ML072330523
| ML072330523 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/13/2007 |
| From: | Mims D Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05732-DCM/RJR | |
| Download: ML072330523 (137) | |
Text
10 CFR 50.55a(f)(5) 10 CFR 50.55a(a)(3)
A--P A subsidiary of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P.O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-05732-DCM/RJR August 13, 2007 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN 50-5281529/530 Third 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests PRR-01, PRR-02, PRR-03, PRR-04, PRR-05, PRR-06, PRR-07 and VRR-01 Pursuant to 10 CFR 50.55a(f)(5)(i), Arizona Public Service Company (APS) has revised the Palo Verde Nuclear Generating Station (PVNGS) pump and valve inservice testing program for the third 10-year test interval for Units 1, 2, and 3. The third interval begins on January 15, 2008. Enclosure 1 provides a summary of the Palo Verde pump and valve inservice testing (IST) program and contains the relief requests required for the third interval. Each of these relief requests were previously authorized for Palo Verde's second interval by the NRC Safety Evaluation dated July 8, 1999, except PRR-02.
Relief request PRR-02 is being requested because the installed instrumentation does not meet the new accuracy requirement from Table ISTB-3500-1 of the 2001 Edition with the 2003 Addenda of the ASME OM Code. Enclosure 2 is an information copy of the revised IST program.
APS requests approval of the relief requests prior to the start of the third inservice testing interval which will begin on January 15, 2008.
This letter contains no new commitments. If you have any questions about this request, please contact Glenn A. Michael at (623) 393-5750.
Sincerely, A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak 0 Diablo Canyon 0 Palo Verde
- South Texas Project
- Wolf Creek W7
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Third 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests Page 2 DCM/GAM/RJR/gt - Palo Verde Pump and Valve Inservice Testing Program Summary Attachment to Enclosure 1 - Third 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests PRR-01, PRR-02, PRR-03, PRR-04, PRR-05, PRR-06, PRR-07 and VRR-01 - Information Copy of the Revised Third 10-Year Interval Pump and Valve Inservice Testing Program cc:
B. S. Mallett NRC Region IV Regional Administrator M. T. Markley NRC NRR Project Manager G. G. Warnick NRC Senior Resident Inspector for PVNGS
ENCLOSURE I Palo Verde Pump and Valve Inservice Testing Program Summary
Palo Verde Pump and Valve Inservice Testing Program Summary Section 50.55a of Title 10 of the Code of Federal Regulations (10 CFR), requires that inservice testing (IST) of certain American Society of Mechanical Engineers (ASME)
Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) IST program intervals in accordance with the specified ASME Code incorporated by reference in the regulations, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Nuclear Regulatory Commission (NRC or the Commission) pursuant to paragraphs (a)(3)(i), (a)(3)(ii), or (f)(5)(iii) of 10 CFR 50.55a. In accordance with 10 CFR 50.55a(f)(4)(ii), Arizona Public Service Company (APS) is required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month IST program interval. In accordance with 50.55a(f)(4)(iv), inservice tests of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to NRC approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
The Palo Verde Nuclear Generating Station (PVNGS) Pump and Valve Inservice Testing Program was developed in accordance with the 2001 Edition with the (w/) 2003 Addenda of the ASME OM Code. The Palo Verde third 10-year IST interval for all three units begins on January 15, 2008.
The attachment to this enclosure contains the relief requests required for the third interval. Enclosure 2 is an information copy of the revised IST program.
Relief Requests PRR-02, PRR-06, PRR-07 and VRR-01 are being submitted under the provision of 10 CFR 50.55a(a)(3)(i), wherein the proposed alternatives would provide an acceptable level of quality and safety.
Relief Requests PRR-01, PRR-03, PRR-04 and PRR-05 are being submitted under the provisions of 10 CFR 50.55a(f)(5)(iii), wherein inservice testing that is impractical for the facility.
Each of these relief requests were previously authorized for Palo Verde's second interval by the NRC Safety Evaluation dated July 8, 1999, except PRR-02. Relief request PRR-02 is being requested because the installed instrumentation does not meet the new accuracy requirement from Table ISTB-3500-1.
The attached APS requests demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety or (2) conformance is impractical for the facility.
APS requests approval of the relief requests prior to the start of the third inservice testing interval which will begin on January 15, 2008.
Page 1
Attachment to Enclosure 1 Third 10-Year Interval Pump and Valve Inservice Testing Program Relief Requests PRR-01, PRR-02, PRR-03, PRR-04, PRR-05, PRR-06, PRR-07 and VRR-01
PUMP RELIEF REQUEST PRR-01 Relief Request In Accordance with 10 CFR 50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
Essential Auxiliary Feedwater Pump Flow Rate Measurement ASME Components Affected:
Pump ID Pump Description Code Class Pump Group AFA-PO1 Essential Auxiliary 3
B Feedwater Pump (Turbine-Driven)
AFB-PO1 Essential Auxiliary 3
B Feedwater Pump (Motor-Driven)
Component/System Function:
The essential auxiliary feedwater (AF) pumps supply water to the steam generators during an accident. They also can be used to supply feedwater to the steam generators during plant startup and shutdown.
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5122, "Group B Test Procedure," "Group B tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5122(b), "The differential pressure or flow rate shall be determined and compared to its reference value."
Impracticality of Compliance:
The Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow Page 1
PUMP RELIEF REQUEST PRR-01 to a specified value) are impractical since this is a fixed resistance recirculation path with no flow instrumentation provided. When the pump operates on minimum flow recirculation (approx. 260 gpm) the specified reference point is essentially achieved by the recirculation lines fixed resistance. To establish the fixed resistance the minimum flow recirculation line contains an administratively controlled locked-throttled drag valve and a locked open manual isolation valve. The use of an ultrasonic flowmeter was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the AF mini-flow piping. Allowing the flow to remain fixed by the locked-in resistance increases the potential for repeatable test results and degradation monitoring rather than changing the resistance based on ultrasonic flow meter readout fluctuations. With this understanding, there is little value added in installing flow instrumentation to measure and record the flow with instrumentation that meets ISTB-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
Burden Caused by Compliance:
To comply with the Code there are only two practical flow paths available for testing AFA-PO1 and AFB-PO1. The primary flow path is into the main feedwater lines to the steam generators. The other flow path is the minimum flow recirculation line that recirculates back to the condensate storage tank. The flow path to the steam generators is equipped with flow instrumentation, but the recirculation line is a fixed-resistance circuit with no provisions for flow indication.
Use of the primary flow path at power would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to thermal shock/fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.
Modifying the minimum flow recirculation line to provide flow indication to meet the +/- 2%
accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed at approximately 260 gpm and differential pressure is used to monitor degradation. Use of an ultrasonic flow meter and possible adjustment of the fixed resistance introduces the potential for less accurate degradation monitoring than currently employed.
Proposed Alternative and Basis for Use:
During plant operation, quarterly Group B pump testing for pumps AFA-PO1 and AFB-PO1 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance to establish the specified reference point.
ISTB-5100(b)(2) allows the use of bypass test loops to be used for Group B tests. The PVNGS minimum flow recirculation line is designed to meet the pump manufacturers Page 2
PUMP RELIEF REQUEST PRR-01 operating specifications of approximately 260 gpm. Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5100-1.
Pumps AFA-P01 and AFB-P01 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps AFA-P01 and AFB-P01 are standby pumps. Little degradation is expected during plant operation when the pumps are idle except for testing. Testing the pumps within +/- 20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with no flow instrumentation provided.
Duration of Proposed Alternative:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
Complies with NRC Generic Letter 89-04, Position 9. Relief Request PRR-01 was previously authorized for Palo Verde pursuant to 10 CFR 50.55a(f)(6)(i) for the second interval in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 3
PUMP RELIEF REQUEST PRR-02 Relief Request In Accordance with 10 CFR 50.55a(a)(3)(i)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety --
Diesel Fuel Oil Transfer Pump Suction Pressure Measurement ASME Components Affected Pump ID Pump Description Code Class Pump Group DFA-P01 Diesel Generator Fuel Oil 3
B Transfer Pump DFB-P01 Diesel Generator Fuel Oil 3
B Transfer Pump Component/System Function:
Transfer diesel fuel from the fuel oil storage tank to the EDG day tank
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-351 0, "General," ISTB-351 0(a), "Accuracy", "Instrument accuracy shall be within the limits of Table ISTB-3500-1."
Table ISTB-3500-1, "Required Instrument Accuracy", Pressure, Comprehensive Test, +
0.5% accuracy.
Reason for the Request:
There are no inlet pressure gauges installed for this pump configuration. Specifically, the pumps are horizontal, centrifugal type with an integral motor. They operate submerged in the diesel fuel oil storage tank. The pump and drive motor are completely housed in an enclosed steel casing with no shaft penetrations requiring seals or packing. The casing has a hermetically sealed compartment for the stator windings of the motor to prevent entrance of pumped liquid or vapor. Pump bearings are cooled by recirculation of pumped fluid. The entire assembly is suspended from a cover plate, which is bolted to a nozzle on the tank.
The diesel generator fuel oil storage tank is equipped with level instrumentation (DFN-LI-33 and DFN-LI-34) having a calculated loop accuracy of +/- 1.5%. The instrument reads out in percent of tank level which is converted to suction pressure during the quarterly pump surveillance test. The calibrated instrument range results in a suction pressure span of 0.2 psig to 4.4 psig. This instrument accuracy is acceptable for use Page 1
PUMP RELIEF REQUEST PRR-02 during Group B pump testing but does not meet the +/- 0.5% accuracy as required by Table ISTB-3500-1 for Comprehensive Pump Testing performed every 2 years.
Proposed Alternative and Basis for Use:
The installed instrumentation converts to a full-scale range of 4.4 psig, which only slightly exceeds the pump suction reference value of 3.8 psig (full scale equals 1.15 times reference).
Considering the existing 1.5% accuracy of the level instrument, the reading could be as high as 3.85 psig or as low as 3.74 psig. This results in less than a 0.06 psig difference in the readings and is considered insignificant when monitoring for degradation. The existing accuracy is equivalent to the 1.5% minimum accuracy allowed by the combination of instrument full-scale range and accuracy as specified in Subsection ISTB 3510 for comprehensive pump testing. This accuracy provides adequate assurance of operability. The current instrumentation provides sufficient repeatability to allow for an evaluation of the pump hydraulic condition and detect pump degradation.
Use of the existing diesel generator fuel oil storage tank instrumentation should be considered an acceptable alternative to the accuracy requirements of Table ISTB-3500-1.
Supporting Facts:
Technical Specification 3.8.3.1 requires that the diesel generator fuel oil storage tank be maintained at _>80% which is verified every 31 days to assure sufficient supply for 7 days of full load operation. The difference between minimum allowable tank level and top of the tank is only 26.4 inches. Due to strict controls placed on fuel oil level, the suction pressure cannot vary by more than 0.7 psig. Review of test history shows that the maximum variance recorded is approximately 0.5 psig. The suction pressure is essentially fixed by the TS level requirements, allowing for very little variation in suction pressure. There is no value added in providing more precise suction pressure instrumentation for monitoring pump degradation.
The following test history shows the essentially constant suction pressure:
Unit Pump ID Date Suction Pressure 1
1 MDFAP01 6/6/2006 3.8 1MDFAP01 8/24/2006 4
1MDFAP01 11/15/2006 4
1MDFAP01 2/8/2007 4
1 MDFAP01 5/3/2007 3.9 1MDFBPO 5/18/2006 4.3 1 MDFBPO0 8/10/2006 3.9 1MDFBPO0 11/2/2006 3.6 1MDFBPO1 1/25/2007 3.8 1MDFBPO0 4/19/2007 3.85 Page 2
PUMP RELIEF REQUEST PRR-02 Unit 2
Pump ID 2MDFAP01 2MDFAP01 2MDFAP01 2MDFAP01 2MDFAP01 2MDFBPO0 2MDFBPO0 2MDFBPO0 2MDFBP01 2MDFBP01 Date 4/20/2006 5/4/2006 7/25/2006 1/10/2007 4/5/2007 2/9/2006 7/13/2006 10/15/2006 12/27/2006 3/21/2007 4/30/2006 6/28/2006 9/19/2006 12/15/2006 3/6/2007 4/18/2006 6/13/2006 9/5/2006 11/28/2006 2/22/2007 Suction Pressure 3.7 3.6 4
4 3.9 3.9 3.8 3.8 3.7 3.7 3
3MDFAP01 3MDFAP01 3MDFAP01 3MDFAP01 3MDFAP01 3MDFBP01 3MDFBP01 3MDFBP01 3MDFBPO0 3MDFBP01 4.1 3.7 4.1 3.7 3.9 3.4 3.9 4
3.9 3.8 Using the installed instrument (DFN-LI-33 and DFN-LI-34) for Group B and Comprehensive Pump Testing (CPT) provides an acceptable level of quality and safety since the instrument used yields a reading that is at least equivalent to that achieved using an instrument that meets the Code requirements as described in Table ISTB-3500-1.
The installed level instruments, DFN-LI-33 and DFN-LI-34, will be used to determine diesel fuel oil transfer pump suction pressure during inservice testing.
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The existing 1.5% accuracy of the level instrument discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Page 3
PUMP RELIEF REQUEST PRR-02 Duration of Proposed Alternative:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
None
References:
NUREG 1482, Revision 1, 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure."
Page 4
PUMP RELIEF REQUEST PRR-03 Relief Request In Accordance with 10 CFR 50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
LPSI Pump Flow Rate Measurement ASME Components Affected Pump ID Pump Description Code Class Pump Group SIA-PO1 Low Pressure Safety Injection 2
A (LPSI) Pump SIB-PO1 Low Pressure Safety Injection 2
A (LPSI) Pump Component/System Function:
LPSI pumps SIA-P01 and SIB-PO1 provide low-pressure coolant injection of borated water into the reactor coolant system under accident conditions. They also provide shutdown cooling flow post-accident and during normal reactor startup and shutdown.
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5221, "Group A Test Procedure," "Group A tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5221 (b), "The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value."
ISTB-5221(c), 'Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values."
Impracticality of Compliance:
The Code requires the Group A reference point flow rate to be established at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value). It is impractical to meet this requirement since this is a Page 1
PUMP RELIEF REQUEST PRR-03 fixed resistance recirculation path of approximately 180 gpm with limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm ultrasonic flowmeter with +/- 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
To establish the fixed resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations. When the pump operates on minimum flow recirculation, the specified reference point is essentially achieved by the fixed resistance. With this understanding, there is little value added in replacing the existing 0-5000 gpm, +/- 5% ultrasonic flowmeter, or adding instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
Burden Caused by Compliance:
During normal plant operation, the LPSI pumps cannot develop sufficient discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, LPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 180 gpm) of the design flow (4200 gpm). The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined to be impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
The LPSI pumps are categorized as Group A since they are normally used to provide shutdown cooling flow during shutdown operations, and occasionally for recirculating the refueling water tank when the unit is at power. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
Modifying the minimum flow recirculation line to provide flow indication to meet the +/- 2%
accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed and differential pressure is used to monitor degradation.
Proposed Alternative and Basis for Use:
During plant operation, quarterly Group A pump testing for pumps SIA-PO1 and SIB-P01 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 180 gpm to establish the specified reference point.
Subsection ISTB, ISTB-5200(b)(1) allows the use of bypass test loops to be used for Group A tests. The flow rate through the loop is established at the highest practical flow rate of approximately 180 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be Page 2
PUMP RELIEF REQUEST PRR-03 measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5200-1.
Pumps SIA-P01 and SIB-P01 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P01 and SIB-P01 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +/- 20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group A reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
Duration of Proposed Alternative:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
Complies with NRC GL 89-04, Position 9. Relief Request PRR-03 was previously authorized for Palo Verde as Relief Request PRR-05 pursuant to 10 CFR 50.55a(f)(6)(i) for the second interval in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS.
MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 3
PUMP RELIEF REQUEST PRR-04 Relief Request In Accordance with 10 CFR 50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
HPSI Pump Flow Rate Measurement ASME Components Affected Pump ID Pump Description Code Class Pump Group SIA-P02 High Pressure Safety Injection 2
B (HPSI) Pump SIB-P02 High Pressure Safety Injection 2
B (HPSI) Pump Component/System Function:
The HPSI pumps provide high-pressure coolant injection of borated water into the reactor coolant system under accident conditions. They also provide flow for long-term cooling and flushing to prevent boron precipitation.
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5122, "Group B Test Procedure," "Group B tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5122(b) "The differential pressure or flow rate shall be determined and compared to its reference value."
Impracticality of Compliance:
The Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) is impractical since this is a fixed resistance recirculation path of approximately 170 gpm which is measured by limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm ultrasonic flowmeter with +/- 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined to be impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping. To establish the fixed Page 1
PUMP RELIEF REQUEST PRR-04 resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations. When the pump operates on minimum flow recirculation the specified reference point is essentially achieved by the fixed resistance.
With this understanding, there is little value added in replacing the existing 0-5000 gpm,
+/- 5% ultrasonic flowmeter, or adding instrumentation that meets IST-351 0 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
Burden Caused by Compliance:
During normal plant operation, the HPSI pumps cannot develop sufficient discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, HPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 170 gpm) of the design flow (815 gpm). The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
The HPSI pumps are categorized as Group B. Pump SIB-P02 is used only occasionally to recharge the safety injection tanks. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
Modifying the minimum flow recirculation line to provide flow indication to meet the +/- 2%
accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed and differential pressure is used to monitor degradation.
Proposed Alternative and Basis for Use:
During plant operation, quarterly Group B pump testing for pumps SIA-P02 and SIB-P02 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 170 gpm to establish the specified reference point.
ISTB-5100(b)(2) allows the use of bypass test loops to be used for Group B tests. The PVNGS minimum flow recirculation line is designed to meet the pump manufacturers operating specifications. The flow rate through the loop is established at the highest practical flow rate of approximately 170 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5100-1.
Page 2
PUMP RELIEF REQUEST PRR-04 Pumps SIA-P02 and SIB-P02 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P02 and SIB-P02 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +/- 20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
Duration of Proposed Alternative:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
Complies with NRC GL 89-04, Position 9. Relief Request PRR-04 was previously authorized for Palo Verde as Relief Request PRR-06 pursuant to 10 CFR 50.55a(f)(6)(i) for the second interval in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS.
MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 3
PUMP RELIEF REQUEST PRR-05 Relief Request In Accordance with 10 CFR 50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
Containment Spray Pump Flow Rate Measurement ASME Components Affected Pump ID Pump Description Code Class Pump Group SIA-P03 Containment Spray (CS) Pump 2
A SIB-P03 Containment Spray (CS) Pump 2
A Component/System Function:
CS pumps SIA-P03 and SIB-P03 deliver borated water to the containment spray headers, providing containment cooling and pressure control during accident conditions.
The CS pumps can also be lined up to provide flow for shutdown cooling.
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5221, "Group A Test Procedure," "Group A tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5221(b), "The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value."
ISTB-5221 (c), "Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values."
Impracticality of Compliance:
The Code requires the Group A reference point flow rate to be established at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value). It is impractical to meet this requirement since this is a fixed resistance recirculation path of approximately 190 gpm with limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm Page 1
PUMP RELIEF REQUEST PRR-05 ultrasonic flowmeter with +/- 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
To establish the fixed resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations. When the pump operates on minimum flow recirculation, the specified reference point is essentially achieved by the fixed resistance. With this understanding, there is little value added in replacing the existing 0-5000 gpm, +/- 5% ultrasonic flowmeter, or adding instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
Burden Caused by Compliance:
Modifying the minimum flow recirculation line to provide flow indication to meet the +/- 2%
accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed at approximately 190 gpm and differential pressure is used to monitor degradation. The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
The normal containment spray flow path cannot be used for testing the CS pumps without spraying down the inside of the containment building and risking damage to important equipment. The reactor coolant system (RCS) injection portion of the shutdown cooling flow path cannot be used for testing during plant operation because the CS pumps are unable to develop sufficient discharge pressure to overcome RCS pressure.
The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 190 gpm) of the design flow (3890 gpm). The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. A larger recirculation flowpath is available; however, this requires an alternate line up and the same limited capability flow instrument exists in this portion of the recirculation line.
The larger recirculation flowpath is capable of carrying higher flow, but routine surveillance testing at less than the full flow reference value is not practical because of the pump rumble range (1800-2800 gpm). Testing in or near the rumble range is not practical because of the potential for equipment damage. Testing at flow rates above the rumble range (> 2800 gpm) is not practical because flow velocities in the recirculation piping would exceed the design criteria.
Page 2
PUMP RELIEF REQUEST PRR-05 The CS pumps are categorized as Group A since they are normally used to provide shutdown cooling flow during shutdown operations. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
Proposed Alternative and Basis for Use:
During plant operation, quarterly Group A pump testing for pumps SIA-P03 and SIB-P03 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 190 gpm to establish the specified reference point.
ISTB-5200(b)(1) allows the use of bypass test loops to be used for Group A tests. The flow rate through the loop is established at the highest practical flow rate of approximately 190 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5200-1.
Pumps SIA-P03 and SIB-P03 will be comprehensively tested in accordance with ISTB-5223, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P03 and SIB-P03 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +/- 20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group A reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
Duration of Proposed Alternative:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Page 3
PUMP RELIEF REQUEST PRR-05 Precedents:
Complies with NRC GL 89-04, Position 9. Relief Request PRR-05 was previously authorized for Palo Verde as Relief Request PRR-1 1 pursuant to 10 CFR 50.55a(f)(6)(i) for the second interval in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS.
MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 4
PUMP RELIEF REQUEST PRR-06 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(ii)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety --
Charging Pump Vibration Measurement ASME Components Affected Pump ID Pump Description Code Class Pump Group CHA-P01 Charging Pump 2
A CHB-P01 Charging Pump 2
A CHE-P01 Charging Pump 2
A Component/System Function:
The charging pumps provide makeup water to the reactor coolant system for chemistry and volume control. They also provide auxiliary spray to the pressurizer and reactor coolant pump seal injection.
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-351 0, "General", ISTB-351 0(e), "Frequency Response Range", "The frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump rotational speed to at least 1000 Hz."
Reason for Request
The charging pumps are positive-displacement pumps with a constant running speed of 199 rpm (equivalent to 3.3 Hz). Compliance with ISTB-3510(e) would require using vibration instrumentation with a frequency response range of 1.1 Hz to at least 1000 Hz.
A low-speed probe with a frequency response range of 1.6 Hz to 100 Hz was purchased specifically for charging pump testing when the IST requirement for frequency response was one-half pump speed to at least pump shaft rotational speed. However, this probe does not meet the lower bound or the upper bound of the current Code-required frequency response range.
The charging pump bearings are oil-lubricated, sleeve type journal bearings. Because of the high reciprocating loads, the charging pump bearings are not susceptible to oil whirl, which is the primary failure mode that causes vibration below pump shaft rotational speed. There are no other failure mechanisms that manifest themselves with elevated vibration levels in the range of one-third to one-half pump shaft rotational frequency; all the remaining failure modes cause vibration at or above the pump speed. Experience Page 1
PUMP RELIEF REQUEST PRR-06 with these pumps confirms this fact. Therefore vibration instrumentation with a frequency response range above 1.6 Hz is acceptable for monitoring vibration of the charging pumps.
The low-speed probe is sensitive to vibration frequencies up to 30 times the running speed of the charging pumps. This is sufficient to identify bearing degradation, mechanical rubs, and other pump problems producing high-frequency vibrations. These pumps are susceptible to degradation mechanisms that would manifest themselves in the 1.6-100 Hz range and not in the extended vibration range required to be monitored by the Code (100-1000 Hz). Therefore, use of the higher frequency vibration probe provides no benefit. The charging pumps are monitored for other symptoms of degradation under the PVNGS Predictive Maintenance Program (see PRR-07 for a description of the PVNGS Predictive Maintenance Program).
Proposed Alternatives and Basis for Use:
The instrumentation used to measure charging pump vibration will have a frequency response range from 1.6 Hz to 100 Hz. Monitoring in the extended vibration range required to be monitored by the Code (100-1000 Hz) provides no benefit.
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The low-speed probe with a frequency response range of 1.6 Hz to 100 Hz discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Duration of Proposed Alternatives:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
Relief Request PRR-06 was previously authorized for Palo Verde as Relief Request PRR-07 pursuant to 10 CFR 50.55a(a)(3)(ii) for second interval in the NRC Safety Evaluation dated July 8,1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 2
PUMP RELIEF REQUEST PRR-07 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety --
Smooth Running Pumps ASME Components Affected:
Pump ID AFA-P01 AFB-P01 CTA-P01 CTB-P01 ECA-P01 ECB-P01 EWA-P01 EWB-P01 PCA-P01 PCB-P01 SIA-P01 SIB-P01 SIA-P02 SIB-P02 SIA-P03 SIB-P03 Pump Description Code Class Pump Group Essential Auxiliary Feedwater Pump (Turbine Driven)
Essential Auxiliary Feedwater Pump (Motor Driven)
Condensate Transfer Pump Condensate Transfer Pump Essential Chilled Water Circulation Pump Essential Chilled Water Circulation Pump Essential Cooling Water Pump Essential Cooling Water Pump Spent Fuel Pool Cooling Pump Spent Fuel Pool Cooling Pump Low Pressure Safety Injection (LPSI) Pump Low Pressure Safety Injection (LPSI) Pump High Pressure Safety Injection (HPSI) Pump High Pressure Safety Injection (HPSI) Pump Containment Spray Pump Containment Spray Pump Page 1
PUMP RELIEF REQUEST PRR-07 SPA-P01 Essential Spray Pond Pump 3
A SPB-P01 Essential Spray Pond Pump 3
A Component/System Function:
Various
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTB-3300, "Reference Values," Reference values shall be obtained as follows: (a)
Initial reference values shall be determined from the results of testing meeting the requirements of ISTB-31 00, Preservice Testing, or from the results of the first inservice test.
ISTB-3300(f), "All subsequent test results shall be compared to these initial reference values or to new reference values established in accordance with ISTB-331 0, ISTB-3320, or ISTB-6200(c)."
ISTB-6200(a), "Alert Range", "If the measured test parameter values fall within the alert range of Table ISTB-51 00-1, Table ISTB-5200-1, Table ISTB-5300-1, or Table ISTB-5300-2, as applicable, the frequency of testing specified in ISTB-3400 shall be doubled until the cause of the deviation is determined and the condition is corrected."
ISTB-6200(b), "Action Range", "If the measured test parameter values fall within the required action range of Table ISTB-5100-1, Table ISTB-5200-1, Table ISTB-5300-1, or Table ISTB-5300-2, as applicable, the pump shall be declared inoperable until either the cause of the deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with ISTB-6200(c)."
Reason for Request
Palo Verde has several pumps with vibration parameters readings in the range of
_*0.05 ips. Vibration velocities in this range can be significantly affected by hydraulic flow noise and repeatability of the vibration instruments. As a result, Palo Verde could be required to increase the frequency of specified testing when no degradation of the monitored equipment exists.
PVNGS expends considerable resources on preventive and predictive maintenance.
One result of these efforts is a number of pumps run very smoothly. For example, many pumps in the PVNGS IST Program would currently be candidates for "smooth-running" status under PRR-07, as shown in the table below. To impose Code-mandated Alert and Required Action values on "smooth-running" pumps unnecessarily penalizes PVNGS for achieving this high level of performance.
Page 2
PUMP RELIEF REQUEST PRR-07 Typical Vibration Reference Values inch Pump per second (ips)
Auxiliary Feedwater 0.12 - 0.27 Condensate Transfer
- 0.0044 - 0.0883 Essential Chilled Water
- 0.0075 - 0.0597 Essential Cooling Water
- 0.0295 - 0.0931 Low Pressure Safety Injection
- 0.0343 - 0.174 High Pressure Safety Injection 0.0667 - 0.296 Containment Spray 0.078 - 0.161 Spent Fuel Pool Cooling
- 0.031 -0.110 Essential Spray Pond
- 0.0201 - 0.0864
- Candidates for "smooth-running" status under PRR-007 For displacement reference values less than 0.5 mils, it is noted that the Section XI Code in effect for the first interval of the IST Program (1980 Edition, Winter 1981 Addenda) sets the Alert Range at > 1.0 mil and the Required Action Range at > 1.5 mil.
This implies a minimum reference value of 0.5 mils, which is equivalent to 0.047 ips for 1800 rpm pumps and 0.094 ips for 3600 rpm pumps. The effective reference values proposed for smooth-running pumps are roughly equal to the implied Section XI reference values for 1800 rpm pumps and more conservative than the implied reference values for 3600 rpm pumps. Without proposed alternative, the Alert Ranges for several smooth running pumps will be reduced by a factor of 10.
Proposed Alternatives and Basis for Use:
Vibration parameters that have reference values < 0.05 ips are considered "smooth-running". When vibration velocities are less than 0.05 ips, changes have been shown to be non-significant. To reduce any unnecessary penalty for those pump parameters considered "smooth-running", the Alert and Required Action values for these "smooth-running" parameters will be determined as if their reference value is 0.05 ips; that is, the Alert Range will be 0.125 ips to 0.3 ips, and the Required Action Range will be > 0.3 ips.
Candidates for "smooth-running" status will be analyzed per ISTB-3300(g) and ISTB-6400 to verify that use of this relief request will not prevent the detection of significant pump degradation. If any of these parameters are outside normally expected ranges, an evaluation will be performed and appropriate corrective actions will be taken.
The basis for use of these proposed Alert and Required Action ranges is discussed below.
In addition to the Code-mandated monitoring, these pumps are monitored under the PVNGS Predictive Maintenance Program. This program includes the following:
Spectrum band monitoring Bearing acceleration monitoring (on ball and roller bearings only)
Bearing oil analysis (for oil lubricated bearings)
Page 3
VALVE RELIEF REQUEST VRR 01 OMN-1, R 0, 3.4, Effect of MOV Replacement, Repair, or Maintenance, states that when an MOV or its control system is replaced, repaired, or undergoes maintenance that could affect the valve's performance, new inservice test values shall be determined or the previously established inservice test values shall be confirmed before the MOV is returned to service.
Diagnostic test results within the MOV Program setpoint bands are considered to be satisfactory and do not require analysis.
" OMN-1, R 0, 3.5, Grouping of MOVs for Inservice Testing, states that grouping MOVs for inservice testing is permissible.
PVNGS currently has elected not to use Grouping of MOVs for Inservice Testing.
OMN-1, R 0, 3.7, Risk Basis Criteria for MOV Testing, states that if establishing risk based criteria for performance testing, the Owner shall consider the following:
(a) develop an acceptable basis for MOV risk determination; (b) develop MOV screening criteria to determine each MOV's contribution to risk; and (c) establish applicability by a documented evaluation from a plant expert panel.
Palo Verde is currently not planning to implement a Risk Informed Program for its IST program. As noted above, Palo Verde uses risk/safety significance and MOV margin as part of the JOG program to establish MOV testing frequency. This provision is not applicable.
OMN-1, R 0, 6.3, Evaluation of Data, and 6.4, Determination of MOV Functional Margin, state that the owner shall determine which methods are suitable for evaluating test data for each MOV and application and that the owner shall demonstrate that adequate margin exists between the required torque and available torque and that changes to the operating characteristics of the MOV do not result in reaching a point of insufficient margin before the next schedule test activity.
Palo Verde utilizes the JOG Program criteria for determining MOV test frequency.
The MOV test frequencies have been established to ensure MOV setpoints and MOV margins are maintained over the MOV test interval which satisfies this requirement of OMN-1, R 0,.
OMN-1, R 0, 6.4.1, Determination of Required Torque, states that design basis required torque shall be determined from measurements taken during testing at design basis conditions.
Palo Verde determines a Stem Factor for rising stem valves whenever stem thrust and stem torque are measured. However, it is not possible to measure thrust and torque on all rising stem valves.
Page 4
PUMP RELIEF REQUEST PRR-07 0 Motor Current Signature analysis (for all but the smallest motors)
The PVNGS Predictive Maintenance (PdM) Program is part of the Preventive Maintenance (PM) Program described in UFSAR Section 17.2.3.11.1.6. The PM Program was developed using RCM, EPRI, and INPO guidelines as well as factoring in PVNGS site-specific experience and regulatory requirements. The PM Program and PdM activities are controlled by plant procedures. Each of these pumps has a maintenance plan documented in the PM Program which describes the PM and PdM activities performed on that pump. The performance of the system associated with each of these pumps is monitored and compared to performance criteria under the PVNGS Maintenance Rule Program. This ensures the continued effectiveness of the PM program to minimize component failures and maintain or improve system performance (balance availability and reliability).
The PVNGS Predictive Maintenance Program uses vibration analysis, lubricant analysis, and infrared thermographic analysis as appropriate, to predict the need for maintenance so that equipment can be worked prior to failure. The components included in this program include those considered important to safe and reliable plant operation, including certain pumps in the IST Program. The intervals for monitoring are based on manufacturer's recommendations, maintenance history, cost effectiveness, and experience. Although parts of the monitoring, analysis, database, and software used in the Predictive Maintenance Program do not fall under the PVNGS Quality Program, the Predictive Maintenance Program still provides valuable information for assuring the operational readiness of smooth-running pumps.
The vibration analysis program monitors the vibration of rotating machinery. In addition to the vibration at pump bearings, the vibration of the driver (turbine or motor) bearings are also collected and trended. Analyzed parameters and methods include vibration velocity, bearing acceleration, bearing high frequency detection, and spectral analysis.
The lubricant analysis program samples lubricants and analyzes them to identify degradation or negative trends. Most testing is performed at the on-site lubrication laboratory, where capabilities include wear debris, chemical composition, and lubrication cleanliness analysis.
In both the vibration monitoring and lubricant analysis programs, recently acquired data is compared with previous data to detect any indicated degradation of equipment condition. If degradation indicates the reliability of operating equipment may be negatively affected, or if acceptance criteria are no longer being met, appropriate corrective action is taken. Corrective action may include: continuing trending of the degraded condition, if the condition is not considered to be immediately threatening to the equipment and can be corrected during a time window convenient to plant operation; additional testing or monitoring to confirm the suspected degraded condition; inspection and repair of the equipment as necessary; changes to preventive maintenance procedures or schedules; or design changes.
