ML18151A278: Difference between revisions

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(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
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Program Change: Relief Request V-34 was withdrawn.
Program Change: Relief Request V-34 was withdrawn.
At one time, this normally closed manual valve would be opened following initiation of an event to reduce the flowrate through the essential heat exchangers and thus conserve the cooling water inventory in the intake canal. However, it has been determined that this vent valve is no longer required for ,:**:,,,*  
At one time, this normally closed manual valve would be opened following initiation of an event to reduce the flowrate through the essential heat exchangers and thus conserve the cooling water inventory in the intake canal. However, it has been determined that this vent valve is no longer required for ,:**:,,,*  
**> .. >.* .. *'** '* ***'* ->* , ..... , ..... '., .. ,., ... ca.naT:'-wdte:;::*  
**> .. >.* .. *'** '* ***'* ->* , ..... , ..... '., .. ,., ... ca.naT:'-wdte:;::*
:-iuv~llto:t.*y' coucerus*~  
:-iuv~llto:t.*y' coucerus*~  
** , .. _ .. *<** .,.,, .... ;.'. 1-DA-TV-lOOA  
** , .. _ .. *<** .,.,, .... ;.'. 1-DA-TV-lOOA  
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Relief Request V-45 was replaced by Reactor Refueling Justification RRV-7. RRV-7 deals with the RCP thermal barrier isolation check valves located inside containment that are subject to back seat testing. The Revision 5 version of V-45 requested relief from performing a back seat test every cold shutdown.
Relief Request V-45 was replaced by Reactor Refueling Justification RRV-7. RRV-7 deals with the RCP thermal barrier isolation check valves located inside containment that are subject to back seat testing. The Revision 5 version of V-45 requested relief from performing a back seat test every cold shutdown.
OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.
OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.
The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-46 (1-SW-313, 323 and 2-SW-333) must be disassembled every refueling outage. V-46 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04; Positicni  
The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-46 (1-SW-313, 323 and 2-SW-333) must be disassembled every refueling outage. V-46 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04; Positicni
: 2. These check valves can be disassembled while the plant is operating.
: 2. These check valves can be disassembled while the plant is operating.
To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. The Revision 5 version of V-47 submitted on July 24, 1992, requested relief from determining the alert status as required by the old Code. In the NRC SER received in March of 1993, the NRC reviewer determined that V-47 was not necessary because OM Part 10 does not require the determination of the alert acceptance criteria.
To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. The Revision 5 version of V-47 submitted on July 24, 1992, requested relief from determining the alert status as required by the old Code. In the NRC SER received in March of 1993, the NRC reviewer determined that V-47 was not necessary because OM Part 10 does not require the determination of the alert acceptance criteria.
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-the Pump Inservice Test Program and the Valve Inservice Test Program. The development, implementation and administration of these two programs are detailed in subsequent sections.
-the Pump Inservice Test Program and the Valve Inservice Test Program. The development, implementation and administration of these two programs are detailed in subsequent sections.
This IST Program Plan applies to the third 10-year IST interval for Surry Power Station Unit 1. The third interval starts on May 10, 1994 and ends by May 10, 2004. Surry Power Station requested an exemption from Section XI of the ASME Code to extend the Surry Unit 1 second 10-year IST interval for pumps and valves from December 22 ,1992 to May 10, 1994 to coincide with the end of the second 10-year IST interval for Unit 2 by letter to the NRC dated November 10, 1992. The NRC responded by letter dated February 16, 1993 granting this exemption.
This IST Program Plan applies to the third 10-year IST interval for Surry Power Station Unit 1. The third interval starts on May 10, 1994 and ends by May 10, 2004. Surry Power Station requested an exemption from Section XI of the ASME Code to extend the Surry Unit 1 second 10-year IST interval for pumps and valves from December 22 ,1992 to May 10, 1994 to coincide with the end of the second 10-year IST interval for Unit 2 by letter to the NRC dated November 10, 1992. The NRC responded by letter dated February 16, 1993 granting this exemption.
The Code of Federal Register 10CFR50.55a(f}  
The Code of Federal Register 10CFR50.55a(f}
(4} (ii) states in part that the 10-year IST interval "must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b} of this section 12 months prior to the start of the 120-month interval." As described in paragraph (b)(2} of 10 CFR 50.55a that was approved for use on September a, 1992 by the Federal
(4} (ii) states in part that the 10-year IST interval "must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b} of this section 12 months prior to the start of the 120-month interval." As described in paragraph (b)(2} of 10 CFR 50.55a that was approved for use on September a, 1992 by the Federal
* Register, Vol. 57, No. 152, "references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Divh.ion 1, and include addenda through the 1988 Addenda and editions through the 1989 Edition." The IST Program Plan for the third 10-year interval for Surry Unit 1 complies with these addenda and edition
* Register, Vol. 57, No. 152, "references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Divh.ion 1, and include addenda through the 1988 Addenda and editions through the 1989 Edition." The IST Program Plan for the third 10-year interval for Surry Unit 1 complies with these addenda and edition
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==References:==
==References:==


This section identifies references applicable to Technical Specifications and other necessary material as drawings.  
This section identifies references applicable to Technical Specifications and other necessary material as drawings.
: 2) Purpose: This section identifies test objectives.  
: 2) Purpose: This section identifies test objectives.
: 3) Initial Conditions:
: 3) Initial Conditions:
Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use. 4) Precautions:
Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use. 4) Precautions:
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* 3-2 Rev~~ion o November 10, 1993 3.3
* 3-2 Rev~~ion o November 10, 1993 3.3
* 3.4
* 3.4
* PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power station are responsible for administration and execution of the Pump Inservice Test Program. The third 10-year interval IST Program will be officially implemented on May 10, 1994 and governs pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a{f)  
* PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power station are responsible for administration and execution of the Pump Inservice Test Program. The third 10-year interval IST Program will be officially implemented on May 10, 1994 and governs pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a{f)
(4). PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES". 1-CH-P-lA 1-CH-P-lB 1-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for the Safety Injection system and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11448-CBM-SSB, Sheet 2 . 1-SI-P-lA 1-SI-P-1B Low Head Safety Injection Pumps provides low pressure ,._ .... *'.**}****  
(4). PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES". 1-CH-P-lA 1-CH-P-lB 1-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for the Safety Injection system and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11448-CBM-SSB, Sheet 2 . 1-SI-P-lA 1-SI-P-1B Low Head Safety Injection Pumps provides low pressure ,._ .... *'.**}****  
"'*
"'*
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Also, the loop accuracies for the discharge pressure gauges will be maintained at or below an accuracy of 1.75% to ensure that the differential pressure error is below the differential pressure error allowed by the Code
Also, the loop accuracies for the discharge pressure gauges will be maintained at or below an accuracy of 1.75% to ensure that the differential pressure error is below the differential pressure error allowed by the Code
* 3-31 S1PVI3RO Revision o November 10, 1993 3.7 * *
* 3-31 S1PVI3RO Revision o November 10, 1993 3.7 * *
* S1PVI3RO ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the minutes of public meeting on Generic Letter 89-04, "Paragraph  
* S1PVI3RO ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the minutes of public meeting on Generic Letter 89-04, "Paragraph
{g) of 10 CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. Paragraph  
{g) of 10 CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. Paragraph
{g) has been replaced by Paragraph  
{g) has been replaced by Paragraph
{f) in the currently approved 10 CFR 50.55a. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required  
{f) in the currently approved 10 CFR 50.55a. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required  
!ST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program {or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a 'request for relief' to be submitted to the staff. Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3
!ST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program {or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a 'request for relief' to be submitted to the staff. Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3
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* 4.2 *
* 4.2 *
* S1PVI3RO requirements
* S1PVI3RO requirements
* Valves subject to leak testing per Appendix J will be tested to the requirements of OM Part 10, Paragraphs 4.2.2.3(e) and 4.2.2.3(f) as required by 10 CFR 50.55a(b)  
* Valves subject to leak testing per Appendix J will be tested to the requirements of OM Part 10, Paragraphs 4.2.2.3(e) and 4.2.2.3(f) as required by 10 CFR 50.55a(b)
(2) (vii). Appendix J satisfies the testing requirements of OM Part 10, Paragraph 4.2.2.2. The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.
(2) (vii). Appendix J satisfies the testing requirements of OM Part 10, Paragraph 4.2.2.2. The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.
The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted (refer to Section 4.5). The Surry Unit 1 Valve Inservice Test Program complies with the intent of the applicable codes, regulations and guidelines and makes a positive contribution to the safe operation of the plant. PROGRAM IMPLEMENTATION The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Three types of tests are conducted as part of the Valve Test Program: 1) Valve Exercise Tests, 2) Valve Leakage Tests and 3) Safety Valve Tests The Exercise Tests verify that: 1) the valve strokes properly, 2) the valve responds to control commands, 3) the valve stroke time is within specific limits and 4) remote position indication accurately reflects the observed valve position.
The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted (refer to Section 4.5). The Surry Unit 1 Valve Inservice Test Program complies with the intent of the applicable codes, regulations and guidelines and makes a positive contribution to the safe operation of the plant. PROGRAM IMPLEMENTATION The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Three types of tests are conducted as part of the Valve Test Program: 1) Valve Exercise Tests, 2) Valve Leakage Tests and 3) Safety Valve Tests The Exercise Tests verify that: 1) the valve strokes properly, 2) the valve responds to control commands, 3) the valve stroke time is within specific limits and 4) remote position indication accurately reflects the observed valve position.
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* 4-3 Revij;ion O November 10, 1993
* 4-3 Revij;ion O November 10, 1993
* 4.3 4.4 *
* 4.3 4.4 *
* S1PVI3RO A different valve of each group is required to be disassembled, inspected, and manually full stroked exercised at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised.or there is binding or failure of valve internals, the remaining valves in that group must be disassembled, inspected, and manually full stroked exercised during the same outage. PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test Program. The program will be officially implemented on May 10, 1994. The program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.55a{f)  
* S1PVI3RO A different valve of each group is required to be disassembled, inspected, and manually full stroked exercised at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised.or there is binding or failure of valve internals, the remaining valves in that group must be disassembled, inspected, and manually full stroked exercised during the same outage. PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test Program. The program will be officially implemented on May 10, 1994. The program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.55a{f)
(4) .for subsequent 120 month IST intervals.
(4) .for subsequent 120 month IST intervals.
VALVE INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet OM Part 10 requirements.
VALVE INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet OM Part 10 requirements.
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00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-  
00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-  
* * '_,..,,..,,.
* * '_,..,,..,,.
* VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-RH-005 1-RH-011 DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-087A 1 OF 2 E-5 CHECK VALVE "B" RHR Pll!P DISCHARGE CHECK VALVE 11448-CBM-087A 1 OF 2 E-7 CHECK VALVE "A" RHR Pll!P DISCHARGE CHECK VALVE 1-RH-FCV-1605 11448-CBM-087A 2 OF 2 *c-7 AO BFLY ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 10-000 2 10.000 2 12.000 2 C C B CV CV EV FS ST RHR HEAT EXCHANGERS BYPASS FLOW CONTROL VALVE 1-RH-HCV-1758 11448-CBM-087A 2 OF 2 C-5 AO BFLY 1-RH-MOV-100 RHR HEAT EXCHANGERS DISCHARGE FLOW CONTROL VALVE 11448-CBM-087A 2 OF 2 E-3 MO GATE RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RH-MOV-1700 11448-CBM-087A 1 OF 2 A-5 MO GATE :.* ""* . ,_ ~HR ['!,~~?.-!1&#xa3;:'~1 'f J!l~~:".TU?I  
* VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-RH-005 1-RH-011 DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-087A 1 OF 2 E-5 CHECK VALVE "B" RHR Pll!P DISCHARGE CHECK VALVE 11448-CBM-087A 1 OF 2 E-7 CHECK VALVE "A" RHR Pll!P DISCHARGE CHECK VALVE 1-RH-FCV-1605 11448-CBM-087A 2 OF 2 *c-7 AO BFLY ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 10-000 2 10.000 2 12.000 2 C C B CV CV EV FS ST RHR HEAT EXCHANGERS BYPASS FLOW CONTROL VALVE 1-RH-HCV-1758 11448-CBM-087A 2 OF 2 C-5 AO BFLY 1-RH-MOV-100 RHR HEAT EXCHANGERS DISCHARGE FLOW CONTROL VALVE 11448-CBM-087A 2 OF 2 E-3 MO GATE RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RH-MOV-1700 11448-CBM-087A 1 OF 2 A-5 MO GATE :.* ""* . ,_ ~HR ['!,~~?.-!1&#xa3;:'~1 'f J!l~~:".TU?I
:f~.~-,.~r.-
:f~.~-,.~r.-
! ~~-'*1*: HOT LEG 1-RH-MOV-1701 11448-CBM-087A 1 OF 2 A-4 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 1-RH-MOV-1720A 11448-CBM-087A 2 OF 2 C-3 MO GATE RHR RETURN ISOLATION TO 11 B 11 ACCUMULATOR DISCHARGE LI NE 1-RH-MOV-1720B 11448-CBM-087A 2 OF 2 B-3 MO GATE 1-RH-RV-1721 RHR RETURN ISOLATION TO 11 C 11 ACCUMULATOR DISCHARGE LI NE 11448-CBM-087A 2 OF 2 D-4 RELIEF VALVE 12.000 2 6.000 2 14.000 1 ***:,.'.'."-,:*
! ~~-'*1*: HOT LEG 1-RH-MOV-1701 11448-CBM-087A 1 OF 2 A-4 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 1-RH-MOV-1720A 11448-CBM-087A 2 OF 2 C-3 MO GATE RHR RETURN ISOLATION TO 11 B 11 ACCUMULATOR DISCHARGE LI NE 1-RH-MOV-1720B 11448-CBM-087A 2 OF 2 B-3 MO GATE 1-RH-RV-1721 RHR RETURN ISOLATION TO 11 C 11 ACCUMULATOR DISCHARGE LI NE 11448-CBM-087A 2 OF 2 D-4 RELIEF VALVE 12.000 2 6.000 2 14.000 1 ***:,.'.'."-,:*
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1-CC-1105 1-CC-1106 1-CC-1107 Category:
1-CC-1105 1-CC-1106 1-CC-1107 Category:
C Class 3 1-CC-1188 1-CC-1189 1-CC-1190 Function:
C Class 3 1-CC-1188 1-CC-1189 1-CC-1190 Function:
Component Cooling Supply to RCP Thermal Barrier Isolation Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety function to prevent gross leakage. For the following reasons, it is not practical to test the thermal barrier check valves quarterly or at cold shutdown:  
Component Cooling Supply to RCP Thermal Barrier Isolation Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety function to prevent gross leakage. For the following reasons, it is not practical to test the thermal barrier check valves quarterly or at cold shutdown:
: 1) the valves are inside a locked radiation area located inside containment; therefore, they are not accessible during normal operation, 2) the valves are inaccessible for about 24 hours after cold shutdown due to decontamination activities which must be performed before entry into the area, 3) the reactor cooling pump(s) may be running with the reactor cooling* sy:stem temperature less than 200&deg;F if an RHR loop is , .. , unavailable (in this case the valves and thus cooling to the thermal barriers would normally not be isolated) and 4) the valves have soft seats that are replaced every five years and using pressure to back seat these valves on the more frequent cold shutdown frequency may accelerate the degradation of the soft seats. These valves will be exercised only during refueling outages because the small increase in safety gained by performing this test every cold shutdown does not justify the burden of performing a local back pressure test
: 1) the valves are inside a locked radiation area located inside containment; therefore, they are not accessible during normal operation, 2) the valves are inaccessible for about 24 hours after cold shutdown due to decontamination activities which must be performed before entry into the area, 3) the reactor cooling pump(s) may be running with the reactor cooling* sy:stem temperature less than 200&deg;F if an RHR loop is , .. , unavailable (in this case the valves and thus cooling to the thermal barriers would normally not be isolated) and 4) the valves have soft seats that are replaced every five years and using pressure to back seat these valves on the more frequent cold shutdown frequency may accelerate the degradation of the soft seats. These valves will be exercised only during refueling outages because the small increase in safety gained by performing this test every cold shutdown does not justify the burden of performing a local back pressure test
* 4-81 S1PVI3RO Revision O November 10, 1993 REACTOR REFUELING JUSTIFICATION RRV-7 (Cont.)
* 4-81 S1PVI3RO Revision O November 10, 1993 REACTOR REFUELING JUSTIFICATION RRV-7 (Cont.)
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OF INSERVICE TEST RESULTS * *
OF INSERVICE TEST RESULTS * *
* SlPVIJRO 5.1 PUMP INSERVICE TESTING PROGRAM A record of each pump will be maintained in accordance with OM Part 6, Section 7.1 that includes the following:  
* SlPVIJRO 5.1 PUMP INSERVICE TESTING PROGRAM A record of each pump will be maintained in accordance with OM Part 6, Section 7.1 that includes the following:
: 1) the manufacturer and the manufacturer's model and serial or other identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) a copy of the pump manufacturer' -operating limits. A record of inservice test plans will be maintained in accordance with OM Part 6, Section 7.2 that includes the following:  
: 1) the manufacturer and the manufacturer's model and serial or other identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) a copy of the pump manufacturer' -operating limits. A record of inservice test plans will be maintained in accordance with OM Part 6, Section 7.2 that includes the following:
: 1) the hydraulic circuit to be used, 2) the location and type of measurement for the required test parameters, 3) the reference values and 4) the method of determining reference values which are not directly measured by instrumentation.
: 1) the hydraulic circuit to be used, 2) the location and type of measurement for the required test parameters, 3) the reference values and 4) the method of determining reference values which are not directly measured by instrumentation.
A record of test results will be maintained in accordance with OM Part 6, Section 7.3 that includes the following:  
A record of test results will be maintained in accordance with OM Part 6, Section 7.3 that includes the following:
: 1) pump identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 4-91 Revt~ion o November 10, 1993   
: 1) pump identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 4-91 Revt~ion o November 10, 1993   
* *
* *
* S1PVI3RO 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action, 8) evaluation and justification for changes to reference values and 9) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will he maintained in accordance with OM Part 6, Section 7.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Pwnp Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC
* S1PVI3RO 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action, 8) evaluation and justification for changes to reference values and 9) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will he maintained in accordance with OM Part 6, Section 7.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Pwnp Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC
* 4-92 Rev~ion O November 10, 1993 5.2 *
* 4-92 Rev~ion O November 10, 1993 5.2 *
* S1PVI3RO VALVE INSERVICE TESTING PROGRAM A record of each valve will be maintained in accordance with OM Part 10, Section 6.1 that includes the following:  
* S1PVI3RO VALVE INSERVICE TESTING PROGRAM A record of each valve will be maintained in accordance with OM Part 10, Section 6.1 that includes the following:
: 1) the manufacturer and the manufacturer's model and* serial or other unique identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) preservice test results and 4) limiting value of full stroke time. This IST Program Plan meets the requirements of OM Part 10, Section 6.2, Test Plans. A record of test results will be maintained in accordance with OM Part 10, Section 6.3 that includes the following:  
: 1) the manufacturer and the manufacturer's model and* serial or other unique identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) preservice test results and 4) limiting value of full stroke time. This IST Program Plan meets the requirements of OM Part 10, Section 6.2, Test Plans. A record of test results will be maintained in accordance with OM Part 10, Section 6.3 that includes the following:
: 1) valve identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action and
: 1) valve identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action and
* 8) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will be maintained in accordance with OM Part 10, Section 6.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Valve Inservice Test Program, associated surveillance test procedures and results will be kept 4-93 Revtsion o November 10, 1993   
* 8) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will be maintained in accordance with OM Part 10, Section 6.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Valve Inservice Test Program, associated surveillance test procedures and results will be kept 4-93 Revtsion o November 10, 1993   

Revision as of 09:39, 25 April 2019

IST Program Plan for Pumps & Valves Third Insp Interval 940510-20051, Rev 0
ML18151A278
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/10/1993
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18151A277 List:
References
NUDOCS 9310250224
Download: ML18151A278 (231)
v • d • e


Text

  • ;**' *. ,' . . '* ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 THIRD INTERVAL IST PROGRAM REVISION 0 * .---93102so224-93f1 fo--lJ\ PDR ADOCK 05000~80 'f

  • *
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM The following summary describes the changes from Revision 5 of the Surry Power Station Unit 1 Inservice Testing (IST) Program for the second IST interval to Revision O for the third IST interval.

In addition to describing the changes to the program, the summary gives the approval mechanism for each relief request given in Sections 3.6 and 4.6. Revision 5 for the second IST interval was submitted on July 24, 1992 (Serial No.92-286). The NRC issued a Safety Evaluation Report (SER) for Revision 5, by letter dated March 22, 1993. Changes to Revision 5 were issued to the NRC by letters dated October 8, 1992 (Serial No.92-610) and May 6, 1993 (Serial No.93-046). The summary given below presents all changes to the IST Program from Revision 5 dated July 24, 1993, and identifies the corresponding letter if the change had been subsequently submitted.

Changes to the IST Program Plans are highlighted by a revision bar in the right margin. INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

1.0 INTRODUCTION

The introduction was expanded to describe the transition from the second to the third IST interval, and the approval by the NRC of the 1989 Edition of Section XI. Reference to Section XI, the 1980 Edition through the Winter 1980 Addendum was replaced by reference to addenda through the 1988 Addenda and editions through the 1989 Edition. 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION

3.1. PROGRAM

DEVELOPMENT PHILOSOPHY . References to Section XI, the 1980 Edition through the Winter 1980 Addendum were replaced by references to addenda through the 1988 Addenda and editions through th~ 1989 Edition and ASME/ANSI Edition OM-87, Part 6, Add~nda OMa-1988.

3.2 PROGRAM

IMPLEMENTATION Verb tense changed from future tense to present tense . 2

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  • 3.3 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM PROGRAM ADMINISTRATION Reference to updating the IST Program a least once every 40 months was deleted. program periodically is addressed in an administrative procedure.

minimum of at Updating the internal 3.5 PUMP INSERVICE TEST TABLES UNIT 1 PUMP NUMBER 1-RH-P-lA 1-RH-P-lB 1-RS-P-2A 1-RS-P-2B 1-RS-P-lA 1-RS-P-lB 1-SW-P-lA 1-SW-P-lB 1-SW-P-lC 1-EE-P-lC 3.6 OM Part 6 does not require the measurement of bearing temperature.

Therefore, references to bearing temperature were deleted. COMMENT/PROGRAM CHANGE Program Change: Measurements of inlet and discharge pressures were deleted. Differential pressure is measured directly

  • Withdrew Relief Request P-4. Refer to the discussion in Section 3.6. Withdrew Relief Request P-5. Refer to the discussion in Section 3.6. Program change: The measurement of discharge pressure was deleted. Refer to Relief Request P-11. Program change: Diesel fuel oil transfer pump 1-EE-P~lC was moved from the Unit 2 IST Program to the Unit 1 IST Program. PUMP TEST PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 5. It also contains a description of the approval mechanism for each relief request. That is, the summary indicates whether the approval is: 1) 2) through a position in Generic Letter 89-04, through a previously issued NRC SER or 3
  • 3) Unit 1 Relief Request P-0 P-1* P-2 to P-3 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UH:IT 1 IST PROGRAM obtained using a relief request that will need approval by the NRC. Relief requests requiring NRC approval are marked with an asterisk *. Change This relief request number is no longer active. Reference to using vibration velocity (in/sec) instead of vibration displacement (mils) was deleted because vibration velocity is allowed by OM Part 6. The Revision 5 version of P-1 contained a note describing the use of a minimum value (0.5 in/sec) for vibration reference values. Reference to this minimum reference was retained in the current version. Surry Power station was given a three year period ending in August, 1993 to use the minimum reference value. Surry Power Station requested by letter dated June 29, 1993 (Serial No.93-206) that the use of a minimum value be extended for a period of three years. Use of a minimum vibration reference value was recently granted to North Anna Power station in '"*tilii:::

  • hhC~~.i:{R"':-t*e~eiv:ad
  • 'in' S<;:pi..eillb~r
  • ol 1993 (TAC NOS'~ " M86645 & M86646). No period restrictions were placed on North Anna. These relief request numbers are no longer active. P-4 Relief request is being withdrawn.

The Revision 5 version of P-4 dealt with the outside recirculation spray pumps and requested relief for: 1) testing every 24 months instead of quarterly testing, 2) waiting two minutes instead of five minutes before measuring test quantities and 3) calculating inlet pressure.

  • 4
  • *
  • P-5 P-6 P-7 P-8 to P-10 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UN:IT 1 IST PROGRAM For Item 1, the recirculation spray pumps are deep draft pumps that are maintained dry. OM Part 6, Paragraph

5.5 allows

a 24 month test frequency for this type of pump. For Item 2, OM Part 6, Paragraph 5.6 only requires a two minute run time before measuring the test quantities.

For Item 3, the NRC concluded in the NRC SER dated March 22, 1993 (TAC Noso M84333, M84334, M83165, and M83166) for P-4 that calculating the inlet pressure from the surface level is in accordance with the provisions of the Code, and therefore, relief is not required.

Relief request is being withdrawn.

The Revision 5 version of P-5 dealt with the inside recirculation spray pumps and requested relief for: 1) testing every 24 months instead of quarterly testing and 2) measuring inlet and differential pressure

  • For Item 1, the recirculation spray pumps are deep draft pumps that are maintained dry. OM Part 6, Paragraph

5.5 allows

a 24 month test frequency for this type of pump. For Item 2, the NRC concluded

-*in *the***NfiJ.::**'SER -aateu"l*la:.t'(;ll

~2; 1993* ('1.AC Nos;* **,-;;) M84333, M84334, M83165, and M83166) for P-5 that calculating the inlet pressure from the surface level is in accordance with the provisions of the Code, and therefore, relief is not required.

This relief request number is no longer active. The request to stop measuring inlet pressure was deleted for the residual heat removal pumpso OM-6 does not require measuring inlet pressure if differential pressure is measured directly.

The NRC SER dated August 27, 1990 (TAC Nos. 655555 and 65556) granted approval for the extended cold shutdown testing frequency.

These relief request numbers are no longer active. 5

  • *
  • P-11* P-12 to P-15 P-16 P-17 P-18 P-19 P-20 P-21* ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY UNIT 1 IST PROGRAM The basis was expanded to describe the relationship between flow and tide level for the emergency service water pumps. Because the discharge pressure is constant (i.e., atmospheric pressure) and flow is a function of tide level, discharge pressure need not be measured.

The rest of the relief request that dealt with the use of a reference pump curve was approved by the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166). These relief request numbers are no longer active. The date for installing the two additional control room air conditioning systems was changed from the end of 1992 to the end of 1993. However, the final date for the completion of the instrumentation installation has not changed. This relief request was approved by the NRC SER dated June 26, 1992 (TAC Nos. M80297 and M80298)

  • The acceptance criteria were changed to reflect the criteria in OM Part 6, Table 3b. The basis for this relief request was approved by the NRC SER dated June 26, 1992 (TAC Nos. M80297 and MiW298)
  • This relief request number is no longer active. The acceptance criteria were changed to reflect the criteria in OM Part 6, Table 3b. The basis for this relief request was approved by the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166). Relief request is being withdrawn.

Relief Request P-20 requested relief from measuring the static inlet pressure on a pump that is already in operation.

This relief request is being withdrawn because OM Part 6 does not require measuring static ilUet pressure.

Calibrating the inlet pressure instruments for the boric acid transfer pumps to an accuracy within+/- 2% has proven difficult and may be impractical in 6

  • *
  • 3.6 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UN:IT 1 IST PROGRAM the future with the current instruments.

Calibrating the inlet pressure instruments to an accuracy within+/- 3% would be practical.

With the current o to 15 psig inlet pressure gauges calibrated to+/- 3%, a differential pressure can be determined that exceeds the accuracy requirements for differential pressure if the discharge pressure gauge is calibrated to an accuracy within + 1.75%. Relief for going to the+ 3% is new to this relief request. The remainder of the relief request was approved by the NRC SER dated March 22, 1993 (TAC Nos. M84333, M84334, M83165, and M83166). ALTERNATIVE TESTING FOR NON-CODE PUMPS This section describes why certain non-Code components that are included in the IST Program are not tested to the provisions of the Code and describes the alternative tests. The non-Code alternative tests are not relief requests and do not require approval by the NRC. Unit 1

  • Non.;,.;L;vde Alternative Test Change PNC-1 The Revision 5 version of PNC-1 dealt with the diesel fuel oil pumps and described the following deviations from the Code: 1) measuring test quantities when the pump automatically starts on a low tank level signal instead of waiting five minutes, 2) measuring vibration velocity instead of vibration displacement and bearing temperature and 3) measuring inlet and differential pressure.

The waiting period in Item 1 was changed from five minutes to two minutes. The alternative 7

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  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNI'l' 1 IST PROGRAM test is still necessary even with the waiting period reduced to two minutes by OM Part 6. Item 2 was deleted because OM Part 6 allows the use of vibration velocity and does not require bearing temperature measurement.

Item 3 was also deleted because OM Part 6 does not require the measurement of inlet and differential pressure for positive displacement pumps such as the diesel fuel oil transfer pumps. Only discharge pressure need be measured.

Also, pump 1-EE-P-lC was moved from the Unit 2 IST Program to the Unit 1 IST Program and added to PNC-1. 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION

4.1 PROGRAM

DEVELOPMENT PHILOSOPHY References to Section XI, the 1980 Edition through the Winter 1980 Addendum were replaced by references to addenda through the 1988 Addenda and editions through the 1989 Edition and ASME/ANSI Edition OM-87, Part 10, Addenda OMa-1988.

Verb tense changed from future tense to present tense. References to Section XI were replaced by references to OM Part 10. 4.3 PROGRAM ADMINISTRATION Reference to updating the IST Program a least once every 40 months was deleted. program periodically is addressed in an administrative procedure

  • 8 minimum of at Updating the internal
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNJ:T 1 IST PROGRAM 4.4 VALVE INSERVICE TEST TABLES References to Section XI were replaced by references to OM Part 10 in the description of the valve tables. Valves that were added to the program are identified by an asterisk *. Unit 1 Valve Number 1-BD-TV-lOOA to 1-BD-TV-lOOF 1-cc-1105, 1106, 1-CC-1107, 1188, 1-CC-1189, 1190 1-CC-LCV-101 1-CC-RV-112A to C, 1-CC-RV-119A

& B, Comment Program Change: Relief Request V-34 was withdrawn.

Program Change: Relief Request V-45 was replaced by Reactor Refueling Justification RRV-7. Program Change: Relief Request V-47 was revised to reflect the changes in the new Code. Program Change: withdrawn.

Relief Request V-1 was ..... , .. ,,,~r ... ~,' ** 1:;..C;(;~}(\f".-*122 I *12*3 I

  • 1-CC-RV-124, l-CC-RV-138A

& B 1-CC-RV-150 l-CC-TV-107 1-CC-TV-140A*

& B* This relief valve was removed from the system. Program Change: Valve was deleted from the IST Program. This trip valve was removed from the system. Program Change: Valve was deleted from the IST Program. These trip valves were added to the system to replace 1-CC-TV-107.

They must close to isolate the RCP thermal barrier cooling piping inside containment

  • 9
  • *
  • l-CH-230 l-CH-258 1-CH-267 l-CH-276 1-CH-309 1-CH-FCV-1113B, 1-CH-FCV-1114B ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY UNIT 1 IST PROGRAM Program Change: Valves were added to the IST Program to,be tested to the closed position every cold shutdown.

Refer to Cold Shutdown Justification CSV-27. Following an accident, this volume control tank (VCT) discharge check valve must close after recirculation mode transfer to prevent contaminated sump water from entering the VCT via the seal water heat exchanger relief valve 1-CH-RV-1382B.

