View source for L-07-056, Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update

{{Adams
| number = ML070890491
| issue date = 03/28/2007
| title = Requests Approval of Proposed Alternatives and Relief for Inservice Testing Program Ten-Year Update
| author name = Lash J
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/ADRO
| docket = 05000334
| license number = DPR-066
| contact person = 
| case reference number = L-07-056
| document type = Code Relief or Alternative, Letter type:L
| page count = 369
}}

=Text=
{{#Wiki_filter:FENOC FirstEnergyNuclear Operating Company James H. Lash                                                                                  724-682-5234 Site Vice President                                                                       Fax: 724-643-8069 March 28, 2007 L-07-056 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001

==Subject:==
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Inservice Testing Program Ten-Year Update FirstEnergy Nuclear Operating Company (FENOC) requests approval of proposed alternatives and relief requests associated with the fourth ten-year interval update of the Beaver Valley Power Station (BVPS) Unit No. 1 Inservice Testing Program for Pumps and Valves (IST Program). This request was initially submitted with enclosures on CD-ROM by a FENOC letter dated March 21, 2007.
Enclosed with this letter are paper copies of the fourth ten-year interval update of the BVPS Unit No. 1 IST Program, and plant drawings that were previously submitted on CD-ROM with the March 21, 2007 letter. The enclosed paper copies are submitted to replace information submitted on CD-ROM due to difficulty reading the CD-ROM files.
The enclosed IST program has been updated to the American Society of Mechanical Engineers Operations and Maintenance (OM) Code 2001 Edition, "Code for Operation and Maintenance of Nuclear Power Plants," with OM Code Addenda through OMb-2003.
The plant drawings are provided for information.
Proposed alternatives and relief requests associated with Issue 4, Revision 0 of the BVPS Unit No. 1 Inservice Testing Program for Pumps and Valves are submitted in accordance with 10 CFR 50.55a. Thirteen (13) requests are associated with pump testing requirements, and one (1) request is associated with valve test requirements. A list of the 10 CFR 50.55a requests is attached to this letter. The list identifies the request number, applicable code paragraph, requests that are similar to those approved for the third ten-year interval IST Program, and the location in the enclosed IST Program document where the details of the 10 CFR 50.55a requests are presented.
AcLqY

Beaver Valley Power Station, Unit No. 1 Inservice Testing Program Ten-Year Update L-07-056 Page 2 The fourth ten-year inservice testing interval for BVPS Unit No. 1 commences on September 20, 2007. Therefore, FENOC requests NRC approval of the proposed alternatives and relief requests prior to September 20, 2007.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Henry L. Hegrat, Supervisor, FENOC Fleet Licensing at 330-374-3114.
Sincerely, aL    James H. Lash

==Attachment:==

List of 10 CFR 50.55a Requests

==Enclosures:==
: 1. Beaver Valley Power Station, Unit No. 1, Inservice Testing (IST) Program for Pumps and Valves
: 2. Plant Drawings c:    Ms. N. S. Morgan, NRR Project Manager Mr. P. C. Cataldo, NRC Senior Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

ATTACHMENT TO LETTER L-07-056 LIST OF 10 CFR 50.55a REQUESTS Request                                                       Similar to    Enclosure Number       Applicable Code Paragraph                        Approved      Page Request'      Number 3 PRR1         10 CFR 50.55a(a)(3)(i), Proposed Alternative     Similar       51 PRR2         10 CFR 50.55a(a)(3)(i), Proposed Alternative     Similar       54 PRR3         10 CFR 50.55a(f)(5)(iii), Relief Request         Similar       59 PRR4         10 CFR 50.55a(a)(3)(i), Proposed Alternative     Similar       62 PRR5         10 CFR 50.55a(f)(5)(iii), Relief Request         Revised       64 PRR6         10 CFR 50.55a(a)(3)(i), Proposed Alternative     Similar       67 PRR7         10 CFR 50.55a(f)(5)(iii), Relief Request         Similar       72 PRR8         10 CFR 50.55a(a)(3)(i), Proposed Alternative     Similar 2     74 PRR9         10 CFR 50.55a(f)(5)(iii), Relief Request         Similar       78 PRR1O        10 CFR 50.55a(f)(5)(iii), Relief Request         Similar       81 PRR1 1       10 CFR 50.5 5a(a)(3)(ii), Proposed Alternative   New           85 PRR12        10 CFR 50.55a(a)(3)(ii), Proposed Alternative    New           98 PRR13        10 CFR 50.55a(a)(3)(i), Proposed Alternative     New           106 VRR1         10 CFR 50.55a(a)(3)(i), Proposed Alternative     New           319 Notes:
: 1. Requests are identified as "Similar" or "Revised" with respect to the requests approved for the third ten-year interval IST Program. Other requests are identified as "New."
: 2. Request PRR8 is "Similar" with respect to the requests approved for the third ten-year interval IST Program, but was applied to additional pumps.
: 3. Pump requests (PRR) are provided in Section III, and the valve request (VRR) is provided in Section IX of the enclosed document.

Beaver Valley Power Station Unit 1 Inservice Testing (IST) Program For Pumps And Valves Issue 4, Revision 0 Preparer                                                 Date: 51-IQR                                                      Date:          7 Technical Services Engineering Review                    Date:
Operations Approval                                      Date:
'This 10-year interval update was made using the ASME OM Code-2001 Edition with Addenda through OMb-2003.

Beaver Valley Power Station Unit I Inservice Testing (IST) Program For Pumps And Valves Issue 4, Revision 0 Effective Date of Procedure: 9/20107

Beaver Valley Power Station                          Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                                           Page 2 of 320 Table Of Contents SECTION I:             PUMP TESTING REQUIREMENTS ................................................................                                3 SECTIO N II:           PUM P O UTLINE TABLES .............................................................................                     17 SECTION III:           PUM P RELIEF REQUESTS .........................................................................                        50 SECTION IV:            PUMP MINIMUM OPERATING POINT (MOP) CURVES ...............................                                             108 SECTION V:             VALVE TESTING REQUIREMENTS ..............................................................                             126 S EC T IO N V I:       VA LV E TA BLES ..............................................................................................        143 SECTION VII:           VALVE COLD SHUTDOWN JUSTIFICATIONS (VCSJ) .................................                                           233 SECTION VIII:          VALVE REFUELING OUTAGE JUSTIFICATIONS (VROJ) ............................                                             265 SECTIO N IX:           VALVE RELIEF REQ UESTS ..........................................................................                     318 Table of Contents

Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves              Page 3 of 320 SECTION I:     PUMP TESTING REQUIREMENTS

Beaver Valley Power Station                         Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 4 of 320 Title 10, Part 50.55a of the Code of Federal Regulations, Paragraph (f)(4)(ii) requires that 10-year IST Programs comply with the latest NRC approved edition and addenda of the Code incorporated by reference in Paragraph (b), 12 months prior to the start of the 120-month inspection interval. The fourth 10-year inservice testing interval for Beaver Valley Power Station (BVPS) Unit 1 commences on September 20, 2007. The use of any later edition and addenda of the ASME OM Code is allowed if it has been incorporated in Paragraph (b)(2) of 10 CFR 50.55a, or if approved by the NRC as an acceptable alternative.
The Inservice Testing (IST) Program for pumps at BVPS, Unit 1, is based on the following:
* American Society of Mechanical Engineers (ASME) OM Code-2001 Edition, Code for Operation and Maintenance of Nuclear Plants, with Addenda through OMb-2003.
* Generic Letter No. 89-04, "Guidance on Developing Acceptable Inservice Testing Programs"
* NUREG-1482, Revision 1 "Guidelines for Inservice Testing at Nuclear Power Plants"
* Technical Specification 5.5.4, "Inservice Testing Program" The pumps included in this program are all ASME Class 1, 2, or 3 centrifugal and positive displacement pumps that are provided with an emergency power source, which are required in shutting down a reactor to the safe shutdown condition, maintaining the safe shutdown condition, or mitigating the consequences of an accident, at BVPS, Unit 1. Unit 1 was designed with Hot Shutdown as its Safe Shutdown condition (Per NUREG-1482, Revision 1, Section 2.2, "If the plant was licensed for a safe shutdown condition of hot standby or hot shutdown rather than cold shutdown, the IST Program document will stipulate that the plant was not designed and licensed for a safe shutdown of cold shutdown"). Although Unit 1 was not designed and licensed for a safe shutdown of cold shutdown, it will generally be treated as such for consistency with BVPS-2.
Exclusions The following are excluded from the requirements of Subsection ISTB:
* Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver.
* Pumps that are supplied with emergency power solely for operating convenience.
         " Skid-mounted pumps that are tested as part of the major component and are justified by BVPS-1 to be adequately tested. Skid-Mounted Pumps are pumps which are integral to or support operation of a parent pump or major component. NUREG-1482, Rev.1, Section 3.4, "Skid-mounted Components and Component Subassemblies" provides further discussion pertaining to skid-mounted components.
NOTE:        Transitioning to the applicable edition of the ASME OM Code for the IST Fourth 10-Year Interval requires the Grouping of pumps according to function as well as adopting the Comprehensive Pump Test. The pump Groupings, instrument accuracy requirements, test parameters and acceptance criteria for tests parameters are detailed in the following.

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 5 of 320 When a Group A test is required a Comprehensive test may be substituted. When a Group B test is required a Group A test or Comprehensive test may be substituted. A preservice test may be substituted for any inservice test.
Group A Pumps The ASME OM Code defines Group A pumps as those pumps that are operated continuously or routinely during normal operation, cold shutdown, or refueling operations. BVPS considers the following Unit 1 pumps as being categorized as Group A as well as justification for grouping. Justification does not necessarily consider all safety related functions.
Charging / High Head Safety Injection Pumps, [ICH-P-1A, 1B, IC] - The Charging Pumps support the Reactor Coolant System (RCS) during all normal modes of plant operation. The functions performed include, but are not limited to, the following; maintenance of seal water injection flow to the Reactor Coolant Pumps (RCPs); control of RCS inventory; supplying pressurizer auxiliary spray and reducing the radioactivity level in the reactor coolant. The pumps also serve as the High Head Safety Injection (HHSI) Pumps for emergency cool cooling during post accident conditions.
             "    Boric Acid Transfer Pumps, [ICH-P-2A, 2B] - The Boric Acid Transfer Pumps provide a solution of soluble boric acid for reactor coolant makeup. These pumps also provide boric acid for emergency boration.
* Residual Heat Removal Pumps, [I RH-P-1A, 1B] - The Residual Heat Removal Pumps are required to operate when maintaining the plant in a cold shutdown condition. Although not needed for safe shutdown of Unit 1, the removal of decay and sensible heat by the Residual Heat Removal System is considered a safety related function.
* Component Cooling Water Pumps, [ICC-P-1A, 1B, 1C] - The Component Cooling Water Pumps operate continuously during normal plant operation to supply cooling water to non-essential heat loads as well as cooling water to the RCP motor bearings and thermal barrier. Their safety related function is to provide cooling water for Residual Heat Removal System support.
             "    River Water Pumps [IWR-P-1A, 1B, 1C] - The River Water Pumps operate continuously during normal plant operation to supply cooling water to non-essential heat loads. During post accident conditions they provide the heat sink to the following components: recirculation spray heat exchangers, charging pump lube oil coolers, control room river water cooling coil and Emergency Diesel Generator cooling system heat exchanger.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                            Page 6 of 320 Group B Pumps The ASME OM Code defines Group B pumps as those pumps in standby systems that are not operated routinely except for testing. BVPS-1 considers the following pumps as being categorized as Group B as well as justification for grouping.
* Low Head Safety Injection Pumps, [1SI-P-1A, 1B] -The Low Head Safety Injection Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating Modes. The pumps are required to operate primarily during a large break loss-of-coolant accident (LOCA), in addition to other design basis accidents (DBA), in order to provide low head safety injection and recirculation flow to the RCS, and for long term shutdown cooling during post-LOCA conditions.
* Quench Spray Pumps, [1QS-P-1A, 1B] - The Quench Spray Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating modes. The pumps are required to operate only during a loss-of-coolant accident (LOCA) for containment heat removal and pressure suppression. The Quench Spray System also serves in removing fission products released into the containment atmosphere during a LOCA by the admission of sodium hydroxide to the spray stream.
* Chemical Injection Pumps, [IQS-P-4A, 4B, 4C, 4D] - The Chemical Injection Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating modes. The pumps are required to operate only during a loss-of-coolant accident (LOCA) to provide sodium hydroxide to the Quench Spray System in order to provide iodine removal from the containment atmosphere and to maintain containment sump pH levels.
* Inside Recirculation Spray Pumps, [1RS-P-1A, IB] -The Inside Recirculation Spray Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating modes. The pumps are required to operate only during a loss-of-coolant accident (LOCA) for long term containment heat removal and pressure suppression after sufficient inventory has collected in the containment sump to support pump operation.
* Outside Recirculation Spray Pumps, [1RS-P-2A, 2B] - The Outside Recirculation Spray Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating modes. The pumps are required to operate only during a loss-of-coolant accident (LOCA) for long term containment heat removal and pressure suppression after sufficient inventory has collected in the containment sump to support pump operation. The pumps also have the capability of providing sump inventory to the suction supply of the High Head Safety Injection Pumps.
* Turbine Driven Auxiliary Feedwater Pump, [1FW-P-2]. - The Turbine Driven Auxiliary Feedwater Pump is not utilized during any plant operating evolution. The pump remains in standby during all operating modes and is required to operate only in the event of a main turbine trip with a total loss of all electrical power (Station Blackout) in order to provide emergency makeup to the Steam Generators during a loss of normal feedwater.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 7 of 320
* Motor Driven Auxiliary Feedwater Pumps, [IFW-P-3A, 3B] - The Motor Driven Auxiliary Feedwater Pumps may be utilized during startup from refueling outages to fill the steam generators and to maintain steam generator level prior to initiation of normal feedwater. However, restart is not dependent upon operation of the Motor Driven Auxiliary Feedwater Pumps since the Steam Generator startup Feedwater Pump
[1 FW-P-4] may be used to perform this non-safety related function. With the possible exception of the above, the Motor Driven Auxiliary Feedwater Pumps remain in standby during all operating modes. The pumps also serve as an emergency source of feedwater supply to the steam generators during a loss of normal feedwater, loss of offsite power, secondary side pipe ruptures, or cool down following a steam generator tube rupture.
* DG Fuel Oil Transfer Pumps, [IEE-P-1A, IB, IC, 1D] - The Fuel Oil Transfer Pumps are not utilized during any plant operating evolution. The pumps remain in standby during all operating Modes. The pumps are required to operate only during emergency diesel generator operation to replenish day tank inventory.
Instrument Accuracy Requirements Instrument accuracy shall be within the limits specified in Table ISTB-3500-1, as reflected below. If a parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table ISTB-3500-1. For individual analog instruments, the required accuracy is percent of full scale. For digital instruments, the required accuracy is over the calibrated range. For a combination of instruments, the required accuracy is loop accuracy. Table ISTB-3500-1 below reflects the required instrument accuracies for both the Group A test and Group B test as well Comprehensive testing applicable to Group A and Group B pumps and Preservice tests.
The full-scale of each analog instrument shall be not greater than three times the reference value. Per Code Case OMN-6, Alternate Rules for Digital Instruments, digital instruments shall be selected such that the reference value does not exceed 90% of the calibrated range of the instrument. This Code Case is unconditionally approved for use by US NRC Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code.
Table ISTB-3500-1 Required Instrument Accuracy (%)
Quantity                   Group A and              Comprehensive and Group B Tests, %            Preservice Tests, %
Pressure                                 +/-2                              1/
Flow Rate                                +/-2                            +2 Speed                                    +2                            +2 Vibration                                 +/- 5                           +5 Differential Pressure                    +/- 2                           + 1/2 Instrument accuracy is defined as the allowable inaccuracy of an instrument loop based on the square root of the sum of the square of the inaccuracies of each instrument in the loop when considered separately. Alternatively, the allowable inaccuracy of the instrument loop may be based on the output for a known input into the instrument loop.

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 8 of 320 Instrument loop is defined as two or more instruments working together to provide a single output (e.g., a vibration probe and its associated signal conditioning and readout devices, transmitter and indicator, etc.). Per ASME OM Code Interpretation 04-07, pump suction and discharge pressure instruments are not considered an instrument loop when used in conjunction to determine differential pressure.
Test Parameters The requirements of the Code and the guidance provided by NUREG-1482, Rev. 1 will be followed at all times unless specific relief has been granted by the NRC. A Group A or Group B inservice test, run quarterly, as applicable, and a Comprehensive inservice test, run biennially, to measure or observe the test quantities listed in Table ISTB-3000-1, below, is required for all pumps in the IST Program.
Pursuant to ISTB-3550, "Flow Rate"; When measuring flow rate, a rate or quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include the method used to reduce the data. Internal recirculated flow is not required to be measured. External recirculated flow is not required to be measured if it is not practical to isolate, has a fixed resistance, and has been evaluated by BVPS-1 to not have a substantial effect on the results of the test.
TABLE ISTB-3000-1 INSERVICE TEST PARAMETERS Quantity       Preservice Group A         Group B Comprehensive                      Remarks Test         Test         Test          Test Speed: N                 X            X           X              X          If variable speed Differential             X            X           X              X          Centrifugal pumps, including Pressure: AP                                   (Notel)                      vertical line shaft pumps Discharge                X            X           X              X          Positive displacement pumps Pressure: P Flow Rate: Q             X            X           X              X (Note 1)
Vibration:               X            X                          X          Peak Velocity, V, NOTE:
(1)   For positive displacement pumps, flow rate shall be measured or determined. For all other pumps, differential pressure or flow rate shall be measured or determined.
Test Duration (a)   For the Group A test and the Comprehensive test, after pump conditions are as stable as the system permits, each pump shall be run at least 2 minutes. At the end of this time at least one measurement or determination of each of the required quantities shall be made and recorded.
(b)   For the Group B test, after pump conditions are stable, at least one measurement or determination of the required quantity shall be made and recorded.

Beaver Valley Power Station                         Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 9 of 320 Reference Values (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.
(b)  New or additional reference values shall be established as required by ISTB-3310, ISTB-3320, or ISTB-6200(c).
(c)  Reference values shall be established only when the pump is known to be operating acceptably.
(d)  Reference values shall be established at a point(s) of operation (reference point) readily duplicated during subsequent tests.
(e)  Reference values shall be established in a region(s) of relatively stable pump flow.
(1)     Reference values shall be established within +/-20% of pump design flow rate (i.e.,
the flow rate at the design point or the accident analysis flow, with operation at the best efficiency point (BEP) desired provided all are greater than or equal to the maximum accident analysis flow) for the Comprehensive pump test.
(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 shall be established at the highest practical flow rate.
(f)  All subsequent test results shall be compared to these initial reference values or to new reference values established per ISTB-3310, ISTB-3320, or ISTB-6200(c).
(g)  Related conditions that can significantly influence the measurement or determination of the reference value shall be analyzed in accordance with ISTB-6400.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 10 of 320 Centrifugal Pump Test Acceptance Criteria The allowable ranges for centrifugal pump test parameters are specified in Table ISTB-51 00-1 and are reflected below. It should be noted that the hydraulic acceptance criteria defining Acceptable Range and Required Action Range for the quarterly Group A and Group B tests are less stringent than the acceptance range imposed on the hydraulic test parameters associated with the biennial Comprehensive test. In addition, an Alert Range is imposed on the hydraulic parameters for centrifugal pumps during the Comprehensive test.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria Required Pump          Test       Acceptable                               Action Range Test Type          Speed      Parameter        Range          Alert Range          Low           High N/A          Q        0.90 to 1.10 Qr         None          < 0.90 Qr     > 1.10 Qr N/A          AP      0.90 to 1.10 APr         None         < 0.90 APr    > 1.10 APr Group A1'2                                                  > 2.5Vr  to 6 Vror                   >6Vr
                         >600       V, or Vd        < 2.5Vr        >0.325 to 0.7        None            or in/sec                     >0.7 in/sec N/A          Q        0.90 to 1.10 Qr         None          < 0.90 Qr     > 1.10 Qr N/A          AP      0.90 to 1.10 APr         None         < 0.90 APr    > 1.10 APr N/A          Q        0.94 to 1.03 Qr   0.90 to <0.94 Qr    < 0.90 Qr     > 1.03 Qr N/A          AP      0.93 to 1.03 APr  0.90 to <0.93 APr   < 0.90 APr    > 1.03 APr Comprehensive 12                                                > 2.5V, to 6 Vr or                   >6 Vr
_>600      V, or Vd        < 2.5Vr        >0.325 to 0.7        None            or in/sec                     >0.7 in/sec NOTES: The subscript r denotes reference value, the subscript v denotes vibration velocity reference value, and the subscript d denotes displacement.
(1)    Vibration parameter per Table ISTB-3000-1. Vr is vibration reference value in the selected units.
(2)    Refer to Fig. ISTB-5200-1 to establish displacement limits for pumps with speeds
                   &#x17d;>600 rpm.
All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200, as reflected in the Corrective Action section following pump test acceptance criteria.
NOTE:      The vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-51 00-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 11 of 320 Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria The allowable ranges for vertical line shaft centrifugal pump test parameters are specified in Table ISTB-5200-1 and are reflected below. It should be noted that the hydraulic acceptance criteria defining Acceptable Range and Required Action Range for the quarterly Group A and Group B tests are less stringent than the acceptance range imposed on the hydraulic test parameters associated with the biennial Comprehensive test.
A vertical line shaft pump is defined as a vertically suspended pump, where the pump driver and the pumping element are connected by a line shaft within an enclosing column which contains the pump bearings, making pump bearing vibration measurements impracticable.
Table ISTB-5200-1 Vertical Line Shaft and Centrifugal Pumps Test Acceptance Criteria Required Pump         Test       Acceptable                               Action Range Test Type           Speed     Parameter        Range           Alert Range         Low           High N/A          Q       0.95 to 1.10 Qr    0.93 to <0.95 Qr   < 0.93 Qr     > 1.10 Qr N/A         AP       0.95 to 1.10 APr  0.93 to <0.95 AP,  < 0.93 APr   > 1.10 APr Group    A1'2                                                  > 2.5V, to 6 Vr                   >6Vr
_>600     Vv or Vd         - 2.5Vr         >0.325 to 0.7      None            or in/sec t>0.7                        in/sec in/sec N/A        Q, or     0.90 to 1.10 Qr          None         < 0.90 Qr     > 1.10 Qr N/A         AP       0.90 to 1.10 APr         None        < 0.90 AP,    > 1.10 APr N/A          Q       0.95 to 1.03 Qr    0.93 to <0.95 Q,   < 0.93 Qr     > 1.03 Qr N/A         AP       0.95 to 1.03 APr  0.93 to <0.95 AP,  < 0.93 APr    > 1.03 APr Comprehensive 1,2                                                  > 2.5Vr to 6 Vr                   >6Vr
_&#x17d;600     V, or Vd        < 2.5Vr          >0.325 to 0.7      None            or in/sec t>0.7                        in/sec in/sec NOTES: The subscript r denotes reference value, the subscript v denotes vibration velocity reference value, and the subscript d denotes displacement.
(1)   Vibration parameter per Table ISTB-3000-1. Vr is vibration reference value in the selected units.
(2)   Refer to Fig. ISTB-5200-1 to establish displacement limits for pumps with speeds
                   &#x17d;_600 rpm.
All deviations from the reference values shall be compared with the ranges of Table ISTB-5200-1 and corrective action taken as specified in ISTB-6200, as reflected in the Corrective Action section following pump test acceptance criteria.
NOTE:       The vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-5200-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 12 of 320 Positive Displacement Pump Test Acceptance Criteria The allowable ranges for positive displacement parameters are specified in Table ISTB-5300-1 and Table ISTB-5300-2, and are reflected below. It should be noted that the hydraulic acceptance criteria defining Acceptable Range and Required Action Range for the quarterly Group A and Group B tests are less stringent than the acceptance range imposed on the hydraulic test parameters associated with the biennial Comprehensive test.
Table ISTB-5300-1 Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria Required Pump         Test        Acceptable                               Actio Range Test Type         Speed      Parameter        Range           Alert Range         Low          High N/A           Q       0.95 to 1.10 Qr   0.93 to <0.95 Qr    < 0.93 Qr    > 1.10 Qr 0.90 to <0.93 Pr   < 0.90 Pr    > 1.10 Pr Group A1'2          N/A           P       0.93 to 1.10 Pr
                                                                 > 2.5Vr to 6 Vror     None        >6Vror
                        >600       V, or Vd        < 2.5Vr     >0.325 to 0.7 in/sec              >0.7 in/sec Group B            N/A           Q       0090 to 1.10 Qr          None         < 0.90 Qr    > 1.10 Qr N/A           Q       0.95 to 1.03 Qr    0.93 to <0.95 Qr   <0.93 QO     > 1.03 Qr Comprehensive1,2        N/A C rn          P       0.93 to 1.03 Pr   >0.90 2   to <0.93
                                                                      .5Vr Pr to 6 Vror < 0.90 NonePr     >>6Vror 1.03 Pr N/A       Vv or Vd        < 2.5Mr     >0.325 to 0.7 in/sec              >0.7 in/sec NOTES: The subscript r denotes reference value, the subscript v denotes vibration velocity reference value, and the subscript d denotes displacement.
(1)  Vibration parameter per Table ISTB-3000-1. Vr is vibration reference value in the selected units.
(2)   Refer to Fig. ISTB-5200-1 to establish displacement limits for pumps with speeds
_>600 rpm.
Table ISTB-5300-2 Reciprocating Positive Displacement Pump Test Acceptance Criteria Required Pump          Test       Acceptable                               Action Range Test Type         Speed      Parameter        Range           Alert Range         Low          High N/A           Q       0.95 to 1.10 Qr    0.93 to <0.95 Qr   < 0.93 QO > 1.10 Qr Group A            N/A           P       0.93 to 1.10 Pr    0.90 to <0.93 Pr   < 0.90 Pr    > 1.10 Pr N/A       V,, or Vd       < 2.5V,         > 2.5Vr to 6 Vr     None         >6Vr Group B            N/A           Q       0.90 to 1.10 Or          None         < 0.90 Qr    > 1.10 QO N/A           Q       0.95 to 1.03 Qr    0.93 to <0.95 Qr   < 0.93 Qr    > 1.03 Qr Comprehensive         N/A           P       0.93 to 1.03 Pr    0.90 to <0.93 Pr   < 0.90 Pr    > 1.03 Pr N/A       Vv or Vd        _<2.5Vr         > 2.5Vr to 6 Vr     None         >6Vr NOTES: The subscript r denotes reference value, the subscript v denotes vibration velocity reference value, and the subscript d denotes displacement.

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 13 of 320 All deviations from the reference values shall be compared with the ranges of Table ISTB-5300-1 or Table ISTB-5300-2, as applicable, and corrective action taken as specified in ISTB-6200, as reflected in the Corrective Action section following pump test acceptance criteria.
NOTE:     The vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-5300-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.
Corrective Action (a)   Alert Range [ISTB 6200(a)]. 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 paragraph ISTB 3400 shall be doubled until the cause of the deviation is determined and the condition corrected.
(b)   Action Range [ISTB 6200(b)]. 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 corrected, or an analysis of the pump is performed and new reference values are established in accordance with paragraph ISTB-6200(c). The analysis of the pump's condition with respect to system operability and Technical Specifications shall also be made as follows:
(1)    If the inoperable pump is specifically identified in the technical specifications, then the applicable technical specification required action statements shall be followed.
(2)    If the inoperable pump is in a system covered by a technical specification, an assessment of its condition shall be made to determine if it makes the system inoperable. If the condition of the pump renders the system inoperable, then the applicable system technical specification required action statements shall be followed.
(3)    Nothing in the ASME OM Code shall be construed to supersede the requirements of any technical specification.
(c)   New Reference Values [ISTB 6200(c)]. In cases where the pump's test parameters are within either the alert or required action ranges of Table ISTB-51 00-1, Table ISTB-5200-1, Table ISTB-5300-1 or Table ISTB-5300-2, as applicable, and the pump's continued use at the changed values is supported by an analysis, a new set of reference values may be established. The analysis shall include verification of the pump's operational readiness. The analysis shall include both a pump level and a system level evaluation of operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of this analysis shall be documented in the record of tests.
When a test shows measured parameter values that fall outside of the acceptable range of Table ISTB-5100-1, Table ISTB-5200-1, Table ISTB-5300-1 or Table ISTB-5300-2, as applicable, that have resulted from an identified systematic error, such as improper system lineup or inaccurate instrumentation, the test shall be rerun after correcting the error.

Beaver Valley Power Station                            Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 14 of 320 If the reference value of a particular parameter being measured or determined can be significantly influenced by other related conditions, then these conditions shall be analyzed and documented in the record of tests.
Reference Pump Curves Utilization of a pump curve in the BVPS-1 IST Program for performing testing and establishing acceptance criteria is considered acceptable since the guidelines provided by NUREG-1482, Rev. 1, Section 5.2 relating to the use of a pump curve shall be followed:
(a)    A pump curve shall be developed, or manufacturer's pump curve validated, when the pump is known to be operating acceptably.
(b)    The reference points used to develop or validate a pump curve shall be measured using instruments at least as accurate (accuracy and range) as required by ISTB-3510. The instrument accuracy requirements specified in Table ISTB-3500-1 for Comprehensive and Preservice tests shall apply when developing a pump curve.
(c)    A pump curve shall be based on an adequate number of reference points, with a minimum of five (5).
(d)    Sufficient reference points shall be beyond the "flat" portion (low flow rates) of the pump curve in a range which includes or is as close as practical to the design basis flow rate.
(e)    Acceptance criteria based on a pump curve shall not conflict with technical specifications or UFSAR operability criteria (minimum operating point/curve) for flow rate and differential pressure, for the affected pump.
(f)     If vibration levels vary significantly over the range of pump conditions, a method of assigning appropriate vibration acceptance criteria should be developed for regions of the pump curve.
(g)     When the reference pump curve may have been affected by repair, replacement, or routine servicing, a new reference pump curve shall be determined or the previous pump curve revalidated by an inservice test.
Records and Reports Records of the results of inservice tests and corrective actions as required by ISTB-9000 are maintained in computerized or in tabular form. Pump performance characteristics will be examined for trends.
Pump Definitions OperationalReadiness - The ability of a component to perform its intended function when required.
Plant Operation - The conditions of startup, operation at power, hot standby, and reactor cool down, as defined by the plant Technical Specifications.
Reference Point - A point of operation at which reference values are established and inservice test parameters are measured for comparison with applicable acceptance criteria.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 15 of 320 Reference Values - One or more values of test parameters measured or determined when the equipment is known to be operating acceptably.
Safe Shutdown - The operating Mode a plant must achieve subsequent to a design basis accident as reflected in the plant safety analysis. BVPS-1 is licensed as hot shutdown being safe shutdown.
Trending - A comparison of current data to previous data obtained under similar conditions for the same equipment.
NOTE:    The following three sections of this document are the "Pump Outline Tables", "Pump Relief Requests", and "Pump Minimum Operating Point (MOP) Curves" sections.
Pump Outline Tables The "Pump Outline Tables" are a listing of all the pumps in the IST Program, their testing requirements, and their specific pump relief request reference numbers. The pumps are arranged according to system and pump number. The following abbreviations and designations are used on the Pump Outline Tables and throughout the IST Program for pumps:
N          - Speed P          - Discharge Pressure AP         - Differential Pressure Q          - Flow rate V          - Vibration 1 BVT      - Unit 1 Beaver Valley Test lOST       - Unit 1 Operating Surveillance Test CMP        - Corrective Maintenance Procedure CPT        - Comprehensive Pump Test Q          - Quarterly Test Frequency CSD        - Cold Shutdown Frequency R          - Refueling Test Frequency 2 YR       - Required every 2 years (biennial), but normally done at refueling outages PRR        - Pump Relief Request X          - Meets or exceeds ASME OM Code ISTB requirements NA         - Not Applicable

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 16 of 320 Pump Relief Requests The "Pump Relief Requests" section contains the detailed technical description of particular conditions and equipment installations prohibiting the testing of some of the characteristics of safety-related pumps. An alternate test method and the frequency of revised testing are also included to meet the intent of 10CFR50.55a. The relief request(s) for a specific pump is referenced by the number(s) listed on the pump's testing outline sheet.
Pump Minimum Operating Point (MOP) Curves The "Pump Minimum Operating Point (MOP) Curves" section contains a graphical representation of the minimum allowable pump flow versus head, which is required to meet the applicable safety analysis, for each centrifugal pump in the Unit 1 IST Program.

Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                 Page 17 of 320 SECTION II:      PUMP OUTLINE TABLES