Page 4
PUMP RELIEF REQUEST PRR-07 The following table contains examples of Unit I vibration test result history demonstrates consistent smooth running operation (Unit 2 and 3 are similar):
Unit Pump Date Pump Pump Axial Horizontal Vertical 1
CTAP01 7/2/2006
.016
.012
.006 1
CTAP01 9/18/2006
.020
.012
.0079 1
CTAP01 12/11/2006
.021
.014
.007 1
CTAP01 3/8/2007
.019
.012
.0058 1
CTBP01 11/8/2006
.024
.007
.0082 1
CTBPO1 12/7/2006
.014
.007
.0095 1
CTBPO1 1/29/2007
.016
.006
.011 1
CTBPO1 4/25/2007
.017
.007
.009 1
ECAP01 8/22/2006
.036
.034
.010 1
ECAP01 11/13/2006
.044
.027
.0092 1
ECAP01 2/5/2007
.057
.057
.0081 1
ECAP01 5/1/2007
.042
.034
.007 1
ECBPO1 8/8/2006
.026
.021
.013 1
ECBPO1 10/31/2006
.028
.024
.016 1
ECBPO1 1/22/2007
.030
.026
.012 1
ECBPO1 4/16/2007
.023
.027
.012 1
EWAP01 8/22/2006
.031
.028
.020 1
EWAP01 11/13/2006
.032
.023
.0214 1
EWAP01 2/6/2007
.033
.031
.0182 1
EWAP01 5/3/2007
.032
.034
.023 1
EWBPO1 8/8/2006
.033
.034
.026 1
EWBP01 10/31/2006
.033
.032
.026 1
EWBP01 1/23/2007
.033
.031
.023 1
EWBPO1 4/17/2007
.035
.038
.027 1
SIAP01(b) 4/11/2004
.033
.048 (a) 1 SIAP01(D) 11/29/2005
.047
.053 (a) 1 SIAP01(b) 12/8/2005
.043
.061 (a) 1 SIAP01(b) 6/1/2006
.057
.071 (a) 1 SIBP01 (b) 10/4/2002
.031
.032 (a) 1 SlBP01(b) 4/23/2004
.044
.060 (a) 1 SIBPO1(b) 10/16/2005
.027
.035 (a) 1 SIBPO1(b) 5/29/2006
.041
.062 (a) 1 PCAP01 6/28/2006
.060
.040
.024 1
PCAP01 9/26/2006
.059
.036
.027 1
PCAP01 12/11/2006
.058
.038
.029 1
PCAP01 3/6/2007
.058
.037
.023 1
PCBPO1 6/20/2006
.077
.037
.023 1
PCBPO1 9/11/2006
.075
.041
.025 1
PCBPO1 12/4/2006
.072
.045
.026 Page 5
PUMP RELIEF REQUEST PRR-07 Unit Pump Date Pump Pump Axial Horizontal Vertical 1
PCBP01 2/26/2007
.071
.041
.021 1
SPAP01(b) 8/22/2006
.049
.027
.0275 1
SPAP01(b) 11/14/2006
.052
.023
.0270 1
SPAP01(b) 2/6/2007
.055
.027
.0250 1
SPAP01(b) 5/3/2007
.049
.027
.0283 1
SPBP01(b) 8/7/2006
.092
.047
.0261 1
SPBP01(b) 11/1/2006
.088
.027
.0240 1
SPBP01(b) 1/23/2007
.090
.030
.029 1
SPBP01(b) 4/19/2007
.088
.035
.026 (a) - Inaccessible (b) - vibration readings taken at the motor-
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The revised Alert and Required Action values discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Duration of Proposed Alternatives:
The proposed alternative identified in this 10 CFR 50.55a Request shall be utilized during the Third 10-year IST Interval.
Precedents:
Relief Request PRR-07 was previously authorized for Palo Verde as Relief Request PRR-08 pursuant to 10 CFR 50.55a(a)(3)(i) for the second interval in the NRC Safety Evaluation dated July 8,1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Page 6
VALVE RELIEF REQUEST VRR 01 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
On the basis that the proposed alternative provides an acceptable level of quality and safety.
Code Case OMN MOV Exercising and Stroke Timing Component(s) Affected:
Motor-operated valve assemblies currently included in the Palo Verde Nuclear Generating Station (PVNGS) Motor-Operated Valve (MOV) Program Component/System Function: Various
Applicable Code Edition and Addenda
ASME OM Code 2001 Edition w/2003 Addenda Applicable Code Requirement(s):
ISTA-3130, "Application of Codes Cases," paragraph (b) states that Code Cases shall be applicable to the edition and addenda specified in the test plan.
ISTC-3500, "Valve Testing Requirements," states that active and passive valves in the categories defined in ISTC-1 300 shall be tested in accordance with the paragraphs specified in Table ISTC-3500-1 and the applicable requirements of ISTC-5100 and ISTC-5200.
ISTC-3700, "Position Verification Testing," states that valves with remote position indicators shall be observed locally at least once every 2 years to verify the valve operation is accurately indicated.
ISTC-5120, "Motor-Operated Valves," paragraph states that active valves shall have their stroke times measured when exercised in accordance with ISTC-3500.
Reason for Request
Code Case OMN-1, Revision 0 provides alternative rules to those of OM Code, Subsection ISTC, for preservice and inservice testing to assess the operational readiness of certain electric motor-operated valve assemblies in light-water reactor power plants. However, Regulatory Guide (RG) 1.192 has not yet extended its use to the 2001 Edition w/2003 Addenda of the OM Code which is the basis for the planned third 10-year IST program at Palo Verde.
Proposed Alternatives and Basis for Use:
In lieu of the provisions for MOV testing in Subsection ISTC of the 2001 Edition w/2003 Addenda of the ASME OM Code, APS requests relief for the continued use of ASME Code Case OMN-1, Revision 0.
Page 1
VALVE RELIEF REQUEST VRR 01 Pursuant to ASME Code Case OMN-1, Revision 0 and the guidelines provided in NUREG-1482, Revision 1, Section 4.2.5, PVNGS proposes to continue implementation of Code Case OMN-1 in lieu of the stroke-time provisions specified in ISTC-5120 for MOVs. Code Case OMN-1 has been determined by the NRC to provide an acceptable level of quality and safety when implemented in conjunction with the conditions imposed in RG 1.192.
The conditions specified in RG 1.192 are as follows:
Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, dated June 2003 states that licensees may use Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants," Revision 0, in lieu of the provisions for stroke-time testing in Subsection ISTC of the 1995 Edition up to and including the 2000 Addenda of the ASME OM Code when applied in conjunction with the provisions for leakage rate testing in, as applicable, ISTC 4.3 (1995 Edition with the 1996 and 1997 Addenda) and ISTC-3600 (1998 Edition with the 1999 and 2000 Addenda). In addition, licensees who continue to implement Section Xl of the ASME BPV Code as their Code of Record may use OMN-1 in lieu of the provisions for stroke-time testing specified in Paragraph 4.2.1 of ASME/ANSI OM Part 10 as required by 10 CFR 50.55a(b)(2)(vii) subject to the conditions in this Regulatory Guide (RG) 1.192.
Licensees who choose to apply OMN-1 are required to apply all its provisions.
The relevant provisions are as follows:
(1) The adequacy of the diagnostic test interval for each motor-operated valve (MOV) must be evaluated and adjusted as necessary, but not later than 5 years or three refueling outages (whichever is longer) from initial implementation of OMN-1.
(2) When extending exercise test intervals for high risk MOVs beyond a quarterly frequency, licensees must ensure that the potential increase in Core Damage Frequency (CDF) and risk associated with the extension is small and consistent with the intent of the Commission's Safety Goal Policy Statement.
(3) When applying risk insights as part of the implementation of OMN-1, licensees must categorize MOVs according to their safety significance using the methodology described in Code Case OMN-3, "Requirements for Safety Significance Categorization of Components Using Risk Insights for Inservice Testing of LWR Power Plants," with the conditions discussed in RG 1.192 or use other MOV risk ranking methodologies accepted by the NRC on a plant specific or industry-wide basis with the conditions in the applicable safety evaluations.
In addition, the following implementation clarifications are necessary:
OMN-1, R 0, 3.1, Design Basis Verification Test, states that justifications for testing at conditions other than design bases conditions and for grouping like MOVs shall be documented by an engineering evaluation, alternative testing techniques, or both.
Page 2
VALVE RELIEF REQUEST VRR 01 Design Basis Verification Testing was completed during plant startup testing and in response to NRC Generic Letter (GL) 89-10 testing requirements, which satisfies the requirement of OMN-1.
OMN-1, R 0, 3.2, Preservice Test, states that each MOV shall be tested during the preservice test period or before implementing inservice testing.
Preservice Testing was performed pursuant to NRC GL 89-10 testing requirements, which meet the intent of this requirement.
OMN-1, R 0, 3.3 (b), Inservice Test, states that inservice tests shall be conducted in the as-found condition.
Because of the extensive PVNGS MOV performance history, some as-found MOV testing can be waived by a documented engineering evaluation, e.g., if a modification to the valve or actuator will be performed or if valve maintenance is planned (such as valve repacking) and for activities that will require a post maintenance diagnostic test to return the MOV to service. This provision will not apply if there is reason to suspect the MOV is not operating properly prior to the maintenance activity.
OMN-1, R 0, 3.3 (c), Inservice Test, states that the inservice testing program will include a mix of static and dynamic MOV performance testing.
Dynamic testing will be performed to address MOV modifications.
PVNGS performed differential pressure testing in accordance with NRC GL 89-10 and also participated in the Joint Owners Group (JOG) differential pressure testing program (i.e., dynamic testing) which has been completed. The mix of static and dynamic testing at PVNGS in the future will be static testing with additional dynamic testing performed as required by the PVNGS MOV Program to address MOV modifications.
OMN-1, R 0, 3.3.1, Inservice Test Frequency, states that the inservice test frequency shall be determined in accordance with 6.4.4 or that testing shall be conducted every 2 refueling cycles or 3 years (whichever is longer) until sufficient data exist to determine a more appropriate test frequency not to exceed 10 years.
Palo Verde has committed to the JOG program as part of its response to NRC GL 96-05. Inservice Test Intervals will be established based on MOV margin and the valve's risk/safety significance in accordance with JOG program requirements.
PVNGS is currently implementing the JOG Interim Test Program in accordance with JOG Report MPR 1807. PVNGS will implement the final JOG Periodic Verification Program in accordance with JOG Report MPR 2524-A as noted in the NRC SER on the JOG program.
Page 3
VALVE RELIEF REQUEST VRR 01
" OMN-1, R 0, 6.4.2.1, Available Output Based on Motor Capabilities and 6.4.2.2, Available Output Based on Torque Switch Setting, states that stem torque shall be determined.
Palo Verde actuator output capabilities are determined as an integral part of the MOV design basis calculations and are not performed as part of the evaluation of MOV test data. The evaluation of test data compares actuator output to the acceptance band determined in design basis calculations. This applies to all actuators and includes those actuators setup based on limit switches.
For actuators setup based on torque switches, available output includes torque measurement uncertainty (or displacement uncertainty if springpack displacement is used) and torque switch repeatability.
" OMN-1, R 0, 6.4.3, Calculation of MOV Functional Margin, states that MOV functional margin shall be calculated as the difference between the available stem torque and the required stem torque.
Palo Verde calculates the margin as a percentage (vice difference in thrust or torque between available output and valve operating requirements).
" OMN-1, R 0, 6.4.4, Determination of MOV Test Interval, states that calculations for determining MOV functional margin shall also be evaluated to account for anticipated time-related changes in performance.
As noted above for OMN-1, R 0, 3.3.1, the test interval is based on the NRC approved JOG program.
" OMN-1, R 0, 9.1, Test Information, states that test information shall be recorded or verified for MOV testing described in Section 3 and provides information that should be considered.
Test Information relevant to the MOV being tested and relevant test parameters will be recorded electronically with the test trace and/or on the test data sheet. MOV configuration data not directly related to testing, e.g., name plate information, breaker setting, etc. are maintained in plant records.
Code Case OMN-1, R 0, should be considered acceptable for use with OM Code-2001 Edition w/2003 Addenda as the Code of record. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), PVNGS requests relief from the specific ISTC Code requirements identified in this relief request.
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
Page 5
VALVE RELIEF REQUEST VRR 01 (i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The continued use of ASME Code Case OMN-1, Revision 0, as discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Duration of Proposed Alternatives:
The proposed alternative identified in this relief request shall be utilized during the third 10-year IST interval.
Precedents:
Relief Request VRR-01 was previously authorized for Palo Verde as Relief Request VRR-1 2 pursuant to 10 CFR 50.55a(a)(3)(i) for second interval in the NRC Safety Evaluation dated July 8,1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
References:
NUREG-1482, Revision 1, Section 4.2.5, "Alternatives to Stroke-Time Testing" Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code", Table 2, "Conditionally Acceptable OM Code Cases" OM Code-2001 Edition w/2003 Addenda, Paragraph ISTC-5120, "Motor Operated Valves" OM Code-2001 Edition w/2003 Addenda, Paragraph ISTA-3130, "Application of Code Cases" Code Case OMN-1, Revision 0, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants" Page 6
ENCLOSURE 2 Information Copy of the Revised Third 10-Year Interval Pump and Valve Inservice Testing Program
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 1 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Procedure Intent This procedure identifies the pump and valve tests performed to meet the requirements of 10 CFR 50.55a, ASME/ANSI OM Code 2001 Edition w/2003 Addenda, and Technical Specification 5.5.8 for the Third 10-Year IST Interval.
Revision 20 Changes
- This revision represents a total re-write to reflect the requirements for the Third 10-Year IST Interval, effective 1/15/2008 through 1/14/2018.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 2 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Table of Contents Section Page 1.0 Program Purpose..................................................................
3 2.0 R egulatory B asis..................................................................
4 3.0 OM Code Case Acceptability.................................................
6 4.0 Program Development..........................................
8 5.0 Component Tables................................................................
9 6.0 References.........................................................................
9 Component Table - Pumps..............................................................
10 Component Table - Valves..............................................................
12 Code Deviation Index.....................................................................
50 Pump 10CFR50.55a Requests..............................................................
51 Valve Cold Shutdown Justifications.......................................................
78 Valve Refueling Outage Justifications.....................................................
88 Valve 1 OCFR50.55a Requests...............................................................
90 Notes, Legends, Definitions and Abbreviations...........................................
95
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 3 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 1.0 PROGRAM PURPOSE Third 10-Year Interval IST Program Update.
This procedure identifies the pump and valve tests performed to meet the requirements of 10 CFR 50.55a, ASME/ANSI OM Code 2001 Edition w/2003 Addenda, and Technical Specification 5.5.8.
This program is applicable to PVNGS Units 1, 2, and 3. The pumps and valves within the scope of this program are identified in the component tables.
This program plan document provides the requirements for assessing the operational readiness of pumps and valves whose specific functions are required to bring the reactor from any operating mode to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.
Palo Verde Nuclear Generating Station is licensed with a safe shutdown condition of Cold Shutdown.
The Inservice Testing Program for Pumps and Valves is applicable for a one hundred twenty (120) month interval. The chronology for Palo Verde Nuclear Generating Station is listed below:
In 1995, PVNGS changed the 120-month intervals for the Unit 1, 2, and 3 IST programs in order to establish concurrent intervals. The change revised the end dates of the initial 120-month intervals and the start dates of the second 120-month intervals of all three units to a common date of January 15, 1997. The original schedules were based on the commercial operation dates of the units.
This change was made to provide greater consistency between units and to simplify the 120-month updates required by 10 CFR 50.55a(f)(4)(ii).
" In 1997, the NRC granted a 1-Year Interval extension (to January 15, 1998) for all three units.
- 1. The first 120-month interval for Unit 1 began on 1/28/1986, the commercial operating date, through 01 / 15/1998.
- 2. The first 120-month interval for Unit 2 began on 9/22/1986, the commercial operating date, through 01/15/1998.
- 3. The first 120-month interval for Unit 3 began on 1/08/1988, the commercial operating date, through 01/15/1998.
" The second 120-month interval IST Program for all three units began on, 01/15/1998 and ends on 01/14/2008.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 4 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 The third 120-month interval IST Program for all three units begins on 01/15/2008 and ends on 01/14/2018.
The IST Program is submitted to the NRC for their overall review and specific approval of associated 1 OCFR50.55a Requests for the successive 120-month IST Program. The program documents submitted to the NRC are used to prepare for IST inspections and to review 10CFR50.55a Requests.
Regarding periodic changes, NUREG 1482, Revision 1, Section 2.6, "Program Documents," specifies that between a licensee's 10-year interval program submittal, the NRC would like to receive up-to-date program documents when the licensee makes significant changes to the IST program to facilitate these regulatory activities. As long as the IST program is consistent with the regulations, ASME Code relief is not required.
That is, deletions from or additions to the'IST program do not necessarily require NRC approval. The burden is on each licensee to verify that its IST program is complete and includes all components that require IST, and that all such components are tested to the extent practical. If a licensee deletes a particular component from its IST program, the staff recommends that the licensee should document the reason in an appropriate place.
The staff expects each licensee to maintain its IST program up-to-date and ensure that it remains consistent with changes in plant configuration. If a particular relief request is no longer required because of changes in hardware, system design, or new technology, the licensee is expected to revise its program to withdraw the relief request. Conversely, if a system modification results in the addition of a component to the IST program, the licensee should ensure that it meets the Code requirements or the provisions of GL 89-04, or that a relief request is submitted for NRC review and approval, as appropriate.
This program plan document establishes the requirements which have been translated into implementing (surveillance) procedures for inservice testing and evaluation of Class 1, 2, and 3 pumps and valves. Additionally, using the guidance in NUREG 1482, Revision 1, certain other pumps and valves not required to be classified as Class 1, 2, and 3, but which perform a specific function required to bring the reactor from any operating mode to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident, are also included.
2.0 REGULATORY BASIS Code of Federal Regulations, Title 10, Section 50.55a (10CFR50.55a), "Codes and Standards," states requirements for IST of certain safety-related pumps and valves.
These components are required to be tested according to the requirements of Operation and Maintenance of Nuclear Power Plants, ASME OM Code-2001 Edition through the 2003 Addenda. The testing is intended to assess operational readiness of components.
The tests conducted during the initial and successive 120-month intervals are to be based on the requirements in the applicable edition and addenda of the Code, to the extent
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 5 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 practical, within the limitations of design, geometry, and materials of construction, as.
described in 10 CFR50.55a(f)(4).
10 CFR50.55a(f)(4)(ii) requires that IST in each 120-month interval following the initial interval be conducted in compliance with the requirements of the latest edition and addenda of the Code incorporated by reference in 10CFR50.55a(b), in effect 12 months before the start of the interval. Pursuant to 10CFR50.55a(f)(4)(iv), IST may meet the requirements of subsequent editions and addenda incorporated by paragraph (b) or portions of a revised edition. When portions of a revised edition are used, all related requirements of the respective editions or addenda must be met and approval of the NRC obtained as clarified by RIS-04-012 dated 7/28/2004.
The NRC may authorize alternatives to Code testing requirements submitted as 10CFR50.55a requests, or submitted in a similar format that includes a description of the requirements, a description of the proposed alternative, and the justification for approval of the alternative. 10CFR50.55a(a)(3)(i) allows the NRC to authorize alternatives if the proposed alternatives would provide an acceptable level of quality and safety. The NRC will normally approve an alternative pursuant to this provision only if the licensee proposes a method of testing that is an equivalent method, or an improvement, to the Code method, or if the testing will comply or is consistent with the later Code editions approved by NRC in 1 OCFR50.55a(b). Where plant design makes the testing of certain components complicated or impossible, an alternate method of testing is documented in a 1 OCFR50.55a Request.
The Palo Verde Nuclear Generating Station (PVNGS) Inservice Testing Program for Pumps and Valves was developed in accordance with the requirements of ASME OM Code-2001, (Subsections ISTA, ISTB, ISTC, Mandatory Appendix I and Mandatory Appendix II) including subsequent changes in the ASME OMb Code-2003 Addenda.
The components were classified and categorized in accordance with the Code of Record with test requirements and intervals assigned accordingly. Technical Specification, UFSAR and other licensing commitments were referenced during the assignment of test intervals. Additional guidance for the development of the PVNGS Inservice Testing Program was obtained from NUREG 1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants."
The 1 OCFR50 Appendix J Program for Primary Containment Testing at Palo Verde Nuclear Generating Station is in compliance with the requirements of Option B of IOCFR50 Appendix J, Regulatory Guide 1.163, September 1995, NEI 94-01 Revision 0, July 1995 and Station Technical Specifications.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 6 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 3.0 OM CODE CASE ACCEPTABILITY 3.1 ISTA-3130 Application of Code Cases (a)
Code Cases to be used during a preservice or inservice test or examination shall be identified in the test plan.
(b)
Code Cases shall be applicable to the edition and addenda specified in the test plan.
(c)
Code Cases shall be in effect at the time the test plan is filed, except as provided in ISTA-3130(d).
(d)
Code Cases issued subsequent to filing the test plan may be proposed for use in amendments to the test plan.
3.2 NUREG 1482, Revision 1, Section 2.1.1, ASME Code Case Applicability If a licensee would like to use an ASME Code Case with a Edition or Addendum of the ASME Code to which it is not applicable, the licensee has the following options:
- a. Have the alternative to use the Code Case, beyond its stated applicability, authorized by the NRC pursuant to 1 OCFR50.55a(a)(3),
- b. If the Code Case is applicable to an Edition or Addendum of the ASME Code later than the version of the Code being used by the licensee, the licensee could update to the later version of the Code pursuant to 10CFR50.55a(f)(4)(iv) or (g)(4)(iv) and then use the Code Case, provided the Code Case has been approved for use in the appropriate Regulatory Guide and incorporated by reference into, 10CFR50.55a. Note that the later version of the ASME Code must also have been incorporated by reference into 10CFR50.55a, the licensee must update all related requirements of the respective Edition or Addenda; and the update must be specifically approved by the Commission.
Licensee should not use ASME Code Cases with Editions and Addenda of the ASME Code to which they do not apply and that are not specifically approved for use by the NRC. More specifically, licensees should not "reconcile" the Applicability of Code Cases without consulting with the applicable ASME Code Committee.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 7 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 3.3 Regultory Guide 1.192 Introduction and Discussion Regulatory guide 1.192 identifies the Code Cases that have been determined by the NRC to be acceptable alternatives to applicable parts of the OM Code.
These Code Cases may be used by licensees, without request to the NRC, provided they are used with any identified limitations or modifications.
(SEE ABOVE OM ISTA-3130(b) REQUIREMENT,; i.e., THE CODE CASE MUST BE APPLICABLE TO THE EDITION AND ADDENDA SPECIFIED IN THE TEST PLAN. PER NUREG 1482, A UTHORIZA TION IS REQUIRED WHEN USING CODE CASES BEYOND THEIR STA TED APPLICABILITY)
OM Code Cases not yet endorsed by the NRC may be implemented through 10CFR50.55a(a)(3), which permits the use of alternatives to the Code requirements referenced in 10CFR50.55a provided the proposed alternatives result in an acceptable level of quality and safety and provided their use is authorized by the Director of the Office of Nuclear Reactor Regulation.
Regulatory Guide 1.192, Appendix A lists the OM Code edition or addenda for each Code Case, with the date of approval by the ASME Board on Nuclear Codes and Standards. Appendix B is a numerical listing of the OM Code Cases.
Table 1, "Acceptable OM Code Cases," lists the Code Cases that are acceptable to the NRC for implementation in the IST of lightwater cooled nuclear power plants.
Table 2, "Conditionally Acceptable OM Code Cases," lists the Code Cases that are acceptable provided they are used with the identified limitations or modifications, i.e., the Code Case is generally acceptable but the NRC has determined that the alternative requirements must be supplemented in order to provide an acceptable level of quality and safety.
OM Code Cases that the NRC has determined to be unacceptable are listed in Regulatory Guide 1.193, "ASME Code Cases Not Approved for Use."
With regard to the use of any Code Case, it is the responsibility of the user to make certain that the provisions of the Code Case do not conflict with regulatory requirements or licensee commitments.
3.4 Code Cases Selected for use at Palo Verde As documented in 10CFR50.55a Request VRR-01, as an alternative to the rules of OM Code ISTC to assess the operational readiness of certain electric motor-
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 8 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 operated valves, PVNGS adopts the alternative test requirements specified in Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants OM-1995, Subsection ISTC," including the associated additional requirements specified in RG 1.192.
4.0 PROGRAM DEVELOPMENT The IST Program covers components in ASME Code Class systems and a limited number of Non-ASME Code Class systems. Components included in the IST Program are those whose specific functions are required to bring the reactor from any operating mode to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.
ASME Class 1, 2 and 3 piping and components are identified on the PVNGS Piping and Instrument Diagrams (P&ID's). The P&ID's were reviewed to identify systems or portions of systems that are Code Class 1, 2, or 3. P&ID's containing Class 1, 2, or 3 plant pumps and valves or other pumps and valves with safety functions that require testing are identified in the Component Tables. Each Class 1, 2, and 3 component was reviewed to determine which require testing to satisfy the scope requirements of ASME OM Code-2001, including subsequent changes through the ASME OMb Code-2003 Addenda, Subsection ISTA, "General Requirements", Article ISTA-1000, "Introduction",
Subarticle ISTA-1100,"Scope".
After all systems or portions of systems containing pumps and valves within the scope of the IST Program were identified, the safety function(s) for each component was determined. The safety function of each component is identified and documented in a computerized database. The references used in these determinations are also recorded and include the UFSAR, Technical Specifications, and other design basis documents. IST categories per ASME OM Code-2001, including subsequent changes through the ASME OMb Code-2003 Addenda are also identified. In cases where an interpretation of the ASME OM Code or applicable regulations was necessary, the interpretation was documented in a plant-specific Technical Position. These Technical Positions are documented in procedure 73DP-9XI02, "Pump and Valve Inservice Testing Program -
Administrative Requirements."
Where the testing of certain plant components is not possible during normal plant operation, an alternate testing schedule is documented in a Cold Shutdown Justification.
Where the testing of certain plant components is not possible during a cold shutdown, an alternate testing schedule is documented in a Refueling Outage Justification. Where plant design makes the testing of certain components complicated or impossible, an alternate method of testing is documented in a 10CFR50.55a Request.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 9 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Components failing to meet test requirements will be dispositioned by the Plant's Corrective Action program. Specific responsibilities are defined in the Plant procedures.
5.0 COMPONENT TABLES The IST Program is comprised of component tables for pumps and valves followed by any associated code deviations referred to as Cold Shutdown Justifications, Refueling Outage Justifications and 10CFR50.55a Requests. Lastly, for ease of table and program interpretation, this document contains the table notes, pump table legend, valve table legend, accompanying definitions and associated abbreviations. This information is located at the end of the document.
6.0 REFERENCES
6.1 Implementing References
" 73DP-9XI02, "Pump and Valve Inservice Testing Program - Administrative Requirements"
- Surveillance test procedures as listed in the Pump Table and Valve Component Tables
- 73DP-9CL02, Containment Leakage Rate Testing Program
- 73DP-9XI05, Check Valve Condition Monitoring Program
- 73DP-0X103, Check Valve Predictive Maintenance And Monitoring Program
- 39DP-9ZZ03, Motor-Operated Valve Program
" 73DP-9ZZ02, Air-Operated Valve Program
" 73TI-9XI01, Vibration Data Collection for Surveillance Tests 6.2 Developmental References
- Developmental references for the Pump and Valve IST Program are listed in 73DP-9XI02
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 10 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Pump ID /
Pump Code Drawing Description Cat.
Class Coord.
Speed Press Flow Vib Procedure Remarks AFA-P01 B
3 AFP-001 QTR QTR PRR-01 Not 73ST-9AF02 Group B Essential Auxiliary Horiz.
D06 Required Min flow Feedwater Pump Cent.
(Turbine-Driven) 8-Stage 2YR 2YR 2YR 2YR 73.T-9AF04 CPT - Full-flow test AFB-PO1 B
3 AFP-001 NA QTR PRR-01 Not 73ST-9AF03 Group B Essential Auxiliary Horiz.
B06 Required Min flow Feedwater Pump Cent.
(Motor-Driven) 8-Stage NA 2YR 2YR 2YR 73ST-9AF05 CPT - Full-flow test
{
t r
- e ).....
8 -s..a.g.............
A....................
....7 7...R.....
................... 2 Y
.Y
.7.S.T
.9...5............
C.
.PT
!.-f
. w. t s AFN-P01 N
N AFP-001 NA QTR Not QTR 73ST-9AFO1 Augmented, tested Non-Class Horiz.
H06 Measured pursuant to SR 3.7.5.2 Auxiliary Cent.
Fixed Feedwater Pump 8-Stage Flow No Comprehensive (Motor-Driven)
Test performed.
CHA-PO1 A
2 ClP-002 NA QTR QTR PRR-06 73ST-9CH06 Group A Test Charging Pump 3-Cyl B03 Pos.
NA 2YR 2YR 2YR 73ST-9CH02 CPT - Full-flow test CHB-PO0 A
2 CHP-002 NA QTR QTR PRR-06 73ST-9CH06 Group A Test Charging Pump 3-Cyl D03 Pos.
NA 2YR 2YR 2YR 73ST-9CH02 CPT - Full-flow test CHE-PO1 A
2 CHP-002 NA QTR QTR PRR-06 73ST-9CH06 Group A Test Charging Pump 3-Cyl G03 Pos.
NA 2YR 2YR 2YR 73ST-9CH02 CPT - Full-flow test Displ.
CTA-P01 A
3 CTP-001 NA QTR QTR QTR 73ST-9CTOI Group A Test Condensate Horiz.
C05 Transfer Pump Cent.
1-Stamge _.NA 2YR 2YR 2YR 73ST-9CT02 CPT - Full-flow test CTB-P01 A
3 CTP-001 NA QTR QTR QTR 73ST-9CTO0 Group A Test Condensate Horiz.
B05 Transfer Pump Cent.
1-Stage NA 2YR 2YR 2YR 73ST-9CT02 CPT - Full-flow test DFA-P01 B
3 DFP-001 NA QTR QTR NA*
73ST-9DFOI Group B Test Diesel Generator Horiz.
B06 Fuel Oil Transfer Cent.
- Submerged - no Pump I-Stage accessible bearings.
NA PRR-02 2YR NA*
73ST-9DF02 CPT - Full-flow test DFB-P01 B
3 DFP-001 NA QTR QTR NA*
73ST-9DFO0 Group B Test Diesel Generator Horiz.
B02 Fuel Oil Transfer Cent.
- Submerged - no Pump I-Stage accessible bearings NA PRR-02 2YR NA*
73ST-9DF02 CPT - Full-flow test ECA-P01 A
3 ECP-001 NA QTR QTR QTR 73ST-9ECOI Group A Test Essential Chilled Horiz.
B08 Water Circulation Cent.
NA 2YR 2YR 2YR 73ST-9EC02 CPT - Full-flow test Pump I -Stage ECB-P01 A
3 ECP-001 NA QTR QTR QTR 73ST-9ECOI Group A Test Essential Chilled Horiz.
B04 Water Circulation Cent.
NA 2YR 2YR 2YR 73ST-9EC02 CPT - Full-flow test Pump 1-Stage I
I I
I I
II
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 11 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Pump ID /
Pump Code Drawing Description Cat.
Class Coord.
Speed Press Flow Vib Procedure Remarks EWA-P01 A
3 EWP-00I NA QTR QTR QTR 73ST-9EWO1 Group A Test Essential Cooling Horiz.
E06 Water Pump Cent.
NA 2YR 2YR 2YR 73ST-9EW02 CPT - Full-flow test a............................
I -s t g e EWB-P01 A
3 EWP-001 NA QTR QTR QTR 73ST-9EWO0 Group.A Test Essential Cooling Horiz.
E02 Water Pump Cent.
NA 2YR 2YR 2YR 73ST-9EW02 CPT - Full-flow test I-Stage PCA-PO1 A
3 PCP-001 NA QTR QTR QTR 73ST-9PCOI Group A Test Spent Fuel Pool Horiz.
D15 Cooling Pump Cent.
NA 2YR 2YR 2YR 73ST-9PC02 CPT - Full-flow test
..... ta g e PCB-POI A
3 PCP-001 NA QTR QTR QTR 73ST-9PCOI Group A Test Spent Fuel Pool Horiz.
B 15 Cooling Pump Cent.
NA 2YR 2YR 2YR 73ST-9PC02 CPT - Full-flow test I-Stage SIA-P01 A
2 SIP-001 NA QTR PRR-03 QTR 73ST-9S11 Group A Test Low Pressure Vert.
Fl1 Min Flow Safety Injection Cent.
(LPSI) Pump-
_ -Stage NA 2YR 2YR 2YR 73ST-9SI14 CPT - Full-flow test SIB-POI A
2 SIP-001 NA QTR PRR-03 QTR 73ST-9SI11i Group A Test Low Pressure Vert.
B 11 Min Flow Safety Injection Cent.
(LPSI) Pump I-Stage NA 2YR 2YR 2YR 73ST-9SI14 CPT - Full-flow test SIA-P02 B
2 SIP-001 NA QTR PRR-04 Not 73ST-9SI10 Group B Test High Pressure Horiz.
El I Required Min Flow Safety Injection Cent.
_HPSI)PumR 8-Stage NA 2YR 2YR 2YR 73ST-9XI33 CPT - Full-flow test SIB-P02 B
2 SIP-001 NA QTR PRR-04 Not 73ST-9SI10 Group B Test High Pressure Horiz.
Al I Required Min Flow Safety Injection Cent.
(HPSI) Pump 8-Stage NA 2YR 2YR 2YR 73sT-9XI33 CPT - Full-flow test SIA-P03 A
2 SIP-001 NA QTR PRR-05 QTR 73ST-9SI06 Group A Test Containment Spray Vert.
H 11 Min Flow Pump Cent.
I-Stage NA 2YR 2YR 2YR 73ST-9SI15 CPT - Full-flow test SEB-P03 A
2 SIP-001 NA QTR PRR-05 QTR 73ST-9SI06 Group A Test Containment Spray Vert.
CI1 Min Flow Pump Cent.
