI-MOV-1885D Function:

RWST Isolation Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.2.2.J(f) - Valves or valve combinations with leakage rates exceeding the values specified by the Owner in (e) above shall be declared inoperable and be either repaired or replaced.

Basis For Request Valves 1-CH-LCV-lllSB and D, and 1-SI-25 are in the supply line to the charging pumps from the RWST.

Valves 1-SI-MOV-188SA, B, C and Dare on test lines that run from the discharge of the low head SI pumps to the RWST.

During recirculation mode transfer, the RWST is isolated and the low head SI pumps recirculate highly contaminated water from the containment sump to the reactor vessel.

The RWST isolation valves work as a system of valves to protect the RWST from the contaminated sump water.

Permissible valve leakage rates are based on each valve's possible contribution to the total allowable leakage rate to the RWST.

When the leakages from each valve have been measured and summed, an individual valve's permissible leakage rate may have been exceeded but the overall allowable leakage to the RWST may not have been exceeded.

In these cases, a repair or replacement may not be necessary because the system of isolation valves has been verified to be performing adequately

4-JJa S1PVI3RO Revision o August 4, 1994

RELIEr REQUEST V-52 (Cont.}

Alternate Testing Proposed In addition to repair or replacement as corrective actions, an evaluation can be performed which demonstrates that even if a valve has exceeded its permissible leakage rate, the overall leakage rate to the RWST will be maintained below the overall allowable RWST leakage rate.

No repair or replacement is necessary if the evaluation is performed.

4-33b S1PVI3RO Revision o August 4, 1994

RELIEF REQUEST V-53 system Service water Valve(s):

l-SW-839 l-SW-840 category:

C Class 3

Function:

Control room condenser water system discharge Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used."

This sentence implies that each valve in the. group given above must be disassembled every refueling outage.

Basis For Request The discharge check valves are downstream from the recirculation loops for two of the five trains in the control room condenser water system.

These two trains were added to the control room air conditioning system in 1994 and were designed to operate with a service water temperature of 95 °F.

These two trains have such a large cooling capacity that one of the two trains can absorb the heating load of the entire control room air conditioning system.

To maintain a high service water temperature, these trains must be operated with most of the service water flow diverted to the recirculation lines.

To achieve full design flow through the check valve, one train would have to be isolated and the flow of the other train diverted to the discharge check valve.

If the flow was diverted to the discharge check valve, the service water temperature would drop and th~ condenser system would trip off line on low condenser suction pressure.

Thus both trains would be out of service.

Also, the control room air conditioning system heat load balance would be upset.

The Surry control room is common to both units.

One of the two additional trains must be available for service while either Unit l or Unit 2 is operable.

Therefore, performing the full flow test is not practical when either unit is operating.

As an alternate test, these valves will be disassembled and inspected.

4-33c S1PVI3RO Revision o August 4, 1994 I

=<

(J

RELIEF REQUEST V-53 (Cont.)

These check valves can be disassembled while the plant is operating.

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

Alternate Testing Proposed These valves will be placed into a group and one valve from the group will be disassembled and inspected on a reactor refueling frequency.

A different valve will be disassembled for each inspection. If a valve fails its inspection, the remaining valve will be disassembled and inspected.

The check valves will be partial stroke tested every three months.

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

4-33d S1PVI3RO Revision O August 4, 1994 I

~

u

S1PVI3RO COLD SHUTDOWN JUSTIFICATION CSV-29 Cold Shutdown Justification Withdrawn 4-61 Revision o August 4, 1994

..,...J

COLD SHUTDOWN JUSTIFICATION CSV-32 system Valve(s):

Main Steam 1-MS-NRV-lOlA 1-MS-NRV-lOlB 1-MS-NRV-lOlC Category:

C Class NC Function:

Main steam Non-Return Valves Cold Shutdown Justification Valve Description The main steam non-return valves (NRVs) at Surry Power Station are located in the main steam valve house and are a globe type.

stop check design.

The valves measure approximately 16 feet from the bottom of the valve body to the top of the hand wheel and weigh almost 18,000 lbs.

The disk is welded to a hollow piston and the whole assembly is free to move about 25 vertical inches within the valve body cylinder.

The disk measures 25.5 inches across and the disk and piston assembly weighs approximately 1,200 lbs.

When the main steam system is not inservice, a motor operator is used to run the valve stem down onto the disk to secure the main steam line.

The valves open to allow steam to the turbine.

For accident conditions, the non-return valves in conjunction with the main steam trip valves prevent the blowdown of more than one steam generator for any break location, even if one valve fails to close.

For example, for a break upstream of the trip valve in one line, the closure of either the non-return valve in that line or the trip valves in the other lines prevents the blowdown of the other steam generators.

Method of Testing The piping downstream of each non-return valve leads to a common distribution manifold and cannot be isolated.

Therefore, performing a back seat test using flow is not practical.

Also, valve disassembly and inspection are not practical alternatives due to the size of the valve and the weight of the disk

4-64 SlPVIJRO Revision o August 4, 1994

COLD SHUTDOWN JUSTIFICATION CSV-34 System.

Service Water Valve(s):

1-sw-12 Category:

B Class 3

Function:

Service Water Supply Header Manual Isolation Valve Cold Shutdown Justification The 10 inch manual isolation valve 1-sw-12 isolates service water to the plant chilled water system condensers.