Beaver Valley Power Station                                    Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                          Page 18 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                        Pump Number:           Code Class:       System:
1A Charging Pump                  lCH-P-1A               2                 7-Chemical and Volume Control Function:     To support the RCS during all normal modes of plant           Type:                          Dwg. OM No.:
operation. The functions performed include, but are not       Centrifugal                   7-1 limited to, the following; maintenance of seal water         C injection flow to the RCPs; control of RCS inventory;        Group:                         Dwg. Coord.:
supplying pressurizer auxiliary spray and reducing the radioactivity level in the reactor coolant. The pumps        A                              C-4 also serve as the High Head Safety Injection Pumps for emergency cool cooling during post accident conditions.
Remarks:       Pump is tested quarterly (Group A test) on recirculation flow with the VCT via the normal charging header while at power or via the VCT or RWST when shutdown. Itcan also be tested via the miniflow recirc path with the RWST when shutdown. Comprehensive test is performed during refueling outages at full flow to the RCS (design point is 150 gpm, accident analysis flow per Calc. 8700-DMC-1430 (Rev.1, Add.0) is 510 gpm (required discharge check valve flow)). Also see PRRI.
Parameter             lOST             Req'd                                 Group A Comments (Group A)       (Frequency)
N                 NA                NA        Constant speed induction motor.
AP               7.4 (Q)              X        Calculated using the Pump Discharge Pressure Indicator [Pl-1CH-151](local) and a temporary suction pressure test gauge (local).
Q               7.4 (Q)              X        Summation of flow rates from Flow Indicators [FI-1CH-122A, 124, 127, 130, 160] (Control Room) and [FI-1CH-180] (local).
V               7.4 (Q)              X        Portable monitoring equipment using velocity units.
Parameter            lOST-             Req'd                           Comprehensive Test Comments (CPT)          (Frequency)
N                  NA                NA        Constant speed induction motor.
AP            11.14B (R)              X        Calculated using a temporary suction and discharge pressure test gauge (local).
Q             11.148 (R)              X        Flow rate measured at FI-1SI-943 (local DVM)
V             11.14B (R)              X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 19 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                        Pump Number:            Code Class:      System:
1B Charging Pump                  1CH-P-1B                2                7-Chemical and Volume Control Function:    To support the RCS during all normal modes of plant           Type:                         Dwg. OM No.:
operation. The functions performed include, but are not       Centrifugal                   7-1 limited to, the following; maintenance of seal water         Centrifugal_7-1 injection flow to the RCPs; control of RCS inventory;         Group:                        Dwg. Coord.:
supplying pressurizer auxiliary spray and reducing the radioactivity level inthe reactor coolant. The pumps          A                             D-4 also serve as the High Head Safety Injection Pumps for emergency cool cooling during post accident conditions.
Remarks:      Pump is tested quarterly (Group A test) on recirculation flow with the VCT via the normal charging header while at power or via the VCT or RWST when shutdown. It can also be tested via the miniflow recirc path with the RWST when shutdown. Comprehensive test is performed during refueling outages at full flow to the RCS (design point is 150 gpm, accident analysis flow per CaIc. 8700-DMC-1430 (Rev.1, Add.0) is 510 gpm (required discharge check valve flow)). Also see PRRI.
Parameter           lOST               Req'd                             Group S Test Comments (Group A)      (Frequency)
N                 NA                NA       Constant speed induction motor.
AP             7.5 (Q)              X        Calculated using the Pump Discharge Pressure Indicator [PI-1CH-152]
(local) and a temporary suction pressure test gauge (local)..
Q              7.5 (Q)              X        Summation of flow rates from Flow Indicators [FI-1CH-122A, 124, 127, 130, 160] (Control Room) and [FI-1CH-180] (local).
V              7.5 (Q)              X        Portable monitoring equipment using velocity units.
Parameter           lOST-               Req'd                        Comprehensive Test Comments (CPT)        (Frequency)
N                NA                 NA       Constant speed induction motor.
AP            11.14B (R)             X        Calculated using a temporary suction and discharge pressure test gauge (local).
Q            11.14B (R)             X        Flow rate measured at FI-1SI-943 (local DVM).
V            11.14B (R)             X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 20 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:              Code Class:     System:
1C Charging Pump                 1CH-P-1C                  2               7-Chemical and Volume Control Function:     To support the RCS during all normal modes of plant          Type:                         Dwg. OM No.:
operation. The functions performed include, but are not      Centrifugal                   7-1 limited to, the following; maintenance of seal water         Centrifugal_7-1 injection flow to the RCPs; control of RCS inventory;        Group:                        Dwg. Coord.:
supplying pressurizer auxiliary spray and reducing the radioactivity level in the reactor coolant. The pumps        A                             E-4 also serve as the High Head Safety Injection Pumps for emergency cool cooling during post accident conditions.
Remarks:      Pump is tested quarterly (Group A test) on recirculation flow with the VCT via the normal charging header while at power or via the VCT or RWST when shutdown. It can also be tested via the miniflow recirc path with the RWST when shutdown. Comprehensive test is performed during refueling outages at full flow to the RCS (design point is 150 gpm, accident analysis flow per Calc. 8700-DMC-1430 (Rev.1, Add.0) is 510 gpm (required discharge check valve flow)). Also see PRR1.
Parameter            lOST             Req'd                              Group A Test Comments (Group A)       (Frequency)
N                NA               NA       Constant speed induction motor.
AP             7.6 (Q)              X       Calculated using the Pump Discharge Pressure Indicator [PI-1CH-1 53]
(local) and a temporary suction pressure test gauge (local).
Q              7.6 (Q)              X       Summation of flow rates from Flow Indicators [FI-1CH-122A, 124, 127, 130, 160] (Control Room) and [FI-1CH-180] (local).
V             7.6 (Q)              X       Portable monitoring equipment using velocity units.
Parameter           lOST-             Req'd                          Comprehensive Test Comments (CPT)         (Frequency)
N                NA                NA       Constant speed induction motor.
AP            11.14B (R)             X       Calculated using a temporary suction and discharge pressure test gauge (local).
Q            11.14B (R)             X       Flow rate measured at FI-1SI-943 (local DVM)
V            11.14B (R)             X       Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                           Page 21 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:               Code Class:      System:
2A Boric Acid Transfer Pump     1CH-P-2A                   3                7-Chemical and Volume Control Function:      To provide a solution of soluble boric acid for reactor      Type:                          Dwg. OM No.:
coolant makeup. These pumps also provide boric acid          Centrifugal                    7-3 for emergency boration.
Group:                         Dwg. Coord.:
A                              C-3 Remarks:       Pump is tested by recirculating the Boric Acid Tank quarterly (Group A test) using a fixed-resistance minimum flow line and at full flow through a larger recirculation line once every 2 years (Comprehensive test) (design point is 75 gpm, accident analysis flow per CaIc. 8700-DMC-2384 (Rev. 1) is 68.6 gpm (MOP)).
The full-flow (Comprehensive test) may be performed in lieu of the quarterly (Group A) recirculation flow test. Also see PRR1, PRR6 and PRR8.
Parameter            lOST             Req'd                                       Comments (Frequency)
N                 NA              NA        Constant speed induction motor.
AP               7.1 (Q)             X        Calculated using the Pump Discharge Pressure Indicator [PI-lCH-110]
(local) and the calculated suction pressure from the level in the Boric Acid Storage Tank [LI-CH-106 (161)], in accordance with Section 5.5.3 of NUREG-1482, Rev.1 (Control Room).
Q               7.1 (Q)             X        No installed instrumentation to measure flow rate quarterly. Pump tested on a fixed-resistance recirculation line with the flow assumed to be (PRR6)      constant.
V               7.1 (Q)             X        Portable monitoring equipment using velocity units.
Parameter           lOST-             Req'd                           Comprehensive Test Comments (CPT)          (Frequency)
N                 NA              NA        Constant speed induction motor.
AP            7.13 (2YR)            X        Calculated using a temporary discharge pressure test gauge (local) and the calculated suction pressure measured by taking the voltage from the Boric Acid Storage Tank Level Transmitter [LT-CH-106 (161)], (local), in accordance with Section 5.5.3 of NUREG-1482, Rev. 1.
Q             7.13 (2YR)            X        Flow rate measurement using portable ultrasonic flow meter (local) at least once every 2 years.
V            7.13 (2YR)            X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 22 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:              Code Class:      System:
2B Boric Acid Transfer Pump      1CH-P-2B                  3                7-Chemical and Volume Control Function:      The Boric Acid Transfer Pumps provide a solution of          Type:                         Dwg. OM No.:
soluble boric acid for reactor coolant makeup. These pumps also provide boric acid for emergency boration.        Centrifugal                   7-3 Group:                        Dwg. Coord.:
A                             G-3 Remarks:       Pump is tested by recirculating the Boric Acid Tank quarterly (Group A test) using a fixed-resistance minimum flow line and at full flow through a larger recirculation line once every 2 years (Comprehensive test) (design point is 75 gpm, accident analysis flow per Calc. 8700-DMC-2384 (Rev. 1) is 68.6 gpm (MOP)).
The full-flow (Comprehensive test) may be performed in lieu of the quarterly (Group A) recirculation flow test. Also see PRRI, PRR6 and PRR8.
Parameter            lOST             Req'd                               Group A Test Comments (Group A)        (Frequency)
N                NA               NA        Constant speed induction motor.
AP              7.2 (Q)             X        Calculated using the Pump Discharge Pressure Indicator [PI-lCH-105A]
(local) and the calculated suction pressure from the level in the Boric Acid Storage Tank [LI-1CH-108 (163)], in accordance with Section 5.5.3 of NUREG-1482, Rev. 1 (Control Room).
Q              7.2 (Q)             X        No installed instrumentation to measure flow rate quarterly. Pump is tested on a fixed-resistance minimum flow recirculation line with the flow (PRR6)      assumed to be a constant.
V              7.2 (Q)             X        Portable monitoring equipment using velocity units.
Parameter            lOST-             Req'd                           Comprehensive Test Comments (CPT)         (Frequency)
N                 NA               NA        Constant speed induction motor.
AP             7.14 (2YR)            X        Calculated using a temporary discharge pressure test gauge (local) and the calculated suction pressure measured by taking the voltage from the Boric Acid Storage Tank Level Transmitter [LT-1CH-108 (163)], in accordance with Section 5.5.3 of NUREG-1482, Rev.1.
Q             7.14 (2YR)            X        Flow rate measurement using portable ultrasonic flow meter (local) at least once every 2 years.
V             7.14 (2YR)            X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 23 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:               Code Class:     System:
1A Residual Heat Removal        1RH-P-1A                   2               10-Residual Heat Removal Pump Function:     To operate when maintaining the plant in a cold              Type:                        Dwg. OM No.:
shutdown condition. Although not needed for safe shutdown of Unit 1, the removal of decay and sensible        Vertically-mounted           10-1 heat by the Residual Heat Removal System is                  Centrifugal considered a safety related function.                        Group:                       Dwg. Coord.:
A                            E-3 Remarks:      Per PRR7, the pump is tested during cold shutdowns and refueling outages at full flow by recirculating the RCS (design point is 4000 gpm, accident analysis flow per Calc. 8700-DMC-2924 (Rev.0) is 4148.9 gpm (MOP)). The full-flow (Comprehensive test) may be performed in lieu of the quarterly (Group A) recirculation flow test.. During cold shutdowns and extended outages, the Group A test will occur at least every 92 days. The Comprehensive test will be performed in lieu of the Group A test at least once during refueling outages. Also see PRR1 and PRR8.
Parameter            lOST              Req'd                              Group A Test Comments (Group A)       (Frequency)
N                 NA               NA       Constant speed induction motor.
AP            10.1 (CSD)            X        Calculated using temporary test pressure gauges installed on the pump discharge on [1 RH-209] (local) and pump suction on [1 RH-200] (local) or from temporary AP gauge installed between [1 RH-200] and [1 RH-213]
(local).
Q            10.1 (CSD)            X         Measured using flow indicator [Fl-1 RH-605] (Control Room) or calculated from the transmitter voltage measured in the process racks.
V            10.1 (CSD)            X         Portable monitoring equipment using velocity units. (Only motor bearing vibration readings will be obtained because the pump bearings are inthe driver.)
Parameter            lOST-             Req'd                          Comprehensive Test Comments (CPT)         (Frequency)
N                 NA               NA       Constant speed induction motor.
AP              10.1 (R)            X        Calculated using temporary test pressure gauges installed on the pump discharge on [1 RH-209] (local) and pump suction on [1 RH-200] (local) or from temporary AP gauge installed between [1RH-200] and [IRH-213]
(local).
Q              10.1 (R)            X         Measured using flow indicator [Fl-1 RH-605] (Control Room) or calculated from the transmitter voltage measured in the process racks.
V              10.1 (R)            X         Portable monitoring equipment using velocity units. (Only motor bearing vibration readings will be obtained because the pump bearings are in the driver.)

Beaver Valley Power Station                              Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                     Page 24 of 320 BVPS-1I1ST PUMP OUTLINE TABLE Pump Name:                      Pump Number:            Code Class:     System:
1B Residual Heat Removal        1RH-P-1 B               2               10-Residual Heat Removal Pump Function:     The Residual Heat Removal Pumps are required to           Type:                         Dwg. OM No.:
operate when maintaining the plant in a cold shutdown     Vertically-mounted condition. Although not needed for safe shutdown of       Cerifal10-1 Unit 1, the removal of decay and sensible heat by the     Centrifugal Residual Heat Removal System is considered a safety       Group:                        Dwg. Coord.:
related function.
A                             F-3 Remarks:      Per PRR7, the pump is tested during cold shutdowns and refueling outages at full flow by recirculating the RCS (design point is 4000 gpm, accident analysis flow per Calc. 8700-DMC-2924 (Rev.0) is 4189.3 gpm (MOP)). During cold shutdowns and extended outages, the Group A test will occur at least every 92 days.
The Comprehensive test will be performed in lieu of the Group A test at least once during refueling outages.
Also see PRR1 and PRR8.
Parameter             lOST           Req'd                             Group A Test Comments (Group A)        (Frequency)
N                 NA             NA       Constant speed induction motor.
AP            10.1 (CSD)           X       Calculated using temporary test pressure gauges installed on the pump discharge on [1RH-210] (local) and pump suction on [1RH-200] (local) or from temporary AP gauge installed between [1RH-200] and [1RH-213]
(local).
Q            10.1 (CSD)           X       Measured using flow indicator [FI-1 RH-605] (Control Room) or calculated from the transmitter voltage measured in the process racks..
V            10.1 (CSD)           X       Portable monitoring equipment using velocity units.
Parameter            lOST-           Req'd                         Comprehensive Test Comments (CPT)         (Frequency)
N                 NA             NA       Constant speed induction motor.
AP              10.1 (R)           X       Calculated using temporary test pressure gauges installed on the pump discharge on [1RH-210] (local) and pump suction on [1RH-200] (local) or from temporary AP gauge installed between [1RH-200] and [1 RH-213]
(local).
Q               10.1 (R)           X       Measured using flow indicator [Fl-1 RH-605] (Control Room) or calculated from the transmitter voltage measured in the process racks.
V               10.1 (R)           X       Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 25 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:               Code Class:       System:
1A Low Head Safety               1SI-P-1A                   2                 11-Safety Injection Injection Pump Function:      To operate primarily during a large break LOCA, in             Type:                      Dwg. OM No.:
addition to other DBA, in order to provide low head           Vertical line shaft          11-1 safety injection and recirculation flow to the RCS, and for long term shutdown cooling during post-LOCA                Group:                     Dwg. Coord.:
conditions. The pump is not utilized during any plant operating evolution and remains in standby during all          B                          F-2 operating Modes.
Remarks:       Pump is tested quarterly (Group B test) on recirculation flow with the RWST. Comprehensive test is performed during refueling outages at full flow to the RCS (design point is 3000 gpm, accident analysis flow per CaIc. 8700-DMC-1430 (Rev.1) is 3335 gpm (required discharge check valve flow)). Also see PRR1.
Parameter             lOST            Req'd                                 Group B Test Comments (Group B)        (Frequency)
N                NA               NA         Constant speed induction motor.
AP             11.1 (Q)            X          Calculated using the Pump Discharge Pressure Indicator [P1-1SI-943]
(local) and the calculated suction pressure using RWST level indicators
[LI-QS-10OA-D], in accordance with Section 5.5.3 of NUREG-1482, Rev.1 (Control Room).
Q             11.1 (Q)            X          Flow indicator [FI-1 SI-941] (local).
V                NA               NA         Not required during the quarterly Group B test.
Parameter            lOST-            Req'd                             Comprehensive Test Comments (CPT)          (Frequency)
N                 NA               NA         Constant speed induction motor.
AP            11.14A (R)            X          Calculated using the Pump Discharge Pressure Indicator [PI-1SI-943]
(local) and the calculated suction pressure measured by taking the voltage from the RWST Level Transmitter [LT-QS-100A, B, C or D], in accordance with Section 5.5.3 of NUREG-1482, Rev.1 (Control Room).
Q            11.14A (R)             X         Flow Indicator [F1-1SI-945] (Control Room).
V            11.14A (R)            X          Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                   Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                            Page 26 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:               Code Class:      System:
1B Low Head Safety               1SI-P-1 B                  2                 11-Safety Injection Injection Pump Function:      To operate primarily during a large break LOCA, in            Type:                          Dwg. OM No.:
addition to other DBA, in order to provide low head safety injection and recirculation flow to the RCS, and       Vertical line shaft            11-1 for long term shutdown cooling during post-LOCA               Group:                         Dwg. Coord.:
conditions. The pump is not utilized during any plant operating evolution and remains in standby during all          B                             F-4 operating Modes.
Remarks:       Pump is tested quarterly (Group B test) on recirculation flow with the RWST. Comprehensive test is performed during refueling outages at full flow to the RCS (design point is 3000 gpm, accident analysis flow per Calc. 8700-DMC-1430 (Rev.1) is 3335 gpm (required discharge check valve flow)). Also see PRR1.
Parameter             lOST           Req'd                                 Group B Test Comments (Group B)        (Frequency)
N                 NA              NA         Constant speed induction motor.
AP              11.2 (Q)            X         Calculated using the Pump Discharge Pressure Indicator [PI-1SI-944]
(local) and the calculated suction pressure using RWST level indicators
[LI-1QS-100A-D], in accordance with Section 5.5.3 of NUREG-1482 (Control Room).
Q              11.2 (Q)            X         Flow indicator [F-I1SI-941] (local). (Mini flow and test line flow indicator).
V                 NA              NA         Not required during the quarterly Group B test.
Parameter            lOST-           Req'd                             Comprehensive Test Comments (CPT)          (Frequency)
N                 NA              NA         Constant speed induction motor.
AP            11.14A (R)            X         Calculated using the Pump Discharge Pressure Indicator [PI-1SI-944]
(local) and the calculated suction pressure measured by taking the voltage from the RWST Level Transmitter [LT-QS-100A, B, C or D], in accordance with Section 5.5.3 of NUREG-1482, Rev. 1 (Control Room).
Q            11.14A (R)            X         Flow Indicator [FI-1SI-946] (Control Room).
V            11.14A (R)            X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                             Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                       Page 27 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                     Pump Number:             Code Class:     System:
1A Quench Spray Pump           1QS-P-1A                2                13-Containment Depressurization Function:    To operate only during a loss-of-coolant accident          Type:                           Dwg. OM No.:
(LOCA) for containment heat removal and pressure suppression. The Quench Spray System also serves           Centrifugal                     13-1 in removing fission products released into the             Group:                          Dwg. Coord.:
containment atmosphere during a LOCA by the admission of sodium hydroxide to the spray stream.         B                              C-5 The pump is not utilized during any plant operating evolution and remains in standby during all operating modes.
Remarks:     Per PRR12, pump is tested quarterly (Group B test) and once every 2 years (Comprehensive test) by recirculating the RWST on recirculation flow at approximately 30% of design flow (design point is 2500 gpm). As discussed in PRR12, the recirculation line is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. Also see PRR1.
Parameter            lOST           Req'd                             Group B Test Comments (Group B)       (Frequency)
N                  NA             NA      Constant speed induction motor.
AP             13.1 (Q)           X       Calculated using the Pump Discharge Pressure Indicator [PI-1QS-101A]
(local) and a temporary suction pressure test gauge (local).
Q              13.1 (Q)            X      Total flow rates from recirculation line Flow Indicators [FI-1QS-103] and (PRR12)    [FI-1 QS-1 04] (local).
V                  NA             NA       Not required during the quarterly Group B test.
Parameter           lOST-            Req'd                          Comprehensive Test Comments (CPT)        (Frequency)
N                 NA             NA       Constant speed induction motor.
AP            13.1 (2YR)           X       Calculated using a temporary suction and discharge pressure test gauge (local).
Q            13.1 (2YR)           X       Total flow rates from recirculation line Flow Indicators [FI-1QS-103] and (PRR12)     [FI-1QS-104] (local).
V            13.1 (2YR)           X        Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                              Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 28 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:            Code Class:      System:
1B Quench Spray Pump            1QS-P-1B                2                13-Containment Depressurization Function:    To operate only during a loss-of-coolant accident           Type:                          Dwg. OM No.:
(LOCA) for containment heat removal and pressure suppression. The Quench Spray System also serves            Centrifugal                     13-1 in removing fission products released into the             Group:                         Dwg. Coord.:
containment atmosphere during a LOCA by the admission of sodium hydroxide to the spray stream.          B                              D-5 The pump is not utilized during any plant operating evolution and remains in standby during all operating modes Remarks:      Per PRR12, pump is tested quarterly (Group B test) and once every 2 years (Comprehensive test) by recirculating the RWST on recirculation flow at approximately 30% of design flow (design point is 2500 gpm). As discussed in PRR12, the recirculation line is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. Also see PRR1.
Parameter            lOST            Req'd                              Group B Test Comments (Group B)       (Frequency)
N               NA               NA       Constant speed induction motor.
AP            13.2 (Q)            X        Calculated using the Pump Discharge Pressure Indicator [PI-1QS-101 B]
(local) and a temporary suction pressure test gauge (local).
Q            13.2 (Q)            X        Total flow rates from recirculation line Flow Indicator [FI-1QS-103] and (PRRI2)     [FI-1 QS-1 04] (local).
V               NA               NA        Not required during the quarterly Group B test.
Parameter           lOST-            Req'd                           Comprehensive Test Comments (CPT)         (Frequency)
N               NA               NA       Constant speed induction motor.
AP            13.2 (2YR)           X        Calculated using a temporary suction and discharge pressure test gauge (local).
Q            13.2 (2YR)           X        Total flow rates from recirculation line Flow Indicator [Fl-IQS-103] and (PRR12)     [FI-1QS-104] (local).
V            13.2 (2YR)           X        Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                                Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                           Page 29 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:             Code Class:      System:
4A Chemical Injection Pump      1QS-P-4A                  2                13-Containment Depressurization Function:     To operate only during a loss-of-coolant accident            Type:                          Dwg. OM No.:
(LOCA) to provide sodium hydroxide to the Quench Spray System in order to provide iodine removal from         Positive Displacement          13-1 the containment atmosphere and to maintain                   Group:                         Dwg. Coord.:
containment sump pH levels. The pump is not utilized during any plant operating evolution and remains in          B                              G-3 standby during all operating modes.
Remarks:      Pump is tested quarterly (Group B test) at full flow by recirculating the Chemical Addition Tank. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 32 gpm). Also see PRR1 and PRR8.
Parameter       lOST (Frequency)         Req'd                             Group B Test Comments (Group B)
N                   NA                NA       Constant speed induction motor.
P                   NA                NA       Not required during the quarterly Group B test.
Q              13.1OA (Q)              X       Recirculation line Flow Indicator [FI-1QS-108] (local).
V                   NA                NA       Not required during the quarterly Group B test.
Parameter              lOST-             Req'd                          Comprehensive Test Comments (CPT)           (Frequency)
N                   NA                NA       Constant speed induction motor.
P             13.1OA (2YR)             X       Temporary discharge pressure test gauge (local).
Q             13.1OA (2YR)             X       Recirculation line Flow Indicator [FI-1QS-108] (local).
V             13.1OA (2YR)             X       Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                            Page 30 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:            Code Class:        System:
4B Chemical Injection Pump       1QS-P-4B                2                  13-Containment Depressurization Function:     To operate only during a loss-of-coolant accident             Type:                           Dwg. OM No.:
(LOCA) to provide sodium hydroxide to the Quench Spray System in order to provide iodine removal from          Positive Displacement           13-1 the containment atmosphere and to maintain                    Group:                          Dwg. Coord.:
containment sump pH levels. The Chemical Injection Pumps are not utilized during any plant operating            B                               G-5 evolution. The pump remains in standby during all operating modes.
Remarks:       Pump is tested quarterly (Group B test) at full flow by recirculating the Chemical Addition Tank. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 32 gpm). Also see PRR1 and PRR8.
Parameter             lOST              Req'd                              Group B Test Comments (Group B)         (Frequency)
N                  NA                NA        Constant speed induction motor.
P                  NA                NA        Not required during the quarterly Group B test.
Q              13.10B (Q)             X        Recirculation line Flow Indicator [FI-1 QS-1 08] (local).
V                  NA                NA        Not required during the quarterly Group B test.
Parameter            lOST-              Req'd                          Comprehensive Test Comments (CPT)           (Frequency)
N                  NA                NA        Constant speed induction motor.
P            13.10B (2YR)             X        Temporary discharge pressure test gauge (local).
Q            13.108 (2YR)             X        Recirculation line Flow Indicator [FI-1QS-108] (local).
V            13.10B (2YR)             X        Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                           Page 31 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:            Code Class:       System:
4C Chemical Injection Pump        1QS-P-4C               2                 13-Containment Depressurization Function:     To operate only during a loss-of-coolant accident            Type:                           Dwg. OM No.:
(LOCA) to provide sodium hydroxide to the Quench Spray System in order to provide iodine removal from         Positive Displacement           13-1 the containment atmosphere and to maintain                   Group:                          Dwg. Coord.:
containment sump pH levels. The Chemical Injection Pumps are not utilized during any plant operating            B                               G-3 evolution. The pump remains instandby during all operating modes.
Remarks:      Pump is tested quarterly (Group B test) at full flow by recirculating the Chemical Addition Tank. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 32 gpm). Also see PRR1 and PRR8.
Parameter      lOST (Frequency)           Req'd                            Group B Test Comments (Group B)
N                   NA                 NA        Constant speed induction motor.
P                   NA                 NA        Not required during the quarterly Group B test.
Q               13.1OA (Q)              X        Recirculation line Flow Indicator [FI-1 QS-1 08] (local).
V                   NA                 NA        Not required during the quarterly Group B test.
Parameter              lOST-              Req'd                          Comprehensive Test Comments (CPT)           (Frequency)
N                   NA                 NA        Constant speed induction motor.
P             13.1OA (2YR)              X        Temporary discharge pressure test gauge (local).
Q             13.1OA (2YR)              X        Recirculation line Flow Indicator [FI-1 QS-108] (local).
V             13.1OA (2YR)             X         Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                               Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                           Page 32 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:            Code Class:        System:
4D Chemical Injection Pump       1QS-P-4D                2                  13-Containment Depressurization Function:     To operate only during a loss-of-coolant accident             Type:                          Dwg. OM No.:
(LOCA) to provide sodium hydroxide to the Quench Spray System in order to provide iodine removal from the containment atmosphere and to maintain                    Group:                         Dwg. Coord.:
containment sump pH levels. The Chemical Injection Pumps are not utilized during any plant operating             B                              G-5 evolution. The pump remains in standby during all operating modes.
Remarks:      Pump is tested quarterly (Group B test) at full flow by recirculating the Chemical Addition Tank. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 32 gpm). Also see PRR1 and PRR8.
Parameter             lOST              Req'd                               Group B Test Comments (Group B)         (Frequency)
N                  NA                 NA        Constant speed induction motor.
P                  NA                 NA        Not required during the quarterly Group B test.
Q              13.10B (Q)              X        Recirculation line flow indicator [Fl-lQS-108] (local).
V                  NA                 NA        Not required during the quarterly Group B test.
Parameter             lOST-              Req'd                          Comprehensive Test Comments (CPT)           (Frequency)
N                  NA                 NA        Constant speed induction motor.
P            13.10B (2YR)              X        Temporary discharge pressure test gauge (local).
Q            13.1OB (2YR)              X        Recirculation line Flow Indicator [FI-1QS-1 08] (local).
V            13.10B (2YR)              X        Portable monitoring equipment using velocity units during the Comprehensive test.

Beaver Valley Power Station                                 Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                          Page 33 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:              Code Class:      System:
1A Inside Recirc. Spray          1RS-P-1A                  2                 13-Containment Depressurization Pump Function:      To operate only during a loss-of-coolant accident            Type:                          Dwg. OM No.:
(LOCA) for long term containment heat removal and            Vertical line shaft            13-2 pressure suppression after sufficient inventory has collected in the containment sump to support pump            Group:                         Dwg. Coord.:
operation. The pump is not utilized during any plant operating evolution and remains in standby during all         B                             E-2 operating modes.
Remarks:       Per ISTB-3430, "Pumps Lacking Required Fluid Inventory", pumps in dry sumps need not be tested every 3 months, however, they shall be tested at least once every 2 years with the required fluid inventory provided during this test. Per PRR1 1, this pump is tested by filling a temporary dike built around the containment sump area and recirculating water through a 4" test loop on recirculation flow during refueling outages only at approximately 41% of design flow and 38% of accident analysis flow (design point is 3500 gpm, accident analysis flow per CaIc. 8700-US(B)-263 (Rev.2) is 3320 gpm).. As discussed in PRR1 1, the 4" recirculation test loop is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. In all cases, the Comprehensive test will be performed in lieu of the Group B test at refueling. Also see PRR1.
Parameter           lOST-            Req'd                                 Group B Test Comments (Group B)       (Frequency)
N               NA              NA        Constant speed induction motor.
AP               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
Q                NA              NA        Comprehensive test will be performed in lieu of the Group B test.
V                NA              NA        Not required during the quarterly Group B test.
Parameter           lOST-            Req'd                             Comprehensive Test Comments (CPT)         (Frequency)
N                NA              NA        Constant speed induction motor.
AP           1BVT 1.13.5           X        Calculated using a temporary discharge pressure test gauge (local) and the calculated suction pressure using the level inthe dike as measured by (R)                       a ruler (local), in accordance with Section 5.5.3 of NUREG-1482, Rev.1.
Q           1BVT 1.13.5           X        Recirculation test line flow is calculated by measuring differential pressure (R)          (PRR1 1)     across local flow orifice using test gauges.
V           1BVT 1.13.5           X        Portable monitoring equipment using velocity units.
(R)

Beaver Valley Power Station                                 Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                          Page 34 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:              Code Class:      System:
1B Inside Recirc. Spray          1RS-P-1B                  2                13-Containment Depressurization Pump Function:      To operate only during a loss-of-coolant accident            Type:                         Dwg. OM No.:
(LOCA) for long term containment heat removal and            Vertical line shaft           13-2 pressure suppression after sufficient inventory has          Verticallineshaft_13-2 collected in the containment sump to support pump            Group:                        Dwg. Coord.:
operation. The pump is not utilized during any plant operating evolution and remains in standby during all        B                             E-4 operating modes.
Remarks:        Per ISTB-3430, "Pumps Lacking Required Fluid Inventory", pumps in dry sumps need not be tested every 3 months, however, they shall be tested at least once every 2 years with the required fluid inventory provided during this test. Per PRR1 1, this pump is tested by filling a temporary dike built around the containment sump area and recirculating water through a 4" test loop on recirculation flow during refueling outages only at approximately 41% of design flow and 39% of accident analysis flow (design point is 3500 gpm, accident analysis flow per Calc. 8700-US(B)-263 (Rev.2) is 3370 gpm).. As discussed in PRR1 1, the 4" recirculation test loop is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. In all cases, the Comprehensive test will be performed in lieu of the Group B test at refueling. Also see PRR1.
Parameter          lOST-            Req'd                                 Group B Test Comments (Group B)       (Frequency)
N               NA              NA        Constant speed induction motor.
AP               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
Q               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
V               NA              NA        Not required during the quarterly Group B test.
Parameter           lOST-            Req'd                             Comprehensive Test Comments (CPT)         (Frequency)
N               NA              NA        Constant speed induction motor.
AP           1BVT 1.13.5          X        Calculated using a temporary discharge pressure test gauge (local) and the calculated suction pressure using the level in the dike as measured by (R)                       a ruler (local), in accordance with Section 5.5.3 of NUREG-1482, Rev 1.
Q            1BVT 1.13.5          X        Recirculation test line flow is calculated by measuring differential pressure (R)          (PRRI 1)     across local flow orifice using test gauges.
V           1BVT 1.13.5          X        Portable monitoring equipment using velocity units.
(R)

Beaver Valley Power Station                                 Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 35 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:              Code Class:      System:
2A Outside Recirc. Spray        1RS-P-2A                  2                 13-Containment Depressurization Pump Function:     To operate only during a loss-of-coolant accident            Type:                         Dwg. OM No.:
(LOCA) for long term containment heat removal and            Vertical line shaft           13-2 pressure suppression after sufficient inventory has          _erticallineshaft    _        13-2 collected in the containment sump to support pump            Group:                        Dwg. Coord.:
operation. The pumps also have the capability of providing sump inventory to the suction supply of the         B                            E-7 High Head Safety Injection Pumps. The pump is not utilized during any plant operating evolution and remains in standby during all operating modes.
Remarks:      Per ISTB-3430, "Pumps Lacking Required Fluid Inventory", pumps in dry sumps need not be tested every 3 months, however, they shall be tested at least once every 2 years with the required fluid inventory provided during this test. Per PRR1 1 this pump is tested by filling the pump casing and recirculating water through a test loop on recirculation flow during refueling outages only at approximately 41% of design flow and 40% of accident analysis flow (design point is 3500 gpm, accident analysis flow per Calc. 8700-US(B)-263 (Rev.2) is 3385 gpm).. As discussed in PRR1 1, the 4" recirculation test loop is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. In all cases, the Comprehensive test will be performed inlieu of the Group B test at refueling. Also see PRR1.
Parameter          lOST-           Req'd                                Group B Test Comments (Group B)      (Frequency)
N               NA              NA        Constant speed induction motor.
AP               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
Q               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
V               NA              NA        Not required during the quarterly Group B test.
Parameter          lOST-           Req'd                             Comprehensive Test Comments (CPT)        (Frequency)
N                NA              NA        Constant speed induction motor.
Ap            13.7A (R)           X         Calculated using a temporary suction and discharge pressure test gauge (local).
Q            13.7A (R)           X         Flow Indicator [FI-1 RS-157A] (local).
(PRR11)
V            13.7A (R)           X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                 Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 36 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:              Code Class:      System:
28 Outside Recirc. Spray        1RS-P-2B                  2                13-Containment Depressurization Pump Function:     To operate only during a loss-of-coolant accident            Type:                         Dwg. OM No.:
(LOCA) for long term containment heat removal and            Vertical line shaft           13-2 pressure suppression after sufficient inventory has collected in the containment sump to support pump            Group:                        Dwg. Coord.:
operation. The pumps also have the capability of providing sump inventory to the suction supply of the        B                             E-9 High Head Safety Injection Pumps. The pump is not utilized during any plant operating evolution and remains in standby during all operating modes.
Remarks:      Per ISTB-3430, "Pumps Lacking Required Fluid Inventory", pumps indry sumps need not be tested every 3 months, however, they shall be tested at least once every 2 years with the required fluid inventory provided during this test. Per PRR1 1 this pump is tested by filling the pump casing and recirculating water through a test loop on recirculation flow during refueling outages only at approximately 41% of design flow and 39% of accident analysis flow (design point is 3500 gpm, accident analysis flow per Calc. 8700-US(B)-263 (Rev.2) is 3340 gpm).. As discussed in PRR1 1, the 4" recirculation test loop is unable to accommodate 20% of design flow as required for Comprehensive Pump testing. In all cases, the Comprehensive test will be performed in lieu of the Group B test at refueling. Also see PRR1.
Parameter           lOST-           Req'd                                Group B Test Comments (Group B)     (Frequency)
N               NA              NA        Constant speed induction motor.
AP               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
Q               NA              NA        Comprehensive test will be performed in lieu of the Group B test.
V               NA              NA        Not required during the quarterly Group B test.
Parameter           lOST-           Req'd                             Comprehensive Test Comments (CPT)       (Frequency)
N               NA              NA        Constant speed induction motor.
AP           13.7B (R)            X        Calculated using a temporary suction and discharge pressure test gauge (local).
Q            13.7B (R)            X        Flow Indicator [FI-1 RS-157B] (local).
(PRR11)
V            13.78 (R)           X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                       Page 37 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                    Pump Number:                Code Class:    System:
1A Component Cooling          1CC-P-1A                    3              15-Reactor Plant Component Cooling Water Water Pump Function:    To operate continuously during normal plant operation       Type:                          Dwg. OM No.:
to supply cooling water to non-essential heat loads as well as cooling water to the RCP motor bearings and         Centrifugal                    15-1 thermal barrier. Its safety related function consists of    Group:                         Dwg. Coord.:
providing cooling water for Residual Heat Removal System support.                                             A                              E-6 Remarks:     Pump is tested quarterly (Group A test) through various CCR heat exchangers using a pump curve per PRR3. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 4700 gpm, accident analysis flow per Calc. 8700-DMC-3052 (Rev.0) is 5006 gpm (MOP)). Also see PRR1 and PRR2.
Parameter           lOST            Req'd                               Group A Test Comments (Group A)      (Frequency)
N               NA               NA         Constant speed induction motor.
AP            15.1 (Q)             X         Calculated using Discharge Pressure Indicator [PI-1 CC-1 00A] and Pump Suction Pressure Indicator [P1-1 CC-181] (local). See PRR2 for range (PRR2)        and accuracy of Pump Discharge Pressure Indicator [PI-i CC-1 O0A].
Q            15.1 (Q)             X         Summation from Flow Indicators [PDI-1CC-117], [PDI-1CC-118] and
[PDI-1CC-119], local gages or control room indicators, [FI-1CC-117],
(PRR2)        [FI-1CC-118] and [FI-1CC-119]. See PRR2 for range and accuracy of pump Flow Indicators [FI-1CC-117], [FI-1CC-118], [FI-1CC-119] and
[PDI-1 CC-1 19].
V           15.1 (Q)             X          Portable monitoring equipment using velocity units.
Parameter           lOST-            Req'd                           Comprehensive Test Comments (CPT)        (Frequency)
N               NA               NA         Constant speed induction motor.
AP          15.1 (2YR)             X         Calculated using a temporary suction and discharge pressure test gauge (PRR2)        (local).
Q           15.1 (2YR)             X         Summation from Flow Indicators [PDI-1 CC-1 17], [PDI-l CC-1 18] and
[PDI-lCC-119], local gages or control room indicators, [FI-1CC-117],
(PRR2)        [FI-1CC-118] and [FI-1CC-119]. See PRR2 for range and accuracy of pump Flow Indicators [Fi-iCC-117], [FI-iCC-118], [FI-1CC-119] and
[PDI-I CC-1 19].
V          15.1 (2YR)             X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 38 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                    Pump Number:                Code Class:      System:
1B Component Cooling          1CC-P-1 B                   3                15-Reactor Plant Component Cooling Water Water Pump Function:    To operate continuously during normal plant operation         Type:                         Dwg. OM No.:
to supply cooling water to non-essential heat loads as well as cooling water to the RCP motor bearings and           Centrifugal                   15-1 thermal barrier. Its safety related function consists of      Group:                        Dwg. Coord.:
providing cooling water for Residual Heat Removal System support.                                               A                             E-7 Remarks:     Pump is tested quarterly (Group A test) through various CCR heat exchangers using a pump curve per PRR3. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 4700 gpm, accident analysis flow per CaIc. 8700-DMC-3052 (Rev.0) is 5006 gpm (MOP)). Also see PRR1 and PRR2.
Parameter          lOST             Req'd                                 Group A Test Comments (Group A)      (Frequency)
N               NA                NA         Constant speed induction motor.
AP            15.2 (Q)              X         Calculated using Discharge Pressure Indicator [PI-l CC-1 00B] and Pump Suction Pressure Indicator [P1-1 CC-1 83] (local). See PRR2 for range (PRR2)        and accuracy of Pump Discharge Pressure Indicator [PI-1 CC-100B].
Q            15.2 (Q)              X         Summation from Flow Indicators [PDI-lCC-117], [PDI-1CC-118] and
[PDI-1CC-1 19], local gages or control room indicators, [FI-1CC-1 17],
(PRR2)        [FI-1CC-118] and [FI-iCC-119]. See PRR2 for range and accuracy of pump Flow Indicators [FI-1CC-117], [FI-1CC-118], [FI-1CC-119] and
[PDI-1 CC-1 19].
V            15.2 (Q)              X         Portable monitoring equipment using velocity units.
Parameter          lOST-             Req'd                             Comprehensive Test Comments (CPT)        (Frequency)
N               NA                NA         Constant speed induction motor.
AP           15.2 (2YR)             X         Calculated using a temporary suction and discharge pressure test gauge (PRR2)        (local).
Q           15.2 (2YR)             X         Summation from Flow Indicators [PDI-1CC-1 17], [PDI-1CC-1 18] and
[PDI-1 CC-1 19], local gages or control room indicators, [FI-1 CC-1 17],
(PRR2)        [FI-1CC-118] and [FI-1CC-119]. See PRR2 for range and accuracy of pump Flow Indicators [FI-1CC-117], [FI-1CC-118], [FI-iCC-119] and
[PDI-1 CC-1 19].
V           15.2 (2YR)             X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                               Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                       Page 39 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                    Pump Number:               Code Class:      System:
1C Component Cooling          1CC-P-lC                   3                15-Reactor Plant Component Cooling Water Water Pump Function:    To operate continuously during normal plant operation        Type:                         Dwg. OM No.:
to supply cooling water to non-essential heat loads as                                     151 well as cooling water to the RCP motor bearings and          Centrifugal thermal barrier. Its safety related function consists of     Group:                        Dwg. Coord.:
providing cooling water for Residual Heat Removal System support.                                              A                             E-8 Remarks:     Pump is tested quarterly (Group A test) through various CCR heat exchangers using a pump curve per PRR3. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 4700 gpm, accident analysis flow per Calc. 8700-DMC-3052 (Rev.0) is 5006 gpm (MOP)). Also see PRR1 and PRR2.
Group A Test Comments Constant speed induction motor.
Calculated using Discharge Pressure Indicator [PI-1CC-1OOC] and Pump Suction Pressure Indicator [P1-1CC-185] (local). See PRR2 for range and accuracy of Pump Discharge Pressure Indicator [PI-1 CC-10OC].
Summation from Flow Indicators [PDI-1CC-117], [PDI-lCC-118] and
[PDI-1CC-119], local gages or control room indicators, [FI-lCC-117],
[FI-iCC-118] and [FI-CC-119]. See PRR2 for range and accuracy of pump Flow Indicators [FI-1CC-117], [FI-1CC-118], [FI-1CC-119] and
[PDI-l CC-1 19].
Portable monitoring equipment using velocity units.
Parameter          lOST-               Req'd                          Comprehensive Test Comments (CPT)         (Frequency)
N               NA                 NA        Constant speed induction motor.
Ap           15.3 (2YR)              X         Calculated using a temporary suction and discharge pressure test (PRR2)      gauge (local).
Q           15.3 (2YR)              X         Summation from Flow Indicators [PDI-1CC-117], [PDI-1CC-118] and
[PDI-1CC-1 19], local gages or control room indicators, [FI-1CC-1i17],
(PRR2)       [FI-iCC-118] and [FI-1CC-119]. See PRR2 for range and accuracy of pump Flow Indicators [FI-1CC-117], [FI-1CC-118], [FI-lCC-119] and
[PDI-1 CC-119].
V         15.3 (2YR)                X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                 Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                          Page 40 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:               Code Class:      System:
Steam Driven Auxiliary Feed      1FW-P-2                   3                24-Auxiliary Feedwater Pump Function:     To provide emergency makeup to the Steam                      Type:                          Dwg. OM No.:
Generators during a loss of normal feed water following a main turbine trip with a total loss of all        Centrifugal                    24-2 electrical power (Station Blackout). The pump is not          Group:                         Dwg. Coord.:
utilized during any plant operating evolution and remains instandby during all operating modes.                  B                             F-7 Remarks:      Per PRR1 0, pump is tested quarterly (Group B test), on a staggered test basis with the other AFW pumps, on recirculation flow by recirculating the PPDWST and at full flow (Comprehensive test) from the PPDWST to the Steam Generators when in Mode 3 during shutdown for refueling or during startup from refueling outages (design point is 700 gpm, accident analysis flow per CaIc. 8700-DMC-1429 (Rev.0, Add.4) is 464 gpm (MOP), however, required discharge check valve flow is 615 gpm per CaIc. 8700-DMC-2402 (Rev.1)).
Also see PRR1 and PRR2.
Parameter             lOST            Req'd                                Group B Test Comments (Group B)        (Frequency)
N               24.4 (Q)            X         No installed rpm indication. Use portable monitoring equipment-Stroboscope, with speed recorded to within +/-1% of the reference point per ISTB-5122(a)..
AP               24.4 (Q)            X         Calculated using Discharge Pressure Indicator [PI-1 FW-1 55] and Pump Suction Pressure Indicator [PI-1 FW-1 56] (local). See PRR2 for range (PRR2)       and accuracy of Pump Suction Pressure Indicator [PI-1 FW-1 56].
Q               24.4 (Q)            X         Flow instrumentation which meets ASME OM Code requirements does not exist. Flow measurement will be performed during refueling outages (PRR10)       per PRR10.
V                  NA              NA         Not required during the quarterly Group B test.
Parameter             lOST-            Req'd                           Comprehensive Test Comments (CPT)          (Frequency)
N               24.9 (R)            X         No installed rpm indication. Use portable monitoring equipment-Stroboscope, with speed recorded to within +/-1% of the reference point per ISTB-5123(a)..
AP               24.9 (R)            X         Calculated using Discharge Pressure Indicator [PI-1 FW-155] and a (PRR2)       temporary suction pressure test gauge (local).
Q               24.9 (R)            X         Summation of flow to Steam Generators through Flow Indicators
[FI-1 FW-1 O0A, B and C] (Control Room) and L.O. cooler line flow using a portable ultrasonic flow meter (local) at refueling.
V               24.9 (R)            X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                   Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                            Page 41 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:               Code Class:      System:
3A Motor Driven Auxiliary        1FW-P-3A                   3                24-Auxiliary Feedwater Feed Pump Function:      To provide an emergency source of feedwater supply            Type:                           Dwg. OM No.:
to the steam generators during a loss of normal feedwater, loss of offsite power, secondary side pipe         Centrifugal                     24-2 ruptures, or cool down following a steam generator            Group:                          Dwg. Coord.:
tube rupture. The pump is not normally utilized during any plant operating evolution and normally remains in          B                              F-2 standby during all operating Modes.
Remarks:       Per PRR9, pump is tested quarterly (Group B test), on a staggered test basis with the other AFW pumps, on recirculation flow by recirculating the PPDWST and at full flow (Comprehensive test) from the PPDWST to the Steam Generators during refueling outages (design point is 350 gpm, accident analysis flow per Calc.
8700-DMC-2402 (Rev.2, Add.2) is 315 gpm (required discharge check valve flow)). Also see PRR1, PRR2 and PRR8.
Parameter              lOST             Req'd                               Group B Test Comments (Group B)         (Frequency)
N                   NA               NA         Constant speed induction motor.
AP               24.2 (Q)             X         Calculated using Discharge Pressure Indicator [PI-1 FW-1 55A] and Pump Suction Pressure Indicator [PI-1 FW-1 56A] (local). See PRR2 for range (PRR2)       and accuracy of Pump Suction Pressure Indicator [PI-1 FW-156A].
Q                24.2 (Q)             X         Flow instrumentation which meets ASME OM Code requirements does not exist. Flow measurement will be performed during refueling outages (PRR9)       per PRR9.
V                   NA               NA         Not required during the quarterly Group B test.
Parameter              lOST-             Req'd                          Comprehensive Test Comments (CPT)           (Frequency)
N                   NA               NA        Constant speed induction motor.
AP              24.8A (R)             X        Calculated using Discharge Pressure Indicator [PI-1 FW-155A] and a (PRR2)      temporary suction pressure test gauge (local).
Q               24.8A (R)             X        Summation of flow to Steam Generators through Flow Indicators (PRR2)      [FI-1 FW-100A, B and C] (Control Room) and L.O. cooler line flow using a portable ultrasonic flow meter (local) during refueling. See PRR2 for range and accuracy of pump Flow Indicators [FI-1 FW-1 O0A, B and C],
V               24.8A (R)             X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                            Page 42 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                       Pump Number:              Code Class:       System:
3B Motor Driven Auxiliary        1FW-P-3B                  3                 24-Auxiliary Feedwater Feed Pump Function:      To provide an emergency source of feedwater supply           Type:                           Dwg. OM No.:
to the steam generators during a loss of normal feedwater, loss of offsite power, secondary side pipe         Centrifugal                    24-2 ruptures, or cool down following a steam generator            Group:                         Dwg. Coord.:
tube rupture. The pump is not normally utilized during any plant operating evolution and normally remains in         B                              F-5 standby during all operating Modes.
Remarks:       Per PRR9, pump is tested quarterly (Group B test), on a staggered test basis with the other AFW pumps, on recirculation flow by recirculating the PPDWST and at full flow (Comprehensive test) from the PPDWST to the Steam Generators during refueling outages (design point is 350 gpm, accident analysis flow per Calc.
8700-DMC-2402 (Rev.2, Add.2) is 315 gpm (required discharge check valve flow)). Also see PRR1, PRR2 and PRR8.
Parameter               lOST             Req'd                               Group B Test Comments (Group B)         (Frequency)
N                   NA                NA        Constant speed induction motor.
AP               24.3 (Q)             X         Calculated using Discharge Pressure Indicator [PI-1 FW-1 55B] and Pump Suction Pressure Indicator [PI-1 FW- 56B] (local). See PRR2 for (PRR2)       range and accuracy of Pump Suction Pressure Indicator [PI-1FW-156B].
Q                24.3 (Q)             X         Flow instrumentation which meets ASME OM Code requirements does not exist. Flow measurement will be performed during refueling (PRR9)       outages per PRR9.
V                   NA                NA        Not required during the quarterly Group B test.
Parameter              lOST-             Req'd                           Comprehensive Test Comments (CPT)           (Frequency)
N                   NA                NA        Constant speed induction motor.
Ap               24.8B (R)             X         Calculated using Discharge Pressure Indicator [PI-1 FW-155B] and a (PRR2)       temporary suction pressure test gauge (local).
Q               24.8B (R)             X         Summation of flow to Steam Generators through Flow Indicators (PRR2)       [FI-1FW-100A, B and C] (Control Room) and L.O. cooler line flow using a portable ultrasonic flow meter (local) during refueling. See PRR2 for range and accuracy of pump Flow Indicators [FI-1 FW-1OOA, B and C].
V               24.8B (R)             X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 43 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                        Pump Number:            Code Class:      System:
1A River Water Pump               1WR-P-1A                3                30-River Water Function:     To operate continuously during normal plant operation        Type:                          Dwg. OM No.:
to supply cooling water to non-essential heat loads.
During post accident conditions it provides the heat        Vertical line shaft            30-1 sink to the following components: recirculation spray        Group:                         Dwg. Coord.:
heat exchangers, charging pump lube oil coolers, control room river water cooling coil and Emergency          A                              B-1 Diesel Generator cooling system heat exchanger.
Remarks:       Pump is tested quarterly (Group A test) at full flow through the River Water flush line. This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 9000 gpm, accident analysis flow per Calc. 8700-DMC-3136 (Rev.3) is 9010 gpm (MOP)). Also see PRR1 ,PRR8 and PRR13.
Parameter              lOST             Req'd                              Group A Test Comments (Group A)        (Frequency)
N                  NA               NA      Constant speed induction motor.
AP               30.2 (Q)            X       Calculated using the Pump Discharge Pressure Indicator [PI-1 RW-101A]
and the calculated suction pressure using the Ohio River Level Recorder
[LR-1CW-101] in accordance with Section 5.5.3 of NUREG-1482, Rev.1.
(local).
Q               30.2 (Q)            X        Flow indicator [FI-1RW-102A] (Control Room).
V              30.2 (Q)             X       Portable monitoring equipment using velocity units.
Parameter             lOST-             Req'd                           Comprehensive Test Comments (CPT)          (Frequency)
N                  NA                NA      Constant speed induction motor.
AP             30.2 (2YR)             X       Calculated using the Pump Discharge Pressure Indicator [PI-1RW-101A]
and the calculated suction pressure using the Ohio River Level Recorder (PRR13)     [LR-1CW-101].
Q             30.2 (2YR)             X        Flow indicator [FI-1 RW-1 02A] (Control Room).
V             30.2 (2YR)             X       Portable monitoring equipment using velocity units.