I-Stage NA 2YR 2YR 2YR 73ST-9SI15 CPT - Full-flow test SPA-POI A
3 SPP-001 NA QTR QTR QTR 73ST-9SP01 Group A Test Essential Spray Vert.
Sh. I Pond Pump Line C04 2YR 2YR 2YR 73ST-9SP02 CPT - Full-flow test
._+/-yert. Line Shaft)
Shaft SPB-P01 A
3 SPP-001 NA QTR QTR QTR 73ST-9SP01 Group A Test Essential Spray Vert.
Sh. 1 Pond Pump Line C07 2YR 2YR 2YR 73ST-9SP02 CPT - Full-flow test (Vert. Line Shaft)
Shaft
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 12 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 2
Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks AFAV007 AFP-001 8
C BDC CMP 73ST-9AF04 Notes 1,2, 3, 4 TURBINE-DRIVEN AFW PUMP SUCTION D07 CK ACTIVE CVO CMP 73ST-9AF04 CHECK VALVE FROM CONDENSATE 3
SA 0
STORAGE TANK AFAV015 AFP-001 6
C CVC QTR 73ST-9AF02 Notes 1,2, 3 TURBINE-DRIVEN AUXILIARY E05 CK ACTIVE CVO CSD 73ST-9AF02 CSJ-01 FEEDWATER PUMP DISCHARGE CHECK 3
SA O/C VALVE AFBV022 AFP-001 8
C BDC CMP 73ST-9AF05 Notes 1,2, 3, 4 MOTOR-DRIVEN AFW PUMP SUCTION C07 CK ACTIVE CVO CMP 73ST-9AF05 CHECK VALVE FROM CONDENSATE 3
SA 0
STORAGE TANK AFBV024 AFP-001 6
C CVC QTR 73ST-9AF03 Notes 1,2, 3 MOTOR-DRIVEN AUXILIARY FEEDWATER C05 CK ACTIVE CVO CSD 73ST-9AF05 CSJ-01 PUMP DISCHARGE CHECK VALVE 3
SA O/C AFBHV0030 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRA/RA MOTOR-DRIVEN AFW PUMP TO SG #1 804 GL ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 FLOW CONTROL VALVE 3MO
/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFBHV0031 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRA/RA MOTOR-DRIVEN AFW PUMP TO SG #2 B04 GL ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 FLOW CONTROL VALVE 3
MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFAHV0032 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRA/RA TURBINE-DRIVEN AFW PUMP TO SG #1 D04 GL ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 FLOW CONTROL VALVE 3
MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFCHV0033 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRA/RA TURBINE-DRIVEN AFW PUMP TO SG #2 C04 GL ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 FLOW CONTROL VALVE 3
MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFBUVO034 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRN/RA MOTOR-DRIVEN AFW PUMP TO SG #1 B03 GA ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE (PEN. 75) 2 MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFBUVO035 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note5 QTR FS FOR PRNIRA MOTOR-DRIVEN AFW PUMP TO SG #2 C03 GA ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE (PEN. 76) 2 MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9X[05 VRR-01 AFCUVO036 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note5 QTR FS FOR PRA/RA TURBINE-DRIVEN AFW PUMP TO SG #1 D03 GA ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE (PEN. 75) 2 MO O/C STC 18M 73ST-9XI05 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFAUVO037 AFP-001 6
B FSC QTR 73ST-9XI05 VRR-01 Note 5 QTR FS FOR PRA/RA TURBINE-DRIVEN AFW PUMP TO SG #2 D03 GA ACTIVE FSO QTR 73ST-9XI05 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE (PEN. 76) 2 MO O/C STC 18M 73ST-9X105 VRR-01 STO 18M 73ST-9XI05 VRR-01 AFAHV0054 AFP-001 4
B FSO QTR 73ST-9AF02 VRR-01 Note 5 TURBINE-DRIVEN AFW PUMP G04 GL ACTIVE QTR FS FOR PRNRA TRIP/THROTTLE VALVE N
MO 0
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 13 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Reviion AND COMPONENT TABLES 2
Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks AFAV079 AFP-001 6
C CVC CSD 73ST-9AF04 Notes 1, 2, 3. Also exercised AFW TO SG #1 CHECK VALVE (PEN. 75)
E02 CK ACTIVE CVO CSD 73ST-9AF04 CSJ-02 open in 73ST-9AF05.
2 SA O/C AFBV080 AFP-001 6
C CVC CSD 73ST-9AF05 Notes 1,2, 3. Also exercised AFW TO SG #2 CHECK VALVE (PEN. 76)
C02 CK ACTIVE CVO CSD 73ST-9AF05 CSJ-02 open in 73ST-9AF05.
2 SA O/C AFAV096 AFP-001 4
C BDO CMP 40OP-9AF01 Notes 1,2, 3, 4 AUX STEAM SUPPLY CHECK VALVE TO G02 CK ACTIVE CVC CMP 73ST-9X136 AFW TURBINE 3
SA C
AFBPSVO106 AFP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR B03 SV ACTIVE AFBUV0034 BONNET(PEN. 75) 2 SA O/C AFBPSVO107 AFP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR C03 SV ACTIVE AFBUVO035 BONNET (PEN. 76) 2 SA O/C AFAPSV0108 AFP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR D03 SV ACTIVE AFCUVO036 BONNET (PEN. 75) 2 SA O/C AFAPSVO109 AFP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR D03 SV ACTIVE AFAUVO037 BONNET (PEN. 76) 2 SA O/C AFAV137 AFP-001 6
C BDC CMP 73ST-9AF04 Notes 1,2, 3, 4 TURBINE DRIVEN AFW PUMP D06 CK ACTIVE CVO CMP 73ST-9AF04 DISCHARGE CHECK VALVE 3
SA 0
AFBV138 AFP-001 6
C BDC CMP 73ST-9AF05 Notes 1,2, 3, 4 MOTOR DRIVEN AFW DISCHARGE CHECK C06 CK ACTIVE CVO CMP 73ST-9AF05 VALVE 3
SA 0
CHEVM70 CHP-001 3
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 CHARGING TO REGENERATIVE HEAT F15 CK ACTIVE CVC CMP 73ST-9CLO1 EXCHANGER INLET INBOARD CIV (PEN.
2 SA O/C
- 41)
CVO CMP 73ST-9CH06 CHNVI44 CHP-002 3
B FSC 2YR 73ST-9XI44 MANUAL ISOLATION VALVE FROM RWT B14 DI ACTIVE FSO 2YR 73ST-9XI44 TO SPENT FUEL POOL CLEANUP PUMPS 3
MA O/C CHNV154 CHP-002 3
C BDC CMP 40ST-9CH04 Notes 1,2, 3, 4 BORIC ACID MAKEUP PUMP DISCHARGE B13 CK ACTIVE CVO CMP 40ST-9CH04 CHECK VALVE 3
SA 0
CHNV155 CHP-002 3
C BDC CMP 40ST-9CH04 Notes 1,2, 3, 4 BORIC ACID MAKEUP PUMP DISCHARGE B13 CK ACTIVE CVO CMP 40ST-9CH04 CHECK VALVE 3
SA 0
CHNV164 CHP-002 3
B FSO 2YR 73ST-9XI45 BORIC ACID MAKEUP FILTER BYPASS D11 DI ACTIVE LINE ISOLATION VALVE 3
MA 0
CHAV177 CHP-002 3
C BDC CMP 40ST-9CH04 Notes 1,2, 3, 4 BORIC ACID MAKEUP CHECK VALVE TO B07 CK ACTIVE CVO CMP 40ST-9CH04 VCT OUTLET 2
SA 0
CHAV190 CHP-002 3
C BDC CMP 40ST-9CH04 Notes 1,2, 3, 4 RWT TO CHARGING PUMP SUCTION A07 CK ACTIVE CVO CMP 40ST-9CH04 CHECK VALVE 2
SA 0
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 14 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 I
Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID CoordlSht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks CHBHV0203 CHP-001 2
B FSC CSD 73ST-9XI22 CSJ-03 Cycled every 18 months per TRM AUXILIARY PRESSURIZER SPRAY VALVE H10 GL ACTIVE FSO CSD 73ST-9XI22 CSJ-03 TSR 3.4.100.3 1
so O/C FTC CSD 73ST-9XI22 CSJ-03 STC CSD 73ST-9XI22 CSJ-03 STO CSD 73ST-9XI22 CSJ-03 VP 2YR 73ST-9X127 CHAHV0205 CHP-001 2
B FSC CSD 73ST-9XI22 CSJ-03 Cycled every 18 months per TRM AUXILIARY PRESSURIZER SPRAY VALVE Hi1 GL ACTIVE FSO CSD 73ST-9XI22 CSJ-03 TSR 3.4.100.3 1
so O/C FTC CSD 73ST-9XI22 CSJ-03 STC CSD 73ST-9XI22 CSJ-03 STO CSD 73ST-9X122 CSJ-03 VP 2YR 73ST-9XI27 CHEHV0239 CHP-001 2
B FSC QTR 73ST-9X106 NORMAL CHARGING FLOWPATH Gl1 GL ACTIVE FTC QTR 73ST-9XI06 ISOLATION VALVE 2
AO O/C STC QTR 73ST-9XI06 VP 2YR 73ST-9X106 CHEPDV0240 CHP-001 2
B FSC QTR 73ST-9XI06 NORMAL CHARGING FLOWPATH Gl1 GL ACTIVE FTC QTR 73ST-9XI06 ISOLATION VALVE 1
AO O/C STC QTR 73ST-9XI06 VP 2YR 73ST-9X106 CHBHV0255 CHP-001 1.5 A
AJ CLR 73ST-9CLO1 Note 5 RCP SEAL INJECTION OUTBOARD CIV G04 GL ACTIVE FSC 1CY 73ST-9X122 VRR-01 (PEN. 72) 2 MO C
CHBV305 CHP-002 20 C
CVC CMP 73ST-9XI39 Notes 1, 2, 3, 4 REFUELING WATER TANK OUTLET B15 CK ACTIVE CVO CMP 73ST-9S111 CHECK VALVE TO SI SUCTION HEADER 2
SA O/C CHAV306 CHP-002 20 C
CVC CMP 73ST-9XI39 Notes 1,2, 3, 4 REFUELING WATER TANK OUTLET C13 CK ACTIVE CVO CMP 73ST-9SI11 CHECK VALVE TO SI SUCTION HEADER 2
SA O/C CHAPSV0315 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 CHARGING PUMP SUCTION PRESSURE C05 SV ACTIVE RELIEF VALVE 2
SA O/C CHAV316 CHP-002 4
B FSC 2YR 73ST-9XI44 CHARGING PUMP CHA-p01 NORMAL B05 DI ACTIVE FSO 2YR 73ST-9XI44 SUCTION FROM VCT MANUAL ISOLATION 2
MA O/C VALVE CHBPSV0318 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve CHARGING PUMP SUCTION PRESSURE F05 SV ACTIVE RELIEF VALVE 2
SA O/C CHBV319 CHP-002 4
B FSC 2YR 73ST-9XI45 CHARGING PUMP CHB-P01 NORMAL D05 DI ACTIVE FSO 2YR 73ST-9X145 SUCTION FROM VCT MANUAL ISOLATION 2
MA O/C VALVE CHEPSV0321 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 CHARGING PUMP SUCTION PRESSURE H05 SV ACTIVE RELIEF VALVE 2
SA O/C CHEV322 CHP-002 4
B FSC 2YR 73ST-9XI44 CHARGING PUMP CHE-p01 NORMAL G05 DI ACTIVE FSO 2YR 73ST-9X144 SUCTION FROM VCT MANUAL ISOLATION 2
MA O/C VALVE CHEPSV0324 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 CHARGING PUMP DISCHARGE G02 SV ACTIVE PRESSURE RELIEF VALVE 2
SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 15 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks CHBPSV0325 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 CHARGING PUMP DISCHARGE E02 SV ACTIVE PRESSURE RELIEF VALVE 2
SA O/C CHAPSV0326 CHP-002 0.75 C
SV 10Y 73ST-9ZZ20 CHARGING PUMP DISCHARGE C02 SV ACTIVE PRESSURE RELIEF VALVE 2
SA O/C CHBV327 CHP-002 3
B FSC 2YR 73ST-9XI45 CHARGING PUMP ALTERNATE SUCTION E05 DI ACTIVE FSO 2YR 73ST-9X145 COMMON ISOLATION VALVE 2
MA O/C CHAV328 CHP-002 2
C BDC QTR 73ST-9CH06 Notes 1,2, 3 CHARGING PUMP CHA-P01 DISCHARGE B02 CK ACTIVE CVO QTR 73ST-9CH06 CHECK VALVE 2
SA 0
CHBV331 CHP-002 2
C BDC QTR 73ST-9CH06 Notes 1,2, 3 CHARGING PUMP CHB-P01 DISCHARGE E02 CK ACTIVE CVO QTR 73ST-9CH06 CHECK VALVE 2
SA 0
CHEV334 CHP-002 2
C BDC QTR 73ST-9CH06 Notes 1,2, 3 CHARGING PUMP CHE-P01 DISCHARGE G02 CK ACTIVE CVO QTR 73ST-9CH06 CHECK VALVE 2
SA 0
CHEV429 CHP-001 2
C BDC CMP 73ST-9ZZ25 Notes 1,2, 3, 4 COMMON CHARGING LINE TO D16 CK ACTIVE CVO CMP 40OP-90OP05 REGENERATIVE HEAT EXCHANGER 2
SA 0
CHECK VALVE CHEV431 CHP-001 2
C BDC CMP 73ST-9ZZ25 Notes 1,2, 3, 4 PRESSURIZER AUXILIARY SPRAY CHECK G09 CK ACTIVE CVO CMP 73ST-9XI27 VALVE 1
SA 0
CHEV433 CHP-001 2
C BDC CMP 73ST-9ZZ25 Notes 1,2, 3, 4 CHARGING LINE CHECK VALVE TO RCS G09 CK ACTIVE CVO CMP 40OP-90OP05 1
SA 0
CHEV435 CHP-001 2
C BDC CMP 73ST-9ZZ25 Notes 1,2, 3, 4 REGENERATIVE HEAT EXCHANGER Fll CK ACTIVE CVO CMP 73ST-9CH06 OUTLET CHECK VALVE 1
SA 0
CHEV494 CHP-003 1.5 AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 REACTOR MAKEUP WATER SUPPLY E15 CK ACTIVE BDO CMP 40OP-9CH01 CHECK VALVE TO RDT INBOARD CIV 2
SA C
(PEN. 45)
CVC CMP 73ST-9CL01 CHNUV0501 CHP-002 4
B FSC 1CY 73ST-9XI22 VRR-01 Note 5 VOLUME CONTROL TANK OUTLET C07 GA ACTIVE ISOLATION VALVE 2
MO C
CHBUV0505 CHP-002 1
A AJ CLR 73ST-9CL01 REACTOR COOLANT SEAL BLEED-OFF H13 GL ACTIVE FSC RFO 73ST-9XI22 ROJ-02 OUTBOARD CIV (PEN. 43) 2 AO C
FTC RFO 73ST-9XI22 ROJ-02 STC RFO 73ST-9XI22 ROJ-02 VP 2YR 73ST-9XI22 CHAUVO506 CHP-002 1
A AJ CLR 73ST-9CLO1 REACTOR COOLANT SEAL BLEED-OFF H14 GL ACTIVE FSC RFO 73ST-9X122 ROJ-02 INBOARD CIV (PEN. 43) 2 AO C
FTC RFO 73ST-9XI22 ROJ-02 STC RFO 73ST-9X122 ROJ-02 VP 2YR 73ST-9XI22 CHNUV0514 CHP-002 3
B FSO 1CY 73ST-9XI06 VRR-01 Note5 BORIC ACID MAKEUP TO CHARGING B10 GL ACTIVE PUMP SUCTION ISOLATION VALVE 3
MO 0
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CsJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks CHBUV0515 CHP-001 2
B FSC CSD 73ST-9XI22 CSJ-04 LETDOWN ISOLATION VALVE H15 GL ACTIVE FTC CSD 73ST-9XI22 CSJ-04 1
AD C
STC CSD 73ST-9XI22 CSJ-04 VP 2YR 73ST-9XI22 CHAUV0516 CHP-001 2
A AJ CLR 73ST-9CL01 LETDOWN INBOARD CIV (PEN. 40)
H15 GL ACTIVE FSC CSD 73ST-9XI22 CSJ-04 1
AO C
FTC CSD 73ST-9XI22 CSJ-04 STC CSD 73ST-9XI22 CSJ-04 VP 2YR 73ST-9X122 CHBUV0523 CHP-001 2
A AJ CLR 73ST-9CLO1 LETDOWN FROM REGENERATIVE HEAT F13 GL ACTIVE FSC CSD 73ST-9XI22 CSJ-04 EXCHANGER OUTBOARD CIV (PEN. 40) 2 AO C
FTC CSD 73ST-9X122 CSJ-04 STC CSD 73ST-9XI22 CSJ-04 VP 2YR 73ST-9X122 CHAHV0524 CHP-O01 2
B AJ CLR 73ST-9CLO1 Note 5 CHARGING LINE OUTBOARD CIV (PEN. 41)
D16 GL PASSIVE NO EXERCISE REQ'T -
2 MO O
PASSIVE VALVE (NO PRA OR TS 3.3.5.4 REQ'TS FOR THIS MOV).
Open w/power removed - no VP test required.
CHNUV0527 CHP-002 3
B FSC QTR 73ST-9XI06 MAKEUP TO CHARGING VCT BYPASS B08 GA ACTIVE FTC QTR 73ST-9XI06 ISOLATION VALVE 3
AD C
STC QTR 73ST-9X106 VP 2YR 73ST-9X106 CHBHV0530 CHP-002 20 B
FSC QTR 73ST-9X104 VRR-01 Note 5 REFUELING WATER TANK OUTLET C15 GA ACTIVE FSO QTR 73ST-9X104 VRR-01 QTR FS FOR PRA/RA ISOLATION VALVE 2
MO O/C CHAHV0531 CHP-002 20 B
FSC QTR 73ST-9XI03 VRR-01 Note 5 REFUELING WATER TANK OUTLET C14 GA ACTIVE FSO QTR 73ST-9XI03 VRR-01 QTR FS FOR PRA/RA ISOLATION VALVE 2
MO O/C CHEHV0532 CHP-002 3
B FSC 2YR 73ST-9XI22 Treated as a manual valve, air ISOLATION FOR REFUELING WATER E16 GL ACTIVE FSO 2YR 73ST-9X122 operator is not used for normal or TANK TO BORIC ACID MAKEUP PUMPS 2
AO O/C emergency operation.
TANKTO BRICVP~
2YR 73ST-9XI22 CHEHV0536 CHP-002 3
B FSO 1CY 73ST-9XI22 VRR-01 Note 5 REFUELING WATER TANK TO CHARGING A14 GL ACTIVE PUMP SUCTION ISOLATION VALVE 3
MO 0
CHAUV0560 CHP-003 3
A AJ CLR 73ST-9CLO1 REACTOR DRAIN TANK OUTLET INBOARD B15 GL ACTIVE FSC QTR 73ST-9XI06 CIV (PEN. 44) 2 AO C
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9X106 CHBUV0561 CHP-003 3
A AJ CLR 73ST-9CLO1 REACTOR DRAIN TANK INBOARD CIV A15 GL ACTIVE FSC QTR 73ST-9X106 (PEN. 44) 2 AO C
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9X106 CHAUV0580 CHP-003 1.5 A
AJ CLR 73ST-9CLO1 REACTOR MAKEUP WATER TO RDT F14 GA ACTIVE FSC QTR 73ST-9X106 OUTBOARD CIV (PEN. 45) 2 AO C
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9X106
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 17 of 100 Revision PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 21 AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks CHAUV0715 CHP-003 0.5 A
AJ CLR 73ST-9CLO1 PASS TO RDT CIV (PEN. 45)
E13 GL ACTIVE FSC QTR 73ST-9XI06 2
so C
FTC QTR 73ST-9XI06 STC QTR 73ST-9XI06 VP 2YR 73ST-9XI06 CHAV755 CHP-002 3
B FSC 2YR 73ST-9X144 CHARGING PUMP CHA-P01 ALTERNATE C05 DI ACTIVE FSO 2YR 73ST-9X144 SUCTION MANUAL ISOLATION VALVE 2
MA O/C CHBV756 CHP-002 3
B FSC 2YR 73ST-9XI45 CHARGING PUMP CHB-P01 ALTERNATE D05 DI ACTIVE FSO 2YR 73ST-9X145 SUCTION MANUAL ISOLATION VALVE 2
MA O/C CHEV757 CHP-002 3
B FSC 2YR 73ST-9XI44 CHARGING PUMP CHE-P01 ALTERNATE F05 DI ACTIVE FSO 2YR 73ST-9XI44 SUCTION MANUAL ISOLATION VALVE 2
MA O/C CHNV835 CHP-001 1.5 AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 RCP SEAL INJECTION SUPPLY LINE G03 CK ACTIVE BDO CMP 40DP-9OP05 CHECK VALVE (PEN. 72) 2 SA C
CVC CMP 73ST-9CLO1 CHEV854 CHP-001 0.75 A
AJ CLR 73ST-9CLO1 CHARGING LINE CHEMICAL ADDITION E15 GL PASSIVE ISOLATION VALVE (PEN. 41) 2 MA C
CHBUV0924 CHP-001 0.5 A
AJ CLR 73ST-9CLO1 LETDOWN TO PASS CIV (PEN. 40)
E14 GL ACTIVE FSC QTR 73ST-9X106 2
so C
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9X106 CPBUVO003A CPP-O01 42 B
FSC RFO 73ST-9XI23 ROJ-01 Note 5 Note 6 CONTAINMENT REFUELING PURGE D05 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M STC REQ'D FOR TS 3.3.5.4 SUPPLY INBOARD CIV (PEN. 56) 2 MO C
CPBUVO003B CPP-001 42 B
FSC RFO 73ST-9X123 ROJ-01 Note 5 Note6 CONTAINMENT REFUELING PURGE E02 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M STC REQ'D FOR TS 3.3.5.4 EXHAUST OUTBOARD CIV (PEN. 57) 2 MO C
CPAUVO004A CPP-O01 8
A AJ CLR 73ST-9CL07 CONTAINMENT POWER ACCESS PURGE D06 BF ACTIVE FSC QTR 73ST-9XI15 SUPPLY OUTBOARD CIV (PEN. 78) 2 AO C
FTC QTR 73ST-9X115 STC QTR 73ST-9XI15 VP 2YR 73ST-9XI15 CPAUVO004B CPP-001 8
A AJ CLR 73ST-9CL07 CONTAINMENT POWER ACCESS PURGE D03 BF ACTIVE FSC QTR 73ST-9XI15 EXHAUST INBOARD CIV (PEN. 79) 2 AO C
FTC QTR 73ST-9XI15 STC QTR 73ST-9XI15 VP 2YR 73ST-9XI15 CPBUVO005A CPP-001 8
A AJ CLR 73ST-9CL07 CONTAINMENT POWER ACCESS PURGE D05 BF ACTIVE FSC QTR 73ST-9XI15 SUPPLY INBOARD CIV (PEN. 78) 2 AO C
FTC QTR 73ST-9XI15 STC QTR 73ST-9XI15 VP 2YR 73ST-9XI15 CPBUVO005B CPP-001 8
A AJ CLR 73ST-9CL07 CONTAINMENT POWER ACCESS PURGE C02 BF ACTIVE FSC QTR 73ST-9XI15 EXHAUST OUTBOARD CIV (PEN. 79) 2 AO C
FTC QTR 73ST-9XI15 STC QTR 73ST-9XI15 VP 2YR 73ST-9XI15
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 18 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSjI Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks CPAUVO002A CPP-001 42 B
FSC RFO 73ST-9XI23 ROJ-01 Note 5 Note6 CONTAINMENT REFUELING PURGE D06 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M STC REQ'D FOR TS 3.3.5.4 SUPPLY OUTBOARD CIV (PEN. 56) 2 MO C
CPAUVO002B CPP-001 42 B
FSC RFO 73ST-9X123 ROJ-01 Note 5 Note6 CONTAINMENT REFUELING PURGE E03 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M STC REQ'D FORTS 3.3.5.4 EXHAUST INBOARD CIV (PEN. 57) 2 MO C
CTAHV0001 CTP-001 10 B
FSC QTR 73ST-9X105 VRR-01 The tests in the open direction are for an augmented function AFN-P01 SUCTION ISOLATION VALVE E02 BF ACTIVE FSO QTR 73ST-9XI05 VRR-01 Note 5 FROM CONDENSATE STORAGE TANK 3
MO C
QTR FS FOR PRA/RA.
CTAHV0004 CTP-001 10 B
FSC QTR 73ST-9XI05 VRR-01 The tests in the open direction are for an augmented function AFN-P01 SUCTION ISOLATION VALVE E03 BF ACTIVE FSO QTR 73ST-9XI05 VRR-01 Note 5 FROM CONDENSATE STORAGE TANK 3
MO C
QTR FS FOR PR5RA.
CTAV016 CTP-001 3
C BDC QTR 73ST-9CT01 Notes 1,2, 3.
CONDENSATE TRANSFER PUMP C04 CK ACTIVE CVO QTR 73ST-9CT01 DISCHARGE CHECK VALVE 3
SA 0
CTAV018 CTP-001 3
B FSC QTR 73ST-9CT01 CONDENSATE TRANSFER TO SPENT C03 GA ACTIVE FSO QTR 73ST-9CT01 FUEL POOL ISOLATION 3
MA O/C CTBV019 CTP-001 3
B FSC QTR 73ST-9CT01 CONDENSATE TRANSFER TO SPENT B03 GA ACTIVE FSO QTR 73ST-9CT01 FUEL POOL ISOLATION 3
MA O/C CTBV020 CTP-001 3
C BDC QTR 73ST-9CT01 Notes 1,2, 3.
CONDENSATE TRANSFER PUMP B04 CK ACTIVE CVO QTR 73ST-9CT01 DISCHARGE CHECK VALVE 3
SA 0
CTAV037 CTP-001 3
C BDC QTR 73ST-9CT01 Notes 1,2, 3.
CONDENSATE TRANSFER TO SPENT C04 CK ACTIVE CVO QTR 73ST-9CT01 FUEL POOL CHECK VALVE 3
SA 0
CTBV038 CTP-001 3
C BDC QTR 73ST-9CT01 Notes 1,2, 3.
CONDENSATE TRANSFER TO SPENT B04 CK ACTIVE CVO QTR 73ST-9CT01 FUEL POOL CHECK VALVE 3
SA 0
DFAV012 DFP-001 2
C BDC CMP 73ST-9DF01 Notes 1,2, 3, 4 FUEL OIL TRANSFER PUMP DISCHARGE D06 CK ACTIVE CVO CMP 73ST-9DF01 CHECK VALVE 3
SA 0
DFBV019 DFP-001 2
C BDC CMP 73ST-9DF01 Notes 1,2, 3, 4 FUEL OIL TRANSFER PUMP DISCHARGE D02 CK ACTIVE CVO CMP 73ST-9DF01 CHECK VALVE 3
SA 0
DFAV041 DFP-001 1
B FSC 2YR 73ST-9XI44 DIESEL FUEL OIL FILTER DP GAUGE H07 GL ACTIVE FSO 2YR 73ST-9XI44 MANUAL ISOLATION VALVE 3
MA C
DFAV042 DFP-001 1
B FSC 2YR 73ST-9X144 DIESEL FUEL OIL FILTER DP GAUGE G07 GL ACTIVE FSO 2YR 73ST-9X144 MANUAL ISOLATION VALVE 3
MA C
DFBV051 DFP-001 1
B FSC 2YR 73ST-9XI45 DIESEL FUEL OIL FILTER DP GAUGE H03 GL ACTIVE FSO 2YR 73ST-9XI45 MANUAL ISOLATION VALVE 3
MA C
DFBV052 DFP-001 1
B FSC 2YR 73ST-9XI45 DIESEL FUEL OIL FILTER DP GAUGE G03 GL ACTIVE FSO 2YR 73ST-9X145 MANUAL ISOLATION VALVE 3
MA C
DGAPSVO005 DGP-001 sht 9 1
C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY H06 SV ACTIVE RELIEF VALVE 3
SA O/C DGBPSVO006 DGP-001 sht 9 1
C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY D06 SV ACTIVE RELIEF VALVE 3
SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 19 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks DGAPSVO007 DGP-001 sht 9 1
C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY F06 SV ACTIVE RELIEF VALVE 3
SA O/C DGBPSVO008 DGP-001 sht9 1
C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY C03 SV ACTIVE RELIEF VALVE 3
SA O/C DGAV066 DGP-001 sht 9 1
C BDO QTR 40ST-9DG01 Notes 1,2, 3. Required in all EDG STARTING AIR DRYER OUTLET F06 CK ACTIVE CVC QTR 73ST-9XI17 modes including shutdown.
SA C
DGAV067 DGP-001 sht 9 1
C BDO QTR 40ST-9DG01 Notes 1,2, 3. Required in all EDG STARTING AIR DRYER OUTLET G06 CK ACTIVE CVC QTR 73ST-9XI17 modes including shutdown.
SA C
DGBV068 DGP-001 sht 9 1
C BDO QTR 40ST-9DG02 Notes 1,2, 3. Required in all EDG STARTING AIR DRYER OUTLET D06 CK ACTIVE CVC QTR 73ST-9XI18 modes including shutdown.
SA C
DGBV069 DGP-001 sht 9 1
C BDO QTR 40ST-9DG02 Notes 1, 2, 3. Required in all EDG STARTING AIR DRYER OUTLET C06 CK ACTIVE CVC QTR 73ST-9XI18 modes including shutdown.
SA C
DWEV061 DWP-002 2
A AJ CLR 73ST-9CLO1 DW SUPPLY HEADER OUTSIDE C03 GL PASSIVE CONTAINMENT ISOLATION VALVE (PEN. 6) 2 MA C
DWEV062 DWP-002 2
A AJ CLR 73ST-9CLO1 DW SUPPLY HEADER INSIDE C02 GL PASSIVE CONTAINMENT ISOLATION VALVE (PEN. 6) 2 MA C
ECAV038 ECP-001 1.5 C
BDO CMP 73ST-9ZZ25 Notes 1,3, 4 MAKEUP LINE CHECK VALVE FROM DW D07 CK ACTIVE CVC CMP 73ST-9ZZ25 Disassembly and Inspection 3
SA C
ECAV041 ECP-001 1.5 C
BDO CMP 73ST-9ZZ25 Notes 1,3, 4 MAKEUP LINE CHECK VALVE FROM CT C07 CK ACTIVE CVC CMP 73ST-9ZZ25 Disassembly and Inspection 3
SA C
ECAV043 ECP-001 1
C BDO CMP 73ST-9ZZ25 Notes 1,3, 4 NITROGEN SUPPLY CHECK VALVE TO EC C07 CK ACTIVE CVC CMP 73ST-9ZZ25 Disassembly and Inspection EXPANSION TANK 3
SA C
ECBV060 ECP-001 1.5 C
BDO CMP 73ST-9ZZ25 Notes 1,3, 4 MAKEUP LINE CHECK VALVE FROM DW D03 CK ACTIVE CVC CMP 73ST-9ZZ25 Disassembly and Inspection 3
SA C
ECBV064 ECP-001 1
C BDO CMP 73ST-9ZZ25 Notes 1,3, 4 NITROGEN SUPPLY CHECK VALVE TO EC C03 CK ACTIVE CVC CMP 73ST-9ZZ25 Disassembly and Inspection EXPANSION TANK 3
SA C
ECBV072 ECP-001 1.5 C
BDO CMP 73ST-9ZZ25 Notes 1,3, 4 MAKEUP LINE CHECK VALVE FROM CT D03 CK ACTIVE CVC CMP 73ST-97725 Disassembly and Inspection 3
SA C
ECAPSVO075 ECP-001 1.5 C
SV 10Y 73ST-9ZZ20 EC EXPANSION TANK RELIEF VALVE D06 SV ACTIVE 3
SA O/C ECBPSVO076 ECP-001 1.5 C
SV 10Y 73ST-9ZZ20 EC EXPANSION TANK RELIEF VALVE D03 SV ACTIVE 3
SA O/C ECAPSVO095 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESF SWITCHGEAR ROOM ESSENTIAL E05 SV ACTIVE ACU RELIEF VALVE 3
SA O/C ECBPSVO096 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESF SWITCHGEAR ROOM ESSENTIAL E02 SV ACTIVE ACU RELIEF VALVE 3
SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 20 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks ECAPSVO097 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve CONTROL ROOM ESSENTIAL ACU RELIEF E07 SV ACTIVE VALVE 3
SA O/C ECBPSVO098 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve CONTROL ROOM ESSENTIAL ACU RELIEF E04 SV ACTIVE VALVE 3
SA O/C ECAPSVO099 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve WEST ELECTRICAL PENETRATION ROOM F07 SV ACTIVE ESSENTIAL ACU RELIEF VALVE 3
SA O/C ECBPSVO100 ECP-001 1
C SV 10Y 73ST-97720 Thermal Relief Valve EAST ELECTRICAL PENETRATION ROOM F03 SV ACTIVE ESSENTIAL ACU RELIEF VALVE 3
SA O/C ECAPSVO101 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve EW PUMP ROOM ESSENTIAL ACU RELIEF F06 SV ACTIVE VALVE 3
SA O/C ECBPSVO102 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve EW PUMP ROOM ESSENTIAL ACU RELIEF F02 SV ACTIVE VALVE 3
SA O/C ECAPSV0103 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve CS PUMP ROOM ESSENTIAL ACU RELIEF H07 SV ACTIVE VALVE 3
SA O/C ECBPSVO104 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve CS PUMP ROOM ESSENTIAL ACU RELIEF H04 SV ACTIVE VALVE 3
SA O/C ECAPSV0105 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve HPSI PUMP ROOM ESSENTIAL ACU H06 SV ACTIVE RELIEF VALVE 3
SA O/C ECBPSVO106 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve HPSI PUMP ROOM ESSENTIAL ACU H03 SV ACTIVE RELIEF VALVE 3
SA O/C ECAPSV0107 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve LPSI PUMP ROOM ESSENTIAL ACU H05 SV ACTIVE RELIEF VALVE 3
SA O/C ECBPSVO108 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve LPSI PUMP ROOM ESSENTIAL ACU H02 SV ACTIVE RELIEF VALVE 3
SA O/C ECBPSVOI09 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve AFW PUMP ROOM ESSENTIAL ACU F04 SV ACTIVE RELIEF VALVE 3
SA O/C ECAPSVO117 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve AFW PUMP ROOM ESSENTIAL ACU F05 SV ACTIVE RELIEF VALVE 3
SA O/C ECBPSVO120 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve DC EQUIPMENT ROOM ESSENTIAL ACU E03 SV ACTIVE RELIEF VALVE 3
SA O/C ECAPSVO121 ECP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve DC EQUIPMENT ROOM ESSENTIAL ACU E06 SV ACTIVE RELIEF VALVE 3
SA O/C EWAPSVO047 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SHUTDOWN HEAT EXCHANGER RELIEF B07 SV ACTIVE VALVE 3
SA O/C EWBPSVO048 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SHUTDOWN HEAT EXCHANGER RELIEF B03 SV ACTIVE VALVE 3
SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 21 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLESP 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks EWAPSVO061 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESSENTIAL CHILLER OUTLET LINE D07 SV ACTIVE RELIEF VALVE 3
SA O/C EWBPSVO062 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESSENTIAL CHILLER OUTLET LINE E03 SV ACTIVE RELIEF VALVE 3
SA O/C EWAUVO065 EWP-001 12 B
FSC 1CY 73ST-9XI23 VRR-01 Note 5 EW TO NUCLEAR COOLING WATER C08 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M ST FOR TS 3.3.5.4 RETURN ISOLATION VALVE 3
MO C
EWAHCV0067 EWP-001 10 B
FSC 2YR 73ST-9XI44 Passive closed valve, exercising FUEL POOL HEAT EXCHANGER RETURN E08 BF PASSIVE FSO 2YR 73ST-9XI44 is augmented testing because of ISOLATION VALVE 3
MA C
importance (but non-safety) to open.
EWBHCV0068 EWP-001 10 B
FSC 2YR 73ST-9X145 Passive closed valve, exercising FUEL POOL HEAT EXCHANGER RETURN E04 BF PASSIVE FSO 2YR 73ST-9XI45 is augmented testing because of ISOLATION VALVE 3
MA C
importance (but non-safety) to open.