A full stroke test of 1-sw-12 may require that the condensers be secured.

The chilled water system supplies cooling water to the containment coolers for each unit.

The chilled water system is needed during much of the year while the plant is operating to ensure that the containment coolers have enough added capacity to maintain the containment air partial pressure within the acceptable operation range as described in Technical Specification Section 3.8, Figure 3.8-1.

Therefore, service water flow should not-be interrupted to the chilled water system while the plant is operating.

Full stroke exercising the valve during the cold shutdowns will be an adequate demonstration of operational readiness because the valve is a simple manual gate valve that is not subject to the failure mechanisms associated with power operated valves.

The small increase in safety gained by partial stroke exercising the valve every three months does not justify the burden of performing the partial stroke test.

Testing Frequency This manual isolation valve will be full stroke exercised every cold shutdown but not more frequently than once every three months.

4-67a SlPVI3RO Revision o August 4, 1994

~

REACTOR REFUELING JUSTIFICATION RRV-3 System Safety Injection Valve(s):

l-SI-107 1-SI-128 l-SI-145 Category:

C Class 1

l-SI-109 l-SI-130 l-SI-147 Function:

Accumulator Discharge Check Reactor Refueling Justification These valves cannot be partial or full flow tested during normal operation because the accumulator pressure (600 to 650 psig) is below Reactor Coolant System pressure and the injection of borated water would upset the reactor coolant chemistry.

During cold shutdown, the RCS pressure still prevents full flow testing.

To achieve full flow through the valves during reactor refueling, the accumulator would have to be discharged from an initial pressure of 600 psig.

Discharging the accumulator from this pressure would stress the piping system and inject-nitrogen into the RCS.

Nitrogen in the RCS has been linked to gas binding of the RHR pumps.

However, the accumulator can be discharged from a lower pressure during reactor refuelings when the RCS is depressurized.

At this pressure, full flow conditions will not be established; however, enough flow will be developed to open the check valves to the full open position.

This event can be verified and documented using non-intrusive diagnostic techniques.

A partial flow test is not practical during cold shutdowns.

The flow from the accumulator is dependent on the pressure differential between the accumulator and the RCS.

The pressure differential cannot be controlled to the fine degree necessary to preclude dumping too much water into the pressurizer, thus making it difficult to control pressurizer level while pressure is being reduced during cooldown.

Also, dumping cold accumulator water into the RCS could thermally shock the system.

Testing Frequency Non-intrusive diagnostic techniques will be used to determine that the check valves open to the full open position.

A sampling program will be applied to the non-intrusive techniques as described in Relief Request V-26

4-72 SlPVIJRO Revision o August 4, 1994

REACTOR REFUELING JUSTIFICATION RRV-5 system RWST Cross Tie Valve(s):

1-SI-25 1-SI-410 category:

C Class 2

Function:

Charging Pump Suction from RWST Cross Tie Reactor Refueling Justification Exercising these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank.

This would cause a sudden increase in reactor coolant boron inventory.

Full flow for the charging system can only be established during reactor refueling when the RCS is depressurized.

Valve 1-SI-25 must close to preserve inventory from the Unit 2 RWST when the cross tie lines are opened.

This valve is also subject to leak testing, which is performed every*reactor refueling.

Verification of closure will be performed during the leak test every reactor refueling instead of every cold shutdown because the small increase in safety gained by testing during cold shutdown does not justify performing a leak rate test.

Testing Frequency, These valves will partial flow tested during every cold shutdown and full flow tested during every reactor refueling.

Valve l-SI-25 will be exercised to the closed position every refueling outage.

.*,;£-

4-78 SlPVI3RO Revision o August 4, 1994

ATTACHMENT 2 CHANGES TO SURRY UNIT 2 THIRD INTERVAL INSERVICE TESTING PROGRAM REVISION 0 CHANGE 1 9410180169 941011 PDR ADOCK 05000280 p

PDR

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM The following is a section by section summary of changes for Revision o, Change 1 of the Surry Power station Unit 2 Inservice Testing (IST) Program for the third IST interval.

Revision o for the third IST interval was submitted on October 19, 1993 (Serial No.93-658).

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 3.5 PUMP INSERVICE TEST TABLES Unit 2 Pump Number Program Change CC-P-2A Relief Request P-19 was added for the suction'-

2-CC-P-2B pressure instrumentation.

3.6 PUMP TEST PROGRAM RELIEF REQUESTS Unit 2 Rel*ief Request Program Change P-19 This relief request is being added to the IST Program for the component cooling water pumps 2-cc-P-2A and B.

Recently installed inlet pressure gauges have a full scale range of Oto 3.5 psig.

Readings from these inlet pressure gauges over the past year indicate that the dynamic pressures fall within the bottom third of full scale.

However, the difference in the error between the Oto 3.5 psig gauges and gauges that would meet the ASME Section XI three times full-scale rule are so small that the o to 3.5 psig gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.

Therefore, inlet pressure will be measured with gauges that have a full-scale of Oto 3.5 psig.

2

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 3.7 ALTERNATIVE TESTING FOR NON-CODE PUMPS Unit 2 Non-Code Alternative Test PNC-1 Program Change Reference to the frequency response range of the vibration transducers was added.