Program Change: The valve category was changed from C to A, and a closure test and leakage test were added. The closure test will be performed every reactor refueling as discussed in Reactor Refueling Justification RRV-8. Program Change: Relief Request V-14 was replaced by Reactor Refueling Justification RRV-1. Program Change: This valve was moved from Cold Shutdown Justification csv-20 to Reactor Refueling Justification RRV-6 and the test *frequ.1::mcy was changed from cold shutdown to reactor refueling.

It was determined that the failure of these valves to close will not reduce the operator's ability to manually use the emergency boration system. Program Change: Valves were deleted from the IST Program. 1-CH-LCV-lllSB

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

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

  • 10
  • *
  • 1-CH-MOV-1267A 1-CH-MOV-1269A 1-CH-MOV-1270A 1-CH-RV-1203 1-CH-RV-1382A 1-CH~TV-1204B

& B 1-CS-MOV-lOlA to D 1*-CV-TV-lSOB 1-CW-117 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM These valves are passive. They do not have to change position to fulfill their safety functions.

Program Change: The exercise test was deleted. Program Change: Relief Request V-1 was withdrawn.

Program Change: Relief Request V-34 was withdrawn.

Program Change: Relief Request V-39 was withdrawn.

Program Change: Relief Request V-34 was withdrawn.

At one time, this normally closed manual valve would be opened following initiation of an event to reduce the flowrate through the essential heat exchangers and thus conserve the cooling water inventory in the intake canal. However, it has been determined that this vent valve is no longer required for ,:**:,,,*

    • > .. >.* .. *'** '* ***'* ->* , ..... , ..... '., .. ,., ... ca.naT:'-wdte:;::*
-iuv~llto:t.*y' coucerus*~
    • , .. _ .. *<** .,.,, .... ;.'. 1-DA-TV-lOOA

& B 1-DA-TV-103A

& B 1-DG-TV-lOSA

& B 1-EE-19 1-EE-RV-105 1-EE-SOV-104 1-EE-RV-103 1-EE-RV-105 1-EE-RV-106 1-EE-RV-108 Program Change: Valve was deleted from the IST Program. Program Change: Relief Request V-34 was withdrawn.

Program Change: Relief Request V-34 was withdrawn.

Program Change: These valves were moved from the Unit 2 IST Program to the Unit 1 IST Program. Program Change: Relief Request V-1 was withdrawn.

11

  • 1-EE-SOV-100 1-EE-SOV-101 1-EE-SOV-104 1-EE-SOV-105 1-EG-SOV-100A

& B 3-EG-SOV-300A

& B 1-GW-TV-100 to 1-GW-TV-107, 1-GW-TV-111A

& B 1-IA-446 1*-IA-938, 939 1-IA-RV-114, 115 1-IA-TV-100 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY UNIT 1 IST PROGRAM Program Change: Relief Request V-36 was replaced by Non-Code Alternative Testing VNC-4. Valve 1-EE-SOV-104 was added to VNC-4. Program Change: Relief Request V-37 was replaced by Non-Code Alternative Testing VNC-3. Program Change: Relief Request V-34 was withdrawn.

Program Change: Relief Request V-39 was withdrawn.

Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. Program Change: Relief Request V-1 was withdrawn.

Program Change: Relief Requests V-34 and 39 were withdrawn.

  • '**.*.*

,.,*,,,: .. , ,-1 ... 1u.~-;l'V-100A'tu*,H*;:

,.c:prog:t:'tlfil' Cha..i.191!::*:.

Reli~f Requests v-34*and *39 ... ,,, were withdrawn.

  • 1-MS-NRV-lOlA to B Program Change: Relief Request V-48 was replaced by Cold Shutdown Justification csv-32. 1-MS-RV-lOlA to C Program Change: Relief Request V-47 was revised to reflect the changes in the new Code. 1-MS-SV-101A to c, Program Change: Relief Request V-1 was 1-MS-SV-102A to c, withdrawn.

1-MS-SV-103A to C, 1-MS-SV-104A to C, 1-MS-SV-lOSA to C l~MS-TV-120 This valve is a mechanical trip device valve that is normally open. It trips closed to protect the turbine on the auxiliary 12

  • 1-RC-160 1-RC-PCV-1455C 1-RC-PCV-1456 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM feedwater pump from over speed conditions and has to be locally reset. The valve is passive in the open position and need not be tested * . Program Change: Valve was deleted from the IST Program. Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. These power operated relief valves need to open on setpoint to protect the reactor coolant system from overpressurization when the reactor vessel is cooled down to less than 275 °F. Program Change: A setpoint test was added and Relief Request V-34 was withdrawn

  • 1-RC-SOV-lOOAl

& 2 Program Change: Relief Request V-31 was 1-RC-SOV-lOOBl

& 2 replaced by Cold Shutdown Justification csv-33 and Relief Request V-34 was withdrawn.

1-RC-RV-1551A to C Program Change: Relief Request V-1 was ',"' t-,;,,,, ,, ' ',y-\ ",,t~~'1¥r*

~**.,,1,~

r ..,,,.'"<lj~~~-*1;*1:'wi*i;i.1.di~&*\:i.11~~-~;'*,.

  • _;,,~¥,'-:O**

,*"., .. ,; ... .'.;.,,, .. , .. ,.,, ...... :,_*,,. ,.,,*.1,,.~*:*:.*1;/r.*,;'.,,.'.~*?i" *.. 1,**-*,.:

..... **, .. _* i",:*:,.

  • 1-RH-FCV-1605 1-RH-HCV-1758 1-RH-RV-1721 1-RL-3 & 5 1"-RM-3 1-RM-TV-lOOA to C Program Change: Relief Request V-47 was revised to reflect the changes in the new Code. Program Change: Relief Request V-1 was withdrawn.

Program Change: Relief Request V-39 was withdrawn.

Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. Program Change: Relief Request V-34 was withdrawn

  • 13
  • 1-RS-46 & 52 1-RS-MOV-lSSA

& B 1-SI-25 1-SI-46A & B 1-SI-50 & 58 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM Program Change: Relief Request V-39 was withdrawn.

Program Change: Relief Request V-39 was withdrawn.

Following an accident, this valve isolates the reactor water storage tank (RWST) to prevent contaminated sump water from entering the RWST after recirculation mode transfer.

Program Change: The valve category was changed from C to A, a leakage test were added and Relief Request V-28 was replaced by Reactor Refueling Justification RRV-5. Program Change: Relief Request v-21 was replaced by Reactor Refueling Justification RRV-2. 1-SI-79, 82, 85, Program Change: Relief Request V-27 was 1-SI-88, 91, 94, revised to reference only back seat testing 1-SI-224, 225, of valves l-SI-88 and 238, and 1-SI-91 and 1-SI-226, 227, 239, and 1-SI-94 and 240 in pairs. The 1-SI-228, 229, reference to test frequency was removed from 1-SI-235, 236, V-27 for all valves and replaced by Reactor **** ** **** "l-s:i:~2:31*;

'" 238 ~,,,,,, -,,,_. "":Keiualhig*.-Ju..,i;ificd:~ion RRV-4 .. , .. ' * .. ,.,,,_,.., ,.,."_,.,'

,.,.,. --. -**.:-:,;i~-

  • 1-SI-239, 240, l-SI-241, 242, 243 l-SI-107, 109, 1-SI-128, 130, l-SI-145, 147 l-SI-150 & 174 1-SI-201 & 207 Program Change: The justification for testing every refueling was moved to Reactor Refueling Justification RRV-3. Relief Request V-26 was revised to describe a sampling plan for non-intrusive testing techniques.

Program Change: Relief Request V-39 was withdrawn.

These check valves are on a 3/4 inch supply line from the RWST to the LHSI pump seals. This line has been permanently isolated.

Therefore, the valves no longer have a safety function

  • 14
  • * " -. )* ..
  • 1-SI-234 1-SI-301 & 311 1-SI-410 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY U!U:T 1 IST PROGRAM Program Change: Valves were deleted from the IST Program. Program Change: Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. Program Change: Relief Request V-39 was withdrawn.

Program Change: Relief Request V-28 was replaced by Reactor Refueling Justification RRV-5. 1-SI-MOV-1860A

& B Program Change: Relief Request V-39 was withdrawn.

1-SI-MOV-1867C

& D Program Change: Relief Request V-39 was 1-SI-MOV-1869A withdrawn.

1-SI-MOV-1885A to 1-SI-MOV-1885D Following an accident, these valves isolate the reactor water storage tank (RWST) to prevent contaminated sump water from entering the RWST after recirculation mode transfer.

Program Change: The valve category was ,-:* i*;*,::'.,'f'i',**:*~*,::*-:-:,*r

  • .\:.:---~

.. :_.-.. .,..: .. ;;J.~ ---~ i:-:*:*:.*cl1a11ged:

  • f1.-:u.an~*B:-~:-t.O'""A*,"
  • and a leakage *test' *was ~r:. added. 1-SI-RV-1845A to c Program Change: Relief Request V-1 was withdrawn.

1-SI-TV-lOlB Program Change: Relief Request V-34 was withdrawn.

1-SS-TV-lOOA

& B, 1-SS-TV-lOlA

& B, 1-SS-TV-102A

& B, 1-SS-TV-104A

& B, 1-SS-TV-106A

& B 1-SW-108 1-SW-113 1-SW-130 1-SW-262 1-SW-268 Program Change: Relief Request V-34 was withdrawn.

The design basis for the charging pump service water system is being reevaluated.

A full flow acceptance criteria will not be available until this evaluation is complete.

In the mean time, these valves will be 15

  • *
  • 1-SW-263 1-SW-PCV-lOOA to 1-SW-PCV-lOOC, 1-SW-PCV-lOlA to 1-SW-PCV-lOlC, 1-SW-TCV-lOSA to 1-SW-TCV-lOSC 1-VG-TV-109A

& B 1-VP-12 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM disassembled and inspected.

Program Change: The valves will be disassembled and inspected.

Refer to Relief Request v-so. Also, the ASME Class for valve l-SW-130 was changed from Class 3 to Class. This valve has no remote position indication.

Therefore, there are no Section XI test requirements.

Program Change: Valve was deleted from the IST Program. Program Change: Relief Request V-47 was revised to reflect the changes in the new Code. Program Change: Relief Request V-34 was withdrawn.

Program Change: Relief Request V-44 was *.

  • r~plaeed hy Rea~~or .Refueling J*ustification RRV-6. 1-VS-MOV-lOOA to Program Change: Relief Request V-39 was 1-VS-MOV-lOOD, withdrawn.

1-VS-MOV-101

& 102 16

  • *
  • 4.5 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UN:IT 1 IST PROGRAM VALVE TEST PROGRAM RELIEF REQUESTS The following summarizes the changes to relief requests since Revision 5. It also contains a description of the approval mechanism.

for each relief request. That is, the summary indicates whether the approval is: 1) through a position in Generic Letter 89-04, 2) through a previously issued NRC SER or 3) obtained using a relief request that will need approval by the NRC. Relief requests requiring NRC approval are marked with an asterisk ** Unit 1 Relief Request Change V-1 V-2 to V-4 V-5 V-6 to V-13 Relief request is being withdrawn.

The Revision 5 version of V-1 requested relief from testing safety and relief valves in accordance with PTC-25.3-1976 and to use OM Part 1 instead. OM Part 10 references OM Part 1 for safety and relief valve testing. These relief request numbers are no longer active. The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-5 (l-FW-10, 41 and 72) must be disassembled every refueling outage. V-5 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2. These relief request numbers are no longer active. 17

  • *
  • V-14 V-15 to V-19 V-20 V-21 V.;....22 to V-25 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM Relief request is being withdrawn.

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

According to OM Part 10, Section 6.2, the test plan must justify the deferral of stroke testing. These relief request numbers are no longer active. The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in v-20 (l-SI-47 and 56) must be disassembled every refueling outage. v-20 describes the disassembly and inspection of one valve from a group of two valves. This test frequency is in accordance with Generic Letter 89-04, Position 2. Relief request is being withdrawn.

Relief Request v-:21 *was '"replaced by Reawtor Refueling-

    • *-* * *-* * * -:-, -*' ,,, Justification RRV-2. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

These relief request numbers are no longer active. Relief Request V-26 was revised to describe a sampling program for non-intrusive techniques used in testing the SI accumulator discharge check valves. The sampling program is as follows. During the first refueling outage where 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-18

  • V-27 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNJ:T 1 IST PROGRAM intrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified.

In this case, all valves in the group will be subjected to the non-intrusive techniques.

The sampling program is in accordance with Generic Letter 89-04, position 2. A similar non-intrusive technique sampling program was approved for use by North Anna Power Station in the NRC SER received in September of 1993(TAC NOS. M86645 & M86646). The justification for going to a reactor refueling frequency was moved to RRV-3. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

The alternative test method was changed from disassembly and inspection to using non-intrusive techniques to verify that the check valves go to the full open position

  • The portion of Relief Request V-27 which dealt with test frequency was replaced by Reactor Refueling Justification RRV-4. RRV-4 deals with the cold leg and hot leg SI check valves. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves ., .. y_., .. 'c:<,.:v-,,.-,., >,,.,,. -. -.. *,., *'- *** c.,*: to* btai *-te;!;j'i;i,;i\}**-uu:ciHg*::i'~di.;i;o.C ref*aelings*'if testing*'

~-V-28

  • during normal operation and cold shutdown is impractical.

The portion of Relief Request V-27 which dealt with check valve pairs 1-SI-88 and 238, l-SI-91 and 239, and 1-SI-94 and 240 remains. Relief request is being withdrawn.

Relief Request V-28 was replaced by Reactor Refueling Justification RRV-5. RRV-5 deals with the SI cross tie check valves (1-SI-25 and 410). OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

The Revision 5 version of V-28 indicated that 1-SI-25 would be disassembled and inspected every other outage. Reference to the disassembly and inspection every other outage was deleted from RRV-5. The test method and frequency are in accordance with OM Part 10, Paragraph 4.3.2.4(c)

  • 19
  • * ] -** ,: ** ~-J.' ' ' *
  • V-29 & V-30 V-31 V-32 & V-33 V-34 _;,,*:*,*.:,..

-V-35 V-36 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY UNIT 1 IST PROGRAM These relief request numbers are no longer active. Relief request is being withdrawn.

Relief Request V-31 was replaced by Cold Shutdown Justification CSV-33. CSV-33 deals with the head vent isolation valves and was originally a relief request because there could exist plant conditions during some cold shutdowns that prevent testing of these valves. Because OM Part 10 allows for a testing frequency as long as a reactor refueling frequency, relief from Code requirements is no longer necessary.

As shown by the test frequency description, the appropriate test plan justification is a cold shutdown justification and not a reactor refueling justification.

These relief request numbers are no longer active. Relief request is being withdrawn.

The Revision 5 version of Relief Request V-34 requested relief from applying an alert range acceptance criteria for stroke time to rapid acting valves (i.e., valves that stroke in less than two seconds).

OM Part 10, Paragraph 4.2.1.B(e) addresses rapid . acting .. Viil ",f~S *~** :::..::he:ce:f Di:"i::l 1 :relie.i:

f .t*olil. *Coue ... , .. * ,*. .. :,-,***.*0* requirements is no longer necessary.

This relief request number is no longer active. Relief request is being withdrawn.

Relief Request V-36 was replaced by Non-Code Alternative Testing VNC-4. The valves in VNC-4 (1-EE-SOV-100, 101 and 105) are non-Code valves. According to the Minutes of Public Meetings on Generic Letter 89-04, "If non-Code components are included in the ASME Code IST program (or some other developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.SSa) do not require a 'request for relief' to be submitted to the staff. Nevertheless, documentation that provides assurance of the continued operability of the Code components through the performed tests should be available at the plant site." The non-Code 20

  • *
  • V-37 V-38 V-39 V-40 V-41 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY ON:IT 1 IST PROGRAM alternative testing given in Section 4.8 documents the method for showing continued operability for these valves. Relief request is being withdrawn.

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

This relief request number is no longer active. Relief request is being withdrawn.

The Revision 5 version of Relief Request V-39 requested relief from individually leak testing containment isolation valves and allowing groups of valves to be tested together.

OM Part 10, Paragraphs 4.2.2.J(e) and (f) allow for the testing of valve combinations.

Therefore, relief from Code requirements is no longer necessary

  • This relief request number is no longer active. The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, ,Hui1:>>a1:u::1e:wbly
  • every:-re:fi.:.ll'::li:i:,y* (ili.taye
  • t;o ve:i'ify ,,, .. ,. ** ,;,** operability of check valves may be used." This sentence implies that each check valve in the groups given in V-41 (1-FW-144, 159 and 174 in one group and 1-FW-148, 163 and 178 in another group) must be disassembled every refueling outage. v-41 describes the disassembly and inspection of one valve from each group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2. These check valves can be disassembled while the plant is operating.

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. Also, reference to part stroke exercising every three months was deleted. There is no flow 21

  • V-42
  • V-43 V-44
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM instrumentation or other means to detect partial flow. The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-42 (1-MS-176, 178 and 182) must be disassembled every refueling outage. V-42 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04, Position 2. These check valves can be disassembled while the plant is operating.

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disass1:wbly

  • every ref*u.eli.ral:J outage to verify*' operability of check valves may be used." This sentence implies that each check valve in the groups given in V-43 (l-CS-105 and 127 in one group, 1-CS-13 and 24 in another group and 1-RS-11 and 17 in another group) must be disassembled every refueling outage. V-43 describes the disassembly and inspection of one valve from each group of two valves. This test frequency is in accordance with Generic Letter 89-04, Position 2. Relief request is being withdrawn.

Relief Request V-44 was replaced by Reactor Refueling Justification RRV-6. RRV-6 deals with certain containment isolation valves located inside containment that are subject to leakage testing. The Revision 5 version of V-44 requested relief from performing a back seat test every cold shutdown.

OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during 22

  • V-45 V-46 *
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY UNIT 1 IST PROGRAM reactor refuelings if testing during normal operation and cold shutdown is impractical.

Relief request is being withdrawn.

Relief Request V-45 was replaced by Reactor Refueling Justification RRV-7. RRV-7 deals with the RCP thermal barrier isolation check valves located inside containment that are subject to back seat testing. The Revision 5 version of V-45 requested relief from performing a back seat test every cold shutdown.

OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for valves to be tested during reactor refuelings if testing during normal operation and cold shutdown is impractical.

The Code requirement reference was changed from Section XI, IWV to OM Part 10. OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each check valve in the group given in V-46 (1-SW-313, 323 and 2-SW-333) must be disassembled every refueling outage. V-46 describes the disassembly and inspection of one valve from a group of three valves. This test frequency is in accordance with Generic Letter 89-04; Positicni

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

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. The Revision 5 version of V-47 submitted on July 24, 1992, requested relief from determining the alert status as required by the old Code. In the NRC SER received in March of 1993, the NRC reviewer determined that V-47 was not necessary because OM Part 10 does not require the determination of the alert acceptance criteria.

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

Also, relief from measuring the full-stroke time 23

  • V-48 V-49
  • V-50 .. ,.-.* , *'-~ -,'* -: ... ;uc.*"** *
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM from the initiation of the actuating signal was added. Relief request is being withdrawn.

Interim Relief Request V-48 was replaced by Cold Shutdown Justification CSV-32. The Revision 5 version of V-48 requested an interim period from testing the main steam non-return valves until an alternative test method could be developed.

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

The Revision 5 version ,of V-49 requested relief from IWV-3427(b) which required trending of leakages for Category A valves larger than six inches. OM-Part 10 does not have a similar requirement.

Therefore, relief from Code requirements is no longer necessary

  • These relief request is being added for check valves 1-SW-108, 113, 130, 262 and 268. The design basis for the charging pump service water system is being reevaluated.

A full flow acceptance criteria will not be available until ** this*'evaluat.iun is **cuiu}:)lei:e.*

In the mean time, , ... :*,* . these valves will be disassembled and inspected.

The test frequency is in accordance with Generic Letter 89-04, Position 2. These check valves can be disassembled while the plant is operating.

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. This relief request is being added and applies to containment isolation valves subject to Appendix J, Type c leak testing. For cases where a valve has exceeded its permissible leakage rate but the overall containment leakage is below 0.6La, and the repair or replacement of the valve will have an adverse impact on plant startup and/or continued operation, an evaluation can be used as 24

  • *
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNJ:T 1 IST PROGRAM corrective action. A similar relief request was approved for use by North Anna Power Station in the NRC SER received in September of 1993(TAC NOS. M86645 & M86646). 4.6 VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS References to IWV were replaced with *references to OM Part 10. Also, a section was added to each justification which gives a summary of the testing frequency.

The following summarizes the changes to cold shutdown justifications since Revisions.

Unit 1 Cold Shutdown Just csv..-1 CSV-2 and CSV-3 CSV-4 CSV-5 CSV-6 CSV-7 to CSV-9 CSV-10 CSV-11 csv-12 Change Added test frequency summary. These cold shutdown justification numbers ar~ no longer active. Reference to full flow testing check valves 1-. FW-142*?'*157*'a1iid**172 wa:=; a~&ed..* Al&o; a test*-**, frequency summary was added. Added test frequency summary. Added the phrase "when the reactor coolant pumps are secured" and a test frequency summary. Added test frequency summaries.

The relief valve setting was changed from 700 psig to 600 psig. Also, a test frequency summary-was added. Added test frequency summary. This cold shutdown justification number is no longer active

  • 25
  • **
  • CVS-13 CSV-14 to CSV-18 CSV-19 CSV-20 CSV-21 CSV-22 to CSV-24 CSV-25 & CSV-26 CSV-27 CSV-28 CSV-29 to CSV-31 CSV-32 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM Added the phrase "when the reactor coolant pumps are secured" and a test frequency summary. Added test frequency summaries.

Deleted reference to partial stroke testing of check valves 1-CH-225, 227 and 229. These valves will be full stroke tested every quarter when the boric acid concentration is above* 100 ppm. Also, a test frequency summary was added. Replaced by Reactor Refueling Justification RRV-6. Added test frequency summary. These cold shutdown justification numbers are no longer active. Added test frequency summaries.

Deleted valve l-CC-TV-107 and added valves 1-cc-TV-140A and B. Also, a test frequency s\:liwl1a:cy was added. Deleted reference to part stroke testing the main feedwater bypass valves every three months and added an explanation as to why this testing is not necessary.

Also, a test frequency summary was added. Added test frequency summaries.

Cold Shutdown Justification CSV-32 was added to the IST Program to replace Interim Relief Request V-48. The Revision 5 version of V-48 requested an interim period from testing the main steam non-return valves until an alternative.test method could be developed.

This alternative method was developed during the Surry Unit 2 1993 refueling outage and is described in CSV-32. CSV-32 was sent to the 26

  • *
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UN:IT 1 IST PROGRAM NRC by letter dated May 6, 1993 (Serial No.93-046). CSV-33 Cold Shutdown Justification CSV-33 was added to the IST Program to replace Relief Request V-31. CSV-33 deals with the head vent isolation valves and was originally a relief request because there could exist plant conditions during some cold shutdowns that prevent testing of these valves. Because OM Part 10 allows for a testing frequency as long as a reactor refueling frequency, relief from Code requirements is no longer necessary.

As shown by the test frequency description, the appropriate test plan justification is a cold shutdown justification and not a reactor refueling justification.

4.7 VALVE

TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS Section 4.7 was added to the IST Program and the Revision 5 Section 4.7 was renumbered to Section 4.8. OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during reactor refueling (but not more frequently than every three months),.

if"t.he .. :valves' c~:~uu,:,t be *exercised**

dm:.' h1g** f,Q:c*.u1al 0 ,**,

  • operation or cold shutdown.

IWV allowed testing to be deferred only to cold shutdowns.

Therefore, no request for relief for testing every reactor refueling is necessary.

A number of relief requests were replaced by reactor refueling justifications.

Unit 1 Reactor Refuel Just Change RRV-1 RRV-2 Reactor Refueling Justification RRV-1 was added to the IST Program to replace Relief Request V-14. No other changes were made to the justification.

Reactor Refueling Justification RRV-2 was added to the IST Program to replace Relief Request v-21. No other changes were made to the justification

  • 27
  • RRV-3 RRV-4 RRV-5
  • RRV-6 RRV-7 RRV-8
  • ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SURRY UNIT 1 IST PROGRAM The justification for going to a reactor refueling frequency was moved from V-26 to RRV-3 for the SI accumulator discharge check valves. The alternative test method was changed from disassembly and inspection to using non-intrusive techniques to verify that the check valves go to the full open position.

A sampling program will be applied to the non-intrusive techniques as described in Relief Request V-26. Reactor Refueling Justification RRV-4 was added to the IST Program to replace the test frequency descriptions previously found in Relief Request V-27 for the hot leg, cold leg and HHSI check valves. Reactor Refueling Justification RRV-5 was added to the IST Program to replace Relief Request V-28. The Revision 5 version of V-28 indicated that 1-SI-25 would be disassembled and inspected every other outage. Reference to the disassembly and inspection every other outage was deleted from RRV-5. The test method and frequency are in accordance with OM Part 10, Paragraph 4.3.2.4(c).

Reactor Refueling Justification RRV-6 was added to

  • the IST*PL"ug:t.'a:ut'tu*

replace-Relief Rey:ue=:it

  • V-44'~':""*" ,,; No other changes were made to the justification.

Reactor Refueling Justification RRV-7 was added to the IST Program to replace Relief Request V-45 and cold Shutdown Justification csv-20. Reactor Refueling Justification RRV-8 was added to the IST Program to present the basis for testing the VCT discharge check valve 1-CH-230 closed every reactor refueling

  • 28
  • * * --------~--

---4.8 ATTACHMENT 1

SUMMARY

OF CHANGES TO THE SORRY tJNJ:T 1 IST PROGRAM ALTERNATIVE TESTING FOR NON-CODE VALVES The Revision 5 Section 4.7 was renumbered to Section 4.8. Unit 1 Non-Code Alternative Test Change VNC-1 VNC-2 VNC-3 VNC-4 There is no change to VNC-1. Non-Code alternative testing is being withdrawn.

VNC-2 dealt with valve 1-CW-117 which was deleted from the IST Program. The air start system solenoid valves SOV-lOOA and B, and 3-EG-SOV-300A and B were added to VNC-3. These valves were covered by Relief Request V-37 in Revisions

  • Non-Code Alternative Testing VNC-4 was added to the IST Program to replace Relief Request V-36. Also, valve 1-EE-SOV-104 was moved from the Unit 2 IST Program to the Unit 1 IST Pro1;r..cal1l*-*ariu.*
  • ciuuti!u
  • to * *,,.-NC-4
  • *
  • 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 PUMP INSERVICE TESTING PROGRAM References to IWP were replaced with references to OM Part 6, Sections 7.1 to 7.4. 5.2 VALVE INSERVICE TESTING PROGRAM References to IWV were replaced with references to OM Part 10, Sections 6.1 to 6.4
  • 29
  • *
  • VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES THIRD INSPECTION INTERVAL MAY 10, 1994 -MAY 10, 2004 REVISION 0 ADDRESSES:

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

  • *
  • TABLE OF CONTENTS
  • INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES

1.0 INTRODUCTION

2.0 PROGRAM

DESCRIPTION 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION

3.1 Program

Development Philosophy

3.2 Program

Implementation

3.3 Program

Administration 3.4 Pump Reference List 3.5 Pump Inservice Test Tables 3.6 Pump Test Program Relief Requests 3.7 Alternative Testing for Non-Code Pumps 4.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 Program Development Philosophy Program Implementation Program Administration Valve Inservice Test Table Valve Test Program Relief Requests Valve Test Program Cold Shutdown Justifications Valve Test Program Reactor Refueling Justifications Alternative Testing for Non-Code Valves 5.0 REPORTING OF INSERVICE TEST RESULTS 5.1 Pump Inservice Test Program 5.2 Valve Inservice Test Program 6.0 QUALITY ASSURANCE PROGRAM ii S1PVI3RO Revision o November 10, 1993 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES *

1.0 INTRODUCTION

  • S1PVI3RO This Pump and Valve Inservice Test (IST} Program Plan is applicable to the Surry Power Station Unit 1 which began commercial operation on December 22, 1972. The IST Program Plan is comprised of two independent subprograms

-the Pump Inservice Test Program and the Valve Inservice Test Program. The development, implementation and administration of these two programs are detailed in subsequent sections.

This IST Program Plan applies to the third 10-year IST interval for Surry Power Station Unit 1. The third interval starts on May 10, 1994 and ends by May 10, 2004. Surry Power Station requested an exemption from Section XI of the ASME Code to extend the Surry Unit 1 second 10-year IST interval for pumps and valves from December 22 ,1992 to May 10, 1994 to coincide with the end of the second 10-year IST interval for Unit 2 by letter to the NRC dated November 10, 1992. The NRC responded by letter dated February 16, 1993 granting this exemption.

The Code of Federal Register 10CFR50.55a(f}

(4} (ii) states in part that the 10-year IST interval "must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b} of this section 12 months prior to the start of the 120-month interval." As described in paragraph (b)(2} of 10 CFR 50.55a that was approved for use on September a, 1992 by the Federal

  • Register, Vol. 57, No. 152, "references to Section XI of the ASME Boiler and Pressure Vessel Code refer to Section XI, Divh.ion 1, and include addenda through the 1988 Addenda and editions through the 1989 Edition." The IST Program Plan for the third 10-year interval for Surry Unit 1 complies with these addenda and edition
  • 1-1 Rev:i,_sion o November 10, 1993 2.0 * *
  • S1PVI3RO PROGRAM DESCRIPTION This Inservice Testing Program for ISI Class 1, 2, 3 and NC pumps and valves meets the requirements of Subsections IWP and IWV of Section XI of the ASME Boiler and Pressure Vessel Code, addenda through the 1988 Addenda and editions through the 1989 Edition. Where these requirements are determined to be impractical, specific requests for relief have been written and included in the program plan attached
  • 2-1 Rev.i,_sion o November 10, 1993 3.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION
  • *
  • SlPVI3RO 3.1 PROGRAM DEVELOPMENT PHILOSOPHY

3.2 Highly

reliable safety-grade equipment is a vital consideration in the operation of a nuclear generating station. To help assure operability, the Surry Power station Unit 1 Pump Inservice Test Program was developed.

The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operating parameters of vital pumps and to initiate corrective action when necessary.

As described in Section 2, the Program must meet the requirements of Subsection IWP, of Section XI of the ASME Boiler and Pressure Vessel Code. Subsection IWP, addenda through the 1988 Addenda and editions through the 1989 Edition, references Part 6, Edition OM-87, ASME/ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988. Therefore, the Program is based on the requirements of Part 6, along with NRC staff guidelines provided in Generic Letter 89-04 for complying with certain provisions of 10CFR50.55a(f).

The Nuclear Regulatory Commission and Code Committee recognized that design differences among plants may render impractical certain Code requirements.

Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code. Alternate testing requirements have been proposed when warranted.

PROGRAM IMPLEMENTATION Surveillance testing is performed to detect equipment malfunction or degradation and to initiate corrective action. Since the safeguards pumps are normally in standby mode, periodic testing of this equipment is especially important.

The Surry Power Station Unit 1 Inservice Test Program provides a schedule for testing safety-grade pumps and is implemented as part of normal periodic surveillance testing. Reference data is gathered during initial surveillance tests. In most cases, test parameters are measured with normal plant instrumentation.

This approach simplifies the test program and promotes timely completion of periodic surveillance testing. When permanently installed instrumentation is not available, portable instrumentation is used to record the required parameters

  • 3-1 Revision o November 10, 1993
  • *
  • S1PVI3RO During subsequent surveillance tests, flow rate is normally selected as the independent test parameter and is set to match the reference flow rate. Other hydraulic and mechanical performance parameters are measured and evaluated against the appropriate reference values. The results of such evaluations determine whether or not corrective action is warranted.

Each pump in the Pump Inservice Test Program is tested according to a detailed test procedure.