EWAPSVO079 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESSENTIAL CHILLED WATER HEAT F07 SV ACTIVE EXCHANGER A PRESSURE RELIEF VALVE 3
SA O/C EWBPSVO080 EWP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve ESSENTIAL CHILLED WATER HEAT F03 SV ACTIVE EXCHANGER B PRESSURE RELIEF VALVE 3
SA O/C EWAPSVO103 EWP-001 2
C SV 10Y 73ST-9ZZ20 ESSENTIAL COOLING WATER SURGE H06 SV ACTIVE TANK A PRESSURE RELIEF VALVE 3
SA O/C EWBPSV0104 EWP-001 2
C SV 10Y 73ST-9ZZ20 ESSENTIAL COOLING WATER SURGE H02 SV ACTIVE TANK B PRESSURE RELIEF VALVE 3
SA O/C EWAPSVOI05 EWP-001 2
C SV 10Y 73ST-9ZZ20 EW SURGE TANK VACUUM RELIEF VALVE H06 VR ACTIVE 3
SA O/C EWBPSVO106 EWP-001 2
C SP 10Y 73ST-9ZZ20 EW SURGE TANK VACUUM RELIEF VALVE H02 VR ACTIVE 3
SA O/C EWAHCV0133 EWP-001 10 B
FSC 2YR 73ST-9XI44 Passive dosed valve, exercising FUEL POOL HEAT EXCHANGER SUPPLY D06 BF PASSIVE FSO 2YR 73ST-9XI44 is augmented testing because of ISOLATION VALVE 3
MA C
importance (but non-safety) to open.
EWBHCV0134 EWP-001 10 B
FSC 2YR 73ST-9XI45 Passive closed valve, exercising FUEL POOL HEAT EXCHANGER SUPPLY D02 BF PASSIVE FSO 2YR 73ST-9XI45 is augmented testing because of ISOLATION VALVE 3
MA C
importance (but non-safety) to open.
EWAUVO145 EWP-001 12 B
FSC 1CY 73ST-9XI23 VRR-01 Note 5 EW TO NUCLEAR COOLING WATER C04 BF ACTIVE STC 18M 73ST-9XI23 VRR-01 18M ST FOR TS 3.3.5.4 SUPPLY ISOLATION VALVE 3
MO C
EWAV234 EWP-001 2
B FSC 2YR 73ST-9XI44 EW SURGE TANK INSTRUMENTATION G07 GL ACTIVE FSO 2YR 73ST-9XI44 EXCESS FLOW CHECK VALVE MANUAL 3
MA C
ISOLATION VALVE EWAV235 EWP-001 2
B FSC 2YR 73ST-9XI44 EW SURGE TANK INSTRUMENTATION F07 GL ACTIVE FSO 2YR 73ST-9XI44 EXCESS FLOW CHECK VALVE MANUAL 3
MA C
ISOLATION VALVE EWBV238 EWP-001 2
B FSC 2YR 73ST-9XI45 EW SURGE TANK INSTRUMENTATION G03 GL ACTIVE FSO 2YR 73ST-9XI45 EXCESS FLOW CHECK VALVE MANUAL 3
MA C
ISOLATION VALVE
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 22 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks EWBV239 EWP-001 2
B FSC 2YR 73ST-9XI45 EW SURGE TANK INSTRUMENTATION F03 GL ACTIVE FSO 2YR 73ST-9XI45 EXCESS FLOW CHECK VALVE MANUAL 3
MA C
ISOLATION VALVE FPEV089 FPP-006 6
A AJ CLR 73ST-9CLO1 FIRE WATER OUTSIDE CONTAINMENT E08 GL PASSIVE ISOLATION VALVE (PEN. 7) 2 MA C
FPEV090 FPP-006 6
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 FIRE WATER INSIDE CONTAINMENT F09 CK ACTIVE CVC CMP 73ST-9CLO1 ISOLATION VALVE (PEN. 7) 2 SA O/C CVO CMP 14FT-9FP13 GAAUVO001 GAP-001 1
A AJ CLR 73ST-9CLO1 HIGH PRESSURE NITROGEN SUPPLY E07 GL ACTIVE FSC QTR 73ST-9XI07 HEADER OUTSIDE CIV (PEN. 30) 2 so C
FTC QTR 73ST-9XI07 STC QTR 73ST-9X107 VP 2YR 73ST-9XI07 GAAUVO002 GAP-001 1
A AJ CLR 73ST-9CLO1 LOW PRESSURE NITROGEN SUPPLY F03 GL ACTIVE FSC QTR 73ST-9XI07 HEADER OUTSIDE CIV (PEN. 29) 2 so C
FTC QTR 73ST-9X107 STC QTR 73ST-9XI07 VP 2YR 73ST-9XI07 GAEV011 GAP-001 1
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4.
HIGH PRESSURE NITROGEN SUPPLY D06 CK ACTIVE BDO CMP 40ST-9ZZM1 INSIDE CONTAINMENT ISOLATION CHECK 2
SA C
VALVE (PEN. 30)
CVC CMP 73ST-9CL01 GAEV015 GAP-001 1
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3,4 LOW PRESSURE NITROGEN SUPPLY E02 CK ACTIVE BDO CMP 40DP-9OP05 INSIDE CONTAINMENT ISOLATION CHECK 2
SA C
VALVE (PEN. 29)
CVC CMP 73ST-9CL01 GRAUVO001 GRP-001 1
A AJ CLR 73ST-9CLO1 Note 5 QTR FS FOR PRA/RA CONTAINMENT ISOLATION BETWEEN H07 GL ACTIVE FSC QTR 73ST-9XI07 VRR-01 18M ST FOR TS 3.3.5.4 RDT AND GAS SURGE HEADER (PEN 52) 2 MO C
STC 18M 73ST-9XI07 VRR-01 GRBUVO002 GRP-001 1
A AJ CLR 73ST-9CLO1 CONTAINMENT ISOLATION (SOV)
H07 GL ACTIVE FSC QTR 73ST-9XI07 BETWEEN RDT AND GAS SURGE 2
so C
FTC QTR 73ST-9XI07 STC QTR 73ST-9XI07 VP 2YR 73ST-9XI07 HCBUVO044 HCP-001 1
A AJ CLR 73ST-9CLO1 CONTAINMENT ATMOSPHERE RADIATION E03 GL ACTIVE FSC QTR 73ST-9XI40 MONITOR INLET CIV (PEN 25A) 2 so C
FTC QTR 73ST-9XI40 STC QTR 73ST-9X140 VP 2YR 73ST-9X140 HCAUVO045 HCP-001 1
A AJ CLR 73ST-9CLO1 CONTAINMENT ATMOSPHERE RADIATION E02 GL ACTIVE FSC QTR 73ST-9XI40 MONITOR INLET CIV (PEN. 25A) 2 so C
FTC QTR 73ST-9XI40 STC QTR 73ST-9XI40 VP 2YR 73ST-9XI40 HCAUVO046 HCP-001 1
A AJ CLR 73ST-9CLO1 CONTAINMENT ATMOSPHERE RADIATION D02 GL ACTIVE FSC QTR 73ST-9XI40 MONITOR OUTLET CIV (PEN. 25B) 2 so C
FTC QTR 73ST-9X140 STC QTR 73ST-9XI40 VP 2YR 73ST-9X140
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 23 of 100 Revision PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 21 AND COMPONENT TABLESr 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks HCBUVO047 HCP-001 1
A AJ CLR 73ST-9CL01 CONTAINMENT ATMOSPHERE RADIATION D03 GL ACTIVE FSC QTR 73ST-9XI40 MONITOR OUTLET CIV (PEN. 25B) 2 so C
FTC QTR 73ST-9XI40 STC QTR 73ST-9XI40 VP 2YR 73ST-9XI40 HCAHV0074 HCP-001 0.75 B
VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE D08 GL PASSIVE TRANSMITTER CIV (PEN. 54A) 2 so 0
HCBHV0075 HCP-001 0.75 B
VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE C02 GL PASSIVE TRANSMITTER CIV (PEN. 55A) 2 so 0
HCCHV0076 HCP-001 0.75 B
VP 2YR 73ST-9X140 CONTAINMENT PRESSURE C08 GL PASSIVE TRANSMITTER CIV (PEN. 32A) 2 so 0
HCDHV0077 HCP-001 0.75 B
VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE C02 GL PASSIVE TRANSMITTER CIV (PEN. 62A) 2 so 0
HPAUVO001 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM SUPPLY FROM E15 GL ACTIVE FSC ICY 73ST-9XI08 VRR-01 18M ST FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 35) 2 MO O/C FSO iCY 73ST-9X108 VRR-01 STC 18M 73ST-9XI08 VRR-01 STO 18M 73ST-9XI08 VRR-01 HPAV002 HPP-001 2
AC AJ CLR 73ST-9CLO1 Notes 1, 2, 3, 4 H2 CONTROL SYSTEM RETURN LINE TO F15 CK ACTIVE CVC CMP 73ST-9CLO1 CONTAINMENT INBOARD CIV (PEN. 38) 2 SA O/C CVO CMP 73ST-9CLO1 HPBUVO002 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM SUPPLY FROM C15 GL ACTIVE FSC 1CY 73ST-9XI08 VRR-01 18M ST FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 36) 2 MO O/C FSO iCY 73ST-9XI08 VRR-01 STC 18M 73ST-9XI08 VRR-01 STO 18M 73ST-9XI08 VRR-01 HPAUVO003 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM SUPPLY FROM E14 GL ACTIVE FSC iCY 73ST-9XI08 VRR-01 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 35) 2 MO O/C FSO ICY 73ST-9XI08 VRR-01 STC 18M 73ST-9XI08 VRR-01 STO 18M 73ST-9XI08 VRR-01 HPBUVO004 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM SUPPLY FROM C14 GL ACTIVE FSC iCY 73ST-9XI08 VRR-01 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 36) 2 MO O/C FSO 1CY 73ST-9XI08 VRR-01 STC 18M 73ST-9XI08 VRR-01 STO 18M 73ST-9XI08 VRR-01 HPBV004 HPP-001 2
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 H2 CONTROL SYSTEM RETURN LINE TO C15 CK ACTIVE CVC CMP 73ST-9CLO1 CONTAINMENT INBOARD CIV (PEN. 39) 2 SA O/C CVO OMP 73ST-9CLO1 HPAUVO005 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM RETURN TO E14 GL ACTIVE FSC ICY 73ST-9XI08 VRR-01 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN 38) 2 MO O/C FSO 1CY 73ST-9XI08 VRR-01 STC 18M 73ST-9XI08 VRR-01 STO 18M 73ST-9XI08 VRR-01
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 24 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM Revision AND COMPONENT TABLESr 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks HPBUVO006 HPP-001 2
A AJ CLR 73ST-9CLO1 Note 5 H2 CONTROL SYSTEM RETURN TO C14 GL ACTIVE FSC 1CY 73ST-9XI08 VRR-01 18M ST FORTS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 39) 2 MO O/C FSO 1CY 73ST-9XI08 VRR-01 STC 18M 73ST-9X108 VRR-01 STO 18M 73ST-9X108 VRR-01 HPAHV0007A HPP-001 1
A AJ CLR 73ST-9CLO1 POST-LOCA H2 MONITOR INLET CIV (PEN.
F14 GL ACTIVE FSC QTR 73ST-9XI08
- 35) 2 s0 0/C FSO QTR 73ST-9XI08 FTC QTR 73ST-9XI08 STC QTR 73ST-9XI08 STO QTR 73ST-9XI08 VP 2YR 73ST-9XI08 HPAHV0007B HPP-001 1
A AJ CLR 73ST-9CLO1 POST-LOCA H2 MONITOR OUTLET CIV G14 GL ACTIVE FSC QTR 73ST-9XI08 (PEN. 38) 2 so O/C FSO QTR 73ST-9XI08 FTC QTR 73ST-9XI08 STC QTR 73ST-9XI08 STO QTR 73ST-9XI08 VP 2YR 73ST-9XI08 HPBHV0008A HPP-001 1
A AJ CLR 73ST-9CLO1 POST-LOCA H2 MONITOR INLET CIV (PEN.
C13 GL ACTIVE FSC QTR 73ST-9XI08
- 36) 2 so O/C FSO QTR 73ST-9XI08 FTC QTR 73ST-9XI08 STC QTR 73ST-9XI08 STO QTR 73ST-9XI08 VP 2YR 73ST-9XI08 HPBHV0008B HPP-001 1
A AJ CLR 73ST-9CLO1 POST-LOCA H2 MONITOR OUTLET CIV B14 GL ACTIVE FSC QTR 73ST-9XI08 (PEN. 39) 2 so O/C FSO QTR 73ST-9XI08 FTC QTR 73ST-9XI08 STC QTR 73ST-9XI08 STO QTR 73ST-9XI08 VP 2YR 73ST-9XI08 HPAUVO023 HPP-001 0.5 A
AJ CLR 73ST-9CLO1 Valve size is 1" in Units 2 and 3.
CONTAINMENT H2 MONITORING SYSTEM G14 GL ACTIVE FSC QTR 73ST-9X108 RETURN FROM PASS OUTBOARD CIV 2
so C
(PEN 38)FTC QTR 73ST-9XI08 (PEN. 38)
STC QTR 73ST-9XI08 VP 2YR 73ST-9XI08 HPAUVO024 HPP-001 0.5 A
AJ CLR 73ST-9CLO1 Valve size is 1" in Units 2 and 3 CONTAINMENT H2 MONITORING SYSTEM F12 GL ACTIVE FSC QTR 73ST-9XI08 TO PASS CIV (PEN. 35) 2 so C
FTC QTR 73ST-9XI08 STC QTR 73ST-9Xl08 VP 2YR 73ST-9XI08 IAAUVO002 IAP-003 2
A AJ CLR 73ST-9CLO1 INSTRUMENT AIR SUPPLY OUTSIDE G07 GL ACTIVE FSC CSD 73ST-9XI23 CSJ-06 CONTAINMENT ISOLATION VALVE (PEN.
2 so C
FTC CSD 73ST-9XI23 CSJ-06 31)
STC CSD 73ST-9XI23 CSJ-06 VP 2YR 73ST-9XI23
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 25 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 1
21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act..
S.P.
Test Freq Procedure VRR Remarks IAEV021 IAP-003 2
AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 INSTRUMENT AIR SUPPLY INSIDE G05 CK ACTIVE BDO CMP 40DP-90P05 CONTAINMENT ISOLATION VALVE (PEN.
2 SA C
- 31)
CVC CMP 73ST-9CL01 IAEV072 IAP-002 3
A AJ CLR 73ST-9CL01 BREATHING AIR CONTAINMENT G09 GL PASSIVE ISOLATION VALVE (PEN. 59) 2 MA C
IAEV073 IAP-002 3
AC AJ CLR 73ST-9CLO1 Notes 1, 2, 3 BREATHING AIR SUPPLY INSIDE H07 CK PASSIVE CONTAINMENT ISOLATION VALVE (PEN.
2 SA C
59)
NCEV118 NCP-003 10 AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 NUCLEAR COOLING WATER SUPPLY TO E06 CK ACTIVE BDO CMP 40DP-90P05 RCP COOLER INBOARD CIV (PEN. 33) 2 SA C
CVC CMP 73ST-gCLOl NCAHCV0244 NCP-002 10 B
FSC 2YR 73ST-9XI44 Augmented NUCLEAR COOLING WATER TO SPENT B04 BF ACTIVE FUEL POOL HEAT EXCHANGER 3
MA C
ISOLATION VALVE NCBHCV0245 NCP-002 10 B
FSC 2YR 73ST-9XI45 Augmented NUCLEAR COOLING WATER TO SPENT B04 BF ACTIVE FUEL POOL HEAT EXCHANGER 3
MA C
ISOLATION VALVE NCAPSV0250 NCP-002 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve FUEL POOL COOLING HEAT EXCHANGER E02 SV ACTIVE RELIEF VALVE 3
SA O/C NCBPSV0251 NCP-002 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve FUEL POOL COOLING HEAT EXCHANGER D02 SV ACTIVE RELIEF VALVE 3
SA O/C NCAHCV0258 NCP-002 10 B
FSC 2YR 73ST-9X144 Augmented NUCLEAR COOLING WATER TO SPENT C04 BF ACTIVE FUEL POOL HEAT EXCHANGER 3
MA C
ISOLATION VALVE NCBHCV0259 NCP-002 10 B
FSC 2YR 73ST-9X145 Augmented NUCLEAR COOLING WATER TO SPENT B04 BF ACTIVE FUEL POOL HEAT EXCHANGER 3
MA C
ISOLATION VALVE NCBUV0401 NCP-003 10 A
AJ CLR 73ST-9CL01 Note 5 NUCLEAR COOLING WATER SUPPLY TO E07 BF ACTIVE FSC 1CY 73ST-9X]23 VRR-01 18M ST FOR TS 3.3.5.4 RCP COOLER OUTBOARD CIV (PEN. 33) 2 MO C
STC 18M 73ST-9X]23 VRR-01 NCAUV0402 NCP-003 10 A
AJ CLR 73ST-9CLO1 Note 5 NUCLEAR COOLING WATER SUPPLY TO F07 BF ACTIVE FSC 1CY 73ST-9XI23 VRR-01 18M ST FOR TS 3.3.5.4 RCP COOLER OUTBOARD CIV (PEN. 34) 2 MO C
STC 18M 73ST-9XI23 VRR-01 NCBUV0403 NCP-003 10 A
AJ CLR 73ST-9CLO1 Note 5 NUCLEAR COOLING WATER SUPPLY TO F06 BF ACTIVE FSC 1CY 73ST-9XI23 VRR-01 18M ST FOR TS 3.3.5.4 RCP COOLER INBOARD CIV (PEN. 34) 2 MO C
STC 18M 73ST-9XI23 VRR-01 NCEPSV0614 NCP-003 6
C SV 10Y 73ST-9ZZ20 Augmented NC CONTAINMENT ISOLATION VALVE E05 SV ACTIVE RELIEF VALVE N
SA 0
NCEPSV0615 NCP-003 6
C SV 10Y 73ST-9ZZ20 Augmented NC CONTAINMENT ISOLATION VALVE E05 SV ACTIVE RELIEF VALVE N
SA 0
NCEPSV0617 NCP-003 0.75 AC AJ CLR 73ST-9CLO1 NC CONTAINMENT PENETRATION RELIEF E07 SV ACTIVE SV 10Y 73ST-9ZZ20 VALVE (PEN 34) 2 SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 26 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks PCAV013 PCP-001 8
C CVC QTR 73ST-9PCO1 Notes 1,2, 3. Augmented.
SPENT FUEL POOL COOLING PUMP D15 CK ACTIVE CVO QTR 73ST-9PC01 DISCHARGE CHECK VALVE 3
SA O/C PCBV017 PCP-001 8
C CVC QTR 73ST-9PC01 Notes 1,2, 3. Augmented.
SPENT FUEL POOL COOLING PUMP B15 CK ACTIVE CVO QTR 73ST-9PCO1 DISCHARGE CHECK VALVE 3
SA O/C PCAPSVO035 PCP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SPENT FUEL POOL COOLING HEAT E13 SV ACTIVE EXCHANGER PRESSURE RELIEF VALVE 3
SA O/C PCBPSVO036 PCP-001 1
C SV 10Y 73ST-9ZZ20 Augmented SPENT FUEL POOL COOLING HEAT B13 SV ACTIVE EXCHANGER PRESSURE RELIEF VALVE 3
SA O/C PCEV070 PCP-001 4
A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION.
El0 GA PASSIVE RETURN CONTAINMENT ISOLATION 2
MA C
VALVE (PEN 50)
PCEV071 PCP-001 4
A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION E09 GA PASSIVE RETURN CONTAINMENT ISOLATION 2
MA C
VALVE (PEN 50)
PCEV075 PCP-001 4
A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION SUPPLY G06 GA PASSIVE CONTAINMENT ISOLATION VALVE (PEN 2
MA C
51)
PCEV076 PCP-001 4
A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION SUPPLY G05 GA PASSIVE CONTAINMENT ISOLATION VALVE (PEN 2
MA C
51)
PCNV215 CHP-002 3
B FSC 2YR 73ST-9XI44 RWTTO SPENT FUEL POOL MANUAL All DI ACTIVE FSO 2YR 73ST-9XI44 ISOLATION VALVE 3
MA O/C RCAHV0101 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 REACTOR VESSEL HEAD VENT VALVE G15 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 2
so O/C FTC CSD 73ST-9XI24 CSJ-07 STC CSD 73ST-9XI24 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9XI24 RCBHV0102 RCP-001 1
B FSC CSD 73ST-9X124 CSJ-07 REACTOR VESSEL HEAD VENT VALVE G15 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 2
so O/C FTC CSD 73ST-9X124 CSJ-07 STC CSD 73ST-9X124 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9XI24 RCAHV0103 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 PRESSURIZER VENT VALVE G14 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 2
so O/C FTC CSD 73ST-9X124 CSJ-07 STC CSD 73ST-9X124 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9XI24
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 27 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks RCBHV0105 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 PRESSURIZER/REACTOR VESSEL HEAD G13 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 VENT VALVE TO REACTOR DRAIN TANK 2
so O/C FTC CSD 73ST-9XI24 CSJ-07 STC CSD 73ST-9XI24 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9XI24 RCAHV0106 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 PRESSURIZER/REACTOR VESSEL HEAD G13 GL ACTIVE FSO CSD 73ST-9X124 CSJ-07 VENT VALVE TO CONTAINMENT 2
so O/C FTC CSD 73ST-9XI24 CSJ-07 STC CSD 73ST-9XI24 CSJ-07 STO CSD 73ST-9X124 CSJ-07 VP 2YR 73ST-9XI24 RCBHV0108 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 PRESSURIZER VENT VALVE G13 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 1
so O/C FTC CSD 73ST-9XI24 CSJ-07 STC CSD 73ST-9XI24 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9X124 RCBHV0109 RCP-001 1
B FSC CSD 73ST-9XI24 CSJ-07 PRESSURIZER VENT VALVE G13 GL ACTIVE FSO CSD 73ST-9XI24 CSJ-07 1
so O/C FTC CSD 73ST-9XI24 CSJ-07 STC CSD 73ST-9XI24 CSJ-07 STO CSD 73ST-9XI24 CSJ-07 VP 2YR 73ST-9XI24 RCEPSV0200 RCP-001 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV ACTIVE 040634) 1 SA O/C RCEPSV0201 RCP-001 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV ACTIVE 040634) 1 SA O/C RCEPSV0202 RCP-001 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV ACTIVE 040634) 1 SA O/C RCEPSV0203 RCP-001 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV ACTIVE 040634) 1 SA O/C RDAV020 RDP-002 sht 2 4
C CVC CMP 73ST-9ZZ25 Notes 1,3, 4 CONTAINMENT SPRAY PUMP ROOM B14 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection FLOOR DRAIN CHECK VALVE TO ESF 3
SA O/C SUMP RDAV021 RDP-002 sht 2 4
C CVC CMP 73ST-9ZZ25 Notes 1, 3, 4 HPSI PUMP ROOM FLOOR DRAIN CHECK B05 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection VALVE TO ESF SUMP 3
SA O/C RDAV022 RDP-002 sht 2 4
C CVC CMP 73ST-9ZZ25 Notes 1, 3, 4 LPSI PUMP ROOM FLOOR DRAIN CHECK B14 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection VALVE TO ESF SUMP 3
SA O/C RDAUVO023 RDP-001 3
A AJ CLR 73ST-9CLO1 Note 5 QTR FS FOR PRN/RA CONTAINMENT RADWASTE SUMP G04 GA ACTIVE FSC QTR 73ST-9XI07 VRR-01 18M ST FOR TS 3.3.5.4 OUTLET INBOARD CIV (PEN. 9) 2 MO C
STC 18M 73ST-9XI07 VRR-01
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 28 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9X101 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks RDBUVO024 RDP-001 3
A AJ CLR 73ST-9CLO1 CONTAINMENT RADWASTE SUMP G04 GA ACTIVE FSC QTR 73ST-9XI07 OUTLET OUTBOARD CIV (PEN. 9) 2 AO C
FTC QTR 73ST-9XI07 STC QTR 73ST-9XI07 VP 2YR 73ST-9XI07 RDBV040 RDP-002 sht 3 4
C CVC CMP 73ST-9ZZ25 Notes 1,3, 4 CONTAINMENT SPRAY PUMP ROOM B05 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection FLOOR DRAIN CHECK VALVE TO ESF 3
SA O/C SUMP RDBV041 RDP-002 sht 3 4
C CVC CMP 73ST-9ZZ25 Notes 1,3, 4 HPSI PUMP ROOM FLOOR DRAIN CHECK B05 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection VALVE TO ESF SUMP 3
SA O/C RDBV042 RDP-002 sht 3 4
C CVC CMP 73ST-9ZZ25 Notes 1,3, 4 LPSI PUMP ROOM FLOOR DRAIN CHECK B05 CK ACTIVE CVO CMP 73ST-97725 Disassembly and Inspection VALVE TO ESF SUMP 3
SA O/C RDAV203 RDP-002 sht 3 4
C CVC CMP 73ST-9ZZ25 Disassembly and Inspection AUXILIARY FEEDWATER PUMP ROOM G04 CK ACTIVE CVO CMP 73ST-9ZZ25 TRAIN A FLOOR DRAIN CHECK VALVE TO N
SA O/C NON-ESF SUMP RDBV204 RDP-002 sht 3 4
C CVC CMP 73ST-9ZZ25 Disassembly and Inspection AUXILIARY FEEDWATER PUMP ROOM F03 CK ACTIVE CVO CMP 73ST-9ZZ25 TRAIN B FLOOR DRAIN CHECK VALVE TO N
SA O/C NON-ESF SUMP RDBUV0407 RDP-001 0.5 A
AJ CLR 73ST-9CLO1 CONTAINMENT RADWASTE SUMP G04 GL ACTIVE FSC QTR 73ST-9XI07 OUTLET TO POST ACCIDENT SAMPLING 2
so C
FTC QTR 73ST-9XI07 STC QTR 73ST-9XI07 VP 2YR 73ST-9XI07 SGEV003 SGP-002 24 C
BDO CMP Normal Ops Notes 1,2, 3, 4 ECONOMIZER FEEDWATER LINE CHECK El0 CK ACTIVE CVC CMP 73ST-9XI32 VALVE(PEN.8) 2 SA C
SGEV005 SGP-002 24 C
BDO CMP Normal Ops Notes 1,2, 3, 4 ECONOMIZER FEEDWATER LINE CHECK A10 CK ACTIVE CVC CMP 73ST-9XI32 VALVE (PEN. 10) 2 SA C
SGEV006 SGP-002 24 C
BDO CMP Normal Ops Notes 1,2, 3, 4 ECONOMIZER FEEDWATER LINE CHECK A10 CK ACTIVE CVC CMP 73ST-9XI32 VALVE (PEN. 10) 2 SA C
SGEV007 SGP-002 24 C
BDO CMP Normal Ops Notes 1, 2, 3, 4 ECONOMIZER FEEDWATER LINE CHECK El0 CK ACTIVE CVC CMP 73ST-9XI32 VALVE (PEN. 8) 2 SA C
SGEVA19 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 170 INSTRUMENT AIR CHECK VALVE NA CK ACTIVE CVC CMP 73ST-9SGO1 2
SA C
LT 2YR 73ST-9SGO1 SGEVA20 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 170 INSTRUMENT AIR CHECK VALVE NA CK ACTIVE CVC CMP 73ST-9SGO1 2
SA C
LT 2YR 73ST-9SGO1 SGEVA21 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 180 INSTRUMENT AIR CHECK NA CK ACTIVE CVC CMP 73ST-9SGO1 VALVE 2
SA C
LT 2YR 73ST-9SGO1 SGEVA22 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 180 INSTRUMENT AIR CHECK NA CK ACTIVE CVC CMP 73ST-9SGO1 VALVE 2
SA C
LT 2YR 73ST-9SGO1
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CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGEVA23 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 171 INSTRUMENT AIR CHECK NA CK ACTIVE CVC CMP 73ST-9SGO1 VALVE 2
SA C
LT 2YR 73ST-9SGO1 SGEVA24 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 171 INSTRUMENT AIR CHECK NA CK ACTIVE CVC CMP 73ST-9SGO1 VALVE 2
SA C
LT 2YR 73ST-9SGO1 SGEVA25 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV 181 INSTRUMENT AIR CHECK VALVE NA CK ACTIVE CVC CMP 73ST-9SGO1 2
SA C
LT 2YR 73ST-9SGO1 SGEVA26 VM M234A-14 0.5 AC BDO CMP 73ST-9SGO1 Notes 1,2, 3, 4 MSIV181 INSTRUMENT AIR CHECK NA CK ACTIVE CVC CMP 73ST-9SGO1 VALVE 2
SA C
LT 2YR 73ST-9SGO1 SGAVA27 VM M234A-55 0.5 AC BDO CMP 73ST-9XI16 Notes 1,2, 3, 4 ECONOMIZER FWIV 174 INSTRUMENT NA CK ACTIVE CVC CMP 73ST-9XI16 AIR CHECK VALVE 2
SA C
LT 2YR 73ST-9XI 16 SGAVA28 VM M234A-55 0.5 AC BDO CMP 73ST-9XI16 Notes 1,2, 3, 4 ECONOMIZER FWIV 177 INSTRUMENT NA CK ACTIVE CVC CMP 73ST-9XI16 AIR CHECK VALVE 2
SA C
LT 2YR 73ST-9XI16 SGBVA29 VM M234A-55 0.5 AC BDO CMP 73ST-9XI16 Notes 1,2, 3, 4 ECONOMIZER FWIV 132 INSTRUMENT NA CK ACTIVE CVC CMP 73ST-9XI16 AIR CHECK VALVE 2
SA C
LT 2YR 73ST-9XI16 SGBVA30 VM M234A-55 0.5 AC BDO CMP 73ST-9XI16 Notes 1,2, 3, 4 ECONOMIZER FWIV 137 INSTRUMENT AIR NA CK ACTIVE CVC CMP 73ST-9XI16 CHECK VALVE SA C
LT 2YR 73ST-9XI16 SGAV043 SGP-001 sht 1 6
C CVC CMP 73ST-9AF04 Notes 1,2, 3, 4 STEAM SUPPLY CHECK VALVE TO E12 CK ACTIVE CVO CMP 73ST-9AF04 TURBINE-DRIVEN AFW PUMP 3
SA O/C SGAV044 SGP-001 sht 1 6
C CVC CMP 73ST-9AF04 Notes 1,2, 3, 4 STEAM SUPPLY CHECK VALVE TO C12 CK ACTIVE CVO CMP 73ST-9AF04 TURBINE-DRIVEN AFW PUMP 3
SA O/C SGBUVO130 SGP-002 8
B FSC CSD 73ST-9XI19 CSJ-08 Fails closed on loss of air.
SG 1 DOWNCOMER FEEDWATER Gl1 GA ACTIVE FTC CSD 73ST-9XI19 CSJ-08 DOWNSTREAM ISOLATION VALVE (PEN.
2 AO C
11)STC CSD 73ST-9XI19 CSJ-08 VP 2YR 73ST-9XI19 SGBUVO132 SGP-002 24 B
FSC CSD 73ST-9XI16 CSJ-08 PSC is an Augmented Test (see SG 1 ECONOMIZER FEEDWATER E12 GA ACTIVE FTC CSD 73ST-9XI16 CSJ-08 CSJ-08)
DOWNSTREAM ISOLATION VALVE 2
HY C
(PEN. 8)
PSC QTR 73ST-9XI16 STC CSD 73ST-9XI16 CSJ-08 VP 2YR 73ST-9XI16 SGAUVO134 SGP-001 sht 1 6
B FSC QTR 73ST-9AF02 VRR-01 Note 5 SG 1 STEAM SUPPLY TO AUX FEED PUMP E14 GA ACTIVE FSO QTR 73ST-9AF02 VRR-01 Leakage test is 'Augmented TRIEIOAINVALVE (PEN. 2) 2 M
O0/C requirement.
TURBINE ISOLATION LT RFO 73ST-9XI34 QTR FS FOR PRA/RA STC 18M 73ST-9AF02 VRR-01 18M ST FOR TS 3.3.5.4 STO 18M 73ST-9AF02 VRR-01
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Cat.
CSj/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGBUVO134A SGP-001 sht 1 1
B FSC QTR 73ST-9AF02 Leakage test is "Augmented" TDAFW PUMP STEAM SUPPLY WARM-UP E13 GL ACTIVE FSO QTR 73ST-9AF02 requirement.
LINE ISOLATION VALVE 2
FTC QTR 73ST-9AF02 LT RFO 73ST-9XI34 STC QTR 73ST-9AF02 STO QTR 73ST-9AF02 VP 2YR 73ST-9AF02 SGBUVO135 SGP-002 8
B FSC CSD 73ST-9XI 19 CSJ-08 Fails closed on loss of air only SG 2 DOWNCOMER FEEDWATER Cll GA ACTIVE FTC CSD 73ST-9XI19 CSJ-08 DOWNSTREAM ISOLATION VALVE (PEN.
2 AO C
STO CSD 73ST-9X119 CSJ-08 12)
VP 2YR 73ST-9XI19 SGBUV0137 SGP-002 24 B
FSC CSD 73ST-9XI16 CSJ-08 PSC is an Augmented Test (see SG 2 ECONOMIZER FEEDWATER A12 GA ACTIVE FTC CSD 73ST-9XI16 CSJ-08 CSJ-08)
DOWNSTREAM ISOLATION VALVE 2
HY C
(PEN 10)PSC QTR 73ST-9XI16 (PEN. 10)
STC CSD 73ST-9XI16 CSJ-08 VP 2YR 73ST-9XI16 SGAUVO138 SGP-001 sht 1 6
B FSC QTR 73ST-9AF02 VRR-01 Note 5 SG 2 STEAM SUPPLYTO AUX FEED PUMP C13 GA ACTIVE FSO QTR 73ST-9AF02 VRR-01 Leakage test is"Augmented" TURBINE ISOLATION VALVE (PEN. 3) 2 MO 0/C requirement.
LT RFO 73ST-9XI34 QTR FS FOR PRA/RA STC 18M 73ST-9AF02 VRR-01 18M ST FORTS 3.3.5.4 STO 18M 73ST-9AF02 VRR-01 SGAUVO138A SGP-001 sht 1 1
B FSC QTR 73ST-9AF02 Leakage test is "Augmented" TDAFW PUMP STEAM SUPPLY WARM-UP C14 GL ACTIVE FSO QTR 73ST-9AF02 requirement.