The minimum pump shaft rotational speed for the diesel fuel oil pumps is 690 rpm.

To meet the one-third shaft speed requirement,.the low end of the frequency response range would have to be 3.8 hz.

The transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz.

These transducers are capable of detecting vibrations at frequencies of at least one times the rotational speed of the pump, which is adequate for detecting degradation in positive displacement pumps.

A note indicating that OM Part 6 does not require the measurement of suction pressure for positive displacement pumps was added.

3

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION

4

4 VALVE INSERVICE TEST TABLES Unit 2 Valve Number Comment/Program Change 2-MS-NRV-201A 2-MS-NRV-201B 2-MS-NRV-201C 2-MS-TV-209 2-MS-TV-210 2-CH-LCV-2115B.

2-CH-LCV-2115D 2-SI-25 2-SI-MOV-2885A 2-SI-MOV-2885B 2-SI-MOV-2885C 2-SI-MOV-2885D 2-SI-25 Program Change:

The ASME Code Classification was changed from Class 2 to non-Code Class.

As for Unit 1, these isolation valves prevent leakage of contaminated containment sump water to the refueling water storage tank from the discharge side of the low head safety injection pumps during recirculation mode transfer phase of safety injection.

Relief Reque~t V-52 is being added to the IST program and states that in addition to replacement and repair as corrective actions, an evaluation can be performed.

Relief Request V-52 was sent to the NRC by letter dated April 26, l.994 (serial No.94-223) and is being included in the IST Program through Change 1 to Revision o.

Program Change:

Relief Request V-52 is being added for the leak test.

The test method to verify valve closure was changed from disassembly and inspection to back seat testing every reactor refueling.

Refer to Reactor Refueling Justification RVV-

5.

Program Change:

Reactor Refueling Justification RRV-5 was revised.

4

2-SI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 2-SI-147 2-SW-130 ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM These accumulator discharge check.valves will be tested as pairs to the closed position.

Refer to Relief Request V-26.

Program Change:

Relief Request V-26 was revised to indicate that valves 2-SI-107 and 109, and 2-SI-128 and 130, and 2-SI-145 and 147 will be tested as pairs of valves in series to the closed position.

Also, Cold Shutdown Justification CSV-29 is no longer necessary for valves 2-SI-109, 130 and 147, and was deleted from the program.*

The internal parts were removed from this check valve.

Program Change:

The valve was removed from the IST program

4.5 VALVE TEST PROGRAM RELIEF REQUESTS Unit 2 Relief Request V-26 Program Change This relief request was revised to indicate that the accumulator discharge check valves will be tested as pairs of valves to the closed position.

Valves 2-SI-107 and 109, 2-SI-128 and 130, and 2-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system.

The downstream valves, 1-SI-109, 130 and 147 were previously chosen as the isolation valves and were subject to back seat tests while the other valves were considered as backup valves and were not subject to back seat tests.

The other set of valves cannot be individually back seated with the current piping configuration.

Testing experience has shown that a severe water hammer can be produced by attempting to individually test the downstream isolation valve.

Treating the check valves as a pair of isolation valves would eliminate the possibility of creating 5

I v-so V-52 ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM a water hammer event through testing.

The accumulators have level indicators and high/low tank level alarms in the control room.

Therefore, during normal operation the accumulator level is constantly monitored to ensure that one out of two check valves is seated properly to prevent in leakage from the reactor coolant system.

Valve 2-SW-130 was removed from the relief request.

This relief request is being added to the IST program for the RWST isolation valves.

The RWST isolation valves prevent leakage of contaminated containment sump water to the refueling water storage tank from the discharge side of the low head safety injection pumps during the recirculation mode transfer phase of safety injection. Relief Request V-52 states that in addition to replacement and repair as corrective actions, an evaluation can be performed.

Relief Request V-52 was sent to the NRC by letter dated April 26, 1994 (Serial No.94-223) and is being included in the IST Program through Change 1 to Revision o.

4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS Unit 2 Cold Shutdown Just Program Change CSV-29 This cold shutdown justification is being deleted from the IST program.

The accumulator discharge check.valves will be tested as pairs to the closed position per Relief Request V-26.

6

ATTACHMENT

SUMMARY

OF CHANGES TO THE SURRY UNIT 2 IST PROGRAM 4.7 VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Units 2 Reactor Refuel Just RRV-3 RRV-5 Program Change Justification was added for not performing a partial stroke test on the accumulator discharge check valves during cold shutdowns.

Reactor Refueling Justification RRV-5 was revised to indicate that 1-SI-25 (Unit l} and 2-SI-25 (Unit 2) will be back seat/leak tested to verify closure every reactor refueling instead of disassembled and inspected.

7

SURRY POWER STATION UNIT 2 REPLACEMENT PAGES

PUMP IN SERVICE TEST TABLE Pump ASME system Inlet Disch Diff Flow Pump Lubrication Relief

!dent.