The procedure include, as minimum: 1)

References:

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

2) Purpose: This section identifies test objectives.
3) Initial Conditions:

Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use. 4) Precautions:

Precautions should be established to alert the individual performing the task to those situations in which important measures should be taken early or where extreme care should be used to protect equipment and personnel.

Cautionary notes applicable to specific steps in the procedure should be included in the main body of the procedure as appropriate and should be identified as such. 5) Instructions:

The main body of a procedure should contain step by step instructions in the degree of detail necessary for performing a required test. 6) Acceptance Criteria:

The ranges within which test data are considered acceptable are established and included in the test procedure.

In the event that data fall outside the acceptable range, operator action is governed by approved station procedures.

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

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

  • 3-2 Rev~~ion o November 10, 1993 3.3
  • 3.4
  • PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power station are responsible for administration and execution of the Pump Inservice Test Program. The third 10-year interval IST Program will be officially implemented on May 10, 1994 and governs pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a{f)

(4). PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES". 1-CH-P-lA 1-CH-P-lB 1-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for the Safety Injection system and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11448-CBM-SSB, Sheet 2 . 1-SI-P-lA 1-SI-P-1B Low Head Safety Injection Pumps provides low pressure ,._ .... *'.**}****

"'*

  • safecy injeci:.ion'

'to* ti1e** core for lung term* coolir,g a:i.1d as a backup to accumulators.

See drawing 11448-CBM-89A, Sheet 1.

  • S1PVI3RO 1-CS-P-lA 1-CS-P-lB Containment Spray Pumps provide a cooled, chemically treated, borated spray to reduce containment pressure following a loss of coolant accident.

See drawing 11448-CBM-84A, Sheet 2. 1-RS-P-2A 1-RS-P-2B outside Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident.

See drawing 11448-CBM-84B, Sheet 2 . 3-3 Revi~ion o Novelilber 10, 1993

  • *
  • S1PVI3RO 1-RS-P-lA 1-RS-P-1B Inside Recirculation Spray Pumps aid the containment spray system in reducing containment pressure rapidly following a loss of coolant accident.

see drawing 11448-CBM-84B, Sheet 1. 1-FW-P-JA 1-FW-P-JB 1-FW-P-2 Auxiliary Feedwater Pumps supply the steam generator with feedwater in the event of a complete loss of normal feedwater.

See drawing 11448-CBM-GSA, Sheet 3. 1-RH-P-lA 1-RH-P-1B The function of Residual Heat Removal Pumps is to remove heat energy from the core when the Reactor Coolant system is below 350°F. See drawing 11448-CBM-87A, Sheet 1. 1-CC-P-lA 1-CC-P-lB Component Cooling Water Pumps are used to supply water to remove heat from the Residual Heat Removal System. See drawing 11448-CBM-72D, Sheet 1. 1-CH-P-2A 1-CH-P-2B Boric Acid Transfer Pumps supply boric acid to suction of charging pumps via normal coolant boration and emergency makeup. See drawing 11448-CBM-SSA, .Sheet 1. 1-CC-P-2A 1-CC-P-2B Charging Pump Cooling Water Pumps provide water to transfer heat from the charging pump mechanical seals. See drawing 11448-CBM-71B, Sheet 2. 1-SW-P-lOA 1-SW-P-lOB Charging Pump Service water Pumps provide cooling water for Charging Pump Cooling Water Systems. See drawing 11448-CBM-71B, Sheet 1

  • 3-4 Revi~ion o Nov~:mber 10, 1993
  • *
  • S1PVI3RO 1-SW-P-lA 1-sw-P-lB 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 DBA. See drawing 11448-CBM-71A, Sheet 1. 1-EE-P-lA 1_;EE-P-1C 1-EE-P-lD 1-EE-P-lF Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank. See drawing 11448-CBB-38A, Sheet 2. 1-VS-P-lA 1-VS-P-lB 1-vs-P-1c 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, Sheet 1 . 1-VS-P-2A 1-VS-P-2B 1-VS-P-2C

  • ~-,,,,_* * .. Haid: ccm~:.t:'ol**Room

.. Air .. Conditioning System* chiller siue *, pumps circulated chilled water to the main control room and switch ge~r room air handling units. See drawing 11448-FB-41A, Sheet 2 . 3-5 Revi~;;ion o Noveinber 10, 1993 3.5 * *

  • S1PVI3RO PUMP INSERVICE TEST TABLES This tabulation identifies the pumps to be tested, code classes, required test quantities and frequencies.

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

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

For non-Code pumps, a request for relief is not necessary when provisions of the Code cannot be met. Section 3.7 contains a discussion of the testing requirements for non-Code pumps and descriptions of alternative testing in cases where the provisions of the Code cannot be met. To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the table headings and abbreviations are provided below. 1) Pump Number -Each pump in the plant has a unique "tag" number which identifies the system to which the pump belongs. 2) Code Class -ASME Code Class of each pump as per 10CFRS0.55a and Regulatory Guide 1.26

  • Note: NC is for non-Code pumps. These pumps are important to safety but are not in systems that are classified ASME Class 1, 2 or 3. ** 3) * ::;ystem &e::ii'l:::li::*'" -*:t:ithe.c FIX-for a test loop with a fixed system resistance or VAR for a test loop with a system resistance that can be varied. 4) The required Section XI test quantities of Inlet Pressure, Differential Pressure (Discharge Pressure is not a required test quantity but is listed for clarity), Flow Rate, Vibration, Pump Speed and Lubrication Level/Pressure are given as column headings.

The following abbreviations are used to describe the test status: Q -the test will be performed on a quarterly basis CSD -the test will be performed every cold shutdown.

A relief request explains the need for deviating from Section XI test frequency requirements 3-6 Revision o November 10, 1993

  • *
  • S1PVIJRO NA -the test is not applicable, see corresponding relief request RR -the test will be performed every reactor refueling.

A relief request explains the need for deviating from Section XI test frequency requirements.

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

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

No relief is necessary . 3-7 Revi~ion o November 10, 1993

  • PUMP IN SERVICE Pump ASME System Inlet Disch Diff Flow !dent. Class Resist Press Press Press Rate 1-CH-P-lA 2 VAR 0 0 0 0 1-CH-P-lB 2 VAR 0 0 0 0 1-CH-P-lC 2 VAR 0 0 0 Q 1-SI-P-lA 2 FIX Q 0 0 0 1-SI-P-lB 2 FIX 0 0 0 0 1-CS-P-lA 2 FIX 0 0 0 0 J 1-CS-P-lB 2 FIX Q 0 Q Q* 1-RS-P-2A 2 FIX 2Y 2Y 2Y 2Y 1-RS-P-2B 2 FIX 2Y 2Y 2Y 2Y 1-RS-P-lA 2 VAR RR RR RR RR 1-RS-P-lB 2 VAR RR RR RR RR 1-FW-P-JA 3 VAR 0 0 0 0 1-FW-P-JB 3 VAR 0 0 0 Q 1-FW-P-2 3 VAR 0 Q 0 Q 1-RH-P-lA 2 VAR NA NA CSD CSD 1-RH-P-lB 2 VAR NA NA CSD CSD 3-8 S1PVI3RO TEST TABLE Pump Vibration Speed 0 NA 0 NA 0 NA 0 NA 0 NA 0 NA 0 NA 2Y NA 2Y NA RR NA RR NA 0 NA Q NA Q Q CSD NA CSD NA
  • Lubrication Relief Level/Pressure Request 0 1 0 1 0 1 NA 1 NA 1 Q 1 Q 1 NA 1 NA 1 NA 1 NA 1 Q 1 0 1 0 1 NA 1. 7 NA 1,7 Revision O November 10, 1993 PUMP INSERVICE TEST TABLE Pump ASME System Inlet Disch Diff Flow Pump Lubrication Relief !dent. Class Resist Press Press Press Rate Vibration Speed Level/Pressure Request 1-CC-P-lA 3 VAR Q Q Q Q Q NA Q 1.19 1-CC-P-lB 3 VAR Q Q Q Q Q NA Q 1, 19 ,, ,, 1-CH-P-2A 2 VAR Q Q Q Q Q NA NA 1.21 1-CH-P-2B 2 VAR Q Q Q Q Q NA NA 1.21 1-CC-P-2A 3 VAR Q Q Q Q Q NA NA 1 1-CC-P-2B 3 VAR Q Q Q Q Q NA NA 1 1-SW-P-lOA 3 VAR Q Q Q Q Q NA NA 1 1-SW-P-lOB 3 VAR Q Q Q Q 0 NA NA 1 1-sw-P~1A 3 FIX 0 NA Q Q Q Q Q 1.11 1-SW-P-lB 3 FIX Q NA Q Q Q Q Q 1, 11 1-SW-P-lC 3 FIX Q NA Q Q Q Q Q 1, 11 1-EE-P-lA NC FIX NA Q NA Q Q NA NA 1.PNC-1 1-EE-P-lC NC FIX NA Q NA Q Q NA NA 1.PNC-1 1-EE-P-lD NC FIX NA Q NA Q Q NA NA 1.PNC-1 1-EE-P-lF NC FIX NA Q NA Q Q NA NA 1.PNC-1 Note: PNC-1 is not a request for relief but a description of alternative testing for non-Code pumps. Refer to Section 3.7. 3-9 Revision 0 S1PVI3R.
  • November-.1993
  • Pump !dent. 1-VS-P-lA l-VS-P-1B 1-VS-P-1C 1-VS-P-2A 1-VS-P-2B l-VS-P-2C

,, ,, S1PVI3RO ASME Class 3 3 3 3 3 3 System Inlet Disch Resist Press Press VAR NA 0 VAR NA 0 VAR NA 0 VAR 0 0 VAR Q 0 VAR Q Q

  • PUMP IN SERVICE Diff Flow Press Rate NA NA NA NA NA NA 0 Q 0 Q 0 Q 3-10 TEST TABLE Pump Vibration Speed 0 NA 0 NA 0 NA Q NA Q NA Q NA
  • Lubrication Relief Level/Pressure Request NA 1.16 NA 1.16 NA 1.16 NA 1.17 NA 1.17 NA 1.17 Revision O November 10, 1993
  • *
  • S1PVI3RO 3.6 *PUMP TEST PROGRAM RELIEF REQUESTS Relief Requests identify code requirements which are impractical for Surry Unit 1 and provide justification for the requested exception.

Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed

  • 3-11 Rev,i.sion o November 10, 1993
  • *
  • S1PVI3RO RELIEF REQUEST P-0 Relief Request Withdrawn 3-12 Revi~;ion o November 10, 1993

* *

  • RELIEF REQUEST P-1 Systems: Various Pump(s): IWP Program Pumps. See PUMP INSERVICE TEST TABLE. Class OM Part 6 Code Requirements For Which Relief Is Requested Section 4.3 Reference Values Reference values shall be determined from the results of preservice testing or from the results of the first inservice test. This request applies only to vibration testing. Basis For Request Small reference values for vibration (Vr) will produce small acceptable ranges for pump operation.

Based on a small acceptable range, an adequately and smoothly running pump could be subject to corrective action. To avoid this situation, a minimum value for Vr of 0.05 in/sec has been established for velocity measurements.

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

  • 3-13 S1PVI3RO Revision o Noveinber 10, 1993
  • *
  • S1PVI3RO INTERIM RELIEF REQUEST P-2 Relief Request Withdrawn RELIEF REQUEST P-3 Relief Request Withdrawn RELIEF REQUEST P-4 Relief Request Withdrawn RELIEF REQUEST P-5 Relief Request Withdrawn RELIEF REQUEST P-6 Relief Request Withdrawn 3-14 Revi~ion o November 10, 1993
  • *
  • RELIEF REQUEST P-7 * : System : Residual Heat Removal Pump(s): 1-RH-P-lA 1-RH-P-lB Class I : 2 OM Part 6 Code Requirements For Which Relief Is Requested Frequency of Pump Test. Basis For Request The low pressure RHR pumps take suction from and discharge to the reactor coolant system which operates nominally at 2235 psig. This is well above the operating pressure for the RHR pumps. Therefore, testing during normal operation is not possible.

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

  • 3-15 S1PVI3RO *Revision o November 10, 1993
  • *
  • S1PVI3RO RELIEF REQUEST P-8 Relief Request Withdrawn INTERIM RELIEF REQUEST P-9 Relief Request Withdrawn RELIEF REQUEST P-10 Relief Request Withdrawn 3-16 Revtsion o November 10, 1993
  • *
  • RELIEF REQUEST P-11 system: Service Water Pump{s): 1-SW-P-1A 1-SW-P-1B 1-SW-P-1C Class 3 OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph

4.3 requires

reference values to be points of operation readily duplicated during subsequent tests. All subsequent test results shall be compared to these initial reference values. OM Part 6, Paragraph 4.6.2.2 requires that differential

  • pressure across the pump be determined using either "a differential pressure transmitter that provides direct measurement of pressure difference or the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe." Basis For Request The emergency service water pumps take suction from the James river and discharge into the intake canal. The James river near the plant is subject to a tide level variation of approximately five feet. Therefore, the total static head for the system can vary from test to test; There are no valves'in the lines to throttle flow and to compensate for the change in system static head. The only way to duplicate flow and differential pressure from test to test is to perform the test at the same tide level each time. Trying to perform this test within a small enough tide level range to produce repeatable results has proven impractical.

To compensate for the change in total system head, a pump reference curve will be prepared based on test results taken at different tide levels. Tests will be conducted within the tide level limits of the curve, and results will be compared to acceptance criteria based on the reference curve and the ranges given in OM Part 6, Table 3b. As stated above, the emergency service water pumps discharge into the intake canal. The end of the discharge pipe is above the level of the canal and the pressure at the end of the discharge pipe is always equal to the atmospheric pressure.

Therefore, the total head and the corresponding flow will depend upon the tide level and will vary as the tide level varies. For purposes of testing, the system head is set by the tide level, and the 3-17 SlPVI3RO Rev~sion o November 10, 1993

  • *
  • RELIEF REQUEST P-11 (Cont.) corresponding measured flow will be compared to the acceptance criteria.

Because the pressure at the end of the discharge piping is always equal to the atmospheric pressure and the flow varies as a function of tide level, there is no need to measure the discharge pressure at a point closer to the pump. Also, OM Part 6, Paragraph 4.6.2.2 states that differential pressure can be determined by the difference between the pressure at a point in the inlet pipe and the pressure at a point in the discharge pipe. In the case of the emergency service water pumps, the end of the discharge pipe can be considered the "point in the discharge pipe" where the discharge pressure is determined (i.e., atmospheric pressure).

The inlet pressure is dependent on the tide level. Although the discharge pressure will not be measured, the intent of Paragraph 4.6.2.2 is met and the test is equivalent to that described in Paragraph 4.6.2.2. Alternate Testing Proposed The flow is dependent upon tide level. Tests will be conducted within the tide level limits of the pump reference curve, and flow will be compared to acceptance criteria based on the reference curve and the ranges given in OM Part 6, Table 3b. Discharge pressure will not be measured . 3-18 S1PVI3RO Revision O November 10, 1993

  • *
  • S1PVI3RO RELIEF REQUEST P-12 Relief Request Withdrawn RELIEF REQUEST P-13 Relief Request Withdrawn RELIEF REQUEST P-14 Relief Request Withdrawn RELIEF REQUEST P-15 Relief Request Withdrawn 3-19 Rev~~ion o November 10, 1993
  • *
  • INTERIM RELIEF REQUEST P-16 *System: Main Control Room Air Conditioning Pwnp{s): 1-vs-P-lA 1-VS-P-lB 1-VS-P-lC Class 3 OM Part 6 Code Requirements For Which Interim Relief Is Requested Measure flow, inlet pressure and differential pressure.

Basis For Interim Request No flow or inlet pressure instrumentation is installed.

According to Technical Specification Paragraph 3.23.C.1.b, "If one chiller becomes inoperable, return the inoperable chiller to operable status within seven (7) days or bring both units to Hot Shutdown within the next six (6) hours and be in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." Because the main control and emergency switchgear room emergency ventilation system is common for both units, the above action statement applies whenever Unit 1 or Unit 2 is operating

  • Given the scope of the required instrwnentation modifications and the existing system configuration, it is estimated that installation of the appropriate flow and pressure instrumentation cannot be completed within the Technical Specification 7 day aetion statement.

Two additional Main Control Room and Emergency switchgear Room Air Conditioning System chillers are scheduled for installation by the end of 1993. The additional chillers will eliminate the need for entry into the Technical Specification action statement to install the instrumentation.

Also, the flow elements for the chiller service water pumps cannot be installed at power. Therefore, installation of the additional instrumentation is scheduled to be completed by the end of the Unit 1 Cycle 12 refueling outage currently scheduled for second quarter of 1994. Interim Alternate Testing Proposed The control room chillers are monitored at least once every quarter for adequate performance.

Part of this surveillance verifies that minimwn service water flow requirements are being met by the pumps. A flow rate of 240 gpm is the minimum required I 3-20 SlPVI3RO Revi~:don o Nov~inber 10, 1993

  • *
  • INTERIM RELIEF REQUEST P-16 (Cont.) service water flow for condenser operability.

The minimum flow is verified by measuring the differential pressure across the chiller condensers.

The normal operating range is 4 to 7 psid across the chiller condensers.

An alert value has been established at 10% above the minimum flow or 264 gpm. This flow equates to a differential pressure of 4 psid. If a differential pressure of at least 3.5 psid (240 gpm) cannot be achieved after any adjustments (i.e., adjusting the backwash valve and cleaning the service water pump Y-strainer) then the pump is declared inoperable.

When differential pressure exceeds 7 psid, the condenser tubes require cleaning.

Also, if a pump discharge pressure of 30 psig cannot be achieved with a fully shut backwash isolation valve, then an investigation is initiated to check for possible upstream restriction or a degraded pump. Vibration monitoring has been added to the surveillance and will be performed at least once every quarter. The acceptance criteria for vibration are based ~pon the Section XI program. The correlation between condenser differential pressure and flow was established during special tests that were conducted in June of 1989. The special tests consisted of fabricating a temporary instrumented loop of pipe with a straight run long enough to produce stable flow. The permanent piping has no straight runs that are long enough to measure flow. A section of permanent pipe was removed and the temporary section installed.

The results of the tests are given in Figure 1 and Table 1. Inlet pressure and flow irtstrumentation installation will be completed by the end of the Surry Unit 1 Cycle 12 refueling outage, currently scheduled for the second quarter of 1994. As the instrumentation is installed, inlet pressure, differential pressure, flow and vibration will be measured at least once every three months-in accordance with ASME Section XI requirements . 3-21 S1PVI3RO Rev.i.~ion o November 10, 1993

~* :g H t,J 0 !z: 0 (D < < i ~-,m *~* (D 0 11 f-JO 0 .. .... '° '° t,J t,J I 6.4 5.6 (/) CL 4.8 z CL 4.0 0 0:::: 3.2 w (/) 2.4 z w 0 1.6 z 0 u 0.8 I I 0.0 -"" 0 2 4 3 6

  • MCR CHILLERS 1-VS-E-4A, 48, 4C CONDENSER DELTA P vs SW FLOW .£ , l-r ... ' ,.,_ -IY --~ i_.-., ... 6 9 1 1 1 1 2 2 2 2 9 2 1 3 6 8 0 3 5 7 . . 5 8 1 4 7 0 3 6 2 1 . . 1 2 2 2 2 3 3 3 V 2 9 9 3 SW FLOW IN GPM FROM 1-VS-P-lA, 18, 1 C + 4A X 48 o 4C ""'" FROM sr-2J, fl/l~.,e.17~fJI RUNS CCNDCN5CRS ClEANEO JUST PR R IO TEST
  • t%j ,1 tt V, 0 H < z tr:I 8 tr:I C/l q H C/l n 0 tr:I z t'i 0 H tr:I tr:I z ttj ttj C/l tr:I H G1 tr:I !a ,0 0 q H tr:I tr:I ttj .... C/l t%j 8 tr:I to tr:I I 3 3 2 4 2 5 z .... 8 O'I H -n 0 . 4 4 I'd ::s rt tr:I C/l -C/l !a tr:I ..
  • *
  • SlPVIJRO INTERIM RELIEF REQUEST P-16 (Cont.) TABLE 1 FLOW VERSUS CONDENSER DIFFERENTIAL PRESSURE SPECIAL TEST ST-2~5 RUN 6/15 THRU 17/89 MCR CHILLERS 1-vs-E-4A, 4B, AND 4C FLOW RATES CONDENSER DP IN PSI FPS GPM E-4A E-4B E-4C **************************************************

o.o o.o 0.1 1.0 23.0 0.2 2.0 46.0 0.3 3.0 69.2 0.4 4.0 92.1 0.7 s.o 115.1 1.0 6.0 138.2 1.3 7.0 161.2 1.7 8.o 184.2 2.2 9.0 207.2 2.6 10.0 230.3 3.0 11.0 253.3 3.8 12.0 276.3 4.2 13.0 299.3 s.o 14.0 322.4 5.7 15.0 345.4 6.3 3-23 o.o 0.1 0.2 0.4 0.6 1.0 1.3 1.6 2.2 2.8 3.1 3.8 4.3 5.0 5.7 6.4 o.o 0.1 0.2 0.5 0.9 1.0 1.3 1.7 2.2 2.6 3.1 3.7 4.1 4.9 Revi~ion o Noveniber 10, 1993

  • *
  • RELIEF REQUEST P-17 system: Main control Room Air Conditioning Pump{s): 1-VS-P-2A 1-VS-P-2B 1-VS-P-2C Class 3 OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph

4.3 requires

reference values to be points of operation readily duplicated during subsequent tests. All subsequent test results shall be compared to these initial reference values. Basis For Request The 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 November 10, 1993

  • *
  • RELIEF REQUEST P-17 (Cont.} compared to either graphical and/or tabular acceptance criteria based on the straight line approximation of the reference pump curve. For example, given the straight line equation determined from the two reference points for flow and differential pressure:

Prdiff =a+ b*Q where Prdiff = the reference differential pressure based on the test value for flow (Q) recorded during subsequent tests and, a and bare constants, the acceptance criteria for the flow (Q} would be as follows: Upper Required Action= 1.l*Prdiff Lower Required Action= 0.90*Prdiff The multipliers on Prdiff are taken from OM Part 6, Table 3b. The actual recorded differential pressure (Padiff) will then be compared to the acceptance criteria determined from Prdiff. Also, the tests results can be trended from test to test by normalizing Padiff to Prdiff. For acceptable operation, the ratio of Pllliff/Prdiff must fall between 0.9 and 1.1. A decrease in the ratio from test to test would indicate a steady degradation in pump performance

  • 3-25 S1PVI3R0 *Revision o November 10, 1993
  • *
  • SlPVIJRO L_ INTERIM RELIEF REQUEST P-18 Relief Request Withdrawn 3-26 Revj,sion o November 10, 1993
  • *
  • RELIEF REQUEST P-19 ,System : Component Cooling Pwnp(s): 1-CC-P-lA 1-CC-P-lB Class 3 OM Part 6 Code Requirements For Which Relief Is Requested OM Part 6, Paragraph

4.3 requires

reference values to be points of operation readily duplicated during subsequent tests. All subsequent test results shall be compared to these initial reference values. Basis For Request During testing of the component cooling water pumps, flow is adjusted to the reference flow rate using an 18 inch butterfly valve. The butterfly valve is a crude throttling device and does not provide the fine tuning that is required to duplicate the reference flow rate from test to test. Consequently, throttling to the same reference flow rate during each test is not practical . Alternate Testing Proposed Two reference points of flow versus differential pressure will be established from the reference test for each pump. A straight line approximation will be used todei::.ermine differential pressure reference points as a function of flow between the two test points. By keeping the difference between two test points small, the straight line is a good approximation of the pump curve within the two test points. During the subsequent tests, test flow will be throttled as close as practical to the reference flow value. The test flow must fall between the two reference points used to establish the straight line approximation.

The test flow and the corresponding differential pressure will be compared to either graphical and/or tabular acceptance criteria based on the straight line approximation of the reference pump curve

  • 3-27 S1PVI3RO Revision o November 10, 1993
  • *
  • RELIEF REQUEST P-19 (Cont.) For example, given the straight line equation determined from the two reference points for flow and differential pressure:

Prdiff =a+ b*Q where Prdiff = the reference differential pressure based on the test value for flow (Q) recorded during subsequent tests and, a and bare constants, the acceptance criteria for the flow (Q) would be as follows: Upper Required Action= 1.l*Prdiff Lower Required Action= 0.90*Prdiff The multipliers on Prdiff are taken from Table 3b in OM Part 6. The actual recorded differential pressure (Padiff) will then be compared to the acceptance criteria determined from Prdiff. Also, the tests results can be trended from test to test by normalizing Padiff to Prdiff. For acceptable operation, the ratio of P.diff/Prdiff must fall between 0.9 and 1.1. A decrease in the ratio from test to test would indicate a steady degradation in pump performance

  • 3-28 S1PVI3RO Revision o November 10, 1993
  • *
  • S1PVI3RO RELIEF REQUEST P-20 Relief Request Withdrawn 3-29 Revision O November 10, 1993
  • *
  • RELIEF REQUEST P-21 System: Chemical and Volume Control Pump(s): 1-CH-P-2A 1-CH-P-2B Class 2 OM Part 6 Code Requirements For Which Relief Is Requested The pressure instrument accuracy shall be within+ 2% (OM Part 6, Paragraph 4.6.1.1) The full-scale range of each-instrument shall be three times the reference value or less (OM Part 6, Paragraph 4.6.1.2).

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

Calibrating the inlet pressure instruments to an accuracy within+ 3% would be practical

  • Also, the 15 psig. pressures the three pressures inlet pressure gauges have a full scale range of o to These instruments were sized by evaluating the static present at the suction side of the pumps and applying times rule of OM Part 6, Paragraph 4.6.1.2. The static range from 6 to 7 psig. When the pumps are started, the pressure at the suction side of the pumps drops to approximately 2 psig; therefore, the inlet pressure gauges do not meet the three times rule for dynamic inlet pressure.

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

Using a lower range temporary gauge on a quarterly basis presents a hardship because the process fluid contains boric acid and is contaminated.

If contaminated, the temporary instruments would probably become waste material.

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

  • 3-30 S1PVI3RO Revision o November 10, 1993
  • *
  • RELIEF REQUEST P-21 (Cont.) Each boric acid transfer pump discharge pressure gauge (0 to 150 psig range) has an instrument loop accuracy of 1.59%. Computing the maximum error for differential pressure using the current instrument configuration and an inlet pressure gauge accuracy of +/- 3%, yields an error of 2.85 psid. Computing the Code allowed error for differential pressure for an inlet pressure gauge with a 2% accuracy and a o to 5 psig range and a discharge pressure instrument with a 2% accuracy and a o to 150 psig range yields an error of 3.1 psid. With the current instrument configuration, the loop accuracy of each discharge pressure instrument could be as high as 1.75%, which equates to a 3.075 psid error, and still be within the Code allowed error of 3.1 psid for differential pressure.

Therefore, for purposes of trending pump degradation using differential pressure and flow, the current instrument is adequate as long as the discharge pressure instrument loop accuracies remain at or below 1.75%. Alternate Testing Proposed The inlet pressure gauges with a full scale range of Oto 15 psig and calibrated to an accuracy within+/- 3%, will be used to measure dynamic inlet pressures.

Also, the loop accuracies for the discharge pressure gauges will be maintained at or below an accuracy of 1.75% to ensure that the differential pressure error is below the differential pressure error allowed by the Code

  • 3-31 S1PVI3RO Revision o November 10, 1993 3.7 * *
  • S1PVI3RO ALTERNATIVE TESTING FOR NON-CODE PUMPS According to the minutes of public meeting on Generic Letter 89-04, "Paragraph

{g) of 10 CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. Paragraph

{g) has been replaced by Paragraph

{f) in the currently approved 10 CFR 50.55a. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required

!ST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program {or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a 'request for relief' to be submitted to the staff. Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3

  • Surry Power Station has elected to include certain Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability.

The alternate testing is described in this ~et:-cion.

'i'he:t:e may be* other ***** **:*"* ** deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site. As indicated in the minutes of public meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components.

Therefore, the alternative tests described in this section are not 'requests for relief' but are provided for information . 3-32 Revision o November 10, 1993

  • *
  • NON-CODE ALTERNATIVE TESTING PNC-1 System: Fuel Oil Pump(s): 1-EE-P-lA 1-EE-P-lC 1-EE-P-lD 1-EE-P-lF Class NC OM Part 6 Code Requirements Which Cannot Be Met Measure test quantities after the pump has been running for at least two minutes (OM Part 6, Paragraph 5.6). Basis For Alternate Testing The pump 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 five minutes prior to measuring the test quantities and the fuel consumption rate is low, not enough time is available to gather all of the required Section XI test data. Alternate Testing The-meas'U:'.i:.';i;l:-..-Ue:a'L uZ. G~c'i:.iou

    • XI 'g-u.antiti~:3 will b..:gin*~w:i::i.en'*the" *pump*-~ automatically starts on a low tank level signal
  • 3-33 SlPVI3RO Revision o November 10, 1993

4.0 VALVE

INSERVICE TEST PROGRAM DESCRIPTION

  • *
  • S1PVI3RO 4.1 PROGRAM DEVELOPMENT PHILOSOPHY Surry Power station Unit 1 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The Code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity.

The Surry Unit 1 Valve Inservice Test Program satisfies these requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. Subsection IWV, addenda through the 1988 Addenda and editions through the 1989 Edition, references Part 10, Edition OM-87, ASME/ANSI, Operation and Maintenance of Nuclear Power Plants, Addenda OMa-1988.

Therefore, the Program is based on the requirements of Part 10, along with NRC Staff guidelines provided in Generic Letter 89-04 for complying with certain provisions of 10 CFR 50.55a(f).

This program includes valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident." It is important to note that the scope of ASME Section XI and the Surry Inservice Testing Program for its implementation includes many valves which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specif icd*tions.

In these cases, the requirements of Section XI, OM Part 10 shall be met except where relief has been granted. To generate the Surry Unit 1 Valve Program, ASME Class 1, 2 and 3 valves were analyzed to determine their required type and frequency of testing. The valves to be tested under OM Part 10 commitments are listed by system and drawing in the Valve Test Tables. Surry Unit 1 is committed to meeting the leak rate testing requirements of: 1) 10CFR50, Appendix J for containment isolation valves and 2) OM Part 10 for other valves for which seat leakage is limited to a specific maximum amount (i.e. pressure isolation valves) unless relief is specifically requested from OM Part 10 4-1 Rev~~;ion o November 10, 1993

  • 4.2 *
  • S1PVI3RO requirements
  • Valves subject to leak testing per Appendix J will be tested to the requirements of OM Part 10, Paragraphs 4.2.2.3(e) and 4.2.2.3(f) as required by 10 CFR 50.55a(b)

(2) (vii). Appendix J satisfies the testing requirements of OM Part 10, Paragraph 4.2.2.2. The Code recognizes that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.

The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where warranted (refer to Section 4.5). The Surry Unit 1 Valve Inservice Test Program complies with the intent of the applicable codes, regulations and guidelines and makes a positive contribution to the safe operation of the plant. PROGRAM IMPLEMENTATION The Valve Inservice Test Program is executed as part of the normal plant surveillance routine. Three types of tests are conducted as part of the Valve Test Program: 1) Valve Exercise Tests, 2) Valve Leakage Tests and 3) Safety Valve Tests The Exercise Tests verify that: 1) the valve strokes properly, 2) the valve responds to control commands, 3) the valve stroke time is within specific limits and 4) remote position indication accurately reflects the observed valve position.

Remote valve position indication will be verified every two years. Fail safe valves are tested by observing the valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.