LINE ISOLATION VALVE 2
so O/C (PEN. 3)
FTC QTR 73ST-9AF02 LT RFO 73ST-9XI34 STC QTR 73ST-9AF02 STO QTR 73ST-9AF02 VP 2YR 73ST-9AF02 SGEUVO169 SGP-001 sht 1 4
B FSC QTR 73ST-9X101 MSIV BYPASS VALVE (PEN. 2)
Dll GA ACTIVE FTC QTR 73ST-9X101 2
AO C
STC QTR 73ST-9X101 VP 2YR 73ST-9X101 SGEUV0170 SGP-001 sht 1 28 B
FSC CSD 73ST-9SGO1 CSJ-09 PSC is an Augmented Test (see MAIN STEAM ISOLATION VALVE (PEN. 1)
G10 GA ACTIVE FTC CSD 73ST-9SGO1 CSJ-09 CSJ-09) 2 HY C
PSC QTR 73ST-9SGO1 STC CSD 73ST-9SGO1 CSJ-09 VP 2YR 73ST-9SG01 SGEUVO171 SGP-001 sht 1 28 B
FSC CSD 73ST-9SGO1 CSJ-09 PSC is an Augmented Test (see MAIN STEAM ISOLATION VALVE (PEN. 3)
D10 GA ACTIVE FTC CSD 73ST-9SGO1 CSJ-09 CSJ-09)
.2 HY C
PSC QTR 73ST-9SGO1 STC CSD 73ST-9SGO1 CSJ-09 VP 2YR 73ST-9SGO1 SGAUVO172 SGP-002 8
B FSC CSD 73ST-9X1 19 CSJ-08 Fails closed on loss of air only SG 1 DOWNCOMER FEEDWATER G12 GA ACTIVE FTC CSD 73ST-9X119 CSJ-08 UPSTREAM ISOLATION VALVE 2
AO C
(PEN. 11)
STC CSD 73ST-9XI19 CSJ-08 VP 2YR 73ST-9XI19
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Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGAUVO174 SGP-002 24 B
FSC CSD 73ST-9X116 CSJ-08 PSC is an Augmented Test (see SG 1 ECONOMIZER FEEDWATER E12 GA ACTIVE FTC CSD 73ST-9XI16 CSJ-08 CSJ-08)
UPSTREAM ISOLATION VALVE 2
HY C
PSC QTR 73ST-9X116 (PEN. 8)
STC CSD 73ST-9XI16 CSJ-08 VP 2YR 73ST-9XI16 SGAUVO175 SGP-002 8
B FSC CSD 73ST-9XI19 CSJ-08 Fails closed on loss of air only SG 2 DOWNCOMER FEEDWATER C12 GA ACTIVE FTC CSD 73ST-9XI19 CSJ-08 UPSTREAM ISOLATION VALVE 2
AO C
(PEN. 12)
STC CSD 73ST-9XI19 CSJ-08 VP 2YR 73ST-9XI19 SGAUVO177 SGP-002 24 B
FSC CSD 73ST-9XI16 CSJ-08 PSC is an Augmented Test (see SG 2 ECONOMIZER FEEDWATER A12 GA ACTIVE FTC CSD 73ST-9XI16 CSJ-08 CSJ-08)
UPSTREAM ISOLATION VALVE 2
HY C
(PEN. 10)
PSC QTR 73ST-9XI16 STC CSD 73ST-9XI16 CSJ-08 VP 2YR 73ST-9X116 SGBHV0178 SGP-001 sht 2 12 B
FSC QTR 73ST-9X120 STEAM GENERATOR ATMOSPHERIC E02 GL ACTIVE FSO QTR 73ST-9X120 DUMP VALVE (ADV) (PEN. 2) 2 AO O/C FTC QTR 73ST-9XI20 STC QTR 73ST-9X120 STO QTR 73ST-9XI20 VP 2YR 73ST-9XI20 SGAHV0179 SGP-001 sht 2 12 B
FSC QTR 73ST-9XI20 STEAM GENERATOR ATMOSPHERIC B02 GL ACTIVE FSO QTR 73ST-9XI20 DUMP VALVE (ADV) (PEN. 4) 2 AO O/C FTC QTR 73ST-9XI20 STC QTR 73ST-9XI20 STO QTR 73ST-9X120 VP 2YR 73ST-9XI20 SGEUVO180 SGP-001 sht 1 28 B
FSC CSD 73ST-9SGO1 CSJ-09 PSC is an Augmented Test (see MAIN STEAM ISOLATION VALVE (PEN. 2)
Flo GA ACTIVE FTC CSD 73ST-9SGO1 CSJ-09 CSJ-09) 2 HY C
PSC QTR 73ST-9SG01 STC CSD 73ST-9SGO1 CSJ-09 VP 2YR 73ST-9SG01 SGEUV0181 SGP-001 sht 1 28 B
FSC CSD 73ST-9SG01 CSJ-09 PSC is an Augmented Test (see MAIN STEAM ISOLATION VALVE (PEN. 4)
B10 GA ACTIVE FTC CSD 73ST-9SG01 CSJ-09 CSJ-09) 2 HY C
PSC QTR 73ST-9SGO1 STC CSD 73ST-9SGO1 CSJ-09 VP 2YR 73ST-9SG01 SGEUVO183 SGP-001 sht 1 4
B FSC QTR 73ST-9XI02 MSIV BYPASS VALVE (PEN. 3)
Cll GA ACTIVE FTC QTR 73ST-9X102 2
AO C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAHV0184 SGP-001 sht 2 12 B
FSC QTR 73ST-9XI20 STEAM GENERATOR ATMOSPHERIC G02 GL ACTIVE FSO QTR 73ST-9XI20 DUMP VALVE (ADV) (PEN. 1) 2 AO O/C FTC QTR 73ST-9X120 STO QTR 73ST-9X120 STO QTR 73ST-9X120 VP 2YR 73ST-9X120
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Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGBHV0185 SGP-001 sht2 12 B
FSC QTR 73ST-9XI20 STEAM GENERATOR ATMOSPHERIC D02 GL ACTIVE FSO QTR 73ST-9XI20 DUMP VALVE (ADV) (PEN. 3) 2 AO O/C FTC QTR 73ST-9XI20 STC QTR 73ST-9XI20 STO QTR 73ST-9XI20 VP 2YR 73ST-9XI20 SGBHV0200 SGP-002 0.375 B
FSC QTR 73ST-9XI01 CHEMICAL INJECTION ISOLATION VALVE Fll GL ACTIVE FTC QTR 73ST-9XI01 (PEN. 11) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9X101 SGBHV0201 SGP-002 0.375 B
FSC QTR 73ST-9XI02 CHEMICAL INJECTION ISOLATION VALVE Bl1 GL ACTIVE FTC QTR 73ST-9XI02 (PEN. 12) 2 s0 C
STC QTR 73ST-9X102 VP 2YR 73ST-9XI02 SGAUV0204 SGP-002 0.5 B
FSC QTR 73ST-9X101 SG 1 HOT LEG BLOWDOWN SAMPLE LINE F03 GL ACTIVE FTC QTR 73ST-9X101 ISOLATION VALVE (PEN. 37B) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9X101 SGAUV0211 SGP-002 0.5 B
FSC QTR 73ST-9XI01 SG 1 COLD LEG BLOWDOWN SAMPLE G03 GL ACTIVE FTC QTR 73ST-9XI01 LINE ISOLATION VALVE (PEN. 37A) 2 so C
STC QTR 73ST-9X101 VP 2YR 73ST-9XI01 SGBUV0219 SGP-002 0.5 B
FSC QTR 73ST-9XI01 SG 1 HOT LEG BLOWDOWN SAMPLE LINE G03 GL ACTIVE FTC QTR 73ST-9XI01 ISOLATION VALVE (PEN. 37B) 2 so C
STC QTR 73ST-9X101 VP 2YR 73ST-9XI01 SGAUV0220 SGP-002 0.5 B
FSC QTR 73ST-9XI01 SG 1 DOWNCOMER BLOWDOWN SAMPLE G06 GL ACTIVE FTC QTR 73ST-9XI01 LINE ISOLATION VALVE (PEN. 49) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9X101 SGBUV0221 SGP-002 0.5 B
FSC QTR 73ST-9X101 SG 1 DOWNCOMER BLOWDOWN SAMPLE G05 GL ACTIVE FTC QTR 73ST-9XI01 LINE ISOLATION VALVE PEN. 49) 2 so C
STC QTR 73ST-9X101 VP 2YR 73ST-9XI01 SGBUV0222 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 COLD LEG BLOWDOWN SAMPLE C04 GL ACTIVE FTC QTR 73ST-9X102 LINE ISOLATION VALVE (PEN. 63B) 2 so C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAUV0223 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 COLD LEG BLOWDOWN SAMPLE C03 GL ACTIVE FTC QTR 73ST-9XI02 LINE ISOLATION VALVE (PEN. 63B) 2 so C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGBUV0224 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 HOT LEG BLOWDOWN SAMPLE LINE D04 GL ACTIVE FTC QTR 73ST-9XI02 ISOLATION VALVE (PEN. 63A) 2 so C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 33 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGAUV0225 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 HOT LEG BLOWDOWN SAMPLE LINE D02 GL ACTIVE FTC QTR 73ST-9XI02 ISOLATION VALVE (PEN. 63A) 2 SO C
STC QTR 73ST-9X102 VP 2YR 73ST-9X102 SGBUV0226 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 DOWNCOMER BLOWDOWN SAMPLE C05 GL ACTIVE FTC QTR 73ST-9XI02 LINE ISOLATION VALVE (PEN. 48) 2 SO C
STC QTR 73ST-9X102 VP 2YR 73ST-9X102 SGAUV0227 SGP-002 0.5 B
FSC QTR 73ST-9XI02 SG 2 DOWNCOMER BLOWDOWN SAMPLE C05 GL ACTIVE FTC QTR 73ST-9X102 LINE ISOLATION VALVE (PEN. 48) 2 SO C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGBUV0228 SGP-002 0.5 B
FSC QTR 73ST-9XI01 SG 1 COLD LEG BLOWDOWN SAMPLE G03 GL ACTIVE FTC QTR 73ST-9XI01 LINE ISOLATION VALVE (PEN. 37A) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9XI01 SGBPSV0302 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGBHV178 NITROGEN F06 SV ACTIVE sv 10Y 73ST-9ZZ20 ACCUMULATOR PRESSURE RELIEF 3
SA O/C VALVE SGBPSV0305 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGBHV178 NITROGEN SUPPLY F05 SV ACTIVE sv 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3
SA O/C SGAPSV0309 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGAHV179 NITROGEN C06 SV ACTIVE SV 10Y 73ST-9ZZ20 ACCUMULATOR PRESSURE RELIEF 3
SA O/C VALVE SGAPSV0312 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGAHV179 NITROGEN SUPPLY C05 SV ACTIVE SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3
SA O/C SGAPSV0316 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGAHVI84 NITROGEN H06 SV ACTIVE SV 10Y 73ST-9ZZ20 ACCUMULATOR PRESSURE RELIEF 3
SA O/C VALVE SGAPSV0319 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGAHV184 NITROGEN SUPPLY H05 SV ACTIVE SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3
SA O/C SGBPSV0322 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGBHV185 NITROGEN E06 SV ACTIVE SV 10Y 73ST-9ZZ20 ACCUMULATOR PRESSURE RELIEF 3
SA O/C VALVE SGBPSV0325 SGP-001 sht 2 1
AC LT 2YR 73ST-9SG05 ADV SGBHV185 NITROGEN SUPPLY E05 SV ACTIVE SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3
SA O/C SGEV346 SGP-001 sht 2 1
AC BDO CMP 73ST-9XI20 Notes 1, 2, 3, 4 INSTRUMENT AIR CHECK VALVE TO ADV B04 CK ACTIVE CVC CMP 73ST-9SG05 184 3
SA C
LT 2YR 73ST-9SG05 SGEV348 SGP-001 sht 2 1
AC BDO CMP 73ST-9XI20 Notes 1, 2, 3, 4 INSTRUMENT AIR CHECK VALVE TO ADV G04 CK ACTIVE CVC CMP 73ST-9SG05 179 3
SA C
CMP LT 2YR 73ST-9SG05
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 34 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGEV357 SGP-001 sht 2 1
AC BDO CMP 73ST-9XI20 Notes 1,2, 3, 4 INSTRUMENT AIR CHECK VALVE TO ADV F04 CK ACTIVE CVC CMP 73ST-9SG05 178 3
SA C
LT 2YR 73ST-9SG05 SGEV358 SGP-001 sht 2 1
AC BDO CMP 73ST-9XI20 Notes 1,2, 3, 4 INSTRUMENT AIR CHECK VALVE TO ADV D04 CK ACTIVE CVC CMP 73ST-9SG05 185 SA C
LT 2YR 73ST-9SG05 SGAUV0500P SGP-002 6
B FSC QTR 73ST-9XI01 STEAM GENERATOR BLOWDOWN E03 GA ACTIVE FTC QTR 73ST-9XI01 SAMPLE CIV (PEN. 46) 2 AO C
STC QTR 73ST-9X]01 VP 2YR 73ST-9XI01 SGBUV0500Q SGP-002 6
B FSC QTR 73ST-9XI01 STEAM GENERATOR BLOWDOWN E02 GA ACTIVE FTC QTR 73ST-9XI01 SAMPLE CIV (PEN. 46) 2 AO C
STC QTR 73ST-9X101 VP 2YR 73ST-9X101 SGBUV0500R SGP-002 6
B FSC QTR 73ST-9X102 STEAM GENERATOR BLOWDOWN A03 GA ACTIVE FTC QTR 73ST-9XI02 SAMPLE CIV (PEN. 47) 2 AO C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAUVO500S SGP-002 6
B FSC QTR 73ST-9X102 STEAM GENERATOR BLOWDOWN A02 GA ACTIVE FTC QTR 73ST-9XI02 SAMPLE CIV (PEN. 47) 2 AO C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGEPSV0554 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D12 SV ACTIVE 038788)
LINE 1 (PEN. 3) 2 SA O/C SGEPSV0555 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D13 SV ACTIVE 038788)
LINE 1 (PEN. 3) 2 SA O/C SGEPSV0556 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D14 SV ACTIVE 038788)
LINE 1 (PEN. 3) 2 SA O/C SGEPSV0557 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D15 SV ACTIVE 038788)
LINE 1 (PEN. 3) 2 SA O/C SGEPSV0558 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A15 SV ACTIVE 038788)
LINE 2 (PEN. 4) 2 SA O/C SGEPSV0559 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A14 SV ACTIVE 038788)
LINE 2 (PEN. 4) 2 SA O/C SGEPSV0560 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A13 SV ACTIVE 038788)
LINE 2 (PEN. 4) 2 SA O/C SGEPSV0561 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A12 SV ACTIVE 038788)
LINE 2 (PEN. 4) 2 SA O/C SGEPSV0572 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H12 SV ACTIVE 038788)
LINE 1 (PEN. 1) 2 SA O/C SGEPSVO573 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H13 SV ACTIVE 038788)
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 35 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Reviion AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGEPSV0574 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H14 SV ACTIVE 038788)
LINE 1 (PEN. 1) 2 SA O/C SGEPSV0575 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H14 SV ACTIVE 038788)
LINE 1 (PEN. 1) 2 SA O/C SGEPSVO576 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F15 SV ACTIVE 038788)
LINE 2 (PEN. 2) 2 SA O/C SGEPSV0577 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F14 SV ACTIVE 038788)
LINE 2 (PEN. 2) 2 SA O/C SGEPSV0578 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ1.8 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F13 SV ACTIVE 038788)
LINE 2 (PEN. 2) 2 SA O/C SGEPSV0579 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F12 SV ACTIVE 038788)
LINE 2 (PEN. 2) 2 SA O/C SGEV642 SGP-002 8
C BDO CMP Normal Ops Notes 1,2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK Gl1 CK ACTIVE CVC CMP 73ST-9XI32 VALVE (PEN. 11) 2 SA C
SGEV652 SGP-002 8
C BDO CMP Normal Ops Notes 1,2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK G10 CK ACTIVE CVC CMP 73ST-9X132 VALVE (PEN. 11) 2 SA C
SGEV653 SGP-002 8
C BDO CMP Normal Ops Notes 1,2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK C10 CK ACTIVE CVC CMP 73ST-9X132 VALVE (PEN. 12) 2 SA C
SGEPSV0691 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F15 SV ACTIVE 038788)
LINE 2 (PEN. 2) 2 SA O/C SGEPSV0692 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H15 SV ACTIVE 038788)
LINE 1 (PEN. 1) 2 SA O/C SGEV693 SGP-002 8
C BDO CMP Normal Ops Notes 1,2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK Cl1 CK ACTIVE CVC CMP 73ST-9XI32 VALVE (PEN. 12) 2 SA C
SGEPSV0694 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A15 SV ACTIVE 038788)
LINE 2 (PEN. 4) 2 SA O/C SGEPSVO695 SGP-001 sht 1 6
C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D15 SV ACTIVE 038788)
LINE 1 (PEN. 3) 2 SA O/C SGEV887 SGP-001 sht 1 2
C CVC CMP 73ST-9X136 Notes 1,2, 3, 4 WARM-UP LINE CHECK VALVE TO D12 CK ACTIVE CVO CMP 73ST-9AF02 TURBINE-DRIVEN AFW PUMP 3
SA O/C SGEV888 SGP-001 sht 1 2
C CVC CMP 73ST-9X136 Notes 1, 2, 3, 4 WARM-UP LINE CHECK VALVE TO C13 CK ACTIVE CVO CMP 73ST-9AF02 TURBINE-DRIVEN AFW PUMP 3
SA O/C SGEV982 SGP-001 sht 2 1
AC BDO CMP 73ST-9SG05 Notes 1, 2, 3, 4 ADV NITROGEN SUPPLY CHECK VALVE B06 CK ACTIVE CVC CMP 73ST-9SG05 SA C
LT 2YR 73ST-9SG05 SGEV985 SGP-001 sht 2 1
AC BDO CMP 73ST-9SG05 Notes 1, 2, 3, 4 ADV NITROGEN SUPPLY CHECK VALVE G06 CK ACTIVE CVC CMP 73ST-9SG05 3
SA C
LT 2YR 73ST-9SG05
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 36 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SGEV988 SGP-001 sht 2 1
AC BDO CMP 73ST-9SG05 Notes 1, 2, 3, 4 ADV NITROGEN SUPPLY CHECK VALVE D06 CK ACTIVE CVC CMP 73ST-9SG05 3
SA C
LT 2YR 73ST-9SG05 SGEV991 SGP-001 sht 2 1
AC BDO CMP 73ST-9SG05 Notes 1, 2, 3, 4 ADV NITROGEN SUPPLY CHECK VALVE F06 CK ACTIVE CVC CMP 73ST-9SG05 SA C
LT 2YR 73ST-9SG05 SGAUV1133 SGP-001 sht 1 1
B FSC QTR 73ST-9XI01 STEAM TRAP SGN-M23 ISOLATION VALVE E15 GL ACTIVE FTC QTR 73ST-9XI01 (PEN. 2) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9X132 SGAUV1134 SGP-001 sht 1 1
B FSC QTR 73ST-9XI02 STEAM TRAP SGN-M24 ISOLATION VALVE C14 GL ACTIVE FTC QTR 73ST-9XI02 (PEN. 3) 2 so C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI32 SGBUV1135A SGP-001 sht 1 1
B FSC QTR 73ST-9XI01 STEAM TRAP SGN-M01 ISOLATION VALVE Hll GL ACTIVE FTC QTR 73ST-9XI01 (PEN. 1) 2 so C
STC QTR 73ST-9X101 VP 2YR 73ST-9XI32 SGBUV1135B SGP-001 sht 1 1
B FSC QTR 73ST-9X101 STEAM TRAP SGN-M02 ISOLATION VALVE Fll GL ACTIVE FTC QTR 73ST-9X101 (PEN. 2) 2 so C
STC QTR 73ST-9XI01 VP 2YR 73ST-9XI32 SGBUVI136A SGP-001 1
B FSC QTR 73ST-9XI02 STEAM TRAP SGN-M03 ISOLATION VALVE Dll GL ACTIVE FTC QTR 73ST-9XI02 (PEN. 3) 2 s0 C
STC QTR 73ST-9XI02 VP 2YR 73ST-9XI32 SGBUV1136B SGP-001 sht 1 1
B FSC QTR 73ST-9XI02 STEAM TRAP SGN-M04 ISOLATION VALVE All GL ACTIVE FTC QTR 73ST-9XI02 (PEN. 4) 2 50 C
STC QTR 73ST-9XI02 VP 2YR 73ST-9X132 SGEPSE1183 SGP-001 sht 2 1
AD LT 2YR 73ST-9SG05 Replaced every 5 years per ADV NITROGEN SUPPLY RUPTURE DISK F05 RD ACTIVE REP 5YR Task# 89948 Mandatory Appendix I, 1-1360 3
SA O/C SGEPSE1184 SGP-001 sht 2 1
AD LT 2YR 73ST-9SG05 Replaced every 5 years per ADV NITROGEN SUPPLY RUPTURE DISK D05 RD ACTIVE REP 5YR Task# 89951 Mandatory Appendix I, 1-1360 3
SA O/C SGEPSE1185 SGP-001 sht 2 1
AD LT 2YR 73ST-9SG05 Replaced every 5 years per ADV NITROGEN SUPPLY RUPTURE DISK B05 RD ACTIVE REP 5YR Task# 108503 Mandatory Appendix 1, 1-1360 3
SA O/C SGEPSE1186 SGP-001 sht 2 1
AD LT 2YR 73ST-9SG05 Replaced every 5 years per ADV NITROGEN SUPPLY RUPTURE DISK G05 RD ACTIVE REP 5YR Task# 108443 Mandatory Appendix I, 1-1360 3
SA O/C SIAVA10 SIP-002 1
C CVC CMP 73ST-9XI21 Notes 1,2, 3, 4 PRESSURE LOCKING CHECK VALVE FOR G03 CK ACTIVE CVO CMP 73ST-9XI21 SIAUV0655 BONNET 2
SA O/C SIBVA15 SIP-002 1
C CVC CMP 73ST-9XI21 Notes 1,2, 3, 4 PRESSURE LOCKING CHECK VALVE FOR G1O CK ACTIVE CVO CMP 73ST-9XI21 SIBUV0656 BONNET (PEN. 26) 2 SA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 37 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIEV113 SIP-002 3
C CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 HPSI CHECK VALVE TO RCS COLD LEG F14 CK ACTIVE CVO CMP 73ST-9XI33 INJECTION HEADER 2
SIEV114 SIP-002 12 C
CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 LPSI CHECK VALVE TO RCS COLD LEG F13 CK ACTIVE CVO CMP 73ST-9XI27 INJECTION HEADER 2
SIEV123 SIP-002 3
C CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 HPSI CHECK VALVE TO RCS COLD LEG F12 CK ACTIVE CVO CMP 73ST-9X133 INJECTION HEADER 2
SIEV124 SIP-002 12 C
CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 LPSI CHECK VALVE TO RCS COLD LEG Fl1 CK ACTIVE CVO CMP 73ST-9X127 INJECTION HEADER 2
SIEV133 SIP-002 3
C CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 HPSI CHECK VALVE TO RCS COLD LEG' F07 CK ACTIVE CVO CMP 73ST-9X133 INJECTION HEADER 2
SIEV134 SIP-002 12 C
CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 LPSI CHECK VALVE TO RCS COLD LEG F06 CK ACTIVE CVO CMP 73ST-9XI26 INJECTION HEADER 2
SIBPSVO140 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve SI PUMP SUCTION LINE FROM B15 SV ACTIVE CONTAINMENT SUMP PRESSURE RELIEF 2
SIBPSVO141 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE RELIEF VALVE BETWEEN B15 SV ACTIVE ISOLATION VALVES TO FUEL POOL 3
SA O/C COOLING SIEV143 SIP-002 3
C CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 HPSI CHECK VALVE TO RCS COLD LEG F04 CK ACTIVE CVO CMP 73ST-9XI33 INJECTION HEADER 2
SIEV144 SIP-002 12 C
CVC CMP 73ST-9SI05 Notes 1,2, 3, 4 LPSI CHECK VALVE TO RCS COLD LEG F04 CK ACTIVE CVO CMP 73ST-9XI26 INJECTION HEADER 2
SIAPSVOI50 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE RELIEF VALVE BETWEEN H15 SV ACTIVE ISOLATION VALVES TO FUEL POOL 3
SA O/C COOLING SIAPSVO151 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve SI PUMP SUCTION LINE FROM CONTMT G15 SV ACTIVE SUMP PRESSURE RELIEF VALVE (PEN.
2 SA O/C 23)
SLAV157 SIP-001 18 C
BDC CMP 73ST-9SI06 Notes 1,2, 3, 4 CONTAINMENT SPRAY PUMP SUCTION G13 CK ACTIVE CVO CMP 73ST-9SI06 LINE CHECK VALVE 2
SA 0
SIBV158 SIP-001 18 C
BDC CMP 73ST-9SI06 Notes 1,2, 3, 4 CONTAINMENT SPRAY PUMP SUCTION B13 CK ACTIVE CVO CMP 73ST-9S106 LINE CHECK VALVE 2
SA 0
SIAPSVO161 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve LPSI/SDC LINE PRESSURE RELIEF VALVE H06 SV ACTIVE 2
SA O/C
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Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIAPSVO162 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE RELIEF VALVE BETWEEN G05 SV ACTIVE ISOLATION VALVES TO FUEL POOL 3
SA O/C COOLING SIAV164 SIP-002 10 AC AJ CLR 73ST-9CLO1 Notes 1,3, 4 CONTAINMENT SPRAY HEADER CHECK F08 CK ACTIVE CVC CMP 73ST-9CLO1 VALVE AND INBOARD CIV (PEN. 21) 2 SA O/C CVO CMP 73ST-9CLOl SIBV165 SIP-002 10 AC AJ CLR 73ST-9CLO1 Notes 1,3, 4 CONTAINMENT SPRAY HEADER CHECK F06 CK ACTIVE CVC CMP 73ST-9CL01 VALVE AND INBOARD CIV (PEN. 22) 2 SA O/C CVO CMP 73ST-9CLO1 SIBPSVO166 SIP-002 0.75 C
SV 10Y 73ST-9ZZ20 HPSI LONG TERM RECIRC PRESSURE G09 SV ACTIVE RELIEF VALVE 2
SA O/C SIBPSVOI69 SIP-002 0.75 C
SV 5YR 73ST-9ZZ20 Thermal Relief Valve SHUTDOWN COOLING LINE PRESSURE D10 SV ACTIVE RELIEF VALVE 1
SA O/C SIAPSVO179 SIP-002 6
C SV 10Y 73ST-9ZZ19 SHUTDOWN COOLING RETURN LINE G03 SV ACTIVE LTOP RELIEF VALVE (PEN. 27) 2 SA O/C SIBPSVO189 SIP-002 6
C SV 10Y 73ST-9ZZ19 SHUTDOWN COOLING RETURN LINE FIll SV ACTIVE LTOP RELIEF VALVE (PEN. 26) 2 SA O/C SIBPSVO191 SIP-001 1.5 C
SV 10Y 73ST-9ZZ20 SHUTDOWN COOLING HEAT D07 SV ACTIVE EXCHANGER OUTLET PRESSURE 2
SA O/C RELIEF VALVE SIBPSVO192 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve PRESSURE RELIEF VALVE BETWEEN C05 SV ACTIVE ISOLATION VALVES TO FUEL POOL 3
SA O/C COOLING SIBPSVOI93 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve LPSI/SDC LINE PRESSURE RELIEF VALVE D06 SV ACTIVE 2
SA O/C SIAPSVO194 SIP-001 1.5 C
SV 10Y 73ST-9ZZ20 SHUTDOWN COOLING HEAT H07 SV ACTIVE EXCHANGER OUTLET PRESSURE 2
SA O/C RELIEF VALVE SIBV200 SIP-001 20 C
BDC CMP 73ST-9XI 11 Note 1, 2, 3, 4 LPSI PUMP SUCTION LINE CHECK VALVE B12 CK ACTIVE CVO CMP 73ST-9XI 11 2
SA 0
SLAV201 SIP-001 20 C
BDC CMP 73ST-9XI 11 Note 1, 2, 3, 4 LPSI PUMP SUCTION LINE CHECK VALVE F13 CK ACTIVE CVO CMP 73ST-9XI11 2
SA 0
SIAV205 SIP-001 24 C
BDC CMP 73ST-9ZZ25 Notes 1,3, 4 CONTAINMENT RECIRCULATION SUMP F14 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection CHECK VALVE TO SI SUPPLY HEADER 2
SA 0
SIBV206 SIP-001 24 C
BDC CMP 73ST-9ZZ25 Notes 1,3, 4 CONTAINMENT RECIRCULATION SUMP A14 CK ACTIVE CVO CMP 73ST-9ZZ25 Disassembly and Inspection CHECK VALVE TO SI SUPPLY HEADER 2
SA 0
SIEPSVO211 SIP-002 2
C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 2A PRESSURE E15 SV ACTIVE RELIEF VALVE 2
SA O/C SIEV215 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 Leak test frequency is 18 months SAFETY INJECTION TANK DISCHARGE A15 CK ACTIVE CVO CMP 73ST-9XI25 per TS SfR 3.4.15. 1.
SA O/C LT 18M 73ST-9SI03
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 39 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIEV217 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION LOOP A13 CK ACTIVE CVO CMP 73ST-9XI25 Leak test frequency is 18 months CHECK VALVE 1
SA O/C LT 18M 73ST-9SI033.4.15.1.
SIEPSVO221 SIP-002 2
C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 2B PRESSURE E12 SV ACTIVE RELIEF VALVE 2
SA O/C SIEV225 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 A12 K
ATIV c~~ OM 73T-9125Leak test frequency is 18 months SAFETY INJECTION TANK DISCHARGE A12 CK ACTIVE CVO CMP 73ST-9XI25 Lea ts fr 3.4.15.1.
SA O/C LT 18M 73ST-9SI03 SIEV227 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION LOOP A10 CK ACTIVE CVO CMP 73ST-9XI25 Leak test frequency is 18 months CHECK VALVE 1
SA O/C LT 18M 73ST-9SI03 per TS SR 3.4.15.1.
SIEPSVO231 SIP-002 2
C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 1A PRESSURE E08 SV ACTIVE RELIEF VALVE 2
SA O/C SIEV235 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 SAFETY INJECTION TANK DISCHARGE A07 CK ACTIVE CVO CMP 73ST-9XI25 Leak test frequency is 18 months CHECK VALVE 1
SA O/C LT 18M 73ST-9SI03 per TS SR 3.4.15.1.
SIEV237 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION LOOP A06 CK ACTIVE CVO CMP 73ST-9XI25 Leak test frequency is 18 months CHECK VALVE 1
SA O/C LT 18M 73ST-9SI33.4.15.1.
SIEPSVO241 SIP-002 2
C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 1B PRESSURE E05 SV ACTIVE RELIEF VALVE 2
SA O/C SIEV245 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 SAFETY INJECTION TANK DISCHARGE A05 CK ACTIVE CVO CMP 73ST-9X125 Leak test frequency is 18 months CHECK VALVE 1
SA O/C LT 18M 73ST-9SI03 per TS SR 3.4.15.1.
SIEV247 SIP-002 14 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 Leak test frequency is 18 months COLD LEG SAFETY INJECTION LOOP A04 CK ACTIVE CVO CMP 73ST-9XI25 per TS SR 3.4.15.1.
SA O/C LT 18M 73ST-9SI03 SIAPSVO285 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve SI PUMP COMBINED RECIRC PRESSURE F09 SV ACTIVE RELIEF VALVE 2
SA O/C SIBPSVO286 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve SI PUMP COMBINED RECIRC PRESSURE B09 SV ACTIVE RELIEF VALVE 2
SA O/C SIBPSVO287 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve CONTAINMENT SPRAY LINE PRESSURE C09 SV ACTIVE RELIEF VALVE 2
SA O/C SIEPSVO288 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SI MAXIFLOW RECIRC LINE RELIEF VALVE E05 SV ACTIVE 3
SA O/C SIAPSVO289 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve CONTAINMENT SPRAY LINE PRESSURE G09 SV ACTIVE RELIEF VALVE 2
SA O/C SIAHV0306 SIP-001 10 B
FSC 1CY 73ST-xXI11 VRR-01 FSO includes position stop LPSI DISCHARGE HEADER ISOLATION G05 GL ACTIVE FSO 1CY 73ST-xXIll VRR-01 verification perTS SR 3.5.3.7 VALVE 2
MO O/C Note 5 SIBHV0307 SIP-001 10 B
FSC 1CY 73ST-xXI12 VRR-01 FSO includes position stop LPSI HEADER DISCHARGE ISOLATION B04 GL ACTIVE FSO 1CY 73ST-xXI12 VRR-01 verification perTS SR 3.5.3.7 VALVE 2
MO O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 40 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLESr 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SICHV0321 SIP-002 3
B FSC QTR 73ST-xXI 11 VRR-01 FSO includes position stop HPSI LONG TERM RECIRCULATION CIV G02 GL ACTIVE FSO QTR 73ST-xXI 11 VRR-01 verification per TS SR 3.5.3.7 HPILN TR EICUAINC Note 5 (PEN. 77) 2 MO O/C QTR FS FOR PRA/RA.
SIBUVO322 SIP-002 1
B FSC QTR 73ST-9XI13 HOT LEG INJECTION CHECK VALVE LEAK E02 GL ACTIVE FTC QTR 73ST-9XI 13 ISOLATION VALVE 1
AO C
STC QTR 73ST-9X113 VP 2YR 73ST-9XI13 SIDHV0331 SIP-002 3
B FSC QTR 73ST-xXI12 VRR-01 FSO includes position stop HPSI LONG TERM RECIRCULATION CIV G09 GL ACTIVE FSO QTR 73ST-xXI12 VRR-01 verification per TS SR 3.5.3.7 (PEN. 67) 2 MO O/C Note 5 OTR FS FOR PRA/RA.