Beaver Valley Power Station                               Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 44 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:             Code Class:      System:
1B River Water Pump              1WR-P-1B                3                30-River Water Function:     To operate continuously during normal plant operation       Type:                         Dwg. OM No.:
to supply cooling water to non-essential heat loads.        Vertical line shaft           30-1 During post accident conditions it provides the heat sink to the following components: recirculation spray       Group:                        Dwg. Coord.:
heat exchangers, charging pump lube oil coolers, control room river water cooling coil and Emergency         A                             C-1 Diesel Generator cooling system heat exchanger.
Remarks:      Pump is tested quarterly (Group A test) at full flow through the River Water flush line. The same configuration is used during the biennial Comprehensive test (design point is 9000 gpm, accident analysis flow per CaIc. 8700-DMC-3136 (Rev.3) is 9010 gpm (MOP)). Also see PRR1, PRR8 and PRR13.
Parameter            lOST            Req'd                               Group A Test Comments (Group A)       (Frequency)
N                NA               NA        Constant speed induction motor.
AP             30.3 (Q)             X        Calculated using the Pump Discharge Pressure Indicator [PI-1 RW-101 B]
and the calculated suction pressure using the Ohio River Level Recorder
[LR-1CW-101], in accordance with Section 5.5.3 of NUREG-1 482, Rev.1. (local).
Q             30.3 (Q)             X        Flow indicator [FI-1 RW-102B] (Control Room).
V             30.3 (Q)             X        Portable monitoring equipment using velocity units.
Parameter            lOST-            Req'd                            Comprehensive Test Comments (CPT)         (Frequency)
N                NA               NA        Constant speed induction motor.
AP            30.3 (2YR)            X         Calculated using the Pump Discharge Pressure Indicator [PI-1 RW-1 0163]
and the calculated suction pressure using the Ohio River Level Recorder (PRR13)      [LR-iCW-101].
Q            30.3 (2YR)            X         Flow indicator [FI-1 RW-1 026] (Control Room).
V            30.3 (2YR)            X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                               Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                        Page 45 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:             Code Class:      System:
1C River Water Pump              1WR-P-1C                3                30-River Water Function:     To operate continuously during normal plant operation       Type:                          Dwg. OM No.:
to supply cooling water to non-essential heat loads.
During post accident conditions it provides the heat        Vertical line shaft            30-1 sink to the following components: recirculation spray       Group:                         Dwg. Coord.:
heat exchangers, charging pump lube oil coolers, control room river water cooling coil and Emergency         A                              D-1 Diesel Generator cooling system heat exchanger.
Remarks:      Pump is tested quarterly (Group A test) at full flow through the River Water flush line. The same configuration is used during the biennial Comprehensive test (design point is 9000 gpm, accident analysis flow per Calc. 8700-DMC-3136 (Rev.3) is 9010 gpm (MOP)). Also see PRR1, PRR8, and PRR13.
Parameter           lOST              Req'd                              Group A Test Comments (Group A)       (Frequency)
N                 NA                NA       Constant speed induction motor.
AIP         30.6A or 6B (Q)          X        Calculated using the Pump Discharge Pressure Indicator [PI-1RW-101C]
and the calculated suction pressure using the Ohio River Level Recorder
[LR-lCW-101], in accordance with Section 5.5.3 of NUREG-1482, Rev.l. (local).
Q          30.6A or 6B (Q)          X        Flow indicator [FI-1 RW-1 02A or B] (Control Room).
V          30.6A or 6B(Q)           X        Portable monitoring equipment using velocity units.
Parameter           10ST-             Req'd                           Comprehensive Test Comments (CPT)         (Frequency)
N                 NA                NA       Constant speed induction motor.
AP            30.6A or 6B            X        Calculated using the Pump Discharge Pressure Indicator [PI-1RW-101C]
(2YR)           (and             the calculated suction pressure using the Ohio River Level Recorder
                                        )(PRR13)     [LR-1CW-101.
Q            30.6A or 6B            X        Flow indicator [FI-1 RW-1 02A or B] (Control Room).
(2YR)
V            30.6A or 6B            X        Portable monitoring equipment using velocity units.
(2YR)

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 46 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:             Code Class:       System:
1A DG #1 Fuel Transfer          1EE-P-1A                 3                 36-Station Service 4KV Pump Function:     To operate only during emergency diesel generator            Type:                          Dwg. OM No.:
operation to replenish day tank inventory. The pump is Positive Displacement               36-2 not used during any plant operating evolution and remains instandby during all operating Modes.                Group:                         Dwg. Coord.:
B                              B-4 Remarks:      Pump is normally tested bi-monthly (Group B test) at full flow from the fuel oil storage tank to the day tank.
This same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 10 gpm, accident analysis flow (minimum required flow per EM 115885) is 3.6 gpm). Also see PRR1, PRR4, PRR5 and PRR8.
Parameter          lOST             Req'd                                 Group B Test Comments (Group B)      (Frequency)
N                NA              NA          Constant speed induction motor.
P                NA              NA          Not required during the Group B test.
Q             36.1 (Q)             X         No instrumentation is provided for flow. Pursuant to NUREG-1482, Rev. 1, Section 5.5.2, a level change over time inthe day tank will be (PRR4)        measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)        Ranges are used per PRR5.
V                NA              NA          Not required during the Group B test.
Parameter          lOST-             Req'd                            Comprehensive Test Comments (CPT)        (Frequency)
N               NA               NA          Constant speed induction motor.
P           36.1 (2YR)             X         Positive displacement pump. Pump discharge pressure shall be determined by the use of a temporary test gauge (local). Expanded (PRR5)        Ranges are used per PRR5.
Q           36.1 (2YR)             X         No instrumentation is provided for flow. Pursuant to NUREG-1482, Rev. 1, Section 5.5.2, a level change over time inthe day tank will be (PRR4)        measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)        Ranges are used per PRR5.
V           36.1 (2YR)             X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                               Unit  I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 47 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:            Code Class:        System:
1B DG #1 Fuel Transfer          1EE-P-1B                3                  36-Station Service 4KV Pump Function:    To operate only during emergency diesel generator             Type:                         Dwg. OM No.:
operation to replenish day tank inventory. The pump is        Positive Displacement         36-2 not used during any plant operating evolution and remains in standby during all operating Modes.                Group:                        Dwg. Coord.:
B                             A-4 Remarks:      Pump is normally tested bi-monthly (Group B test) at full flow from the fuel oil storage tank to the day tank.
The same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 10 gpm, accident analysis flow (minimum required flow per EM 115885) is 3.6 gpm). Also see PRR1, PRR4, PRR5 and PRR8.
Parameter           lOST             Req'd                                Group B Test Comments (Group B)       (Frequency)
N                 NA              NA        Constant speed induction motor.
P                 NA              NA        Not required during the Group B test.
Q              36.1 (Q)            X        No instrumentation is provided for flow. Pursuant to NUREG-1482, (PRR4)      Rev.1, Section   5.5.2, a level change over time in the day tank will be measured    using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)      Ranges are used per PRR5.
V                 NA              NA        Not required during the Group B test.
Parameter          lOST-             Req'd                           Comprehensive Test Comments (CPT)         (Frequency)
N                NA               NA        Constant speed induction motor.
P            36.1 (2YR)            X        Positive displacement pump. Pump discharge pressure shall be determined by the use of a temporary test gauge (local). Expanded (PRR5)      Ranges are used per PRR5.
Q            36.1 (2YR)            X        No instrumentation is provided for flow. Pursuant to NUREG-1482, (PR R4)     Rev.1, Section 5.5.2, a level change over time inthe day tank will be measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)      Ranges are used per PRR5.
V            36.1 (2YR)            X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                                Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 48 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                     Pump Number:              Code Class:      System:
1C DG #2 Fuel Transfer         1EE-P-1C                 3                36-Station Service 4KV Pump Function:     To operate only during emergency diesel generator           Type:                          Dwg. OM No.:
operation to replenish day tank inventory. The pump is      Positive Displacement          36-2 not used during any plant operating evolution and remains in standby during all operating Modes.              Group:                         Dwg. Coord.:
B                             F-4 Remarks:      Pump is normally tested bi-monthly (Group B test) at full flow from the fuel oil storage tank to the day tank.
The same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 10 gpm, accident analysis flow (minimum required flow per EM 115885) is 3.6 gpm). Also see PRR1, PRR4, PRR5 and PRR8.
Parameter          lOST             Req'd                               Group B Test Comments (Group B)      (Frequency)
N                NA              NA        Constant speed induction motor.
P                NA              NA        Not required during the Group B test.
Q             36.2 (Q)            X        No instrumentation is provided for flow. Pursuant to NUREG-1482, Rev. 1, Section 5.5.2, a level change over time in the day tank will be (PRR4)      measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)      Ranges are used per PRR5.
V                NA              NA        Not required during the Group B test.
Parameter          lOST-            Req'd                           Comprehensive Test Comments (CPT)        (Frequency)
N                NA              NA        Constant speed induction motor.
P           36.2 (2YR)            X        Positive displacement pump. Pump discharge pressure shall be determined by the use of a temporary test gauge (local). Expanded (PRR5)      Ranges are used per PRR5.
Q           36.2 (2YR)            X        No instrumentation is provided for flow. Pursuant to NUREG-1482, Rev. 1, Section 5.5.2, a level change over time in the day tank will be (PRR4)      measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)      Ranges are used per PRR5.
V           36.2 (2YR)            X        Portable monitoring equipment using velocity units.

Beaver Valley Power Station                               Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                         Page 49 of 320 BVPS-1 IST PUMP OUTLINE TABLE Pump Name:                      Pump Number:             Code Class:      System:
1D DG #2 Fuel Transfer          1EE-P-1 D                3                36-Station Service 4KV Pump Function:     To operate only during emergency diesel generator           Type:                           Dwg. OM No.:
operation to replenish day tank inventory. The pump is      Positive Displacement          36-2 not used during any plant operating evolution and           PositiveDisplacement            36-2 remains in standby during all operating Modes.              Group:                          Dwg. Coord.:
B                               E-4 Remarks:      Pump is normally tested bi-monthly (Group B test) at full flow from the fuel oil storage tank to the day tank.
The same flow path is utilized during the performance of the Comprehensive test once every 2 years (design point is 10 gpm, accident analysis flow (minimum required flow per EM 115885) is 3.6 gpm). Also see PRR1, PRR4, PRR5 and PRR8.
Parameter          lOST             Req'd                                Group B Test Comments (Group B)      (Frequency)
N                NA              NA         Constant speed induction motor.
P                NA              NA         Not required during the Group B test.
Q             36.2 (Q)            X         No instrumentation is provided for flow. Pursuant to NUREG-1482, (PRR4)       Rev. 1, Section 5.5.2, a level change over time in the day tank will be measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)       Ranges are used per PRR5.
V                NA              NA         Not required during the Group B test.
Parameter          lOST-             Req'd                           Comprehensive Test Comments (CPT)        (Frequency)
N               NA               NA         Constant speed induction motor.
P           36.2 (2YR)            X         Positive displacement pump. Pump discharge pressure shall be determined by the use of a temporary test gauge (local). Expanded (PRR5)       Ranges are used per PRR5.
Q           36.2 (2YR)            X         No instrumentation is provided for flow. Pursuant to NUREG-1482, (PRR4)       Rev. 1, Section 5.5.2, a level change over time in the day tank will be measured using a ruler and converted to flow rate, per PRR4. Expanded (PRR5)       Ranges are used per PRR5.
V           36.2 (2YR)            X         Portable monitoring equipment using velocity units.

Beaver Valley Power Station                  Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                       Page 50 of 320 SECTION III:             PU AP RELIEF REQUESTS

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 51 of 320 PUMP RELIEF REQUEST I 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.
Component(s)               All of the Code Class 2 and 3 pumps in the IST Program.
Affected:
Component/System           Various Function:
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-6200, "Corrective Action", Paragraph ISTB-6200(a), "Alert Range",
Requirement(s):            states, If the measured test parameter values fall within the alert range of Table ISTB-5100-1, Table ISTB-5200-1, ISTB-5300-1, or 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.
Reason for Request:        ASME OM Code paragraph ISTB-6200(c), "New Reference Values",
states, In cases where the pump's test parameters are within either the alert or required action ranges of Table ISTB-51 00-1, Table ISTB-5200-1, ISTB-5300-1, or ISTB-5300-2, as applicable, and the pump's continued use at the changed values is supported by analysis, a new set of reference values may be established. This analysis shall include verification of the pumps operational readiness. The analysis shall include both a pump level and system evaluation of operational readiness, the cause of the change in pump performance, and an evaluation of all trends indicated by available data. The results of the analysis shall be documented in the record of tests.
The reason for testing a pump on a doubled frequency, per ISTB-6200(a),
when test parameters fall in the alert range is to obtain additional information so that the condition of the pump may be determined.
Additional information may already exist to support an analysis demonstrating pump operational readiness and its continued use at the parameters acquired during the test in lieu of placing the pump on a doubled frequency as required by ISTB-6200(a). Additionally, for pumps that can only be tested during shutdowns, compliance to ISTB-6200(a) would require a plant shutdown to facilitate testing at a doubled frequency.
As part of the BVPS-1 Predictive Maintenance Program, spectral analysis may be used to determine the mechanical condition of a pump. Spectral data can provide information to determine if misalignment, unbalance, resonance, looseness or a bearing problem is present. Through a review of the spectral data over a period of time, any change in condition of the pump may also be determined.

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 52 of 320 PUMP RELIEF REQUEST 1 Reason for Request:       Also, a significant amount of historical trended data associated with (Cont.)                   hydraulic parameters exists which could be used to support an analysis demonstrating pump operational readiness and its continued use at the parameters acquired during the test.
Proposed Alternative      In lieu of the double frequency test requirements specified in ISTB-6200(a) and Basis for Use:        an evaluation and analysis shall be performed per the guidelines provided in ISTB-6200(c). BVPS-1 proposes to use the provisions of ISTB-6200(c),
for measured parameters associated with all pumps in the IST Program.
All available data acquired during previous inservice tests, in addition to spectral vibration data will be evaluated each time a pump enters the alert range. If the evaluation, per the guidelines specified in ISTB-6200(c),
supports an analysis which demonstrates pump operational readiness and continued use then the frequency of testing will not be doubled. However, a condition report will be initiated to document the evaluation and analysis and to track the condition of the pump. If the results of the evaluation and analysis are inconclusive or do not demonstrate pump operational readiness then the test frequency shall be doubled until the cause of the deviation is determined and the condition corrected. A condition report will be initiated to document the evaluation and analysis in addition to the cause of the deviation. Testing at a doubled frequency will be scheduled immediately following the "Alert Range" condition of the pump and will not be removed from the schedule until an evaluation and analysis has been performed that provides verification of pump operational readiness or the pump has returned to acceptable operation. When applying this proposed alternative and the requirements of ISTB-6200(c), to avoid stair-stepping to failure, a new set of reference values may only be obtained once prior to performing corrective maintenance. For pumps that can only be tested during shutdowns, testing will be performed at the next available opportunity if the results of the evaluation and analysis are inconclusive or do not demonstrate operational readiness. The plant will not shutdown to facilitate testing at a doubled frequency. This proposed alternative will minimize the potential of testing a pump at a doubled frequency when its operational readiness and continued use are supported by conclusive analyses.
Using the provisions of this relief request as an alternative to the requirements of ISTB-6200(a) will ensure pump operational readiness and provides an acceptable level of quality and safety. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date September 4, 1997, Safety Evaluation of Relief Requests (PRR1) for Third 10-Year Interval for Pumps and Valves Inservice Testing (IST) Program, (TAC No. M98620)

Beaver Valley Power Station                     Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                   Page 53 of 320 PUMP RELIEF REQUEST I

==References:==
Paragraph ISTB-6200, "Corrective Action" Table ISTB-5100-1, "Centrifugal Pump Test Acceptance Criteria" Table ISTB-5200-1, "Vertical Line Shaft and Centrifugal Pumps Test Acceptance Criteria" Table ISTB-5300-1, "Positive Displacement Pump (Except Reciprocating)
Test Acceptance Criteria" Table ISTB-5300-2, "Reciprocating Positive Displacement Pump Test Acceptance Criteria"

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 54 of 320 PUMP RELIEF REQUEST 2 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.
Component(s)                Various Code Class 2 and 3 pumps in the IST Program. See the attached Affected:                   Table for certain Code Class 2 and 3 pumps in the IST Program.
Component/System            Various Function:
Applicable Code             ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code             ISTB-3510(b)(1), "Range", states, The full-scale for each analog Requirement(s):             instrument shall not be greater than three times the reference value.
Reason for Request:         The pumps listed on the attached table use instruments which do not meet the requirements of ISTB-3510(b)(1), however, the accuracy of the instruments used is more conservative than the requirements of ISTB-351 0(a), "Accuracy" and Table ISTB-3500-1 "Required Instrument Accuracy" for Group A and Group B tests and Comprehensive tests. Per the attached table, the combination of higher range and better accuracy for each instrument yields a reading at least equivalent to the reading achieved from instruments that meet ISTB-3510(b)(1) and Table ISTB-3500-1.
Proposed Alternative       NUREG-1482, Rev.1, Section 5.5.1, "Range and Accuracy of Analog and Basis for Use:         Instruments", states; When the range of a permanently installed analog instrument is greater than three times the reference value, but the accuracy of the instrument is more conservative than that required by the Code, the staff may grant relief when the combination of the range and accuracy yields a reading that is as at least equivalent to that achieved using instruments that meet the Code requirements (i.e., up to +/-6 percent for Group A and B tests, and +/-1.5 percent for pressure and differential pressure instruments for Preservice and Comprehensive tests). The instruments identified on the attached Table are instrumentation that satisfies the guidance provided in NUREG-1482, Rev.1, Section 5.5.1.
Additional basis for use and the applicable test type are also provided with the attached Table.
Using the provisions of this relief request as an alternative to the requirements of ISTB-3510(b)(1) provides an acceptable level of quality and safety since their use yields a reading that is as at least equivalent to that achieved using instruments that meet the Code requirements as described in NUREG-1482, Rev.1, Section 5.5.1. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 55 of 320 PUMP RELIEF REQUEST 2 Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date September 4, 1997, Safety Evaluation of Relief Requests (PRR2) for Third 10-Year Interval for Pumps and Valves Inservice Testing (IST) Program, (TAC No. M98620)

==References:==
Paragraph ISTB-3510 "Data Collection - General" NUREG-1482, Rev.1, Section 5.5.1 "Range and Accuracy of Analog Instruments"

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                     Page 56 of 320 PUMP RELIEF REQUEST        2 IST PUMP INSTRUMENTATION Pump ID#
1Instrument ID#         Condition Requiring Relief         Basis for RelieflAlternate Test 1CC-P-1A      PI-1CC-100A    The range of the gauges is   These gauges are the discharge pressure 1CC-P-l B     PI-1CC-100B    slightly greater than three  gauges for the CCR pumps. The range of 1CC-P-1C      PI-1CC-100C    times the reference          the gauges is 0-400 psig. The use of a pressure during quarterly    pump curve is allowed for these pumps testing.                     per PRR3, and the typical pressure readings are slightly lower than 1/3 the range, varying between 108-124 psig.
The calibration accuracy is 1.0%, which would yield a reading more accurate than Code requirements. The use of these pressure instruments is applicable to Group A tests only since the combination of range and accuracy yields a reading of
                                                           +/-3.70 percent which is less than the +/-6 percent required by Code for the Group A test. During Comprehensive testing, temporary pressure instrumentation will be used having a calibrated accuracy of at least +/-0.5 percent of full scale with a sufficient range to satisfy the +/-1.5 percent required by the Code for the Comprehensive test.
FI-1CC-117     The range of the gauges is   These flow indicators are in the branch FI-1CC-118     greater than three times the lines of the component cooling water Fl-1CC-119     reference flow.              system. They are only used if the installed PDls are over-ranged. In that case, the typical flow expected would be enough to meet Code requirements, except for [Fl-1CC-117], which could be placed in service with a flow of 4000 gpm. [FI-1 CC-117] is sized for all flow conditions with a range of 0-14,000 gpm and an accuracy of 1.5%. It is in the 24" CCR header supplying the cooling loads inside containment. When the RHR System is in operation, the flow through this line is significantly higher. The calibration accuracy of this gauge would yield a reading more accurate than Code requirements. These flow instruments will be used during both the Group A tests and Comprehensive tests since the combination of range and accuracy yields a reading of +/-5.25 percent which is less than the +/-6 percent required by Code.

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                     Page 57 of 320 PUMP RELIEF REQUEST          2 IST PUMP INSTRUMENTATION Pump ID#         Instrument Condition Requiring Relief          Basis for Relief/Alternate Test Pump ID#ID#
1CC-P-1A      PDI-1CC-119    The range of the flow meter   This flow indicator is in the CCR header 1CC-P-1 B                    is greater than three times   supplying the cooling loads in the Auxiliary 1CC-P-1C                     the reference flow for        Building, has a range of 0-150 inwc.
(Cont.)                      normal operations.            Since the use of a pump curve is approved per relief, the reference flow may not be at a specific flow point.
Typical test flow dP is approx. 43 to 46 inwc. The accuracy of the gauge is 0.5%,
which would yield a reading more accurate than Code requirements. This flow instrument will be used during both the Group A tests and Comprehensive tests since the combination of range and accuracy yields a reading of +/-1.74 percent which is less than the +/-6 percent required by Code.
1FW-P-3A      FI-lFW-100A    The range of the gauges is    These flow indicators are in the three lines 1 FW-P-3B     FI-1FW-100B    greater than three times the  to the S/Gs from the AFW Pumps. The Fl-iFW-100C    reference flow for the Motor- flow indicators are sized to measure Driven AFW Pumps.             accident flow from the Turbine-Driven AFW Pump as well as the Motor-Driven Pumps, with a range of 0-400 gpm. The reference value for the Motor-Driven Pumps, full-flow test is approx. 110 gpm, 27.5% of the range. The calibration accuracy of the flow meters is 1.0%, which would yield a reading more accurate than Code requirements. These flow instruments will be used during both the Group B tests and Comprehensive tests since the combination of range and accuracy yields a reading of +/-3.63 percent which is less than the +/-6 percent required by Code.

Beaver Valley Power Station                     Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                    Page 58 of 320 PUMP RELIEF REQUEST         2 PumpD#
Pump ID#
I nstrument In   m IST PUMP INSTRUMENTATION Condition Requiring Relief Codiio Reurn Basis for Relief/Alternate Test ReIe 1 FW-P-2      PI-1FW-156     The range of the gauges is   These gauges are the suction pressure 1 FW-P-3A     PI-1FW-156A    greater than three times the gauges for the Auxiliary Feedwater 1FW-P-3B      PI-1FW-156B    reference pressure.          Pumps. In 1991, DCP 1557 changed the (Cont.)                                                   existing 0-160 psig gauges to the present 0-60 psig gauges. This range was selected as a compromise between the IST Program requirements and possible accident pressures (i.e., River Water supplying the AFW Pumps). The 0-60 psig range will accommodate the accident pressure and typical test pressure of 10 psig. With a calibration accuracy of 0.5%,
this results in a reading more accurate than Code requirements. The use of these pressure instruments is applicable to Group B tests only since the combination of range and accuracy yields a reading of +/-3.0 percent which is less than the +/-6 percent required by Code for the Group B test. During Comprehensive testing, temporary pressure instrumentation will be used having a calibrated accuracy of at least +/-0.5 percent of full scale with a sufficient range to satisfy the +/-1.5 percent required by the Code for the Comprehensive test.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 59 of 320 PUMP RELIEF REQUEST 3 Proposed Alternative In Accordance with 10CFR50.55a(f)(5)(iii)
On the basis that compliance with the Code requirement is impractical for BVPS-I.
Component(s)               1CC-P-1A, Component Cooling Water Pump, (Class 3)
Affected:                  1CC-P-1 B, Component Cooling Water Pump, (Class 3) 1CC-P-1 C, Component Cooling Water Pump, (Class 3)
Component/System           The Component Cooling Water Pumps circulate cooling water through Function:                  various reactor plant components during normal operation, and through the Residual Heat Removal (RHR) Heat Exchangers following an accident in order to achieve and maintain the plant in a cold shutdown condition.
Component Cooling Water flow is also provided to the RHR pumps' seal water coolers to support long term pump operation.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-5121, "Group A Test Procedure", states; Group A tests shall be Requirement(s):            conducted with the pump operating at a specific reference point. ISTB-5121 (b) states; The resistance of the system shall be varied until the flow rate equals the reference value. The pressure shall then be determined and compared to its reference value. Alternatively, the flow rate can be varied until the pressure equals the reference value and the flow rate shall be determined and compared to the reference flow rate value.
ISTB-5123, "Comprehensive Test Procedure", states; Comprehensive tests shall be conducted with the pump operating at a specific reference point. ISTB-5123(b) states; For centrifugal pumps the resistance of the system shall be varied until the flow rate equals the reference value. The pressure shall then be determined and compared to its reference value.
Alternatively, the flow rate can be varied until the pressure equals the reference value and the flow rate shall be determined and compared to the reference flow rate value.
Reason for Request:        The amount of Reactor Plant Component Cooling Water System flow is dependent on the plant's seasonal heat load requirements and on River Water System and seasonal Ohio River water temperatures. The overall amount of flow may vary by several hundred gallons per minute between cold winter months and hot summer months.
Varying Component Cooling header flows by adding or removing heat loads from service in order to increase or decrease flow rate to a specific reference value is impractical. An exact flow rate cannot be duplicated because flow to some heat exchangers cannot be throttled and those that can be throttled are not always capable of being throttled due to system heat load requirements. The test is typically performed by either isolating or placing into service non-essential heat exchangers which results in a gross flow change. For this reason, a wider range of flow values, as on a pump curve, is needed as a reference.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 60 of 320 PUMP RELIEF REQUEST 3 Reason for Request:       In addition, to throttle flow to a reference value during hot summer months (Cont.)                   when flow demand is greatest requires the use of a manual butterfly valve at the discharge of the pumps. A butterfly valve is not designed to be used as a throttle valve so throttling may result in excessive wear and premature failure of the valve. No other valves are available to throttle header flow.
Also, operating experience has shown that any throttling of the pump discharge butterfly valves results in a large reduction in cooling water flow to the Reactor Coolant Pump thermal barrier heat exchangers, bearing lube oil coolers and motor stator air coolers. Reduced header flows result in low flow alarms and heat up of the Reactor Coolant Pumps to near required manual pump trip set points which could ultimately result in a plant trip. Finally, the added thermal cycling of these coolers for pump testing could cause premature degradation of these heat exchangers.
Proposed Alternative       A pump curve, developed per the guidelines provided in NUREG-1482, and Basis for Use:         Rev.1, Section 5.2.2, " Reference Curves" will be used to compare flow rate with developed pump head at the flow conditions dictated by plant seasonal heat load requirements per 1OST-1 5.1, 1OST-1 5.2 and 1OST-15.3 (Reactor Plant Component Cooling Water Pump Tests) during each quarterly Group A test and biennial Comprehensive test. Since normal flow varies, the most limiting vibration acceptance criteria will be used over this range of flows based on baseline vibration data obtained at various flow points on the pump curve.
ISTB-3320, "Establishment of Additional Set of Reference Values",
provides for multiple sets of reference values. A pump curve is merely a graphical representation of the fixed response of the pump to an infinite number of flow conditions which are based on some finite number of reference values verified by measurement. Relief is, therefore, required to use a pump curve, which provides a reasonable alternative in trending pump performance and degradation to that required by the Code. Flow will be permitted to vary as system conditions require. Delta-P will be calculated and converted to a developed head for which ranges will be applied.
Using the provisions of this relief request as an alternative to the requirements of ISTB-5121 (b) and ISTB-5123(b) provides a reasonable alternative to the Code requirements. Based on the determination that compliance with the Code requirements is impractical, it is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed       The proposed alternative identified in this relief request shall be utilized Alternative:               during the Fourth Ten Year IST Interval.
Precedents:                Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date September 4, 1997, Safety Evaluation of Relief Requests (PRR3) for Third 10-Year Interval for Pumps and Valves Inservice Testing (IST) Program, (TAC No. M98620)

Beaver Valley Power Station                    Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                   Page 61 of 320 PUMP RELIEF REQUEST 3

==References:==
NUREG-1482, Rev.1, Section 5.2.2, " Reference Curves" ISTB-3320, "Establishment of Additional Set of Reference Values",
ISTB-5121, "Group A Test Procedure" ISTB-5123, "Comprehensive Test Procedure"

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 62 of 320 PUMP RELIEF REQUEST 4 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.
Component(s)                1EE-P-1A,   Diesel Fuel  Oil Transfer Pump,   (Class 3)
Affected:                   1EE-P-1 B,  Diesel Fuel  Oil Transfer Pump,   (Class 3) 1EE-P-1C,   Diesel Fuel  Oil Transfer  Pump,  (Class  3) 1EE-P-1 D,  Diesel Fuel  Oil Transfer  Pump,  (Class  3)
Component/System           The Diesel Fuel Oil Transfer Pumps transfer fuel oil from the underground Function:                  Emergency Diesel Generator Fuel Oil Storage Tank to the Day Tank in order to provide continuous operation of the Diesel at rated load for up to 7 days during an emergency.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-3550, "Flow Rate", states; When measuring flow rate, a rate or Requirement(s):            quantity meter shall be installed in the pump test circuit. If a meter does not indicate the flow rate directly, the record shall include the method used to reduce the data.
Table ISTB-3000-1, "Inservice Test Parameters", identifies flow rate as a required test parameter and Note 1 states; for positive displacement pumps, flow rate shall be measured or determined.
Reason for Request:        There is no installed instrumentation provided to measure flow rate for these Emergency Diesel Generator Fuel Oil Transfer Pumps. However, a level sight glass does exist on the side of the Diesel Generator Fuel Oil Day Tank, which can be used to measure a change in level over time as the pumps transfer fuel oil from the underground Storage Tank to the Day Tank. The reading scale for measuring the level change over time, and the calculational method yield an accuracy within +/-2% as required by Table ISTB-3500-1, "Required Instrument Accuracy".
Proposed Alternative        Flow rate will be calculated by measuring the level change over time in the and Basis for Use:          Diesel Generator Fuel Oil Day Tank, and converting this data into Fuel Oil Transfer Pump flow rate during both the Group B tests and Comprehensive tests per 1OST-36.1 and 1OST-36.2 (Emergency Diesel Generator and Fuel Oil Transfer Pump Tests).
This proposed alternative is consistent with the guidelines provided in NUREG-1482, Rev.1, Section 5.5.2. Calculating flow rate by a level change in the day tank should be considered acceptable since the level of accuracy required by Table ISTB-3500-1 is satisfied and the method provides reasonable assurance of pump operational readiness.