Class Resist Press Press Press Rate Vi'bration Speed Level/Pressure Request 1-CC-P-lC 3

VAR 0

0 0

NA 0

1, 16 1-CC-P-lD 3

VAR 0

Q 0

Q Q

NA 0

1, 16 1-CH-P-2C 2

VAR 0

Q Q

NA NA 1, 18

.l-CH-P-2Q 2

VAR Q

Q Q

NA NA 1.1s 2-CC-P-2A 3

VAR 0

Q Q

NA NA 1.19 2-CC-P-2B 3

VAR Q

Q Q

NA NA

1. 19 2-SW-P-lOA 3

VAR Q

Q Q

NA NA 1

2-SW-P-lOB 3

VAR Q

Q Q

NA NA 1

1-EE-P-lB NC FIX NA Q

NA Q

Q NA NA 1.PNC-:-1 l-EE-P-lf.i

. N~

[IX NA Q

NA Q

Q NA NA l.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 S2PVI3RO Revision o August 4, 1994

~

I

~

u

RELIEF REQUEST P-19 system:

Pump(s):

Component Cooling Water 2-cc-P-2A 2-cc-P-2B Class 3

OM Part 6 Code Requirements For Which Relief Is Requested The full-scale range of each instrument shall be three times the reference value or less (OM Part 6, Paragraph 4.6.1.2).

Basis For Request Recently installed inlet pressure gauges have a full scale range of o to 3.5 psig.

Readings from these.inlet pressure gauges over the past year.indicate that the dynamic pressures fall within the bottom third of full scale.

However, the difference in the error between the Oto 3.5 psig gauges and gauges that would meet the three times full-scale rule are so small that the o_to 3.5 psig gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.

For example, the lowest recorded inlet pressure for pump 2-CC-P-2A is 0.5 psig.

A gauge that meets the three times full-scale rule would have a full scale of 1.5 psig*or less.

A 2% accuracy for the 1.5 psig gauge translates to an error of 0.03 psig.

A 2%

accuracy for the 3.5 psig gauge translates to an error of 0.07 psig.

The difference in error of 0.04 psig is insignificant when determining the differential pressures for these pumps which range between 50 and 60 psig.

Therefore, the two gauges can be considered to be equivalent in terms of accuracy for determining differential pressure.

Alternate Testing Proposed Inlet pressure will be measured with gauges that have a full-scale of Oto 3.5 psig.

3-20a S2PVI3R0 Revision o August 4, 1994

' 2

<.J

NON-CODE ALTERNATIVE TESTING PNC-1 System:

Pump(s):

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

The*freguency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump shaft rotational speed to at least 1000 HZ (OM Part 6, Paragraph 4.6.1.6).

Basis For Alternate Testing The pump operating time *is limited due to operational restraints.

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

The pump run time can vary depending upon the diesel load and the resulting fuel consumption rate. If the pumps are allowed to run for two minutes prior to measuring the test quantities and the fuel consumption rate is low, not enough time is available to gather all of the required Section XI test data.

The minimum pump shaft rotational speed for these pumps is 690 rpm.

To meet the one-third shaft speed requirement, the low end of the frequency response range would have to be 3.8 hz.

The transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz.

These transducers are capable of detecting vibrations at frequencies of at least one times the rotational speed of the pump, which is adequate for detecting degradation in positive displacement pumps.

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

The transducers used for testing the diesel fuel oil transfer pumps have a low end frequency response of 10 hz versus the 3.8 hz required by the Code for a pwnp riuming at 690 rpm.

3-22 S2PVI3RO Revision o August 4, 1994

NON-CODE ALTERNATIVE TESTING PNC-1 (Cont.)

Note:

The diesel oil transfer pumps are positive displacement pumps.

According to OM Part 6, Table 2, only discharge pressure need be measured for positive displacement pumps.

3-23 S2PVI3RO Revision O August 4, 1994

.._..i I

~

<.J

VIRGINIA POlo'ER a>>IPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO VALVE NIMBER DRA"ING Nll4BER SHEET DRYG VALVE Nll4BER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE

C" CHARGING PlJIP DISCHARGE RECIRC LINE CHECK VALVE 2-CH-276 11548-CBM-0888 2 OF 2 D-4 CHECK VALVE 3.000 2 C

CV

c* CHARGING Pl.MP DISCHARGE CHECK VALVE 2-CH-309 11548*C8M*D88C 1 OF 2 D-4 CHECK VALVE MAIN CHARGING SUPPLY HEADER, INSIDE CONTAIN*

NENT ISOLATION CHECK VALVE 2*CH-FCV*2113A 11548-CBM-0888 1 OF 2 C-3 AO GLOSE MANUAL EMERGENCY BORATION PATH FLl7J CONTROL VALVE 2-CH*FCV-2114"- 11548*CBM*088B. 1 OF 2 D*4 AO GLOBE PRIMARY GRADE WATER SUPPLY TO BORIC ACID BLENDER ISOLATION VALVE 2-CH-FCV-2160 11548-CBM*D88C 1 OF 2 B*4 AO GLOBE CHARGING FLOW CONTROL TO LOOP FILL HEADER, OJTSIDE CONTAINl4ENT ISOLATION VALVE 2-CH-LCV-2115B 11548-CBM-0888 2 OF 2 B-8 NO GATE CHARGING PUMP SUPPLY ISOLATION VALVE FRIii REFUELING WATER STORAGE TANK 2-CH-LCV*2115C 11548-CBM*OSBB 1 OF 2 C-6 NO GATE CHARGING PUMP SUPPLY ISOLATION FRCII VOLUME CONTROL TANK 3.000 2 1.000 2 2.000 2 2.000 1 8.000 2 4.000 2 AC CIV CV LT B

B EV FS ST VP EV FS ST VP AE CIV LT VP A

B EV LT ST VP EV ST VP 2-CH-LCV-21150 11548-CBM-0888 2 OF 2 C-8 NO GATE 8.000 2 A

EV LT ST VP PAGE:

8 OF 66 REVISION: DO DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV-RRV-VOi-C 0

C C

0 0

0 oc C

C C

oc C

0 C

C 0

oc C

C oc C

0 C

C 0

oc 52 52 11 11 6

~.