SIBUVO332 SIP-002 1
B FSC QTR 73ST-9XI14 HOT LEG INJECTION CHECK VALVE LEAK El0 GL ACTIVE FTC QTR 73ST-9XI14 ISOLATION VALVE 1
AO C
STO QTR 73ST-9XI14 VP 2YR 73ST-9XI14 SIAV404 SIP-001 4
C CVC CMP 73ST-9XI33 Notes 1, 2, 3, 4 HPSI PMP DISCHARGE CHECK VALVE F06 CK ACTIVE CVO CMP 73ST-9XI33 FSC also performed in 73ST-2 SA O/C SIBV405 SIP-001 4
C CVC CMP 73ST-9XI33 Notes 1,2, 3, 4 HPSI PMP DISCHARGE CHECK VALVE B04 CK ACTIVE CVO MP 73ST-9X33 FSC also performed in 73T-2 SA O/C 9XI35 SIEPSVO407 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SAFETY INJECTION TANK FILL LINE E08 SV ACTIVE RELIEF VALVE 3
SA O/C SIBPSVO409 SIP-001 1.5 C
SV 10Y 73ST-9ZZ20 HPSI LINE PRESSURE RELIEF VALVE B02 SV ACTIVE 2
SA O/C SIAPSVO417 SIP-001 1.5 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve HPSI LINE PRESSURE RELIEF VALVE F02 SV ACTIVE 2
SA O/C SIAV424 SIP-001 2
C BDC QTR 73ST-9SI 11 Notes 1,2, 3 HPSI PUMP RECIRC LINE CHECK VALVE F10 CK ACTIVE CVO QTR 73ST-9SI10 2
SA 0
SlBV426 SIP-001 2
C BDC QTR 73ST-9SI11 Notes 1,2, 3 HPSI PUMP RECIRC LINE CHECK VALVE A10 CK ACTIVE CVO QTR 73ST-9SI10 VRR-01 2
SA 0
SIAV434 SIP-001 10 C
BDC CMP 73ST-9SI14 Notes 1,2, 3, 4 LPSI PUMP DISCHARGE CHECK VALVE F09 CK ACTIVE CVO CMP 73ST-9SI14 2
SA 0
SIAPSVO439 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 LPSI LINE PRESSURE RELIEF VALVE H02 SV ACTIVE 2
SA O/C SIBV446 SIP-001 10 C
BDC CMP 73ST-9SI14 Notes 1,2, 3, 4 LPSI PUMP DISCHARGE CHECK VALVE B09 CK ACTIVE CVO CMP 73ST-9SI14 2
SA 0
SIBV448 SIP-001 2
C BDC QTR 73ST-9SI06 Notes 1,2, 3 LPSI PMP RECIRC LINE CHECK VALVE B10 CK ACTIVE CVO QTR 73ST-9S111 2
SA 0
SIBPSVO449 SIP-001 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve LPSI LINE PRESSURE RELIEF VALVE D02 SV ACTIVE 2
SA O/C SIAV451 SIP-001 2
C BDC QTR 73ST-9SIa6 Notes 1,2, 3 LPSI PMP RECIRC LINE CHECK VALVE Gl1 CK ACTIVE CVO QTR 73ST-9S 111 2
SA 0
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 41 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type AlP ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIEV463 SIP-001 2
A AJ CLR 73ST-9CLO1 SAFETY INJECTION TANK FILL/DRAIN D08 GL PASSIVE HEADER OUTBOARD CIV (PEN. 28) 2 MA C
SIAPSVO468 SIP-002 0.75 C
SV 10Y 73ST-9ZZ20 Thermal Relief Valve HPSI LONG TERM RECIRC PRESSURE G02 SV ACTIVE RELIEF VALVE 2
SA O/C SIAPSVO469 SIP-002 0.75 C
SV 5YR 73ST-9ZZ20 Thermal Relief Valve SHUTDOWN COOLING LINE PRESSURE D03 SV ACTIVE RELIEF VALVE 1
SA O/C SIEPSVO473 SIP-001 1
C SV 10Y 73ST-9ZZ20 Thermal Relief Valve SAFETY INJECTION TANK FILL/DRAIN E10 SV ACTIVE LINE PRESSURE RELIEF VALVE 2
SA O/C SIEPSV0474 SIP-001 0.75 AC AJ CLR 73ST-9CL01 Thermal Relief Valve SAFETY INJECTION TANK FILL/DRAIN D09 SV ACTIVE SV 10Y 73ST-9ZZ20 LINE PRESSURE RELIEF VALVE (PEN. 28) 2 SA OIC SIBV484 SIP-001 10 C
BDC CMP 73ST-9SI15 Notes 1,2, 3, 4 CONTAINMENT SPRAY PUMP C10 CK ACTIVE CVO CMP 73ST-9SI15 DISCHARGE CHECK VALVE 2
SA 0
SIAV485 SIP-001 10 C
BDC CMP 73ST-9SI15 Notes 1,2, 3, 4 CONTAINMENT SPRAY PUMP H10 CK ACTIVE CVO CMP 73ST-9SI15 DISCHARGE CHECK VALVE 2
SA 0
SIAV486 SIP-001 2
C BDC QTR 73ST-9SI10 Notes 1,2, 3 CONTAINMENT SPRAY PMP RECIRC LINE G10 CK ACTIVE CVO QTR 73ST-9S106 CHECK VALVE 2
SA 0
SIBV487 SIP-001 2
C BDC QTR 73ST-9SI10 Notes 1,2, 3 CONTAINMENT SPRAY PMP RECIRC LINE C10 CK ACTIVE CVO QTR 73ST-9S106 CHECK VALVE 2
SA 0
SIAV522 SIP-002 3
AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 HPSI LONG-TERM RECIRC CHECK VALVE C02 CK ACTIVE CVO CMP 73ST-9XI33 Leak teat frequency is 18 months 1
SA O/C LT 18M 73ST-9S103 per TS SR 3.4.15.1 SIAV523 SIP-002 3
AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 HPSI LONG-TERM RECIRC INBOARD CIV F02 CK ACTIVE CVO CMP 73ST-9X133 Leak test frequency is 18 months (PEN. 77) 1 SA O/C LTer TS SR 3.4.15.1 SIBV532 SIP-002 3
AC CVC CMP 73ST-9SI03 Notes 1, 2, 3, 4 HPSI LONG-TERM RECIRC CHECK VALVE B10 CK ACTIVE CVO CMP 73ST-9XI33 Leak test frequency is 18 months 1
SA O/C LT 18M 73ST-9SI03 perTS SR 3.4.15.1 SIBV533 SIP-002 3
AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 HPSI LONG-TERM RECIRC INBOARD CIV F09 CK ACTIVE CVO CMP 73ST-9XI33 Leak test frequency is 18 months (PEN. 67) 1 SA O/C LT 18M 73ST-9SIp3 perTS SR 3.4.15.1 SIEV540 SIP-002 12 AC CVC CMP 73ST-9S103 Notes 1,2,3,4 COLD LEG SAFETY INJECTION CHECK B13 CK ACTIVE CLeak test frequency is 18 months VALVE 1
SA I/C CVO CMP 73ST-9SI33 per TS SR 3.4.15.1 LT 18M 73ST-9SI03 SIEV541 SIP-002 12 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION CHECK B11 CK ACTIVE CVO CMP 73ST-9SI33 Leak test frequency is 18 months VALVE 1
SA O/C LT 18M 73ST-9SIp3 per TS SR 3.4.15.1 SIEV542 SIP-002 12 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION CHECK C06 CK ACTIVE CVO CMP 73ST-9SI33 Leak test frequency is 18 months VALVE 1
SA O/C LT 18M 73ST-9SI03 per TS SR 3.4.15.1 SIEV543 SIP-002 12 AC CVC CMP 73ST-9SI03 Notes 1,2, 3, 4 COLD LEG SAFETY INJECTION CHECK C04 CK ACTIVE CVO CMP 73ST-9SI33 Leak test frequency is 18 months VALVE 1
SA O/C LT 18M 73ST-9SI33.15.1
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 42 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSj/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIAHV0604 SIP-001 3
B FSC QTR 73ST-9XI13 VRR-01 Note 5 HPSI LONG TERM RECIRC ISOLATION G03 GA ACTIVE FSO QTR 73ST-9XI13 VRR-01 QTR FS FOR PRA/RA.
VALVE 2
MO O/C SIAHV0605 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-1 0 SAFETY INJECTION TANK 2A F15 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
SO O/C FTC OSO 73ST-9XI37 CSJ-1 0 STC CSD 73ST-9XI37 CSJ-1 0 STO CSD 73ST-9XI37 CSJ-1 0 VP 2YR 73ST-9XI37 SIAHV0606 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-10 SAFETY INJECTION TANK 2B F12 GL ACTIVE FSO CSD 73ST-9X137 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9X137 CSJ-10 STC CSD 73ST-9X137 CSJ-10 STO CSD 73ST-9X137 CSJ-10 VP 2YR 73ST-9X137 SIAHV0607 SIP-002 1
B FSC CSD 73ST-9X137 CSJ-10 SAFETY INJECTION TANK 1A F07 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9XI37 CSJ-10 STO CSD 73ST-9XI37 CSJ-10 STO 0SD 73ST-9X137 CSJ-10 VP 2YR 73ST-9XI37 SIAHV0608 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-lO SAFETY INJECTION TANK 1B F04 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9X137 CSJ-10 STO CSD 73ST-9X137 CSJ-10 VP 2YR 73ST-9XI37 SIBHV0609 SIP-001 3
B FSC QTR 73ST-9XI14 VRR-01 Note 5 HPSI LONG TERM RECIRC ISOLATION C03 GA ACTIVE FSO QTR 73ST-9XI14 VRR-01 QTR FS FOR PRAIRA.
VALVE 2
MO O/C SIBUVO611 SIP-002 2
B FSC QTR 73ST-9XI04 SAFETY INJECTION TANK 2A FILL/DRAIN B16 GL ACTIVE FTC QTR 73ST-9XI04 ISOLATION VALVE 2
AO C
STC QTR 73ST-9X104 VP 2YR 73ST-9XI04 SIBHV0613 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-10 SAFETY INJECTION TANK 2A E15 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9XI37 CSJ-10 STO CSD 73ST-9X137 CSJ-10 VP 2YR 73ST-9XI37 SIBUVO614 SIP-002 14 B
FSO 1CY 73ST-9XI25 VRR-01 Note 5 SAFETY INJECTION TANK 2A DISCHARGE A15 GA ACTIVE STO 18M 73ST-9XI25 VRR-01 18M ST FORTS 3.3.5.4 ISOLATION VALVE 1
MO 0
SIBUVO615 SIP-002 12 B
FSO 1CY 73ST-xXI12 VRR-01 FSO includes position stop LPSI DISCHARGE HEADER OUTBOARD G14 GL ACTIVE STO 18M 73ST-xXI12 VRR-01 verification per SR 3.5.3.7 CIV (PEN. 17) 2 MO O
18M STforTS 3.3.5.4 Note 5 SIBUV0616 SIP-002 2
B FSO QTR 73ST-9XI14 VRR-01 Note 5 G14 GLACTIVEQTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD G14 GL ACTIVE STO 18M 73ST-9XI14 VRR-01 18M ST FOR TS 3.3.5.4 CIV (PEN. 13) 2 MO O
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 43 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLESI921 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIAUV0617 SIP-002 2
B FSO QTR 73ST-9XI13 VRR-01 Note 5 QTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD G15 GL ACTIVE STO 18M 73ST-9XI13 VRR-01 18M ST FOR TS 3.3.5.4 CIV (PEN. 13) 2 MO 0
SIBUVO618 SIP-002 1
B FSC QTR 73ST-9XI04 SAFETY INJECTION TANK 2A CHECK B16 GL ACTIVE FTC QTR 73ST-9X104 VALVE LEAKAGE TEST LINE ISOLATION 1
AO C
SCQR75-X0 VALVE STC QTR 73ST-9XI04 VP 2YR 73ST-9X104 SIAHV0619 SIP-002 1
B VP 2YR 73ST-9X125 SIT NITROGEN SUPPLY ISOLATION VALVE D15 GL PASSIVE 2
AO C
SIBUV0621 SIP-002 2
B FSC QTR 73ST-9XI04 SAFETY INJECTION TANK 2B FILL/DRAIN B12 GL ACTIVE FTC QTR 73ST-9XI04 ISOLATION VALVE 2
AO C
STC QTR 73ST-9XI04 VP 2YR 73ST-9XI04 SIBHV0623 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-10 SAFETY INJECTION TANK 2B E12 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9XI37 CSJ-10 STO CSD 73ST-9XI37 CSJ-10 VP 2YR 73ST-9XI37 SIBUVO624 SIP-002 14 B
FSO 1CY 73ST-9XI25 VRR-01 Note5 SAFETY INJECTION TANK 28 DISCHARGE A12 GA ACTIVE STO 18M 73ST-9XI25 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE 1
MO 0
SIBUVO625 SIP-002 12 B
FSO lCY 73ST-xXI12 VRR-01 FSO includes position stop LPSI DISCHARGE HEADER OUTBOARD Gl1 GL ACTIVE STO 18M 73ST-xXI 12 VRR-01 verification per SR 3.5.3.7 CIV (PEN. 18) 2 MO O
18M ST forTS 3.3.5.4 Note 5 SIBUVO626 SIP-002 2
B FSO QTR 73ST-9XI14 VRR-01 Note 5 QTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD Gl1 GL ACTIVE STO 18M 73ST-9XI14 VRR-01 18M ST FOR TS 3.3.5.4 CIV (PEN. 14) 2 MO 0
SIAUVO627 SIP-002 2
B FSO QTR 73ST-9XI13 VRR-01 Note 5 OTR FS FOR PRANRA HPSI DISCHARGE HEADER OUTBOARD G12 GL ACTIVE STO 18M 73ST-9XI13 VRR-01 18M ST FORTS 3.3.5.4 CIV (PEN. 14) 2 MO 0
SIBUVO628 SIP-002 1
B FSC QTR 73ST-9X104 SAFETY INJECTION TANK 2B CHECK B13 GL ACTIVE FTC QTR 73ST-9X104 VALVE LEAKAGE TEST LINE ISOLATION 1
AO C
VALVE STC QTR 73ST-9X104 VP 2YR 73ST-9XI04 SIAHV0629 SIP-002 1
B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D12 GL PASSIVE 2
AO C
SIBUVO631 SIP-002 2
B FSC QTR 73ST-9XI03 SAFETY INJECTION TANK 1A FILL/DRAIN C08 GL ACTIVE FTC QTR 73ST-9XI03 ISOLATION VALVE 2
AO C
STC QTR 73ST-9XI03 VP 2YR 73ST-9XI03 SIBHV0633 SIP-002 1
B FSC CSD 73ST-9XI37 CSJ-10 SAFETY INJECTION TANK 1A E07 GL ACTIVE FSO CSD 73ST-9XI37 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9XI37 CSJ-10 STO CSD 73ST-9XI37 CSJ-10 VP 2YR 73ST-9XI37
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 44 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIAUVO634 SIP-002 14 B
FSO 1CY 73ST-9XI25 VRR-01 Note 5 SAFETY INJECTION TANK 1A DISCHARGE B07 GA ACTIVE STO 18M 73ST-9XI25 VRR-01 18M ST FOR TS 3.3.5.4 ISOLATION VALVE 1
MO 0
SIAUVO635 SIP-002 12 B
FSO 1CY 73ST-xXI 11 VRR-01 FSO includes position stop LPSI DISCHARGE HEADER OUTBOARD G06 GL ACTIVE STO 18M 73ST-xXI 11 VRR-01 verification per SR 3.5.3.7 CIV (PEN. 19) 2 MO O
10M ST forTS 3.3.5.4 Note 5 SIBUVO636 SIP-002 2
B FSO QTR 73ST-9XI14 VRR-01 Note 5 QTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD G07 GL ACTIVE STO 18M 73ST-9XI14 VRR-01 18M ST FOR TS 3.3.5.4 CIV (PEN. 15) 2 MO 0
SIAUVO637 SIP-002 2
B FSO QTR 73ST-9XI13 VRR-01 Note 5 QTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD G08 GL ACTIVE STO 18M 73ST-9XI13 VRR-01 18M ST FORTS 3.3.5.4 CIV (PEN. 15) 2 MO 0
SIBUVO638 SIP-002 1
B FSC QTR 73ST-9XI03 SAFETY INJECTION TANK 1A CHECK B08 GL ACTIVE FTC QTR 73ST-9X103 VALVE LEAKAGE TEST LINE ISOLATION 1
AO C
VALVE STC QTR 73ST-9XI03 VP 2YR 73ST-9X103 SIAHV0639 SIP-002 1
B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D07 GL PASSIVE 2
AO C
SIBUVO641 SIP-002 2
B FSC QTR 73ST-9X103 SAFETY INJECTION TANK 1B FILL/DRAIN B06 GL ACTIVE FTC QTR 73ST-9XI03 ISOLATION VALVE 2
AO C
STC QTR 73ST-9XI03 VP 2YR 73ST-9X103 SIBHV0643 SIP-002 1
B FSC CSD 73ST-9X137 CSJ-10 SAFETY INJECTION TANK 1B E04 GL ACTIVE FSO CSD 73ST-9X137 CSJ-10 ATMOSPHERIC VENT VALVE 2
so O/C FTC CSD 73ST-9XI37 CSJ-10 STC CSD 73ST-9XI37 CSJ-10 STO CSD 73ST-9XI37 CSJ-10 VP 2YR 73ST-9XI37 SIAUV0644 SIP-002 14 B
FSO iCY 73ST-9XI25 VRR-01 Note5 SAFETY INJECTION TANK 1B DISCHARGE B04 GA ACTIVE STO 18M 73ST-9XI25 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 ISOLATION VALVE 1
MO 0
SIAUVO645 SIP-002 12 B
FSO 1CY 73ST-xXI11 VRR-01 FSO includes position stop LPSI DISCHARGE HEADER OUTBOARD G04 GL ACTIVE STO 18M 73ST-xXIll VRR-01 verification per SR 3.5.3.7 CIV (PEN. 20) 2 MO O
18M ST for TS 3.3.5.4 Note 5 SIBUVO646 SIP-002 2
B FSO QTR 73ST-9XI14 VRR-01 Note 5 OTR FS FOR PRA/RA HPSI DISCHARGE HEADER OUTBOARD G04 GL ACTIVE STO 18M 73ST-9XI14 VRR-01 18M ST FORTS 3.3.5.4 CIV (PEN. 16) 2 MO 0
SIAUVO647 SIP-002 2
B FSO QTR 73ST-9XI13 VRR-01 Note 5 HPSI DISCHARGE HEADER OUTBOARD G05 GL ACTIVE STO 18M 73ST-9XI13 VRR-01 QTR FS FOR PRA/RA CIV (PEN. 16) 2 MO O
18M ST FORTS 3.3.5.4 SIBUVO648 SIP-002 1
B FSC QTR 73ST-9X103 SAFETY INJECTION TANK 1B CHECK B06 GL ACTIVE FTC QTR 73ST-9X103 VALVE LEAKAGE TEST LINE ISOLATION 1
AO C
VALVE STC QTR 73ST-9XI03 VP 2YR 73ST-9X103 SIAHV0649 SIP-002 1
B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D05 GL PASSIVE 2
AO C
SIAUVO651 SIP-002 16 A
FSC iCY 73ST-9X121 VRR-01 Leak test frequency is 18 months SHUTDOWN COOLING SUCTION C03 GA ACTIVE FSO iCY 73ST-9X121 VRR-01 perTS SR 3.4.15.1 ISOLATION VALVE 1
MO O/C LT 18M 73ST-9SI03 Note 5
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 45 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 21Revisi AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIBUVO652 SIP-002 16 A
FSC iCY 73ST-9XI21 VRR-01 Leak test frequency is 18 months per TS SR 3.4.15.1 SHUTDOWN COOLING SUCTION C10 GA ACTIVE FSO iCY 73ST-9XI21 VRR-01 Note 5 ISOLATION VALVE 1
MO O/C LT 18M 73ST-9SI53 SICUVO653 SIP-002 16 A
FSC CSD 73ST-9XI21 CSJ-05 Leak test frequency is 18 months SHUTDOWN COOLING SUCTION D03 GA ACTIVE FSO CSD 73ST-9XI21 CSJ-05 perTS SR 3.4.15.1 INBOARD CIV (PEN. 27) 1 MO 0/C Note 5 LT 18M 73ST-9SI03 PRA/RA REQ'D QTR EXERCISING IS N/A PER CSJ-11.
SIDUVO654 SIP-002 16 A
FSC CSD 73ST-9XI21 CSJ-05 Leak test frequency is 18 months C~_5per TS SIR 3.4.15.1 SHUTDOWN COOLING SUCTION D10 GA ACTIVE FSO CSD 73ST-9XI21 CSJ-05 5e S INBOARD CIV (PEN. 26)
MO O/C LT 18M 73ST-9SI53 PRARA REQ'D QTR EXERCISING IS N/A PER CSJ-11.
SIAUVO655 SIP-002 16 B
FSC iCY 73ST-9XI21 VRR-01 Note 5 SHUTDOWN COOLING SUCTION G03 GA ACTIVE FSO iCY 73ST-9XI21 VRR-01 OUTBOARD CIV (PEN. 27) 2 MO O/C SIBUVO656 SIP-002 16 B
FSC ICY 73ST-9XI21 VRR-01 Note5 SHUTDOWN COOLING SUCTION G10 GA ACTIVE FSO iCY 73ST-9XI21 VRR-01 OUTBOARD CIV (PEN. 26) 2 MO O/C SIAHV0657 SIP-001 16 B
FSC iCY 73ST-9XI13 VRR-01 Note 5 SHUTDOWN COOLING HEAT H03 BF ACTIVE FSO iCY 73ST-9XI13 VRR-01 EXCHANGER OUTLET THROTTLE VALVE 2
MO O/C SIBHV0658 SIP-001 16 B
FSC iCY 73ST-9XI14 VRR-01 Note 5 SHUTDOWN COOLING HEAT C03 BF ACTIVE FSO iCY 73ST-9XI14 VRR-01 EXCHANGER OUTLET THROTTLE VALVE 2
MO O/C SIBUVO659 SIP-O01 4
B FSC QTR 73ST-9XI14 SI COMBINED RECIRC TO RWT B06 GL ACTIVE FSO QTR 73ST-9XI14 ISOLATION VALVE 2
so O/C FTC QTR 73ST-9XI14 STC QTR 73ST-9XI14 STO QTR 73ST-9XI14 VP 2YR 73ST-9XI14 SIAUVO660 SIP-O01 4
B FSC QTR 73ST-9XI13 SI COMBINED RECIRC TO RWT F06 GL ACTIVE FSO QTR 73ST-9XI13 ISOLATION VALVE 2
so O/C FTC QTR 73ST-9XI13 STC QTR 73ST-9XI13 STO QTR 73ST-9XI13 VP 2YR 73ST-9XI13 SIAUVO664 SIP-001 2
B FSC ICY 73ST-9XI03 VRR-01 Note 5 CP To GI GIL ACTIVE FSO iCY 73T-9X03 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT SPRAY PUMP RECIRC C
73ST-9SI06 may be required for RWT ISOLATION VALVE 2
MO 0/C STC 18M 73ST-9XI03 VRR-01 retest after open limit switch STO 18M 73ST-9XI03 VRR-01 adjustment SIBUV0665 SIP-001 2
B FSC ICY 73ST-9XI04 VRR-01 Note.5 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT SPRAY PUMP RECIRC TO B10 GL ACTIVE FSO 1CY 73ST-9XI04 VRR-01 73ST-9SI06 may be required for RWT ISOLATION VALVE 2
MO O/C STC 18M 73ST-9X104 VRR-01 retest after open limit switch STO 18M 73ST-9X104 VRR-01 adjustment SIAUVO666 SIP-001 2
B FSC iCY 73ST-9XI13 VRR-01 Note 5 HPSI PUMP RECIRC TO RWT ISOLATION F10 GL ACTIVE FSO ICY 73ST-9XI13 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 VALVE 2
MO O/C STC 18M 73ST-9XI13 VRR-01 STO 18M 73ST-9XI13 VRR-01
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 46 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIBUVO667 SIP-001 2
B FSC iCY 73ST-9XI14 VRR-01 Note 5 HPSI PUMP RECIRC TO RWT A10 GL ACTIVE FSO iCY 73ST-9XI14 VRR-01 18M ST REQ'D FORTS 3.3.5.4 2
MO O/C STC 18M 73ST-9XI14 VRR-01 STO 18M 73ST-9XI14 VRR-01 SIBUVO668 SIP-001 2
B FSC iCY 73ST-9X14 VRR-01 Note 5 LPSI PUMP RECIRC TO RWT ISOLATION B10 GL ACTIVE FSO iCY 73ST-9X14 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 VALVE 2
MO O/C STC 18M 73ST-9XI14 VRR-01 STO 18M 73ST-9XI14 VRR-01 SIAUVO669 SIP-001 2
B FSC ICY 73ST-9XI13 VRR-01 Note 5 LPSI PUMP RECIRC TO RWT ISOLATION G10 GL ACTIVE FSO ICY 73ST-9XI13 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 VALVE 2
MO 0/C STC 18M 73ST-9XI13 VRR-01 STO 18M 73ST-9XI13 VRR-01 SIBUVO671 SIP-O01 8
B FSC iCY 73ST-9XI04 VRR-01 Note 5 CONTAINMENT SPRAY CONTROL VALVE C06 GA ACTIVE FSO iCY 73ST-9XI04 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 AND OUTBOARD CIV (PEN. 22) 2 MO O/C SrC 18M 73ST-9X104 VRR-01 STO 18M 73ST-9XI04 VRR-01 SIAUVO672 SIP-001 8
B FSC iCY 73ST-9XI03 VRR-01 Note5 CONTAINMENT SPRAY CONTROL VALVE G06 GA ACTIVE FSO iCY 73ST-9XI03 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 AND OUTBOARD CIV (PEN. 21) 2 MO O/C STC 18M 73ST-9X103 VRR-01 STO 18M 73ST-9XI03 VRR-01 SIAUVO673 SIP-001 24 A
FSC 18M 73ST-9Xi03 VRR-01 Note5 CONTAINMENT SUMP TO SI PUMP G16 BF ACTIVE FSO 18M 73ST-9XI03 VRR-01 18M ST FORTS 3.3.5.4 SUCTION INBOARD CIV (PEN. 23) 2 MO O/C LT 2YR 73ST-9X143 STO 18M 73ST-9XI03 VRR-01 SIAUVO674 SIP-O01 24 B
FSO QTR 73ST-9XI03 VRR-01 Note 5 QTR FS FOR PRA/RA CONTAINMENT SUMP TO SI PUMP G14 BF ACTIVE STO 18M 73ST-9XI03 VRR-01 18M ST FOR TS 3.3.5.4 SUCTION OUTBOARD CIV 2
MO 0
(PEN. 23)
SIBUVO675 SIP-001 24 A
FSC 18M 73ST-9XI04 VRR-01 Note 5 CONTAINMENT SUMP TO SI PUMP A16 BF ACTIVE FSO 18M 73ST-9X104 VRR-01 18M ST FOR TS 3.3.5.4 SUCTION INBOARD CIV (PEN. 24) 2 MO O/C LT 2YR 73ST-9X143 STO 18M 73ST-9X104 VRR-01 SIBUVO676 SIP-001 24 B
FSO QTR 73ST-9X104 VRR-01 Note5 QTR FS FOR PRA/RA CONTAINMENT SUMP TO SI PUMP A14 BF ACTIVE STO 18M 73ST-9X104 VRR-01 18M ST FOR TS 3.3.5.4 SUCTION OUTBOARD CIV (PEN. 24) 2 MO O
SIAHV0678 SIP-01 10 B
FSC ICY 73ST-9XI03 VRR-01 Note 5 S/D COOLING HEAT EXCHANGER H09 GA ACTIVE FSO iCY 73ST-9XI03 VRR-01 ISOLATION TRAIN A 2
MO O/C SIBHV0679 SIP-001 10 B
FSC iCY 73ST-9XI04 VRR-01 Note 5 S/D COOLING HEAT EXCHANGER C09 GA ACTIVE FSO iCY 73ST-9X104 VRR-01 ISOLATION TRAIN B 2
MO O/C SIAUVO682 SIP-001 2
A AJ CLR 73ST-9CL01 SAFETY INJECTION TANK FILL LINE CIV D10 GL ACTIVE FSC QTR 73ST-9XI03 (PEN. 28) 2 AO C
FTC QTR 73ST-9X103 STC QTR 73ST-9X103 VP 2YR 73ST-9X103 SIAHV0683 SIP-001 20 B
FSC QTR 73ST-9X103 VRR-01 Note 5 LPSI PUMP SUCTION ISOLATION TRAIN A F13 GA ACTIVE FSO QTR 73ST-9XI03 VRR-01 QTR FS FOR PRA/RA 2
MO O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 47 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 I
Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIAHV0684 SIP-001 10 B
FSC iCY 73ST-9XI03 VRR-01 Note 5 CTMT SPRAY TO S/D COOLING HEAT H09 GA ACTIVE FSO iCY 73ST-9XI03 VRR-01 EXCHANGER ISOLATION TRAIN A 2
MO O/C SIAHV0685 SIP-001 10 B
FSC iCY 73ST-9XI13 VRR-01 Note5 LPSI PUMP TO SHUTDOWN COOLING G08 GA ACTIVE FSO iCY 73ST-9XI13 VRR-01 HEAT EXCHANGER ISOLATION VALVE 2
MO O/C SIAHV0686 SIP-001 20 B
FSC iCY 73ST-9XI13 VRR-01 Note 5 SHUTDOWN COOLING HEAT H06 GA ACTIVE FSO ICY 73ST-9XI13 VRR-01 EXCHANGER OUTLET TO LPSI ISOLATION 2
MO O/C VALVE SIAHV0687 SIP-001 10 B
FSC iCY 73ST-9XI13 Note 5 CTMT SPRAY ISOLATION TRAIN A G06 GA ACTIVE FSO ICY 73ST-9XI13 2
MO 0
SIAHV0688 SIP-OOl 10 B
FSC iCY 73ST-9X103 VRR-01 Note 5 CONTAINMENT SPRAY BYPASS VALVE G09 GA ACTIVE FSO iCY 73ST-9XI03 VRR-01 2
MO C
SIBHV0689 SIP-001 10 B
FSC iCY 73ST-9X104 VRR-01 Note 5 CTMT SPRAY TO S/D COOLING HEAT C09 GA ACTIVE FSO iCY 73ST-9X104 VRR-01 EXCHANGER ISOLATION TRAIN B 2
MO O/C SIBHV0690 SIP-002 10 B
FSC iCY 73ST-9XI04 VRR-01 Note 5 SHUTDOWN COOLING WARMUP BYPASS H13 GL ACTIVE FSO iCY 73ST-9XI04 VRR-01 CONTAINMENT ISOLATION VALVE (PEN.
2 MO O/C 26)
SIAHV0691 SIP-002 10 B
FSC iCY 73ST-9XI03 VRR-01 Note 5 SHUTDOWN COOLING WARMUP BYPASS H03 GL ACTIVE FSO iCY 73ST-9XI03 VRR-01 CONTAINMENT ISOLATION VALVE (PEN.
2 MO O/C 27)
SIBHV0692 SIP-001 20 B
FSC QTR 73ST-9XI04 VRR-01 Note 5 LPSI PUMP SUCTION ISOLATION TRAIN B B13 GA ACTIVE FSO QTR 73ST-9XI04 VRR-01 QTR FS FOR PRNRA 2
MO O/C SIBHV0693 SIP-001 10 B
FSC iCY 73ST-9XI04 VRR-01 Note 5 CONTAINMENT SPRAY BYPASS VALVE C09 GA ACTIVE FSO ICY 73ST-9XI04 VRR-01 2
MO O/C SIBHV0694 SIP-001 10 B
FSC iCY 73ST-9XI14 VRR-01 Note 5 LPSI CROSS CONNECT VALVE TO C08 GA ACTIVE FSO ICY 73ST-9XI14 VRR-01 SHUTDOWN COOLING HEAT EXCHANGER 2
MO O/C SIBHV0695 SIP-001 10 B
FSC iCY 73ST-9XI14 Note 5 CTMT SPRAY ISOLATION TRAIN B C06 GA ACTIVE FSO iCY 73ST-9XI14 2
MO 0
SIBHV0696 SIP-001 20 B
FSC iCY 73ST-9XI14 VRR-01 Note 5 SHUTDOWN COOLING HEAT C06 GA ACTIVE FSO iCY 73ST-9XI14 VRR-01 EXCHANGER OUTLET TO LPSI ISOLATION 2
MO O/C VALVE SIAHV0698 SIP-001 4
B FSC iCY 73ST-9XI33 VRR-01 Note 5 PREVIOUSLY TESTED IN 73ST-HPSI HEADER DISCHARGE ISOLATION F04 GA ACTIVE FSO 1CY 73ST-gXI33 VRR-01 9XI13.
VALVE 2
MO O/C SIBHV0699 SIP-001 4
B FSC iCY 73ST-9XI33 VRR-01 Note 5 PREVIOUSLY TESTED IN 73ST-HPSI HEADER DISCHARGE ISOLATION B03 GA ACTIVE FSO lCY 73ST-9XI33 VRR-01 9XI14.
VALVE 2
MO O/C SIAUVO708 SIP-001 0.5 B
STC RFO 73ST-9XI21 STC is an augmented test, CONTAINMENT SUMP TRAIN A SAMPLE G15 GL PASSIVE VP 2YR 73ST-9X21 performed at RFO to satisfy ESF TO PASS ISOLATION VALVE (PEN. 23) 2 P0 C response time testing per SR 3.3.5.4 and CIV isolation time testing per SR 3.6.3.5.
SIAUVO709 SIP-001 0.5 B
STC RFO 73ST-9XI21 STC is an augmented test, MINI-FLOW RECIRC LINE SAMPLE E08 GL PASSIVE VP 2YR 73ST-9XI21 performed at RFO to satisfy ESF ISOLATION VALVE 2
50 C
response time testing per SR 3.3.5.4.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 48 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-XI01 Revision AND COMPONENT TABLES 21 Drawing Size (in)
Cat.
CSJI Valve ID Coord/Sht#
Type A/P ROJI Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SIBUVO710 SIP-0O1 0.5 B
STC RFO 73ST-9XI21 STC is an augmented test, MINI-FLOW RECIRC LINE SAMPLE 807 GL PASSIVE VP 2YR 73ST-9XI21 performed at RFO to satisfy ESF ISOLATION VALVE 2
SO C
response time testing per SR 3.3.5.4.
SlAPSV0754 SIP-002 0.5 C
SV 5YR 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR B03 SV ACTIVE SIAUVO651 BONNET 1
SA O/C SIBPSVO755 SIP-002 0.5 C
SV 5YR 73ST-9ZZ20 Thermal Relief Valve PRESSURE LOCKING RELIEF VALVE FOR B03 SV ACTIVE SIBUV0652 BONNET 1
SA O/C SIAV997 SIP-002 1
C CVC CMP 73ST-9XI21 Notes 1,2, 3, 4 PRESSURE LOCKING CHECK VALVE FOR E03 CK ACTIVE CVO CMP 73ST-9XI21 SICUV0653 BONNET I
SA O/C SIBV998 SIP-002 1
C CVC CMP 73ST-9XI21 Notes 1,2, 3, 4 PRESSURE LOCKING CHECK VALVE FOR D10 CK ACTIVE CVO CMP 73ST-9XI21 SIDUV0654 BONNET 1
SA O/C SPBV012 SPP-00l 24 C
BDC CMP 73ST-9SP02 Notes 1,2, 3, 4 ESSENTIAL SPRAY POND PUMP C06 CK ACTIVE CVO CMP 73ST-9SP01 DISCHARGE CHECK VALVE 3
SA 0
SPAPSVO029 SPP-002 1
C SV 10Y 73ST-9ZZ20 ESSENTIAL COOLING WATER HEAT D03 SV ACTIVE EXCHANGER PRESSURE RELIEF VALVE 3
SA O/C SPBPSVO030 SPP-002 1
C SV 10Y 73ST-9ZZ20 ESSENTIAL COOLING WATER HEAT D06 SV ACTIVE EXCHANGER PRESSURE RELIEF VALVE 3
SA O/C SPAV041 SPP-001 24 C
BDC CMP 73ST-9SP02 Notes 1,2, 3, 4 ESSENTIAL SPRAY POND PUMP C04 CK ACTIVE CVO CMP 73ST-9SP01 DISCHARGE CHECK VALVE 3
SA 0
SPAPSVO137 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG FUEL OIL COOLER PRESSURE G02 SV ACTIVE RELIEF VALVE 3
SA O/C SPBPSV0138 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG LUBE OIL COOLER PRESSURE G06 SV ACTIVE RELIEF VALVE 3
SA O/C SPAPSVO139 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG JACKET WATER COOLER F02 SV ACTIVE PRESSURE RELIEF VALVE 3
SA O/C SPBPSVO140 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG AIR INTERCOOLER PRESSURE F06 SV ACTIVE RELIEF VALVE 3
SA O/C SPAPSVO141 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG AIR INTERCOOLER PRESSURE F02 SV ACTIVE RELIEF VALVE 3
SA O/C SPBPSV0142 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG JACKET WATER COOLER F06 SV ACTIVE PRESSURE RELIEF VALVE 3
SA O/C SPAPSVO143 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG LUBE OIL COOLER PRESSURE E02 SV ACTIVE RELIEF VALVE 3
SA O/C SPBPSVO144 SPP-002 2.5 C
SV 10Y 73ST-9ZZ20 EDG FUEL OIL COOLER PRESSURE F06 SV ACTIVE RELIEF VALVE 3
SA O/C SPEHCV0207 SPP-001 10 B
FSC 6M 73ST-9XI31 SPRAY POND CROSSCONNECT VALVE E05 BF ACTIVE FSO 6M 73ST-9XI31 3
MA O/C
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 49 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01Revision AND COMPONENT TABLES 21 Drawing Size (in) Cat.