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 63 of 320 PUMP RELIEF REQUEST 4 Proposed Alternative      Using the provisions of this relief request as an alternative to the and Basis for Use:        requirements of ISTB-3550 provides an acceptable level of quality and (Cont.)                   safety since the alternative provides reasonable assurance of pump operational readiness and the accuracy requirement for measuring flow, as specified in Table ISTB-3500-1 is satisfied. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date September 4, 1997, Safety Evaluation of Relief Requests (PRR4) for Third 10-Year Interval for Pumps and Valves Inservice Testing (IST) Program, (TAC No. M98620)

==References:==
ISTB-3550 "Flow Rate" Table ISTB-3000-1, "Inservice Test Parameters",
Table ISTB-3500-1, "Required Instrument Accuracy" NUREG-1482, Rev.1, Section 5.5.2, "Use of Tank Level to Calculate Floe Rate for Positive Displacement Pumps"

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 64 of 320 PUMP RELIEF REQUEST 5 Proposed Alternative In Accordance with 10CFR50.55a(f)(5)(iii)
On the basis that compliance with the Code requirement is impractical for BVPS-1.
Component(s)               1EE-P-1A, Diesel Fuel Oil Transfer Pump, (Class 3)
Affected:                  1EE-P-1 B, Diesel Fuel Oil Transfer Pump, (Class 3) 1EE-P-1C, Diesel Fuel Oil Transfer Pump, (Class 3) 1EE-P-1 D, Diesel Fuel Oil Transfer Pump, (Class 3)
Component/System           The Diesel Fuel Oil Transfer Pumps transfer fuel oil from the underground Function:                  Emergency Diesel Generator Fuel Oil Storage Tank to the Day Tank in order to provide continuous operation of the Diesel at rated load for up to 7 days during an emergency.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-5323, "Comprehensive Test Procedure", Paragraph ISTB-5323(e),
Requirement(s):            states; All deviations from the reference values shall be compared with the ranges of Table ISTB-5300-1 and corrective action taken as specified in ISTB-6200.
Reason for Request         The test acceptance criteria for pressure (P) and flow (Q) limits, as applicable to Group B tests and Comprehensive tests, given in Table ISTB-5300-1 for positive displacement pumps (except reciprocating) are as follows:
Group B Tests        Acceptable               Alert         Required Action 0.90 to 1.1OQr           None           <0.90 to >1.1 OQr Comprehensive Tests                Acceptable               Alert         Required Action 0.95 to 1.03Qr      0.93 to <0.95Qr    <0.93 to >1.03Qr 0.93 to 1.03Pr      0.90 to <0.93Pr    <0.90 to >1.03P, These limits are too restrictive for the Fuel Oil Transfer Pumps at BVPS-1.
The baseline discharge pressures for these four pumps range from 6.8 psig to 13.0 psig. Applying the Acceptable limits from the ASME OM Code for these values, the average allowable degradation from the reference value is only 0.7 psig for the Comprehensive test. The discharge pressure has historically varied by as much as 1 psig from one test to the next and between 1 to 2 psig over the course of a year which is more than the Acceptable Range for discharge pressure.
The baseline flows for these four pumps range from 9.0 to 13.3 gpm. The average allowable degradation for flow is therefore only 1.1 gpm for the Group B test and only 0.56 gpm for the Comprehensive test. The flow values also vary from test to test and between 1 to 1.5 gpm over the course of a year which is more than the Acceptable Range for flow.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 65 of 320 PUMP RELIEF REQUEST 5 Reason for Request:        The ASME OM Code limits are, too restrictive and therefore, impractical to (Cont.)                    apply. Normal historic variation in discharge pressure and flow would require the pumps to enter the Alert or Required Action Ranges. Trends would not be observed because the pumps would have to be declared inoperable before enough data could be obtained to determine if the data obtained is a true indication of a degrading condition or data scatter. In addition, the ASME OM Code trending would also pick-up variations caused by fouling of the suction strainer or discharge filter or by chattering of the relief valve. An allowable variation larger than 0.7 psig or 0.56 gpm, is therefore needed for both the Group B test and Comprehensive test, as applicable, to trend pump performance.
NUREG-1482, Rev.1, Section 5.6 "Operability Limits of Pumps," states that if expanded ranges are needed, relief must be obtained. "The request for relief must include the licensee's basis for the expanded ranges and the basis for finding that the pump performance does not demonstrate degrading conditions. The basis for acceptable pump performance pertains to the pump and not the system, though pump performance must meet system requirements to remain in an analyzed condition."
Therefore, BVPS-1 requests relief to use expanded ranges for flow during the Group B tests and discharge pressure and flow during the Comprehensive tests for the Fuel Oil Transfer Pumps. The proposed ranges to be used during both the Group B tests and Comprehensive tests are as follows:
Group B Tests         Acceptable             Alert          Required Action 0.80 to 1.15Qr          None           <0.80 to >1.15Qr Comprehensive Tests                 Acceptable             Alert          Required Action 0.90 to 1.15Qr     0.80 to <0.90Qr    <0.80 to >1.15Qr 0.80 to 1.20Pr     0.70 to <0.80Pr    <0.70 to >1.20Pr The function of these pumps is to be able to deliver fuel to the day tank to supply the Diesel Generator under full load. The amount of fuel that is required to be delivered is 3.6 gpm, significantly lower than the reference values for all of the pumps. In addition, due to the nature of positive displacement pumps, flow should be the more consistent parameter. The proposed range for the flow value is more restrictive because the flow rate is the more critical parameter for the system. The high flow limit is based on approximately half of the allowable variation expected in pumps with this rated flow rate, from the Hydraulic Institute Test Standard for Rotary Pumps, 14th edition.
These ranges would only result in an allowed variation of -2.04 psig and
                            +11.36 psig for the lowest expected pressure reading (6.8 psig) and -1.8 gpm and +0.9 gpm for the lowest expected flow reading (9 gpm). In addition, during discussions with Ingersoll-Dresser Pumps, the pump manufacturer, when questioned about a limiting value for pump

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 66 of 320 PUMP RELIEF REQUEST 5 Reason for Request:       performance, the pump manufacturer has stated that as the pump wears (Cont.)                   and the clearances open, the performance will gradually change. No limiting value for either flow or discharge pressure was provided and sudden performance degradation is not expected. These expanded ranges will allow degrading conditions to be identified and provide assurance that the Fuel Oil Transfer Pumps will be capable of fulfilling their safety function.
Proposed Alternative      BVPS-1 proposes the use expanded limits for test acceptance criteria in and Basis for Use:        lieu of the test acceptance criteria specified in Table ISTB-5300-1. Testing will be performed per 1OST-36.1 and 2 (Diesel Generator Monthly Tests) using expanded ranges for flow and discharge pressure during the Comprehensive tests and for flow during the Group B tests. Extensive hardware changes would be required in order to comply with the requirements of Table ISTB-5300-1 with little or no enhancement or compensating increase to the quality of the tests or the ability to detect pump degradation. These expanded ranges will allow degrading conditions to be identified without needlessly declaring the pumps inoperable and provide assurance that the Fuel Oil Transfer Pumps will be capable of fulfilling their safety function.
Using the provisions of this relief request as an alternative to the requirements of Table ISTB-5300-1 provides a reasonable alternative to the Code requirements. Based on the determination that compliance with the Code requirements is impractical, it is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date December 21, 1998. Safety Evaluation of Inservice Testing Relief Request PRR-5, (TAC No. MA2114)

==References:==
NUREG-1482, Rev.1, Section 5.6, "Operability Limits for Pumps" Table ISTB-5300-1, "Positive Displacement Pump (Except Reciprocating)
Test Acceptance Criteria" ISTB-5323, "Comprehensive Test Procedure"

Beaver Valley Power Station                          Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 67 of 320 PUMP RELIEF REQUEST 6 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.
Component(s)                1CH-P-2A, Boric Acid Transfer Pump, (Class 3)
Affected:                   1CH-P-2B, Boric Acid Transfer Pump, (Class 3)
Component/System           The boric acid transfer pumps supply borated water from the Boric Acid Function:                  Tanks to the suction of the Charging / High Head Safety Injection Pumps for injection into the RCS for emergency boration.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code             ISTB-5100(b), "Bypass Loops", ISTB-5100(b)(1), states; A bypass test Requirement(s):             loop may be used for a Group A test or Comprehensive test, provided the flow rate through the loop meets the requirements as specified in ISTB-3300.
ISTB-3300, "Reference Values", ISTB-3300(e)(2), states; 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-5121, "Group A Test Procedure" and Table ISTB-3000-1, "Inservice Test Parameters," state; Group A tests shall be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph. Table ISTB-3000-1 identifies flow rate as a test parameter and Note 1 states; differential pressure or flow rate shall be measured or determined.
Reason for Request:        Testing the Boric Acid Transfer Pumps using the emergency boration flow path is impractical during power operation because it would inject water with higher concentration of boric acid into the RCS which would result in a reactivity transient and subsequent reactor shutdown. Therefore, the Code-required quarterly Group A testing is performed using an alternate test loop as shown on the attached figure. The pumps are Group A tested quarterly through [RO-1CH-ORBA-1 (2)], the restricting orifices in the minimum flow fixed resistance recirculation lines. However, there are no installed flow instruments in these recirculation lines. Because of the restricting orifices, the flow is assumed to be fixed and at its reference value. Delta-P and vibration are then measured and compared to the acceptance criteria.
NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices", in part states; In cases where only the minimum flow return line is available for pump testing, regardless of the test Interval, the staffs position is that flow instrumentation that meets the requirements of Subsection ISTB-3500

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 68 of 320 PUMP RELIEF REQUEST 6 Reason for Request:        should be installed in the minimum flow return line. Installation of this (Cont.)                    instrumentation is necessary to provide flow rate measurements during pump testing so that this data can be evaluated with the measured pump differential pressure to monitor for pump hydraulic degradation. The guidance provided in GL 89-04, Position 9 still applies.
Since a full flow loop exists that can be easily instrumented and utilized only during certain plant operating modes, the guidance provided in GL 89-04, Position 9, for non-instrumented minimum flow paths shall be followed during the quarterly Group A test.
Position 9 of GL 89-04 states that, "In cases where flow can only be established through a non-instrumented minimum flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code requirements, provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibrations is continued."
In accordance with Position 9 of the GL 89-04, the pumps have also been tested through their full-flow recirculation flow paths through [HCV-1CH-110(105)], at a refueling frequency. For the full-flow recirc test, the flow is measured by a portable ultrasonic flow meter that has been "wet-flow" calibrated to within the +/-2% accuracy required by Table ISTB-3500-1.
In order to install the flow meters, however, the insulation on the piping must be removed and the heat trace elements must be moved away from where the transducers and tracks will be installed. Moving the heat trace elements places stresses on them, which increases the probability of failure of the heat trace elements. The heat tracing on the boric acid piping is needed to support system operability. Therefore, it is impractical to test the pumps quarterly and at a cold shutdown frequency.
A review of past test results has shown that this combination of quarterly Group A testing and refueling frequency Comprehensive testing is capable of assessing pump performance and detecting degradation.
The use of the portable ultrasonic flow meter and full-flow recirc flow path was considered for the quarterly test. It was determined, however, that use of the full-flow recirc line was impractical for quarterly testing. Testing quarterly using the temporary ultrasonic flow meter would lead to the increased probability of failure of the heat trace elements and to increased dose for the laborers who remove/reinstall the insulation and the technicians who install the flow meters.
Also, additional calibrated flow instrumentation would have to be purchased to ensure the availability of equipment. Permanently installing the flow meters would require a design change to the plant and the purchase of additional flow instrumentation. Performing the full-flow test

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 69 of 320 PUMP RELIEF REQUEST 6 Reason for Request:       quarterly and during cold shutdowns would not enhance our ability to (Cont.)                   assess the operability of the pumps enough to justify the increased cost or a system design change.
In addition, testing during refueling outages diverts manpower from other refueling tasks. These tests must be scheduled at a time in the outage when the Boric Acid Tanks are not required to be part of the Tech Spec boration flow path and must be coordinated with power supply outages.
Even though the actual performance of these tests may be completed in a relatively short time, the set-up and restoration is approximately 8 to 10 hours for each pump. Removing the tests from the outage schedule would allow a greater focus on other safety-related tasks without impacting the level of quality and safety of the Boric Acid Transfer Pumps. In addition, a PRA risk evaluation has determined that there is no increase in risk for the performance of this test, whether on-line or during refueling outages.
Therefore, it is requested to perform the full-flow test at least once every 2 years which satisfies the inservice test frequency of biennially specified in Table ISTB-3400-1 for the Comprehensive test. Overall, proper monitoring of pump performance will be maintained via the quarterly Group A testing and full-flow Comprehensive testing at least once every 2 years..
Proposed Alternative      Perform the quarterly Group A test through a fixed-resistance non-and Basis for Use:        instrumented minimum-flow recirculation line assuming flow to be constant and measuring delta-P in 1OST-7.1(2) (Boric Acid Transfer Pump Operational Tests) and perform the full flow Comprehensive test at least once every 2 years, through a larger recirculation line, using a portable ultrasonic flow meter in 1OST-7.13(14) (Boric Acid Transfer Pump Full-Flow Tests).
Separate vibration reference and acceptance criteria values will be used for the different test conditions of the recirc and full-flow tests.
This proposed alternative is consistent with the guidelines provided in NUREG-1482, Rev.1, Section 5.9 and GL 89-04, Position 9 and provides reasonable assurance of pump operational readiness without causing operational concerns, such as reactivity transients.
Using the provisions of this relief request as an alternative to the requirements of ISTB-5121 provides an acceptable level of quality and safety since the alternative provides reasonable assurance of pump operational readiness. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.

Beaver Valley Power Station                     Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                   Page 70 of 320 PUMP RELIEF REQUEST 6 Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date November 12, 2002, Safety Evaluation of Inservice Testing Relief Request PRR-6. (TAC No. MB5558)

==References:==
ISTB-5121, "Group A Test Procedure" ISTB-5100(b), "Bypass Loops" ISTB-3300, "Reference Values" NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices" Generic Letter (GL) 89-04, Position 9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices"

Beaver Valley Power Station                  Unit I          Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves               Page 71 of 320 PUMP RELIEF REQUEST 6 ICH-TK-1A 10 I CH-P-2A 104         TO BLENDER 79 ICH-TK-1 9 80               MOV-ICH..350 TO EMERGENCY SORATION

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                      Page 72 of 320 PUMP RELIEF REQUEST 7 Proposed Alternative In Accordance with 10CFR50.55a(f)(5)(iii)
On the basis that compliance with the Code requirement is impractical for BVPS-1.
Component(s)               1RH-P-1A, Residual Heat Removal Pump, (Class 2)
Affected:                  1RH-P-1 B, Residual Heat Removal Pump, (Class 2)
Component/System           The Residual Heat Removal (RHR) Pumps provide long-term removal of Function:                  decay heat from the reactor core and sensible heat from the Reactor Coolant System (RCS) in order to achieve and maintain the plant in a cold shutdown condition.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-3400, "Frequency of Inservice Tests", states; An inservice test shall Requirement(s):            be run on each pump as specified in Table ISTB-3400-1.
Table ISTB-3400-1, "Inservice Test Frequency", requires Group A pumps to be tested on a quarterly frequency.
Reason for Request:        The Residual Heat Removal (RHR) Pumps are in a standby condition during power operation, and are not required to be in service until the Reactor Coolant System (RCS) temperature is < 350F and RCS pressure is < 430 psig. Therefore, they are not exposed to operational wear except when the RCS is at low temperature and pressure and the RHR System is in operation for normal shutdown cooling.
The RHR Pumps have a design pressure of 600 psig. They take suction from the RCS, pass flow through the RHR Heat Exchangers, and then discharge back to the RCS. The RHR System is considered to be a low pressure system that could be damaged if exposed to the normal operating RCS pressure of approximately 2235 psig. In order to prevent this, the RHR Inlet and Return Isolation Valves are interlocked with an output signal from the RCS pressure transmitters, which prevent the valves from being opened when the RCS pressure exceeds 430 psig. In addition, these valves are also maintained shut with their breakers de-energized and administratively controlled (caution tagged). Therefore, testing of the RHR Pumps during normal operation is not practicable since there are no alternate supply sources and aligning the RCS to the suction of the RHR pumps, during operation at power, would result in damage to piping and components due to overpressurization. Major plant and system modifications would be needed to allow quarterly Group A testing of the RHR pumps according to ASME OM Code requirements.
In addition, although overpressure precludes testing of the RHR pumps, they are also located inside containment. Testing at power, subsequent to system modification, would require test personnel to make a containment entry in order to monitor pump operation. Since radiation levels and air temperature inside containment are higher than normal during power

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 73 of 320 PUMP RELIEF REQUEST 7 Reason for Request:       operation, this would involve higher radiological dose rates and heat stress (Cont.)                   risks to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis while on-line.
Based on the above, compliance with the ASME OM Code test frequency requirement for Group A pump tests is impractical. Testing is only possible during a surveillance interval frequency of cold shutdown and refueling.
Proposed Alternative      These pumps will be tested during cold shutdowns and refueling outages, and Basis for Use:        not more often than once every 92 days, per 1OST-10.1 (Residual Heat Removal Pumps Performance Test). For a cold shutdown or refueling outage that extends longer than 3 months, the pumps will be tested every 3 months in accordance with Table ISTB-3400-1. In the instance of an extended outage, a Group A test may be performed, otherwise; a Comprehensive test will be performed each refueling.
This proposed alternative is necessary to prevent the potential for piping and component damage as a result of overpressurization.
Using the provisions of this relief request as an alternative to the frequency requirements of Table ISTB-3400-1 provides a reasonable alternative to the Code requirements. Based on the determination that compliance with the Code requirements is impractical, it is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date July 2, 2004, Safety Evaluation of Inservice Testing Relief Request PRR-7 (TAC No. MC2317 and MC2318).
Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date February 24, 2006, Safety Evaluation of Inservice Testing Relief Request PRR-7 (TAC No. MC5901, MC5902 and MC5903).

==References:==
Table ISTB-3400-1, "Inservice Test Frequency" ISTB-3400, "Frequency of Inservice Tests" LAR 1A-317

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 74 of 320 PUMP RELIEF REQUEST 8 Proposed Alternative In Accordance with 1 OCFR50.55a(a)(3)(i)
On the basis that the proposed alternative provides an acceptable level of quality and safety.
Component(s)                1 CH-P-2A (Class 3)        1QS-P-4C (Class 2)        1WR-P-1C (Class 3)
Affected:
1CH-P-2B (Class 3)         1QS-P-4D (Class 2)        1EE-P-1A (Class 3) 1RH-P-1A (Class 2)         1FW-P-3A (Class 3)        1 EE-P-1 B (Class 3) 1 RH-P-1 B (Class 2)       1FW-P-3B (Class 3)        1EE-P-1C (Class 3) 1QS-P-4A (Class 2)         1WR-P-1A (Class 3)        1EE-P-1D (Class 3) 1QS-P-4B (Class 2)         1WR-P-1B (Class 3)
This Request for Relief may also be applied to any pump in the IST Program scope should a vibration reading of <0.05 in/sec be obtained as a new reference value subsequent to repair or replacement.
Component/System           Various Function:
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003 Edition and Addenda:
Applicable Code             ISTB-3300, "Reference Values" Requirement(s):
ISTB-3300(a), states; Initial reference values shall be determined from the results of testing meeting the requirements of ISTB-3100, "preservice Testing", or from the results of the first inservice test.
ISTB-3300(d), states; Reference values shall be established at a point(s) of operation (reference point) readily duplicated during subsequent tests.
ISTB-3300(f), states; 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-5120, "Inservice Testing" (Centrifugal Pumps, Except Vertical Line Shaft Centrifugal Pumps)
ISTB-5121 (e) and ISTB-5123(e), "Group A Test and Comprehensive Test Procedure", states; All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200. Vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-5100-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.
ISTB-5220, "Inservice Testing" ( Vertical Line Shaft Centrifugal Pumps)

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 75 of 320 PUMP RELIEF REQUEST 8 Applicable Code            ISTB-5221 (e) and ISTB-5223(e), "Group A Test and Comprehensive Test Requirement(s):            Procedure", states; All deviations from the reference values shall be (Cont.)                    compared with the ranges of Table ISTB-5200-1 and corrective action taken as specified in ISTB-6200. Vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-5200-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.
ISTB-5320, "Inservice Testing" (Positive Displacement Pumps, Except Reciprocating)
ISTB-5321(e) and ISTB-5323(e), "Group A Test and Comprehensive Test Procedure", states; All deviations from the reference values shall be compared with the ranges of Table ISTB-5300-1 and corrective action taken as specified in ISTB-6200. Vibration measurements shall be compared to both the relative and absolute criteria shown in the alert and required action ranges of Table-ISTB-5300-1. For example, if vibration exceeds either 6Vr, or 0.7 in./sec, the pump is in the required action range.
Note:    BVPS-1 has no reciprocating positive displacement pumps in the IST Program.
Reason for Request:        The above pumps in the BVPS-1 IST Program have at least one vibration reference value (Vr) that is currently less than 0.05 in/sec. A small value for Vr produces a small acceptable range for pump operation. The ASME OM Code Acceptable Range limit for pump vibrations from Table ISTB-5100-1, Table ISTB-5200-1, and Table ISTB-5300-1 for both the Group A test and Comprehensive test is *2.5 Vr. Based on a small acceptable range, a smooth running pump could be subject to unnecessary corrective action if it exceeds this limit. ISTB-6200(a), "Corrective Action - Alert Range", states; If the measured test parameter values fall within the alert range of Table ISTB-5100-1, Table ISTB-5200-1, or Table ISTB-5300-1, 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.
For very small reference values for vibrations, flow variations, hydraulic noise and instrument error can be a significant portion of the reading and affect the repeatability of subsequent measurements. Also, experience gathered by the BVPS Predictive Maintenance (PdM) Group has shown that changes in vibration levels in the range of 0.05 in/sec do not normally indicate significant degradation in pump performance.
In order to avoid unnecessary corrective actions, a minimum value for Vr of 0.05 in/sec is proposed. This minimum value would be applied to individual vibration locations for those pumps with reference vibration values less than 0.05 in/sec. Therefore, the smallest ASME OM Code Acceptable Range limit for any IST pump vibration location would be no lower than 2.5 times Vr, or 0.125 in/sec, which is within the "fair" range of the "General Machinery Vibration Severity Chart" provided by IRD Mechanalysis, Inc. Likewise, the smallest ASME OM Code Alert Range

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 76 of 320 PUMP RELIEF REQUEST 8 Reason for Request:       limit for any IST Pump vibration location for which the pump would be (Cont.)                   inoperable would be no lower than 6 times Vr, or 0.300 in/sec.
ASME XI, Table IWP-3100-2, "Allowable Ranges of Test Quantities",
specifies a vibration Acceptable Range limit of 1.0 mil for a displacement reference value _<0.5 mils. In velocity units, a displacement reference value of 0.5 mils is equivalent to 0.047 in/sec for an 1800 rpm pump and 0.094 in/sec for a 3600 rpm pump.
The effective minimum reference value proposed (0.05 in/sec) for smooth-running pumps is roughly equal to the ASME XI IWP reference value for an 1800 rpm pump and more conservative than the reference value for a 3600 rpm pump. Without this relief, the ASME Xl Acceptable Range limit for some extremely smooth running pumps is reduced by as much as a factor of 10.
In addition to the requirements of ISTB for IST, the pumps in the BVPS-1 IST Program are also included in the BVPS PdM Program. The BVPS PdM Program currently employs predictive monitoring techniques such as:
vibration monitoring and analysis beyond that required by ISTB, bearing temperature trending, oil sampling and analysis, and/or thermography analysis as applicable.
If the measured parameters are outside the normal operating range or are determined by analysis to be trending toward an unacceptable degraded state, appropriate actions are taken that may include: a Condition Report (CR) initiated, increased monitoring to establish a rate of change, review of component specific information to identify cause, and removal of the pump from service to perform maintenance.
It should be noted that all of the pumps in the IST Program will remain in the BVPS PdM Program even if certain pumps have very low vibration readings and are considered to be smooth running pumps.
Proposed Alternative      In lieu of applying the vibration acceptance criteria ranges specified in and Basis for Use:        Table ISTB-51 00-1, Table ISTB-5200-1, or Table ISTB-5300-1, as applicable, smooth running pumps with a measured reference value below 0.05 in/sec for a particular vibration measure location will have subsequent test results for that location compared to an Acceptable Range limit of 0.125 in/sec and an Alert Range limit of 0.300 in/sec (based on a minimum reference value 0.05 in/sec). These proposed ranges shall be applied to vibration test results during both Group A tests and Comprehensive tests.
In addition to the Code requirements, all pumps in the BVPS-1 IST Program are included in and will remain in the BVPS PdM Program regardless of their smooth running status.

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 77 of 320 PUMP RELIEF REQUEST 8 Proposed Alternative      Using the provisions of this relief request as an alternative to the specific and Basis for Use:        requirements of ISTB identified above will provide adequate indication of (Cont.)                   pump performance and continue to provide an acceptable level of quality and safety without unnecessarily imposing corrective action since changes in vibration levels in the range of 0.05 in/sec do not normally indicate significant degradation in pump performance.
Using the provisions of this relief request as an alternative to the vibration acceptance criteria ranges specified in Table ISTB-51 00-1, Table ISTB-5200-1, or Table ISTB-5300-1 provides an acceptable level of quality and safety since the alternative provides reasonable assurance of pump operational readiness and the ability to detect pump degradation. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date December 27, 2004, Evaluation of Inservice Testing Pump Relief Request PRR-8, (TAC No. MC3240)

==References:==
ISTB-3300, "Reference Values" ISTB-5120, "Inservice Testing", (Centrifugal Pumps, Except Vertical Line Shaft Centrifugal Pumps)
Table ISTB-5100-1, "Centrifugal Pump Test Acceptance Criteria" ISTB-5220, "Inservice Testing", (Vertical Line Shaft Centrifugal Pumps)
Table ISTB-5200-1, "Vertical Line Shaft and Centrifugal Pumps Test Acceptance Criteria" ISTB-5320, "Inservice Testing", (Positive Displacement Pumps, Except Reciprocating)
Table ISTB-5300-1, "Positive Displacement Pump (Except Reciprocating)
Test Acceptance Criteria" NUREG-1482, Rev.1, Section 5.4, "Monitoring Pump Vibration in Accordance with ISTB" ASME XI, Table IWP-3100-2, "Allowable Ranges of Test Quantities" General Machinery Vibration Severity Chart provided by IRD Mechanalysis, Inc.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 78 of 320 PUMP RELIEF REQUEST 9 Proposed Alternative In Accordance with 10CFR50.55a(f)(5)(iii)
On the basis that compliance with the Code requirement is impractical for BVPS-1.
Component(s)               1FW-P-3A, Motor Driven Auxiliary Feed Water Pump, (Class 2)
Affected:                  1FW-P-3B, Motor Driven Auxiliary Feed Water Pump, (Class 2)
Component/System           During any loss of normal feedwater flow, the motor-driven auxiliary Function:                  feedwater pumps are required to transfer a source of emergency make-up water from the Demineralized Water Storage Tank or, as a backup, from the River Water System to the Steam Generators.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-5100(b), "Bypass Loops", ISTB-5100(b)(2), states; A bypass test Requirement(s):            loop may be used for a Group B tests if it is designed to meet the pump manufacturer's operating specifications (e.g., flow rate, time limitations) for minimum flow operation.
ISTB-3300, "Reference Values", ISTB-3300(e)(2), states; 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" and Table ISTB-3000-1, "Inservice Test Parameters," state; Group B tests shall be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph. Table ISTB-3000-1 identifies flow rate as a test parameter and Note 1 states; differential pressure or flow rate shall be measured or determined.
Reason for Request:        Aligning auxiliary feedwater flow to the Steam Generators is not practical during normal plant operation because the introduction of relatively cold auxiliary feedwater into the Steam Generators produces a potential for thermal shock to both the main feed piping (thermal sleeves) and the secondary side of the Steam Generators. Although the thermal sleeves and Steam Generators are designed for thermal shock, the exposure to the Station to these events shall be minimized in order to ensure that the benefits of plant life extension can be realized. In addition, feeding the Steam Generators with a large volume of relatively cold water would also result in a large level transient in the Steam Generators and could cause a reactor trip.
Additionally, these pumps receive their suction from the Demineralized Water Storage Tank. The water in the Demineralized Water Storage Tank is not treated for pH or oxygen; therefore, it could have some impact on the corrosion rates in the Steam Generators. From a Chemistry perspective, it is preferred to minimize the use of this water while in Modes 1, 2, or3.

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 79 of 320 PUMP RELIEF REQUEST 9 Reason for Request:       Therefore, it is impractical to test these pumps using this flow path during (Cont.)                   normal plant operation. In order to perform the quarterly Group B test, a recirculation flow path must be used. However, this flow path does not have installed flow instrumentation that meets ASME OM Code requirements. BVPS-1 considers the installation of temporary flow instrumentation, during the performance of the Group B quarterly test impractical without a compensating increase in the quality of the test.
NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices", in part states; In cases where only the minimum flow return line is available for pump testing, regardless of the test Interval, the staffs position is that flow instrumentation that meets the requirements of Subsection ISTB-3500 should be installed in the minimum flow return line. Installation of this instrumentation is necessary to provide flow rate measurements during pump testing so that this data can be evaluated with the measured pump differential pressure to monitor for pump hydraulic degradation. The guidance provided in GL 89-04, Position 9 still applies.
Since an instrumented full flow loop exists that can be utilized only during certain plant operating modes, the guidance provided in GL 89-04, Position 9, for non-instrumented minimum flow paths shall be followed during the quarterly Group B test.
Position 9 of GL 89-04 states that, "In cases where flow can only be established through a non-instrumented minimum flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code requirements, provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that quarterly testing also measuring at least pump differential pressure and vibrations is continued.
In accordance with Position 9 of the GL 89-04, the pumps have also been tested through their full-flow paths by injecting flow into the steam generators via flow instrumentation [FI-1FW-100A, B and C], at a refueling frequency. During this test flow is also measured to the lube oil coolers by attaching an ultrasonic flow meter.
Proposed Alternative      The quarterly Group B test will be performed using the recirculation flow and Basis for Use:        path while measuring delta-p per 1OST-24.2 and 3 (Motor-Driven Auxiliary Feedwater Pump Tests), with flow assumed to be fixed and at its reference value. The biennial Comprehensive test will be performed during refueling outages when plant conditions permit directing flow to the Steam Generators. Full flow will be measured using the flow instrumentation in the Steam Generator supply headers while also measuring delta-p and vibrations per 1OST-24.8A and 8B (Motor-Driven Auxiliary Feedwater Pump Check Valve and Full-Flow Tests). Separate delta-p reference and acceptance criteria values will be used for the different test conditions of

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 80 of 320 PUMP RELIEF REQUEST 9 Proposed Alternative      the recirculation and full-flow tests. Also note that 1OST-24.8A and 8B and Basis for Use:        may be performed in lieu of the quarterly tests, 1OST-24.2 and 3, if their (Cont.)                   scheduled performances coincide.
This proposed alternative is in accordance with the guidelines provided in GL 89-04, Position 9.
Using the provisions of this relief request as an alternative to the requirements of ISTB-5122 provides a reasonable alternative to the Code requirements. Based on the determination that compliance with the Code requirements is impractical, it is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date May 9, 2005, Evaluation of Inservice Testing Relief Request PRR-9 and PRR-10, (TAC No. MC5195 and MC5196)

==References:==
ISTB-5100(b), "Bypass Loops" ISTB-3300, "Reference Values" ISTB-5122, "Group B Test Procedure" NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices" Generic Letter (GL) 89-04, Position 9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 81 of 320 PUMP RELIEF REQUEST 10 Proposed Alternative In Accordance with 10CFR50.55a(f)(5)(iii)
On the basis that compliance with the Code requirement is impractical for BVPS-1.
Component(s)               1 FW-P-2, Turbine Driven Auxiliary Feed Water Pump, (Class 2)
Affected:
Component/System           During any loss of normal feedwater flow, the Turbine-Driven Auxiliary Function:                  Feedwater Pump is required to transfer a source of emergency make-up water from the Demineralized Water Storage Tank or, as a backup, from the River Water System to the Steam Generators.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-5100(b), "Bypass Loops", ISTB-5100(b)(2), states; A bypass test Requirement(s):            loop may be used for a Group B test if it is designed to meet the pump manufacturer's operating specifications (e.g., flow rate, time limitations) for minimum flow operation.
ISTB-3300, "Reference Values", ISTB-3300(e)(2), states; 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" and Table ISTB-3000-1, "Inservice Test Parameters," state; Group B tests shall be conducted with the pump operating at a specified reference point. The test parameters shown in Table ISTB-3000-1 shall be determined and recorded as required by this paragraph. Table ISTB-3000-1 identifies flow rate as a test parameter and Note 1 states; differential pressure or flow rate shall be measured or determined.
Reason for Request:        Aligning auxiliary feedwater flow to the Steam Generators is not practical during normal plant operation because the introduction of relatively cold auxiliary feedwater into the Steam Generators produces a potential for thermal shock to both the main feed piping (thermal sleeves) and the secondary side of the Steam Generators. Although the thermal sleeves and Steam Generators are designed for thermal shock, the exposure to the Station to these events shall be minimized in order to ensure that the benefits of plant life extension can be realized. In addition, feeding the Steam Generators with a large volume of relatively cold water would also result in a large level transient in the Steam Generators and could cause a reactor trip. Additionally, these pumps receive their suction from the Demineralized Water Storage Tank. The water in the Demineralized Water Storage Tank is not treated for pH or oxygen; therefore, it could have some impact on the corrosion rates in the Steam Generators. From a Chemistry perspective, it is preferred to minimize the use of this water while in Modes 1, 2, or 3.

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 82 of 320 PUMP RELIEF REQUEST 10 Reason for Request:        Therefore, it is impractical to test these pumps using this flow path during (Cont.)                    normal plant operation. In order to perform the quarterly Group B test, a recirculation flow path must be used. However, this flow path does not have installed flow instrumentation that meets ASME OM Code requirements. BVPS-1 considers the installation of temporary flow instrumentation, during the performance of the Group B quarterly test impractical without a compensating increase in the quality of the test.
NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices", in part states; In cases where only the minimum flow return line is available for pump testing, regardless of the test Interval, the staffs position is that flow instrumentation that meets the requirements of Subsection ISTB-3500 should be installed in the minimum flow return line. Installation of this instrumentation is necessary to provide flow rate measurements during pump testing so that this data can be evaluated with the measured pump differential pressure to monitor for pump hydraulic degradation. The guidance provided in GL 89-04, Position 9 still applies.
Since an instrumented full flow loop exists that can be utilized only during certain plant operating modes, the guidance provided in GL 89-04, Position 9, for non-instrumented minimum flow paths shall be followed during the quarterly Group B test.
Position 9 of GL 89-04 states that, "In cases where flow can only be established through a non-instrumented minimum flow path during quarterly pump testing and a path exists at cold shutdowns or refueling outages to perform a test of the pump under full or substantial flow conditions, the staff has determined that the increased interval is an acceptable alternative to the Code requirements, provided that pump differential pressure, flow rate, and bearing vibration measurements are taken during this testing and that the quarterly Group B testing also measuring at least pump differential pressure and vibrations is continued."
As stated above, Generic Letter 89-04 requires full flow testing during cold shutdowns or refueling outages. Note that full flow testing of the turbine driven auxiliary feedwater pump can only be performed in Mode 3 because the turbine requires steam from any of the three steam generators to drive the pump. It is not desirable to test the pump during cold shutdown, but rather only in Mode 3 during shutdown or during startup after a refueling outage for the following reasons.
In Mode 3, the introduction of relatively cold auxiliary feedwater into the Steam Generators produces a potential for thermal shock to both the main feed piping (thermal sleeves) and the secondary side of the Steam Generators. Although the thermal sleeves and Steam Generators are designed for thermal shock, the exposure of the Station to these events shall be minimized in order to ensure that the benefits of plant life extension can be realized.

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 83 of 320 PUMP RELIEF REQUEST 10 Reason for Request:       As previously stated, this pump takes suction from the Demineralized (Cont.)                   Water Storage Tank. The water in the Demineralized Water Storage Tank is not treated for pH or oxygen; therefore, it could have some impact on the corrosion rates in the Steam Generators. For this reason from a Chemistry perspective, it is preferred to minimize the use of this water while in Modes 1,2, or3.
In addition during startup, this test can only be performed once the steam pressure exceeds 600 psig. Testing at this time during startup causes a temperature transient. The turbine draws steam from the Steam Generators, causing the Reactor Coolant System (RCS) to cool down. In addition, the relatively cold auxiliary feedwater is injected into the Steam Generators, causing the RCS to cool even more. This cool down delays startup and is critical path time. At this point in the outage, the only heat source for the RCS is the Reactor Coolant Pumps. Therefore, any cool down is costly in the amount of time required to heat back up again.
For these reasons, performing a full-flow test of the Turbine-Driven Auxiliary Feedwater Pump at each cold shutdown is not desired. Testing will be performed in Mode 3 during shutdown or during startup after a refueling outage by injecting flow into the steam generators via flow instrumentation [FI-1FW-1OOA, B and C].
Proposed Alternative      This pump will receive the quarterly Group B test using the recirculation and Basis for Use:        flow path while measuring delta-p per 1OST-24.4 (Steam Turbine-Driven Auxiliary Feedwater Pump Test), with flow assumed to be fixed and at its reference value. The Comprehensive test will be performed in Mode 3 during shutdown or during startup after refueling outages when plant conditions permit directing flow to the Steam Generators. Full flow will be measured using the flow instrumentation in the Steam Generator supply headers while also measuring delta-p and vibrations per 1OST-24.9 (Turbine-Driven Auxiliary Feedwater Pump Operability Test). Separate delta-p reference and acceptance criteria values will be used for the different test conditions of the recirculation and full-flow tests. Also note that 1OST-24.9 will be performed in lieu of the quarterly Group B test, 1OST-24.4, during refueling.
This proposed alternative is consistent with the guidelines provided in GL 89-04, Position 9.
Using the provisions of this relief request as an alternative to the requirements of ISTB-5122 provides a reasonable alternative to the Code requirements. Based on the determination that compliance with the Code requirements is impractical, it is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.