(J

~

VIRGINIA POWER COMPANY SURRY UMJT 2 PAGE:

32 OF 66 REVISION: 00 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE DATE: 08/04/94 NC ISO VALVE NlMBER DRAWING NUMBER SHEET DRYli VALVE NIMBER COOR TYPE VALVE ASNE IW VALVE TEST SIZE CLASS CAT TYPE TYPE REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV* VOi-2-MS-087 11548*CBH*064A 1 OF 6 C-6 MANUAL GATE MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PlllP ISOLATION VALVE 4.000 2 2-MS-120 11548*CBM*064A 2 OF 6 C-6 MANUAL GATE MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PlllP ISOLATION VALVE 4.000 2 B

B 2-MS-158 11548*CBM*064A 3 OF 6 C-6 IWIUAL GATE MAIN STEAM LINE TO TURBINE DRIVEN AUXILIARY FEEDWATER PlllP ISOLATION VALVE 4.000 2 B

- - - - m******** ***** ***** ***

2-MS-176 2-MS-178 11548*CBM*064A 4 OF 6 C-7 CHECIC VALVE

A* MAIN STEAM HEADER SUPPLY CHECIC VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PlJ4P 11548-CBM*064A 4 OF 6 D-7 CHECIC VALVE

.*. *B* MAIN STEAM HEADER SUPPLY CHECIC VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 3.000 2 3.000 2

*--------------------------------------------- ----- g----

2-MS-182 11548*CBM*064A 4 OF 6 D-7 CHECIC VALVE

c* MAIN STEAM HEADER SUPPLY CHECIC VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUNP 3.000 2 2*MS*NRV*201A 11548*CBM*064A 1 OF 6 E-4 MO STOP CHECIC 30.000 NC NAN MAIN STEAM HEADER NON-RETURN VALVE C

C C

C 2-MS*NRV-2018 11548*CBM*064A 2 OF 6 D-3 MO STOP CHECIC 30.000 NC C

e* MAIN STEAM HEADER NON-RETURN VALVE 2*MS*NRV*201C 11548-CBM*064A 3 OF 6 D-3 MO STOP CHECIC 30.000 NC C

CN MAIN STEAM.HEADER NON-RETURN VALVE 2*MS-PCV*202A 11548*CBM*064A 4 OF 6 C-4 AO GATE I\\CAJN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER P1.14P 3.000 2 B

EV e

EV C

CV.

C CV 0

C ci CV.

C CV VP CV VP 0

C oc C

oc 42 42 42 42 42 42 32 32 CV VP C

32 oc EV C

0 FS C

ST C

0 VP OC

VALVE NLIIBER 2*MS*TV*201B DRA\\IING NLIIBER VIRGINIA POWER CDNPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING P~OGRAM

VALVE TABLE SHEET DR\\IG VALVE IUIBER CDOR TYPE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11S48*CBM*064A 2 OF 6 C-4 AO CHECK VALVE 30.000 2 B

EV ST VP

e* MAIN STEAM HEADER TRIP VALVE 2*MS*TV*201C 11548*CBM*064A 3 OF 6 C*4 AO CHECK VALVE 30.000 2 B

c* MAIN STEAM HEADER TRIP VALVE 2*MS*TV*209 2*MS*TV*210 11S48*CBM*064A 4 OF 6 F*5 AO GATE MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO CONDENSER 11S48*CBM*064A 4 OF 6 F-7 AO GATE MAIN STEAM HIGH PRESSURE DRAIN ISOLATION TO STEAM GENERATOR BL°"8>DYN SYSTEM 3.000 NC

, B 2.000 NC B

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

35 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV-VCII-C C

oc C

C oc C

C C

oc C

C C

oc

~

\\ <

I;..)

~.

~

(..)