Those valves which are scheduled to be exercised during cold shutdown are subject to the requirements of OM Part 10, Paragraph 4.2.1.2(g) which states that: "valve exercising during cold shutdown shall commence within 48 hr of achieving cold 4-2 Revi~ion O November 10, 1993

  • *
  • S1PVI3RO shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr provided all valves required to be tested during cold shutdown will be tested prior to plant startup. However, it is not the intent of this Part to keep the plant in cold shutdown in order to complete cold shutdown testing." Valve Leakage Tests verify that valves are leak tight in accordance with Appendix J or ASME Section XI. Relief and Safety valves are required to be tested to the requirements of OM Part 1. Certain valves cannot be full stroke exercised during normal operation following maintenance.

These valves are described in the cold shutdown justifications (refer to Section 4.6) and reactor refueling justifications (refer to Section 4.7). If maintenance cannot be deferred to a shutdown condition, then an engineering evaluation must be performed prior to the maintenance to determine the effect of the maintenance on valve performance.

If the evaluation shows that performance will not be affected, then no post maintenance testing is required.

A partial stroke test will be performed if possible

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

j* *

  • At:~OL'uiiiy'*'

Lo Geh.;;::i.

i(.: Let*~er '89-04, disassembly*:.:*andi*:,,,\*:t,,S/.*e,il inspection of the check valves on a sampling basis is an acceptable alternative testing method. As described in Generic Letter 89-04, the sample disassembly and inspection program involves grouping $imilar valves and testing one valve in each group during each refueling outage. The sampling technique requires that each valve in the group be the same design (manufacturer, size, model number, and materials of construction) and have the same service conditions including valve orientation.

The group size cannot exceed four valves. Additionally, at each disassembly it must be verified that the disassembled valve is capable of full-stroking and that the internals of the valve are structurally sound. Also, to verify the full stroke capability of the valve, the disk should be manually exercised

  • 4-3 Revij;ion O November 10, 1993
  • 4.3 4.4 *
  • S1PVI3RO A different valve of each group is required to be disassembled, inspected, and manually full stroked exercised at each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full stroked exercised.or there is binding or failure of valve internals, the remaining valves in that group must be disassembled, inspected, and manually full stroked exercised during the same outage. PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test Program. The program will be officially implemented on May 10, 1994. The program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.55a{f)

(4) .for subsequent 120 month IST intervals.

VALVE INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet OM Part 10 requirements.

The tables reflect the positions taken in support of the relief requests.

To aid the reader in the interpretation of the tables, brief explanations of the table headings and abbreviations are provided.

For non-Code valves, a request for relief is not necessary when provisions of the Code cannot be met. Section 4.8 contains a discussion of the testing * 'rey:uir,;i:l'w~hi:.;.::;

    • i:vi. '*nor . .--CuJ.e*'Val vel::i= 'and* des~riptiuns
  • 0*of 0:-.,y;1,!-Y, alternative testing in*cases where the provisions of the Code cannot be met. 1) 2) 3) 4) Valve Number -Each valve in the plant has a unique "tag" number which identifies the system to which the equipment belongs and type of equipment.

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

Function -A brief description of the function of the valve. Code Class -ASME Code Class of each valve as per 10 CFR 50.55a and Regulatory Guide 1.26. ~: NC is for non-Code valves. These valves are important to safety but are not in systems that are 4-4 Revi?ion o Noveinber 10, 1993

  • *
  • S1PVI3RO classified ASME Class 1, 2 or 3 . 5) category -Categories are defined by OM Part 10, Section 1.4. Each valve has specific testing requirements which are determined by the category to which it belongs. Valves marked with an "E" are passive valves. 6) Size -Nominal pipe diameter to which valve connects is given in inches. 7) Valve Type -A brief description of the actuator and valve type. The following abbreviations are used :to describe actuator types. Valves may be actuated in more than one way. MO -Motor Operated AO -Pneumatic (Air Operated)

MAN -Manually Operated so -Electronic solenoid Operated Valves 8) Isolation Valve Type -Valves that are assigned a maximum leakage. The following abbreviations are used to describe the main isolation valve types: CIV -Containment Isolation Valve subject.to Appendix J leakage testing. PIV -Pressure Isolation Valve which protects low pressure safety related piping from RCS pressure.

Technical' Specif icat:i-u:a

    • ciu:t1 \3
  • 1. c
  • specil iE~s*' the'*r~* pressure isolation valves that are tested in accordance with this program. 9) Test Position -The following abbreviations are used to describe normal valve positions to which the valves are tested (including the valve safety position):

o -Open c -Closed oc -Open and Closed 10) Test Required -Testing requirements identified for the valves are identified here. ST -Stroke times shall be measured per OM Part 10, Par~graph 4.2.1.4 or as modified by a specific relief request

  • 4-5 Revision O November 10, 1993
  • *
  • S1PVI3RO EV -Exercise valve for operability at least once every 3 months per OM Part 10, Paragraph 4.2.1.4 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, section 4.2.1.2. LT -Leak test shall be performed per OM Part 10, Section 4.2.2 or as modified by specific relief request. CV -Check valves shall be exercised at least once every 3 months per OM Part 10, Paragraph 4.3.2.1 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, Section 4.2.2.2. VP -Valve position indication shall be verified per OM Part 10, Paragraph 4.1 or as modified by a specific relief request. SP -Set points of safety and relief valves shall be tested per OM Part 1 or as modified by a j specific relief request. FS -Valves with fail-safe actuators shall be tested by observing the operation of the valves upon loss of the actuator power at least once every 3 months per OM Part 10, Paragraph 4.2.1.6 or as modified by a specific cold shutdown or reactor refueling justification which is allowed by OM Part 10, Section 4.2.1.2
  • 4-6 Revision o Noveinber 10, 1993
  • VALVE NUMBER 1-BD-TV-100A 1*BD*TV-100B 1-BD-TV-100C 1*BD-TV-100D
  • 1-BD-TV-100E 1-BD-TV-100F
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE*

TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-124A 1 OF 4 C-7 AO GATE 11 A 11 STEAM GENERATOR BLOWDOWN, INSIDE CON~ TAINMENT ISOLATION VALVE 11448-CBM-124A 1 OF 4 C-6 AO GATE "A" STEAM GENERATOR BLOWDOWN, OUTSIDE TAINMENT ISOLATION VALVE 11448-CBM-124A 2 OF 4 C-7 AO GATE 11 B 11 STEAM GENERATOR BLOWDOWN, INSIDE TAINMENT ISOLATION VALVE 11448-CBM-124A 2 OF 4 C-6. AO GATE 11 B 11 STEAM GENERATOR BLOWDOWN, OUTSIDE TAINMENT ISOLATION VALVE 11448-CBM-124A 3 OF 4 C-7 AO GATE 11 C 11 STEAM GENERATOR BLOWDOWN, INSIDE TAINMENT ISOLATION VALVE 11448-CBM-124A 3 OF 4 C-6 AO GATE "C" STEAM GENERATOR BLOWDOWN, OUTSIDE TAINMENT ISOLATION VALVE 3.000 2 3.000 2 3.000 2 3.000 2 3.000 2 ----------3.000 2 B B B B B B EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP PAGE: 1 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN* C C C oc C C C oc C C C oc C C C oc C C C oc C C C oc ---21 21 21 21 21 21 21 21 21 21 21 21 21 21 21 ----21 21 21 --------

  • VALVE NUMBER 1-cc-0001 1-CC-0058 1-CC-0059 1-CC-0176 1-CC-0177 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAlllNG NUMBER SHEET DRllG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448*CBM*072A 2 OF 7 F-7 CHECK VALVE CC SUPPLY TO "A" RC PUMP LO, STATOR SHROUD & THERM BARRIER COOLERS, ISOL CHECK VLV 11448*CBM*072A 3 OF 7 F-7 CHECK VALVE CC SUPPLY TO 11 8 11 RC PUMP LO, STATOR SHROUD & THERM BARRIER COOLERS, ISOL CHECK VLV 11448*CBM*072A 4 OF 7 F-7 CHECK VALVE CC SUPPLY TO 11 C 11 RC PUMP LO, STATOR SHROUD & THERM BARRIER COOLERS, ISOL CHECK VLV 11448*CBM*072A 1 OF 7 F-7 CHECK VALVE CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE 11448*CBM*072A 1 OF 7 F-7 CHECK VALVE CC SUPPLY TO RHR HEAT EXCHANGER CHECK VALVE 6.000 3 C CV 6.000 3 C CV 6.000 3 C CV 18.000 3 C CV 18.000 3 C CV ----------------------------------------------*--------------

1-CC-0181 1-CC-0185 11448*CBM*072A 1 OF 7 A-6 MANUAL BFLY CC RETURN FROM RHR HEAT EXCHANGER MANUAL ISOLATION VALVE 11448*CBM*072A 1 OF 7 A-4 MANUAL BFLY 18.000 3 B EV 18.000 3 B EV . ,., ,:,:./. *. -. r., .... '-"*-*, :,t ,: *:,.\**, ,: *,*:, .. ,cc*. k~Tlii<N ~:~~:!<HR" HEifi"'*'

i;)ii;:1~;.JGfk NAl"iUAL,-,,,,,.-

.. *: *. " .. * -.: ' * . 1-CC-0224 1-CC-0233.

1-CC-0242 1-CC-0557 1-CC-0563

  • ISOLATION VALVE 11448-CBM-0728 2 OF 3 D-2 CHECK VALVE CC SUPPLY TO 11 C 11 RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-0728 2 OF 3 D-6 CHECK VALVE CC SUPPLY TO 11 8 11 RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-0728 2 OF 3 D-8 CHECK VALVE CC SUPPLY TO "A" RECIRC AIR COOLING COILS, INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-0720 1 OF 5 D*S CHECK VALVE "A" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 11448-CBM-0720 1 OF 5 C*S CHECK VALVE 6.000 3 C CV 6.000 3 C CV 6.000 3 C CV 18.000 3 C CV 18.000 3 C CV PAGE: 2 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C C C C 0 C 0 C 0 C 0 C C C C 0 C 6 6 6 5 5 5 5 26

  • 26 26 26 5 5 5
  • * * *VALVE NUMBER 1-CC-0563 1-CC-0752 1-CC-0764 1-CC-0805 1-CC-1105 1-CC-1106 1-CC-1107 1-CC-1188 1-CC-1189 1-CC-1190 1-CC-LCV-101 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-072D 1 OF 5 C-5 CHECK VALVE "B" COMPONENT COOLING PUMP DISCHARGE CHECK VALVE 18.000 3 C CV 11448-CBM-071B 2 OF 2 C-3 CHECK VALVE ---------------------------------------
  • -----CHARGING PUMP COOLING WATER PUMP DISCHARGE CHECK VALVE 11448-CBM-071B 2 OF 2 C-7 *CHECK VALVE CHARGING PUMP COOLING WATER PUMP DISCHARGE CHECK VALVE 11448-CBM-072C 4 OF 4 C-5 CHECK VALVE CHARGING PUMP SEAL COOLING SURGE TANK MAKEUP CHECK VALVE 11448-CBM*072A 4 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11448-CBM-072A 3 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11448-CBM-072A 2 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISO!.ATION CHEr:K l/ALV!a 11448-CBM-072A 2 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATlot.l CHECK VALVE 11448-CBM-072A 3 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11448-CBM-072A 4 OF 7 C-6 CHECK VALVE COMPONENT COOLING WATER TO RCP THERMAL BARRIER ISOLATION CHECK VALVE 11448-CBM-071B 2 OF 2 D-5 AO GATE CHARGING PUMP SEAL COOLING SURGE TANK LEVEL CONTROL/ISOLATION VALVE 2.000 3 2.000 3 1.000 3 2.000 3 2.000 3 2.000 3 2.000 3 2.000 3 2.000 3 ----------1.000 3 C CV C CV C CV C CV C CV C CV C CV C CV C CV ---B EV FS ST PAGE: 3 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 C 0 C 0 0 C C C C C C C 0 C C 0 ---47 47 30 7 7 7 7 7 7 ------------31 31 31 31 31

  • * * . VALVE NUMBER 1*CC*RV*112A VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING SHEET DRWG VALVE NUMBER NUMBER COOR TYPE 11448*CBM*072B 2 OF 3 C-7 RELIEF VALVE REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT\ TYPE TYPE -------------) ---------.750 3 C SP 1*CC*RV*112B 11448*CBM*072B 2 OF 3 C*S RELIEF VALVE .750 3 C SP 1*CC*RV*112C 1*CC*RV-119A 1*CC*RV*119B 1-CC*RV-122 1-CC*RV-123 1-CC*RV-124 REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 11448*CBM*072B 2 OF 3 C*4 RELIEF VALVE* REACTOR CONTAINMENT AIR RECIRCULATION COOLER RELIEF VALVE 11448*CBM-072A 1 OF 7 E-3 RELIEF VALVE "A" RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 11448*CBM*072A 1 OF 7 D-3 RELIEF VALVE 11 8 11 RHR HEAT EXCHANGER COMPONENT COOLING RELIEF VALVE 11448*CBM*072D 1 OF 5 F*6 RELIEF VALVE COMPONENT COOLING SURGE TANK RELIEF 11448*CBM*072D 1 OF 5 F-7 RELIEF VALVE COMPONENT COOLING SURGE TANK VACUUM RELIEF 11448*CBM*072A 5 OF 7 F-6 R~lJF.F VALVE COMPONENT COOLING PIPING RELIEF 1*CC*RV*138A.

11448*CBM*072A 2 OF 7 F*6 RELIEF VALVE REACTOR SHROULD COOLING COIL 1*CC*RV*138B 1*CC*RV~138C 1*CC*TV*105A RELIEF VALVE ' 11448*CBM*072A 3 OF 7 F-6 RELIEF VALVE REACTOR SHROULD COOLING COIL RELIEF VALVE 11448*CBM*072A 4 OF 7 F*6 RELIEF VALVE REACTOR SHROULD COOLING COIL RELIEF VALVE 11448*CBM*072A 2 OF 7 B-4 AO BALL .750 3 C 1.500 3 C 1.500 3 C 3.000 3 C 3.000 3 C .750 3 C .750 3 C .750 3 C .750 3 C 6.000 3 B .SP SP SP SP SP SP SP SP SP EV FS ST VP L ---------------PAGE: 4 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN-0 0 0 0 0 0 0 0 0 0 0 C C C oc ---------------. I 6 6 6

  • *
  • VALVE NUMBER 1*CC*TV-105B 1*CC-TV-105C 1*CC-TV-109A 1*CC*TV-109B 1*CC-TV-110A 1*CC*TV*110B 1*CC*TV-110C VIRGINIA POWER CC14PANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE CC RETURN FROM "A" RC PUMP LO,STATOR

& SHROUD COOLERS, llJTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM-072A 3 OF 7 B-4 AO BALL CC RETURN FROM 11 8 11 RC PUMP LO,STATOR

& SHROUD COOLERS, llJTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072A 4 OF 7 B-4 AO BALL CC RETURN FROM "C" RC PUMP LO,STATOR

& SHROUD COOLERS, llJTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 6.000 3 B 6.000 3 B EV FS ST VP EV FS ST VP 11448-CBM-072A 1 OF 7 B-7 AO BFLY 18.000 3 B EV FS ST CC RETURN FROM 11 A 11 RHR HEAT EXCHANGER, SIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072A 1 OF 7 C-7 AO BFLY CC RETURN FROM "B" RHR HEAT EXCHANGER, SIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072B 2 OF 3 E-7 AO BFLY CC RETURN FROM "A" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072B 2 OF 3 E-5 AO BFLY CC RETURN FROM "B" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072B 2 OF 3 E-4 AO BFLY 18.000 3 B 6.000 3 B 6.000 3 B 6.000 3 B VP EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP PAGE: 5 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS .V-CSV-RRV-VCN-C C C oc C C C oc C 0 C C 0 oc C 0 C C 0 oc C C C oc C C C oc C C C oc 6 6 6 6 6 6

  • *
  • VALVE NlMBER 1-CC-TV-120A VIRGINIA P°"'=R 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 CC RETURN FROM "C" RECIRC AIR COOLING COILS, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072A 2 OF 7 C-5 AO GATE CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 1.500 3 B EV ST VP ---------~

1-CC-TV-120B 1-CC-TV-120C 1-CC-TV-140A 1-CC-TV-140B 11448-CBM-072A 3 OF 7 C-5 AO GATE CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 11448-CBM-072A 4 OF 7 C-5 AD GATE CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER ISOLATION VALVE 11448-CBM-072A 1 OF 7 D-7 AO GLOBE CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIER, INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-072A 1 OF 7 D-7 AO GLOBE CC RETURN FROM REACTOR COOLANT PUMP THERMAL BARRIERS, OUTSIDE CONTAINMENT ISOLATION VALVE 1.500 3 1.500 3 ----------3.000 3 3.000 3 B B B B EV ST VP EV ST VP EV FS ST VP EV FS ST VP PAGE: 6 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C DC C C DC C C DC C C C DC C C C DC 27 27 27 27 27 27 27 27 27 27 27 27 --------

  • *
  • VALVE NUMBER 1-CH-076 1-CH-092 1-CH-225 1-CH-227 1-CH-228 1-CH-229 1-CH-230 1-CH-256 1-CH-258 1-CH-265 1-CH-267 1-CH-274 VIRGINIA POIJER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRI.IG VALVE NUMBER COOR TYPE VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-OSSA 1 OF 4 C-7 CHECK VALVE "A" BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 11448-CBM-OSSA 1 OF 4 C-6 CHECK VALVE 11 B 11 BORIC ACID TRANSFER PUMP DISCHARGE CHECK VALVE 11448-CBM-OSSB 1 OF 3 C-3 CHECK VALVE MANUAL EMERGENCY BORATION PATH CHECK VALVE 11448-CBM-OSSB 2 OF 3 A-3 CHECK VALVE MAIN EMERGENCY BORATION LINE TO CHARGING PUMP SUCTION CHECK VALVE 11448-CBM-OSSB 1 OF 3 B-4 MANUAL GATE MANUAL EMERGENCY PATH BORATION MANUAL VALVE 11448-CBM-OSSB 2 OF 3 A-4 CHECK VALVE MANUAL EMERGENCY BORATION PATH CHECK VALVE, CHARGING PUMP SUCTION CHECK VALVE 2.000 2 C 2.000 2 C 1.000 2 C 2.000 2 C 1.000 2 B 1.000 2 C 11448-CBM-OSSB 1 OF 3 B-6 CHECK VALVE 4.000 2 AC CHARGING PUMP SUPPLY FROM VOLUME CONTROL TANK DISCHARGE CHECK VALVE 11448-CBM-OSSB 2 OF 3 D-7 CHECK VALVE "A" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 2.000 2 11448-CBM-OSSB 2 OF 3 D-7 CHECK VALVE 3.000 2 11 A 11 CHARGING PUMP DISCHARGE CHECK VALVE 11448-CBM-OSSB 2 OF 3 D-6 CHECK VALVE "B" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 11448-CBM-OSSB 2 OF 3 D-6 CHECK VALVE "B" CHARGING PUMP DISCHARGE CHECK VALVE 11448-CBM-OSSB 2 OF 3 D-4 CHECK VALVE 2.000 2 3.000 2 2.000 2 C C C C C CV CV CV CV EV CV CV LT CV CV CV CV CV PAGE: 7 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0 0 0 0 0 C 0 C 0 C 0 0 C 0 0 19 19 19 19 8

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE "C" CHARGING PUMP DISCHARGE RECIRC LINE CHECK VALVE 1-CH-276 1-CH-309 11448-CBM-0888 2 OF 3 D-4 CHECK VALVE 11 C 11 CHARGING PUMP DISCHARGE CHECK VALVE 11448-CBM-OSSC 1 OF 2 D-4 CHECK VALVE MAIN CHARGING SUPPLY HEADER, INSIDE MENT ISOLATION CHECK VALVE 1-CH-FCV-1113A 11448-CBM-OSSB 1 OF 3 C-3 AO GLOBE MANUAL EMERGENCY BORATION PATH FLOW CONTROL VALVE 3.000 2 3.000 2 1.000 2 1-CH-FCV-1114A 11448-CBM-OSSB 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-OSSC 1 OF 2 B-4 AO GLOBE CHARGING FLOW CONTROL TO LOOP FILL HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CH-LCV-1115B 11448-CBM-OSSB 2 OF 3 B-8 MO GATE CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 1-CH-LCV-1115C 11448-CBM-0888 1 OF 3 C-6 MO GATE CHARGING PUMP SUPPLY ISOLATION FROM VOLUME CONTROL TANK 1-CH-LCV-1115D 11448-CBM-OSSB 2 OF 3 C-8 MO 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 REVISION:

00 DATE: 11/10/93 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 oc C 0 C C 0 oc C C oc C 0 C C 0 oc 11 11 6

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRIIG VALVE NUMBER COOR TYPE VALVE ASHE IIIV VALVE TEST SIZE CLASS CAT TYPE TYPE CHARGING PUMP SUPPLY ISOLATION VALVE FROM REFUELING WATER STORAGE TANK 1-CH-LCV-1115E 11448-CBM-0888 1 OF 3 C-6 MO GATE CHARGING PUMP SUPPLY ISOLATION VALVE FROM VOLUME CONTROL TANK 1-CH-LCV-1460A 11448-CBM-OSSC 1 OF 2 F-7 AO GLOBE NORMAL LETDOWN TO REGENERATIVE HEAT EXCHANGER ISOLATION VALVE 1-CH-LCV-1460B 11448-CBM-OSSC 1 OF 2 F-7 AO GLOBE NORMAL LETDOWN TO REGENERATIVE HEAT EXCHANGER ISOLATION VALVE 1-CH-MOV-1267A 11448-CBM-0888 2 OF 3 C-7 MO GATE CHARGING PUMP SUCTION ISOLATION VALVE FROM RIIST, VCT AND LHSI PUMP 1-CH-MOV-12678 11448-CBM-OSSB 2 OF 3 B-7 MO GATE LOW HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 1-CH-MOV-1269A 11448-CBM-OSSB 2 OF 3 C-5 MO GATE CHARGING PUMP SUCTION ISOLATION VALVE FROM RIIST, VCT AND LHSI PUMP 1-CH-MOV-1269B 11448-CBM-OSSB 2 OF 3 B-5 MO GATE LOW HEAD SI PUMP TO CHARGING PUMP SUCTION ISOLATION VALVE 1-CH-MOV-1270A 11448-CBM-OSSB 2 OF 3 C-3 MO GATE CHARGING PUMP SUCTION ISOLATION VALVE FROM RIIST, VCT AND LHSI PUMP 1-CH-MOV-1270B 11448-CBM-OSSB 2 OF 3 B-3 MO GATE LOIi HEAD SI PUMP TO CHARGING PUMP SUCTION I SOLA Tl ON VAL VE 1-CH-MOV-1275A 11448-CBM-0888 2 OF 3 D-7 MO GATE 4_000 2 B 2-000 1 B 2.000 1 B 6.000 2 E 6.000 2 E 6.000 2 E 6.000 2 E 6.000 2 E 6.000 2 E 2.000 2 B EV ST VP EV FS ST VP EV FS ST VP VP VP VP VP VP VP EV ST PAGE: 9 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C oc C C C QC C C C QC oc oc oc QC QC QC C 0 C 0 11 11 15 15 15 15 15 15 --------

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-CH-MOV-1275A 11448-CBM-088B 2 OF 3 D-7 MO GATE "A" CHARGING PUMP MINIMUM RECIRCULATION LATION VALVE 1-CH-MOV-1275B 11448-CBM-088B 2 OF 3 D-5 MO GATE "B" CHARGING PUMP MINIMUM RECIRCULATION LATION VALVE 1-CH-MOV-1275C 11448-CBM-OBBB 2 OF 3 D-3 MO GATE 11 C 11 CHARGING PUMP MINIMUM RECIRCULATION LATION VALVE 1-CH-MOV-1286A 11448-CBM-0888 2 OF 3 E-7 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1286B 11448-CBM-0888 2 OF 3 E-6 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1286C 11448-CBM-088B 2 OF 3 E-4 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1287A 11448-CBM-088B 2 OF 3 D-7 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1287B 11448-CBM-088B 2 OF 3 D-6 MO GATE 2-000 2 2.000 2 2.000 2 3.000 2 3.000 2 3.000 2 3.000 2 3.000 2 B B B B B B B B VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV PAGE: 10 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-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 0 oc C 0

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-CH-MOV-12878 11448-CBM-0888 2 OF 3 D-6 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1287C 11448-CBM-0888 2 OF 3 D-4 MO GATE CHARGING PUMP MAIN DISCHARGE ISOLATION VALVE 1-CH-MOV-1289A 11448-CBM-088C 1 OF 2 B-4 MO GATE MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 3.000 2 3.000 2 3.000 2 1-CH-MOV-1289B 11448-CBM-088C 1 OF 2 B-3 MO GATE 3.000 2 MAIN CHARGING HEADER ISOLATION VALVE, OUTSIDE CONTAINMENT 1-CH-MOV-1350 11448-CBM-0888 1 OF 3 B-5 MO GATE EMERGENCY BORATION TO CHARGING PUMP SUCTION 1-CH-MOV-1373 11448-CBM-088B 2 OF 3 E-7 MO GATE CHARGING PUMP'RECIRCULATION HEADER ISOLATION VALVE 1-CH-MOV-1381 11448-CBM-088B 1 OF 3 C-8 MO GATE 1-CH-RV-1203 REACTOR COOLANT PUMP SEAL WATER RETURN, SIDE CONTAINMENT ISOLATION VALVE 11448-CBM-088C 1 OF 2 F-4 RELIEF VALVE 2.000 2 3.000 2 3.000 2 2.000 2 LETDOWN RELIEF VLV DOWNSTREAM OF REGEN HX, RV DISCHARGE TO PRESSURIZER RELIEF TANK 1-CH-RV-1382A 11448-CBM-088C 2 OF 2 F-5 RELIEF VALVE REACTOR COOLANT PUMP SEAL WATER RELIEF VALVE, RV DISCHARGE TO PRESSURIZER RELIEF TANK 2.000 2 -----------------*-------------------------------------------

B B ST VP EV ST VP A CIV EV LT ST VP B B E EV ST VP EV ST VP VP A CIV EV LT ST VP C SP C SP PAGE: 11 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0 oc C 0 C 0 oc C C C oc C C oc 0 0 oc oc C C C oc 0 0 16 16 16 16 19 19 13 13

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO VALVE NUMBER DRA"ING NUMBER SHEET DR"G VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1*CH*RV*1382B 11448*CBM*088B 1 OF 3 C-7 RELIEF VALVE SEAL "ATER HEAT EXCHANGER RELIEF VALVE, RV DISCHARGE TO VOLUME CONTROL TANK 1*CH*TV*1204A 11448*CBM*088C 1 OF 2 0*3 AO GATE LETDOWN CONTROL FROM REGEN HX, INSIDE CONTAINMENT ISOLATION VALVE 1*CH*TV*1204B 11448-CBM*OBBA 4 OF 4 D-3 AO GATE LETDOWN CONTROL FROM REGEN HX, OUTSIDE CONTAINMENT ISOLATION VALVE 2.000 2 ----------2.000 2 ----------2.000 2 C SP ---A CIV EV FS LT ST VP -------A CIV EV FS LT ST VP PAGE: 12 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* 0 --------C 15 C 15 C C 15 oc --------C 15 C 15 C C 15 oc -------------------------------------------------------------

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-CS-013 1-CS-024 1-CS-105 1-CS-127 1-CS-MOV-100A DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-084A 2 OF 3 F-4 CHECK VALVE 11 A 11 CONT SPRAY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 11448-CBM-084A 2 OF 3 E-4 CHECK VALVE "B" CONT SPRAY PUMP INSIDE CONTAINMENT ISOLATION DISCHARGE CHECK VALVE 11448-CBM-084A 2 OF 3 F-3 CHECK VALVE CONTAINMENT SPRAY PUMP DISCHARGE CHECK VALVE 11448-CBM-084A
  • 2 OF 3 F-5 MO GATE "A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CS-MOV-101B 11448-CBM-084A 2 OF 3 F-5 MO GATE "A" CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CS-MOV-101C 11448-CBM-084A 2 OF 3 E-5 MO GATE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 8.000 2 8.000 2 8.000 2 8.000 2 12.000 2 12.000 2 AC CIV CV LT AC CIV CV LT C C B B CV CV EV ST VP EV ST VP 8.000 2. A CIV EV LT ST 8.000 2 8.000 2 VP A CIV EV LT ST VP A CIV EV PAGE: 13 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0 C C 0 C C 0 C 0 0 0 oc 0 0 oc C 0 C C 0 DC C 0 C C 0 DC C 43 43 43 43 43 43 43 43

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  • VALVE NUMBER DRA"ING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL .INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DR"G VALVE NUMBER COOR TYPE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1*CS*MOV*101C 11448*CBM*084A 2 OF 3 E-5 MO GATE 8.000 2 A CIV EV LT ST 11 B 11 CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-CS*MOV*101D 11448*CBM*084A 2 OF 3 E-5 MO GATE. 11 8 11 CONT SPRAY PUMP DISCHARGE ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1*CS*MOV*102A 11448*CBM-084A 3 OF 3 C-6 MO GATE CHEMICAL ADDITION TANK DISCHARGE TO R"ST ISOLATION VALVE 8.000 2 6.000 2 1-CS*MOV-102B 11448*CBM-084A 3 OF 3 B-6 MO GATE 6.000 2 CHEMICAL ADDITION TANK DISCHARGE TO R"5T ISOLATION VALVE VP A CIV EV LT ST B B VP EV ST VP EV ST VP PAGE: 14 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV* VCN-0 C C 0 oc C 0 C C 0 oc 0 0 oc 0 0 oc

  • * *
  • VALVE NUMBER 1-cv-002 1-CV*HCV-100 1*CV*TV*150A VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM*OSSA 1 OF 2 D-4 MAN GATE CONTAINMENT VACUUM EJECTOR SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1144B*CBM*085A 1 OF 2 D-3 AO GATE CONTAINMENT VACUUM EJECTOR, INSIDE CONTAIN* MENT ISOLATION VALVE 11448-CBM*OSSA 2 OF 2 E-4 AO GATE 11 A 11 CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IIIV VALVE TEST SIZE CLASS CAT TYPE TYPE 8.000 2 8.000 2 2.000 2 AE CIV LT AE CIV LT VP A CIV EV FS LT ST VP ----------------------------------------------------~--------

1*CV*TV-150B 1*CV*TV*150C 1*CV*TV-150D 11448*CBM*085A 2 OF 2 E-5 AO GATE "A" CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM*OBSA 2 OF 2 D-4 AO GATE ,*,. 11 8 11 r."*lTA.rn"!t:NT

""'"-llM PUMP $1Jl'.:TllJN ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM*OSSA 2 OF 2 D-5 AO GATE 11 B 11 CONTAINMENT VACUUM PUMP SUCTION ISOLATION VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 2.000 2 A CIV EV FS LT ST VP 2.000 2 A CIV EV FS LT ST VP 2.000 2 A CIV EV FS LT ST VP PAGE: 15 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN-C C oc C C C C oc C C C C oc C C C C oc C C C C oc ------------,

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  • VIRGINIA POWER COMPANY , SURRY UNIT 1 THIRD,INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 1-CW-MOV-100A 11448-CBM-071A 2 OF 4 F-7 MO BFLY CONDENSER DISCHARGE ISOLATION VALVE 1-CW-MOV-100B 11448-CBM-071A 2 OF 4 F-7 MO BFLY CONDENSER DISCAHRGE ISOLATION VALVE 1-CW-MOV-100C 1144B-CBM-071A 2 OF 4 F-6 MO BFLY CONDENSER DISCHARGE ISOLATION VALVE 1-CW-MOV-100D 11448-CBM-071A 2 OF 4 F-5 MO BFLY CONDENSER DISCHARGE ISOLATION VALVE 1-CW-MOV-106A 11448-CBM-071A 2 OF 4 D-7 MO BFLY CONDENSER INLET ISOLATION VALVE 1-CW-MOV-106B 11448-CBM-071A 2 OF 4 D-7 MO BFLY CONDENSER INLET ISOLATION VALVE -------------------------------
  • -----------------------------