Beaver Valley Power Station                     Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 84 of 320 PUMP RELIEF REQUEST 10 Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               Beaver Valley Power Station, Unit 1, Docket No. 50-334, SER Date May 9, 2005, Evaluation of Inservice Testing Relief Request PRR-9 and PRR-10, (TAC No. MC5195 and MC5196)

==References:==
ISTB-5100(b), "Bypass Loops" ISTB-3300, "Reference Values" ISTB-5122, "Group B Test Procedure" NUREG-1482, Rev.1, Section 5.9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices" Generic Letter (GL) 89-04, Position 9, "Pump Testing Using Minimum Flow Return Lines With or Without Flow Measuring Devices"

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 85 of 320 PUMP RELIEF REQUEST 11 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
On the basis that compliance with certain Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Component(s)                1RS-P-1A; Inside Recirculation Spray Pump, (Class 2)
Affected:                   1RS-P-1 B; Inside Recirculation Spray Pump, (Class 2) 1RS-P-2A; Outside Recirculation Spray Pump, (Class 2) 1 RS-P-2B; Outside Recirculation Spray Pump, (Class 2)
Component/System            SYSTEM FUNCTION Function:
The recirculation spray system at the Beaver Valley Power Station Unit No. 1, is designed to recirculate water from the containment sump through coolers to spray containment after a Containment Isolation Phase B signal (CIB) and predetermined time delay. The time delay in starting the recirculation spray pumps allows the containment sump to fill, thereby ensuring adequate NPSH is available for the pumps and to avoid pump operating difficulties due to vortexing. The sump is filled with water from the quench spray system and water from ruptured lines or vessels in the reactor coolant system. Recirculation spray system operation is required during post accident conditions for heat removal to reduce containment pressure to less than 50 percent of the peak calculated pressure for the LOCA within 24 hours after the postulated accident.
During the recirculation phase of safety injection, the outside recirculation spray pumps may be manually aligned to provide containment sump water to the high head safety injection pumps. The water is injected into the reactor coolant system for core cooling. The outside recirculation spray pumps are used in this application only when the low head safety injection pumps are unavailable.
COMPONENT DESCRIPTION The four recirculation spray pumps receive their suction supply from the containment sump. Two pumps are located inside containment and two pumps are located outside containment. The water from the sump is recirculated through recirculation spray coolers where it is cooled by the river water system. The cooled water is then used to spray the containment via four recirculation spray headers and the cycle repeats itself for an extended period after the design basis accident.
The piping configuration for the inside recirculation spray pumps (1 RS-P-1A and 1 B) consists of the pumps receiving suction directly from the containment sump and discharging via ten-inch lines to the recirculation spray coolers. From the coolers, the water flows to the containment spray headers via 12-inch lines. The pump discharge piping is provided with a four-inch recirculation test line which returns flow to the containment sump and is utilized only during pump testing. Locked shut manual isolation

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 86 of 320 PUMP RELIEF REQUEST 11 Component/System           valves normally isolate the non-Code four-inch recirculation test line. A Function: (Cont.)          spectacle flange is provided in the pump discharge piping to isolate flow to the spray headers during pump testing.
The piping configuration for the outside recirculation spray pumps (1 RS-P-2A and 2B) is similar to that of the inside recirculation spray pumps.
However, the outside recirculation spray pumps receive their suction from a pump pit, which is provided inventory from 12-inch cross connect lines from the containment sump. The pumps' suction is located below the level of the containment sump. The cross-connect/suction and discharge lines are provided with normally open motor operated valves, which receive an automatic signal to open upon generation of a CIB. In addition, a spectacle flange is provided in the pump discharge piping, which is used to isolate flow to the spray headers during pump testing.
The pumps' discharge piping is provided with a six-inch branch connection to the high head safety injection pump suction. To facilitate pump testing, provisions exist for recirculation from the outside recirculation spray pumps discharge to the pump casing. A local flow indicator (FI-1 RS-1 57A, B) is provided in the four-inch recirculation line.
When testing the pumps with water the associated spectacle flange must be rotated, the suction and discharge isolation valves closed, and the pump filled with an external supply of primary grade water.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code            ISTB-31 00, "Preservice Testing", Paragraph ISTB-31 00(b) requires Requirement(s):            preservice testing of vertical line shaft pumps to be performed in accordance with ISTB-521 0, "Preservice Testing". Paragraph ISTB-5210(a) states that in systems where resistance can be varied, flow rate and differential pressure shall be measured at a minimum of 5 points. If practicable, these points shall be from pump minimum flow to at least pump design flow. A pump curve shall be established based on the measured points. At least one point(s) shall be designated as the reference point(s).
ISTB-3300, "Reference Values", Paragraph ISTB-3300(e)(1) requires reference values to be established within +/-20% of pump design flow rate for the comprehensive test.
ISTB-3430, "Pumps Lacking Required Fluid Inventory" requires Group B pumps lacking required fluid inventory (e.g. pumps in dry sumps) to receive a comprehensive test at least once every 2 years except as provided in ISTB-3420, "Pumps in Systems Out of Service". The required fluid inventory shall be provided during this test. A Group B test is not required.

Beaver Valley Power Station                         Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 87 of 320 PUMP RELIEF REQUEST 11 Reason for Request:        Due to the restrictions associated with the existing piping configuration,
                             +/-20 percent of the design flow rate cannot be achieved through the four-inch recirculation test line for either set of pumps. Refer to Attachment 1 for a simple diagram of the inside and outside recirculation spray pump test circuits.
Prior to initial startup, the inside and outside recirculation spray pumps for Unit No. 1 were subject to long term full flow testing. This testing was performed in 1972 as follows:
: a. With the nozzle openings blocked off (195 per header), temporary connections were made between the nozzle headers and containment sumps.
: b. Sufficient water was then added to the containment sump so that a recirculation spray pump could recirculate water up through its respective cooler and header.
: c. The full flow test through the shell side of the cooler initially ensured that the required recirculation spray for containment depressurization was achieved.
: d. Upon completion of the above system test, the water was drained from each recirculation cooler, the pumps, the headers and the sumps. The temporary connections between the header and sumps were removed and the nozzles installed.
Since the system was left in a dry, ready condition after the initial full flow tests, no further testing with water flow through the shell side of the recirculation spray heat exchangers is deemed necessary to ensure system capability. Further, the spray nozzles are inaccessible without a significant amount of scaffolding. Even if accessibility was not a concern, the plugging of 780 spray nozzles, the installation of temporary piping, the performance of the full flow test and the return of the system to its operable configuration present substantial challenges. The effort would present challenges in terms of complexity of the temporary modifications, labor intensive nature of the modifications, the controls and post modification testing to ensure that the system is returned to the original configuration.
Re-establishing this full flow test circuit for the purpose of periodic design flow rate testing would require a similar modification every two years.
The expensive and time consuming temporary changes described above would be necessary to duplicate the initial full flow tests, and would cause a hardship without a compensating increase in the level of quality and safety. Likewise, replacement of the four-inch recirculation test line with a line of sufficient size to accommodate design flow rate testing would cause a hardship without a compensating increase in the level of quality and safety.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 88 of 320 PUMP RELIEF REQUEST 11 Proposed Alternative      PROPOSED ALTERNATIVE and Basis for Use:
As an alternative to measuring at least five points for the preservice test over a range from pump minimum flow rate to at least pump design flow rate as required by ISTB-3100(b) and ISTB5210(a), the five points will be obtained within approximately 41 percent of the design flow rate and within approximately 38 to 40 percent of the maximum required accident flow rates. Should a baseline curve be required, the manufacturers curve would be used in conjunction with the pump minimum operating point curves and the points obtained would be reconciled to the manufacturers curve to provide assurance of acceptable pump operation.
The proposed alternative to ISTB-3100(b) and ISTB-5210(a) provides an acceptable level of quality and safety.
As an alternative to testing within 20 percent of the design flow rate during the comprehensive test, as required by ISTB-3300(e)(1) and ISTB-3430, the reference values will be established within approximately 41 percent of the design flow rate (3500 gpm) and within approximately 38 to 40 percent of the maximum required accident flow rates.
The proposed alternative to the requirements specified in ISTB-3300(e)(1) and ISTB-3430 provides an acceptable level of quality and safety and would provide reasonable assurance that the pump would be able to perform its function as well as providing sufficient indication of any potential degradation occurring to the pumps.
Testing will be conducted as follows:
The test circuits identified in Attachment 1 will be used to satisfy preservice testing requirements.
The inside recirculation spray pumps shall have a dike constructed in the containment sump encompassing the pump suction and four-inch recirculation test line return. Sufficient inventory will be provided to establish stable flow conditions through the four-inch recirculation test line. Temporary test instrumentation, of required accuracy, shall be installed as required, in the pump test circuit.
The outside recirculation spray pumps shall be tested by establishing the hydraulic test circuit in a solid condition. Flow shall be recirculated through the pump casing while measuring flow with flow indication provided in the four-inch recirculation test line. Temporary pressure instrumentation shall be utilized at the pumps' suction.
Pump vibration will be measured and recorded in accordance with the criteria specified in the Code. In addition, vibration spectral analysis will also be performed which is a more accurate method of detecting mechanical degradation or changes than that of the traditional inservice test vibration requirements.

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 89 of 320 PUMP RELIEF REQUEST 11 Proposed Alternative       BASIS FOR USE and Basis for Use:
(Cont.)                   The inside and outside recirculation spray pumps have a design flow rate of 3500 gpm with varying maximum required accident flow rates. The table below shows the maximum required accident flow rates for each pump and the range of values within which test flows are established.
The minimum test flow rate for recirculation spray pump 1R-P-1A is 38 percent less than the maximum required accident flow rate of 3320 gpm.
This percentage of the maximum required accident flow rate is specified for recirculation spray pump 1R-P-1A and the other recirculation spray pumps in the table below.
Percent of Pump ID Accident Flow              Test Flow       Accident Flow 1RS-P-1A        3320 gpm         2050-2075 gpm           -38 %
1RS-P-1 B       3370 gpm         2050-2075 gpm           -39 %
1RS-P-2A        3385 gpm         2040-2060 gpm           -40 %
1RS-P-2B        3340 gpm         2040-2060 gpm           -39 %
Presently the inservice test reference flow rates are typically established with the existing test circuit in the range of 2040 to 2075 gpm. The low reference flow rates result from restrictions due to the small four-inch recirculation line and the limited volume of water in the test circuit.
With the restrictions described, the highest flow rate that can be measured while maintaining stable test conditions is within approximately 41 percent of the 3500 gpm design flow rate and within approximately 38 to 40 percent of the maximum required accident flow rates.
In the 2040 to 2075 gpm range of the head curve for these pumps, the curve is not flat but well sloped. Refer to Attachment 2. Therefore, as performance degrades due to internal recirculation caused by increasing internal pump clearances, the differential pressure will measurably decrease for a given reference flow rate.
To be within 20 percent of pump design flow rate on the low end requires a minimum reference flow rate of 2800 gpm. To be within 20 percent of the maximum required accident flow rate on the low end would require minimum reference flow rates ranging from 2656 to 2708 gpm, depending on the pump being tested. For the reasons previously stated, reference flow rates are procedurally controlled within a range of 2040 to 2075 gpm, which is not within the 20 percent of the design flow rate required during the comprehensive test.
Testing at near design flow rate conditions is important for pumps with characteristic head-flow curves that are flat or gently sloping in the low flow region (little change in developed head with increasing flow rate). In the low flow region, increasing internal flow rates, as a result of internal wear, are difficult to detect. Pumps with the flat portion of the curve at low flow rates should be tested at or near design conditions to determine if

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 90 of 320 PUMP RELIEF REQUEST 11 Proposed Alternative      increasing internal recirculation flow rates have degraded pump and Basis for Use:        performance to the point where design performance cannot be met. This (Cont.)                   situation does not apply to the inside and outside recirculation spray pumps if they are tested within approximately 41 percent of the design flow rate when considering the slope of the curve. Testing at the proposed reference flow rates will detect degradation since the pump head-curve is well sloped at the point of testing.
OTHER CONSIDERATIONS In addition to the aforementioned tests, the inside and outside recirculation spray pumps are included in the Beaver Valley Predictive Maintenance (PdM) Program. All pumps have spectral vibration data obtained each refueling outage. The outside recirculation spray pumps are subject to periodic oil sample analysis. The bearings associated with the inside recirculation spray pumps are grease lubricated. These activities are beyond that required by ISTB and further provide assurance as to the ability to detect pump degradation. Also, as a preventive maintenance activity, the pumps' mechanical seals are replaced every seventh refueling outage.
If measured parameters are outside the normal operating range or are determined by analysis to be trending towards a degraded state, appropriate actions are taken. These actions may include monitoring of additional parameters, review of component specific information to identify cause and removal of the pump from service to perform corrective maintenance.
Historically, the pumps have demonstrated excellent performance during surveillance testing. The only corrective maintenance recorded for the pumps was associated with inside recirculation spray pump [1 RS-P-1A].
As a result of a failed surveillance test on March 23, 2000, during the thirteenth maintenance and refueling outage, the pump was disassembled for inspection and overhaul. A piece of lumber was found lodged in the pump impeller. The resulting Condition Report determined that the wood had been left in the pump suction since initial startup and became unlodged during the surveillance test. A post-maintenance test was performed and acceptable results were obtained on March 31, 2000.
Additional corrective maintenance for [1 RS-P-1A] includes the repair of pump seal leakage detected during surveillance testing performed in 1993.
Following impeller replacement on March 31, 2000, a five point pump curve was obtained between 1376 gpm and 2077 gpm. Although the new pump curve was below the manufacturer's curve, it generally followed the shape of the manufacturer's curve. Based on this, it was expected that the new pump's performance would continue to follow the shape of the manufacturer's curve at higher flows and also provide adequate margin above the MOP Curve at higher flows. Pump operation since the new impeller was installed has continued to be satisfactory at its tested flow rate of approximately 2050 gpm.

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 91 of 320 PUMP RELIEF REQUEST 11 Proposed Alternative      CONCLUSION and Basis for Use:
(Cont.)                   Compliance with the specific ISTB Code requirements identified in this relief request would require hardware changes and cause a hardship without a compensating increase in the level of quality and safety as previously described. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the fourth 10-year inservice test interval at BVPS Unit No. 1.
Precedents:               The precedents cited below are cases where other plants have submitted relief requests that were granted. The FirstEnergy Nuclear Operating Company relief request is similar to these precedents, and the precedents support the position that the proposed alternative is acceptable.
: 1. Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339. SER date January 28, 2002. North Anna Power Station, Units 1 and 2. Re: Inservice Testing for Pumps and Valves, Third Ten Year Interval Update (TAC Nos. MB2221 and MB2222)
: 2. Seabrook Station, Unit No. 1, Docket No. 50-443, - Relief from ASME Code Operations and Maintenance Code ISTB 4.3(e)(1)
Ten-Year Interval Inservice Test for Containment Spray Pumps CBS-P9A and CBS-P9B (TAC No. MB6676)

==References:==
NUREG-1482, Revision 1, Section 5.10, "Alternative to ASME OM Code Comprehensive Pump

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 92 of 320 PUMP RELIEF REQUEST 11 ATTACHMENT 1 INSIDE RECIRCULATION SPRAY PUMP TEST CIRCUIT Inside Recirculation Spray Pump [I RS-P-1A, 1B] Test Circuit Ten-inch Discharge Ten -inch Discharge                          to Spray Headers to Spray Headers                                             Spectce Flange Spcctacic Flange

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                   Page 93 of 320 PUMP RELIEF REQUEST 11 ATTACHMENT I OUTSIDE RECIRCULATION SPRAY PUMP TEST CIRCUIT Outside Recirculation Spray Pump [1RS-P-2A, 2B] Test Circuit Ten- inih Disvhargc Unc 07)0 MOV 155A (155B)

Beaver Valley Power Station                           Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                           Page 94 of 320 PUMP RELIEF REQUEST 11 ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 1A Inside Recirculation Spray Pump Pump Number: [1RS-P-1A]
[1RS-P-1A]
Manufacturer, 3/31/00 Tested, and MOP Curves 360.0 320.0       "
280.0 cc 240.0---
200.0-160.0 120.0 1500          2000      2500         3000       3500      4000 Flow (gpm) 3/31/00                     Manufacturer's   MOP Flow          Pump Curve          Flow         Curve Head     Curve Head                                        Head 1376              322.0           1500             329.2      306.9 1579              317.4           1750             321.0      299.3 1889              303.5          2000              312.7      291.7 2065               300.1          2050              311.0      290.2 2077               297.7          2250              304.0      283.7 2500              294.6      275.0 2750              284.2      264.2 3000              272.4      251.0 3180              263.0      241.4 3250              259.1      237.0 3500              243.8      220.0 3750              226.3      198.2 4000              206.2      173.0

Beaver Valley Power Station                    Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                            Page 95 of 320 PUMP RELIEF REQUEST 1_
ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 1B Inside Recirculation Spray Pump Pump Number: [1RS-P-1B]
[1RS-P-1 B]
Manufacturer and MOP Curves 360.0 320.0.
280.0--
240.0 200.0 160.0 120.0 1500     2000       2500         3000       3500 4000 Flow (gpm)
Manufacturer's       MOP Flow      Curve Head          Curve Head 1500          332.8           306.9 1750          324.8           299.3 2000          316.6           291.7 2050          314.9           290.2 2250          308.0           283.7 2500          298.7           275.0 2750          288.6           264.2 3000          277.5           251.0 3180          268.6           241.4 3250          265.0           237.0 3500          251.0           220.0 3750          235.3           198.2 4000          217.7           173.0

Beaver Valley Power Station                    Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                             Page 96 of 320 PUMP RELIEF REQUEST 11 ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 2A Outside Recirculation Spray PumpPump Number: [1RS-P-2A]
[1 RS-P-2A]
Manufacturer and MOP Curves 400.0 360.0 320.0 280.0                                      0 240.0 200.0-160.0 120.0 1500     2000       2500         3000        3500 4000 Flow (gpm)
Manufacturer's        MOP Flow      Curve Head          Curve Head 1500          345.1            323.7 1750          336.2            314.6 2000          327.0            305.2 2040          325.5            303.6 2050          325.2           303.2 2250          317.5           295.3 2500          307.4           285.0 2750          296.6           273.3 3000          284.9           260.0 3165          276.6           251.7 3250          272.1           246.8 3500          258.0           232.0 3750          242.4           214.3 4000          225.1            195.0

Beaver Valley Power Station                   Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                            Page 97 of 320 PUMP RELIEF REQUEST 11 ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 2B Outside Recirculation Spray Pump, Pump Number: [1RS-P-2B]
[I RS-P-2B]
Manufacturer and MOP Curves 400.0 360.0 320.0
: 280.0 -
240.0 200.0 160.0 120.0 1500    2000      2500        3000       3500   4000 Flow (gpm)
Flow    Manufacturer's      MOP Curve Head        Curve Head 1500         345.1          323.7 1750         336.2          314.6 2000         327.2          305.2 2040         325.7          303.6 2050         325.4          303.2 2250         317.9          295.3 2500         308.0          285.0 2750         297.4          273.3 3000         285.8          260.0 3165         277.6          251.7 3250         273.1          246.8 3500         259.1          232.0 3750         243.5          214.3 4000         226.1          195.0

Beaver Valley Power Station                         Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                          Page 98 of 320 PUMP RELIEF REQUEST 12 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
On the basis that compliance with certain Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Component(s)                 1QS-P-1A; Quench Spray Pump, (Class 2)
Affected:                    1QS-P-1B; Quench Spray Pump, (Class 2)
Component/System            The quench spray system at the Beaver Valley Power Station Unit No. 1 is Function:                   designed to provide cold water from the refueling water storage tank (RWST) after a Containment Isolation Phase B (CIB) signal, chemically treat the water and spray containment. This function is required during post accident conditions for heat removal to reduce containment pressure.
Containment depressurization is required to eliminate leakage out of containment after a CIB and to ensure containment integrity. The quench spray flow is treated with sodium hydroxide (NaOH) to improve removal of radioactive iodine from the containment atmosphere and to control containment sump pH. The system is provided with two 100 percent capacity redundant trains, each having a design discharge capacity of 2500 gpm. The quench spray pumps are manually stopped when the RWST water level drops below a predetermined level to prevent cavitation.
Subsequent to stopping the quench spray pumps, recirculation spray pumps will continue spray flow to the containment.
The piping configuration for the quench spray pumps (1QS-P-1A and 1B) consists of the pumps receiving suction from the RWST and discharging to the containment through ten-inch lines supplying the quench spray headers. The pumps discharge piping is provided with four-inch recirculation test lines, which by design, are provided for intermittent testing of the quench spray pumps.
Flow testing is performed by opening the locked shut manual isolation valves in the test line thereby allowing a recirculation flow path back to the RWST. Flow instrument FI-1QS-103 is provided in the four-inch recirculation test line and flow instrument FI-1 QS-1 04 is provided in the 1.5-inch branch connection off the four-inch recirculation test line. The 1.5-inch branch connection serves as the RWST test spray header.
The combination of local flow instrumentation provides the ability to measure total flow through the recirculation test line. During the performance of Group B and Comprehensive pump testing, containment isolation valves MOV-1QS-101A and MOV-IQS-101B (as applicable) are de-energized in the closed position to prevent inadvertent discharge of quench spray flow to the containment via the quench spray headers.
Applicable Code             ASME OM Code-2001 Edition, with Addenda through OMb-2003 Edition and Addenda:

Beaver Valley Power Station                         Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                           Page 99 of 320 PUMP RELIEF REQUEST 12 Applicable Code            ISTB-31 00, "Preservice Testing," Paragraph ISTB-31 00(a) requires Requirement(s):            preservice testing of centrifugal pumps to be performed in accordance with ISTB-51 10, "Preservice Testing." Paragraph ISTB-51 10(a) states that in systems where resistance can be varied, flow rate and differential pressure shall be measured at a minimum of five points. If practicable, these points shall be from the pump minimum flow rate to at least the design flow rate. A pump curve shall be established based on the measured points. At least one point shall be designated as the reference point.
ISTB-3300, "Reference Values," Paragraph ISTB-3300(e)(1) requires reference values to be established within +/-20 percent of pump design flow rate for the comprehensive test.
Reason for Request:        Due to the flow restrictions associated with the existing piping configuration, +20 percent of the 2500 gpm design flow rate cannot be achieved through the four-inch recirculation test line. Refer to Attachment 1 for a simple diagram of the quench spray pump test circuits.
Prior to initial startup, the quench spray pumps for Unit No. 1 were subject to long term full flow testing. Temporary connections were made on the quench spray headers and pipe plugs were placed in the spray nozzle sockets and the header drain lines. The quench spray pumps were started and tested, circulating water through the spray header supply lines to the spray headers and out the temporary test connections. This system capability test was conducted to ensure that the system meets flow requirements. It also provided a complete flush of the system to remove any particulate matter, which could conceivably result in plugging of the spray nozzles at a future time. At the completion of this test, the temporary test connections were removed, the pipe plugs were removed and the spray nozzles were installed. The system was then ready for operation. The spray header piping has no remnants of the temporary test connections used to facilitate preoperational full flow testing.
Re-establishing this full flow test circuit for the purpose of periodic design flow rate testing would require similar modification or replacement of the four-inch recirculation test line with a line of sufficient size to pass +/-20 percent of the 2500 gpm design flow rate or a minimum flow rate of 2000 gpm. Such hardware modifications would cause a hardship without a compensating increase in the level of quality and safety.
PROPOSED ALTERNATIVE As an alternative to measuring at least five points for the preservice test over a range from the pump minimum flow rate to at least the design flow rate as required by ISTB-31 00(a) and ISTB-51 10(a), the five points will be obtained over the range of 0 gpm to approximately 1750 gpm. The manufacturer's curve would be used in conjunction with the pump

Beaver Valley Power Station                        Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 100 of 320 PUMP RELIEF REQUEST 12 Proposed Alternative      minimum operating point curve and the points obtained would be and Basis for Use:        reconciled to the manufacturer's curve to provide assurance of acceptable pump operation. Refer to Attachment 2 for pump curves. The proposed alternative to ISTB-31 00(a) and ISTB-51 10(a) provides an acceptable level of quality and safety.
As an alternative to testing within 20 percent of the design flow rate during the comprehensive test, as required by ISTB-3300(e)(1), the reference values will be established at approximately 30 percent of the design flow rate (that is, approximately 1750 gpm). The proposed alternative to the requirements specified in ISTB-3300(e)(1) provides an acceptable level of quality and safety and provides reasonable assurance that the pumps would be able to perform their function as well as providing sufficient indication of any potential degradation occurring to the pumps.
Testing will be conducted as follows:
The test circuits identified in Attachment 1 will be used to satisfy testing requirements.
The quench spray pumps shall be tested by establishing a recirculation flow path back to the RWST via the four-inch recirculation test line.
Temporary pressure instrumentation shall be utilized in the pump suction with sufficient calibrated accuracy to satisfy ASME OM Code requirements. Differential pressure will be fixed and flow measured.
Pump vibration will be measured and recorded in accordance with the criteria specified in the Code. In addition, vibration spectral analysis will also be performed which is a more accurate method of detecting mechanical degradation or changes than that of the traditional inservice test vibration requirements.
BASIS FOR USE To be within 20 percent of pump design flow rate on the low end requires a minimum reference flow rate of 2000 gpm. Presently the inservice test reference flow rates are established with the existing test circuit at approximately 1750 gpm, when setting differential pressure as the fixed reference value.                                     I Reference flow rates are not within the 20 percent of design flow rate required during the comprehensive test. The test flows are lower than the design flow rate as a result of restrictions due to the small four-inch recirculation line. With the recirculation line restrictions, the highest flow rate that can be measured (approximately 1750 gpm) while maintaining stable test conditions is within approximately 30 percent of the pump design flow rate.

Beaver Valley Power Station                        Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                       Page 101 of 320 PUMP RELIEF REQUEST 12 Proposed Alternative      At approximately 1750 gpm, the head curve for these pumps is not flat and Basis for Use:        but well sloped (See Attachment 2). Therefore, as performance degrades (Cont.)                   due to internal recirculation caused by increasing internal pump clearances, the flow rate will measurably decrease for a given reference differential pressure.
Testing at near design flow rate conditions is important for pumps with characteristic head-flow curves that are flat or gently sloping in the low flow region (little change in developed head with increasing flow rate). In the low flow region, increasing internal flows, as a result of internal wear, are difficult to detect. Pumps with the flat portion of the curve at low flow rates should be tested at or near design conditions to determine if increasing internal recirculation flows have degraded pump performance to the point where design performance cannot be achieved. This situation does not apply to the quench spray pumps if they are tested within approximately 30 percent of the design flow rate. Testing at the proposed reference flow rates will detect degradation since the pump head-curve is well sloped at the point of testing.
OTHER CONSIDERATIONS In addition to the aforementioned tests, the quench spray pumps are included in the Beaver Valley Predictive Maintenance (PdM) Program. All pumps have spectral vibration data obtained each refueling outage and are subject to periodic oil sample analysis. Also, as a preventive maintenance activity, the pumps' mechanical seals are replaced every seventh refueling outage and the pump bearing oil is changed and coupling lubricated every 72 weeks.
If measured parameters are outside the normal operating range or are determined by analysis to be trending towards a degraded state, appropriate actions are taken. These actions may include monitoring additional parameters, review of component specific information to identify cause and removal of the pump from service to perform corrective maintenance.
Historically, the pumps have demonstrated excellent performance during surveillance testing. The only corrective maintenance recorded for the pumps was associated with quench spray pump 1QS-P-1A. Subsequent to the tenth maintenance and refueling outage (in 1995), pump 1QS-P-1A was damaged due to air binding and the rotating element assembly (that is, the impeller) was replaced. The replacement impeller was 10.75 inches in diameter. It was determined that the 10.75-inch impeller was the wrong size since the damaged impeller was 9.85 inches in diameter. The larger impeller resulted in a seven percent increase in the hydraulic data. A successful containment analysis of the DBA conditions with the 10.75-inch pump impeller required that the recirculation spray heat exchanger tube plugging limits be changed from the initial plugging limit of 56 tubes to 20 tubes. In 2001, the recirculation spray heat exchangers had 12 tubes

Beaver Valley Power Station                       Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                      Page 102 of 320 PUMP RELIEF REQUEST 12 Proposed Alternative      plugged resulting in an eight-tube margin. Therefore, the System and Basis for Use:        Engineering group recommended replacement of the 10.75-inch impeller (Cont.)                   with a 9.85-inch impeller during fourteenth maintenance and refueling outage (in 2001). Impeller replacement was completed on October 1, 2001 and a five point pump curve was obtained between 600 gpm and 1797 gpm. Although the new pump curve was slightly below the manufacturer's curve, it generally followed the shape of the manufacturer's curve. Based on this, it was expected that the new pump's performance would continue to follow the shape of the manufacturer's curve at higher flows and also provide adequate margin above the MOP Curve at higher flows. Pump operation since the new impeller was installed has continued to be satisfactory at its tested flow rate of approximately 1750 gpm.
CONCLUSION Compliance with the specific ISTB Code requirements identified in this relief request would require hardware changes and cause a hardship without a compensating increase in the level of quality and safety as previously described. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the fourth ten-year inservice test interval at Beaver Valley Power Station Unit No. 1.
Precedents:               The precedents cited below are cases where other plants have submitted relief requests that were granted. The FirstEnergy Nuclear Operating Company relief request is similar to these precedents, and the precedents support the position that the proposed alternative is acceptable.
: 1. North Anna Power Station, Unit Nos. 1 and 2, Docket Nos. 50-338 and 50-339, Inservice Testing for Pumps and Valves, Third Ten Year Interval Update (TAC Nos. MB2221 and MB2222), dated January 28, 2002.
: 2. Seabrook Station, Unit No. 1, Docket No. 50-443, Relief from ASME Code Operations and Maintenance Code ISTB 4.3(e)(1)
Ten-Year Interval Inservice Test for Containment Spray Pumps CBS-P9A and CBS-P9B (TAC No. MB6676), dated May 30, 2003.

==References:==
NUREG-1482, Revision 1, Section 5.10, "Alternative to ASME OM Code Comprehensive Pump Testing Requirements."

Beaver Valley Power Station                      Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                              Page 103 of 320 PUMP RELIEF REQUEST 12 ATTACHMENT 1 QUENCH SPRAY PUMPS TEST CIRCUIT Quench Spray Pump [IQS-P-IA, IB] Test Circuit FI.IQS-104 nI-               .- nhRS From Chemical InjetOun Pumps

Beaver Valley Power Station                      Unit I Issue 3 Revision 19 Inservice Testing (1ST) Program For Pumps And Valves                               Page 104 of 320 PUMP RELIEF REQUEST 12 ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 1A Quench Spray Pump                Pump Number: 1QS-P-1A Manufacturer's Curve         MOP Curve Flow         Head       Flow      Head 0           414         0        395 803          384        800       375 1522          357       1330       348 2119          310       1630       327 2516          270       1712       321 2597          261       1730       320 2769          240       1830       312 3222          191       1930       303 2030      294 Tested Curve  (10/1101)   2230      275 Flow         Head       2330      265 600         389.0      2430      254 800         382.1      2530      243 1200         366.1      2630      232 1600         343.1      2730      220 1797         327.6      2893      200

Beaver Valley Power Station                             Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                         Page 105 of 320 PUMP RELIEF REQUEST 12 ATTACHMENT 2 MANUFACTURER'S AND PUMP MINIMUM OPERATING POINT (MOP) CURVES Pump Name: 1B Quench Spray Pump                        Pump Number: 1QS-P-1B
[IQS-P-1 B]
Manufacturer and MOP Curves 420      . . . . ..         . .. . .      . .   . . .
380 340   .-
S300-260.
220-180.
0          500      1000        1500       2000     2500  3000 Flow (gpm)
Manufacturers Curve               MOP Curve Flow          Head         Flow      Head 0            413           0        395 866            388          800       375 1527            359         1330       348 2141            316         1630       327 2496            279         1700       322 2597            268         1730       320 2769            246         1830       312 3181            199         1930       303 2030       294 2230       275 2330       265 2430       254 2530       243 2630       232 2730       220 2893      200

Beaver Valley Power Station                         Unit 1 Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                        Page 106 of 320 PUMP RELIEF REQUEST 13 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.
AND Proposed Alternative In Accordance with 10CFR50.55a(a)(3)(ii)
On the basis that compliance with the Code requirement would result in hardship and unusual difficulty without a compensating increase in the level of quality and safety.
Component(s)                1WR-P-1A, River Water Pump (Class 3)
Affected:                   1WR-P-1 B, River Water Pump (Class 3) 1WR-P-1C, River Water Pump (Class 3)
Component/System           The River Water Pumps operate continuously during normal plant Function:                  operation to supply cooling water to non-essential heat loads. During post accident conditions they provide the heat sink to the following components:
recirculation spray heat exchangers, charging pump lube oil coolers, control room river water cooling coil and emergency diesel generator cooling system heat exchanger.
Applicable Code            ASME OM Code-2001 Edition, with Addenda through OMb-2003 Edition and Addenda:
Applicable Code             ISTB-3510(a), "Data Collection; General Accuracy", states; Instrument Requirement(s):            accuracy shall be within the limits of Table ISTB-3500-1. If the parameter is determined by analytical methods instead of measurement, then the determination shall meet the parameter accuracy requirement of Table ISTB-3500-1. For individual analog instruments, the required accuracy is percent of full scale. For digital instruments, the required accuracy is over the calibrated range. For a combination of instruments, the required accuracy is loop accuracy.
Table ISTC-3500-1, "Required Instrument Accuracy" requires pressure instruments to be calibrated to at least 0.5 percent when used during the Comprehensive Pump test.
Reason for Request:        The BVPS-1 River Water Pumps are vertical line-shaft pumps that receive their suction from a pit that communicates with the Ohio river. Differential pressure is calculated using Pump Discharge Pressure Indicator [PI-1WR-101A, B and C] and the calculated suction pressure using river water elevation from Ohio River Level Recorder [LR-1CW-101], local. The transmitter associated with [LR-1 CW-1 01] is calibrated to 1.5% of full scale and the recorder is calibrated to 1.0% of full scale resulting in a loop accuracy of 1.8% of full scale. The overall loop accuracy is greater than the 0.5% required by Table ISTC-3500-1 when performing a Comprehensive or Preservice test. Replacing [LR-1CW-101] with level indication calibrated to 0.5% is considered a hardship or unusual difficulty without a compensating increase in the level of quality or safety.

Beaver Valley Power Station                       Unit I Issue 3 Revision 19 Inservice Testing (IST) Program For Pumps And Valves                                      Page 107 of 320 PUMP RELIEF REQUEST 13 Reason for Request:       Typical Ohio River elevation is between 665 and 667 feet resulting in a (Cont.)                   small variance between calculated suction pressure when determined by the calculational method provided by the procedure. However, it should be noted that during the spring, river elevations may be higher due to rain.
This condition is evaluated with the test results to ensure operational readiness of the pumps.
Proposed Alternative      BVPS-1 proposes to use existing level instrumentation when determining and Basis for Use:        differential pressure during Comprehensive and Preservice testing, with a calibrated loop accuracy of 1.80% full scale, in lieu of replacing existing instrumentation to satisfy the 0.5% accuracy requirement for pressure instrumentation, as specified in Table ISTC-3500-1. BVPS-1 considers the level of accuracy of existing instrumentation sufficient for determining pump operational readiness and provides an acceptable level of quality and safety.
Other activities are implemented at BVPS-1, in addition to those required by the ASME OM Code that enhances the ability to detect pump degradation. As part of the BVPS-1 Predictive Maintenance Program, spectral analysis may be used to determine the mechanical condition of a pump. Spectral data can provide information to determine if misalignment, unbalance, resonance, looseness or a bearing problem is present.
Through a review of the spectral data over a period of time, any change in condition of the pump may also be determined. Additionally, as part of the BVPS-1 Preventive Maintenance Program, the pump motors are inspected, lubricated, and tested every 144 weeks. The pump and motor are completely overhauled every 312 weeks. Motor overhaul includes sending it to the vendor. This frequency is based on the expected condition of the pumps as a result of historical overhauls and was established to allow overhaul prior to the point of degradation resulting in questionable operational readiness.
Using the provisions of this relief request as an alternative to the accuracy requirements of Table ISTB-3500-1, when performing Comprehensive or Preservice tests, provides an acceptable level of quality and safety. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTB Code requirements.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               None

==References:==
ISTB-3510(a), "Data Collection; General Accuracy" Table ISTB-3500-1, "Required Instrument Accuracy" NUREG-1482, Rev.1, Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure".

Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                    Page 108 of 320 SECTION IV:     PUMP MINIMUM OPERATING POINT (MOP) CURVES

Beaver Valley Power Station                                                       Unit I Inservice Testing (IST) Program For Pumps And Valves                                                                                                              Issue 4 Revision 0 Page 109 of 320 Pump Name: Charging/High Head Safety Injection Pumps                                                                                                Pump Number: [1CH-P-1A]
11 CH-P-1 B]
[1 CH-P-1 C]
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Beaver Valley Power Station                                     Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 110 of 320 Pump Name: 2A Boric Acid Transfer Pump                                    Pump Number: [1CH-P-2A]
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Beaver Valley Power Station                             Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                              Page 111 of 320 Pump Name: 2B Boric Acid Transfer Pump                               Pump Number: [1CH-P-2B]
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Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                 Page 112 of 320 Pump Name: 1A Residual Heat Removal Pump                Pump Number: [1RH-P-1A]
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Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                       Page 113 of 320 Pump Name: 1lB Residual Heat Removal Pump                     Pump Number: [1 RH-P-1 B]
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Beaver Valley Power Station                           Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                            Page 114 of 320 Pump Name: Low Head Safety Injection Pumps                            Pump Number: [1SI-P-1A]
[1SI-P-1B]
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Beaver Valley Power Station                   Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                       Page 115 of 320 Pump Name: Quench Spray Pumps                                  Pump Number: [1QS-P-1A]
[1 QS-P-1 B]
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Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                   Page 116 of 320 Pump Name: 1A and 1B Inside Recirculation Spray Pump      Pump Number: [1RS-P-1A]
[1 RS-P-1 B]
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Beaver Valley Power Station                   Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                    Page 117 of 320 Pump Name: 2A and 2B Outside Recirculation Spray Pump      Pump Number: [1RS-P-2A]
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Beaver Valley Power Station                                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                                 Page 118 of 320 Pump Name: 1A Component Cooling Water Pump                                               Pump Number: [1CC-P-1A]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                   Page 119 of 320 Pump Name: 1 B Component Cooling Water Pump             Pump Number: [1CC-P-1B]
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Beaver Valley Power Station                     Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                       Page 120 of 320 Pump Name: 1C Component Cooling Water Pump                      Pump Number: [1CC-P-1C]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                  Page 121 of 320 Pump Name: Turbine Driven Auxiliary Feed Pump                Pump Number: [1FW-P-2]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                       Page 122 of 320 Pump Name: Motor Driven Auxiliary Feed Pump                  Pump Number: [1FW-P-3A]
[1 FW-P-3B]
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Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                      Page 123 of 320 Pump Name: 1A Reactor Plant River Water Pump                  Pump Number: [1WR-P-1A]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves              Page 124 of 320 Pump Name: 1B Reactor Plant River Water Pump          Pump Number: [1WR-P-1B]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                  Page 125 of 320 Pump Name: 1C Reactor Plant River Water Pump        Pump Number: [1WR-P-1C]
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Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                 Page 126 of 320 SECTION V:     VALVE TESTING REQUIREMENTS

Beaver Valley Power Station                           Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 127 of 320 The Inservice Test (IST) Program for valves at Beaver Valley Power Station (BVPS), Unit 1, is based on the following:
             " American Society of Mechanical Engineers (ASME) OM Code-2001 Edition, Code for Operation and Maintenance of Nuclear Plants, with Addenda through OMb-2003."
* Generic Letter No. 89-04, "Guidance on Developing Acceptable Inservice Testing Programs"
             " NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants"
* Technical Specification 5.5.4, "Inservice Testing Program"
* Implementation of ASME OM Code Case OMN-1 in accordance with Corrective Maintenance Procedure (CMP) 1/2-CMP-E-75-021 for rising stem MOVs and 1/2CMP-75-Quarter Turn-I E for butterfly and ball valves. (See Valve Relief Request No. 1, VRR1)
* Implementation of ASME OM Code Case OMN-12 in accordance with Maintenance Instruction (MI) 1/2MI-75-Ultracheck A-1I for all AOVs.
The valves included in this program are all ASME Class 1, 2 or 3 required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident. The pressure-relief devices covered are those for protecting systems or portions of systems which perform one or more of the three aforementioned functions at BVPS-1. Unit 1 was not designed and licensed for a safe shutdown of cold shutdown (Per NUREG-1482, Revision 1, Section 2.2, "Ifthe plant was licensed for a safe shutdown condition of hot standby or hot shutdown rather than cold shutdown, the IST Program document will stipulate that the plant was not designed and licensed for a safe shutdown of cold shutdown"). Although Unit 1 was not designed and licensed for a safe shutdown of cold shutdown, it will generally be treated as such for consistency with BVPS-2.
Category A and B Valves Category A valves are valves for which seat leakage in the closed position is limited to a specific maximum amount for fulfillment of their function. Category B valves are valves for which seat leakage in the closed position is inconsequential for fulfillment of their function.
Active Category A and B valves shall be full-stroke exercised nominally every three months to the position required to fulfill their function unless such operation is not practicable during operation at power. If only limited operation is practicable during operation at power, the valves may be part-stroke exercised during operation at power and full-stroke exercised during cold shutdowns. If exercising is not practicable during operation at power, the valves may be limited to full-stroke exercising during cold shutdowns. Ifexercising is not practicable during operation at power and full-stroke during cold shutdowns is also not practicable, the valves may be limited to part-stroke exercising during cold shutdowns, and full-stroke exercising during refueling outages. If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke exercising during refueling outages. Power-operated relief valves shall be tested once per fuel cycle per ISTC-3510. Exception is taken to part-stroke exercising motor-operated valves, unless specifically stated. This is necessary because the motor-operated valve circuitry prevents throttling of these valves. Under normal operation, the valves must travel to either the full open or shut position prior to reversing direction. In the case of frequent cold shutdowns, these valves need not be exercised more

Beaver Valley Power Station                            Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 128 of 320 often than once every three months. All valve exercising required to be performed during a refueling outage shall be completed prior to returning the plant to operation. For a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within 3 months prior to placing the system in an operable status, the valves shall be exercised and the schedule resumed.
Stroke Time Limits and Testing Requirements for Category A and B Valves The stroke time of all power-operated valves shall be measured to at least the nearest second. Full-stroke time is the time interval from initiation of the actuating signal to the end of the actuating stroke. The time to full-stroke exercise each power-operated valve will be measured and compared to a reference value (baseline time) and an acceptable range and/or an ASME limiting stroke time as follows:
: 1. Motor-operated valves (MOVs) with reference stroke times greater than 10 seconds shall exhibit no more than a +/-15% change in stroke time when compared to the reference time. MOVs with reference stroke times less than or equal to 10 seconds shall exhibit no more than a +/-25% or +/-1 second change in stroke time, whichever is greater, when compared to the reference time.
NOTE:       As an alternative to the requirements of paragraph ISTC-5120 of the ASME OM Code-2001 through OMb-2003, Code Case OMN-1 "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants" provides an alternative to MOV stroke time testing.
BVPS-1 shall adopt the alternative test requirements specified in ASME OM Code Case OMN-1 in lieu of stroke timing certain motor operated valves (MOVs) in accordance with the requirements specified in paragraph ISTC-5120 and position indication testing in accordance with the requirements specified in paragraph ISTC-3700. The BVPS MOV Program satisfies the criteria specified in ASME OM Code Case OMN-1 and the conditional acceptance specified in Reg. Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code". Paragraph 3.6 of OMN-1 requires MOVs to be full stroke exercised (not timed) to the position(s) required to fulfill their function(s) on an interval not to exceed one year or one refueling cycle (which ever is longer). Full stroke exercising is based on the practicality of exercising during power operation, cold shutdown, or refueling. Justification for extended full stroke exercising of ASME OM Code Case OMN-1 scoped MOVs beyond a quarterly frequency are provided in Sections VII and VIII of the BVPS-1 IST Program. Further guidance regarding the use of ASME OM Code Case OMN-1 is provided in NUREG-1482, Revision 1, Section 4.2.5, "Alternatives to Stoke-Time Testing". Refer to Valve Relief Request VRR1 and 1/2-ADM-2049, "MOV Administration Program" for further discussion regarding the implementation of ASME OM Code Case OMN-1.
Implementation of ASME OM Code Case OMN-1 for diagnostic testing and stroke timing of MOVs at increased test intervals shall be performed using Corrective Maintenance Procedure (CMP) 1/2-CMP-E-75-021 for rising stem MOVs and 1/2CMP-75-Quarter Turn-1 E for butterfly and ball valves.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 129 of 320
: 2. All other power-operated valves (TV, HYV, SOV, etc.) with reference stroke times greater than 10 seconds shall exhibit no more than a +/-25% change in stroke time when compared to the reference time. All other power-operated valves with reference stroke times less than or equal to 10 seconds shall exhibit no more than a +/-50% change in stroke time when compared to the reference time.
NOTE:      As an alternative to the requirements of paragraph ISTC 5130 and ISTC-5140 of the ASME OM Code-2001 Edition through OMb-2003 Addenda, Code Case OMN-12 "Alternative Requirements for Inservice Testing Using Risk Insights for Pneumatically and Hydraulically-Operated Valve Assemblies in LWR Power Plants" provides an alternative to AOV and HOV stroke time testing.
BVPS-1 shall adopt the alternative test requirements specified in ASME OM Code Case OMN-12 in lieu of stroke timing certain air operated valves (AOVs) and hydraulic operated valves (HOVs) in accordance with the requirements specified in paragraphs ISTC-5130 and ISTC-5140 and position indication testing in accordance with the requirements specified in paragraph ISTC-3700. The BVPS AOV Program satisfies the criteria specified in ASME OM Code Case OMN-12 and the conditional acceptance specified in Reg. Guide 1.192, "Operation and Maintenance Code Case Acceptability, ASME OM Code". Paragraphs 4.2.3 and 5.5 of OMN-12 require AOVs and HOVs to be exercised through one full stroke (open and closed) once during each fuel cycle of operation based on the practicality of exercising during power operation, cold shutdown, or refueling. Justification for extended full stroke exercising of ASME OM Code Case OMN-12 scoped AOVs and HOVs beyond a quarterly frequency are provided in Sections VII and VIII of the BVPS-1 IST Program. Further guidance regarding the use of ASME OM Code Case OMN-12 is provided in NUREG-1482, Revision 1, Section 4.2.5, "Alternatives to Stoke-Time Testing". Since ASME OM Code Case OMN-12 is approved for use with ASME OM Code-2001 Edition per Reg. Guide 1.192, request for relief to use this Code Case is not necessary. Refer to 1/2-ADM-2029, "Air Operated Valve Program" for further discussion regarding the implementation of ASME OM Code Case OMN-12.
Implementation of ASME OM Code Case OMN-12 shall be in accordance with Maintenance Instruction (MI) 1/2MI-75-Ultracheck A-1I for all AOVs.
: 3. Valves that stroke in less than 2 seconds may be exempted from 1 and 2 above, in such cases the maximum limiting stroke time shall be 2.0 seconds.
: 4. The limiting value of full-stroke time is based on the following:
: a. The Technical Specification or License Requirements Manual value.
: b. Containment isolation or ESF response time requirements.
: c. The reference stroke time times 2 for valves with reference stroke times less than or equal to 10 seconds.
: d. The reference stroke time times 1.5 for valves with reference stroke times greater than 10 seconds.
: e. The design time listed in UFSAR.

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 130 of 320 A limiting value of full-stroke time is the calculated maximum allowable valve stroke time limit established to assure that corrective action is taken on a degraded valve before it reaches the point where there is a high probability of failure to perform its safety function if called upon. If a design, Technical Specification, UFSAR, or accident analysis limit exists which is more limiting, then it shall be used as the limiting value of full-stroke time in lieu of the calculated value.
: 5. Since valves included in OMN-1 are not required to follow the stroke time requirements of ISTC-5120, stroke timing to the position(s) required to fulfill their function(s) will only be performed during diagnostic testing. The stroke times during diagnostic testing will only be compared to a reference value and a limiting value of full-stroke time for trending purposes. Acceptable Range limits specified in ISTC-5122 are not required to be used.
: 6. Since valves included in OMN-12 are not required to follow the stroke time requirements of ISTC-5130 and ISTC-5140, stroke timing will only be performed during diagnostic testing. The stroke times during diagnostic testing will only be compared to a reference value and a limiting value of full-stroke time for trending purposes.
Acceptable Range limits specified in ISTC-5132 and ISTC-5142 are not required to be used.
The necessary valve disk movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights which signal the required change of disk position, or by observing other evidence, such as changes in system pressure, flow rate, level, or temperature, which reflect disk position. Control Room position indicating lights (or arrows for modulating valves) are used for valve stroke indication for all testing of power-operated valves with remote position indicators on the Control Board. In addition, valves with remote position indicators will be observed locally at least once every 2 years (except where extended per OMN-1 or OMN-12) to verify that valve operation is accurately indicated in the direction required to fulfill its function. Where practicable, this local observation may be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify disk position. However, these observations need not be concurrent. Where local observation is not possible other indications shall be used for verification of valve operation.
Fail-Safe Testing for Category A and B Valves Fail-safe valves are valves equipped with fail-safe actuators that are required to move to a position to fulfill the intended safety function upon a loss of actuating power (typically instrument air and/or electrical control power). All valves with fail-safe actuators (e.g.,
solenoid operated valves, air operated valves or air operated control valves) shall be tested by observing the operation of the actuator upon loss of valve actuating power.
Solenoid operated valves (SOVs) are tested from the Control Room by their remote operating (control) switch. Placing the control switch to the fail-safe position de-energizes the solenoid thus positioning the valve in the fail-safe position. Air operated trip valves (TVs) are tested from the Control Room by their remote operating (control) switch. Placing the control switch to the fail-safe position de-energizes the control power to the solenoid which vents air from the valve actuator thus positioning the valve in the fail-safe position.
Air operated control valves may be tested in a similar fashion, or the valve actuating power (e.g., electrical or air supply) may be removed to position the valve in the fail-safe position.

Beaver Valley Power Station                           Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 131 of 320 Corrective Actions for Category A and B Valves Corrective action shall be taken if necessary, using the following:
: 1. If a valve fails to exhibit the required change of valve disk position or exceeds its specified ASME OM Code limiting value of full-stroke time, then the valve shall be declared inoperable immediately. An evaluation of the valve's condition with respect to system operability and technical specifications shall be made as follows:
: a. If the inoperable valve is specifically identified in the technical specifications, then the applicable technical specification required action statements shall be followed.
: b. If the inoperable valve is in a system covered by a technical specification, an assessment of its condition shall be made to determine if it makes the system inoperable. If the condition of the valve renders the system inoperable, then the applicable system technical specification required action statements shall be followed.
: c. Nothing in the ASME OM Code shall be construed to supersede the requirements of any technical specification.
: 2. Valves with measured stroke times which do not meet the acceptance criteria specified in Paragraphs ISTC-5122 (MOVs), ISTC-5132 (AOVs), ISTC-5142 (HOVs), ISTC-5152 (SOVs), or ISTC-5114 (PORVs) (i.e., % change when compared to the baseline time) shall be immediately retested or declared inoperable as follows:
: a. If the valve is retested and the second set of data meets the acceptance criteria, the cause of the initial deviation shall be analyzed and the results documented in the test.
: b. If the valve is retested and the second set of data also does not meet the acceptance criteria, the data shall be analyzed within 96 hours to verify that the new stroke time represents acceptable valve operation, or the valve shall be declared inoperable. Valve operability based on analysis shall have the results of the analysis documented in the test.
: 3. Valves declared inoperable may be repaired, replaced, or the data may be analyzed to determine the cause of the deviation and the valve shown to be operating acceptably.
Valve operability based on analysis shall have the results of the analysis documented in the test.
: 4. When a valve or its control system has been replaced, repaired or has undergone maintenance that could affect the valve's performance, a new reference value shall be determined or the previous value reconfirmed by an inservice test run prior to the time it is returned to service or immediately if not removed from service, to demonstrate that the performance parameters which could be affected by the replacement, repair or maintenance are within acceptable limits. Deviations between the previous and new reference values shall be identified and analyzed. Verification that the new values represent acceptable operation shall be documented in the test. Examples of maintenance that could affect valve performance parameters are adjustment of stem packing, limit switches, or control system valves, and removal of the bonnet, stem assembly, actuator, obturator, or control system components.

Beaver Valley Power Station                          Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 132 of 320 Manual Valves Although ISTC-3540 permits manual valves to be full-stroke exercised at least once every 5 years; pursuant to 10 CFR 50.55a(b)(3)(vi), manual valves within the IST program scope that perform an active safety function shall be exercised through a complete cycle at least once every 2 years. Exercise testing shall be considered acceptable if valve stem travel exhibits unrestricted movement with no abnormal resistance or binding through one complete cycle. Where practical, process parameters may be utilized to verify obturator movement. However, where process parameters are utilized to verify obturator movement it is not necessary to be performed simultaneous to manual exercising. This testing methodology is consistent with the discussion provided in NUREG-1482, Revision 1, Section 4.4.4. If a valve fails to exhibit the required change of obturator position, the valve shall immediately declared inoperable.
The use of a valve persuader (cheater) for additional mechanical advantage will not invalidate the test, as it is recognized that larger valves may exhibit increased packing friction and/or increased friction associated with the disk to seat interface. In addition, a valve persuader may be used for personnel safety depending on a valve's service application (i.e. main steam).
Leak Testing In addition, Category A valves shall be leak rate tested at least once every two years normally, but not necessarily, at refueling outages. The Category A valves that are tested in accordance with Option B of 10CFR50, Appendix J, Type C, are leak rate tested at the frequency specified in Option B of 10CFR50, Appendix J. For other than containment isolation valves with a leakage requirement based on other functions, shall be tested in accordance with ISTC-3630. Example of these other functions are RCS pressure isolation valves, certain owner defined system functions such as inventory preservation, system protection, or flooding protection. Ifthe leak rate exceeds the allowable limit, the valves will be repaired or replaced. A retest demonstrating acceptable operation will be performed following any required corrective action before the valve is returned to service.
Category C Valves Category C valves are valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillment of their function. Category C valves are divided into two groups; safety or relief valves and check valves.
Safety and Relief Valves ASME Class 1, 2 and 3 safety and relief valves are tested in accordance with ASME OM Code Appendix I,, "Inservice Testing of Pressure Relief Devices in Light-Water Reactor Nuclear Power Plants" All Main Steam Safety Valves and ASME Class 1 safety and relief valves are tested at least once every 5 years, with at least 20% of the valves in each system category (i.e., same manufacturer, type, system application and service media) included in the BVPS-1 IST Program tested within any 24 months. All ASME Class 2 and 3 safety and relief valves are tested at least once every 10 years, with at least 20% of the valves in each system category included in the BVPS-1 IST Program tested within any 48 months. A test is defined as a seat tightness test and a set pressure test. A seat tightness test shall be based on a quantitative or qualitative acceptance criteria specified by the owner for gross determination of the as-found seat tightness of a safety or relief valve.

Beaver Valley Power Station                          Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 133 of 320 Following the as found seat tightness test, a set pressure test shall be performed. If any safety or relief valve fails its set pressure test, additional valves shall be set pressure tested on the basis of 2 additional valves to be tested for each valve failure up to the total number of valves from the same system category. If any of the additional valve(s) fail, then all remaining valves in the same system category shall be set pressure tested. A failure is defined as when the as found set pressure (first test actuation) exceeds the greater of either the +/-tolerance limit of the Owner-established set pressure acceptance criteria or +/-3% of the valve nameplate set pressure. Any safety or relief valve which exceeds its set pressure or leakage test acceptance criteria shall be evaluated for cause and effect then repaired or replaced. The cause of failure shall be determined and corrected, and the valve shall successfully pass a retest before it is returned to service.
Set point adjustment is an acceptable means of corrective action in lieu of repair or replacement. In addition, a seat tightness test shall be based on a quantitative or qualitative acceptance criteria specified by the owner for gross determination of the as-found seat tightness of a safety or relief valve. Class 1 thermal relief valves shall be tested in accordance with the requirements of paragraph 1-1320 of Appendix I. Class 2 and 3 thermal relief valves shall be tested or replaced every 10 years in accordance with the requirements of paragraph 1-1390 of Appendix I. A thermal relief valve is a device whose only overpressure protection function is to protect isolated components (i.e. tanks, heat exchangers), systems or portions of systems from fluid expansion caused by changes in fluid temperature.
Check Valves NOTE:       In transitioning to ASME OM Code-2001 with Addenda through OMb-2003, each check valve will require exercising to both the open and closed positions regardless of their safety function. Additionally, periodic partial stroke exercising is no longer a Code requirement.
Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3522 and ISTC-5221. During operation at power, each check valve shall be exercised or examined in a manner that verifies obturator travel by using the methods in ISTC-5221. Each check valve exercise test shall include an open and closed test. Open and closed tests need only be performed at an interval when it is practicable to perform both tests. Test order (e.g. whether the open test precedes the closed test) shall be determined by BVPS. Open and close tests are not required to be performed at the same time if they are both performed within the same interval.
NOTE:       Bi-directional testing in the non-safety related direction can be performed anytime during the fuel cycle. If testing cannot be performed during operation at power, a Valve Cold Shutdown Justification (VCSJ) or Valve Refueling Outage Justification (VROJ) is not required to support the deferral of testing.
If exercising is not practicable during operation at power, it shall be performed during cold shutdowns. If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages. Valves exercised at shutdowns shall be exercised during each shutdown, except as specified in ISTC-3522(e). Such exercise is not required ifthe interval since the previous exercise is less than 3 months. During extended shutdowns, valves that are required to perform their intended function shall be exercised every 3 months, if practicable. Per ISTC-3522(e), valve exercising shall commence within 48 hours of achieving cold shutdown and continue until all testing is complete or the plant is ready to return to operation at power. For extended outages, testing need not be commenced in 48 hours if all valves required to be tested during cold

Beaver Valley Power Station                         Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 134 of 320 shutdown will be tested before or as part of plant startup. However, it is not the intent of Subsection ISTC to keep the plant in cold shutdown to complete cold shutdown testing.
All valve testing required to be performed during a refueling outage shall be completed before returning the plant to operation at power.
Valves that operate in the course of plant operation at a frequency that would satisfy the exercising requirements of ISTC need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the plant record at intervals no greater than specified in ISTC-351 0.
For a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within 3 months before placing the system in an operable status, the valves shall be exercised and the schedule followed in accordance with requirements of ISTC.
Per ISTC-5221, check valve obturator movement shall be verified as follows:
Check Valve Flow Exercising During exercise testing with flow, the necessary obturator movement shall be demonstrated by performing both an open and a close test. [ISTC-5221(a)]
: 1. Check valves that have a safety function in both the open and close directions shall be exercised by initiating flow and observing that the obturator has traveled to either the full open position or the position required to perform its intended function(s) and verify that on cessation or reversal of flow, the obturator has traveled to its seat.
: 2. Check valves that have a safety function in only the open direction shall be exercised by initiating flow and observing that the obturator has traveled to either the full open position or the position required to perform its intended function(s) and verify closure.
: 3. Check valves that have a safety function in only the close direction shall be exercised by initiating flow and observing that the obturator has traveled at least to the partially open position (normal or expected system flow), and verify that on cessation of reversal of flow, the obturator has traveled to the seat.
Observations shall be made by observing a direct indicator (e.g. position indicating device) or other positive means (e.g. changes in system pressure, flow rate, level, temperature, seat leakage testing, or non-intrusive testing results.
Check Valve Mechanical Exercising If a mechanical exerciser is used to exercise a valve, the force or torque required to move the obturator and fulfill its safety function(s) shall meet the acceptance criteria specified by BVPS-1 [ISTC-5221 (b)]. If practicable, the force(s) or torque(s) required to move the obturator and fulfill any non-safety function should be evaluated to detect abnormality or erratic action for corrective action. The following shall be considered when determining acceptance criteria for mechanical exercising:
: 1. Exercise test(s) shall detect a missing obturator, sticking (closed or open), binding (throughout obturator movement), and the loss of any weight(s). Both an open and closed test may not be required.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 135 of 320
: 2. Acceptance criteria shall consider the specific design, application, and historical performance. (A reference opening torque +/-50% was used in the previous 10-year interval per OM-10, Paragraph 4.3.2.4(b).)
: 3. If impracticable to detect a missing obturator or the loss or movement of any weight(s) using a mechanical exerciser, other positive means may be used (e.g., seat leakage tests and visual observations to detect obturator loss and the loss or movement of external weight(s), respectively).
Check Valve Sample Disassembly and Inspection Per ISTC-5221(c); If the test methods in ISTC-5221(a) (flow exercising) and ISTC-5221(b)
(mechanical exercising) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly and inspection program shall be used to verify obturator movement. If maintenance is performed on one of these valves that could affect its performance, the post-maintenance testing shall be conducted in accordance with ISTC-5221(c)(4).
Check valves that will be disassembled and inspected shall be grouped by similar design, application, and service condition and require a periodic examination of one valve from group each refueling outage. The details and bases of the sampling program shall be documented and recorded in the test plan. The following shall be considered when implementing a sample disassembly and inspection program:
: 1. Grouping of check valves for the sample disassembly and inspection program shall be technically justified and shall consider, as a minimum, valve manufacturer, design, service, size, materials of construction, and orientation. [ISTC-5221(c)(1)]
Maintenance and modification history should be considered in the grouping process.
Valve groupings should also consider potential flow instabilities, required degree of disassembly, and the need for tolerance or critical dimension checks.
: 2. During the disassembly process, the full stroke motion of the obturator shall be verified.
Full stroke motion of the obturator shall be verified immediately prior to completing reassembly. Check valves that have their obturator disturbed before full stroke motion is verified shall be examined to determine if a condition exists that could prevent full opening or reclosure of the obturator. Examples of valves that could have their obturators disturbed prior to verifying full stroke motion include; spring loaded check valves or check valves with the obturator supported from the bonnet. [ISTC-5221(c)(2)]
: 3. At least one valve from each group shall be disassembled and inspected each refueling outage; and all valves in the group be disassembled and inspected at least once every 8 years. [ISTC-5221(c)(3)]
: 4. Before return to service, valves that were disassembled for inspection or that received maintenance that could affect their performance, shall be exercised full- or part-stroke, if practicable, with flow in accordance with ISTC-3520. Those valves shall also be tested for other requirements (e.g., closure verification or leak rate testing) before returning them to service. [ISTC-5221(c)(4)]

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 136 of 320 Check Valve Condition Monitoring As an alternative to the requirements of paragraphs ISTC-3510, ISTC-3520, ISTC-3530, ISTC-3550, and ISTC-5221, BVPS-1 may establish a Check Valve Condition Monitoring (CVCM) Program per ISTC-5222. The purpose of this program is to both (a) improve check valve performance and to (b) optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select group of check valves. BVPS-1 may implement this program on a valve or a group of similar valves basis.
Examples of candidates for (a) improved valve performance are check valves that:
* have an unusually high failure rate during inservice testing or operations
* cannot be exercised under normal operating conditions or during shutdown
* exhibit unusual, abnormal, or unexpected behavior during exercising or operation
* the Owner elects to monitor for improved valve performance Examples of candidates for (b) optimization of testing, examination, and preventive maintenance activities are check valves with documented acceptable performance that:
* have had their performance improved under the Check Valve Condition Monitoring Program
            " cannot be exercised or are not readily exercised during normal operating conditions or during shutdowns
* can only be disassembled and examined
* the Owner elects to optimize all the associated activities of the valve or valve group in a consolidated program.
The program shall be implemented in accordance with Appendix II, "Check Valve Condition Monitoring Program", of OMb-2003 Addenda. a site administrative procedure (1/2-ADM-2118, "Check Valve Condition Monitoring Program"), and site implementing procedures which perform the specified tests identified in the individual Check Valve Condition Monitoring (CVCM) Program Plans.
Ifthe Appendix II CVCM Program for a valve or group of valves is discontinued then the requirements of ISTC-3510, ISTC-3520, ISTC-3530, ISTC-3550, and ISTC-5221 shall be implemented.

Beaver Valley Power Station                          Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 137 of 320 Corrective Actions for Category C Check Valves If a check valve fails to exhibit the required change of disk position by any testing above, then the check valve shall be declared inoperable immediately. An evaluation of the check valve's condition with respect to system operability and technical specifications shall be made as follows:
: 1. If the inoperable check valve is specifically identified in the technical specifications, then the applicable technical specification required action statements shall be followed.
: 2. If the inoperable check valve is in a system covered by a technical specification, an assessment of its condition shall be made to determine if it makes the system inoperable. Ifthe condition of the check valve renders the system inoperable, then the applicable system technical specification required action statements shall be followed.
: 3. Corrective action (i.e., Order) shall be initiated immediately for the check valve's repair or replacement.
: 4. Nothing in the ASME OM Code shall be construed to supersede the requirements of any technical specification.
: 5. Check valves in a sample disassembly program that are not capable of full-stroke movement (i.e., due to binding) or have failed or have unacceptably degraded valve internals, shall have the cause of the failure analyzed and the condition corrected.
Other check valves in the sample group that may also be affected by this failure mechanism shall be examined or tested during the same refueling outage to determine the condition of internal components and their ability to function.
Before returning the check valve to service after corrective action, a retest showing acceptable performance shall be run.
Category D Valves Category D valves are valves which are actuated by an energy source capable of only one operation, such as rupture disks or explosively actuated valves. There are no ASME Class 1, 2, or 3 Category D valves in the Beaver Valley Power Station, Unit 1, IST Program.
Valve Inservice Test Requirements All the inservice testing requirements for each different category of valve in the IST Program are summarized in Table ISTC-3500-1. This table lists the paragraphs of ISTC that apply to each different type of valve.

Beaver Valley Power Station                          Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 138 of 320 Table ISTC-3500-1 Valve Inservice Test Requirements Leakage         Exercise         Special       Position Indication Valve         Test Procd      Test Proc/          Test          Verification and Category         Function        Frequency       Frequency       Procedure'           Frequency A             Active        ISTC-3600       ISTC-3510           None             ISTC-3700 A            Passive        ISTC-3600           None            None             ISTC-3700 B            Active            None        ISTC-3510           None             ISTC-3700 B           Passive            None            None            None             ISTC-3700 C3            Active           [Notes       ISTC-5230           None             ISTC-3700 (Safety/Relief)                       (2),(3)]     ISTC-5240 C4            Active        [Notes (3)]     ISTC-3510           None             ISTC-3700 (Check)
D            Active        [Notes (3)]         None        ISTC-5250               None ISTC-5260 Notes:
(1)  Note additional requirements for fail-safe valves, ISTC-3560.
(2)  Leak test as required for Appendix I (3) When more than one distinguishing category characteristic is applicable, all requirements for each of the individual categories are applicable, although the duplication or repetition of common testing requirements is not necessary.
(4) If a "check" valve used for a pressure relief device is capacity certified, then it shall be classified as a pressure or vacuum relief device. If a check valve used to limit pressure is not capacity certified, then it shall be classified as a check valve.
Active valves are valves which are required to change obturator position to accomplish a specific function for accident mitigation or achieving/maintaining safe shutdown. Active may also refer to a particular valve position with respect to safety function.
Passive valves are valves which maintain obturator position and are not required to change obturator position to accomplish a required function. As stated in the table, passive valves are not required to be exercised. Therefore, relief is not required from exercising any passive valve and no testing requirement is listed in the Valve Tables except where leakage testing or remote position verification is required.
Certain exemptions from the valve testing requirements of the OM Code defined by Paragraph ISTC-1200 are listed below:
: 1. Valves used only for operating convenience (i.e., manual vent, drain, instrument and test valves);
: 2. Valves used only for system control (i.e., pressure, temperature or flow regulating valves);
: 3. Valves used only for system or component maintenance; and

Beaver Valley Power Station                           Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 139 of 320
: 4. External control and protection systems responsible for sensing plant conditions and providing signals for valve operation.
: 5. Skid-mounted valves are excluded from Subsection ISTC, provided they are tested as part of the major component and are justified by BVPS to be adequately tested. Further discussion pertaining to skid-mounted valves and component subassemblies is provided in NUREG-1482, Rev.1, Sections 3.4 and 4.1.10. Skid-Mounted valves are valves which are integral to or that support operation of major components, even though these pumps and valves may not be located on the skid. In general, these valves are supplied by the manufacturer of the major component. Examples include: steam admission and trip throttle valves for turbines, and solenoid operated pilot valves used to control air operated valves.
If a question on valve testability exists, the IST program should be the controlling document since each component is individually assessed for testability and inclusion in the IST Program.
If a valve is specifically called out in the Tech. Specs. (i.e., specific valve number or uniquely specified by valve nomenclature) to be tested at one frequency and the IST Program endorses another frequency, then the more restrictive test frequency would be applicable.
Records and Reports Records of the results of inservice tests and corrective actions as required by ISTC-9000 are maintained in computerized or in tabular form. Stroke times of valves will be reviewed for developing trends.
NOTE: The following four sections of this document are the "Valve Tables", 'Valves Cold Shutdown Justifications", "Valve Refueling Outage Justifications" and "Valve Relief Requests" sections.
Valve Tables The "Valve Tables" section is a table listing of all the valves in the IST Program, their system code class and category, whether they are active or passive, their size, valve type, actuator type, drawing number and coordinates, normal, safety and fail-safe positions, required test and frequency, specific cold shutdown justifications, refueling outage justifications and/or relief request reference numbers, test procedure numbers and remarks.
: 1. The valve class will be 1, 2 or 3, corresponding to the safety classifications.
: 2. The category of the valve will be A, B, C or D in accordance with the guidelines in ISTC-1300.
: 3. Whether the valve is Active or Passive will be identified in accordance with the guidelines in ISTA-2000.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                            Page 140 of 320
: 4. The type of valve (i.e., globe, gate, butterfly, ball, check, safety, relief, etc.) will be specified. From the valve ID number given, the type of valve actuator can be determined from the following abbreviations:
FCV - Flow Control Valve HCV - Hand Control Valve HYV - Hydraulic Operated Valve LCV - Level Control Valve MOV - Motor Operated Valve NRV - Non-Return Valve PCV - Pressure Control Valve RV - Relief Valve SOV - Solenoid Operated Valve SV - Safety Valve TV - (Air Operated) Trip Valve D - Damper
: 5. The drawing numbers and coordinates will be the ones used in the Operating Manuals.
: 6. The normal, safety and fail-safe positions will be listed using the following abbreviations:
0 - Open S - Shut A - Automatic T - Throttled LO - Locked Open LS - Locked Shut SS - Sealed Shut The normal position applies to operation at power and in most cases will be the normal system arrangement (NSA) position listed in the applicable Operating Manual. The safety position is the position the valve is required to be in to fulfill its safety function. The fail-safe position is the position the valve is required to be in to fulfill its intended safety function upon a loss of actuating power.
: 7. The required test will be listed using the following abbreviations:
ST-O               Stroke Time Open in Safety Direction ST-S               Stroke Time Shut in Safety Direction FS-O               Fail-Safe Test in Open Safety Direction FS-S               Fail-Safe Test in Shut Safety Direction ET                 Exercise Test (Full Stroke Cycle - Open and Shut) of OMN-1 or OMN-12 Valves DIAG-ST-O          OMN-1 or OMN-12 Diagnostic Test Open in Safety Direction DIAG-ST-S          OMN-1 or OMN-12 Diagnostic Test Shut in Safety Direction CV-O               Stroke Check Valve Open in Safety Direction CV-S                Stroke Check Valve Shut in Safety Direction CV-S-LT            Stroke Check Valve Shut by Leak Test in Safety Direction CV-ME              Stroke Check Valve Open and Shut using a Mechanical Exerciser on the External Weight Arm CV-BDT-O            Stroke Check Valve Open in non-Safety Direction

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 141 of 320 CV-BDT-S             Stroke Check Valve Shut in non-Safety Direction CV-DIS               Disassemble and Inspect Check Valve in Both (Open and Shut)
Directions PMT                  Post-Maintenance Test Following Disassembly and Inspection of a Check Valve MAN                  Full-Stroke Manual Valve in Both (Open and Shut) Directions LM                   Leakage Monitoring LT                   Leak Test LTJ                  Leak Test (10CFR50 Appendix J, Option B / Type C)
SPT                  Set point Test RPV                  Remote Position Verification (Required every 2 years or at the frequency requirements of OMN-1 and OMN-1 2. Some valves may require RPV every 18 months per Tech Spec 3.3.3.3(16)).
: 8. The specific Valve Cold Shutdown Justification (VCSJ) Valve Refueling Outage Justification (VROJ) and/or Valve Relief Request (VRR) reference number(s) will be listed.
: 9. The required frequency, specific test procedure number, and any remarks will be listed using the abbreviations below:
1OM          Operating Manual (Unit 1) 1BVT         Beaver Valley Test (Unit 1) lOST         Operating Surveillance Test (Unit 1)
CMP          Corrective Maintenance Procedure M            Monthly Frequency Q            Quarterly Frequency CSD          Cold Shutdown Frequency R            Refueling Frequency SP           Special Frequency MO           Required Every _ Months YR           Required Every_ Years RFO          Required Every _ Refueling Outages NSO          During "Normal System Operation" (continuously, intermittently, but at a minimum of once each cycle when the valve operates during the course of plant operation per ISTC-3550.)
CVCM         At the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program Plan OMN-1        MOV testing requirements per ASME OM Code Case OMN-1 OMN-12       AOV testing requirements per ASME OM Code Case OMN-12 Valve Cold Shutdown Justifications The "Valve Cold Shutdown Justification" section contains the detailed technical description of conditions prohibiting the required testing of safety-related valves and an alternate test method to be performed during cold shutdowns.. Since the radiation levels and air temperature inside containment are higher than normal during power operation, this would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 142 of 320 environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. Therefore, surveillance testing that requires a reactor containment entry will be performed at cold shutdown and refueling. Per ISTC-3521(g) and ISTC-3522(e), valve exercising during cold shutdown shall commence within 48 hours of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. Attempts will be made to complete testing prior to entering Mode 4, however, completion will not be a Mode 4 requirement. The testing will resume where left off when next entering Mode 5 but need not be completed more often than once every 92 days. For planned or extended cold shutdowns, where ample time is available to complete testing on all valves identified for the cold shutdown test frequency, exceptions to the 48 hour requirement can be taken, provided all valves required to be tested during cold shutdown are tested prior to plant startup.
Valve Refueling Outage Justifications The "Valve Refueling Outage Justifications" section contains the detailed technical description of conditions prohibiting the required testing of safety-related valves and an alternate test method to be performed during refueling outages.
Valve Relief Requests The "Valve Relief Requests" section contains the detailed technical description of particular conditions and equipment installations prohibiting the testing of some of the characteristics of safety-related valves. An alternate test method and the frequency of revised testing is also included to meet the intent of 10CFR50.55a.