VALVE NLJ48ER 2*Sl*025 VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO DRAWING NLJ48ER SHEET DRWG VALVE NlJCBER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11S48*CBM*089A 1 OF 3 E*S CHECIC VALVE a.ooo 2 RWST SUPPLY CHECIC VALVE TD CHARGING PUMP SUCTION HEADER AC CV LT 2*Sl*032 11S48*CBM*089B 1 OF 4 E*3 NAN GLOBE ACCll4ULATDR MAKEUP LINE, CIJTSJDE CONTAINMENT ISOLATION VALVE 1.000 2 AE CIV LT 2*SI*046A 11S48*CBM*089A 1 OF 3 A*3 CHECIC VALVE RWST SUPPLY CHECIC VALVE TD *A* LCII HEAD SJ PUMP SUCTION 12.000 2 2*SI*0468 11548*CBM*089A 1 OF 3 8*3 CHECIC VALVE RWST SUPPLY CHECIC VALVE TO *8* LCII HEAD SJ PUMP SUCTION 12.000 2 2*SI*047 2*SI*D50 2*SI*D53 2*Sl*D56 2*Sl*061 2*Sl*D73 2*Sl*D79 2*SJ*082 11548*C8N*089A 1 OF 3 8*5 CHECIC VALVE 12.000 2

* *9* LCII HEAD SJ PUMP SUCTION CHECIC VALVE FRCII CONTAINMENT SUMP 11548*C8M*D89A 1 OF 3 C*4 CHECK VALVE

9* LCII HEAD SI PUMP DISCHARGE CHECIC VALVE 11548*CBM*089A 2 OF 3 8*4 CHECIC VALVE

a* LOW HEAD SI PUMP MINIIIII FLCII/TEST LINE DISCHARGE CHECK VALVE 11548*CBN*089A 1 OF 3 8*7 CHECIC VALVE

- A* LCII HEAD SJ PlMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 11548*CBN*089A 2 OF 3 8*5 CHECK VALVE

A* LCII HEAD SJ PUMP MINIMUM FLCII/TEST LINE DISCHARGE CHECK VALVE 11548*CBM*089A 2 OF 3 E*7 NAN GLOBE ACCl.tlULATDR TEST LINE, CIJTSIDE CONTAINMENT ISOLATION VALVE 11548*C8M*D89B 4 OF 4 F-7 CHECIC VALVE RCS COLD LEG SJ ADMISSION CHECIC VALVE 11548-CBM-0898 4 OF 4 E*7 CHECK VALVE 10.000 2 2.000 2 12.000 2 2.000 2

.750 2 6.000 1 6.000 1 C

CV C

CV AE CIV LT AC PJV CV LT AC PIV CV PAGE:

47 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST PDS V*

CSV* RRV-VCII*

C D

C C

D D

D C

D D

C C

0 C

C 52 20 20 5

5 2

2 2

2 4

4 4

VALVE NUMBER 2-Sl-082 DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRWG VALVE IIUIBER COOR TYPE ISO VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11548-CBM-0898 4 OF 4 E-7 CHEO:: VALVE 6.000 1 AC PIV CV LT RCS COLD LEG SI ADMISSION CHEO:: VALVE 2-Sl-085 11548-CBM-0898 4 OF 4 D-7 CHEO:: VALVE RCS COLD LEG SI ADNISSIDII CHEO:: VALVE 6.DOO 1 AC PIV CV LT 2-Sl-088 2-Sl-091 2*Sl*107 2-Sl-109 2-Sl-128 2-Sl-130 2-Sl-145 11548-CBM-0898 4 OF 4 D-7 CHECK VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11548-CBM-0898 4 OF 4 c-7 CHEO:: VALVE RCS HOT LEG SI ADMISSION CHECK VALVE 11S48*CBN*089B 4 OF 4 B-7 CHEO:: VALVE RCS HOT LEG SI ADMISSION CHEO:: VALVE 11548-CBM-089&

1 OF 4 B-7 CHECK VALVE

A11 ACCUMULATOR DISCHARGE CHECK VALVE 11548-CBM-089&

1 OF 4 B-8 CHECK VALVE

A* ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11548*CBM*089B 2 OF 4 B-6 CHECK VALVE

&* ACCUMULATOR DISCHARGE CHECK VALVE 11548-CBM-089&

2 OF 4 B-7 CHEO:: VALVE

& 11 ACCUMULATOR COLD LEG ADMISSION CHEO::

VALVE 11548-CBN-0898 3 OF 4 B-5 CHECK VALVE

c* ACCUMULATOR DISCHARGE CHECK VALVE 6.000 1 C

CV 6.DOo* 1 C

CV 6.DOO 1 C

CV 12.000 1 C

CV 12.0DO 1 C

CV PAGE :

48 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV* VCN-0 C

C 0

C C

0 C

0 27 27 27 26 26 26 26 26 4

4 4

3 3

26 3

26 26 26 26 3

3

VALVE NlJ4BER 2-Sl-147 VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO DRAWING NlJ4BER SHEET DRWG VALVE NlJ4BER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11548-CBM-0898 3 OF 4 B-7 CHECIC VALVE

c* Aca.MJLATOR COLD LEG ADMISSION CHECIC VALVE 12.000 1 C

CV 2-Sl-150 11548-CBM-089A 3 OF 3 F-6 MAN GLOBE BORON INJECTION TANK BYPASS LINE ISOLATION VALVE - TO RCS COLD LEG

.750 2 2-Sl-174 11S48*CBM*089A 3 OF 3 D-6 MAN GLOBE

.750 2

- - - - e************************

HIGH HEAD SAFETY INJECTION TO RCS AE CIV LT AE CIV LT 2-Sl-224 2-Sl-225 2-SI-226 2-Sl-227 2-Sl-228 2-Sl-229 2-Sl-235 2-Sl-236 2-SI-237 11548-CBM-0891 4 OF 4 F-3 CHECIC VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECX VALVE 11548-CBM-0891 4 OF 4 E-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECIC VALVE 11548-CBM-0891 4 OF 4 C-3 CHECIC VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECIC VALVE 11548-CBM-0891 4 OF 4 C-~