1-CW-MOV-106C 11448-CBM-071A 2 OF 4 D-5 MO BFLY CONDENSER INLET ISOLATION VALVE 1-CW-MOV-1060 1144B-CBM-071A 2 OF 4 D-5 MO BFLY ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 96.000 NC 96.000 NC 96.000 NC 96.000 NC 96.000 3 96.000 3 96.000 3 96.000 3 B B B B B B B B EV ST VP EV ST VP EV ST w EV ST w EV ST w EV ST w EV ST VP EV ST VP -----------------*

CONDENSER INLET ISOLATION VALVE PAGE: 16 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C oc C C oc C C oc C C oc C C oc C C QC C C oc C C oc

  • VALVE NUMBER 1*DA*TV*100A 1*DA*TV*100B 1*DA*TV*103A 1*DA*TV*103B
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBM*083B 3 OF 3 B-3 AO GATE REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, OUTSIDE CONTAINMENT ISOLATION VALVE . 11448*CBM*083A 2 OF 3 E-7 AO GATE REACTOR CONTAINMENT SUMP PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*083A 2 OF 3 E-7 AO GATE ----------------------------------------*----

POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*083A 2 OF 3 E-7 AO GATE POST ACCIDENT SAMPLE SYSTEM RETURN, OUTSIDE CONTAINMENT TRIP VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 2.000 2 2.000 2 2.000 2 A *CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 17 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV* VCN* C C C C oc C C C C oc C C C C oc C C C C oc

  • VALVE NUMBER 1*DG*TV*108A 1-DG*TV-1088
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-0838 1 OF 3 B-2 AO GATE PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, INSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*083A 1 OF 3 C-7 AO GATE PRIMARY DRAIN TRANSFER PUMPS DISCHARGE, OUT* SIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 2.000 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 18 OF 70 REVISION:

OD DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C C C C oc C C C C oc

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  • VALVE NUMBER 1-EE-015 1-EE-019 1-EE-028 1-EE-035 1-EE-RV-103 1-EE-RV-105 1-EE-RV-106 1-EE-RV-108 1-EE-SOV-100 1-EE-SOV-101 1-EE-SOV-104 1-EE-SOV-105 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRA"ING NUMBER SHEET DR"G VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-FB -038A 2 OF 3 B-7 CHECK VALVE DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 11448-FB -038A 2 OF 3 F-7 CHECK VALVE DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 11448-FB -038A 2 OF 3 F-6 CHECK VALVE DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 11448-FB -038" 2 OF 3 B-6 CHECK VALVE DIESEL EMERGENCY GENERATOR FUEL OIL PUMP DISCHARGE CHECK VALVE 11448-FB -038A 1 OF 3 C-7 RELIEF VALVE DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE VALVE, RV DISCHARGE TO PUMP SUCTION 11448-FB -038A 1 OF 3 F-7 RELIEF VALVE DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 11448-FB -038" 1 OF 3 C-6 RELIEF VALVE DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE VALVE, RV DISCHARGE TO PUMP SUCTION 11448-FB -038A 1 OF 3 E-6 RELIEF VALVE DIESEL FUEL OIL PUMP DISCHARGE RELIEF VALVE 11448-FB -038A 2 OF 3 C-4 SO GATE DIESEL FUEL OIL PUMP DISCHARGE VALVE 11448-FB -038A 2 OF 3 B-4 SO GATE DIESEL FUEL OIL PUMP DISCHARGE VALVE 11448-FB -038A 2 OF 3 F-4 SO GATE DIESEL FUEL OIL PUMP DISCHARGE VALVE 11448-FB -038A 2 OF 3 F-4 SO GATE 1_500 NC C 1.500 NC C 1.500 NC C 1.500 NC C .500 NC C .500 NC C .500 NC C .500 NC C 1.000 NC B 1.000 NC B 1.000 NC B 1.000 NC B CV CV CV CV SP SP SP SP EV ST EV ST EV ST EV ST PAGE: 19 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 4 4 4

  • *
  • VALVE NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE DIESEL FUEL OIL PUMP DISCHARGE VALVE PAGE: 20 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN*

  • 1
  • *
  • VALVE NUMBER 1-EG-040 1-EG-042 1-EG-043 1-EG-044 1-EG-045 1-EG-046 VIRGINIA PO\IER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-FB -046A 1 OF 3 B-8 CHECK VALVE DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 11448-FB -046A 1 OF 3 B-4 CHECK VALVE DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 11448-FB -046A 1 OF 3 E-7 AIR PILOT EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 11448-FB -046A 1 OF 3 E-3 AIR PILOT EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 11448-FB -046A 1 OF 3 E-7 CHECK VALVE EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 11448-FB -046A 1 OF 3 E-4 CHECK VALVE EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE .750 NC AC .750 NC AC NC B NC B NC C NC C CV LT CV LT EV ST EV ST CV CV 1-EG-SOV"-100A 11448-FB -046A 1 OF 3 E-7 SO GATE 1.000 NC B EV ST DIESEL AIR START SYSTEM SOLENOID VALVE 1-EG-SOV-100B 11448-FB -046A 1 OF 3 E-4 SO GATE 3-EG-040 3-EG-042 DIESEL AIR START SYSTEM SOLENOID VALVE 11448-FB -046C 1 OF 3 B-8 CHECK VALVE DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 11448-FB -046C 1 OF 3 B-4 CHECK VALVE 1.000 NC .750 NC .750 NC B AC AC EV ST CV LT CV LT PAGE: 21 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C 0 0 0 0 C 0 C 0 C 0 C 0 C 0 C 0 C C C C 3 3 3 3 3 3 3 3 3 3

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3-EG-043 3-EG-044 3-EG-045 3-EG-046 DIESEL GENERATOR COMPRESSOR DISCHARGE CHECK VALVE 11448-FB *046C 1 OF 3 E-7 AIR PILOT EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 11448-FB *046C 1 OF 3 E-3 AIR PILOT EMERGENCY DIESEL GENERATOR STARTING AIR/DRIVE AIR CONTROL/RELAY VALVE 11448-FB *046C 1 OF 3 E-7 CHECK VALVE EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 11448-FB *046C 1 OF 3 E-4 CHECK VALVE EMERGENCY DIESEL GENERATOR START PRESSURE EQUALIZING CHECK VALVE 3*EG*SOV-300A 11448-FB *046C 1 OF 3 E-7 SO GATE DIESEL AIR START SYSTEM SOLENOID VALVE 3-EG-SOV-300B 11448-FB *046C 1 OF 3 E-4 SO GATE DIESEL AIR START SYSTEM SOLENOID VALVE NC NC NC NC 1.000 NC 1.000 NC B B C C B B EV ST EV ST CV CV EV ST EV ST PAGE: 22 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN* 0 0 0 0 C 0 C 0 C 0 C 0 C 0 C 0 3 3 3 3 3 3 3 3 3 3

  • *
  • VALVE NUMBER 1-FP-151 1-FP-152 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAIJING NUMBER SHEET DRIJG VALVE NUMBER COOR TYPE 11448-CBB-0478 1 OF 3 D-6 MAN BALL FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBB-0478 1 OF 3 E-6 MAN BALL FIRE PROTECTION SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IIJV VALVE TEST SIZE CLASS CAT TYPE TYPE 4.000 2 AE CIV LT 4.000 2 AE CIV LT PAGE: 23 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C -------------------------------------------------------------

  • *

INSIDE 3.000 2 6.000 2 C CV C CV C CV C CV C CV C CV C CV PAGE: 24 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV* VCN-C 5 0 4 C 5 0 4 C 5 0 4 0 4 ,,~a-c~-()~~-\

1 OF 4 B-4. C!lf.r.K VALVE .*, , 6.1)00 2 AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION*

OUTSIDE C CV.,.* O* , ...

INSIDE 11448*CBM*068A 1 OF 4 A-4 CHECK VALVE AUXILIARY FEEDWATER HEADER CHECK VALVE AT CONTAINMENT PENETRATION*

OUTSIDE 11448*CBM*D68A 3 OF 4 D-8 CHECK VALVE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 11448*CBM*D68A 3 OF 4 D-7 CHECK VALVE TURBINE DRIVEN AUXILIARY FEEDWATER PUMP RECIR~ LINE CHECK VALVE 6.000 2 C 6.000 2 C 6.000 3 C 1.000 3 C CV CV CV CV 0 0 C 0 0 41 4 4 4 4

  • *
  • VALVE NUMBER 1-FW-148 . 1-FW-157 1-FW-159 1-FW-163 1-FW-172 1 *FW-174 1-FW-178 1-FW-272 1-FW-273 1-FW-309 1-FW-310 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE*TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-068A 3 OF 4 E-7 CHECK VALVE AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 11448*CBM-068A 3 OF 4 D-6 CHECK VALVE ---------------------.-----------------------

11 A 11 MOTOR DRIVEN AUXILIARY FEEDWATER PUMP DISCHARGE CHECK VALVE 11448-CBM-068A 3 OF 4 D-6 CHECK VALVE 11 A 11 MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 11448-CBM-068A 3 OF 4 E-6 CHECK VALVE AUXILIARY FEEDWATER TO PUMP OIL COOLER CHECK VALVE 11448-CBM-068A 3 Of 4 D-5 CHECK VALVE "B" MOTOR DRIVEN AUXILIARYFEEDWATER PUMP DISCHARGE CHECK VALVE 11448-CBM-068A 3 OF 4 D-5 CHECK VALVE 11 8 11 MOTOR DRIVEN AUXILIARY FEEDWATER PUMP RECIRC LINE CHECK VALVE 11448-CBM-068A 3 OF 4 E-4 CHECK VALVE AUXILIARY FEEDWATER TO PUMP OIL COOLER . .. . *. ., ... Cl!f.~K .:lll.t.VE 11448-CBM*068A 1 OF 4 A-8 CHECK VALVE CHECK VALVE AT CONT PENE (CROSS -CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 11448-CBM-068A 1 OF 4 A-7 CHECK VALVE CHECK VALVE AT CONT PENE (CROSS -CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 11448-CBM*068A 1 OF 4 A-5 CHECK VALVE CHECK VALVE AT CONT PENE (CROSS -CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 11448-CBM-068A 1 OF 4 A-5 CHECK VALVE CHECK VALVE AT CONT PENE (CROSS -CONNECT FOR UNIT 1 AUX FEED FROM UNIT 2) 1.000 3 C CV 6.000 3 C CV 1.000 3 C CV 1.000 3 C CV 6.000 3 C CV 1.000 3 C CV 1.000 3 C CV 6.000 2 C CV 6.000 2 C CV 6.000 2 C CV 6.000 2 C CV 1-FW-FCV-1478 11448-CBM*068A 1 OF 4 E-5 AO GATE 14.000 NC B EV FS ST VP PAGE: 25 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV-RRV* VCN-0 C 0 0 0 C 0 0 0 0 0 0 0 C C C oc 41 41 41 41 41 ---4 4 4 4 4 4 4 4 ----28 28 28 --------

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE MAIN FEEDWATER REGULATING VALVE 1-FW*FCV-1488 11448*CBM*068A 1 OF 4 D-5 AO GATE MAIN FEEDWATER REGULATING VALVE 1-FW*FCV-1498 11448*CBM*068A 1 OF 4 B-5 AO GATE MAIN FEEDWATER REGULATING VALVE 1-FW*HCV-155A 11448*CBM*068A 1 OF 4 F-3 AO GATE MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 1-FW*HCV-155B 11448-CBM*068A 1 OF 4 D-3 AO GATE MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 1*FW*HCV-155C 11448*CBM*068A 1 OF 4 C-3 AO GATE MAIN FEEDWATER REGULATING VALVE BYPASS VALVE 1*FW*MOV-151A 11448*CBM*068A 1 OF 4 B-7 MO GLOBE NORMAL AUXILIARY FEEDWATER SUPPLY TO 11 C 11 STEAM GENERATOR 1-FW*MOV-151B 1144S*CBM-068A 1 OF 4 B-7 MO GLOBE 14.000 NC 14.000 NC ----------4.0.00 NC 4.000 NC 4.000 NC 3.000 2 3.000 2 B B B B B B B , EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP EV ST VP EV ST VP PAGE: 26 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN-C C C oc C C C OC C C C oc C C C oc C C C oc C 0 C 0 QC C Q C 0 QC ---------28 28 28 28 28 28 ----28 28 28 ----28 28 28 ----28 28 28 ------------------------

  • *
  • VIRGINIA P~ER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE STANDBY AUXILIARY FEEDWATER SUPPLY TO 11 C 11 STEAM GENERATOR 1-FW-MOV-151C 11448-CBM-068A 1 OF 4 B-6 MO GLOBE STANDBY AUXILIARY FEEDWATER SUPPLY TO 11 8 11 STEAM GENERATOR 1-FW-MOV-151D 11448-CBM-068A 1 OF 4 B-6 MO GLOBE NORMAL AUXILIARY FEEDWATER SUPPLY TO 11 8" STEAM GENERATOR 1-FW-MOV-151E 11448-CBM-068A 1 OF 4 B-6 MO GLOBE STANDBY AUXILIARY FEEDWATER SUPPLY TO "A" STEAM GENERATOR 1-FW-MOV-151F 11448-CBM-068A 1 OF 4 B-5 MO GLOBE STANDBY AUXILIARY FEEDWATER SUPPLY TO 11 A 11 STEAM GENERATOR 1-FW-MOV-160A 11548-CBM-068A 3 OF 4 F-7 MO GLOBE CROSS -COWNECT FOR UNIT 1 AUXILIARY WATER FROM UNIT 2 1-FW-MOV-160B 11548-CBM-068A 3 OF 4 F-7 MO GLOBE CROSS -CONNECT FOR UNIT 1 AUXILIARY WATER FROM UNIT 2 ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 3.000 2 3.000 2 3.000 2 6.000 3 6.000 3 B B B B B B EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP EV ST VP PAGE: 27 OF 70 REVISION:

00 DATE: 11/10/93 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 0 0 oc 0 0 oc

  • ** VALVE NUMBER 1*GW*TV*100 1*GW*TV*101 1-GW*TV-102 1-GW*TV-103 1-GW*TV-104 1-GW*TV-105 1-GW*TV-106 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBM*090C 1 OF 1 C-6 SO GATE SUCTION LINE TO HYDROGEN ANALYZER*

UNIT 1 11448*CBM*090C 1 OF 1 C-6 SO GATE SUCTION LINE TO HYDROGEN ANALYZER*

UNIT 1 11448*CBM*090C 1 OF 1 A-7 SO GATE DISCHARGE LINE TO HYDROGEN ANALYZER*

UNIT 1 11448*CBM*090C 1 OF 1 A-7 SO GATE DISCHARGE LINE TO HYDROGEN ANALYZER*

UNIT 1 11448*CBM*090C 1 OF 1 E-6 SO GATE SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*090C 1 OF 1 E-6 SO GATE SUPPLY TO UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*090C 1 OF 1 D-7 SO GATE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE .375 2 .375 2 .375 2 .375 2 .375 2 .375 2 .375 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 28 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN-C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc

  • *
  • VALVE NUMBER 1-GW*TV-107 1*GW-TV*111A 1-Gw-:rv-111B VIRGINIA POlolER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM-090C*

1 OF 1 D-7 SO GATE RETURN FROM UNIT 2 HYDROGEN ANALYZER, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*090C 1 OF 1 F-8 SO GATE UNIT 1 SAMPLE LINE TO AIR SAMPLE PANEL, INSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*090C 1 OF 1 F-7 SO GATE UNIT 1 SAMPLE .LINE TO AIR SAMPLE PANEL, OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE -----.375 2 -----.375 2 .375 2 -------A CIV EV FS LT ST VP -------A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 29 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV-RRV-VCN-C C C C oc C C C C oc C C C C oc ------------------------------

.'.

  • VALVE NUMBER 1-IA-446 1-IA-704 1-IA-928 1-IA-938 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-075C 1 OF 5 D-8 MAN GATE BACKUP INSTRUMENT AIR TO CONTAINMENT 11548-CBM-075B 2 OF 2 C-3 MAN GATE BACKUP INSTRUMENT AIR TO CONTAINMENT 11448-FM -075E 1 OF 1 A-2 CHECK VALVE BOTTLED AIR SUPPLY TO 1-RC~PCV-1456 ISOLATION CHECK VALVE 11448-CBM-075C 1 OF 5 F-7 CHECK VALVE INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE ISO VALVE .ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 2.000 2 .750 NC 2.000 2 AE CIV LT AE CIV LT AC AC CIV CV LT CV LT -------------------------------------------------------------

. -----------1-IA-939 1-IA-947 1-IA-948 1-IA-949 1-IA-952 1-IA-953 1-IA-RV-114 1-IA-RV-115 11448-CBM-075C 1 OF 5 F-7 CHECK VALVE INSTRUMENT AIR SUPPLY TO CONTAINMENT, INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-075C 3 OF 5 D-4 CHECK VALVE BOTTLED AIR SUPPLY TO 1-MS-SOV-102A,B ISOLATION CHECK VALVE 11448-CBM-075C 3 OF 5 D-4 CHECK VALVE BOTTLED AIR SUPPLY TO 1-MS-SOV-102A,B SUPPLY CHECK VALVE 11448-FM -075E .1 OF 1 A-2 CHECK VALVE BOTTLED AIR SUPPLY TO 1-RC-PCV-1456 SUPPLY CHECK VALVE 11448-FM -075E 1 OF 1 C-2 CHECK VALVE BOTTLED AIR SUPPLY TO 1-RC-PCV-1455C ISOLATION CHECK VALVE 11448-FM -075E 1 OF 1 D-2 CHECK VALVE BOTTLED AIR SUPPLY TO 1-RC-PCV-1455C SUPPLY CHECK VALVE 11448-FM -075E 1 OF 1 B-4 RELIEF VALVE BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE 11448-FM -075E 1 OF 1 B-3 RELIEF VALVE 2.000 2 .500 NC .500 NC .750 NC .750 NC NC NC AC CIV CV LT AC C C AC C C C CV LT CV CV CV LT CV SP SP PAGE: 30 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C C C C C C C 0 0 C C 0 0 0 6 ----I 6

  • *
  • VALVE NUMBER 1-IA*TV-100 1*1A*TV-101A 1*1A*TV*101B VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE BOTTLED AIR SUPPLY TO PORV'S RELIEF VALVE 11448*CBM*075C 1 OF 5 E-8 AO GATE INSTRUMENT AIR SUPPLY TO CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*075J 1 OF 1 A-3 AO GATE INSTRUMENT.AIR SUCTION FROM CONTAINMENT 11448*CBM*075J 1 OF 1 A-3 AO GATE INSTRUMENT AIR SUCTION FROM CONTAINMENT ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 3.000 2 3.000 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 31 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C C C C oc C C C C oc C C C C oc

  • *
  • VALVE NUMBER 1-LM-TV-100A DRAWING NlllBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NlllBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-OBSA 1 OF 2 B-6 AO GATE .375 2 A CIV EV FS LT ST VP CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE -------------------------------------------------------------

1-LM-TV-100B 1-LM-TV-100C 1-LM-TV-100D 1-LM-TV-100E 1-LM-TV-100F 1-LM-TV-100G 11448-CBM-OBSA 1 OF 2 B-6 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-OBSA 1 OF 2 B-5 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-OBSA 1 OF 2 B-5 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-085A 1 OF 2 B-4 AO GATE. CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-OBSA 1 OF 2 B-5 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-OBSA 1 OF 2 B-6 AO GATE .375 2 .375 2 .375 2 .375 2 .375 2 .375 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 32 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc

  • *
  • VALVE NUMBER 1-LM-TV-100H VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-OSSA 1 OF 2 B-7 AO GATE CONTAINMENT LEAKAGE MONITORING OPEN SYSTEM SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE .375 2 A CIV EV FS LT ST VP PAGE: 33 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C oc l

  • *

1-------------------------"C" MAIN STEAM HEADER NON-RETURN VALVE 1-MS-PCV-102A 11448-CBM-064A 4 OF 6 C-4 AO GATE 3.000 2 B B B C C C C C C B EV EV EV CV CV CV CV VP CV VP CV VP EV FS ST PAGE: 34 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C 0 C 0 C 0 C oc C oc C oc C 0 C C 0 42 42 42 32 32 32 VP OC MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP

  • *
  • VALVE NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1-MS-PCV-102B 11448-CBM-064A 4 OF 6 D-5 AO GATE 3.000 2 B EV FS ST 1-MS-RV-101A 1-MS-RV-101B 1-MS-RV-101C 1-MS-SV-101A 1-MS-SV-101B 1-MS-SV-101C 1-MS-SV-102A 1-MS-SV-102B MAIN STEAM SUPPLY TRIP VALVE TO TURBINE DRIVEN AUXILIARY FEEDWATER PUMP 11448-CBM-064A 1 OF 6 E-5 AO ANGLE 4.000 2 11 A 11 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 11448-CBM-064A 2 OF 6 E-6 AO ANGLE 4.000 2 11 8 11 MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 11448-CBM-064A 3 OF 6 E-5 AO ANGLE "C" MAIN STEAM HEADER DISCHARGE TO ATMOSPHERE POWER OPERATED RELIEF VALVE 11448-CBM-064A . 1 OF 6 E-6 SAFETY VALVE "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448-CBM-064A 2 OF 6 D-6 SAFETY VALVE 11 8 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448-CBM-064A 3 OF 6 D-6 SAFETY VALVE 11 C 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448-CBM-064A 1 OF 6 E-6 SAFETY VALVE "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448-CBM-064A 2 OF 6 D-5 SAFETY VALVE 4.000 2 4.000 2 4.000 2 4.000 2 6.000 2 6.000 2 B B B C C C C C VP EV FS ST VP EV FS ST VP EV FS ST 'IP SP SP SP SP SP PAGE: 35 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST PQS V-CSV-RRV-VCN-C Q C C 0 oc C Q C C 47 Q 47 QC C Q C C Q QC C 0 C C Q QC 0 0 0 0 0 ---47 47 47 47 ------------

  • *
  • VALVE NUMBER 1*MS*SV*102C 1*MS*SV*103A 1*MS*SV*103B 1*MS*SV*103C 1*MS*SV*104A 1*MS*SV*104B 1*MS*SV*104C H4S*SV-105A 1*MS*SV*105B 1*MS*SV*105C 1*MS*TV*101A VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11 8 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM-064A 3 OF 6 D-6 SAFETY VALVE 11 C 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 1 OF 6 E-6 SAFETY VALVE 11 A 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 2 OF 6 D-6 SAFETY VALVE 11 8 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGEE TO ATMOS 11448*CBM*064A 3 OF 6 D-6. SAFETY VALVE 11 C 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 1 OF 6 E-6 SAFETY VALVE 11 A 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 2 OF 6 D-6 SAFETY VALVE 11 8 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 3 OF 6 D-6 SAFETY VALVE "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 1 OF 6 E-5 SAFETY VALVE "A" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*CBM*064A 2 OF 6 D*S SAFETY VALVE 11 8 11 MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS 11448*C8M*064A 3 OF 6 D*S SAFETY VALVE "C" MAIN STEAM HEADER SAFETY VALVE, SV DISCHARGE TO ATMOS ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 6.000 2 C SP 11448*CBM*064A 1 OF 6 D-4 AO CHECK VALVE 30.000 2 8 EV ST VP 11 A 11 MAIN STEAM HEADER TRIP VALVE PAGE: 36 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* 0 0 0 0 0 0 0 0 0 0 C C oc

  • VALVE NUMBER 1*MS*TV*101B 1*MS*TV*101C 1*MS*TV*109 1*MS*TV*110
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448*CBM*064A 2 OF 6 C-4 AO CHECK VALVE 30.000 2 11 8 11 MAIN STEAM HEADER TRIP VALVE 11448*CBM*064A 3 OF 6 C*4 AO CHECK VALVE 30.000 2 11 C 11 MAIN STEAM HEADER TRIP VALVE 11448*CBM*064A 4 OF 6 F*S 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 ISOLATION TO STEAM GENERATOR SLOWDOWN SYSTEM 3.000 2 2.000 2 B B B B EV ST VP EV ST VP EV FS ST VP EV FS ST VP PAGE: 37 OF 70 REVISION:

00 DATE: 11/10/93 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

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-RC-160 DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-0868 2 OF 3 D-7 CHECK VALVE PRIMARY GRADE WATER SUPPLY TO PRESSURIZER RELIEF TANK 1-RC-HCV-1556A 11448-CBM-OS6A 1 OF 3 E-8 AO PLUG LOOP FILL BOUNDARY VALVE 1-RC-HCV-1556B 11448-CBM-086A 2 OF 3 D-8 AO PLUG LOOP FILL BOUNDARY VALVE 1-RC-HCV-1556C 11448-CBM-086A 3 OF 3 D-3 AO PLUG LOOP FILL BOUNDARY VALVE 1-RC-MOV-1535 11448-CBM-0868 1 OF 3 E-4 MO GATE BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 1-RC-MOV-1536 11448-CBM-0868 1 OF 3 D-4 MO GATE BLOCK VALVE FOR PRESSURIZER POWER OPERATED RELIEF VALVE 1-RC-PCV-1455C 11448-CBM-0868 1 OF 3 D-3 AD PLUG PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-PCV-1456 11448-CBM-086B 1 OF 3 E-3 AO PLUG PRESSURIZER POWER OPERATED PRESSURE CONTROL VALVE DISCHARGE TO PRESSURIZER RELIEF TANK ISO VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 2.000 1 2.000 1 2.000 1 3.000 1 AC CIV CV LT E E E B VP VP VP EV ST VP 3.000 1 B EV ST VP -------------3.000 1 BC EV FS SP ST VP -------------3.000 1 BC EV FS SP ST VP PAGE: 38 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C DC oc oc C 0 C 0 DC C 0 C 0 DC C 0 C 0 C 0 DC C 0 C 0 C 0 DC 6 -------7 7 7 7 7 ---------------7 7 7 7 7 f

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE 'VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 1-RC-SOV-100A1 11448-CBM-086A 3 OF 3 B-5 SO GATE REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1-RC-SOV-100A2 11448-CBM-086A 3 OF 3 A-5 SO GATE --------*------------------------------------

REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1-RC-SOV-100B1 11448-CBM-086A

  • 3 OF 3 B-5 SO GATE REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1-RC-SOV-100B2 11448-CBM-D86A 3 OF 3 A-5 SO GATE REACTOR VESSEL VENT LINE ISOLATION VALVE TO REFUELING CAVITY 1-RC-SV-1551A 11448-CBM-0868 1 OF 3 E-6 SAFETY VALVE PRESSURIZER SAFETY VALVE, SY DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-SV-1551B 11448-CBM-0868 1 OF 3 E-5 SAFETY VALVE PRESSURIZER SAFETY VALVE, SY DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-SV-1551C 11448-CBM-0868 1 OF 3 E-5 SAFETY VALVE PRESSURIZER SAFETY VALVE, SY DISCHARGE TO PRESSURIZER RELIEF TANK 1-RC-TV-1519A 11448-CBM-0868 2 OF 3 D-7 AO GATE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1.000 1 ----------1.000 1 ----------,_ooo 1 ----------1.000 1 6.000 1 6.000 1 6.000 1 3.000 2 B ---B ---B ---B. C C C EV FS ST VP EV FS ST VP EV FS ST VP EV FS ST VP SP SP SP A CIV EV FS LT ST VP PAGE: 39 OF 70 REVISION:

00 DATE: 11/10/93 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 0 C C 0 iJC 0 0 0 C C C C oc ---------33 33 33 33 33 ----33 33 33 33 33 ----33 33 33 33 33 ----33 33 33 33 33 ------------------------

  • *
  • VALVE NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE PRIMARY GRADE WATER SUPPLY TO PRT-#2 RCP SEAL STANDPIPES

& FLUSH CONNECT, OUT CONT ISO VLV PAGE: 40 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-

  • * '_,..,,..,,.
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-RH-005 1-RH-011 DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-087A 1 OF 2 E-5 CHECK VALVE "B" RHR Pll!P DISCHARGE CHECK VALVE 11448-CBM-087A 1 OF 2 E-7 CHECK VALVE "A" RHR Pll!P DISCHARGE CHECK VALVE 1-RH-FCV-1605 11448-CBM-087A 2 OF 2 *c-7 AO BFLY ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 10-000 2 10.000 2 12.000 2 C C B CV CV EV FS ST RHR HEAT EXCHANGERS BYPASS FLOW CONTROL VALVE 1-RH-HCV-1758 11448-CBM-087A 2 OF 2 C-5 AO BFLY 1-RH-MOV-100 RHR HEAT EXCHANGERS DISCHARGE FLOW CONTROL VALVE 11448-CBM-087A 2 OF 2 E-3 MO GATE RHR SUPPLY ISOLATION TO REFUEL WATER STORAGE TANK, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RH-MOV-1700 11448-CBM-087A 1 OF 2 A-5 MO GATE :.* ""* . ,_ ~HR ['!,~~?.-!1£:'~1 'f J!l~~:".TU?I
f~.~-,.~r.-

! ~~-'*1*: HOT LEG 1-RH-MOV-1701 11448-CBM-087A 1 OF 2 A-4 MO GATE RHR PUMP SUPPLY ISOLATION FROM RC LOOP 1 HOT LEG 1-RH-MOV-1720A 11448-CBM-087A 2 OF 2 C-3 MO GATE RHR RETURN ISOLATION TO 11 B 11 ACCUMULATOR DISCHARGE LI NE 1-RH-MOV-1720B 11448-CBM-087A 2 OF 2 B-3 MO GATE 1-RH-RV-1721 RHR RETURN ISOLATION TO 11 C 11 ACCUMULATOR DISCHARGE LI NE 11448-CBM-087A 2 OF 2 D-4 RELIEF VALVE 12.000 2 6.000 2 14.000 1 ***:,.'.'."-,:*

14.000 1 10.000 1 10.000 1 3.000 2 B EV FS ST AE CIV LT B ' .. , .~ . B B B C EV ST VP EV ST VP EV ST VP EV ST VP SP PAGE: 41 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0 C 0 C C C 0 0 0 C 0 0 oc 0 0 oc 0 0 oc 0 0 oc 0 8 8 8 8 14 14 47 14 14 14 47 14 9 9 9 9 10 10 10 10

  • * * "VALVE NUMBER DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE RHR SYSTEM RELIEF VALVE PAGE: 42 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST PCS V-CSV-RRV-VCN-

  • *
  • VALVE NUMBER 1-RL-003 . 1-RL-005 1-RL-013 1-Rl-015 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM*118A 2 OF 3 D-3 MAN DIAPHRAGM REFUELING PURIFICATION FROM RP PUMPS TO REACTOR CAVITY, OUTSIDE CONT ISOLATION VALVE 11448*CBM-118A 2 OF 3 D-5 MAN DIAPHRAGM REFUELING PURIFICATION FROM RP PUMPS To* REACTOR CAVITY, INSIDE CONT ISOLATION VALVE 11448*CBM*118A 2 OF 3 8*4 MAN DIAPHRAGM REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, INSIDE CONT ISOLATION VALVE 11448*CBM-118A 2 OF 3 B-3 MAN DIAPHRAGM REFUELING PURIFICATION FROM REACTOR CAVITY TO RP PUMPS, OUTSIDE CONT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT PAGE: 43 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST PCS V* CSV* RRV* VCN* C C C C