CSJ/
Valve ID Coord/Sht#
Type A/P ROJ/
Description Code Class Act.
S.P.
Test Freq Procedure VRR Remarks SPEHCV0208 SPP-001 10 B
FSC 6M 73ST-9XI31 SPRAY POND CROSSCONNECT VALVE E04 BF ACTIVE FSO 6M 73ST-9X131 3
MA O/C SSBUV0200 SSP-001 0.375 A
AJ CLR 73ST-9CL01 HOT LEG SAMPLE LINE OUTBOARD CIV G05 GL ACTIVE FSC QTR 73ST-9XI06 (PEN. 42C) 2 so C
FTC QTR 73ST-9XI06 STC QTR 73ST-9XI06 VP 2YR 73ST-9XI06 SSBUV0201 SSP-001 0.375 A
AJ CLR 73ST-9CLO1 PRESSURIZER SURGE LINE SAMPLE LINE F05 GL ACTIVE FSC QTR 73ST-9XI06 OUTBOARD CIV 2
so C
(PEN. 42A)
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9XI06 SSBUV0202 SSP-001 0.375 A
AJ CLR 73ST-9CLO1 PRESSURIZER STEAM SPACE SAMPLE F05 GL ACTIVE FSC QTR 73ST-9XI06 LINE OUTBOARD CIV 2
so C
(PEN. 42B)
FTC QTR 73ST-9XI06 STC QTR 73ST-9X106 VP 2YR 73ST-9XI06 SSAUV0203 SSP-001 0.375 A
AJ CLR 73ST-9CLO1 HOT LEG SAMPLE LINE INBOARD CIV G07 GL ACTIVE FSC QTR 73ST-9XI06 (PEN. 42C) 2 so C
FTC QTR 73ST-9X106 STC QTR 73ST-9X106 VP 2YR 73ST-9X106 SSAUV0204 SSP-001 0.375 A
AJ CLR 73ST-9CL01 PRESSURIZER SURGE LINE SAMPLE LINE F07 GL ACTIVE FSC QTR 73ST-9XI06 INBOARD CIV (PEN. 42A) 2 so C
FTC QTR 73ST-9X106 STC QTR 73ST-9XI06 VP 2YR 73ST-9XI06 SSAUV0205 SSP-001 0.375 A
AJ CLR 73ST-9CLO1 PRESSURIZER STEAM SPACE SAMPLE E07 GL ACTIVE FSC QTR 73sT-9XI06 LINE INBOARD CIV 2
so C
(PEN. 42B)
FTC QTR 73ST-9XI06 STC QTR 73ST-9XI06 VP 2YR 73ST-9XI06 WCEV039 WCP-001 10 AC AJ CLR 73ST-9CLO1 Notes 1,2, 3, 4 NORMAL CHILLED WATER SUPPLY TO E05 CK ACTIVE CVC CMP 73ST-9CLO1 CONTAINMENT INBOARD CIV (PEN. 60) 2 SA O/C CVO CMVP 40DP-90OP5 WCBUVO061 WCP-001 10 A
AJ CLR 73ST-9CLO1 Note 5 NORMAL CHILLED WATER RETURN FROM G05 GA ACTIVE FSC lCY 73ST-9XI07 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 61) 2 MO C
STC 18M 73ST-9XI07 VRR-01 WCAUVO062 WCP-001 10 A
AJ CLR 73ST-9CLO1 Note 5 NORMAL CHILLED WATER RETURN FROM G05 GA ACTIVE FSC 1CY 73ST-9XI07 VRR-01 18M ST REQ'D FORTS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 61) 2 MO C
STC i8M 73ST-9XI07 VRR-01 WCBUVO063 WCP-001 10 A
AJ CLR 73ST-9CLO1 Note 5 NORMAL CHILLED WATER SUPPLY TO G06 GA ACTIVE FSC 1CY 73ST-9XI07 VRR-01 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 60) 2 MO C
STC 18M 73ST-9X107 VRR-01
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 50 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PRRs, CSJs, ROJs, and VRRs The following table lists the Pump 10CFR50.55a Requests (PRRs), Cold Shutdown Justifications (CSJs),
Refueling Outage Justifications (ROJs), and Valve 10CFR50.55a Requests (VRRs) used in the PVNGS Pump and Valve Inservice Testing Program.
Identifier Subject (and Notes)
PRR-01 Essential Auxiliary Feedwater Pump Flow Rate Measurement PRR-02 Diesel Fuel Oil Transfer Pump Suction Pressure Measurement PRR-03 LPSI Pump Flow Rate Measurement PRR-04 HPSI Pump Flow Rate Measurement PRR-05 Containment Spray Pump Flow Rate Measurement PRR-06 Charging Pump Vibration Measurement PRR-07 Smooth-Running Pumps CSJ-01 AFW Discharge Header Check Valve Open Exercising CSJ-02 AFW Header Check Valve Open Exercising CSJ-03 Auxiliary Pressurizer Spray Valve Exercising CSJ-04 Letdown Isolation Valve Closed Exercising CSJ-05 Shutdown Cooling Suction Isolation Valve Exercising CSJ-06 Instrument Air Containment Isolation Valve Closed Exercising CSJ-07 Reactor Head Vent and Pressurizer Vent Valve Exercising CSJ-08 Feedwater Isolation Valve Closed Exercising CSJ-09 Main Steam Isolation Valve Closed Exercising CSJ-10 SIT Vent Valve Exercising ROJ-01 Containment Refueling Purge Valve Closed Exercising ROJ-02 RCP Seal Bleed-Off Isolation Valve Closed Exercising VRR-01 Code Case OMN MOV Exercising and Stroke Timing
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 51 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-01 Relief Request In Accordance with 10CFR50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
Essential Auxiliary Feedwater Pump Flow Rate Measurement During Group B Test Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class Group AFA-P01 Essential Auxiliary Feedwater Pump 3
B (Turbine-Driven)
AFB-P0 1 Essential Auxiliary Feedwater Pump 3
B I (Motor-Driven)
I The essential auxiliary feedwater (AF) pumps supply water to the steam generators during an accident. They also can be used to supply feedwater to the steam generators during plant startup and shutdown.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5122, "Group B Test Procedure," "Group B tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5122(b), "The differential pressure or flow rate shall be determined and compared to its reference value.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 52 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Impracticality of Compliance:
Burden Caused by Compliance:
The Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) are impractical since this is a fixed resistance recirculation path with no flow instrumentation provided. When the pump operates on minimum flow recirculation (approx. 260 gpm) the specified reference point is essentially achieved by the recirculation lines fixed resistance. To establish the fixed resistance the minimum flow recirculation line contains an administratively controlled locked-throttled drag valve and a locked open manual isolation valve. The use of an ultrasonic flowmeter was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the AF mini-flow piping. Allowing the flow to remain fixed by the locked-in resistance increases the potential for repeatable test results and degradation monitoring rather than changing the resistance based on ultrasonic flow meter readout flucuations. With this understanding, there is little value added in installing flow instrumentation to measure and record the flow with instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
To comply with the Code there are only two practical flow paths available for testing AFA-PO1 and AFB-PO1. The primary flow path is into the main feedwater lines to the steam generators. The other flow path is the minimum flow recirculation line that recirculates back to the condensate storage tank. The flow path to the steam generators is equipped with flow instrumentation, but the recirculation line is a fixed-resistance circuit with no provisions for flow indication.
Use of the primary flow path at power would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.
Modifying the minimum flow recirculation line to provide flow indication to meet the +/- 2% accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed at approximately 260 gpm and differential pressure is used to monitor degradation. Use of an ultrasonic flow meter and possible adjustment of the fixed resistance introduces the potential for less accurate degradation monitoring than currently employed.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 53 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Proposed Alternative and Basis for Use:
During plant operation, quarterly Group B pump testing for pumps AFA-P01 and AFB-PO1 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance to establish the specified reference point. ISTB-5 1 00(b)(2) allows the use of bypass test loops to be used for Group B tests. The PVNGS minimum flow recirculation line is designed to meet the pump manufacturers operating specifications with a flow rate of approximately 260 gpm. Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5100-1.
Pumps AFA-P01 and AFB-P01 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps AFA-P01 and AFB-PO1 are standby pumps. Little degradation is expected during plant plant operation when the pumps are idle except for testing. Testing the pumps within +/- 20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with no flow instrumentation provided.
The proposed alternative identified in this 10CFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Complies with NRC Generic Letter 89-04, Position 9. Relief Request PRR-01 was previously authorized for Palo Verde pursuant to 10 CFR 50.55a(f)(6)(i) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128).
Duration of Proposed Alternative:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 54 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-02 Relief Request In Accordance with 10CFR50.55a(a)(3)(i)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety --
Diesel Fuel Oil Transfer Pump Suction Pressure Measurement Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class Group DFA-P01 Diesel Generator Fuel Oil 3
B Transfer Pump DFB-P0l Diesel Generator Fuel Oil 3
B Transfer Pump Transfer diesel fuel from the fuel oil storage tank to the EDG day tank.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-35 10, "General," ISTB-35 10(a), "Accuracy", Instrument accuracy shall be within the limits of Table ISTB-3500-1.
Table ISTB-3500-1, "Required Instrument Accuracy", Pressure, Comprehensive Test, + 0.5% accuracy.
There are no inlet pressure gauges installed for this pump configuration.
Specifically, the pumps are horizontal, centrifugal type with an integral motor. They operate submerged in the diesel fuel oil storage tank. The pump and drive motor are completely housed in an enclosed steel casing with no shaft penetrations requiring seals or packing. The casing has a hermetically sealed compartment for the stator windings of the motor to prevent entrance of pumped liquid or vapor. Pump bearings are cooled by recirculation of pumped fluid. The entire assembly is suspended from a cover plate, which is bolted to a nozzle on the tank.
The diesel generator fuel oil storage tank is equipped with level instrumentation (DFN-LI-33 and DFN-LI-34) having a calculated loop accuracy of+/- 1.5%. The instrument reads out in percent of tank level which is converted to suction pressure during the quarterly pump surveillance test.
The calibrated instrument range results in a suction pressure span of 0.2 psig to 4.4 psig. This instrument accuracy is acceptable for use during Group B pump testing but does not meet the +/- 0.5% accuracy as required by Table ISTB-3500-1 for Comprehensive Pump Testing performed every 2 years.
Reason for Request:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 55 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Proposed The installed instrumentation converts to a full-scale range of 4.4 psig, Alternatives and which only slightly exceeds the pump suction reference value of 3.8 psig Basis for Use:
(full scale equals 1.15 times reference).
Considering the existing 1.5% accuracy of the level instrument, the reading could be as high as 3.85 psig or as low as 3.74 psig. This results in less than a 0.06 psig difference in the readings and is considered insignificant when monitoring for degradation. The existing accuracy is equivalent to the 1.5%
minimum accuracy allowed by the combination of instrument full-scale range and accuracy as specified in Subsection ISTB 3510 for comprehensive pump testing. This accuracy provides adequate assurance of operability. The current instrumentation provides sufficient repeatability to allow for an evaluation of the pump hydraulic condition and detect pump degradation.
Use of the existing diesel generator fuel oil storage tank instrumentation should be considered an acceptable alternative to the accuracy requirements of Table ISTB-3500-1.
Supporting Facts:
Technical Specification 3.8.3.1 requires that the diesel generator fuel oil storage tank be maintained at > 80% which is verified every 31 days to assure sufficient supply for 7 days of full load operation. The difference between minimum allowable tank level and top of the tank is only 26.4 inches. Due to strict controls placed on fuel oil level, the suction pressure cannot vary by more than 0.7 psig. Review of test history shows that the maximum variance recorded is approximately 0.5 psig. The suction pressure is essentially fixed by the TS level requirements, allowing for very little variation in suction pressure. There is no value added in providing more precise suction pressure instrumentation for monitoring pump degradation.
The following test history shows the essentially constant suction pressure:
Unit Pump ID Date Suction Pressure 1
1MDFAP01 1 6/6/2006 1
3.8 1MDFAP01 8/24/2006 4
1MDFAP01 11/15/2006 4
1MDFAP01 2/8/2007 4
1MDFAP01 5/3/2007 3.9 1MDFBP01 5/18/2006 4.3 1MDFBP01 8/10/2006 3.9 1MDFBP01 11/2/2006 3.6 1MDFBP01 1/25/2007 3.8
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 56 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 2
1MDFBP01 4/19/2007 3.85 2MDFAP01 4/20/2006 3.7 2MDFAP01 5/4/2006 3.6 2MDFAP01 7/25/2006 4
2MDFAP01 1/10/2007 4
2MDFAP01 4/5/2007 3.9 2MDFBP01 2/9/2006 3.9 2MDFBP01 7/13/2006 3.8 2MDFBP01 10/15/2006 3.8 2MDFBP01 12/27/2006 3.7 2MDFBP01 3/21/2007 3.7 3
3MDFAP01 4/30/2006 4.1 3MDFAP01 6/28/2006 3.7 3MDFAP01 9/19/2006 4.1 3MDFAP01 12/15/2006 3.7 3MDFAP01 3/6/2007 3.9 3MDFBP01 4/18/2006 3.4 3MDFBP01 6/13/2006 3.9 3MDFBP01 9/5/2006 4
3MDFBP01 11/28/2006 3.9 3MDFBP01 2/22/2007 3.8 Using the installed instrument (DFN-LI-33 and DFN-LI-34) for Group B and Comprehensive Pump Testing (CPT) provides an acceptable level of quality and safety since the instrument used yields a reading that is as at least equivalent to that achieved using an instrument that meets the Code requirements as described in Table ISTB-3500-1 The installed level instruments, DFN-LI-33 and DFN-LI-34, will be used to determine diesel fuel oil transfer pump suction pressure during inservice testing.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 57 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g),
and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The existing 1.5% accuracy of the level instrument discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Duration of Proposed The proposed alternative identified in this 1 OCFR50.55a Request shall be Alternatives:
utilized during the Third 10-Year IST Interval.
Precedents:
None
References:
NUREG 1482, Revision 1, 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure."
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 58 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-03 Relief Request In Accordance with 10CFR50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
LPSI Pump Flow Rate Measurement Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class Group SIA-P01 Low Pressure Safety Injection (LPSI) Pump 2
A SIB-POl Low Pressure Safety Injection (LPSI) Pump 2
A LPSI pumps SIA-P01 and SIB-POl provide low-pressure coolant injection of borated water into the reactor coolant system under accident conditions.
They also provide shutdown cooling flow post-accident and during normal reactor startup and shutdown.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5221, "Group A Test Procedure," "Group A tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5221 (b), "The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value."
ISTB-5221 (c), "Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values."
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pa2e 59 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Impracticality of Compliance:
The Code requires the Group A reference point flow rate to be established at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value). It is impractical to meet this requirement since this is a fixed resistance recirculation path of approximately 180 gpm with limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm ultrasonic flowmeter with +/- 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2%
calibration on the SI mini-flow piping. To establish the fixed resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations.
When the pump operates on minimum flow recirculation, the specified reference point is essentially achieved by the fixed resistance. With this understanding, there is little value added in replacing the existing 0-5000 gpm, +/- 5% ultrasonic flowmeter, or adding instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 60 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Burden Caused by Compliance:
During normal plant operation, the LPSI pumps cannot develop sufficient discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, LPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 180 gpm) of the design flow (4200 gpm). The permanent plant 0-5000 gpm, + 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements.
The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined to be impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
The LPSI pumps are categorized as Group A since they are normally used to provide shutdown cooling flow during shutdown operations, and occasionally for recirculating the refueling water tank when the unit is at power. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
Modifying the minimum flow recirculation line to provide flow indication to meet the + 2% accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed and differential pressure is used to monitor degradation.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 61 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Proposed Alternative and Basis for Use:
During plant operation, quarterly Group A pump testing for pumps SIA-P01 and SIB-PO1 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 180 gpm to establish the specified reference point. Subsection ISTB, ISTB-5200(b)(1) allows the use of bypass test loops to be used for Group A tests. The flow rate through the loop is established at the highest practical flow rate of approximately 180 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5200-1.
Pumps SIA-P01 and SIB-P01 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P01 and SIB-P01 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +
20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group A reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
The proposed alternative identified in this 10CFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Complies with NRC GL 89-04, Position 9. Relief Request PRR-03 was previously authorized for Palo Verde as Relief Request PRR-05 pursuant to 10 CFR 50.55a(f)(6)(i) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Duration of Proposed Alternative:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 62 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-04 Relief Request In Accordance with 10CFR50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
HPSI Pump Flow Rate Measurement Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class SIA-P02 High Pressure Safety Injection (HPSI) 2 B
Pump SIB-P02 High Pressure Safety Injection (HPSI) 2 B
Pump I
I I
The HPSI pumps provide high-pressure coolant injection of borated water into the reactor coolant system under accident conditions. They also provide flow for long-term cooling and flushing to prevent boron precipitation.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-5122, "Group B Test Procedure," "Group B tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5122(b), "The differential pressure or flow rate shall be determined and compared to its reference value.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 63 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Impracticality of Compliance:
The Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) is impractical since this is a fixed resistance recirculation path of approximately 170 gpm which is measured by limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm ultrasonic flowmeter with + 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined to be impractical due to the difficulty in establishing an application specific 2%
calibration on the SI mini-flow piping. To establish the fixed resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations.
When the pump operates on minimum flow recirculation the specified reference point is essentially achieved by the fixed resistance. With this understanding, there is little value added in replacing the existing 0-5000 gpm, + 5% ultrasonic flowmeter, or adding instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 64 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Burden Caused by Compliance:
During normal plant operation, the HPSI pumps cannot develop sufficient discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, HPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 170 gpm) of the design flow (815 gpm). The permanent plant 0-5000 gpm, + 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements.
The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2% calibration on the SI mini-flow piping.
The HPSI pumps are categorized as Group B. Pump SIB-P02 is used only occasionally to recharge the safety injection tanks. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
Modifying the minimum flow recirculation line to provide flow indication to meet the + 2% accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed and differential pressure is used to monitor degradation.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 65 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Proposed Alternative and Basis for Use:
During plant operation, quarterly Group B pump testing for pumps SIA-P02 and SIB-P02 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 170 gpm to establish the specified reference point. ISTB-5 1 00(b)(2) allows the use of bypass test loops to be used for Group B tests. The PVNGS minimum flow recirculation line is designed to meet the pump manufacturers operating specifications. The flow rate through the loop is established at the highest practical flow rate of approximately 170 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5100-1.
Pumps SIA-P02 and SIB-P02 will be comprehensively tested in accordance with ISTB-5123, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P02 and SIB-P02 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +
20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group B reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
The proposed alternative identified in this I OCFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Complies with NRC GL 89-04, Position 9. Relief Request PRR-04 was previously authorized for Palo Verde as Relief Request PRR-06 pursuant to 10 CFR 50.55a(f)(6)(i) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Duration of Proposed Alternative:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 66 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-05 Relief Request In Accordance with 10CFR50.55a(f)(5)(iii)
-- Inservice Testing Impracticality -
Containment Spray Pump Flow Rate Measurement Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class Group SIA-P03 Containment Spray (CS) Pump 2
A SJB-P03 Containment Spray (CS) Pump 2
A CS pumps SIA-P03 and SIB-P03 deliver borated water to the containment spray headers, providing containment cooling and pressure control during accident conditions. The CS pumps can also be lined up to provide flow for shutdown cooling.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-3300, "Reference Values," ISTB-3300(e)(2), "Reference values shall be established within +/- 20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practical flow rate."
ISTB-522 1, "Group A Test Procedure," "Group A tests shall be conducted with the pump operating at a specified reference point. The test parameter value identified in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph."
ISTB-5221 (b), "The resistance of the system shall be varied until the flow rate equals the reference point. The differential pressure shall then be determined and compared to its reference value. Alternatively, the flow rate shall be varied until the differential pressure equals the reference point and the flow rate determined and compared to the reference flow rate value."
ISTB-5221 (c), "Where it is not practical to vary system resistance, flow rate and pressure shall be determined and compared to their respective reference values."
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 67 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Impracticality of Compliance:
The Code requires the Group A reference point flow rate to be established at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value). It is impractical to meet this requirement since this is a fixed resistance recirculation path of approximately 190 gpm with limited capability permanent plant flow instrumentation. The installed instrumentation is a 0-5000 gpm ultrasonic flowmeter with + 5% accuracy and does not meet the 2% instrument requirements of Table ISTB-3500-1 for pump testing. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2%
calibration on the SI mini-flow piping. To establish the fixed resistance the minimum flow recirculation line contains a flow orifice and a normally open motor-operated valve and solenoid isolation valve. Allowing the flow to remain fixed by the orifice resistance increases the potential for repeatable test results and degradation monitoring rather than attempting to change the resistance based on ultrasonic flowmeter readout fluctuations.
When the pump operates on minimum flow recirculation, the specified reference point is essentially achieved by the fixed resistance. With this understanding, there is little value added in replacing the existing 0-5000 gpm, + 5% ultrasonic flowmeter, or adding instrumentation that meets IST-3510 requirements. The fixed resistance methodology is repeatable from test to test and accomplishes the same result as if flow were being measured and recorded.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 68 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Burden Caused by Modifying the minimum flow recirculation line to provide flow indication Compliance:
to meet the +/- 2% accuracy requirement as specified in Table ISTB-3500-1 adds little value since the flow is fixed at approximately 190 gpm and differential pressure is used to monitor degradation. The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. The use of an ultrasonic flowmeter with 2% accuracy was evaluated and determined impractical due to the difficulty in establishing an application specific 2%
calibration on the SI mini-flow piping.
The normal containment spray flow path cannot be used for testing the CS pumps without spraying down the inside of the containment building and risking damage to important equipment. The RCS injection portion of the shutdown cooling flow path cannot be used for testing during plant operation because the CS pumps are unable to develop sufficient discharge pressure to overcome RCS pressure.
The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction (approx. 190 gpm) of the design flow (3890 gpm). The permanent plant 0-5000 gpm, +/- 5% accuracy, flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy does not meet Table ISTB-3500-1 flow rate 2% accuracy requirements. A larger recirculation flowpath is available; however, this requires an alternate line up and the same limited capability flow instrument exists in this portion of the recirculation line.
The larger recirculation flowpath is capable of carrying higher flow, but routine surveillance testing at less than the full flow reference value is not practical because of the pump rumble range (1800-2800 gpm). Testing in or near the rumble range is not practical because of the potential for equipment damage. Testing at flow rates above the rumble range (> 2800 gpm) is not practical because flow velocities in the recirculation piping would exceed the design criteria.
The CS pumps are categorized as Group A since they are normally used to provide shutdown cooling flow during shutdown operations. Little degradation is expected during plant operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 69 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Proposed Alternative and Basis for Use:
During plant operation, quarterly Group A pump testing for pumps SIA-P03 and SIB-P03 shall be conducted at mini-flow conditions using the minimum flow recirculation line fixed resistance of approximately 190 gpm to establish the specified reference point. ISTB-5200(b)(1) allows the use of bypass test loops to be used for Group A tests. The flow rate through the loop is established at the highest practical flow rate of approximately 190 gpm in accordance with ISTB-3300(e)(2). Flow rate will not be measured or recorded. To monitor for degradation, pump differential pressure shall be determined and compared to its reference value and the associated range as specified in Table ISTB-5200-1.
Pumps SIA-P03 and SIB-P03 will be comprehensively tested in accordance with ISTB-5223, "Comprehensive Test Procedure," on a biennial (2-year) frequency as specified in Table ISTB-3400-1.
Pumps SIA-P03 and SIB-P03 are infrequently used pumps. Little degradation is expected during plant power operation when the pumps are idle except for limited operations and testing. Testing the pumps within +/-
20% of design flow on a 2-year frequency provides additional information regarding the condition of the pumps.
==
Conclusion:==
10 CFR50.55a(f)((5)(iii) states:
"If the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in § 50.4 information to support the determination."
The information provided in this request supports the determination that it is impractical to meet the Code requirements to establish the Group A reference point flow rate at the highest practical flow rate and operate the pump at a specified reference point (i.e., fix the flow to a specified value) since this is a fixed resistance recirculation path with limited capability permanent plant flow instrumentation.
The proposed alternative identified in this 10CFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Complies with NRC GL 89-04, Position 9. Relief Request PRR-05 was previously authorized for Palo Verde as Relief Request PRR-11 pursuant to 10 CFR 50.55a(f)(6)(i) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Duration of Proposed Alternative:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 70 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-06 Proposed Alternative In Accordance with 10CFR50.55a(a)(3)(ii)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety -
Charging Pump Vibration Measurement Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Pump ID Pump Description Code Pump Class Group CHA-P01 Charging Pump 2
A CHB-P01 Charging Pump 2
A CHE-P01 Charging Pump 2
A The charging pumps provide makeup water to the reactor coolant system for chemistry and volume control. They also provide auxiliary spray to the pressurizer and reactor coolant pump seal injection.
ASME OM Code 2001 Edition w/2003 Addenda ISTB-3510, "General", ISTB-3510(e), "Frequency Response Range", The frequency response range of the vibration measuring transducers and their readout system shall be from one-third minimum pump rotational speed to at least 1000 Hz.
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21 Reason for Request
The charging pumps are positive-displacement pumps with a constant running speed of 199 rpm (equivalent to 3.3 Hz). Compliance with ISTB-35 10(e) would require using vibration instrumentation with a frequency response range of 1.1 Hz to at least 1000 Hz.
A low-speed probe with a frequency response range of 1.6 Hz to 100 Hz was purchased specifically for charging pump testing when the IST requirement for frequency response was one-half pump speed to at least pump shaft rotational speed. However, this probe does not meet the lower bound or the upper bound of the current Code-required frequency response range.
The charging pump bearings are oil-lubricated, sleeve type journal bearings.
Because of the high reciprocating loads, the charging pump bearings are not susceptible to oil whirl, which is the primary failure mode that causes vibration below pump shaft rotational speed. There are no other failure mechanisms that manifest themselves with elevated vibration levels in the range of one-third to one-half pump shaft rotational frequency; all the remaining failure modes cause vibration at or above the pump speed.
Experience with these pumps confirms this fact. Therefore vibration instrumentation with a frequency response range above 1.6 Hz is acceptable for monitoring vibration of the charging pumps.
The low-speed probe is sensitive to vibration frequencies up to 30 times the running speed of the charging pumps. This is sufficient to identify bearing degradation, mechanical rubs, and other pump problems producing high-frequency vibrations. These pumps are susceptible to degradation mechanisms that would manifest themselves in the 1.6-100 Hz range and not in the extended vibration range required to be monitored by the Code (100-1000 Hz). Therefore, use of the higher frequency vibration probe provides no benefit. The charging pumps are monitored for other symptoms of degradation under the PVNGS Predictive Maintenance Program (see PRR-07 for a description of the PVNGS Predictive Maintenance Program).
Proposed Alternatives and Basis for Use:
The instrumentation used to measure charging pump vibration will have a frequency response range from 1.6 hz to 100 hz. Monitoring in the extended vibration range required to be monitored by the Code (100-1000 Hz) provides no benefit.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 72 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Conclusion 10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f),
(g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The low-speed probe with a frequency response range of 1.6 Hz to 100 Hz discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
The proposed alternative identified in this 10CFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Relief Request PRR-06 was previously authorized for Palo Verde as Relief Request PRR-07 pursuant to 10 CFR 50.55a(a)(3)(ii) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Duration of Proposed Alternatives:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 73 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 PUMP 10CFR50.55a REQUEST PRR-07 Proposed Alternative In Accordance with 10CFR50.55a(a)(3)(i)
-- On the basis that the proposed alternative provides an acceptable level of quality and safety --
Smooth Running Pumps Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Pump ID Pump Description Code Pump Class Group AFA-P01 Essential Auxiliary Feedwater Pump (Turbine-3 B
Driven)
AFB-P01 Essential Auxiliary Feedwater Pump (Motor-3 B
Driven)
CTA-P01 Condensate Transfer Pump 3
A CTB-P01 Condensate Transfer Pump 3
A ECA-P01 Essential Chilled Water Circulation Pump 3
A ECB-POl Essential Chilled Water Circulation Pump 3
A EWA-P01 Essential Cooling Water Pump 3
A EWB-P01 Essential Cooling Water Pump 3
A PCA-P01 Spent Fuel Pool Cooling Pump 3
A PCB-PO1 Spent Fuel Pool Cooling Pump 3
A SIA-PO1 Low Pressure Safety Injection (LPSI) Pump 2
A SIB-P01 Low Pressure Safety Injection (LPSI) Pump 2
A SIA-P02 High Pressure Safety Injection (HPSI) Pump 2
B SIB-P02 High Pressure Safety Injection (HPSI) Pump 2
B SIA-P03 Containment Spray Pump 2
A SIB-P03 Containment Spray Pump 2
A SPA-P01 Essential Spray Pond Pump 3
A SPB-P01 Essential Spray Pond Pump 3
A Various ASME OM Code 2001 Edition w/2003 Addenda
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follows: (a) Initial reference values shall be determined from the results of testing meeting the requirements of ISTB-3 100, Preservice Testing, or from the results of the first inservice test.
ISTB-3300(f), "All subsequent test results shall be compared to these initial reference values or to new reference values established in accordance with ISTB-3310, ISTB-3320, or ISTB-6200(c).
ISTB-6200(a), "Alert Range", "If the measured test parameter values fall within the alert range of Table ISTB-5100-1, Table ISTB-5200-1, Table ISTB-5300-1, or Table ISTB-5300-2, as applicable, the frequency of testing specified in ISTB-3400 shall be doubled until the cause of the deviation is determined and the condition is corrected."
ISTB-6200(b), "Action Range", "If the measured test parameter values fall within the required action range of Table ISTB-5 100-1, Table ISTB-5200-1, Table ISTB-5300-1, or Table ISTB-5300-2, as applicable, the pump shall be declared inoperable until either the cause of the deviation has been determined and the condition is corrected, or an analysis of the pump is performed and new reference values are established in accordance with ISTB-6200(c).
Reason for Request
Palo Verde has several pumps with vibration parameters readings in the range of < 0.05 ips. Vibration velocities in this range can be significantly affected by hydraulic flow noise and repeatability of the vibration instruments. As a result, Palo Verde could be required to increase the frequency of specified testing when no degradation of the monitored equipment exists.
PVNGS expends considerable resources on preventive and predictive maintenance. One result of these efforts is a number of pumps run very smoothly. For example, many pumps in the PVNGS IST Program would currently be candidates for "smooth-running" status under PRR-07, as shown in the table below. To impose Code-mandated Alert and Required Action values on "smooth-running" pumps unnecessarily penalizes PVNGS for achieving this high level of performance.
Typical Vibration Pump Reference Values inch per second (ips)
Auxiliary Feedwater 0.12 - 0.27 Condensate Transfer
- 0.0044 - 0.0883 Essential Chilled Water
- 0.0075 - 0.0597 Essential Cooling Water
- 0.0295 - 0.0931 Low Pressure Safety Injection
- 0.0343 - 0.174 High Pressure Safety Injection 0.0667 - 0.296
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21 Reason for Request
(Continued)
Proposed Alternatives and Basis for Use:
Typical Vibration Pump Reference Values inch per second (ips)
Containment Spray 0.078 - 0.161 Spent Fuel Pool Cooling
- 0.031 -0.110 Essential Spray Pond
- 0.0201 - 0.0864
- Candidates for "smooth-running" status under PRR-007 For displacement reference values less than 0.5 mils, it is noted that the Section XI Code in effect for the first interval of the IST Program (1980 Edition, Winter 1981 Addenda) sets the Alert Range at >1.0 mil and the Required Action Range at >1.5 mil. This implies a minimum reference value of 0.5 mils, which is equivalent to 0.047 ips for 1800 rpm pumps and 0.094 ips for 3600 rpm pumps. The effective reference values proposed for smooth-running pumps are roughly equal to the implied Section XI reference values for 1800 rpm pumps and more conservative than the implied reference values for 3600 rpm pumps. Without proposed alternative, the Alert Ranges for several smooth running pumps will be reduced by a factor of 10.
Vibration parameters that have reference values _< 0.05 ips are considered "smooth-running". When vibration velocities are less than 0.05 ips, changes have been shown to be non-significant. To reduce any unnecessary penalty for those pump parameters considered "smooth-running", the Alert and Required Action values for these "smooth-running" parameters will be determined as if their reference value is 0.05 ips; that is, the Alert Range will be 0.125 ips to 0.3 ips, and the Required Action Range will be > 0.3 ips.
Candidates for "smooth-running" status will be analyzed per ISTB-3300(g) and ISTB-6400 to verify that use of this relief request will not prevent the detection of significant pump degradation. If any of these parameters are outside normally expected ranges, an evaluation will be performed and appropriate corrective actions will be taken.
The basis for use of these proposed Alert and Required Action ranges is discussed below.
In addition to the Code-mandated monitoring, these pumps are monitored under the PVNGS Predictive Maintenance Program. This program includes the following:
- Spectrum band monitoring
- Bearing acceleration monitoring (on ball and roller bearings only)
- Bearing oil analysis (for oil lubricated bearings)
Motor Current Signature analysis (for all but the smallest motors)
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The PVNGS Predictive Maintenance (PdM) Program is part of the Preventive Maintenance (PM) Program described in UFSAR Section 17.2.3.11.1.6. The PM Program was developed using RCM, EPRI, and INPO guidelines as well as factoring in PVNGS site-specific experience and regulatory requirements.
The PM Program and PdM activities are controlled by plant procedures.
Each of these pumps has a maintenance plan documented in the PM Program which describes the PM and PdM activities performed on that pump. The performance of the system associated with each of these pumps is monitored and compared to performance criteria under the PVNGS Maintenance Rule Program. This ensures the continued effectiveness of the PM program to minimize component failures and maintain or improve system performance (balance availability and reliability).
The PVNGS Predictive Maintenance Program uses vibration analysis, lubricant analysis, and infrared thermographic analysis as appropriate, to predict the need for maintenance so that equipment can be reworked prior to failure. The components included in this program include those considered important to safe and reliable plant operation, including certain pumps in the IST Program. The intervals for monitoring are based on manufacturer's recommendations, maintenance history, cost effectiveness, and experience.
Although parts of the monitoring, analyses, database, and software used in the Predictive Maintenance Program do not fall under the PVNGS Quality Program, the Predictive Maintenance Program still provides valuable information for assuring the operational readiness of smooth-running pumps.
The vibration analysis program monitors the vibration of rotating machinery.
In addition to the vibration at pump bearings, the vibration of the driver (turbine or motor) bearings are also collected and trended. Analyzed parameters and methods include vibration velocity, bearing acceleration, bearing high frequency detection, and spectral analysis.
The lubricant analysis program samples lubricants and analyzes them to identify degradation or negative trends. Most testing is performed at the on-site lubrication laboratory, where capabilities include wear debris, chemical composition, and lubrication cleanliness analysis.