Beaver Valley Power Station                  Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves   Page 143 of 320 SECTION VI:    VALVE TABLES

CD CD     0)
Beaver Valley PowerStation Unit I IST Program                                                                            _ CD 0
VALVE TABLE                                                                                    CD SYSTEM NAME:         Reactor Coolant                                                                                                      SYSTEM NUMBER:            06  CD     C Active I  Size   Valve Actaitor  Drawing           rolitine         Required              Code Frequency   Dev. Procedure           Rrautrki             cc S -U 0
Valve ID I Name  Class Ca. Passive  (in.)  Type   Type     &-Coord   Normal Safely Fall-Safe    Tait (1     CD 1RC-277           2     A    Passive  0.125  Needle          6-2 (F-10)   S       S                LTJ         SP             IBVT 1.47.5 (PT-IRC-458A) ROOT ISOL IRC-278           2     A    Passive  0.125  Globe           6-2 (E-10)   S       S                LTJ         SP             18VT 147.5                                01     0 to (PI-IRC-458A) ROOT ISOL 1RC-8             2    A/C    Active   0.75  Check            6-2(8-3)    S       S              CV-S-LT       SP    VROJ- 01 1BVT 1.47.5          Per CVCM Program PRT NITROGEN SUP CHECK                                                                             LTJ         SP             1BVT 1.47.5                               -n CV-BDT.O      NSO             1OM-52,.R.2.F       During Station SID    0 IRC-72            2    A/C    Active     3   Check            6-2 (C-3)   S       S              CV-S-LT       SP    VROJ -02 10VT 1.47.5          PerECVCM Program     Tu C:
PRT SPRAY LINE CHECK                                                                                LTJ        SP             IBVT 1,47.5                               3 CV-BDT-O      NSO             1101-52.4.R.2.F      During Station S/D  -a MOV-1RC-535        1    8     Active     3    Gate   MOV      6-2 (B-9)   0      Os                 ET          Q             IOST-6.6             Per OMN-1 PRZR PORV ISOL MOV                                                                              DIAG-ST-O     9YR             12--CMP-E-75-021     Per OMN.1 DIAG-ST-S     9YR             1/2-CMP-E-75-021     Per OMN-l RPV        9YR             1/2-CMP-E-75-021     Per OMN-1 MOV      6-2 (C-9)   O      OIS                ET          a             1OST-6.6             Per OMN-1            CD     -
MOV-1RC-536        I    B     Active     3    Gate                                                                                                                      Wl PRZR PORV ISOL MOV                                                                              DIAG-ST,-O    9YR             1I2-CMP-E75.-021     Per OMN-1 DIAG-ST-S     9YR             1/2-CMP-E.75-,021    Per OMN-1 RPV        9YR             112-CMP-E-75-021     Per OMN-1 MOV-IRC-537        I    8     Active     3    Gate   MOV      6-2 (C-9)   0      O/S                ET          Q             1OST-6.6             Per OMN-1 PRZR PORV ISOL MOV                                                                              DIAG-ST-O     9YR             12-CMP-E-75-021      Per OMN-1 DIAG-ST-S     9YR             1/2-CMP-E-75-021     Per OMN-1 RPV        9YR             1/2-CMP-E-75-021     Per OMN-1 PCV-1RC-455C       1    B     Active     3    Plug   PCV     6-2(8-10)    A      O/S      S        FS-S         R             1OST-6,12 PRZR PORV RELIEF VLV                                                                               Sr-O         R             1OST-6.12 ST-S         R             1OST-6.12 RPV        2YR             1OST-6.12 CC CD
                                                                                                                                                                           ~CD 00

Beaver Valley Power Station Unit 1 IST Program                                                                   0 CD CD VALVE TABLE
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SYSTEM NAME:          Reactor Coolant                                                                                                     SYSTEM NUMBER:  06 CD      <D Active I Sz*e  Vat"   Actuator  Drawing           V P0411a           Rcquircd             Cede                                       cc  0)
Valve ID / Naine Class Cat. Passie   (in.)  Type   Type     & Coord   Normal Safety  Fail-Safe   Test   Freqteney   Dew. Procedure           Remarks    CD      C C')
PCV.IRC-4550       1     8    Active     3    Plug    PCV    6-2 (C-10)   A     OS         S      FS-S        R               1OST-6.12 PRZR PORV RELIEF VLV                                                                              ST-O        R               tOST-6.12                      C0      0 ST-S        R               IOST-6.12 RPV       2YR               10STw6.12                      &3
                                                                                                                                                             -4      -
PCV-IRC-456        1     B    Active     3    Plug    PCV    6-2 (C-l0)   A     O/S        S      FS-S        R               IOST-6.12 ST-O        R               10ST-6.12
                                                                                                                                                             ~0 PRZR PORV RELIEF VLV ST-S        R               1OST--612                      o       0 CD RPV       2YR               10ST6. 12 RV-IRC-551A         1    C    Active   6x6   Safety    SV     6-2 (C-6)   S     O/S                SPT      SYR               18VT 1.60.5                    -0 PZR RELIEF                                                                                                                                                   Cn RV-IRC-5518         I    C    Active   6x6   Safely    SV     6-2 (C-7)   S      U/S               SPT      SYR               1BVT.1.60.5 PZR RELIEF CD RV-IRC-551C         I    C    Active   6x6   Safety    SV     6-2 (C-8)   S     o/S                SPT      SYR               1BVT 1.60.5 Cn PZR RELIEF SOV.IRC-102A        I    B    Active     1   Globe   SOV      6-2 (A-1)  LS     0US        S      FS-S      CSD     VCSJ - 01 1OST-llO RCVS RX VESSEL VENT ISOL VLV                                                                      ST-O      GSO     VCSJ - 01 lOST-.O10 ST-S      CSD     VCSJ - 01 IOST-1.10 RPV       2YR               1OST-6.9 SOV-1RC-1028       I     B    Active     1   Globe   SOV. 6-2 (A-1)  LS     OS         S      FS-S      CSD     VCSJ - 01 lOST-110 RCVS RX VESSEL VENT ISOL VLV                                                                      ST-0      CSO     VCSJ - 01 lOST-1.10 ST-S      CSO     VCSJ - 01 1OST-1.10 RPV       2YR               lOST-6O9 CD   -
SOV.IRC-103A       1     B    Active     1   Globe   SOV      6-2 (A-2)  LS     O/S        S      FS-S      CS0     VCSJ - 01 lOST-1,10 RCVS PRZR VENT ISOL VLV                                                                           ST-O      CSD     VCSJ - 01 lOST-1A0 ST-S      CSO     VCSJ-01   1OST-1.10 RPV       2YR               1OST-6.9 CD~
                                                                                                                                                             ~Cn 01 C) C

(n CD Beaver Valley Power Station Unit 1 IST Program                                                                      CD      0 VALVE TABLE 2D CD SYSTEM NAME:        Reactor Coolant                                                                                                         SYSTEM NUMBER:            06 CD Active / Size    Valve   Actuator  Drawing            Positinc           Required             Cede Valvr ID I Name Class Cat. Passive  (in.)   Type     Type    & Courd    Norrmal Safety    Fayl-Safe   Tesi   Frequency   Dev. Procedure         Remarks
(   0 SOV-IRC-1038      1    8    Active     I     Globe    SOV     6-2 (A-2)     LS     O/S         S       FS-S      CSD    VCSJ-01   1OST-1.10 CI)     CD RCVS PRZR VENT ISOL VLV                                                                               ST-0       CSD    VCSJ - 01 1OST-1.10 sT-S      CSD    VCSJ-01   1OST-1.10 RPV       2YR              IOST-6.9 to SOV-IRC-104       1    8    Active      1    Globe    SOV     6-2 (A-3)    I'S     O/S         S       FS-S      CSD    VCSJ - 01 1OST-1.10 IOST-1.10 RCVS VENT TO PRT ISOL VLV                                                                             ST-O       CSD    VCSJ -O1
                                                                                                                                                                          -n ST-S      CSD    VCSJ -01  1OST-1.10 RPV       2YR              1OST-6.9 3
SOV-1RC-1O5       I    B     Active     I    Globe    SOV     &-2 (B-2)    LS      O/S         S       FS-S      CSD    VCSJ - 01 lOST-1_10
                                                                                                                                                                         -0 RCVS VENT TO CNMT ISOL VLV                                                                             ST-O      CSD    VCSJ - 01 IOST-1,10                              -o ST-S      CSD    VCSJ- 01  lOST-I,10 CL RPV       2YR              IOST-,6.9 SOV-IRC.455C1     3    B    Active   0.75  Three-way  SOV     11-2 (G-8)     S     0/S         S       FS-S       R               IOST-6.12                              a/)
ST-O        R               tOST-6.12         ST-O&S performed             C (PCV.IRC-455C) SOLENOID                                                                                                                             in conjunction with
                                                                                                                                                                                 -a 1MSP-&.82-.
ST-S       R               IOSI-6-12                              CD SOV-IRC-455C2     3    B    Active   0.75  Three-way  SOV     11-2 (G-9)     S    O/S          S       FS-S       R               IOST-6.12 (PCV-1RC-455C) SOLENOID                                                                                ST-O       R               1OST-6.12         ST-O&S performed in conjunction with 1MSP-6.82-1 ST-S       R               IOST-6.12 SOV-1RC-455D1     3    B     Active  0.75  Three-way  SOV     11-2 (E-a)     S     O/S         S       FS-S       R               1OST-6.12 (PCV-lRC-4550) SOLENOID                                                                                ST-O       R               1OST-6.12         ST-O&S performed in conjunction with 1MSP-6.83-1 ST-S       R               IOST-6.12 SOV.IRC-45502     3    B    Active   0.75  Three-way  SOV     11-2 (E-9)     S     O/S         S       FS-S       R               IOST-6.12 (PCV-1RC-455D) SOLENOID                                                                                ST-O       R               1OST-6.12         ST-O&S performed in conjunction with 1MSP-6.83-i ST-S       R               tOST-6.12 CC CD CD .
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00 00

o      CD Beaver Valley Power Station Unit I IST Program                                                                  CD      0)
VALVE TABLE                                                                                     &#xa2; CD SYSTEM NAME:        Reactor Coolant                                                                                                     SYSTEM NUMBER.            06 o       -'
0 CD Active /   Size   Valve   Acluator  Drawing           Position          Required           Code Valve ID I Name Class Cat. Passive   (tn.)    Type    Type     & Coerd   Normal Safety   Fail-Safe   Test   Frequnccy Dev. Procedure           Remarks (D      CD)
$OV-1RC-456-1     3    B    Active   0.375  Three-way  SOV     6-2 (8.10)   S     O/S         S      FSAS        R          1OST-6.12 0
(PCV-IRC-456) SOLENOID                                                                               ST-O        R          1OST-6.12           ST-O&S performed in conju*ction with 1MSP-6,84-l               Clo ST-S        R          1OST-6-12 0)
SOV-IRC-456-2     3    B    Active   0.375  Three-way  SOV     6-2 (B-10)   S     O/S         S      FS-S        R          1OST-.6.12 (PCV.1RCA56) SOLENOID                                                                                ST-O        R          1OST-6.12           ST-O&S performed      3 in conjunction with 1MSP-6.844            0 ST-S        R          1OST-6.12
                                                                                                                                                                       -0 TV.1RC-101        2    A    Active    0.75    Globe     TV     6-2(8-2)     S      S          S       LTJ       SP          1BVT 1-47.5                               C PRT N2 SUP ISOL VLV                                                                                  FS-S        Q          1OST.473J                                 3 ST-S        Q          IOST.47.3J
                                                                                                                                                                     - 0)      -
RPV     2YR/181O       lOST-47.3J          18 months per Tech. Specs.
TV-1RC-519        2    A    Active      3   Diaphragm   TV     6-2 (C-1)    S      S          S       LTJ       SP          IBVT 1.47.5 PRT PRIMARY WATER SUP ISOL VLV                                                                       FS-S        a          IOST-47.3J ST-S        a          IOST-47.3J (D      -
RPV     2YRl18MO       10ST-47.3J          18 months per Tech. Specs.
: 0)   C (a    CD 4'CD~
                                                                                                                                                                       -4 <
00 00

CD 0)
Beaver Valley PowerStation Unit I IST Program                                                                           (D 0)
VALVE TABLE                                                                                CD
                                                                                                                                                                   --i      RL SYSTEM NAME: Chemical and Volune Control (Charging & HHSI)                                                                              SYSTEM NUMBER:         07  CD       C Active / Size    Valve   Actuator Drawing           Position         Required             Code                                         (n Valve lID/ Name  Class CaL  Passive (In.)   Type     Type    & Coord   Normal Safely Fall-Safe    Test   Frequency   Dev. Procedure          Remark,%
Cl)      CD ICH.135            3    B   Active    1   Diaphragm          7-3 (E-8)   S      0                 MAN       2YR              1OST-47.3E BORIC ACID BLENDER IN TO CHG PP SUCT ISOL tCH.136            3    C   Active    1     Check            7-3 (F-8)   S      0              CV-BDT-S    CVCM              1BVT 1.47.11       Per CVCM Program  (0        0 BORIC ACID BLENDER IN TO CHG PP SUCT CHECK                                                       CV-O      CSD     VCSJ - 28 1OST-1.10 1CH.141            2    C   Active    2     Check            7-3 (G-8)   S      0              CV-BDT-S    CVCM              1BVT 1.47,11       Per CVCM Program CV-O      CSD     VCSJ - 28 1OST-1l0                              '17 EMER BORATION CHECK                                                                                                                                                0 ICH-152           2    C   Active    2     Check            7-1 (C-3)   0      0              CV-BDT-,S     a               1OST-7.5 CHG PP 1A MIN FLOW CHECK                                                                       CV-BDT-S      0               1OST-7.6                               3 CV-O                        10OST-7.4                            -0 1CH-153            2    C   Acdve     2     Check            7-1 (0-3)   0      0              CV-BDT-S      0               1OST-7.4 CL CHG PP 18 MIN FLOW CHECK                                                                       CV-BDT-S      0               1OST-7_6                                         C CV-O        0               1oST-7.5                               <       0 1CH-154            2    C   Active    2     Check            7-1 (E-3)   0      0              CV-BDT-S      0               1OST-7.5 CHG PP IC MIN FLOW CHECK                                                                       CV-BDT-S      a               1OST-7.4                              CD       -
CV-O        0               1OST-7.6 1CH-1S8            2    9   Active    3     Gate             7-1 (C-3)  LO      S                 MAN       2YR              1OS'-7.5           Perform with RPV CHG PP 1A TO FiLL HDR ISOL                                                                        MAN       2YR              1OST-7.6           Perform with RPV RPV       2YR              1OST-7.5           RV of Reach Rod RPV       2YR              1OST-7.6           RPV of Reach Rod ICH-159           2    B   Active    3     Gate             7-1 (D-3)  LO      S                 MAN       2YR              1OST-7,4           Perform with RPV CHG PP 16 TO FILL HOR ISOL                                                                        MAN       2YR              IOST-7.6           Perform with RPV RPV       2YR              1OST-7A            RPV of Reach Rod RPV       2YR              1OST-7.6           RPV of Reach Rod ICH-161           2    B   Actve     3     Gate             7-1 (E-3)  LO      S                 MAN       2YR              IOST-7.4           Perform with RPV CHG PP IC TO FILL HDR ISOL                                                                        MAN       2YR              1OST-7,5           Perform with RPV RPV       2YR              1OST-7.4           RPV of Reach Rod RPV       2YR              1OST-7.5           RPV of Reach Rod ICH-ITO            1   A/C Passive    2     Check            7-1 (G-2)   S      S                  LT       2YR               1BVT147.11 FILL HDR CHECK                                                                                                                                                      CDC
                                                                                                                                                                       ~CD 0(d
                                                                                                                                                                    -h 00

                                                                                                                                                                                  *"ED aI)
CD CD Beaver Valley PowerStation Unit I IST Program                                                                                 <
_   CD VALVE TABLE                                                                                    CD)
                                                                                                                                                                              --q     <-
SYSTEM NAME:         Chemical and Volume Control (Charging & HHSI)                                                                              SYSTEM NUMBER:          07  *CD      ~-<
Active I  Size     Valave   Atustor   Dra~inst          Positioa           Required             Code 0)
Valve ID I Naxne CIA33 Cat. Passive   (In-)    Type       TVP     & Coord   Normal Safety    Fail-Safe   Test   Frequency   De". Procedure           Remarks ICH-181            2   A/C  Active      2      Check             7-4(8-4)     0       S                CV-S-LT      R     VROJ - 08 1BVT 1.47.11 NSO               ISTC-3550           During Operation of   -0       0 RCP IA SEAL SUP CHECK                                                                                  CV-BDT-O RCP LT       2YR              1BVT 1.47.11
                                                                                                                                                                             -17 1CH.182            2   A/C  Active      2      Check             7-4 (D-4)    0       S                CV-S-LT      R     VROJ - 08 IBVT 1.47.11                                      =3 RCP 18 SEAL SUP CHECK                                                                                  CV.BDT-O   NSO               ISTC-3550           During Operation of RCP 1BVT 1.47.11                             0 LT       2YR ICH-1t3            2   A/C  Active      2      Check              7-4 (G-4)   0       S                CV-S-LT      R     VROJ - 08 IBVT 1.47.11 RCP IC SEAL SUP CHECK                                                                                  CV-BDT-O   NSO               ISTC-3550           During Operation of  3-0  CO RCP                  0C LT       2YR              IBVT 1.47.11                             CD 2
ICH.22             2    C   Active      3      Check             7-1 (C-3)    0     Os                   CV-O       R     VROJ - 03 IOST-l1,148 CHG PP IA DISCH CHECK                                                                                    CV-S       R     VROJ - 03 1OST-I 1.148 CV-S       C               10ST-7.5 CV-S       0               1OST-7.6 1CH-23             2    C   Active      3      Check             7-1 (D-3)    0     OS                   CV-O       R     VROJ- 03  1OST-rl.148                              0     0 CHG PP 18 DISCH CHECK                                                                                    CV-S       R     VROJ - 03 1OST-1114B CV-S       C                1OST-T.4 CV-S       C                IOST-7.6 1CH-24             2    C   Active      3      Check              7-1 (E-3)   0     Os                   CV-O       R     VROJ - 03 IOST-11.14B CHG PP 1C DISCH CHECK                                                                                    CV-S       R     VROJ - 03 10ST-11.148 CV-S       C               IOST-7.4 CV-S       C               107T-7.5
                                                                                                                                                                              "-h 1CH-25             2    6   Active      3      Gate              7-1 (C-2)   LO       S                  MAN       2YR              10ST-7.5            Perfom with RPV CHG PP 1A DISCH HDR ISOL                                                                                 MAN       2YR              10ST-7.6            Perfoffn with RPV RPV       2YR              1OST-7.6            RPV of Reach Rod RPV       2YR              10ST-7.5            RPV of Reach Rod

(n     CD Beaver Valley Power Station Unit 1 IST Program                                                                       CD     0)
CD VALVE TABLE CD
                                                                                                                                                                            --- I 2L SYSTEM NAME:        Chemical and Volume Control (Charging & HHSI)                                                                             SYSTEM NUMBER:           07 CD     C Active!   Size     Valve     Actuator Drawing          Position          Required             Code                                               (n Valve It 1 Name Class Cut. Passive   (ion)    Type       Type    & Coord   Normal Safety Fall-Safe    Test   Frequency    Oev,   Procedure            Remarks 0      0 ICH-26            2    B   Active     3       Gate               7-1 (D-2)  LO      S                MAN        2YR               1OST-7.6            Perform with RPV             CD CHG PP 18 DISCH HOR ISOL                                                                             MAN        2YR               1OST-7.4            Perform wth RPV RPV       2YR               1OST-7.6            RPV of Reach Rod RPV       2YR               1OST-? 4            RPV of Reach Rod      0 (aQ     0 ICH-27            2    8   Active     3       Gate               7-1 (E-2)  LO       $               MAN        2YR               1OST-7.5            Perform wfth RPV CHG PP IC DISCH HDR ISOL                                                                             MAN        2YR               1OST-7.4            Perform with RPV      3 RPV       2YR               1OST-7.4            RPV of Reach Rod       "11 RPV       2YR               IOST-7.5            RPV of Reach Rod
                                                                                                                                                                            ~0 ICH-31            2   NC   Active     3      Check               7.1 (C-1)   0     OiS              CV-S-LT      R     VROJ -04   1BVT 1.47.11 REGEN HX IN CHECK                                                                                    CV-O        a                1OST-47.3K                                3 LT        2YR               1BVT 1.47.11 CL 1CH.32            1    C   Active     3      Check               7-1 (8-2)   0     0                 CV-O        a                10ST-47.3K 0.
REGEN HX OUTLET CHECK                                                                              CV-BOT-S   CVCM                1OST-7.TBD          Per CVCM Program In ICH--369          2   A/C  Active    0.76    Check               7-4 (D-8)   S     O!S               CV-O       SP     VROJ - 11  iarT1.47.5          PerCVCM Program (MOV-ICH-378) BYP CHECK CNMT ISOL PRESS EOUALIZER                                                   CV-S-LT     SP     VROJ - 11  IBVT 1.47.          Per CVCM Program LTJ       SP                I VT 1.47.5 ICH-75            3    C   Active     2      Check               7-3 (C-4)  O/S     0                CV-O       SP     VCSJ - 02  1OST-7.13           During CPT of BORIC ACID PP 2A DISCH CHECK                                                                         CV-0       CSD    VCSJ- 02   IOST-i.o            [1CH-P-2A)
CV-BDT-S    18MO               1OST-7.TBD          Once each Cycle ICH-76            3    C   Active     2      Check               7-3 (G-4)  OIS     0                CV-O       SP     VCSJ - 02  1OST-7.14           During CPT of BORIC ACID PP 28 OISCH CHECK                                                                         CV-O      CSD     VCSJ - 02  10ST-1.10 CV-6DT-S    18MO               10ST-7.TBD          Once each Cycle          CD lCH44             3    C   Active      1     Check               7-3 (E-7)  C/S    0               CV.BDT-S   CVCM                10ST-.7TD           Per CVCM Program BORIC ACID SUP TO BLENDER CHECK                                                                      CV-0      CSD     VCSJ - 28 lOST-Ilt0 ICH-27                     Active      1     Check               7-3 (F-9)   0      S              CV-SLT        R     VROJ - 06   lOST-11.14B CHEMICAL MIXING TANK OUTLET CHECK                                                                  CV-BDT-0    NSO               ISTC-3550            During Zinc Additior CDC (31 CD
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(l CD CD      0 Beaver Valley Power Station Unit 1IST Program                                                                                _  CD VALVE TABLE                                                                                        0*
CD SYSTEM NAME:        Chemical and Volume Control (Charging & HHSI).                                                                                SYSTEM NUMBER:           07  CD      C Active/   Size     Valve     Actuator Drawing           Positioa            Required             Code Valve ID I Name Class Cat. Passive  (in.)    Type       Type    & Coord   Normal Safety    Fail-Safe     Test  Frequency   Dev. Procedure                  Remarks              (  0 FCV-ICH-113A     3     8    Active     2      Globe      FCV     7-3 (E-7)   A      0          0           ET       a                1OST-473E                 Per OMN-12      U)3 CD 1ORIC ACID SUP TO BLENDER FLOW CONT                                                                      FS-O        a               IOST-47.3E                                        C,)
DiAG-ST-O    6YR               1.2M1-75-Ultrachleck A-1I Per OMN-12 0)
RPV       6YR               1/2MI-75-Ultracheck A-il  Per OMN-12      cc        =3 FCV-1CH-114A     3     B    Active     2      Globe      FCV     7-3 (E-8)    S     S          S           ET        a               l0ST-47.3E                PerOMN-12 PRI WATER SUP TO BLENDER FLOW CONT                                                                       FS-S       a                IOST-47.3E DIAG-ST-S    6YR               I/2MI-75-Ultracheck A-11  Per OMN-12      -n 0
                                                                                                        .RPV       SYR               112MI-75-ltracheck A-il   Per OMN-12.
                                                                                                                                                                               -i FCV-ICH-160      2     A   Passive     2      Globe      FCV     7-1 (G-3)   S      S                      LT      2YR               I1BVT 1.47,11 FILL HDR FLOW CONT LCV-1CH-460A      1    B    Active     2      Globe      LCV     7.1 (A-2)   0      S          S         FS-S   CSD orR   VROJ- 13     OST-1.10 LTDN TO REGEN HX.IN ISOL                                                                                 ST-S   CSDorR    VROJ - 13 lOST-I.1D RPV       2YR              lOST-1l10                                          C (n
LCV-ICH-4608      1    8    Active     2      Globe      LCV     7-1 (A-3)   0      S          S         FS-S   CSDorR    VROJ - 13    1OST-1.10                                       '-,
LTDN TO REGEN HX IN ISOL                                                                                 ST-S   CSD or R  VROJ - 13 lOST-l1O.
RPV       2YR              1OST-1.10 MOV-ICH41l5B     2     B    Active     8      Gale       MOV     7-1 (E-6)   S     O1S                    ET        Q               IOST-473E                  Per OMN-1 RWST OUT TO CHG PP SUCT HDR ISOL                                                                      DIAG-ST-O   4.5YR               M12-CMP-E-75-021         Per OMN-l DIAG-ST-S   4&#xfd;SYR             112-CMP-E-75-021           Per OMN-1 RPV      4.5YR             1t2-CMP-E-75-021           Per OMN-1 LT      2YR                tBVT 147.11 MOV-ICH-115C     2     B    Active     4      Gale       MOV     7-1 (G-5)   0      S                     ET    CSDorR    VROJ -O7  1OST-1A0                   Per OMN-1 VCT OUT TO CHG PP SUCT HDR ISOL                                                                       DLAG-ST-S   4.5YR             112-CMP-E-75-021           Per OMN-I RPV      4.5YR             1/2-CMP-E-75-021           Per OMN-1 MOV-ICH-1150     2     A    Active     8      Gale       MOV     7-1 (E-6)   0     O/S                    ET        0               IOST,47,3E                 Per OMN-i RWST OUT TO CHG PP SUCT HDR ISOL                                                                      DiAG-ST-O   4.5YR             112-CMP-E-75-021           Per OMN-I DIAG-ST-S   4.SYR             1/2-CMP-E-75-021           Per OMN-I RPV     4,SYR              1i2-CMP-E-75-021           Per OMN-1 LT       2YR              IBVT 1.47.11 to CD Cn D 0
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Beaver Valley Power Station Unit 1 IST Program                                                                CD      a)
VALVE TABLE                                                                                    _  CD SYSTEM NUMBER:     07 CD      <
SYSTEM NAME: Chemical and Volume Control (Charging & HHSi)                                                                                                     --I     R ActiveI Size  Valve Actuator Drawtng           Position           Required             Code                                       CD      C Valve ID I Name   Class Cmt. Passive (in.) Type   T)pe    & Coord   Normal Safety   Fail-Safe    Test   Frequency   Dev. Procedure           Remarks        cn cc)      0 MOV-tCN-11SE        2    B   Active   4    Gate   MOV     7-1 (F-S)   0       S                  ET     CSDorR    VROJ-07   1OST-1.10           PerOMN-1       C/)     CD VCT OUT TO CHG PP SUCT HDR ISOL                                                               DIAG-T-S     4,SYR            112-CMP-E-7S-021    Per OMN-1 RPV      4.SYR             112-CMP-E-75-021    Per OMN- I             Cf)
MOV-ICH-142         2    A   Active    2   Globe  MOV     7-1 (A-9)   S       S                  LTJ         SP             18VT 147.5                         ~0 RH LTDN TO NON REGEN -IX IN FLOW CONT                                                            ET     CSD or R  VCSJ -03  IOST-1.10           Per OMN-1 DIAG-ST-S     9YR             112-CMP-E-75-021    Per OMN-1 RPV        9YR             112-CMP-E-75-021    Per OMN- I 3
                                                                                                                                                               -nl MOV-ICN-289         2    A   Active    3   Gate   MOV     7-1 (D-1)   0       S                  ET     CSD or R  VROJ -09  1OST-1I10           Per OMN-I      0 CHG PP OISCH HDR TO REGEN HX INCNMT ISOL                                                      DIAG-ST-S   4.5YR             lr2-CMP-E-75-O21    Per OMN-1 RPV      4.SYR             1/2-CMP-E-75.021    Per OMN-1 LT      .2YR              IBVT 1.47.11 CL MOV-1CH-3081A       2    A   Active    2   Globe  MOV     7-4 (6-3)   0       S                  ET     CSDc R    VROJ - 10 lOST-1.iO           PerOMN-1 RCP 1A SEAl. INJ ISOL                                                                         DIAG-ST-S     9YR             112-CMP-E-75.021    Per OMN-1 RPV        9YR             112-CMP-E-75-021    Per OMN-1              C LT        2YR             lBVT 1,47.11 MOV-ICH-3085        2    A   Aclive    2   Globe  MOV     7-4(D-3)    0       S                   ET    CSDorR    VROJ- 10  1OST-1.10           PerOMN-l       Q)
RCP IB SEAL ]NJ ISOL                                                                          OIAG-ST-S     SYR             112-CMP-E-75-021    Per OMN-1 RPV        SYR             112-CMP-E-75-021    Per OMN-1 LT        2YR             1BVT 1.47.11 MOV-1CN-308C        2    A   Active    2   Globe  MOV     7-4 (G-3)   0       S                  ET     CSD or R  VROJ -o l0OST-1.10            Per OMN-1 RCP IC SEAL INJ ISOL                                                                          DIAG-ST-S     SYR             1I2-CMP-E-75-021    Per OMN-1 RPV        SYR              M12-CMP-E-75-021   Per OMN-1 LT        2YR             IBVT 1.47.11 MOV-1CH*-310        I    B   Active    3   Gate   MOV     7.1 (-2)    0       S                  ET     CSDorR    VROJ - 13 1OST-1.10           Per OMN-1 REGEN HX CHG HDR OUT ISOL                                                                     DIAG-ST-S   4.5YR             1/2-CMP-E-75-021    Per OMN-1 RPV      4.5YR             1/2-cMP-E-75-021    Per OMN-1 MOV-tCHN$0          3    8   Active    2   Gate   MOV     7-3 (G-7)   S       0                  ET          0              1OST-47.3E          Per OMN-1 EMER BORATION ISOL                                                                            DIAG-ST-O     SYR             1/2-CMP-E-75-021    Per OMN-1 RPV        SYR             1/2-CMP-E-75-021    Per OMN-1
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(1)      CD Beaver Valley Power Station Unit I IST Program                                                                   CD        0 VALVE TABLE                                                                                          CD
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SYSTEM NAME:         Chemical and Volume Control (Charging & HHSI)
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SYSTEM NUMBER:        07 Actve /    Suze    Valve     Acluator  Drawing          Positiuo          Required              Code CD        CD Valve D/ Iname   "lass Car. Palsive   (in.)   Type       Type     & Coord   Normal Sarety FalI-Sarr    Test    Frequency   Dev. Procedure           Remarks Ci)
MOV-1CH478        2     A    Active    0,75    Gate       MOV     7-4 (D-8)    0      S                 LTJ          SP             IBVT 1.47.5 SEAL WATER RTRN CNMT ISOL                                                                                ET      CSDorR   VROJ - 12 IOST-1.10           Per OU4N-1       (0        0 RPV     9YRI18MO            IOST-1.10           IS months per Tech. Specs.
DIAG-ST-S      9YR             1/2-CMP-E-75-021    Per OIMN-1
                                                                                                                                                                         -n        -
MOV-1CH-381       2     A    Active   0,75     Gate       MOV      7-4 (F-8)   0      S                 LTJ          SP             1BVT 1.47.5 SEAL WATER RTRN CNMT ISOL                                                                                ET     CSDorR    VROJ - 12 1OST-1.10           Per OMN-1        (0 RPV     9YRP18 MO           IOST-1.10           18 months per Tech. Specs.
DIAG-ST-S     9YR              112-CMP-E-75-021    Per OMN-1        3 RV-4CH-203        2    AtC   Active   2x3      Relief      RV      7-1 (A-5)   S     O/S                LTJ         SP              1BVT 1.47.5 Cn LTDN RELIEF                                                                                             SPT       t0YR              1BVT 1,60.5 RV.ICH482A        2    C     Active   2x3      Relief      RV     7-4 (C-S)    S     0/S                SPT       1OYR              1VrT 1.60.5 SEAL RTRN HDR RELIEF CD RV-tCH-382B       2    C     Active   2x3      Relief      RV     7-4 (E-10)   S     0/S                SPT       IOYR              1BVT 1.60.5 SEAL WATER HX RELIEF RV-ICH-383        2    C     Active  3/4 x 1   Relief      RV     7-1 (C-2)    S     OS                 SPT        I0YR             18VT 1.60.5 REGEN HX TUBE SIDE RELIEF RV-ICH-391        1    C     Active  314 x 1   Relief      RV     7-1 (G-2)    S     O/S                SPT       IDYR              18VT 1.60.5 THERMAL RELIEF VALVE FOR CNMT PENETRATION 46 TV-ICH-200A       2    A     Active      2     Globe       TV     7-1 (A-5)    0      S        S        LTJ         SP              1BVT 1-47.5 45 GPM LTDN ORIFICE CNMT ISOL                                                                          FS-S          Q              1OST-47.3K ST-S          a              1OST-47,3K RPV    2YR/18MO             1OST-47.3K          I8 months per        CD   -
Tech. Specs.
TV-ICH-2008       2    A     Active      2     Globe       TV     7.1 (A-8)    0      S        S        LTJ         SP              1BVT 1.47.5 60 GPM LTON ORIFICE CNMT ISOL                                                                          FS-S          0              1OST-47.3K ST-S          Q              1OST-47.3K RPV     2YR/18MO             1OST-47.3K          18 months per Tech. Specs.
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CD      C Beaver Valley PowerStation Unit I IST Program                                                                          CD CD VALVE TABLE                                                                                      CD SYSTEM NAME:         C-.eic   s    Vot     Ccn~o1 (Ch~gn & 11SI)                                                                              SYSTEM NUMBER-         Q'7 CD      <D C
                                                                                                                                                                         -C Active I Size       Valve   Actuator  Drawing          Position         Required             Code Valve ID I Name Cla*s  Cal. I'asst   (in.)      TYpe     Type    & Cnedr    Normal Safely F29l-Safe   Test   Frequency   Dev. Procedure            Remartks 00 TV-ICH-200C       2     A   Active     2        Globe     TV     7-1 (A.7)    0      S        S        LIJ      SP                IBVT 1.47.5                                 (   CD 60 GPM LTDN ORIFICE CNMT ISOL                                                                         FS-S       a               IOST-47.3K ST-S        a               1OST-47.3K                                   0     ,,
RPV    2YR118MO            IOST-47.3K            18 months per Tech. Specs.
                                                                                                                                                                          -n TV-lCH-204        2     A   Active     2         Gate     TV     7-1 (8-10)   0      S        S        LTJ      SP                I VT 1.47.5                            0 REGEN HX LTMN OUT CNMT ISOL                                                                           FS-S    CSDorR   VROJ - 09  1OST-1.10 ST-S    CSDor R  VROJ- 09   lOST-1.10 RPV    2YR/i8MO              1OST-1.10           18 months per     3 Tech, Specs.
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c CD Beaver Valley Power Station Unit 1 IST Program                                                             (D       CI)
VALVE TABLE                                                                                   CD SYSTEM NAME:        Reactor Plant Vents & Drains                                                                                        SYSTEM NUMBER:        09 CD       CD Active/   Size      Valve  Actuator Drawing            Positioa       Required            Code                                             -4 0 Valve I/ Name   Class Cat. Passive   (in.)     Type    Type    &Coord     Normal Safety FallSafe   Test    Frequency 0ev. Procedure            Remarks          CD       C RV-IDA-101       2    AKC Active     3/4 x 1    Relief   RV     9-1 (G-4)    S     O/S              LTJ        SP          1BVT 1.47.5 THERMAL RELIEF VALVE FOR CNMT PENETRATION 38                                                        SPT       10YR         1BVT 1.60-5
                                                                                                                                                                  -n RV-IDG-102       2    A/C   Active   3/4 x I    Relief   RV     9-1 (F-9)    S     O/S              LTJ        SP          IBVT 147.5                            (0 THERMAL RELIEF VALVE FOR CNMT PENETRATION 29                                                        SPT       10YR         1BVT 1.60.5 TV.IDA-100A      2     A    Active      2       Globe    TV     9-1 (G-4)    S      S        S      LTJ        SP          1BVT 1.47.5
                                                                                                                                                                 -a       -
CNMT SUMP DISCH CNMT iSOL                                                                          FS-S         Q          1OST-47.3K ST-S         a          1OST-47.3K                             CL      C/
RPV    2YPJ18MO        1oST-47.3K           18 months per Tech. Specs.
FV.IDA-100B      2     A    Active      2       Globe    TV     9-1 (G-4)    0      S        S      LTJ        SP          1BVT 1,47.5                           (0 CNMT SUMP DISCH CNMT ISOL                                                                          FS-S         0          1OST-47.3L ST-S         a          IOST-47.31 RPV    2YR/1SMO        1OST-47.3L           18 months per Tech. Specs.
W.tOG-108A        2    A     Active     2       Globe     TV    9-1 (F-9)    0               S      LTJ        SP          IB VT 1.A7.5 PRI DRAINS TRANSFER DISCH CNMT ISOL                                                                FS-S         Q          1OST-47.3K ST-S         0          1OST-47.3K RPV    2YRJfaMO        IOST-47.3K           18 months per      10)
Tech. Specs.
Tv-IDG-1088       2    A     Active     2       Globe     TV    9-1 (F-10)   0      S        S       LTJ       SP          IBVT 1.47.5 PRI DRAINS TRANSFER DISCH CNMT ISOL                                                                 FS-S        0          1OST-47.3L                                  ;0 ST-S        0          iOST-47 3L                               CD RPV    2YR/1I8M0       1OST-47.3L           18 months per          <
Tech. Specs,     0f TV-1DG-10AI       2    A    Active     1.5      Globe     TV    9-1 (E-9)    A      S        S      LTJ        SP          1BVT 1.47.5 0.
PRT VENT A TRAIN CNMT ISOL                                                                          FS-S        a          1OST-47.3L ST-S        Q          10ST-47.3L                            0)    C)
RPV    2YRI1 SMO       1OST-47,31.          18 months per Tech. Space.