  • *
  • VALVE NUMBER 1-RM-003 1*RM*TV-100A 1*RM*TV*100B 1*RM*TV-100C VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBP-014A 1 OF 1 B*S CHECK VALVE RETURN TO CONTAINMENT FROM RADIATION MONITOR* ING CABINET, INSIDE CONT ISOL CHECK VALVE 11448-CBP*014A 1 OF 1 B-4 AO GATE RETURN ISOLATION FROM AIR RADIATION MONITOR TO CONTAINMENT, OUTSIDE CONT ISOLATION VALVE 11448-CBP*014A 1 OF 1 F-8 AO GATE SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN* MENT VENT DUCT, OUTSIDE CONT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE .750 2 .750 2 .750 2 AC CIV CV LT A CIV EV FS LT ST VP A CIV EV FS LT ST VP 11448*CBP*014A 1 OF 1 E-8 AO GATE .750 2 A CIV EV FS LT ST VP SUPPLY ISOL TO AIR RAD MONITOR FROM CONTAIN* MENT VENT DUCT, INSIDE CONT ISOLATION VALVE ---* PAGE: 44 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C C C C C C QC C C C C QC C C C C DC 6

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  • VALVE NUMBER 1-RS-011 1-RS-017 1-RS-046 1-RS-052 1-RS-MOV-155A VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBM*084B 2 OF 2 E-4 CHECK VALVE 11 8 11 OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448-CBM-084B 2 OF 2 D-5 CHECK VALVE 11 A 11 OUTSIDE RECIRC SPRAY PUMP INSIDE CONTAINMENT ISOLATION CHECK VALVE 11448*CBM*D84B 2 OF 2 A-6 MAN GATE OUTSIDE RECIRC SPRAY PUMP SUCTION BYPASS LINE ISOLATION VALVE 11448-CBM*084B 2 OF 2 B-6 MAN GATE OUTSIDE RECIRC SPRAY PUMP SUCTION BYPASS LINE ISOLATION VALVE 11448-CBM-084B 2 OF 2 B-6 MO PLUG 11 A 11 OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 10.000 2 10.000 2 2 2 12.000 2 AC CIV CV LT AC CIV CV LT AE CIV LT AE CIV LT A CIV EV LT ST VP 1-RS-MOV-155B 11448-CBM-084B 2 OF 2 B-6 MO PLUG 12.000 2 A CIV EV LT ST 11 8 11 OUTSIDE RECIRC SPRAY PUMP SUCTION ISOLAT VALVE FROM CONTAINMENT SUMP 1-RS*MOV-156A 11448-CBM-084B 2 OF 2 D-6 MO BFLY 11 A 11 OUTSIDE RECIRC SPRAY PUMP DISCHARGE LATION, OUTSIDE CONTAINMENT ISOLATION VALVE 1-RS-MOV-156B 11448-CBM-0848 2 OF 2 E-6 MO BFLY 10.000 2 10.000 2 VP A CIV EV LT ST VP A CIV EV LT ST VP PAGE: 45 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0 C C 0 C C C C 0 C C 0 oc C 0 C C 0 oc C 0 C C 0 oc C 0 C C 0 oc 43 43 43 43

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  • VALVE NUMBER DRAIJING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE SHEET DRIJG VALVE NUMBER COOR TYPE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE "A" OUTSIDE RECIRC SPRAY PUMP DISCHARGE ISO* LATION, OUTSIDE COHTAINMENT ISOLATION VALVE PAGE: 46 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN*

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  • VALVE NUMBER 1-RT-02 1-RT-06 1-RT-21 1-RT-25 1-RT-40 1-RT-44 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBM-124A 1 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-124A 1 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-124A 2 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-124A 2 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-124A 3 OF 4 E-7 MANUAL GLOBE STEAM GENERATOR RECIRCULATION INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-124A 3 OF 4 E-6 MANUAL GLOBE STEAM GENERATOR RECIRCULATION OUTSIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT 3.000 2 AE CIV LT PAGE: 47 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN-C C C C C C

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  • VALVE NUMBER 1-SA-060 DRAWING NUMBER VIRGINIA POlolER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-075G 1 OF 1 C-7 MAN GATE SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, INSIDE CONTAINMENT ISOLATION VALVE 2.000 2 AE CIV LT -------------------------------------------------------------

PAGE: 48 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 1-SA-062 11448-CBM-075G 1 OF 1 C-7 MAN GATE SERVICE AIR SUPPLY TO UNIT 1 CONTAINMENT, OUTSIDE CONTAINMENT ISOLATION VALVE 2.000 2 AE CIV LT , C -------------------------------------------------------------

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  • VALVE NUMBER 1-Sl-025 1-Sl-032 1*Sl-046A 1*Sl *046B 1 *Sl-047 1-Sl-050 1-Sl-053 1-Sl-056 1-Sl-058 1-Sl-061 1-Sl-073 1-Sl-079 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-089A 1 OF 3 F*S CHECK VALVE RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER 11448-CBM-089A 1 OF 3 E-7 MAN GLOBE ACCUMULATOR MAKEUP LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-089A 1 OF 3 A-3 CHECK VALVE RWST SUPPLY CHECK VALVE TO "A" LOW HEAD SJ PUMP SUCTION 11448-CBM-089A 1 OF 3 B-3 CHECK VALVE RWST SUPPLY CHECK VALVE TO "B" LOW HEAD SJ PUMP SUCTION 11448*CBM*089A 1 OF 3 B-5 CHECK VALVE 8.000 2 1.000 2 12.000 2 12.000 2 12.000 2 "B" LOW HEAD SJ PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 11448*CBM-089A 1 OF 3 C-4 CHECK VALVE 10.000 2 11 B 11 LOW HEAD SJ PUMP DISCHARGE CHECK VALVE 11448-CBM-089A 2 OF 3 B-4 CHECK VALVE 2.000 2 ., .* ,., .,,,,.11 8 11 LOW HE~. c;1 PUMP. ~JNIMUM. FL!II/TEST,.

UME ., .. DISCHARGE CHECK VALVE 11448-CBM*089A 1 OF 3 B-7 CHECK VALVE 11 A 11 LOW HEAD SI PUMP SUCTION CHECK VALVE FROM CONTAINMENT SUMP 11448-CBM-089A 1 OF 3 C-6 CHECK VALVE 11 A 11 LOW HEAD SJ PUMP DISCHARGE CHECK VALVE 11448-CBM*089A 2 OF 3 B-6 CHECK VALVE 11 A 11 LOW HEAD SJ PUMP MINIMUM FLOW/TEST LINE DISCHARGE CHECK VALVE 11448-CBM-089A 2 OF 3 F-7 MAN GLOBE ACCUMULATOR TEST LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-089B 4 OF 4 F-7 CHECK VALVE 12.000 2 10.000 2 2.000 2 .750 2 6.000 1 AC CV LT AE CJV LT C CV C CV C CV C CV C CV C CV C CV C CV AE CJV LT AC PJV CV PAGE: 49 OF 70 REVISION:

00 DATE: 11/10/93 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 20 20 5 5 2 2 2 2 2 2 4 4

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00 DATE: 11/10/93 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 C 0 0 C 0 0 C 0 0 27 27 27 26 29 4 4 4 4 4 4 4 4 4 4 3 26 3 26 3 29 26 3 26 3

  • VALVE NUMBER 1-Sl-147 1-Sl-150 1-Sl-174 1-Sl-224 1-Sl-225 1-Sl-226 VIRGINIA PO'JER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE --------------------------*------------------

11 C 11 ACCUMULATOR DISCHARGE CHECK VALVE 11448-CBM-089B 3 OF 4 B-7 CHECK VALVE 11 C 11 ACCUMULATOR COLD LEG ADMISSION CHECK VALVE 11448*CBM-089A 3 OF 3 F-6 MAN GLOBE BORON INJECTION TANK BYPASS LINE ISOLATION VALVE -TO RCS COLD LEG 11448*CBM-089A 3 OF 3 D-6 MAN GLOBE HIGH HEAD SAFETY INJECTION TO RCS 11448-CBM-089B 4 OF 4 F-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 E-3 CHECK VALVE HIGH HEAD SI FROM CHARGING PUMPS TO RCS COLD LEGS, INSIDE CONT CHECK VALVE 11448-CBM-089B 4 OF 4 C-3 CHECK VALVE HIGH HEAD SJ FROM CHARGING PUMPS TO RCS HOT LEGS, INSIDE CONT CHECK VALVE 12.000 1 .750 2 .750 2 3.000 2 3.000 2 3.000 2 C CV AE CIV LT AE CIV LT C CV C CV C CV PAGE: 51 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV* VCN-C 0 C C 0 0 0 29 26 3 4 4 4 . ', .. J-Sl-2~7, **"-*..* 11448-CSM-OR9B, 4 OF_ 4 .. C-3 ..* r,~l"CK \/.4ol.\lF.

,,, . , .* ~.nno 2 C. . ~v , .. Q .. , .. .. -~,. ........ .,, .. " 1-Sl-228 1-SJ-229 1-Sl-234 1-Sl-235

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.----------------1-Sl-301 1-Sl-311 11448-CBM*089A 1 OF 3 B-7 MAN GLOBE LOW HEAD SI FROM CHARGING HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 11448*CBM-089A 1 OF 3 A-5 MAN GLOBE .750 2 AE CIV LT .750 2 AE CIV LT L_ _________________

_ PAGE: 52 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C 0 C 0 C 0 C 0 C 0 C o_ C C 0 C C 0 C C C 27 27 27 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 l

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER 1-Sl-410 DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE LOW HEAD SI FROM CHARGING HEADER TO RCS COLD LEGS, BYPASS LINE ISOLATION VALVE 11448-CBM-089A 1 OF 3 F-4 CHECK VALVE RWST SUPPLY CHECK VALVE TO CHARGING PUMP SUCTION HEADER 1-SI-MOV-1842 11448-CBM-089A 3 OF 3 D-7 MO GATE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 10.000 2 C CV -------------3.000 2 A CIV EV LT ST VP HIGH HEAD SI FROM CHARGING HEADER TO RCS COLO LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1860A 11448-CBM-089A 1 OF 3 B-7 MO GATE "A" LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 1-SI-MOV-1860B 11448-CBM-089A 1 OF 3 B-5 MO GATE 11 B 11 LOW HEAD SI PUMP SUCTION ISOLATION FROM CONTAINMENT SUMP 11 A 11 LOW HEAD SI PUMP SUCTION FROM RWST 1-SI-MOV-1862B 11448-CBM-089A 1 OF 3 B-3 MO GATE 11 B 11 LOW HEAD SI PUMP SUCTION FROM RWST 1-SI-MOV-1863A 11448-CBM-089A 2 OF 3 C-5 MO GATE "A" LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1-SI-MOV-1863B 11448-CBM-089A 2 OF 3 D-3 MO GATE 12.000 2 12.000 2 12.000 2 8.000 2 8.000 2 A CIV EV LT ST VP A CIV EV LT ST VP B B B -1::V ST VP EV ST VP EV ST VP EV ST PAGE: 53 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 *C 0 C C 0 DC 0 C 0 DC 0 C 0 DC C *~ C DC C C DC C 0 C 0 DC C 0 C 5 --------25 25 25 25

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SI-MOV-1863B 11448-CBM-089A 2 OF 3 D-3 MO GATE 11 8 11 LOW HEAD SAFETY INJECTION PUMP SUPPLY ISOLATION TO CHARGING PUMPS 1-SI-MOV-1864A 11448-CBM-089A 2 OF 3 D-6 NO GATE 8.000 2 10.000 2 B B ST VP EV ST PAGE: 54 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN* 0 oc C 0 C ,0 VP OC 11 A 11 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 1-SI-MOV-1864B 11448-CBM-089A 2 OF 3 D-4 MO GATE 11 8 11 LOW HEAD SI PUMP COLD LEG DISCHARGE STOP VALVE 1-SI-MOV-1865A 11448-CBM-0898 1 OF 4 C-7 MO GATE 11 A 11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1-SI-MOV-1865B 11448-CBM-089B 2 OF 4 C-6 MO GATE 11 B 11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1-SI-MOV-1865C 11448-CBM-089B 3 OF 4 C-5 MO GATE 11 C 11 ACCUMULATOR DISCHARGE ISOLATION VALVE TO RCS COLD LEG 1-SI-MOV-1867C 11448-CBM-089A 3 OF 3 E-6 MO GATE HIGH HEAD SAFETY INJECTION TO RCS COLD LEG, OUTSIDE CONTAINMENT ISOLATION VALVE 10.000 2 8 12.000 2 8 12.000 2 B 12.DOO 2 B 3.000 2 A CIV EV ST VP EV ST VP EV ST VP EV ST VP EV LT ST VP C 0 C 0 oc C 0 C 0 oc C 0 C 0 oc C 0 C 0 oc C 0 C C 0 oc 18 18 18 18

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 1-SI*MOV-18670 11448-CBM*089A 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*089A 3 OF 3 D-7 MO GATE HIGH HEAD SI FROM CHARGING HEADER TO RCS HOT LEGS, OUTSIDE CONTAINMENT ISOLATION VALVE 1-Sl*MOV-18698 11448-CBM-089A 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*089A 2 OF 3 B-6 MO GATE ., *--"A" .LOW HEAil i.I PUMP. MU!IMIJM .. F!..N/TEST LINE ISOLATION 1-SI-MOV-18858 11448-CBM-089A 2 OF 3 B-4 MO GATE 11 8 11 LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 1*SI-MOV-1885C 11448-CBM-089A 2 OF 3 B-4 MO GATE 11 8 11 LOW HEAD SI PUMP MINIMUM FLOW/TEST LINE ISOLATION 1-SI-MOV-1885D 11448-CBM-089A 2 OF 3 B-6 MO GATE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3.000 2 ----------3.000 2 3.000 2 2.000 2 2.000 2 2.000 2 2.000 2 A CIV EV LT ST VP -------A CIV EV LT ST VP A CIV EV LT ST A A A A VP EV LT ST VP EV LT ST VP EV LT ST VP EV LT ST VP PAGE: 55 OF 70 REVISION:

00 DATE: 11/10/93 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 C oc C C C oc C C C oc C C C oc ---18 18 18 18 ----25 25 25 25 25 25 25 25 --------

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  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER DRAIIING NUMBER SHEET DRIIG VALVE NUMBER COOR TYPE 11 A 11 LOIi HEAD SI PUMP MINIMUM FLOII/TEST LINE ISOLATION 1-SI-MOV-1890A 11448-CBM-089A 2 OF 3 C-7 MO GATE 11 A" LOIi HEAD SI PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-MOV-1890B 11448-CBM-089A 2 OF 3 E-7 MO GATE "B" LOIi HEAD SI PUMP HOT LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE -------------------------------------------------------------

1-SI-MOV-1890C 11448-CBM-089A 2 OF 3 D-7 MO GATE LOIi HEAD SI PUMPS COLD LEG DISCHARGE STOP VALVE, OUTSIDE CONTAINMENT ISOLATION VALVE 1-SI-RV-1845A 11448-CBM-089A 2 OF 3 E-6 RELIEF VALVE "A" LOIi HEAD SI PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 1-SI-RV-1845B 11448-CBM-089A 2 OF 3 E-5 RELIEF VALVE LOIi HEAD SI HEADER TO COLD LEG RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 1-SI-RV-1845C 11448-CBM-089A 2 OF 3 E-5 RELIEF VALVE 1-SI-TV-100 1-SI-TV-101A 11 8 11 LOIi HEAD SI PUMP DISCHARGE RELIEF VALVE, RV DISCHARGE TO SAFEGUARDS AREA SUMP 11448-CBM-089A 3 OF 3 B-7 AO GATE NITROGEN SUPPLY TO ACCUMULATORS, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-0898 1 OF 4 C-3 AO GATE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 10.000 2 10.000 2 ----------10.000 2 1.000 2 1.000 2 1.000 2 1.000 2 1.000 2 A CIV EV LT ST VP A CIV EV LT ST VP -------A CIV EV LT ST VP C SP C SP C SP A CIV EV FS LT ST VP A CIV EV FS LT PAGE: 56 OF 70 REVISION:

00 DATE: 11/10/93 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 0 0 0 C C C C oc C C C --------17 17 17 17

  • VALVE NUMBER 1*Sl*TV*101A 1*Sl*TV*101B 1*SI*TV*102A 1*SI*TV*102B
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NlllBER COOR TYPE 11448*CBM*089B 1 OF 4 C-3 AO GATE ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-0898 1 OF 4 B-2 AO GATE ACCUMULATORS TO WASTE GAS CHARCOAL FILTERS, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*089A 1 OF 3 F-7 AO GATE UNIT 1 RWST TO UNIT 2 RWST CROSS TIE 11448*CBM*089A 1 OF 3 E-7 AO GATE UNIT 1 RWST TO UNIT 2 RWST CROSS TIE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1.000 2 1.000 2 8.000 2 8.000 2 A CIV ST VP A CIV EV FS LT ST VP B B EV .FS ST VP EV FS ST VP PAGE: 57 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN-C oc C C C C oc 0 0 0 oc 0 0 0 oc

  • VALVE NUMBER 1*SS-TV*100A 1*SS*TV-100B 1-SS*TV*101A 1*SS*TV-101B
  • 1-SS*TV-102A 1*SS*TV-102B 1*SS-TV-103A 1-SS-TV-103B
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM-082B 2 OF 2 F-7 SO GATE PRESSURIZER LIQUID SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-082B 2 OF 2 F-6 AO GATE PRESSURIZER LIQUID SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM-082B 2 OF 2 E-7 SO GATE PRESSURIZER VAPOR SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-082B 2 OF 2 E-6 AO GATE PRESSURIZER VAPOR SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-082B 2 OF 2 D-7 SO GATE REACTOR COOLANT COLD LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-082B 2 OF 2 D-6 SO GATE REACTOR COOLANT COLD LEGS SAMPLE HEADER, OUTSIDE CONTAINMENT ISOLATION VALVE 11448-CBM-0828 2 OF 2 F-7 SO GATE RHR SAMPLE HEADER, INSIDE CONTAINMENT TION VALVE 11448-CBM-0828 2 OF 2 F-6 SO GATE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE .375 1 .375 1 .375 1 .375 1 .375 1 .375 1 .375 2 .375 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST. VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP AE CIV LT VP AE CIV LT PAGE: 58 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN-C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C C C C oc C oc C

  • VALVE NUMBER 1*SS*TV*103B
  • 1 *SS*TV*104A 1*SS*TV-104B 1*SS*TV*106A
  • 1*SS*TV-106B
  • I l VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM* VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBM*082B 2 OF 2 F-6 SO GATE RHR SAMPLE HEADER, OUTSIDE CONTAINMENT TION VALVE 11448-CBM-0828 2 OF 2 D-7 SO GATE PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, INSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*D82B 2 OF 2 C-6 AO GATE PRESSURIZER RELIEF TANK GAS SPACE SAMPLE LINE, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*082B 2 OF 2 E-7 SO GATE REACTOR COOLANT HOT LEGS SAMPLE HEADER, INSIDE CONTAINMENT ISOLATION VALVE 11448*CBM*082B 2 OF 2 E-6 SO GATE REACTOR COOLANT HOT LEGS SAMPLE HEADER, OUT* SIDE CONTAINMENT ISOLATION VALVE ISO VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE .375 2 .375 2 .375 2 .375 1 .375 1 AE CIV VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 59 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV-VCN* oc C C C C oc C C C C oc C C C C oc C C C C oc . I

  • VALVE NUMBER 1-SV-TV-102A
  • DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASNE IW VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-066A 2 OF 3 E-4 AO GATE 6.000 2 A CIV EV FS LT ST VP CONDENSER AIR REMOVAL DISCHARGE TO MENT, OUTSIDE CONTAINMENT ISOLATION VALVE PAGE: 60 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C C C C oc

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  • VALVE NUMBER 1-SW-108 1-SW-113 1-SW-130 1-SW-206 1-SW-208 1-SW-246 1-SW-247 1-SW-248 1-SW-249 1-SW-2SO 1-SW-2S1 1-SW-2S2 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-071B 1 OF 2 B-4 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11448-CBM-071B 1 OF 2 B-7 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP CHECK VALVE 11448-CBM-071B 1 OF 2 D-7 CHECK VALVE CIRCULATING WATER TO DISCHARGE TUNNEL CHECK VALVE 11448-CBM-071A 3 OF 4 E-8 MAN GATE 2.000 3 2.000 3 2.000 NC 2.000 2 CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 11448-CBM-071A 3 OF 4 E-8 MAN GATE CONTAINMENT ISOLATION VALVE FOR SERVICE WATER DRAINS TO HEAT EXCHANGER 11448-CBM-071A 3 OF 4 C-8 CHECK VALVE 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-CBM-071A 3 OF 4 D-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071A 3 OF 4 C-6 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-071A 3 OF 4 D-S CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071A 3 OF 4 C-S CHECK VALVE 2.000 2 3.000 NC 3.000 3 3.000 NC 3.000 3 3.000 NC 3.000 3 3.000 NC C CV C CV C CV AE CIV LT AE CIV LT C CV C CV C CV C CV C CV C CV C CV PAGE: 61 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-C 0 C 0 0 C C 0 0 0 0 0 0 0 so so so

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SW-253 1-SW-262 1-SW-263 1-SW-264 1-SW-265 1-SW-268 RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER RETURN VENT VALVE 11448-CBM-071A 3 OF 4 D-4 CHECK VALVE RECIRCULATION SPRAY HEAT EXCHANGER SERVICE WATER SUPPLY VENT VALVE 11448-CBM-071B 1 OF 2 B-4 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE 11448-CBM-071D 1 OF 1 C-7 AO GATE CONTROL ROOM CONDENSER WATER SELF CLEANING STRAINER ISOLATION VALVE 11448-CBM-071D 1 OF 1 C-5 MANUAL BFLY CONTROL ROOM CONDENSER WATER TO BACKUP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-071D 1 OF 1 C-7 MANUAL BFLY CONTROL ROOM CONDENSER WATER TO BACKUP STRAINER BYPASS LINE ISOLATION VALVE 11448-CBM-071B 1 OF 2 B-6 CHECK VALVE CHARGING PUMP SERVICE WATER PUMP DISCHARGE CHECK VALVE ---------------------------------------------*

1-SW-313 1-SW-323 11448-CBM-071D 1 OF 1 F-7 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 11448-CBM-071D 1 OF 1 F-5 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 1-SW-MOV-101A 11448-CBM-071A 3 OF 4 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 1-SW-MOV-101B 11448-CBM-071A 3 OF 4 B-4 MO BFLY BEARING COOLING WATER HEAT EXCHANGER ISOLATION VALVE 1-SW-MOV-102A 11448-CBM-071A 2 OF 4 D-6 MO BFLY 3.000 3 C 2.000 3 C 6.000 3 E 6.000 3 B 6.000 3 B 2.000 3 C 3.000 3 C 3.000 3 C 36.000 3 B 36.000 3 B 42.000 3 B CV CV VP EV EV CV CV CV EV ST VP EV ST VP EV ST PAGE: 62 OF*70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0 oc 0 0 0 0 0 C C oc C C oc C 0 C 50 50 46 46

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAYING NUMBER SHEET DRIIG VALVE NUMBER COOR TYPE VALVE ASHE IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SII-MOV-102A 11448-CBM-071A 2 OF 4 D-6 MO BFLY SERVICE IIATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SII-MOV-102B 11448-CBM-071A 2 OF 4 D-5 *Mo BFLY SERVICE IIATER HEADER SUPPLY ISOLATION TO COMPONENT COOLING HEAT EXCHANGERS 1-SW-MOV-103A 11448-CBM-071A 3 OF 4 B-8 MO BFLY SERVICE IIATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SW-MOV-103B 11448-CBM-071A 3 OF 4 B-8 MO BFLY SERVICE IIATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 42.000 3 B 42.000 3 B 30.000 3 B 30.000 3 B 1-SW-MOV-103C 11448-CBM-071A 3 OF 4 B-3 MO BFLY 30.000 3 B SERVICE IIATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SII-MOV-103D 11448-CBM-071A 3 OF 4 B-2 MO BFLY SERVICE IIATER HEADER SUPPLY ISOLATION TO RECIRC SPRAY HEAT EXCHANGERS 1-SII-MOV-104A 11448-CBM-071A 3 OF 4 D-7 MO BFLY 30.000 3 24.000 3 SERVICE IIATER SUPPLY TO 11 A 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-HOV-104B 11448-CBM-071A 3 OF 4 D-6 MO BFLY 24.000 3 SERVICE IIATER SUPPLY TO 11 B 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE B B B 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: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 QC C 0 C 0 oc 0 0 QC 0 0 oc 0 0 oc 0 0 oc C 0 C 0 QC C 0 C 0 oc

  • *
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 1-SW-MOV-104C 11448-CBM-071A 3 OF 4 D-5 MO BFLY 24.000 3 SERVICE WATER SUPPLY TO "C" RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-104D 11448-CBM-071A 3 OF 4 D-4 MO BFLY 24.000 3 B B EV ST VP EV ST PAGE: 64 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN* C 0 C 0 OC C 0 C 0 VP OC SERVICE WATER SUPPLY TO 11 0 11 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 11 A 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-105B 11448-CBM-071A 3 OF 4 D-7 MO BFLY SERVICE WATER RETURN FROM 11 8 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-105C 11448-CBM-071A 3 OF 4 D-6 MO BFLY SERVICE WATER RETURN FROM 11 C 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-MOV-105D 11448-CBM-071A 3 OF 4 D-5 MO BFLY SERVICE WATER RETURN FROM 11 0 11 RECIRC SPRAY HEAT EXCHANGER, OUTSIDE CONT ISOLATION VALVE 1-SW-PCV-100A 11448-CBM-071D 1 OF 1 F-7 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 24.000 3 24.000 3 24.000 3 24.000 3 3.000 3 B B B B B EV ST VP EV ST VP EV ST VP EV ST VP EV FS ST C 0 C 0 QC C 0 C 0 OC C 0 C 0 OC C 0 C 0 oc 0 0 0 47

  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE VALVE NUMBER DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 1-SW-PCV-100B 11448-CBM-071D 1 OF 1 F-5 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-100C 11448-CBM-071D 1 OF 1 F-3 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-101A 11448-CBM-071D 1 OF 1 E-8 AO GATE CONTROL ROOM CONDENSER WAjER SYSTEM PRESSURE CONTROL VALVE 1-SW-PCV-101B 11448-CBM-071D 1 OF 1 E-6 AO GATE 1-SW-PCV-101C CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE 11448-CBM-071D 1 OF 1 E-4 AO GATE CONTROL ROOM CONDENSER WATER SYSTEM PRESSURE CONTROL VALVE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 3_000 3 B 3_000 3 B 3_000 3 B 3.000 3 B 3.000 3 B EV FS ST EV FS ST EV FS ST EV FS ST EV FS ST PAGE: 65 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST *REQ JUST JUST TEST POS V-CSV-RRV-VCN-0 0 0 0 0 0 C C C C C C C C C 47 47 47 47 ---47 ------------------------. , 1-SW*TCV-1G8A

.*.-1144~-CBM-0718 1 OF ... ?. E-7 AO .GATE . 1.500 3 B EV .. 0.

  • SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1-SW-TCV-1088 11448-CBM-071B 1 OF 2 E-5 AO GATE SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 1.500 3 B ---------------------------------------------------------*---

1-SW-TCV-108C 11448-CBM-071B 1 OF 2 E-4 AO GATE 2-SW-333 SERVICE WATER TO CHARGING PUMP LUBE OIL COOLER TEMPERATURE CONTROL VALVE 11448-CBM-071D 1 OF 1 F-3 CHECK VALVE CONTROL ROOM CONDENSER WATER SYSTEM PUMP DISCHARGE CHECK VALVE 1.500 3 B 3.000 3 C FS 0 ST O 47 EV FS ST . EV FS ST CV 0 0 0 0 0 0 0 47 47 46

  • *
  • VALVE NUMBER 1-VA-001 1-VA-006 VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448*CBM-0S3A 1 OF 3 B-7 MAN GATE VENT LINE FROM PRIMARY VENT POT, OUTSIDE CONTAINMENT ISOLATION VALVE 11448*CBM-083B 3 OF 3 F-2 MAN GATE VENT LINE FROM PRIMARY VENT POT, INSIDE -CONTAINMENT ISOLATION VALVE ISO VALVE ASME IW VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 AE CIV LT 2.000 2 AE CIV LT PAGE: 66 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV* RRV-VCN-C C

  • VALVE NUMBER 1*VG*TV-109A 1*VG-TV-109B
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAYING NUMBER SHEET DRYG VALVE NUMBER COOR TYPE 11448-CBM*083B 1 OF 3 F-7 AO GATE VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, INSIDE CONT ISOL VLV 11448*CBM*083A 1 OF 3 F-7 AO GATE VENT LINE ISOL FROM PRIMARY DRAINS TRANSFER TANK TO GAS STRIPPERS, OUTSIDE CONT ISOL VLV . ISO VALVE ASME IYV VALVE TEST SIZE CLASS CAT TYPE TYPE 2.000 2 2.000 2 A CIV EV FS LT ST VP A CIV EV FS LT ST VP PAGE: 67 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV* RRV* VCN* C C C C oc C C C C oc

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  • VALVE NUMBER 1-VP-012 DRAWING NUMBER VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE SHEET DRWG VALVE NUMBER COOR TYPE ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-CBM-066A 2 OF 3 F-4 CHECK VALVE 6.000 2 AC CIV CV LT CONDENSER AIR REMOVAL DISCHARG TO CONTAINMENT INSIDE CONTAIN ISOLATION CHECK VALVE PAGE: 68 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V* CSV-RRV* VCN-C C 6

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  • VALVE NUMBER 1-VS-285 1-VS-286 1-VS-288 1-VS-292 1-VS-296 VIRGINIA POIJER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE ISO DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE VALVE ASME JWV VALVE TEST SIZE CLASS CAT TYPE TYPE 11448-FB -041A 2 OF 2 C-6 MANUAL GATE CONTROL ROOM CHILLED WATER CROSS TIE ISOLATION VALVE 11448-FB -041A 2 OF 2 C-5 MANUAL GATE CONTROL ROOM CHILLED WATER CROSS TIE ISOLATION VALVE 11448-FB -041A 2 OF 2 B-7 CHECK VALVE CONTROL ROOM CHILLED WATER PUMP DISCHARGE CHECK VALVE 11448-FB -041A 2 OF 2 B-5 CHECK VALVE CONTROL ROOM CHILLED WATER PUMP DISCHARGE CHECK VALVE 11448-FB -041A 2 OF 2 B-4 CHECK VALVE CONTROL ROOM CHILLED WATER PUMP DISCHARGE CHECK VALVE 3.000 3 B EV 3.000 3 B EV 2.000 3 C CV 2.000 3 C CV 2.000 3 C CV 1-VS-MOV-100A 11448-CBB-006A 1 OF 2 C-4 MO BFLY 36.000 2 AE CIV LT VP CONTAINMENT PURGE SUPPLY, INSIDE CONTAINMENT ISOLATION VALVE 1-VS-MOV-100B 11448-CBB-006A 1 OF 2 C-3 MO BFLY 36.000 2 CONTAINMENT PURGE SUPPLY, OUTSIDE CONTAINMENT ISOLATION VALVE 1-VS-MOV-100C 11448-CBB-006A 1 OF 2 D-4 MO BFLY 36.000 2 CONTAINMENT PURGE EXHAUST, INSIDE CONTAINMENT ISOLATION VALVE 1-VS-MOV-100D 11448-CBB-006A 1 OF 2 D-3 MO BFLY 36.000 2 1-VS-MOV-101 1-VS-MOV-102 CONTAINMENT PURGE EXHAUST, OUTSIDE MENT ISOLATION VALVE 11448-CBB-006A 1 OF 2 D-3 MO BFLY CONTAINMENT PURGE BYPASS, OUTSIDE CONTAINMENT ISOLATION VALVE 8.000 2 11448-CBB-006A 1 OF 2 C-3 MO BFLY 18.000 2 AE CIV LT VP AE CIV LT VP AE CIV LT VP AE CIV LT VP AE CIV LT PAGE: 69 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN* C 0 C 0 C 0 C 0 C 0 C oc C oc C oc C oc C oc C J

  • VALVE NUMBER 1-VS*MOV-1.02
  • VIRGINIA POWER COMPANY SURRY UNIT 1 THIRD INSERVICE TESTING INTERVAL INSERVICE TESTING PROGRAM -VALVE TABLE DRAWING NUMBER SHEET DRWG VALVE NUMBER COOR TYPE 11448-CBB*006A 1 OF 2 C-3 MO BFLY CONTAINMENT VACUUM BREAKER ISO VALVE ASME IWV VALVE TEST SIZE CLASS CAT TYPE TYPE 18.000 2 AE CIV VP PAGE: 70 OF 70 REVISION:

00 DATE: 11/10/93 NC REL CS RR ALT TEST REQ JUST JUST TEST POS V-CSV-RRV-VCN-OC 4.5 * *

  • S1PVIJRO VALVE TEST PROGRAM RELIEF REQUESTS Relief Requests identify code requirements which are impractical for Surry Unit 1 and provide justification for the requested exception.