CHECIC VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECIC VALVE 11548-CBM-0891 4 OF 4 B-3 CHECIC VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECIC VALVE 11548-CBM-0891 4 OF 4 B-3 CHECIC VALVE LOW HEAD SI FROM LHSI PUMP TO RCS HOT LEGS, INSIDE CONT CHECIC VALVE 11548-CBN-0898 4 OF 4 F-7 CHECIC VALVE HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECIC VALVE 11548-CBM-0891 4 OF 4 E-7 CHECX VALVE HIGH HEAD SI TO RCS COLD LEG, INSIDE MISSILE BARRIER CHECIC VALVE 11548-CBM-0891 4 OF 4 D-7 CHECK VALVE 3.000 2 C

CV 3.000 2 C

CV 6.000 2 C

CV 2.000 1 C

CV 2.0DO 1 C

CV PAGE:

49 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN-C 0

C C

0 0

C 0

26 26 3

4 4

VIRGINIA POIJER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE VALVE NUMBER DRA\\IING NUMBER SHEET DR\\IG VALVE NUMBER COOR TYPE 2-SI-MOV-2867D 11548-CBM-089A 3 OF 3 E-6 NO GATE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 A

CIV EV LT ST VP BORON INJECTION TANK OUTLET TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE

- - - - a*********

2-SI-MOV*2869A 11548-CBM-089A 3 OF 3 C*7 MO GATE

. HIGH HEAD SI FRON CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 3.000 2 A

CIV EV LT ST VP 2*SI-MOY*2869B 11548-CBM-089A 3 OF 3 E-4 NO GATE HIGH HEAD SI FRON CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 2*S1*MOV*2885A 11548-CBM-089A 2 OF 3 B-5 NO GATE NAN LOY HEAD SI PUMP MINIMUM FLOY/TEST LINE ISOLATION 2*S1*MOV*2885B 11548-CBM-089A 2 OF 3 B-4 MO GATE

e* LOY HEAD SI PUMP MINIMUM FLOY/TEST LINE ISOLATION 2*S1*MOV*2885C 11548-CBM*089A 2 OF 3 B-4 NO GATE

e* LOY HEAD SI PUMP MINIMUM FLOY/TEST LINE ISOLATION 2-SI-MOV-28850 11548*CBM*089A 2 OF 3 B-5 NO GATE 3.000 2 A

2.000 2 A

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

53 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VCN*

C 0

C C

0 DC C

0 C

C 0

DC C

0 C

C 0

DC C

C 52 C

DC C

C C

DC C

52 C

DC C

C 52 C

DC 18 18 18 18 25 25 25 25 25 25 25 25

~.

I

VALVE NUMBER 2-SW-1!)8 DRAI.IING NlMBER VIRGINIA POIJER COMPAJIY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL JNSERVICE TESTING PROGRAM - VALVE TABLE SHEET DRI.IG VALVE IUIBER COOR TYPE ISO VALVE ASNE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11548-CBM-0718 1 OF 2 B-4 CHECK VALVE 2.000 3 C

CV CHARGING PUMP SERVICE I.IATER PUMP CHECK VALVE 2-SW-113 11548-CBM-0718 1 OF 2 B-7 CHECK VALVE 2.000 3 C

CV CHARGING PUMP SERVICE I.IATER PUMP CHECK VALVE

- - - - G******* ***** ***** *** ****

2-SW-206 11S48*CBM-071A 3 OF 3 E*8 NAJI GATE CONTAINMENT ISOLATION VALVE FDfl SERVICE I.IATER DRAINS TO HEAT EXCHANGER 2.000 2 AE

.CIV LT

- - - - aa*c*-m******-************* ***** ***** *** ****

2-Sl.l-208 2-SW-246 11548-CBM*071A 3 OF 3 E*8 NAJI GATE CONTAINMENT ISOLATION VALVE FDfl SERVICE WATER DRAINS TO HEAT EXCHANGER 2.000 2 11548-CBM*071A 3 OF 3 D*8 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE YATER RETURN VENT VALVE 3.000 NC

*--------------------------------------------- ----- -~---

2-Sl.l-247 2-Sl.l-248 2-Sl.l-249 2-SIJ-250 2-Sl.l-251 2-SIJ-252 2-SW-253 11548-CBM-071A 3 OF 3 D*7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER SUPPLY VENT VALVE 11548-CBM-071A 3 OF 3 D*7 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D*6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER SUPPLY VENT VALVE 11548-CBM*071A 3 OF 3 D*6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER RETURN VENT VALVE 11548-CBM*071A 3 OF 3 D*6 CHECK VALVE

. RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER SUPPLY VENT VALVE 11548-CBM-071A 3 OF 3 D*5 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE I.IATER RETURN VENT VALVE 11548-CBM-071A 3 OF 3 D-5 CHECK VALVE 3.000 3 3.000 NC 3.000 3 3.000 NC 3.000 3 3.000 NC 3.000 3 AE CIV LT C

CV C

CV PAGE:

59 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0

C 0

C C

0 0

50 50 46 46 46 46

VIRGINIA Pa.ER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NLIIBER DRAIIING NUMBER SHEET DRIIG VALVE lllMBER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 2-SW-442 11548-CBM-071B 1 OF 2 B*4 CHECk'. VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2.000 3 C

2*511*445 11548*CBM*071B 1 OF 2 B*6 CHECk'. VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 2.000 3 C

2*S\\l*NOV*201A 11548*CBM*071A 3 OF 3 B*4 NO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 2*S11*NOV-201B 11548*CBM*071A 3 OF 3 B*4 NO BFLY BEARING COOLING WATER HEAT EXCHANGER I SOLA Tl ON VAL VE 2-S11*NOV*202A 11548*CBM*071A 2 OF 3 D-6 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2-Sll**JV-2028 11548°CllN°071A 2 OF 3 D-5 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 2-S11-MOV-203A 11548-CBM*071A 3 OF 3 8*8 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-SII-NOV-2038 11548*CBM*071A 3 OF 3 B*8 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2-S11*NOV-203C 11548*CSM*071A 3 OF 3 B*3 NO BFLY 36.000 3 B

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: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCM-0 0

C C

DC C

C DC C

C DC 0

0 DC 0

0 DC 50 50

VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO VALVE NlMBER DRAl,IING IILICBER SHEET DRl,IG VALVE NlJilBER COOR TYPE VALVE ASHE IW VALVE TEST SIZE CLASS CAT TYPE TYPE SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 2*SW*MOV*203D 11548*CSM*071A 3 OF 3 B-2 NO BFLY SERVICE WATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 30.000 3 B

2*S1,1*MOV*204A 11S48*C8M*071A 3 OF 3 D-7 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *A* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2*Sl,l*MOV*204B 11S48*C8M*071A 3 OF 3 D*6 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO *a* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-Sl,l*MOV*204C 11548*C8M*071A 3 OF 3 D*S NO BFLY 24.000 3 SERVICE l,IATER SUP~LY TO *c* RECIRC SPRAY H~T EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-Sl,l*MOV-2040 11548*CBM*071A 3 OF 3 0*4 NO BFLY 24.000 3 SERVICE WATER SUPPLY TO "I)* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2-Sl,l*MOV-205A 11548-CSM-071A 3 OF 3 0*8 NO BFLY SERVICE WATER RETURN FRON *A* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 2*S1,1*MOV-205B 11548*CSM*071A 3 OF 3 D*7 NO BFLY 24.000 3 24.000 3 B

B B

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

61 OF 66 REVISION: 00 DA TE: D8/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* Val-0 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 DC C

0 C

0 DC

VIRGINIA POWER COMPANY SURRY UNIT 2 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM - VALVE TABLE ISO VALVE NlMBER DRA"ING NlMBER SHEET DR\\IG VALVE NUMBER COOR TYPE VALVE ASHE IW VALVE TEST SIZE ClASS CAT TYPE TYPE SERVICE WATER RETURN FRtlf *a* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CQMT ISOUTION VALVE 2-SW-MOV*205C 11S48*CBM-071A 3 OF 3 D-6 NO BFLY 24.000 3 B

SERVICE WATER RETURN FRCl4 *c* RECIRC SPRAY I

HEAT EXCHANGER, OUTSIDE CQMT ISOLATION VALVE 2-5"-MOV-205D 11548*CBM*071A 3 OF 3 D*5 NO BFLY 24.000 3 B

SERVICE WATER RETURN FRCl4 -o* RECIRC SPRAY HEAT EXCHANGER, OUTSIDE ccelT ISOLATION VALVE 2*S"*TCV-2D8A 11548*CBM*071B 1 OF 2 E*7 AD GATE SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 2*S"*TCV*2D8S 1154S*CBM*071B 1 OF 2 E*S AD GATE SERVICE WATER TO CHARGING PlllP LUSE OIL COOLER TEMPERATURE CONTROL VALVE 1.500 3 B

1.500 3 B

~------------------------------------------------*------- ----- ~---- ---

2*SW*TCV*208C 11548*CBM*071B 1 OF 2 E*4 AD GATE SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1.500 3 B

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

62 OF 66 REVISION: 00 DATE: 08/04/94 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V*

CSV* RRV* VCN*

C 0

oc C

0 C

0 oc 0

0 0

47 47 47

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.

B~sis For Request Exercise to the Open Position 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.

Exercise to the Closed Position Valves 2-SI-107 and 109, 2-SI-128 and 130, and 2-SI-145 and 147 perform as pairs of valves in series to isolate the accumulators from the reactor coolant system *.

The downstream valves, 2-SI-109, 130 and 147 were previously chosen as the isolation valves and were subject to back seat tests while the other valves were 4-15 S2PVI3RO Revision O August 4, 1994

~

\\ <

<.J

RELIEF REQUEST V-26 (Cont.)

considered as backup valves and were not subject to back seat tests.

The other set of valves cannot be individually back seated with the current piping configuration.

Testing experience has shown that a severe water hammer can be produced by attempting to individually test the downstream isolation valve.

To individually test these valves, a reactor coolant system

pressure in excess of 1000 psi was needed to properly seat the valves.