In both the vibration monitoring and lubricant analysis programs, recently acquired data is compared with previous data to detect any indicated degradation of equipment condition. If degradation indicates the reliability of operating equipment may be negatively affected, or if acceptance criteria are no longer being met, appropriate corrective action is taken. Corrective action may include: continuing trending of the degraded condition, if the condition is not considered to be immediately threatening to the equipment and can be corrected during a time window convenient to plant operation; additional testing or monitoring to confirm the suspected degraded condition;
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inspection and repair of the equipment as necessary; changes to preventive maintenance procedures or schedules; or design changes.
The following table contains examples of Unit 1 vibration test result history demonstrates consistent smooth running operation (Unit 2 and 3 are similar):
Unit 1
1 1
1 Pump CTAP01 CTAPO1 CTAPO1 CTAPO1 Date 7/2/2006 9/18/2006 12/11/2006 3/8/2007 Pump Horizontal
.016
.020
.021
.019 Pump Vertical
.012
.012
.014
.012 Axial
.006
.0079
.007
.0058 1
CTBPO1 11/8/2006
.024
.007
.0082 1
CTBPO1 12/7/2006
.014
.007
.0095 1
CTBPO1 1/29/2007
.016
.006
.011 1
CTBPO1 4/25/2007
.017
.007
.009 1
ECAP01 8/22/2006
.036
.034
.010 1
ECAP01 11/13/2006
.044
.027
.0092 1
ECAP01 2/5/2007
.057
.057
.0081 1
ECAP01 5/1/2007
.042
.034
.007 1
ECBPO1 8/8/2006
.026
.021
.013 1
ECBP01 10/31/2006
.028
.024
.016 1
ECBP01 1/22/2007
.030
.026
.012 1
ECBP01 4/16/2007
.023
.027
.012 1
EWAP01 8/22/2006
.031
.028
.020 1
EWAP01 11/13/2006
.032
.023
.0214 1
EWAP01 2/6/2007
.033
.031
.0182 1
EWAP01 5/3/2007
.032
.034
.023 1
EWBPO1 8/8/2006
.033
.034
.026 1
EWBP01 10/31/2006
.033
.032
.026 1
EWBP01 1/23/2007
.033
.031
.023 1
EWBP01 4/17/2007
.035
.038
.027 1
SIAP01(b) 4/11/2004
.033
.048 (a) 1 SIAPO1(b) 11/29/2005
.047
.053 (a)
I SIAPOl(b) 12/8/2005
.043
.061 (a) 1 SIAP01(b) 6/1/2006
.057
.071 (a) 1 SIBP01(b) 10/4/2002
.031
.032 (a) 1 SIBPO1(b) 4/23/2004
.044
.060 (a) 1 SIBP01(b) 10/16/2005
.027
.035 (a) 1 SIBPo1,b) 5/29/2006
.041
.062 (a) 1 PCAP01 6/28/2006
.060
.040
.024 1
PCAP01 9/26/2006
.059
.036
.027 1
PCAP01 12/11/2006
.058
.038
.029 1
PCAP01 3/6/2007
.058
.037
.023 1
PCBP01 6/20/2006
.077
.037
.023 1
PCBP01 9/11/2006
.075
.041
.025 1
PCBP01 12/4/2006
.072
.045
.026 1
PCBPO1 2/26/2007
.071
.041
.021
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Unit 1
1 1
Pump SPAPO1(b)
SPAP0 1(b)
SPAP0 1(b)
SPAPO1(b)
Date 8/22/2006 11/14/2006 2/6/2007 5/3/2007 Pump Horizontal
.049
.052
.055
.049 Pump Vertical
.027
.023
.027
.027 Axial
.0275
.0270
.0250
.0283 1
SPBPO1(b) 8/7/2006
.092
.047
.0261 1
SPBPO1(b) 11/1/2006
.088
.027
.0240 1
SPBPO1(b) 1/23/2007
.090
.030
.029 1
SPBP01(b) 4/19/2007
.088
.035
.026 (a) - Inaccessible (b) - vibration readings taken at the motor-
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g),
and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The revised Alert and Required Action values discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Q The proposed alternative identified in this 1 OCFR50.55a Request shall be utilized during the Third 10-Year IST Interval.
Relief Request PRR-07 was previously authorized for Palo Verde as Relief Request PRR-08 pursuant to 10 CFR 50.55a(a)(3)(i) for Interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No. 9907150128)
Duration of Proposed Alternatives:
Precedents:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 79 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Cold Shutdown Justification No. 1 (CSJ-01)
AFW Discharge Header Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class AFAVO 15 AFW Pump AFA-P01 Discharge 3
C AFP-001 / E05 Header Check Valve AFBV024 AFW Pump AFB-PO1 Discharge 3
C AFP-001 / C05 Header Check Valve Function These check valves open to provide flowpaths from the respective auxiliary feedwater pump to the auxiliary feedwater headers. They close so that if one pump fails to start after an auxiliary feedwater actuation signal (AFAS), flow from the operating pump is not diverted back through the idle pump.
Alternate These valves will be full-stroke exercised open during cold shutdown periods.
Testing Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising open during plant operation is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.
This CSJ is similar to CSJ-3 in the second interval IST Program and CSJ-2 in the first interval IST Program.
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AFW Header Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class AFAV079 AFW Header Check Valve 2
C AFP-001 / E02 AFBV080 AFW Header Check Valve 2
C AFP-001 / C02 Function These check valves have a safety function to OPEN to support injection of 650 gpm of auxilary feedwater flow.
The valve also has a safety function to CLOSE in order to isolate containment and to prevent diversion of feedwater flow.
Alternate These valves will be full-stroke exercised open and closed during cold Testing shutdown periods.
Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising during plant operation is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.
This cold shutdown justification is similar to CSJ-4 in the second interval IST Program and CSJ-3 in the first interval IST Program.
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Auxiliary Pressurizer Spray Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class CHBHV0203 Auxiliary Pressurizer Spray 1
B CHP-001 / H1O Isolation Valve CHAHV0205 Auxiliary Pressurizer Spray I
B CHP-001 / 1111 Isolation Valve Function These valves have an open safety function to provide flow from the charging pump discharge header to the pressurizer for auxiliary pressurizer spray and a close safety function for spray/pressure control.
Alternate The auxiliary pressurizer spray isolation valves will be full-stroke exercised Testing open and closed during cold shutdown periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise tests.
Basis Opening of the auxiliary pressurizer spray isolation valves during plant operation initiates spray flow to the pressurizer. This could cause an RCS pressure transient that could adversely affect plant safety and lead to a plant trip. In addition, the pressurizer spray piping and nozzle would be subjected to unnecessary thermal shock. Opening these valves during plant operation is considered impractical for these reasons.
This cold shutdown justification is similar to CSJ-6 in the second interval IST Program and CSJ-6 in the first interval IST Program.
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Letdown Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class CHBUV0515 Reactor Coolant Letdown Isolation 1
B CHP-001 / H15 Valve CHAUV0516 Reactor Coolant Letdown Inbd.
1 A
CHP-001 / G15 Isolation Valve CHBUV0523 Reactor Coolant Letdown Otbd.
1 A
CHP-001 / F13 Isolation Valve Function These valves open to provide a flowpath for reactor coolant letdown flow -
non-safety function. CHBUV0515 and CHAUV0516 have a closed safety function to secure letdown on a Safety Injection Actuation signal (SIAS).
CHAUV0516 and CHBUV0523 have a safety function to close on a Containment Isolation Actuation signal (CIAS) signal for containment isolation.
Alternate These valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise test.
Basis Closing any of these valves isolates the letdown line from the RCS. During plant operation, this would result in undesirable pressurizer level transients with the potential for a plant trip. If a valve failed to reopen, then a plant shutdown may be required.
This cold shutdown justification is similar to CSJ-9 in the second interval IST Program and CSJ-8 in the first interval IST Program.
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Shutdown Cooling Suction Isolation Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class Shutdown Cooling Suction Inboard 1
A SIP-002 / D03 Containment Isolation Valve Shutdown Cooling Suction Inboard 1
A SIP-002 / D10 Containment Isolation Valve Function These valves have a normally closed safety function to ensure the integrity of the reactor coolant system and to provide containment isolation. They have an open safety function during plant cooldown to initiate shutdown cooling.
Alternate Each of these valves will be full-stroke exercised open and closed during cold Testing shutdown periods. Stroke time testing will be performed in conjunction with the exercise testing.
Basis These valves provide pressure barriers between the reactor coolant system pressure and the lesser rated shutdown cooling piping systems. As an installed safety feature they are provided with electrical interlocks that prevent them from being opened when pressurizer pressure is greater than 400 psig. Although this interlock can be overridden, routine operation of these valves with a large differential pressure across the seats is considered impractical due to the risk of damage to the seating surfaces of the valves.
This cold shutdown justification is similar to CSJ-27 in the second interval IST Program, This cold shutdown justification is similar to CSJ-24 in the first interval IST Program, except that Valves SIAHV065 1, SIBHV0652, SIAUV0655 and SIB-UV0656 have been deleted from that CSJ due to the implementation of ASME OM Code Case OMN-1 per VRR-12.
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Instrument Air Containment Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class IAAUVO002 Instrument Air Supply To 2
A IAP-003 / G07 Containment Isolation Valve Function This valve opens to provide flow for instrument air to the containment - non-safety function. The valve has a closed safety function to provide containment isolation.
Alternate IAAUVO002 will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.
Basis Closing this valve during plant operation isolates instrument air to important equipment within the containment building, including the pressurizer spray control valves and letdown isolation valves. This would, in turn, risk pressurizer level and pressure transients with a potential for a plant trip. If IAAUVO002 were to fail to re-open, an expedited plant shutdown would be required.
This cold shutdown justification is similar to CSJ-13 in the second interval IST Program and CSJ-13 and CSJ-14 in the first interval IST Program.
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Reactor Head Vent and Pressurizer Vent Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class RCAHV0101 Reactor Vessel Vent Valve 2
B RCP-001 / G15 RCBHV0102 Reactor Vessel Vent Valve 2
B RCP-001 / G 15 RCAHV0103 Pressurizer Vent Valve 2
B RCP-001 / G14 RCBHV0105 Reactor Coolant System Common 2
B RCP-001 / G13 Vent Valve To RDT RCAHV0106 Reactor Coolant System Common 2
B RCP-001 / G13 Vent Valve To Containment RCBHV0108 Pressurizer Vent Valve 2
B RCP-001 / G 13 RCBHV0109 Pressurizer Vent Valve 2
B RCP-001 / G 13 Function These valves have an open safety function to remotely vent non-condensible gasses from the reactor vessel and/or pressurizer steam space. They can also be used to depressurize the RCS. They have a safety function to close for reactor coolant system integrity.
Alternate These valves will be full-stroke exercised open and closed during cold Testing shutdown periods. Stroke time testing and fail-safe testing will be performed in conjunction with the exercise testing.
Basis These valves are administratively controlled in the keylocked closed position with the power supply disconnected to prevent inadvertent operation. Since these are reactor coolant system boundary valves, failure of a valve to close or significant RCS leakage following closure can result in a loss of coolant in excess of the limits imposed by the Technical Specifications leading to a plant shutdown. Furthermore, if a valve were to fail open or valve indication fail to show the valve returned to the fully closed position after exercising, it is likely that a plant shutdown would be required. Note also that Technical Specifications require that these valves be closed in Modes 1-4.
This cold shutdown justification is similar to CSJ-15 in the second interval IST Program and CSJ-16 in the first interval IST Program.
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Feedwater Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class SGBUVO 130 Inbd. FWIV to SG #1 Downcomer 2
B SGP-002 / G11 SGBUVO132 Inbd. FWIV to SG #1 Economizer 2
B SGP-002 / E12 SGBUV0135 Inbd. FWIV to SG #2 Downcomer 2
B SGP-002 / C I SGBUV0137 Inbd. FWIV to SG #2 Economizer 2
B SGP-002 / A12 SGAUVO172 Otbd. FWIV to SG #1 Downcomer 2
B SGP-002 / G12 SGAUVO174 Otbd. FWIV to SG #1 Economizer 2
B SGP-002 / E12 SGAUV0175 Otbd. FWIV to SG #2 Downcomer 2
B SGP-002 / C 12 SGAUV0177 Otbd. FWIV to SG #2 Economizer 2
B SGP-002 / A12 Function The main feedwater isolation valves (FWIVs) are normally open during steaming operations to provide flowpaths for main feedwater flow to the steam generators - non-safety function. They have a closed safety function to isolate and maintain the integrity of the steam generators and to secure feeding a faulted steam generator in the event of a steam leak inside containment.
Alternate Each of these valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with the exercise testing.
Basis Closing any of these valves isolates the associated feedwater header. During plant operation, isolation of a feedwater header would require a significant power reduction and could result in unacceptable steam generator level and reactor power transients with the potential for a plant trip.
The downcomer isolation valves do not have partial-stroke capability, however the economizer isolation valves are capable of partial stroke exercising. Part-stroke exercising is not considered practical because of the risk of full closure. This risk was recognized by NUREG-1432, Vol 1, Rev.
1, "Standard Technical Specifications - Combustion Engineering Plants Specifications", which states that "MFIVs should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power" as the basis for the 18-month test frequency specified by SR 3.7.3.1. Nevertheless, part-stroke exercising continues to be performed as an augmented test to satisfy System and Maintenance Engineering's desire to periodically exercise the 4-way pilot valves to confirm continued operability.
This cold shutdown justification is similar to CSJ-l18 in the second interval IST Program and CSJ-17 and CSJ-26 in the first interval IST Program.
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Main Steam Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class SGEUVO170 Main Steam Isolation Valve From 2
B SGP-001, Sh. I / G10 Steam Gen. #1 1
SGEUV0171 Main Steam Isolation Valve From 2
B SGP-001, Sh. 1 / D 10 Steam Gen. #2 SGEUV0180 Main Steam Isolation Valve From 2
B SGP-001, Sh. 1 / F10 Steam Gen. #1 SGEUV0181 Main Steam Isolation Valve From 2
B SGP-001, Sh. 1 / B 10 Steam Gen. #2 1
1 1
Function These valves are normally open during steaming operations to provide flowpaths for steam flow to the main turbine generators and associated auxiliaries - non-safety function. They have a closed safety functionn to isolate and maintain the integrity of the steam generators.
Alternate Each of these valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.
Basis Closing any of these valves isolates the associated steam header. During plant operations, isolation of a main steam header would require a significant power reduction and could result in unacceptable steam generator level and reactor power transients with the potential for a plant trip.
The main steam isolation valves are capable of partial stroke exercising. Part-stroke exercising is not considered practical because of the risk of closure.
This risk was recognized by NUREG-1432, Vol 1, Rev. 1, "Standard Technical Specifications - Combustion Engineering Plants Specifications",
which states that "MSIVs should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power" as the basis for the 18-month test frequency specified by SR 3.7.2.1.
Nevertheless, part-stroke exercising continues to be performed as an augmented test to satisfy System and Maintenance Engineering's desire to periodically exercise the 4-way pilot valves to confirm continued operability.
This cold shutdown justification is similar to CSJ-19 in the second interval IST Program and CSJ-25 in the first interval IST Program.
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SIT Vent Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class SIAHV0605 Safety Inj. Tank 2A Vent Valve 2
B SIP-002 / F 15 SIAHV0606 Safety Inj. Tank 2B Vent Valve 2
B SIP-002 / F12 SIAHV0607 Safety Inj. Tank lA Vent Valve 2
B SIP-002 / F07 SLAHV0608 Safety Inj. Tank lB Vent Valve 2
B SIP-002 / F04 SIBHV0613 Safety Inj. Tank 2A Vent Valve 2
B SIP-002 / E15 SIBHV0623 Safety Inj. Tank 2B Vent Valve 2
B SIP-002 / E12 SIBHV0633 Safety Inj. Tank 1AVent Valve 2
B SIP-002 / E07 SIBHVO643 Safety Inj. Tank 1B Vent Valve 2
B SIP-002 / E04 Function These valves have a normally closed safety function to ensure the integrity of the associated safety injection tank (SIT) so that the required nitrogen overpressure is maintained. They have an open safety function to reduce the nitrogen pressure in the SITs during RCS depressurization to preclude nitrogen injection into the RCS.
Alternate Each of these valves will be exercised open and closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.
Basis These valves are normally closed during plant operation. Plant technical specifications require that power be removed from the valves, and that the SIT nitrogen cover gas pressure be maintained within the required range.
Exercising a valve during operation would render the associated SIT inoperable if the cover gas pressure were reduced below the required range.
A valve failing open during testing would completely depressurize the SIT and result in an expedited plant shutdown.
This cold shutdown justification is similar to CSJ-26 in the second interval IST Program and CSJ-22 in the first interval IST Program.
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Containment Refueling Purge Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class CPAUVO002A Containment Purge Supply Otbd.
2 B
CPP-001 / D06 Isolation Valve CPAUVO002B Containment Purge Exhaust Inbd.
2 B
CPP-001 / E03 Isolation Valve CPBUVO003A Containment Purge Supply Inbd.
2 B
CPP-001 / D05 Isolation Valve CPBUVO003B Containment Purge Exhaust Otbd.
2 B
CPP-001 / E02 Isolation Valve Function These 42" valves open to provide flowpaths for containment ventilation during shutdown periods - non-safety function. They have a safety function to close on a containment purge isolation actuation signal (CPIAS) during a loss of shutdown cooling or a fuel handling accident in containment. They are locked closed and blind flanged during plant operation (Modes 1-4).
Alternate These valves will be full-stroke exercised closed during refueling outage Testing periods. Stroke time testing will be performed in conjunction with exercise test.
Basis Per PVNGS Technical Specification 3.6.3.1, these valves must remain closed during plant operation. These valves are administratively maintained in the closed position at all times when the plant is operating in Modes 1-4. The valves are not capable of closing against accident pressure. The outboard valves are blocked closed by the installation of blind flanges during Mode 1-
- 4. Thus they are not required to operate (stroke closed) during operational periods. Due to the large size of these valves and the potential for damage as a result of frequent cycling, it is not prudent to operate them more than is absolutely necessary. The blind flanges are only removed to place the refueling purge system inservice.
This refueling outage justification is similar to CSJ-10 in the second interval IST Program and CSJ-11 in the first interval IST Program. The change to a refueling interval is based on the addition of blind flanges to ensure closure during plant operation.
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RCP Seal Bleed-Off Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.
Class CHBUV0505 Reactor Coolant Pump Seal Bleed-2 A
CHP-002 / H13 off Otbd. Isolation Valve CHAUV0506 Reactor Coolant Pump Seal Bleed-2 A
CHP-002 / H14 off Inbd. Isolation Valve I
I I
_I Function These valves are normally open during plant operation to provide a flowpath for seal bleed-off from the reactor coolant pumps (RCPs) - non-safety function. They have a closed safety function for containment isolation.
Alternate These valves will be exercised closed during refueling outage periods. Stroke Testing time testing and fail safe testing will be performed in conjunction with exercise testing.
Basis These air-operated valves are electrically interlocked so that they cannot be closed when any of the reactor coolant pumps are in operation. Closing either of these valves during RCP operation would interrupt bleed-off flow from the RCP seals and could result in damage to the seals. Thus testing these valves during plant operation would require the unnecessary shutdown of all of the reactor coolant pumps.
Operation of seal injection is also maintained during cold shutdown periods.
It is noted that paragraph 3.1.1.4 of NUREG-1482, Revision 1, permits deferral of tests that require shutdown of RCPs until refueling outages.
This refueling outage justification is similar to CSJ-32 in the second interval IST Program and CSJ-7 in the first interval IST Program. The change to a refueling outage interval is based on seal injection being used during cold shutdown periods.
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 91 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 VALVE RELIEF REQUEST VRR-01 Proposed Alternative In Accordance with 10CFR50.55a(a)(3)(i)
On the basis that the proposed alternative provides an acceptable level of quality and safety.
Code Case OMN MOV Exercising and Stroke Timing Component(s)
Affected:
Component/System Function:
Applicable Code Edition and Addenda:
Applicable Code Requirement(s):
Motor-operated valve assemblies currently included in the Palo Verde Nuclear Generating Station (PVNGS) Motor-Operated Valve Program Various ASME OM Code 2001 Edition w/2003 Addenda ISTA-3130, "Application of Codes Cases", ISTA-3130(b) states, Code Cases shall be applicable to the edition and addenda specified in the test plan.
ISTC-3500, "Valve Testing Requirements" states; Active and passive valves in the categories defined in ISTC-1300 shall be tested in accordance with the paragraphs specified in Table ISTC-3500-1 and the applicable requirements of ISTC-5 100 and ISTC-5200.
ISTC-3700, "Position Verification Testing" states; Valves with remote position indicators shall be observed locally at least once every 2 years to verify the valve operation is accurately indicated.
ISTC-5120, "Motor-Operated Valves", ISTC-5121 (a) states; Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500.
Code Case OMN-1, Revision 0 provides alternative rules to those of OM Code, Subsection ISTC, for preservice and inservice testing to assess the operational readiness of certain electric motor-operated valve assemblies in light-water reactor power plants. However, RG 1.192 has not yet extended its use to the 2001 Edition w/2003 Addenda of the OM Code which is the basis for the planned third 10-year IST program at Palo Verde.
Pursuant to ASME Code Case OMN-1 and the guidelines provided in NUREG-1482, Revision 1, Section 4.2.5, PVNGS proposes to continue implementation of Code Case OMN-1 in lieu of the stroke-time provisions specified in ISTC-5120 for MOVs. Code Case
Reason for Request
Proposed Alternatives and Basis for Use:
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 92 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revi ion AND COMPONENT TABLES 21 Proposed Alternatives OMN-1 has been determined by the NRC to provide an acceptable and Basis for Use:
level of quality and safety when implemented in conjunction with the conditions imposed in RG 1.192.
(Continued)
The conditions specified in RG 1.192 are as follows:
Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, dated June 2003 states that licensees may use Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants," Revision 0, in lieu of the provisions for stroke-time testing in Subsection ISTC of the 1995 Edition up to and including the 2000 Addenda of the ASME OM Code when applied in conjunction with the provisions for leakage rate testing in, as applicable, ISTC 4.3 (1995 Edition with the 1996 and 1997 Addenda) and ISTC-3600 (1998 Edition with the 1999 and 2000 Addenda). In addition, licensees who continue to implement Section XI of the ASME BPV Code as their Code of Record may use OMNN-I in lieu of the provisions for stroke-time testing specified in Paragraph 4.2.1 of ASME/ANSI OM Part 10 as required by 10 CFR 50.55a(b)(2)(vii) subject to the conditions in this Regulatory Guide (RG) 1.192. Licensees who choose to apply OMN-1 are required to apply all its provisions.
The relevant provisions are as follows:
(1) The adequacy of the diagnostic test interval for each motor-operated valve (MOV) must be evaluated and adjusted as necessary, but not later than 5 years or three refueling outages (whichever is longer) from initial implementation of OM7N-1.
(2) When extending exercise test intervals for high risk MOVs beyond a quarterly frequency, licensees must ensure that the potential increase in Core Damage Frequency (CDF) and risk associated with the extension is small and consistent with the intent of the Commission's Safety Goal Policy Statement.
(3) When applying risk insights as part of the implementation of OMN-1, licensees must categorize MOVs according to their safety significance using the methodology described in Code Case OMN-3, "Requirements for Safety Significance Categorization of Components Using Risk Insights for Inservice Testing of LWR Power Plants," with the conditions discussed in RG 1.192 or use other MOV risk ranking methodologies accepted by the NRC on a plant specific or industry-wide basis with the conditions in the applicable safety evaluations.
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In addition the following implementation clarifications are necessary:
(Continued)
OMN-1, RO, Para. 3.1, Design Basis Verification Test Design Basis Verification Testing was completed during plant startup testing and in response to NRC GL 89-10 testing requirements, which meet the intent of this CC requirement.
OMN-1, RO, Para. 3.2, Preservice Testing Preservice Testing was performed pursuant to NRC GL 89-10 testing requirements, which meet the intent of this CC requirement.
OMN-1, RO, Para. 3.3 (b) Inservice Test Because of the extensive PVNGS MOV performance history, some As-Found MOV testing can be waived by a documented Engineering evaluation, e.g., if a modification to the valve or actuator will be performed or if valve maintenance is planned (such as valve repacking), and the activity will require a post maintenance diagnostic test to return the MOV to service. This provision will not apply if there is reason to suspect the MOV is not operating properly prior to the maintenance activity.
OMN-1, RO, Para. 3.3 (c) Inservice Test PVNGS performed differential pressure testing per NRC GL 89-10 and also participated in the JOG differential pressure testing program (i.e. dynamic testing) that has been completed. The mix of static and dynamic testing at PVNGS in the future will be static testing with additional dynamic testing performed as required by the PVNGS MOV Program to address MOV modifications.
OMN-1, RO, Para. 3.3.1, Inservice Test Interval PVNGS has committed to the JOG program as part of its response to NRC GL 96-05. Inservice Test Intervals will be established based on MOV margin and the valve's risk/safety significance in accordance with JOG program requirements. PVNGS is currently implementing the JOG Interim Test Program per MPR 1807.
PVNGS will implement the final JOG Periodic Verification Program per MPR 2524-A as noted in the NRC SER on the JOG program.
OMN-1, RO, Para. 3.4 Effect of MOV Replacement, Repair, or Maintenance Diagnostic test results within the MOV Program setpoint bands are satisfactory and do not require analysis.
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PVNGS elects not to use Grouping of MOVs for Inservice Testing (Continued)
OMN-1, RO, Para. 3.7 Risk Basis Criteria for MOV Testing PVNGS is currently not planning to implement a Risk Informed Program for its IST program. As noted above, PVNGS uses risk/safety significance and MOV margin as part of the JOG program to establish MOV testing frequency.
OMN-1, RO, Para. 6.3 Evaluation of Data and Para. 6.4 Determination of MOV Functional Margin PVNGS utilizes the JOG Program criteria for determining MOV test frequency. The MOV test frequencies have been established to ensure MOV setpoints and MOV margins are maintained over the MOV test interval which meets the intent of these CC sections.
OMN-1, RO, Para. 6.4.1 Determination of Valve Operating Requirements A Stem Factor shall be determined for rising stem valves whenever stem thrust and stem torque are measured. It is not possible to measure thrust and torque on all rising stem valves.
OMN-1, RO, Para. 6.4.2.1 Available Output Based on Motor Capabilities and CC OMN-1 Para. 6.4.2.2 Available Output Based on Torque Switch Setting Actuator output capabilities are determined as an integral part of the MOV design basis calculations and are not performed as part of the evaluation of MOV test data. This applies to all actuators and includes those actuators set up based on limit switches.
For actuators set up based on torque switches, available output includes torque measurement uncertainty (or displacement uncertainty if spring pack displacement is used) and torque switch repeatability.
OMN-1, RO, Para. 6.4.3 Calculation of Functional Margin Margin is calculated as a percentage (vice difference in thrust or torque between available output and valve operating requirements).
OMN-1, RO, Para. 6.4.4 Determination of MOV Test Interval As noted above for CC OMN-1 Para 3.3.1, test interval is based on the NRC approved JOG program.
OMN-1, RO, Para. 9.1 Test Information Test Information relevant to the MOV being tested and relevant test parameters will be recorded electronically with the test trace and/or
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to testing, e.g., name plate information; breaker setting, etc. are maintained in plant records.
(Continued)
Code Case OMN-1, RO, should be considered acceptable for use with OM Code-2001 Edition w/2003 Addenda as the Code of record.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), PVNGS requests relief from the specific ISTC Code requirements identified in this relief request.
==
Conclusion:==
10 CFR 50.55a(a)(3) states:
"Proposed alternatives to the requirements of paragraphs (c), (d), (e),
(f), (g), and (h) of this section or portions thereof may be used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i)The proposed alternatives would provide an acceptable level of quality and safety, or (ii)Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
The continued use of ASME Code Case OMN-1, Revision 0, as discussed in this relief request provides an acceptable level of quality and safety. Therefore, APS requests that the proposed alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(i).
Duration of Proposed Alternatives:
The proposed alternative identified in this relief request shall be utilized during the Third Ten Year IST Interval.
Precedents:
Relief Request VRR-01 was previously authorized for Palo Verde as Relief Request VRR-12 pursuant to 10 CFR 50.55a(a)(3)(i) for interval 2 in the NRC Safety Evaluation dated July 8, 1999. (TAC NOS. MA0757, MA0758 and MA0759) (ADAMS Accession No.
9907150128)
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References:
NUREG-1482, Revision 1, Section 4.2.5, "Alternatives to Stroke-Time Testing" Regulatory Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code", Table 2, "Conditionally Acceptable OM Code Cases" OM Code-2001 Edition w/2003 Addenda, Paragraph ISTC-5120, "Motor Operated Valves" OM Code-2001 Edition w/2003 Addenda, Paragraph ISTA-3130, "Application of Code Cases" Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants" Interval 2 NRC SER dated 7/8/1999
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 97 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 Notes, Legends, Definitions, and Abbreviations Notes Note 1 Whenever check valve is disassembled for inspection, perform a manual exercise per 73ST-9ZZ25.
Note 2 Manual exercise per 73ST-9ZZ25 can be substituted for the regular check valve exercise test.
Note 3 Perform a partial stroke exercise with flow after reassembly, if practical.
Note 4 Check valve is tested under the PVNGS Check Valve Condition Monitoring Program and 73DP-9XI05.
Note 5 As provided for in ASME OM Code Case OMN-1, MOVs are tested in the PVNGS 89-10 Program in lieu of the stroke time test and valve position verification surveillances that were performed in the past. This Code Case requires Active MOVs to be exercised once per fuel cycle (ICY). Additional exercising is performed at the Licensee's discretion (refer to VRR-01) as delineated in the component tables. Post maintenance retest requirements for MOVs are specified in 39DP-9ZZ04 Appendix G.
Note 6 A 42-inch refueling purge valve is not a required containment isolation valve when its flow path is isolated with a blind flange tested in accordance with TS SR 3.6.1.1 (TS LCO 3.6.3 Note 5)
Pump Table Legend Pump ID Plant equipment identifier. The first 2 letters in the ID indicate the system.
Description Name / description of the pump Code Class ISI classification of the pump: 1, 2, 3, or N (non-class)
Drawing / Coord.
Piping and Instrument Diagram number and coordinates showing the pump Test Parameters The table indicates the frequency which pump speed, pressure, flow rate, and vibration are measured, along with any applicable relief requests Test Procedure Procedure(s) which satisfy the testing requirements Remarks Additional explanation or clarification, if required Valve Table Legend Valve ID Plant equipment identifier. The first 2 letters in the ID indicate the system.
Description Name / description of the valve Drawing Piping and Instrument Diagram number showing the valve Coord Coordinates where the valve is located on the drawing Sht# Drawing sheet number
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Size Nominal pipe size of the valve, in inches Type Valve type:
BF Butterfly Valve CK Check Valve DI Diaphragm valve GA Gate Valve GL Globe Valve PSV Pressure Safety Relief Valve RD Rupture Disk VR Vacuum Relief Act. Valve actuator type:
AO Air Operated HY Hydraulically Operated MA Manually Operated MO Motor Operated SA Self Actuating SO Solenoid Operated Cat. A, B, C, or D, per ISTC-1300, "Valve Categories" A/P A (active) or P (passive) valve, per ISTA-2000, "Definitions."
S.P. Safety position: 0 (open), C (closed), or OC (both open and closed).
Test Test(s) performed on the valve. The first two letters indicate the type of test:
AJ Appendix J Leak Test BD Bi-Directional Check Valve Test (non-safety direction)
CV Check Valve Test (safety function direction)
FS Full Stroke Exercise Test FT Fail Safe Test LT Leak Test other than an Appendix J Test PS Partial Stroke Exercise Test REP Replacement ST Stroke Time Test SV Pressure Safety Relief Valve Test VP Valve Position Indication Test A third letter is used where required to indicate stroke direction: 0 (open) or C (closed), or a special activity, like I (inspection).
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CLR Per the Containment Leak Rate Program CMP Per the Check Valve Condition Monitoring Program CSD Cold Shut Down QTR Quarterly RFO Refueling Outage STF Special Test Frequency 6M Once per 6-months 1YR Once per year 18M Once per 18 months 1CY Once per fuel cycle 2YR Once every 2 years 5YR Mandatory Appendix 1-1320 (at least once every 5 years) 10Y Mandatory Appendix 1-1350 (at least once every 10 years)
Procedure Procedure in which the test is performed CSJ/ROJ/VRR Applicable Cold Shutdown Justification, Refueling Outage Justification, or Valve Relief Request Remarks Additional explanation or clarification, if required Definitions Augmented Components or tests included within the IST Program at the discretion of IST Engineering. Augmented components are generally tested in accordance with the Code to the extent practical; however, deviations from Code requirements do not require relief.
Abbreviations ACU Air Conditioning Unit AF Auxiliary Feedwater system AFAS Auxiliary Feedwater Actuation Signal AFW Auxiliary Feedwater ANII Authorized Nuclear Inservice Inspector AOV Air-Operated Valve ASME American Society of Mechanical Engineers BAMP Boric Acid Makeup Pump CC Code Case CEDM Control Element Drive Mechanism CH Charging system CIAS Containment Isolation Actuation Signal CIV CP CPIAS CS CSD CsJ CST CT DF DG DW EC Containment Isolation Valve Containment Purge system Containment Purge Isolation Actuation Signal Containment Spray Cold Shutdown Cold Shutdown Justification Condensate Storage Tank Condensate Transfer system Diesel Fuel system Diesel Generator system Demineralized Water system Essential Chilled Water system
NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 100 of 100 PUMP AND VALVE INSERVICE TESTING PROGRAM 73DP-9XI01 Revision AND COMPONENT TABLES 21 EDG ESF EW FP FWIV GA GL GR H2 HC HP HPSI HVAC IA ISl IST LCO LOCA LPSI LTOP MFIV MOV MSIV NC PASS PC PEN.
PRA/RA PRR PVNGS RC RCP RCS RD Emergency Diesel Generator Engineered Safety Features Essential Cooling Water system Fire Protection system Feedwater Isolation Valve Service Gas system Generic Letter Gaseous Radwaste system Hydrogen Containment HVAC system Hydrogen Purge system High Pressure Safety Injection Heating, ventilation, and air conditioning Instrument Air system Inservice Inspection Inservice Testing Limiting Condition for Operation Loss of Coolant Accident Low Pressure Safety Injection Low Temperature Over Pressure Main Feedwater Isolation Valve Motor-Operated Valve Main Steam Isolation Valve Nuclear Cooling Water system Post-Accident Sampling System Fuel Pool Cooling Penetration Probablistic Risk Assessment/Risk Assessment Pump Relief Request Palo Verde Nuclear Generating Station Reactor Coolant system Reactor Coolant Pump Reactor Coolant System Radioactive Drains RDT RMW ROJ RWT SDC SG SG SI SIAS SIT SOV SP SR SS TDAFW TRM TS TSR VCT VRR WC Reactor Drain Tank Reactor Makeup Water Refueling Outage Justification Refueling Water Tank Shutdown Cooling Steam Generator Main Steam system Safety Injection system Safety Injection Actuation Signal Safety Injection Tank Solenoid-Operated Valve Essential Spray Pond system Surveillance Requirement Sampling system Turbine-Driven Auxiliary Feedwater Pump Technical Requirements Manual Technical Specification TRM Surveillance Requirement Volume Control Tank Valve Relief Request Normal Chilled Water system