Where appropriate, alternate testing to be performed in lieu of code requirements is proposed

  • 4-7 ,! Revision O November 10, 1993
  • *
  • *
  • RELIEF REQUEST V-5 system Feedwater Valve(s):

1-FW-10 1-FW-41 l-FW-72 Category:

c Class 2 Function:

Main Feedwater check valves at Containment Penetrations.

OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.J.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage. Basis For Request Closure of these valves during power operation would require securing feedwater which would result in reactor trip. Cold shutdown testing of valves using flow to verify closure is -inconclusive due to the inability to establish adequate differential pressure across the valve disc. A test was -conduc:ted*ir1 an*effort to verily whe'Lher closure of these valves can be determined using flow. Because there is no isolation boundary between the steam generators and the valves, the test volume must include the steam generators.

A steam generator was pressurized with a nitrogen blanket to approximately 5 psig. The 0.75 inch drain valve just upstream of the check valve was opened and flow was observed.

The 14 inch check *valve did not stop the back flow through the vent. It was concluded that the flow was inadequate to seat the check valve completely.

Just a small gap between the disc and the seat was sufficient to create a flow area equal to or greater than the flow area through the drain. Therefore, the pressure differential associated with the back flow is being created across the drain valve and not the disc of the check valve. The above test proved to be inconclusive because of the inability to establish a sufficient differential pressure across the disc. The only way to increase the differential pressure is to increase the flow area from the test volume. However, this is not achievable for the existing configuration.

Immediately upstream 4-9 S1PVI3RO Rev;i.~ion O November 10, 1993

  • *
  • RELIEF REQUEST V-5 (Cont.) of the drain valve is another 14 inch check valve, so the only available flow area from the test volume is the drain valve. Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled every reactor refueling.

A different valve will be disassembled every reactor refueling.

This test frequency is in accordance with Generic Letter 89-04, Position 2 . 4-10 S1PVI3RO Revision o November 10, 1993

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  • *
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  • RELIEF REQUEST V-20 *system Safety Injection Valve(s):

1-SI-47 1-SI-56 Category:

C Class : 2 Function:

Low Head Safety Injection Pump Suction from Containment Sump Check Valve OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4(c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage. Basis For Request To partial or full flow test these valves requires taking suction from the reactor containment sump which contains untreated water

  • This water should not be introduced into the system. Alternate Testing Proposed These valves will be grouped together and one valve from this
  • gr0U!:>' will .. be' disasst:!illJJled

'emu. i:t1::1pecteu every reactor**

refueling*~

.. A different valve will be disassembled every reactor refueling.

This test frequency is in accordance with Generic Letter 89-04, Position 2 . 4-13 S1PVI3RO Rev4"~ion o November 10, 1993

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

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

C Class : 1 1-SI-109 1-SI-130 1-SI-147 Function:

Accumulator Discharge Check OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.4(a)

-This section states in part that, "The necessary valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its function, as specified in para. 1.1, or both. Observation.may be by observing a direct indicator such as a position indicating device, or by other indicator(s) such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means." This section implies that the techniques used to verify obturator movement be applied to every valve on a test frequency that is practical.

Basis For Request Non-intrusive techniques are used to verify obturator movement for the SI accumulator discharge check valves. These techniques provide a "positive means" for verifying obturator movement, however, due to the burden of applying these techniques in the field, a sampling program will be used as described below. Alternate Testing Proposed During the first refueling outage where non-intrusive techniques are used, all valves in the group wiil be tested to verify that the techniques verify valve obturator movement.

During subsequent refueling outages, flow testing will be performed on all valves in the group, but the non-intrusive techniques need be applied only to one valve in each group, on a rotating basis, unless indications of problems are identified.

In this case, all valves in the group will be subjected to the non-intrusive techniques.

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

  • 4-15 SlPVIJRO Revision O Noveinber 10, 1993
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  • RELIEF REQUEST V-26 (Cont.) 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 l-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 4-16 S1PVI3RO Rev~ion o November 10, 1993
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  • RELIEF REQUEST V-27 system Safety Injection Valve(s):

1-SI-88 1-SI-91 1-SI-94 category:

c Class : 1 1-SI-238 1-SI-239 1-SI-240 Function:

Safety Injection to RCS Hot Legs Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Section 4.3.2.2 -Each check valve shall be exercised.

Basis For Request Individual valve closure cannot be verified for valves 1-SI-88, 91, 94, 238, 239 and 240. There are no drains between the valve pairs 1-SI-88 and l-SI-238, 1-SI-91 and 1-SI-239, and 1-SI-94 and 1-SI-240 . Alternate Testing Proposed A leakage test will be performed on each of the three pairs of va.lves and the leakage of each pair will be compared to a limit. *-* If the *1eakage li111ic is exceeded, both valves in the pair will be** subject to inspection, repair or replacement.

Note that there is no specified permissible accident leakage limit for these valves. Therefore, these valves are category c

  • 4-17 S1PVI3RO Rev,4;ion O November 10, 1993

by .Non,~cnne JlJ:ternative Testing VNC-4

  • SlPVIJRO 4-18 Revision o November 10, 1993
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  • S1PVI3RO RELIEF REQUEST V-37 Replaced by Non-Code Alternative Testing VNC-3 RELIEF REQUEST V-38 Relief Request Withdrawn RELIEF REQUEST V-39 Relief Request Withdrawn INTERIM RELIEF REQUEST V-40 Relief Request Withdrawn 4-19 Rev~ion o November 10, 1993
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  • System Valve{s) . . Category . . Class . . Function . . FW 1-FW-144 1-FW-148 C 3 RELIEF REQUEST V-41 1-FW-159 1-FW-163 1-FW-174 1-FW-178 Auxiliary Feedwater Pump Recirc Line and Pump Oil Cooler Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4{c}

reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage. Basis For Relief These check valves cannot be partial or full flow tested because instrumentation is not installed to measure flow or differential pressure.

There is no other indirect means to verify full flow for these valves with the current configuration.

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

To allow for flexibility in planning for refueling out.ages*

and ii:ii.:ill mee,>the ini.:ent

  • of OM Part* 10*, the valves will' *, be disassembled on a reactor refueling frequency but not necessarily during refueling outages. Alternate Testing Proposed Valves 1-FW-144, 159, and 174 will be grouped together; valves 1-FW-148, 163, and 178 will be grouped together and one valve from each group will be disassembled and inspected on a reactor j refueling frequency.

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

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

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

  • 4-20 S1PVI3RO Rev~ion O November 10, 1993
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  • RELIEF REQUEST V-42 System : MS Valve(s} : 1-MS-176 1-MS-178 1-MS-182 Category:

C Class : 2 Function:

Main Steam Header Supply Check Valves To Turbine Driven Auxiliary Feedwater Pump OM Part 10 Code Requirements For Which Relief Is Reguested OM Part 10, Paragraph 4.3.2.4(c}

reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage. Basis For Relief These check valves cannot be back seat tested with flow during normal operation because this test would require the venting of process steam while verifying the closed position.

Venting of process steam would endanger the test personnel.

However, these check valves can be isolated and disassembled while the plant is operating.

To allow for flexibility in planning for refueling outages and still meet the intent of OM Part 10, the valves will be disassembled on a reactor refueling frequency but not necessarily during refueling outages. Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected on a reactor refueling frequency.

A different valve will be disassembled for each , inspection.

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

This test frequency is in accordance with Generic Letter 89-04, Position 2. The valves will be full flow tested every three months

  • 4-21 S1PVI3RO Revision O November 10, 1993 I L * *

1-CS-105 1-CS-13 1-RS-11 1-CS-127 1-CS-24 1-RS-17 Category:

AC (1-CS-13,24 and 1-RS-11,17) and C(l-CS-105,127)

Class : 2 Function:

Containment Spray 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 Relief These check valves cannot be partial or full flow exercised during normal operation because this test would introduce containment spray to containment.

These valves cannot be locally exercised during normal operation because they are located inside containment.

These valves are located upstream of the spray nozzles. For valves l-CS-13 and 24, ~nd l-RS-11 and 17, the only way to perio:e.ill a *test* (partial open* or* closed) is to install a blank '", .. ,. flange downstream and locally perform an partial open and close test using air. The small increase in safety gained by performing this test every cold shutdown does not justify the burden of installing the blank flange and locally back seat testing the valves at the increased cold shutdown test frequency.

There are no blank flanges installed downstream for valves 1-cs-105 and 127. Therefore, a back seat test or a partial open test cannot be performed on these valves with the current piping configuration.

These valves have no external lever arms. The only means to exercise valves 1-CS-105 and 127 to the open and closed positions is by disassembly

  • 4-22 S1PVI3RO Revi~;ion O November 10, 1993
  • *
  • RELIEF REQUEST V-43 (Cont.) Valves 1-CS-13 and 24, and 1-RS-11 and 17 do have weight-loaded lever arms, however, the weight position and lever arm angle are subject to adjustment to ensure that the valves open when a pressure differential using air is applied every 18 months as required by T. s. 4.5.C. Therefore, torque measurements would not be repeatable.

Alternate Testing Proposed For testing to the open and closed positions, valves 1-cs-105 and 127 will be grouped together and one valve from the group will be disassembled and inspected every reactor refueling.

A different valve will be disassembled every reactor refueling.

A partial open test cannot be performed on valves 1-CS-105 and 127 with the current piping configuration.

This test frequency is in accordance with Generic Letter 89-04, Position 2. For testing to the full open position; valves 1-CS-13 and 24 will be grouped together; and valves i-RS-11 and 17 will be grouped together and one valve from each group will be disassembled and inspected every reactor refueling.

A different valve from each group will be disassembled every reactor refueling.

This test frequency is in accordance with Generic Letter 89-04, Position 2 . Technical Specifications Paragraph 4.5.C. requires verification that valves 1-CS-13 and 24, and 1-RS-11 and 17 open when the discharge line of the pump is pressurized with air and seat when a vacuum is applied. This test partially strokes the valves open. Valves 1-cs-11 and 24, and l-Rs-11 and 17 are containment

  • isolation valves a.all* are tested to the closed position each *,,-.
  • refueling outage as part of the Appendix J leak testing program . 4-23 S1PVI3RO Revi~ion o November 10, 1993 L __
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  • S1PVI3RO RELIEF REQUEST V-44 Replaced by Reactor Refueling Justification RRV-6 RELIEF REQUEST V-45 Replaced by Reactor Refueling Justification RRV-7 4-24 Revision o November 10, 1993
  • *

1-SW-313 1-SW-323 2-SW-333 Category:

c Class : 3 Function:

Service Water Supply to Main Control Room Air Conditioning System Chillers OM Part 10 Code Requirements For Which Interim 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 Interim Relief These check valves cannot be full flow tested because instrumentation is not installed to directly measure flow or differential pressure across the valve. According to Technical Specification Paragraph 3.23.C.1.b, "If one chiller becomes inoperable, return the inoperable chiller to operable status within seven (7) days or bring both units to Hot Shutdown within the next six (6) hours and be in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />." Because the main control and emergency switchgear room emergency ventilation system is common for both units, the above action statement applies whenever Unit 1 or Unit 2 is operating.

Given the scope of the required instrumentation modifications and the existing system configuration, it is estimated that installation of the appropriate flow and pressure instrumentation cannot be completed within the Technical Specification 7 day action statement.

Two additional Main Control Room and Emergency Switchgear Room Air Conditioning System chillers are scheduled for installation by the end of 1993. The additional chillers will eliminate the need for entry into the Technical Specification action statement to install the instrumentation.

Also, the flow elements for the chiller service water pumps cannot be installed at power. Therefore, installation of the additional instrumentation is scheduled to be completed by the end of the Unit 1 Cycle 12 refueling outage currently scheduled 4-25 S1PVI3RO Revision o November 10, 1993

  • *
  • INTERIM RELIEF REQUEST V-46 (Cont.) for second quarter of 1994. 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. Interim Alternate Testing Proposed These valves will be grouped together and one valve from this group will be disassembled and inspected on a reactor refueling frequency.

A different valve will be disassembled for each inspection.

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

They will be part stroked open once every three months with flow. This test frequency is in accordance with Generic Letter 89-04, Position 2. When flow instrumentation is installed in the second quarter of 1994, flow will be measured directly and the valves will be full flow tested once every three months

  • 4-26 S1PVI3RO Revision o November 10, 1993
  • *
  • RELIEF REQUEST V-47 System Various Valve(s):

Valves affected by this relief request are identified Category:

Class Function:

by Table V-47. OM Part 10 Code Requirements For Which Relief Is Requested Paragraph 1.3, definition of full-stroke time -the time interval from initiation of the actuating signal to the indication of the end of the operating stroke. Paragraph 4.2.1.9(b) which states in part that "Valves with measured stroke times which do not meet the acceptance criteria of para. 4.2.1.8 shall be immediately retested or declared inoperable." Paragraph 4.2.1.8 presents acceptance criteria of +/-25% for power-operated valves with reference stroke times greater than 10 seconds (4.2.1.S(b))

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

Basis For Relief The valvP.s listed in Table V-47 either have no remote indication and no remote co:ntrol i or ua remo*ce open/ close control, or the test requires that the power source be interrupted at the valve and not at the switch. Also, these valves typically exhibit stroke time data scatter from test to test that can exceed the 25% and 50% required by Paragraphs 4.2.1.S(b) and (d). Therefore, timing the full-stroke from the initiation of the actuating signal and applying the acceptance criteria of Paragraphs 4.2.1.S(b) and (d) are not practical.

Valve 1-CC-LCV-101 maintains the water level in the seal cooling water tank for component cooling to charging pump cooling system. This valve has no remote indication or manual position switch. The valve is exercised by manipulating the tank level signal and isolating the power source, and timed by locally observing stem movement.

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

The position of valves 1-MS-RV-lOlA, Band c is controlled by a potentiometer.

Although the valves have remote position 4-27 S1PVI3RO Revision o November 10, 1993

  • *
  • RELIEF REQUEST V-47 (Cont.) indication, there is no open/closed switch. The speed at which the valve goes open or closed depends upon the speed at which the operator turns the potentiometer knob, which in turn affects the repeatability of the stroke time measurements.

Valves l-RH-FCV-1605 and l-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, Band C, and 1-SW-PCV-lOlA, Band C have no remote indication or manual remote control. The valve position is manipulated by venting the actuator diaphragm and the stroke time is measured by observing the movement of the local position indicator.

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

Valves 1-SW-TCV-lOSA, Band C control the flow of service water to the charging pump lube oil coolers. There is no remote indication or manual position switch. Valve position is controlled by lube oil temperature.

The valves are locally manipulated by isolating the power source, and timed by observing stem movement.

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

Alternate

'l'esting "Proposed The full-stroke will be measured by locally observing stem movement and not from the initiation of the actuating signal. Also, maximum stroke times will be established in accordance with Paragraph 4.2.l.9(a).

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

  • 4-28 S1PVI3RO Rev4don O November 10, 1993
  • RELIEF REQUEST V-47 (Cont.) TABLE V-47 Valve Category Class Function *
  • l-CC-LCV-101 1-MS-RV-101A,B,C 1-RH-FCV-1605 1-RH-HCV-1758

~-SW-PCV-lOOA,B,C 1-SW-PCV-101A,B,C 1-SW-TCV-lOSA,B,C S1PVI3RO B 3 B B 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 RHR 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 November 10, 1993

  • *
  • S1PVI3RO INTERIM RELIEF REQUEST V-48 Replaced by Cold Shutdown Justification CVS-32 RELIEF REQUEST V-49 Relief Request Withdrawn 4-30 Revision O November 10, 1993
  • *

1-SW-108 1-SW-113 1-SW-130 category:

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

NC (1-SW-130)

Function:

Charging Pump Service Water Pump discharge Check Valves OM Part 10 Code Requirements For Which Relief Is Requested OM Part 10, Paragraph 4.3.2.4{c) reads in part that, "disassembly every refueling outage to verify operability of check valves may be used." This sentence implies that each valve in the group given above must be disassembled every refueling outage. Basis For Request The design basis for the charging pump service water system is currently undergoing reevaluation.

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

These 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 l-SW-108, 113 and 130 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 Rev4;ion O November 10, 1993

  • *
  • RELIEF REQUEST V-51 system Various Valve(s):

All Containment Isolation Valves Subject to Appendix J Testing -These valves are identified by the abbreviation "CIV" under the Isolation Valve Type Column in the Valve Table. Category:

A and AC Class . . Function:

Provide Containment Isolation OM Part 10 Code Requirements For Which Relief Is Reguested 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 Reguest Permissible valve leakage rates are based on each valve's possible contribution to the total leakage rate for the containment system. The total containment leakage rate must be less than 0.6La as defined in Technical Specification 4.4.C. Exceeding an individual valve's permissible leakage rate may have no affect on the containment's ability to maintain an overall leakage rate less than 0.6LA. Also, there may be plant conditions, or schedule constraints, that preclude repair or replacement of a valve when the individual leakage limit is exceeded, but the overall leakage limits for the Type c-tested valves is met. In these cases, imposing the Code requirements of repair or replacement would create an undue burden with no compensating benefit to quality and safety when the bases for leakage limits is met for the overall limit necessary to ensure containment integrity.

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

However, when the plant conditions are 4-32 S1PVI3RO Revi~ion o November 10, 1993

  • *
  • RELIEF REQUEST V-51 (Cont.) not such that a repair or replacement would adversely impact plant startup and/or continued operations, an evaluation is not appropriate
  • 4-33 S1PVI3RO Revision o November 10, 1993 4.6 * *
  • S1PVI3RO VALVE TEST PROGRAM COLD SHUTDOWN JUSTIFICATIONS OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during Cold Shutdown (but not more frequently than every three months) if the valves cannot be exercised during normal operation.

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

However, OM Part 10, Section 6.2 does require that these valves be specifically identified by the owner. The cold shutdown justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation

  • 4-34 Revi_sion o Nov~inber 10, 1993
  • *

1-MS-TV-lOlA 1-MS-TV-lOlB 1-MS-TV-lOlC category:

B Class : 2 Function:

Main Steam Line Trip Valves Cold Shutdown Justification Full stroke or part stroke exercising of these valves during power operation could result in a turbine and reactor trip. Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months. Note: The technical specification acceptance criteria are more limiting than the standard Section XI test criteria because the technical specification requires the measurement of elapsed time from the manual initiation of steam line isolation to initiation of main trip valve motion (must be less than or equal to 4.0 seconds) and the measurement of elapsed time from full open to full closed (must be less ** than or equal to 5. O *seconds)

..... If either of the* limiting ... ",.~. times are exceeded, the valve fails the test.Section XI requires the measurement of elapsed time from initiation of steam line isolation to full valve closure, which is a less conservative test

  • 4-35 S1PVI3RO Rev,!..sion O November 10, 1993
  • *
  • *
  • system Valve(s):

category:

Class Function:

COLD SHUTDOWN JUSTIFICATION CSV-4 Auxiliary Feedwater Valves affected by this justification are identified by Table CSV-4. Cold Shutdown Justification Except for valves 1-FW-142, 157 and 172, partial or full opening the valves in Table CSV-4 during power operation would introduce cold auxiliary feedwater to the steam generators resulting in thermal stress and possible steam generator tube degradation.

Valves 1-FW-142, 157 and 172 can be full stroke tested every three months. To test valves 1-FW-142, 157 and 172 to the closed position, flow must be established to the steam generators in order to back seat the valves on the discharge side of the non-running pumps. This test would also introduce cold auxiliary feedwater to the steam generators if performed during normal operation.

Testing Frequency Except for valves 1-FW-142, 157 and 172, the valves in Table csv-4 will be full stroke exe:ri;;ised every cold shutdown but not more_. frequently than once every three months. Valves 1-FW-142, 157 and 172 will be full stroke tested once every three months and tested in the closed position every cold shutdown but not more frequently than once every three months

  • 4-37 SlPVIJRO Rev.:j..sion O November 10, 1993
  • *
  • *
  • System Valve(s):

Category:

Class . . Function:

COLD SHUTDOWN JUSTIFICATION CSV-5 Component Cooling Valves affected by this justification are identified by Table CSV-5 Cold Shutdown Justification These valves are located in the containment and may be normally open or closed depending on system lineup. A containment entry and manipulation of other system valves are necessary to test these valves to either the open or closed position.

This is considered impractical during power operation.

Testing Frequency The valves in Table CSV-5 will be tested in the closed position every cold shutdown but not more frequently than once every three months. Valves 1-CC-176 and 177 will be full stroke exercised every cold shutdown but not more frequently than once every three months. Valve 1-CC-176 1-CC-177 l-CC-242 1-CC-233 l-CC-224 . ****TABLE CSV-5 Category C C Class Function 3 Component Cooling to RHR Heat Exchanger Check Valves 3 Component Cooling to Reactor Containment Air Recirculation Coolers 4-39 S1PVI3RO Rev!.sion O November 10, 1993

  • *

Valves affected by this justification are identified category:

Class Function:

by Table CSV-6. Cold Shutdown Justification To perform an operability or a fail-safe test, the component cooling lines must be isolated, thereby stopping the flow of cooling water to the Reactor coolant Pumps. Loss of cooling water to these pumps can be damaging, even for short periods of time. Testing Frequency The valves in Table CSV-6 will be tested in the closed position every cold shutdown when the reactor coolant pumps are secured but not more frequently than once every three months

  • Valve 1-cc-1 1-CC-58 1-CC-59 1-CC-TV-lOSA 1-CC-TV-lOSB 1-CC-TV-lOSC TABLE CSV-6 Category C B Class Function 3 Component Cooling to Reactor ~oolant Pumps 3 Component Cooling from Reactor Coolant Pumps 4-40 S1PVI3RO Revi_sion o November 10, 1993
  • *

1-RC-PCV-1456 1-RC-PCV-1455C Category:

BC Class : 1 Function:

Pressurizer Power Operated Relief Valves Cold Shutdown Justification These pressurizer power operated relief valves have shown a high probability of sticking open while being exercised during power operation

  • . Also, these valves are not required for overpressure protection unless the primary system temperature is under 350 °F per Technical Specification Paragraph 3.1.G.l.b{3).

Testing Frequency These valves will be tested on approach to Cold Shutdown and testing shall not be deferred . 4-41 S1PVI3RO Revi.sion o November 10, 1993

  • *

1-RH-S 1-RH-11 Category:

C Class 2 Function:

RHR Pump Discharge Check Valve Cold Shutdown Justification These valves can only be partial or full stroke exercised to the open position and verified closed during the testing of RHR pumps 1-RH-P-lA and lB (refer to Relief Request P-7). The low pressure pumps take suction from and discharge to the reactor coolant system which operates at 2235 psig. This pressure is well above the operating pressure of the pumps; therefore, testing during normal operation is not possible.

Testing Frequency These valves will be tested to the full open position and the closed position during the testing of the RHR pumps (refer to Relief Request P-7) . 4-42 S1PVI3RO Revision o November 10, 1993

  • *

1-RH-MOV-1700 1-RH-MOV-1701 Category:

B Class : 1 Function:

RHR suction form Reactor Coolant System Cold Shutdown Justification These valves are interlocked with Reactor Coolant System pressure such that the valves cannot be opened at elevated reactor coolant system pressure.

overpressurization of the suction line may cause a LOCA. The interlocks cannot be bypassed with normal control circuits.

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

  • 4-43 S1PVI3RO Revipion o November 10, 1993
  • *

1-RH-MOV-1720A 1-RH-MOV-1720B category:

B Class : 1 Function:

RHR Discharge to Reactor Coolant System Cold Shutdown Justification With the MOV shut and if its respective check valve is leaking, there is no way to determine whether or not an overpressure condition exists before opening the MOV. If the MOV was opened and an overpressure condition did exist between the MOV and the RCS, the primary pressure of 2235 psig will be released on the Residual Heat Removal system with a relief valve setting of 600 psig. This would be an unnecessary challenge to the Residual Heat Removal System. Since the MOV is also part of the discharge piping of an accumulator, there is a possibility of discharging an accumulator into the RHR system and disabling it. The accumulators are maintained at pressure above the normal operating or shutdown pressure of the Residual Heat Removal System. Opening of these valves would dump accum11lator water into the Residual Heat Removal system. This will dilute the boron concentration of*the* accumulator as well as lower its level and pressure, which is a violation of Technical Specifications.

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

  • 4-44 S1PVI3RO Revi~ion O November 10, 1993
  • *

1-CH-LCV-lllSC 1-CH-LCV-lllSE Category:

B Class : 2 Function:

Charging Pump Suction from Volume Control Tanks Cold Shutdown Justification Partial or full stroke exercising these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in Reactor Coolant System boron inventory, which would cause a plant transient.

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

  • 4-45 S1PVI3RO Rev.j.sion o November 10, 1993
  • *
  • *

1-CH-MOV-1381 category:

A Class : 2 Function:

Reactor Coolant Pump Seal Water Return Cold Shutdown Justification:

Closure of this valve with Reactor Coolant Pumps in operation will cause a loss of seal flow resulting in possible pump seal damage. Testing Frequency This valve will be tested to the closed position every cold shutdown when the reactor coolant pumps are secured but not more frequently than once every three months . 4-47 S1PVI3RO Revision o November 10, 1993

  • * * **System Valve(s):

Category:

Class Function:

COLD SHUTDOWN JUSTIFICATION CSV-14 Residual Heat Removal 1-RH-FCV-1605 1-RH-HCV-1758 B 2 Residual Heat Removal Exchanger flow control Cold Shutdown Justification These valves have no remote position indication and are located inside containment.

The valves can only be exercised (partial or full stroke) and timed by locally observing stem movement.

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

Testing Frequency Valve 1-RH-FCV-1605 will be tested to the closed position, and valve 1-RH-HCV-1758 will be tested to the full open position every cold shutdown but not more frequently than once every three months . 4-48 S1PVI3RO Rev~ion o November 10, 1993

  • *

1-CH-TV-1204A 1-CH-LCV-1460A 1-CH-LCV-1460B Category:

Class Function:

1-CH-TV-1204B A {l-CH-TV-1204A, B) and B {l-CH-LCV-1460A, B) 1 {l-CH-LCV-1460A, B) and 2 {l-CH-TV-1204A, B) Reactor Coolant System Letdown Isolation Trip and Level Control Valves Cold Shutdown Justification Exercisi~g these valves during power operation interrupts letdown flow from the reactor coolant system {RCS) to the volume control tank. If the valves should fail closed, reactor coolant inventory control would be lost. The pressurizer level control program controls reactor coolant inventory by regulating the operation of the charging flow control valve so that the charging input flow to the RCS and reactor coolant pump seal injection flow into the RCS matches letdown flow

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

This flow interruption would allow a slug of relatively cool charging water to thermal shock the nozzle connecting the 3 11 chal."ging line to the 21*1 loop 2 cold leg injection line. The valve controllers do not allow for a part stroke exercise test. Testing Freguency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months . 4-49 SlPVIJRO Revj.sion o November 10, 1993

  • *
  • System Chemical and Volume Control Valve(s):

1-CH-MOV-1289A 1-CH-MOV-1289B Category:

A (1-CH-MOV-1289A) and B (1-CH-MOV-1289B)

Class : 2 Function:

Normal Charging Header Isolation Cold Shutdown Justification Failure of these valves in the closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory.

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

  • 4-50 S1PVI3RO Rev.:j.sion o November 10, 1993
  • *

1-SI-MOV-1890C Category:

A Class 2 Function:

Low Head Safety Injection to Reactor Coolant System Cold Legs Cold Shutdown Justification In accordance with Technical Specification 3.3.A.8, during power operation, the A.C. power shall be removed from 1-SI-MOV-1890C with the valve in the open position.

If this valve was stroked during power operation and failed in the closed position, the Low Head Safety Injection System would be rendered inoperable.

Testing Frequency This valve will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months

  • 4-51 SlPVIJRO Revj..sion o November 10, 1993
  • *

l-SI-MOV-1867C l-SI-MOV-1867D Category:

A Class 2 Function:

High Head Safety Injection Isolation Cold Shutdown Justification These valves cannot be partial or full stroke exercised during power operation.

Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient.

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

  • 4-52 SlPVIJRO Revi~ion O November 10, 1993
  • *

1-CH-225 1-CH-227 1-CH-MOV-1350 l-CH-228 1-CH-229 Category:

B (1-CH-MOV-1350, 1-CH-228) and C (1-CH-225,227,229)

Class : 2 Function:

Emergency and Manual Emergency Boration Line Isolation Valves Cold Shutdown Justification To achieve full flow through Check valves 1-CH-225, 227 and 229, the boric acid transfer pumps must be set at high speed, which could inject enough boric acid into the reactor coolant system to cause a reactor power transient.

Under normal plant operating conditions or when the plant is shutdown, valve 1-CH-MOV-1350 can be full stroke exercised and valves l-CH-225, 227 and 229 can be part stroked exercised with the boric acid transfer pumps set on low speed to minimize the amount of boric acid injected into the reactor coolant system. However, during power operation when the concentration of boric acid in the reactor coolant system is low, the addition of boric acid will produce an undesirable transient in reactor power. Low concentrations of boric acid occur near the end of the fuel cycle. Testing Frequency Valve 1-CH-MOV-1350 will be full stroke exercised and check valves 1-CH-225, 227 and 229 will be full stroked exercised every quarter during normal operation when the reactor coolant boric acid concentration is above 100 ppm. Manual valve 1-CH-228 will be stroked open when the other valves in the alternate boration path are exercised.

The increased level of safety gained be exercising this valve every quarter does not justify the added burden of performing a separate test just for the manual valve

  • 4-53 S1PVI3RO Rev~ion o November 10, 1993
  • *
  • *

1-SD-TV-lOOA 1-SD-TV-lOOS 1-SD-TV-lOOC Category:

S Class : 2 1-SD-TV-lOOD 1-SD-TV-lOOE 1-SD-TV-lOOF Function:

Steam Generator Slowdown Isolation Cold Shutdown Justification Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves reopen, a flow surge could occur which automatically isolates the inner valves due to high flow. Then a containment entry is necessary to reset these valves ~nd upon reopening the process may occur again. Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months

  • 4-55 S1PVI3RO Revision O November 10, 1993 L __
  • *

1-SI-MOV-1842 1-SI-MOV-1869A 1-SI-MOV-1869B Category:

A Class : 2 Function:

High Head Safety Injection to reactor Coolant system Cold Shutdown Justification These valves cannot be partial or full stroke exercised during power operation.

Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient and possible thermal shock to the High Head Safety Injection system. Also, according to Technical Specification 3.3.A.9, A. c. power shall be removed with the valves in the closed position during power operation.

  • Testing Frequency
  • These valves will be tested to the full open and closed positions every cold shutdown but not more frequently than once every three months . 4-57 SlPVIJRO Revision o November 10, 1993 I 11 I * *

1-CC-181 1-CC-185 Category:

B (manual) Class . 3 . Function:

Component Cooling Supply/Return to/from RHR Heat Exchanger Isolation Valves Cold Shutdown Justification A containment entry is required to exercise these manual butterfly valves. Therefore, they will be exercised every cold shutdown.

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

  • 4-58 SlPVIJRO Revµ;ion o November 10, 1993 I ---
  • *

1-CC-TV-120A 1-CC-TV-120B 1-CC-TV-120C Category:

B Class : 3 1-CC-TV-140A 1-CC-TV-140B Function:

Component Cooling Return from Reactor Coolant Pump Thermal Barrier Isolation Valves Cold Shutdown Justification Exercising these valves during normal operation would isolate component cooling water to the reactor coolant pump thermal barriers.

Cooling water must be available to the reactor coolant pump thermal barriers when the reactor coolant system temperature is above 200 °F. Cold shutdown is entered when the reactor coolant system temperature drops below 200 °F. The valve controllers do not allow for a part stroke exercise test . Testing Frequency These valves will be tested to the closed position every cold shutdown but not more frequently than once every three months . 4-59 S1PVI3RO Revision O November 10, 1993

  • *

1-FW-FCV-1478 1-FW-FCV-1488 1-FW-FCV-1498 Category:

B Class : NC 1-FW-FCV-lSSA 1-FW-FCV-155B 1-FW-FCV-lSSC Function:

Main Feedwater Regulating and Regulating Bypass Isolation Valves Cold Shutdown Justification These valves are in positions required to sustain power operation.

Full stroke exercising the valves would result in a reactor trip. The main feedwater regulating valves 1-FW-FCV-1478, 1488 and 1498 move during normal operation as they perform their regulating function.

The bypass valves 1-FW-FCV-lSSA, Band Care used only during plant startup. During this startup period, their safety function is to close. During normal operation, these valves remain closed and, thus are passive in the closed position.

Therefore, the bypass valves do not need to be partial stroke tested every three months. Testing Frequency These valves will be full stroke exercised every cold shutdown but not more frequently than once every three months. The main feedwater regulating valves will be part stroke exercised every three months during the turbine inlet valve movement test

  • 4-60 S1PVIJRO Rev,!.:sion o November 10, 1993
  • *

1-SI-109 1-SI-130 1-SI-147 Category:

C Class : 1 Function:

SI Accumulator Discharge Isolation Check Valve Cold Shutdown Justification These check valves are located inside containment and are back seat tested using the installed sampling system. To ensure that all of the leakage that could pass by the check valves is collected, the accumulator discharge motor operated valves MOV-1865A, Band C) must be closed. However, these motor operated valves must be open and de-energized when the reactor coolant system pressure is above 1000 psig according to Technical Specification Paragraph 3.3.A.10.

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

  • 4-61 S1PVI3RO Revi:Sion O November 10, 1993
  • *

1-CC-805 category:

C Class . 3 . Function:

Charging Pump Seal Cooling Surge Tank Makeup Valve Cold Shutdown Justification This valve must open to provide a flow path from the component cooling water system to the charging pump seal water surge tank as a supply of makeup water to the surge tank. There is no flow instrumentation to verify partial or full flow for the check valve. There is level instrumentation on the surge tank. The surge tank can be isolated, drained down and refilled.

However, the surge tank provides the NPSH for the charging pump cooling water pumps and it should not be isolated from the system during normal operation when component cooling water for the charging pumps is required

  • Testing Frequency This valve will be tested to the full open position every cold shutdown but not more frequently than once every three months
  • 4-62 S1PVI3RO Rev~ion o November 10, 1993
  • *

l-CC-LCV-101 category:

B Class : 3 Function:

Charging Pump Seal Cooling Surge Tank Level Control Valve Cold Shutdown Justification This valve must open to maintain the level in the charging pump seal water surge tank and must close to prevent overflowing the surge tank and potentially draining the surge tank through the over flow line. The valve fails closed on lose of operating air. Valve position is determined solely from tank level. In order to manipulate the valve for testing, the surge tank must be isolated.

However, the surge tank provides the NPSH for the charging pump cooling water pumps and it should not be isolated from the system during normal operation when component cooling water for the charging pumps is required

  • Testing Frequency This valve will be exercise to the open and closed positions every cold shutdown but not more frequently than once every three months
  • 4-63 SlPVI3RO Revision o November 10, 1993
  • *

1-MS-NRV-lOlA 1-MS-NRV-lOlB 1-MS-NRV-lOlC category:

c Class 2 Function:

Main Steam Non-Return Valves Cold Shutdown Justification Valve Description The main steam non-return valves (NRVs) at Surry Power Station are located in the main steam valve house and are a globe type stop check 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-returtt 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 S1PVI3RO Revj_sion o November 10, 1993
  • *

When the RCS temperature is between 350 °F and 195 °F during the cooldown process, the main steam trip valves are closed. Then the main steam non-return valves close in response to the loss of steam flow. After the main steam trip valve is closed, the Valve Operation Test and Evaluation System (VOTES) can be used to determine the position of the disk of the NRV. After the main steam trip valve is closed, the non-return valve stem is run down onto the disk after the disk returns to the seat. A change in the running force within the normal travel of the stem indicates a resistance to stem movement (i.e., a stuck disk). Verifying that the stem travels to the seated disk with nominal changes in the running force indicates that the disk is on the seat. The test requires that the cooldown process be delayed between one to two hours to setup the instrumentation and to perform the test on each of three valves. Virginia Power owns the VOTES equipment and has personnel trained to use the equipment and interpret the results. The VOTES consists of a force sensor permanently mounted on the valve yoke, valve switch current probes and a motor current probe. The force sensor detects the strain experienced by the yoke as the valve stem moves. Strain is converted to force. The valve switch probes determine the status of the torque and limit switches, and the open and closed bypass switches in the motor operator control circuit over the course of stem travel. To attach the switch and motor current probes, the power to the valve must be interrupted.

Testing Frequency Discussion Full stroke or part stroke exercising of these valves during power operation would result in a turbine and reactor trip. Plant cooldown procedures require the trip valve to be closed, and then the NRV stem run down onto the disk to isolate the main steam system. The VOTES testing must be performed when the NRVs are initially closed during the cooldown to accurately assess the piston-disk assembly's as-found position.

As indicated above, the VOTES test will delay the cooldown process from between one to two hours. Some cold shutdown outages are forced outages that result from exceeding a Technical Specification limit such as unidentified RCS leakage. The emphasis in a forced outage cooldown is to reach cold shutdown as rapidly as possible and to mitigate the cause of the forced outage. Stopping this process to perform the VOTES test would complicate the operators task to 4-65 S1PVI3RO Rev~ion O November 10, 1993

  • *
  • COLD SHUTDOWN JUSTIFICATION CSV-32 (Cont.) secure the plant and may reduce plant safety. However, during planned cold shutdowns where there are no mitigating circumstances, there is adequate time to notify the test personnel, carry the equipment into the field and perform the test. There is no evidence in the valve history that a valve has stuck in the partial open position.

The piston-disk assembly is not attached to any other internal part, the 1,200 lb piston-disk assembly is maintained parallel within the valve body cylinder -and the main steam system is very clean. Consequently, there no mechanism to prevent the disk from dropping from the full open position to the valve seat. Testing Frequency The VOTES test describ~d above will be performed on e~ch main steam non-return valve during the cooldown process going into each planned cold shutdown.

This test will not be performed more often then once every three months

  • 4-66 S1PVI3RO Revtsion O November 10, 1993
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1-RC-SOV-100A-1 1-RC-SOV-100A-2 1-RC-SOV-100B-1 1-RC-S0V-100B-2 Category:

B Class : 1 Function:

Head Vent for Reactor Vessel Cold Shutdown Justification These valves isolate the reactor vessel from containment atmosphere.

Partial or full stroke exercising the valves during normal operation or during cold shutdowns where the reactor coolant system is pressurized could result in the release of uncontrolled contamination to containment.

Testing Frequency This valve will be exercise to the open and closed positions during cold shutdowns when the reactor coolant system is not pressurized but not more frequently than once every three months

  • 4-67 SlPVIJRO Rev4;ion o November 10, 1993 4.7 * *
  • SlPVIJRO VALVE TEST PROGRAM REACTOR REFUELING JUSTIFICATIONS OM Part 10, Sections 4.2.1.2 and 4.2.2.2 allow for the full stroke exercising of valves during reactor refueling (but not more frequently than every three months) if the valves cannot be exercised during normal operation or cold shutdown.

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

However, OM Part 10, Section 6.2 does require that these valves be specifically identified by the owner. The reactor refueling justifications identify and provide the technical basis for valves exercised during cold shutdown but not during normal operation

  • 4-68 Revision o November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-1 *System Chemical and Volume control Valve(s):

1-CH-258 1-CH-267 1-CH-276 category:

c Class 2 Function:

Charging Pump Discharge Check Valve Reactor Refueling Justification With present plant design, these valves can only be partial stroke exercised during power operation because the charging pumps cannot achieve design accident flow when pumping into the Reactor Coolant system at operating pressure.

The only available flow path to test these valves is into the reactor coolant system. During cold shutdown, stroke exercising these valves could result in an overpressurization of the Reactor Coolant System and could force a safety system to function.

Testing Frequency These valves will be partially stroked every three months and full flow tested each refueling . 4-69 SlPVIJRO Revi~:don o November 10, 1993

  • *
  • REACTOR REFUELING JUsrIFICATION RRV-2 System Safety Injection Valve(s):

Valves affected by this request are identified in category:

Class Function:

Table RRV-2. Reactor Refueling Justification These valves cannot be full stroke exercised during plant power operation.

The only full flow path is into the Reactor Coolant System and Low Head Safety Injection pumps cannot overcome Reactor coolant System operating pressure.

These valves will be partially stroked every three months through the pump recirculation line. During cold shutdown, the Reactor Coolant system pressure still prevents full flow testing of the check valve. During cold shutdown, the charging flow could cause an overpressurization condition.

Testing valves 1-SI-50 and 58 to the closed position requires isolating the suction lines to the low head safety injection pumps, venting on the upstream side of the valve being tested, starting the pump on the other path, checking for leakage and then repeating the process for the other valve. This test can take up to a hour to complete and places the unit into a LCO per Technical Specification 3.3 if performed during normal operation.

Testing Freguency These valves will be partially stroked every three months and full stroked every refueling.

Valves 1-SI-50 and 58 will be tested to the closed position every cold shutdown . 4-70 S1PVI3RO Revision o November 10, 1993

  • *
  • Valve 1-SI-46A 1-SI-46B 1-SI-50 1-SI-58 S1PVI3RO REACTOR REFUELING JUSTIFICATION RRV-2 (Cont.) TABLE RRV-2 Category C C Class Function 2 Low Head Safety Injection Pwnp Suction from Refueling Water Storage TanJc Check 2 Low Head Safety Injection Pwnp Discharge Check 4-71 Revi.!=-ion o November 10, 1993
  • *
  • REACTOR REFUELING JUSTIFICATION RRV-3 System Safety Injection Valve(s):

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

C Class . . 1 1-SI-109 1-SI-130 1-SI-147 . Function:

Accumulator Discharge Check 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.

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 S1PVI3RO Revi~ion o November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-4 system Safety Injection Valve(s):

Valves affected by this request are identified in category:

Class Function:

Table RRV-4. Reactor Refueling Justification Open Test Discussion The valves on the high head injection paths cannot be partial or full stroke exercised to the open position during power operation because flow through these valves would thermal shock the injection system and cause unnecessary plant transients.

Flow cannot be established in the valves on the low head injection paths during power operation because the low head safety injection pumps do not develop sufficient head to overcome reactor coolant system pressure

  • During cold shutdown, exercising the high head injection path valves with flow could cause a low temperature overpressurization of the reactor coolant system and force a safety system to function.

Because of the large flow rate (3000 gpm) produced by the low head safety injection pumps, exercising the low head injection path valves during cold shutdowns when the reactor head is bolted in place presents the risk of filling the pressuizer and overflowing through a pressure operated relief valve into the pressuizer relief tank. Therefore, it is impractical to exercise the high or the low head injection path valves with flow quarterly or during cold shutdowns.

The valves listed in Table RRV-4 are on the high and/or the low head injection paths. Close Test Discussion for l-SI-79. 82. 85. 241. 242 and 243 To individually verify closure for valves l-SI-79, 82, 85, 241, 242 and 243, the piping must be vented upstream and a backseat test performed.

These valves are located inside the containment and would require a subatmospheric containment entry to perform the backseat test if the reactor is above 200°F

  • 4-73 SlPVI3RO Revision O November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-4 {Cont.) Therefore, it is impractical to perform a closure test every quarter. These valves are designated as pressure isolation valves. Technical Specification Table 4.1-2A requires that periodic leakage testing on each of these valves be accomplished prior to entering power operation condition after each time the plant is placed in the cold shutdown condition for refueling and after each time the plant is placed in cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the proceeding 9 months. According to OM Part 10, Paragraph 4.2.1.2(f), "valves stroke exercised at cold shutdowns shall be exercised during each cold shutdown, except as specified in (g) below. Such exercise is not required if the time period since the previous full-stroke exercise is less than 3 months." Paragraph (g) states that "valve exercising during cold shutdown shall commence within 48 hr of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. For extended outages, testing need not be commenced in 48 hr provided all valves required to be tested during cold shutdown will be tested prior to startup. However, it is not the intent of this Part to keep the plant in cold shutdown to complete cold shutdown testing." However, if that first cold shutdown came more than nine months after the last test, Technical Specifications would require that the test be completed regardless of the delay to plant statup. In this respect, the Technical Specification frequency is more '-:"*'* conservative than the IST Program required frequency.

Also, a leakage test provides a better measure of the condition of the valve seats than does a standard backseat test. When compared to the Code requirements for a backseat test performed every cold shutdown, the combination of the Technical Specification required test frequency and leakage testing is an alternative that provides an acceptable level of quality and safety

  • 4-74 SlPVIJRO Rev:j..sion o November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.) Close Test Discussion for 1-SI-88. 91. 94. 238. 239 and 240 Individual valve closure cannot be verified for valves 1-SI-88, 91, 94, 238, 239 and 240. There are no drains between the valve pairs 1-SI-88 and 1-SI-238, 1-SI-91 and 1-SI-239, and 1-SI-94 and 1-SI-240.

To verify closure for each pair of valves, a subatmospheric containment entry must be made and a backseat test performed if the reactor is above 200°F. Therefore, it is impractical to perform a closure test every quarter. A leakage test will be performed on each of the three pairs of valves. This test will be performed on the same test frequency as the pressure isolation valves discussed above (i.e., per Technical Specification Table 4.1-2A). Note that there is no specified permissible accident leakage limit for these valves. Therefore, these valves are Category c. When compared to a backseat test performed every cold shutdown, the combination of the test frequency described in Technical Specification Table 4.1-2A and leakage testing is.an alternative that provides an acceptable level of quality and safety. Close Test Discussion for 1-SI-235.

236 and 237 To verify closure for valves 1-SI-235, 236 and 237, a subatmospheric containment entry must be made and a backseat test performed if the reactor is above 200°F. Therefore, it is impractical to perform a closure test every quarter. In lieu of performing a backseat test on each of these valves every cold shutdu'\,/U, a leakage test will be performed*

on *each_.,.,,,,,.,.

.. valve and the leakage of each valve will be compared to a limit. This test will be performed on the same test frequency as the pressure isolation valves discussed above (i.e., per Technical Specification Table 4.1-2A). Note that there is no specified permissible accident leakage limit for these valves. Therefore, these valves are Category c. When compared to a backseat test performed every cold shutdown, the combination of the test frequency described in Technical Specification Table 4.1-2A and leakage testing is an alternative that provides an acceptable level of quality and safety

  • 4-75 S1PVI3RO Rev~sion.o November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.) Testing Frequency Testing Frequency To the Open Position There is no installed instrumentation that can measure individual flow rates for valves 1-SI-79, 82, 85, 88, 91, 94, 238, 239, 240, 241, 242 and 243. Clamp on ultrasonic flow instrumentation will be used to verify full flow through the hot leg safety injection valves 1-SI-88, 91, 94, 238, 239 and 240 each reactor refueling.

Using low head pump flow, the cold leg injection valves 1-SI-79, 82, 85, 241, 242 and 243 will be acoustically monitored for the disk striki~g the back seat every reactor refueling.

The data will be analyzed to show that the disk struck the back seat, which verifies that the disk stroked to the full. open position.

The remaining valves l-SI-224, 225, 226, 227, 228, 229, 235, 236 and 237 will be full stroke exercised with flow every reactor refueling.

Testing Frequency To the Closed Position Valves 1-SI-79, 82, 85, 241, 242 and 243 will be tested to the closed position per the requirements of Technical Specification Table 4.1-2A. The valve pairs l-SI-88 and 1-SI-238, and 1-SI-91 and l-SI-239, and 1-SI-94 and 1-SI-240 will be tested for leakage to confirm that the valve pairs provide isolation for the three hot leg injection paths. The leakage tests will be performed at the frequency required by Technical Specification Table 4.1-2A. Individual valve verification to the closed position is not possible with the current line configurations.

Valves 1-SI-235, 236 and 237 will be tested for leakage to confirm that the valves are in the closed position.

The leakage tests will be performed at the frequency required by Technical Specification Table 4.1-2A. The remaining valves 1-SI-224, 225, 226, 227, 228 and 229 need only to open to perform their safety function.

No credit is taken for valves 1-SI-224, 225, 226, 227, 228 and 229 to close because isolation for the safety injection flow paths is provided by the upstream and downstream valves. For each of these valves, there are normally closed motor operated valves located upstream and two check valves in series located downstream.

The upstream and downstream valves are tested for closure

  • 4-76 S1PVI3RO Revµ;ion O November 10, 1993
  • Valve l-SI-88, l-SI-94, l-SI-239, l-SI-235 l-SI-236 l-SI-237 l-SI-241 l-SI-242 l-SI-243 l-SI-224, l-SI-226, i-SI-228,
  • l-SI-79,
  • SlPVI3RO REACTOR REFUELING JUSTIFICATION RRV-4 (Cont.) TABLE RRV-4 Category Class 91 C 1 238 240 C 1 AC 1 225 C 2 227 229 C 2 82, 85 AC 1 4-77 Function Safety Injection to RCS Hot Legs High Head Safety Injection to RCS Cold Legs Low Head Safety Injection to RCS Cold Legs High Head Safety Injection Check Valve at Containment Penetrations Low Head Safety Injection Check Valves at Containment Penetrations Safety Injection to RCS Cold Legs Revision o November 10, 1993
  • *
  • REACTOR REFUELING JUSTIFICATION RRV-5 system RWST Cross Tie Valve(s):

l-SI-25 l-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 b~ established during reactor refueling when the RCS is depressurized.

Valve l-SI-25 must close to preserve inventory from the Unit 2 RWST when the cross tie lines are opened. There are no vents or pressure instrumentation upstream of the valve; therefore, the valve cannot be backseat tested with flow. Testing Frequency These valves will partial flow tested during every cold shutdown and full flow tested during every reactor refueling.

Valve l-SI-25 will be disassembled and inspected every refueling outage to verify closure

  • 4-78 SlPVIJRO Rev~ion o November 10, 1993
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  • REACTOR REFUELING JUSTIFICATION RRV-6 System . . Various Valve(s):

Valves affected by this justification are identified Category:

Class Function:

by Table RRV-6. Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety functions.

The only way to verify closure is to perform a local leak rate/back pressure test. Since the valves are located inside containment, they cannot be tested quarterly.

These valves are containment isolation valves and are subject to leak testing every reactor refueling outage per the requirements of the Appendix J leak testing program and OM Part 10, Paragraphs 4.2.2.3(e) and (f). The leak tests not only verify that the valves close adequately as does a normal back pressure test, but the tests also reveal the condition of the valve seating surfaces.

As required by Paragraph 4.2.2.3(e), the leak tests include acceptance criteria for the maximum allowed leakage. Performing a back seat test every cold shutdown does not provide enough increase in safety to justify the burden of back seat testing on a more frequent basis. Testing Frequency Exercise to the closed position every reactor refueling

  • 4-79 SlPVI3RO Revµ;ion o November 10, 1993
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  • Valve l-CH-309 l-IA-938 l-IA-939 l-RC-160 l-RM-3 l-SI-234 l-VP-12 S1PVI3RO REACTOR REFUELING JUSTIFICATION RRV-6 (Cont.) TABLE REACTOR RRV-6 Category AC AC AC AC AC AC Class Function 2 Normal Charging Isolation 2 Instrument Air Containment Isolation 2 Primary Grade Water to Pressurizer Relief TanJc 2 Isolation on Monitor Return Line 2 Nitrogen Accumulators N 2 Supply 2 Condenser Air Removal Discharge to Containment 4-80 Revj_;;ion o November 10, 1993
  • *
  • REACTOR REFUELING JUSTIFICATION RRV-7 System Component Cooling Valve(s):

1-CC-1105 1-CC-1106 1-CC-1107 Category:

C Class 3 1-CC-1188 1-CC-1189 1-CC-1190 Function:

Component Cooling Supply to RCP Thermal Barrier Isolation Reactor Refueling Justification These check valves must seat upon reversal of flow in order to fulfill their safety function to prevent gross leakage. For the following reasons, it is not practical to test the thermal barrier check valves quarterly or at cold shutdown:

1) the valves are inside a locked radiation area located inside containment; therefore, they are not accessible during normal operation, 2) the valves are inaccessible for about 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after cold shutdown due to decontamination activities which must be performed before entry into the area, 3) the reactor cooling pump(s) may be running with the reactor cooling* sy:stem temperature less than 200°F if an RHR loop is , .. , unavailable (in this case the valves and thus cooling to the thermal barriers would normally not be isolated) and 4) the valves have soft seats that are replaced every five years and using pressure to back seat these valves on the more frequent cold shutdown frequency may accelerate the degradation of the soft seats. These valves will be exercised only during refueling outages because the small increase in safety gained by performing this test every cold shutdown does not justify the burden of performing a local back pressure test
  • 4-81 S1PVI3RO Revision O November 10, 1993 REACTOR REFUELING JUSTIFICATION RRV-7 (Cont.)
  • Testing Frequency Exercise to the closed position every reactor refueling . *
  • 4-82 S1PVI3RO Revj.'?ion o November 10, 1993
  • *
  • REACTOR REFUELING JUSTIFICATION RRV-8 **System Chemical and Volume Control Valve(s):

1-CH-230 category:

c Class 2 Function:

Charging Pump Supply from VCT Discharge Reactor Refueling Justification During normal operation, this valve cannot be isolated to perform a back pressure test because normal letdown and charging flow would be interrupted.

Also, if the valve was isolated during normal operation, the charging pumps would have to be secured. This valve is also subject to leak testing, which is performed every reactor refueling.

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

  • Testing Frequency Exercise to the closed position every reactor refueling
  • 4-83 S1PVI3RO Revision o November 10, 1993 4.8 * *
  • S1PVI3RO ALTERNATIVE TESTING FOR NON-CODE VALVES According to the minutes of public meeting on Generic Letter 89-04, "Paragraph (g) of 10CFR 50.55a requires the use of Section XI of the ASME Code for inservice testing of components covered by the Code. For other components important to safety, the licensee also has the burden of demonstrating their continued operability." The minutes go on to state that, "The Code-required IST program is a reasonable vehicle to provide a periodic demonstration of the operability of pumps and valves not covered by the Code. If non-Code components are included in the ASME Code IST program (or some other licensee-developed inservice testing program) and certain Code provisions cannot be met, the Commission regulations (10 CFR 50.55a) do not require a 'request for relief' to be submitted to the staff. Nevertheless, documentation that provides assurance of the continued operability of the non-Code components through the performed tests should be available at the plant site." Non-Code components are components that are important to safety but are not in systems or portions of systems that are classified ASME Class 1, 2 or 3. Surry Power Station has elected to include certain Code components in the ASME IST program. Where the Code provisions cannot be met for non-Code components, alternative testing is performed that is adequate to ensure continued operability.

The alternate testing is described in this section. There may be other deviations from Code provisions that are not described in this section. For these cases, documentation is available at the plant site. As indicated in the minutes of public meeting on Generic Letter 89-04, a 'request for relief' need not be submitted for non-Code components.

Therefore, the alternative tests described in this section are not 'requests for relief' but are provided for information

  • 4-84 Revj.sion o November 10, 1993
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  • NON-CODE ALTERNATIVE TESTING VNC-1 System Instrument Air Valve(s):

1-IA-928 1-IA-947 1-IA-948 Category:

C Class NC 1-IA-949 1-IA-952 1-IA-953 Function:

Bottled Air System Supply/Isolation Section XI Code Requirements Which cannot Be Met Exercise valves every three months. Basis For Alternate Testing Valves 1-IA-928, 947 and 952 must close to ensure that bottled air is available to actuate the main valves (1-RC-PCV-1455C, 1-RC-PCV-1456, and 1-MS-SOV-102A and B). Valves 1-IA-948, 949 and 953 must open to allow bottled air to reach the main valves. There is no direct means to measure the flow of air through the check valves. However, after the instrument air system is isolated and the lines vented, the stroke times of the main valves are measured and compared to acceptance criteria.

Measuring the stroke times provides indir~ct evidence that valves l-IA-948, 949 and 953 open properly and that valves 1-IA-928, 947 and 952 close properly.

The performance of this test renders the main valves inoperable; therefore, the tests cannot be performed during normal operation.

After stroking the main valves with the air bottles, the air bottles must be replaced.

The safety gained in testing the valves every cold shutdown versus every reactor refueling does not justify the burden of replacing the air bottles on the more frequent basis

  • 4-85 S1PVI3RO Rev~sion o November 10, 1993
  • *
  • NON-CODE ALTERNATIVE TESTING VNC-1 (Cont.) Alternative Testing Valves 1-IA-928, 947 and 952 will be tested closed and valves 1-IA-948, 949 -and 953 will be tested open by isolating and venting the instrument air lines, and then stroking the main valves with the bottled air. The stroke times of the main valves will be measured and compared to acceptance criteria.

This test will be performed every reactor refueling . 4-86 S1PVI3RO Revµ;ion o November 10, 1993

  • *
  • SlPVIJRO NON-CODE ALTERNATIVE TESTING VNC-2 Non-Code Alternative Testing Withdrawn 4-87 Rev.:j.sion o November 10, 1993
  • *
  • System Valve(s):

NON-CODE ALTERNATIVE TESTING VNC-3 Emergency Generator 1-EG-43 1-EG-44 1-EG-45 1-EG-46 1-EG-SOV-lOOA 1-EG-SOV-lOOB 3-EG-43 3-EG-44 3-EG-45 3-EG-46 3-EG-SOV-300A 3-EG-S0V-300B Category:

B (1/3-EG-43,44, 1/3-EG-SOV-1/JOOA and B) C (1/3-EG-45,46)

Class : NC Function:

1/3-EG-43,44 EDG Starting Air/Drive Air Control/Relay Valves 1/3-EG-45,46 EDG Air Start Pressure Equalizing Check Valves 1/3-EG-SOV-1/JOOA and B Air start System Solenoid Valves OM Part 10 Code Requirements Which Cannot Be Met For valves l/3-EG-43,44, and 1/3-EG-SOV-1/JOOA, B, measure stroke time. For valves 1/3-EG-45,46, measure flow to verify full open Basis For Alternate Testing Valves 1/3-EG-43 and 44 are air pilot valves that open to supply drive air to the EOG air starting motors. These valves along with the air start solenoid valves 1/3-EG-SOV-1/JOOA and B have actuation times considerably under a second and there is no visual reference on the valve to observe the stroke; therefore, the stroke time cannot be measured.

Valves 1/3-EG-45 and 46 are check valves that close to prevent opening the air start valves before the air motor pinion gears are fully engaged. They open to ensure that the air motor pinions remain engaged (hold-in feature) when the air motors are operating.

The only indication of the proper operation of the 4-88 S1PVI3RO Revi.sion O Nov~inber 10, 1993

  • *
  • NON-CODE ALTERNATIVE TESTING VNC-3 (Cont.) check valves is the proper operation of the pinion gears. The air pilot valves and the check valves work in concert with the air start solenoid valves to start the emergency diesels upon demand within the required time. Alternative Testing These valves will be stroke tested quarterly by observing that the valves perform their intended function, which is to start the diesel engines. Adequate performance of the valves will be verified by recording the time it takes for the diesel engines to reach a predetermined RPM and comparing the time to an acceptance criterion.

Also, the failure of these valves to perform will promptly give a diesel engine trouble alarm. Further investigation would identify problems with the operability of these valves

  • 4-89 S1PVI3RO Revlsion o November 10, 1993
  • *
  • NON-CODE ALTERNATIVE TESTING VNC-4 System . . EE Valve(s):

l-EE-SOV-100 l-EE-SOV-101 Category:

B Class : NC l-EE-SOV-104 l-EE-SOV-105 Function:

Diesel Fuel Oil Pump Discharge Valves OM Part 10 Code Requirements Which cannot Be Met Measure stroke time. Basis For Alternate Testing These valves are small (l"), fast acting solenoid operated gate valves with no position indication lights and no local visual means of determining stroke time. Valve operability can only be indirectly observed by verifying system operability.

Also, these valves are interlocked with the pumps to open and close upon pump startup and shutdown.

Alternate Testing Proposed These solenoid observing that function (fuel valve has been valves will be stroke tested quarterly by the solenoid valves perform their intended oil is flowing to the day tank after the solenoid opened)

  • 4-90 S1PVI3RO Revision o November 10, 1993

5.0 REPORTING

OF INSERVICE TEST RESULTS * *

  • SlPVIJRO 5.1 PUMP INSERVICE TESTING PROGRAM A record of each pump will be maintained in accordance with OM Part 6, Section 7.1 that includes the following:
1) the manufacturer and the manufacturer's model and serial or other identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) a copy of the pump manufacturer' -operating limits. A record of inservice test plans will be maintained in accordance with OM Part 6, Section 7.2 that includes the following:
1) the hydraulic circuit to be used, 2) the location and type of measurement for the required test parameters, 3) the reference values and 4) the method of determining reference values which are not directly measured by instrumentation.

A record of test results will be maintained in accordance with OM Part 6, Section 7.3 that includes the following:

1) pump identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 4-91 Revt~ion o November 10, 1993
  • *
  • S1PVI3RO 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action, 8) evaluation and justification for changes to reference values and 9) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will he maintained in accordance with OM Part 6, Section 7.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Pwnp Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC
  • 4-92 Rev~ion O November 10, 1993 5.2 *
  • S1PVI3RO VALVE INSERVICE TESTING PROGRAM A record of each valve will be maintained in accordance with OM Part 10, Section 6.1 that includes the following:
1) the manufacturer and the manufacturer's model and* serial or other unique identification number, 2) a copy or summary of the manufacturer' acceptance test report if available, 3) preservice test results and 4) limiting value of full stroke time. This IST Program Plan meets the requirements of OM Part 10, Section 6.2, Test Plans. A record of test results will be maintained in accordance with OM Part 10, Section 6.3 that includes the following:
1) valve identification, 2) date of test, 3) reason for test (e.g., post maintenance, routine inservice test establishing reference values, etc.), 4) values of measured parameters, 5) identification of instruments used, 6) comparisons with allowable ranges of test values and analysis of deviations, 7) requirement for corrective action and
  • 8) signature of the person or persons responsible for conducting and analyzing the test. A record of corrective action will be maintained in accordance with OM Part 10, Section 6.4 that includes a summary of the corrections made, the subsequent inservice tests and confirmation of operation adequacy, and the signature of the individual responsible for the corrective action and verification of results. The Valve Inservice Test Program, associated surveillance test procedures and results will be kept 4-93 Revtsion o November 10, 1993
  • S1PVI3RO at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC
  • 4-94 Revision o November 10, 1993
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  • S1PVI3RO 6.0 QUALITY ASSURANCE PROGRAM The Pwnp and Valve Inservice Test Program activities will be conducted in accordance with the Nuclear Operations Department Standards Manual and Technical Specifications for Surry Power Station . 4-95 Rev~ion o November 10, 1993
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