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Beaver Valley Power Station Unit I IST Program
                                                                                                                                                                            ;CD VALVE TABLE                                                                             0        -1 CD       <
SYSTEM NAME:        Reactor Plant Vents & Drains                                                                                         SYSTEM NUMBER:         09 CD       C Code ch ACtti'eI  sue        Vahde Actuator Drawing           Positinn           Required Valve 11)1Name  CUss Cat. Paisive   (in.)      Type   T)pC    & Coord   Normal Safety    Fail-Safe   Test   Frcquenct Iev. PrWcedure           Remarks Co 0 TV-IDG-109A2      2   A     Active     1.5      Globe    TV     9-1 (E-8)   A       S          S       LTJ        SP         IBVT 1.47.5                           C/)      CD PRT VENT B TRAIN CNMT ISOL                                                                            FS.S         a         IOST-47.3K ST-S         0         10ST-47.3K Co)
RPV    2YVR18MO       1OST,47.3K           18 months per Tech. Specs.
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VALVE TABLE                                                                                   CD        <
SYSTEM NAME: Residual Heat Removal                                                                                                     SYSTEM NUMBER:           10 -4i       R CD Active I  Size Valve Actuator  Drawing           Position        Required             Code cn Valve It I Name Class Cat. Passive (in.) Type   Type     & Coord   Normal Safety Fail-Safe   Test   Frequency   0ev. Procedure             Remarks IRH.14           2     A   Passive    6   Gate           10-1 (D-8)   S      S                LTJ        SP              IBVT 1.47.5                               C/        (D)
FUEL POOL AND RWST RTRN ISOL IRH-15            2    A   Passive    6    Gate          10.1 (B-8)   S      S                 LTJ       SP               1BVT 1.47.5                                        0O RWST RTRN ISOL                                                                                RPV       2YR               IBVT 1.47.5          RPVof Reach Rod RPV       2YR              IOST-11.14A           RPV of Reach Rod    3 SP                tBVT 1.47.5                             -4         -
IRH-16            2    A   Passive    4    Ball          10-1 (C-9)   S      S                LTJ                                                                  "O POOL PURIFICATION RTRN ISOL                                                                                                                                        -T 0) 1RH-3             2    C    Active    10  Check          10-1 (E-3)   5     O/S              CV-O       CSD    VCSJ - 04 IOST-10.1                                      CO A PP DISCH CHECK                                                                             CV-S       CSD    VCSJ - 04  IOST-10.1                                 3
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1IRH-4            2    C    Active    10  Check          10-1 (F-3)   S     OIS              CV-O       CSD    VCSJ - 04  IOST-10i1                                CD 6 PP DISCH CHECK                                                                             CV-S       CSD    VCSJ- 04  1OST-10.1 C
MOV-IRH-700       1    A    Active    14  Gate   MOV     10-1 (F-1)   S     OS               ST-O       CSD    VCSJ- 05  1OST-10.4 RESIDUAL HEAT REMOVAL INISOL                                                                  ST-S      CSD    VCSJ - 05 IOST-10.4                                 c.
LT    2YRJ18MO            IOST-10.5             18 MO per Tech. 0)
Specs.
RPV       2YR               1OST-10.4 MOV-lRH-701       1    A    Actve     14   Gate  MOV     10-1 (F-2)   S     or-               ST-O      CSD    VCSJ - 05  1OST-10.4 RESIDUAL HEAT REMOVAL INISOL                                                                  ST-S      CSD    VCSJ - 05 IOST-10.4 LT    2YRP1 8MO           1OST-10.5             18 MO per Tech.
Specs.
RPV       2YR              lOST-104 MOV.IRH-720A      I    A    Active    10   Gate  MOV     10.1 (C-9)   S     OS                 LM       NSO              ISTC-3550             Continwous Monitoring of RHR           CD RESIDUAL HEAT REMOVAL RTRN ISOL                                                                                                                System Pressure     CD      -b.
ST-O      CSD    VCSJ - 05 1OST-10,4                                    0.
ST-S      CS0    VCSJ- 05  lOST-10A RPV       2YR              lOST-10.4 co __.
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VALVE TABLE                                                                                   0)      -
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SYSTEM NAME:       Residual Heat Removal                                                                                                 SYSTEM NUMBER:          L0 CD Active / Size  Valve  Actuator  Drav-ing          position           Required             Code Valve ID/ Name Ciasi Cat. Passive  (inW) Typt    Type     & Coord   Normal Safety    Fail-Safe   Te't   Frequency   Dev. Procedure           Remarks                     CD MOV-1RH-720B     I    A    Active    10   Gate    MOV     10-1 (D-9)   S     O/S                  LM       NSO               ISTC-3550           Continuous RESIDUAL HEAT REMOVAL RTRN [SOL                                                                                                                  Monitoring of RHR  0o      0 System Pressure ST-O      CSD     VCSJ - 05 1OST-10,4                                  CC)
ST-S      CSD     VCSJ - 05 1OST-10.4 3
RPV       2YR              1OST-10.4 RV.IRH-721       2    C    Active   3x4   Relief   RV     10-1 (B-7)   S     01S                  SPT      10YR              1BVr 1,60.5                            0)
RESIDUAL HEAT REMOVAL PP SUCT HDR RELIEF 3
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cn CD Beaver Valley Power Station Unit 1 IST Program                                                                      (D      0)
VALVE TABLE                                                                                    CD      <
SYSTEM NAME: Safety Injection                                                                                                            SYSTEM NUMBER:          11 CD      C Acdtve/ Size  Valve Actuator  Drawing           Posltion           Required               Code Vahe ID / Name   Clans Cal. Passive (in.)  Type  Type     & Cotrd   Normal Safety   Fail-Safe    Test     Frequency   Dev. Prucedure          Remarks                    00 ING,518            3   NC   Active  0.5   Check          11-2 (F-6)   S      S                CV-BOT-O        R               1OST-6.12          Satisfied by (PCV-1RC-455j NITROGEN SUPPLY CHECK                                                                                                              replenishing accumulator inventory after         Co exercising the PORV CV-S-LT        R     VROJ - 30 1OST-6.12 LT        2YR               1OST-6.12 1NG-519            3   AC   Active  0.5   Check          11-2 (E-6)   S      S                CV-B0T-O        R               10ST-6.12          Satisfied by       0
[PCV-1RC-4550] NITROGEN SUPPLY CHECK                                                                                                             replenishing accumulator inventory after exercising the     Co PORV CV-S-LT        R     VROJ - 30 1OST-6,12
                                                                                                                                                                    -0 LT        2YR               1OST-612 1NG-520            3   ANC  Active  0.5   Check          11-2 (G-6)   S      S                CV-BDT-O        R               IOST-6.12          Satisfed by replenishing (PCV-IRC-456) NITROGEN SUPPLY CHECK accummulator       CL Inventory after exercising the PORV CV-S-LT        R     VROJ - 30 IOST-6.12 LT         2YR               1OST-6.12 1S1-1              2    C   Active   12   Check          11-1 (G-3)   S      0                 CV-DIS      CVCM     VROJ -14  1/2CMP-75-ALOYCO   Sample CHECK-IM           Disassembly and CNMT SUMP TO LHSI PP 1A CHECK Inspection with
[SI-2] peWCVCM Program 1SI-10             1   ANC  Active    6   Check          11-1 (D-8)   S     O/S                CV-S-LT        R     VROJ- 17  1OST-11.16                            c~CD LOOP 3 COLD LEG LHSI SUP CHECK                                                                  CV-O       CVCM     VROJ - 17 1OST-11.14A        Per CVCM Program LT     2YPJ18M/CSD           IOST-11.16         CSO or 18 MO per Tech, Specs.
1S1-100            I    C   Active    2   Check          11-1 (A-9)   S      0                CV-SOT-S        R                OST-11.16         During LT of CV-O          R     VROJ- 26  1OST-11.148        ElB5-121 LOOP 1 COLD LEG HHStSUP CHECK CD 4
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Beaver Valley Power Station Unit 1 IST Program CD VALVE TABLE                                                                                        0       -
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SYSTEM NAME:        Safety Injection                                                                                                        SYSTEM NUMBER:            II -1i CD Active I Size  Valve Actaatar  Drawing           Position           Required               Code                                              (n
* Valve ID/1Name  CJan Cal. Passive (in.) Type   T)pe     & Ceord   Normel Safety    Fail-Safe   Test     Frcquency   Dev,    Procedure            Remarks
(   0 Durig LT of 11-101            1    C     Active    2   Check          11-1 (A-9)   S       0                CV-BDT-S       R               1OST-1t.16 S   CD)
LOOP 2 COLO LEG HHSI SUP CHECK                                                                    CV-O         R     VROJ - 26 IOST-11.14B SI1.102         1    C     Active    2   Check          11-1 (B-9)   S       0                CV-BDT.S       R                IOST-11.16          During LTor          01       -
[15-10]
LOOP 3 COLD LEG HHSI SUP CHECK                                                                    CV-0         R     VROJ - 26 1OST-Il.l148 ISI-11            1   A/C    Active    6   Check          11-1 (D-8)   S     O/S                CV-S-LT        R     VROJ- 17  1OST-11.16
                                                                                                                                                                         -11 LOOP 2 COLD LEG LHSI SUP CHECK                                                                    CV-O       CVCM    VROJ
* 17 1OST-11.14A          Per CVCM Program     0 LT    2YRJ18M/CSD           IOST-11.16           CSD or 18 MO per Tech. Specs.         -0 I1M-115           2    C     Active     1  Check          11-1 (C-3)  O/S      S                  CV-S         R     VROJ - 27 1OST-47-3F BORON INJ RECIRC PP 3A DISCH CHECK                                                                CV-S         a               1OST-47.3F                                (n CV-BDT-O      NSO              1OST-47.3F           During Recire of Br[
Surge Tank 1S1-116          2    C     Active    1   Check          11-1 (C-3)  0IS      S                  CVoS         R     VROJ - 27 IOST-47.3F BORON INJ RECIRC PP 3B DISCH CHECK                                                                CV-S         0                lOST-47.3F CV-BDT-O      NSO               IOST-47.3F          During Recite of BIT Surge Tank 1S4.12            1   A/C    Active    6   Check          111 (C-8)    S      O/S                CV-S-LT       R     VROJ - 17 1OST-11.16 LOOP I COLD LEG LHSI SUP CHECK                                                                    CV-O       CVCM    VROJ. 17  1OST.11.14A          Per CVCM Program LT    2YRJ18WMCSD            tOST-11.16          CSD or 18 MO per Tech. Specs, ISI-13           2   A/C    Actve     6   Check          11-1 (F-7)   S      O/S                 CV-O         R     VROJ- 1f  1OST.11.14A HOT LEGS LHSI 1A SUP CHECK                                                                       CV-S-LT       R     VROJ - 18  1BVT 1&#xfd;47.11 LT      2YRt18MO             1BVT 1,47.11        18 MO per Tech.
Specs.
CD   -
1S1-14           2   A/C    Active    a   Check          11-1 (F-7)   S      0/S                 CV-O         R     VROJ - 18  IOST-111.14A HOT LEGS LHSI 1B SUP CHECK                                                                       CV-S-LT       R     VROJ- 18  1BVT 1.47.11 LT      ZYR/iBMO            1BVT 1.47t11         18 MO per Tecth.
Specs.
isi-IS           1   A/C    Active    6   Check          11-1 (F-9)   S     OtS                 CV-S-LT       R     VROJ- 19  1OST-11.19 LOOP I HOT LEG LHSI SUP CHECK                                                                     CV-O       CVCM    VROJ - 19  IOST-l1.14A         Per CVCM Program LT      2YRJIBMO            1OST-11i19           18 MO per Tech.
Specs.
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SYSTEM NAME:         Safety Injecnion                                                                                                       SYSTEM NUMBER:          II CD       CD Active I Size  Valve Actuator   Drawing           Position         Required               Code Vol'e ID I Name Class Cat. Passive  (in.) Type   Type      & Coord    Normal Safely Fait-Safe   Test     Frequency   new. Proerdure           Remarks                  ~    0 151-16             1   A/C    Active     6   Check           11-1 (F-9)    S     O/S             CV-S-LT        R     VROJ
* 19 1OST-11.19 LOOP 2 HOT LEG LHSI SUP CHECK                                                                     CV-O        CVCM    VROJ - 19 IOST-11.14A         Per CVCM Program LT      2YR/1 SMO            lOST-11.19         18 MO per Tech.
Specs.             (0       0 1SI-17            1    ANC Active        6   Check           11-I (F-9)    S     O/S             CV-S-LT         R    VROJ - 19  1OST-11.19 LOOP 3 HOT LEG LHSI SUP CHECK                                                                     CV-O        CVCM    VROJ - 19  IOST-11-14A        Per CVCM Program   -a       -
LT     2YRJ1 8MO             lOST-11-19         18 MO per Tech.     -       CJ Specs.
a-'
ISI-2             2     C     Active    12   Check           11-1 (G-3)    S      0              CV-DIS       CVCM    VROJ - 14  1/2CMP-75-ALOYCO   Sample CNMT SUMP TO LHSI PP lB CHECK                                                                                                   CHECK-IM            Disassembly and Inspection with
[St-1] per CVCM    CD Program            ()
1SI-20            1    A/C    Active     6   Check           11-1 (F-10)   S     O/S             CV-S-LT         R    VROJ - 20 lOST-1i.19 LOOP I HOT LEG SI SUP CHECK                                                                       CV-O        CVCM    VROJ - 20  10ST-1.,14A        Per CVCM Program LT         2YR               1OST-11,19 ISI-21            1    A/C    Active     6   Check          11.1 (FP10)    S     0/S             CV-S-LT         R    VROJ - 20 1OST-1119 LOOP 2 HOT LEG St SUP CHECK                                                                       CV-O        CVCM    VROJ - 20 IOST-1114A          Per CVCM Program LT         2YR              lOST-11,19 1SI-22            1    NC     Active     6   Check          ll-1(F-1O)     S     OS              CV-S-LT        R     VROJ - 20 1OST-1.19 CV-O        CVCM    VROJ - 20 iOST-11.14A         Per CVCM Program    -0W LOOP 3 HOT LEG SI SUP CHECK LT         2YR              IOST-11.19 CD ISI-23            1    NtC    Active     6   Check          111 (C-10)     S     O/S             CV-S-LT        R     VROJ - 21 IOST-11t16 LOOP 1 COLD LEG SI SUP CHECK                                                                      CV-O        CVCM    VROJ - 21 IOST-11.14A         Per CVCM Program LT    2YR/18M/CSD           IOST-11,16          CSO or 18 MO per Tech. Specs.       0.
IS1-24            1    AC     Active     6   Check                (D-10)
(1-1     S     01S             CV-S-LT        R     VROJ - 21  1OST-11,16                                0)   -
LOOP 2 COLD LEG St SUP CHECK                                                                      CV-O        CVCM    VROJ - 21 1OST-11l4A          Per CVCM Program LT    2YR/18MtCSD            1OST-11.16         CSO or 18 MO per Tech. Specs.
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Beaver Valley Power Station Unit 1 IST Program                                                                                (D VALVE TABLE (D     <
SYSTEM NAME: Safety Injection                                                                                                               SYSTEM NUMBER:           II -        -i Active / Size  Valve Actuator   Drawing           Position           Required               Code Valve ID / Name   Class CaL Passive  (in.) Type   Type     & Coerd     Normal Safety   Fail-Sale   Test     Frequency   Dev. Procedure           Remarks
( 0 ISI-25              1   A/C Active     6   Check          11-1 (D-IO)     S    O/S               CV-S-LT         R    VROJ -21  1OST-11.16 CV-O       CVCM     VROJ - 21 1OST-11.14A         Per CVCM Program LOOP 3 COLD LEG SI SUP CHECK LT    2YR/18M/CSD            1OST-11.16         CSD or 18 MO per    Co Tech. Spa=s                8) 8   Check          11-1 (G-1)      S    0/S                CV-O           R    VROJ - 22 1OST.11.148                             (0 IS-27               2   A/C  Active                                                                                                                                      -,,
cc     -
CHO PP RWST SUP CHECK                                                                            CV-S-LT         R    VROJ -22  1BVT 1.47.11                            a)
LT         2YR              1BVT 1.47.11                            3
                                                                                                                                                                         -n 0              IOST-11.2 1SI-28              2    C   Active    2   Check            11-1 (F-4)    S    O/S                CV-O                                                                  0 LHSI PP 1S MIN FLOW LINE CHECK                                                                     CV-S          a              IOST-11.1 C:
2    C   Active    2   Check           1t1- (F-2)     $    O/S                CV-O           0              1OST-11.1 1SI-29                                                                                                                                                                  3 LHSI PP IA MIN FLOW LINE CHECK                                                                     CV-S          Q              1OST-11.2 1SI-41              2    A  Passive     I  Globe          11-2 (D-6)     LS     S                  LTJ          SP              18VT 1.47.5 SI ACC FILL LINE ISOL (n
IS1-42              2   AIC Passive     1  Check           11-2(0-5)      S     S                  LTJ          SP              1 VT 1.47.5 SI ACC FILL LINE CHECK ISI-48              1   ANC  Active    12  Check          11-2 (C-2)      S    O/S               CV-S-LT         R    VROJ.23   10ST.11.49 SIACC 1ADISCH CHECK                                                                                CV-O       CVCM    VROJ - 23 1OST-11.15          Per CVCM Program LT      2YR/i18MO           lOST-11-48           18 MO per Tech.
Specs-1S149               1   A/C  Active    12  Check           11-2 (E-2)     S    O/S               CV-S-LT         R    VROJ - 23  10ST-11.48 SI ACC 11 DISCH CHECK                                                                              CV-O       CVCM    VROJ - 23 10SI-11.15          Per CVCM Program LT      2YR/18MO            1OST-11.4B          18 MO per Tech.
Specs-1SI-5               2    C   Active    12  Check           11-1 (G-2)     S    D/S               CV-8DT-S     CVCM              1BVT-1.47.11        Per CVCM Program    0~
LHSI PP SUCT HOR RWST SUP CHECK                                                                    CV-0       CVCM    VROJ - 15 IOST-11.14A         Per CVCM Program ISI-50              I  A/C  Active    12  Check           11.2 (G-2)     S    0/S               CV-S-LT         R    VROJ- 23  1OSF-11.4B SI ACC 1C DISCH CHECK                                                                              CV-O       CVCM    VROJ- 23   Iosr-11.15         Per CVCM Program LT      2YRF18MO            1OS'.11.4B          18 MO per Tech.
Specs.
(0
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Beaver Valley Power Station Unit 1 IST Program
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SYSTEM NAME: Safety Injection                                                                                                               SYSTEM NUMBER:          II CD       CD Code                                           (n Valve IV / Name     Class CaL.
Active/
PasIve Size (in.)
Valve Type Actuator Type Drawing
                                                            & Coord Position Norml Safety    Fail-Safe Required Tes      Frequency   Dev. Procedure           Remarks
                                                                                                                                                                                  -z
(        0 B)
S13-51             1   A/C   Active   12  Check          11-2 (C-2)   S    0/S                CV-S-Lr        R     VROJ - 23 1OST-11.4A                               I      CD CV-O        CVCM    VROJ - 23 lOST-11l15          Per CVCM Program         (a 0 LOOP 1 COLD LEG St ACC CHECK                                                                                                                                                 -  Cl)
LT      2YR/18MO             1OST-11.4A          18 MO per Tech, Specs.
                                                                                                                                                                                 -0 1SI.52                1   A/C   Active   12  Check          11-2 (E-2)   S     CIS               CV-S-LT        R     VROJ - 23 1OST-1I.4A CV-O        CVCM    VROJ - 23 lOST-11.15          Per CVCM Program LOOP 2 COLD LEG SI ACC CHECK LT    ZYR/18M/CSD           lOST-11.4A          CSD or 18 MO per Tech. Specs.         T11 0
  $13-53              1   AC    Active   12  Check          11-2 (G-2)   S     0iS               CV-S-LT        R     VROJ - 23 1OST-114A
                                                                                                                                                                       "-r LOOP 3 COLD LEG SI ACC CHECK                                                                      CV-O       CVCM     VROJ - 23 1OST-1 1.15         Per CVCM Program CSO or 18 MO per LT    2YR/18MWCSD           lOST-11.4A Tech. Specs.
3 S     O/S                CV-O          R     VROJ- 16  1OST-11.14A
                                                                                                                                                                       =3 0
ISI-6                 2    C    Active   10  Check          11-1 (E-2)
LHSI PP 1A DISCH CHECK                                                                            CV-S          Q               1OST-11.2 11-1 (E-4)   S     O/S                CV-O          R     VROJ- 16  1OST-11.14A                            0-ISI-7                2    C    Active   10  Chead LHS1 PP I    ODISCH CHECK                                                                         CV-S          0               1OST-11.1 lS1-83                1   A/C  Passive    3  Check          11-1 (E-7)   S      S                   LT         2YR              1BVT 1,47.11                           CD       -
Ui)
HOT LEGS HHSI SUP CHECK 11.84                1   A/C  Passive   3   Check          11-1 (F-7)   S      S                   LT         2YR              IBVT 1.47.11 HOT LEGS HHSI SUP CHECK ISC.94               1   A/C   Active    3  Check          11-1(8-7)    S     O/S                CV-O          R     VROJ - 24  1OST-1 1.148 COLD LEGS BIT SUP CHECK                                                                          CV.S-LT        R     VROJ - 24  1BVT 1.47.11 LT         2YR              1BVT 1.47.11 IS1.05                I   A/C   Active    3  Check          11-1 (A-7)   S     0/S                CV.O          R     VROJ - 25 1OST-11.14B W<
COLD LEGS HHSI SUP CHECK                                                                        CV-S-LT         R    VROJ - 25 1BVT 1.47.11 LT         2YR              1BVT 1.47.11 SCD CD N 0)CD 00 00

0 CD Beaver Valley Power Station Unit 1 IST Program                                                                       CD CD VALVE TABLE 04      0 SYSTEM NAME:          Safety Injection                                                                                                      SYSTEM NUMBER:          CD Active I  Size  Valve Actuator  Drawing           Posilon            Required             Cede                                        (Dn     C Valve 10/ N1 Me     Class Col. Passive   in.) Type   Type     & C~ord   Normal Safety   Fail-Safe    Test   Frcqu-ncy   Dry. Procedure           Remarks 00 MOV-IS1436          1    A     Active     3   Gate   MOV     11-1 (A-6)   S     OlS                  ET      CSDorR   VROJ- 28 IOST-1.10            PerOMN-1 C~CD HHSI TO RCL COLD LEG ISOL                                                                         OIAG-ST-O   4.SYR             1/2-CMP-E-75-021    Per OMN-1 Per OMN-1           -   C/)
DIAG-ST-S   4.SYR             112-CMP-E-75-021 RPV      4.5YR             1/2-CMP-E-75-021    Per OMN-1 LT       2YR              1BVT 1.47,11
                                                                                                                                                                     -n MOV.1SI-842         2    A     Active     2   Globe  MOV     11-2 (E-5)   S      S                   LTJ        SP               I8VT .47.5                        (0 SI ACC TEST LINE CNMT ISOL                                                                           ET      CSD or R VCSJ - 08 IOST-1.10           Per OMN-1 DIAG-ST-S    9YR              1/2-CMP-E-75-021    Per OMN-1 RPV    2YPJ18MO             IOST-1.10          18 mofnhs per Tech. Specs.   -0 MOV.1SI-850A        2    B    Passive  0.75   MOV    MOV     11-2 (B-3)   S      S                   RPV       2YR              1OST-1.10                           Cn IA SI ACC TEST LINE ISOL MOV-1SI-85QB        2    B    Passive  0375   MOV    MOV     11-2 (C-3)   S      S                   RPV       2YR                1OST-1.10 1A SI ACC TEST LINE [SOL 0)
MOV-114-0soC        2    B    Passive  0.75   MOV    MOV     11-2 (E-3)   S      S                   RPV       2YR              1OST-1A0 18 St ACC TEST LINE ISOL                                                                                                                                            (D      -
(n MOV-11-850D         2    B    Passive  0,75   MOV    MOV     11-2 (E-3)   S      S                   RPV       2YR              1OST-1.10 IB SI ACC TEST LINE ISOL MOV-1SI-85GE        2    8    Passive  0.75   MOV    MOV     11-2 (G-3)   S      S                   RPV       2YR              IOST-1.10 1C S1 ACC TEST LINE ISOL MOV-151-SOF         2    a    Passive  0.75   MOV    MOV     11-2 (G-3)   S      S                   RPV       2YR              lOST-I.10 IC SI ACC TEST LINE ISOL MOV.1SI.S5A         2    B    Passive     1   MOV    MOV     11-2 (B-4)   S      S                   RPV       2YR              1OST-1.10 1A SI ACC FILL LINE SOL MOV-ISI-851B        2    B    Passive     1   MOV    MOV     11-2 (D-4)   S      S                   RPV       2YR              lOST-1O10 1B SI ACC FILL LINE ISOL MOV-1SI-851C        2    8    Passive     1   MOV    MOV     11-2 (F4)    S      S                   RPV       2YR              1OST-1,10 1C SI ACC FILL LINE ISOL (0     CD CD4~
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SYSTEM NAME:         Safety Injection                                                                                                  SYSTEM NUMBER:    II CD      C ActCle / Size  Valve Actuator  Drawing             Position       Required             Code 0,
Vahle ID / Name  Class Cat. Pasive  (in-) Type   Type     & Caord    Nnssnal Safety Feal-We    Test   Frequency   Dev. Procedure           Remarks MOV-I SI-852A      2    8    Passive   2    MOV    MOV     11-2(0-2)     S       S               RPV       2YR             10ST-1,10 IA S; ACC DRAIN ISOL                                                                                                                                         0~     0 MOV-lSI-852B       2    8    Passive   2    MOV    MOV     11.2 (D-2)    S       S               RPV       2YR             lOST-1.10
                                                                                                                                                            -n 18 SI ACC DRAIN ISOL MOV-1SI-,52C       2    a    Passive   2    MOV    MOV     11.2 (F-2)    S       S               RPV       2YR             1OST-1.10 (0
1C SI ACC DRAIN ISOL                                                                                                                                        -s C)
MOV-ISI-853A       2    8    Passive    1   MOV    MOV     11-2 (A-4)    S       S               RPV       2YR             1OST-47.3L                       3 1A SI ACC N2 SUP ISOL MOV-1SI-8538       2    S    Passive    1   MOV    MOV     11-2 (C-4)    S       S               RPV       2YR             1OST-47.3L 18 SI ACC N2 SUP ISOL MOV-.1SI-853C      2    B    Passive    1   MOV    MOV     11-2 (E-4)    S       S               RPV       2YR             1OST-47.3L 1C SI ACC N2 SUP ISOL MOV-1SI-860A       2    A     Active   12   Gate   MOV     1l-1 (F-3)    S      01S              El       CSD     VCSJ -08 0  OST-1,10           PerOMN-1 1A LHSI PP RX CNMT SUMP SUCT ISOL                                                             DIAG-ST-O    SYR             112-CMP-E-75-021    Per OMN-1 DiAG-ST-S    SYR             1f2-CMP-E-75021     Per OMN-1 RPV       9YR             1/2-CMP-E-75-021    Per OMN-1 LT       2YR             1BVT 1.47.11 MOV-1SI-8608       2    A     Active   12   Gate   MOV     11-1 (F,-4)   S      O/S              ET       CSD     VCSJ-06  1OST-1.10           PerOMN-1 DIAG-ST-O    SYR             112-CWP-E-75.021    Per OMN-1       CD 18 LHSI PP RX CNMT SUMP SUCT ISOL DIAG-ST-S    SYR              1.2-CMP-E-75.021   Per OMN-1    CDl RPV       9YR             112-CMP-E-75-021    Per OMN-1 LT        2YR             IBVT 1.47.11 0.
MOV-1SI-862A       2    6     Active   12   Gate   MOV     11.1, G-3)    0       S               ET         0              IOST-47.3L          Per OMN-1 1A LHSI PP RWST SUCT ISOL                                                                     DIAG-ST-S    9YR             112-CMP-E-75-021    Per OMN-1    C:) 0.
RPV       9YR             1/2-CMP-E-75-021    Per OMN-i MOV-SI-m862B       2    B     Active   12   Gate   MOV     11-1 )G-3)    0       S               ET         a              1OST-47.3F          Per OMN-i 16BLHSI PP RWST SUCT ISOL                                                                     DIAG-ST-S   9YR              1/2-CMP-E-75,021    Per OMN.1 RPV      9YR              1/2-CMP-E-75-021    Per OMN-1

(D      C Beaver Valley PowerStation Unit 1 IST Program (D
VALVE TABLE                                                                            -0      0 SYSTEM NAME: Safety Injection                                                                                                                                CD<
SYSTEM NUMBER:
CDn     (
Active I  Size Valve Actuator  Drawing           Posaitio            Required             Code Valve ID / Nante Class Cat. Passive  (in.) Type   Type     & Comod   Normal Safely    Fail-Safe    Test   Frequeney   1k-v. Procedure           Remarks MOV-ISI-863A       2    B   Active     6   Gate   MOV     11-1 (E-1)   S      0                     ET         Q              1OST-47.3L          Per OMN-1 (0      0 1A LHSI PP TO CHG PP SUP ISOL                                                                   DIAG-ST-O    9YR               1/2-CMP-E-75-021   Per OMN-1 RPV       SYR              112-CMP-E-75-021    Per OMN-1 cc)     :D MOV-ISI-863B       2    B   Active     6   Gale   MOV     11-1 (E-5)   S      0                     ET         a              1OST.47.3F          Per OMN-I 1B LHSi PP TO CHG PP SUP ISOL                                                                   DIAG-ST-O    9YR               112-CMP-E-75-021   Per OMN-i RPV       9YR               112-CMP-E-75-021   Per OMN-1  0)
MOV-ISI-864A       2    B   Active     10  Gate   MOV     11-1 (D-2)   0      S                     ET         a               IOST-47.3L         Per OMN-1  3 IA LHSI PP TO RCL COLD LEGS ISOL                                                                DIAG-ST-S    SYR               1l2-CMP-E-75-021   Per OMN-1 RPV       9YR              112-CMP-E-75-021    Per OMN-1 MOV-lSI-864B       2    B   Active     10  Gate   MOV     11-1 (D-4)   0       S                    ET         a              1OST-47.3F          Per OMN.I  0.
IS LHSI PP TO RCL COLD LEGS ISOL                                                                DIAG-ST-S    9YR              1/2-CMP-E-75-021    Per OMN-1 RPV       SYR              112-CMP-E-75-021    Per OMN-1 MOV.tSI-45A        2    8   Active     12  Gate   MOV     11-2 (B-2)   0       S                    ET       CSD    VCSJ - 07  IOM-52.4.R,1.F     Per OMN-1          C IA SI ACC DISCH ISOL (PWR LOCK OUT)                                                                 ET       C.SD   VCSJ - 07 1OST-1.10           Per OMN-I DiAG-ST-S    9YR              1r2-CMP-E-75-021    Per OMN-1 CD RPV       SYR              1l2-CMP-E-75-021    Per OMN-I  co MOV-lSI-865B       2    8   Active     12  Gate   MOV     11.2 (E.2)   0      S                     ET       CSD    VCSJ - 07 1OM-52.4.R.1.F      PerOMN-1 1B5S1ACC DISCH ISOL (PWR LOCK OUT)                                                                  ET       CSD    VCSJ - 07 IOST-1.10           Per OMN.1 DIAG-ST-S    SYR              1/2-CMP-E-75-021    Per OMN-1 RPV       SYR              112-CMP-E-75-021    Per OMN.i MOV-1SI-865C       2    B   Active     12  Gate   MOV     11-2 (G-2)   0      S                     ET       CSD    VCSJ - 07 1OM-52.4.R.1F       Per OMN.1 IC SI ACC DISCH ISOL (PWR LOCK OUT)                                                                 ET       CSID   VCSJ- 07  1OST-1.10           Per OMN.1 DIAG+ST-S    9YR              I12-CMP-E-75-021    Per OMN-1 RPV       SYR              112-CMP-E-75-021    Per OMN-1 MOV-1SI-867A       2    8   Active     3   Gate   MOV     11-1 (A-2)   S      0                     ET    CSD DrR   VROJ- 29  lOST-.I10           PerOMN-1 BIT IN ISOL                                                                                     DIAG-ST-O   4.5YR             1/2-CMP.E-75-021    Per OMN-I RPV      4.5YR             112-CMP-E-75-021    Per OMN. I (0 D (CD 0)<
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U)      CD Beaver Valley Power Station Unit I IST Program                                                             CD      W VALVE TABLE                                                                                 CD <
(D SYSTEM NAME: Safety Injection                                                                                                          SYSTEM NUMBER:     I1 CD      <
Active /  Size  Valve Actuator  Drawing         Pesition         Required             Code Valve ID I Name  Class Cat. Passive   (it)- Type   Type    & Coord INormal Sarety Fail-Safe    Test   Frequency   0ev. Procedure            Remtarks      CD,     CD MOV-1SI-8678       2    B    Active     3   Gate   MOV     11-1 (A-2)  S     0                 ET     CSDor R   VROJ - 29  IOST-l.10           Per OMN-1 BIT IN ISOL                                                                                 DIAG-ST-O   4.SYR              1/2-CMP-E-75-021    Per OMN-1 RPV      4.SYR              !i2-CMP-FE75-021    Per OMN-1 MOV.iSl-867C       1    A    Active     3   Gate   MOV     11-1 (8-8)  S    cis                ET          R               1OST-l,114B         Per OMN-1     0'      0 BIT OUT ISOL                                                                                    ET         0              IOST-47.3L           Per OMN-1 D0AG-ST-O   4.SYR             112-CMP-E-75-021     Per OMN-1 DIAG-ST-S   4,SYR              1/2-CMP-E-75-021    Per OMN-1 RPV      4.SYR              1/2-CMP-E-75-021    Per OMN.1
                                                                                                                                                              -0 LT       2YR               IBVT 1,4711 C
MOV-ISI-8670       1    A    Acte       3   Gate   MOV     11-1 (B-6)  S     O/S                ET         R               IOST-11148          Per OMN-1 BIT OUT ISOL                                                                                    ET         0                tOST-47.3F         Per OMN-1 DIAG-ST-O   4-SYR              i12-CMP-E-75-021    Per OMN-1 DIAG-ST-S   4,5YR              112-CMP-E-75-021    Per OMN-1     83 RPV      4.5YR              1r2-CMP-E-75-021    Per OMN-1 LT       2YR               I BVT 1.47.11 MOV-1S11-66SA      I    A   Passive     3   Gate   MOV     11-1 (E-7)  S      S                 LT       2YR               IBVT 1.4711 HI.SI TO RCS HOT LEGS [SOL (PWR LOCK OUT)                                                      RPV        2YR              IBVT 1,47.11 MOV-4SI-1698       I    A   Passive     3   Gale   MOV     11-1 (F-7)  S      S                 LT       2YR              IBVT 1,47.11 HHS! TO RCS HOT LEGS ISOL (PWR LOCK OUT)                                                       RPV       2YR               1BVT 1.47.11 MOV-1SI-885A       2    A    Active     2   Globe  MOV     11-1 (F-4)  0      S                 ET         0               IOST-47,3L           Per OMN-1 LHSI PP 1A MIN FLOW LINE TRAIN A ISOL                                                       0IAG-ST-S     9YR              112-CMP-E-75-021    PerOMN-1 RPV       9YR               1/2-CMP-E-75-U2I    Per OAIN-1 LT       2YR              1BVT 1.47.11 MOV-ISI-8858       2    A    Active     2   Globe  MOV     11-1 (,F4)  0      S                 ET         Q              1OST-47,3F           Per OMN-1 LHSI PP 18 MIN FLOW LINE TRAIN A ISOL                                                       DIAG-ST-S    9YR               1W2-CMP-E-75-021     Per OMN-1 RPV       9YR               112-CMP-E-75-021     Per OMN-1 LT        2YR              1BVT 1,47.11
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                                                                                                                                                                         ;'CD VALVE TABLE                                                                           C0     -
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SYSTEM NAME:          Safety Injection                                                                                                      SYSTEM NUMBER:    II -1i     R CD      C Acti-eI   Size   Valve  Actuator  Drawing           Position         Required             Code Valve ID I Name  Class Cal. Passive  (in.)  Type    Type    & Coord    Normal Safety Fail-Safe    Tess   Frequency   Dev. Procedure            Remarks Cn MOV.1S31-885C      2     A     Active     2    Globe   MOV     11.1 (F-5)   0       S                 ET         0             1OST-47.3F           Per OMN-1 LHSI PP IB MIN FLOW LINE TRAIN B ISOL                                                             DIAG-ST.S    9YR             1I2-CMP-E-75-021     Per OMN-. 0 RPV       9YR             112-CMP-E-75-021     Per OMN-1 LT        2YR            1BVT 1.47.11 MOV-1SI485D        2     A     Active     2    Globe   MOV     11-1 (F-5)   0       S                 ET         C             1OST-47.3L           Per OMN-1 LHSl PP 1A MIN FLOW LINE TRAIN 8 ISOL                                                             DIAG-ST-S    9YR             112-CMP-E-75-021     Per OMN-1    -n RPV       9YR             1l2-CMP.E-75-021     Per OMN-1    0)
LT       2YR             1VT 1,47,11 3
MOV-1SI-890A       I     A     Active     10   Gate    MOV     11.1 (0-3)   S      OIS                ET         0             1OST-47.3K           Per OMN-1 1A LIS1 TO RCS HOT LEGS iSOL (PWR LOCK OUT)                                                       DIAG-ST-O     9YR            1l2.CM, P-E-75-021   Per OMN-t DIAG-ST-S     9YR            1/2-CMP-E-75-021     Per OMN-1 RPV        9YR             112-CMP-E-75-021    Per OMN.1 LT        2YR            1BVT 1.47.11                      CD MOV-1S3-890B        1    A     Active     10   Gate    MOV     11-1 (D-5)   S      O/S                ET         a             1OST-47.3F           Per OMN-1 18 LHSI TO RCS HOT LEGS ISOL (PWR LOCK OUT)                                                       DIAG-ST-O    9YR             112-CMP-E-75-021     Per OMN-1 DIAG-ST-S     SYR            1r2-CMP-E-75-021     Per OMN-1 RPV        9YR            1/2-CMP-E-75-021     Per OMN-1 LT        2YR             18VT 1A7.11 MOV-1SI-9SOC        I    A     Active     10   Gate    MOV     11-1 (D-6)   0      OS                 ET       CSD    VCSJ- 09 1OST-1l10            PerOMN-1 LHSI TO RCS COLD LEGS ISOL (PWR LOCK OUT)                                                         DIAG-ST-O    SYR             1/2-CMP-E-75-021     Per OMN-1 DIAG-ST-S     9YR            1/2-CMP-E-75-021     Per OMN-1 RPV        9YR            lt2-CMP.E-75-021     Per OMN-I    a-LT        2YR            1BVT 1 A7.11 RV-IGN.108          3     C    Active  I x 1,5 Relief   RV     11-2 (E-7)   S      0/S               SPT       I0YR             1SVT 1.60.5                      00)     -D (PCV-1RC-455D1 NITROGEN RELIEF RVIGNI-109          3     C    Active  1 x 1.5 Relief   RV     11-2 (F-7)   S      O/S               SPT       IOYR            16VT 1.60.5 (PCV-1RC-455C] NITROGEN RELIEF RV-1GN.117          3    C     Active  1 x 1.5 Relief   RV     11-2 (G-7)   S      O/S               SPT      10YR             1BVT 1.60.5
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SYSTEM NAME:          Safety Injection                                                                                                                               -i     0)
Active I  Size   Valve  Actuator  Drawing            Position           Required           Code                                        CD Valve ID I Name  Class CaL    Paqsvte   (in.)  Type    Type     & Coord    Nermal Safrty    Fail-Safe   Test   Frequency Dev.. Proedure             RIemIrts Cn RV-1GN-118         3     C     Active  3/4 x 1 Relief   RV     11-2 (G-6)    S     O;S                  SPT       10YR         IBVT 1,60.5
[GN-TK-1C) TANK RELIEF                                                                                                                                               0O     0 RV-IGN-119         3     C     Active  3/4 x 1 Relief   RV     11-2 (E-6)     S     O/S                 SPT       10YR         18VT 1.60.5
[GN-TK-1AI TANK RELIEF RV-IGN-120         3     C     Active  314 x 1 Relief   RV     11-2 (F-6)     S     OS                  SPT       10YR         IBVT 1.60.5 CGN-TK-1BI TANK RELIEF C:
RV-1SI-45A         2     C     Active  3/4 x I Relief   RV     11 -1 (D-2)    S    O/S                  SPT       10IYR        1BVT 1,60.5 LHSI PP 1A DISCH RELIEF RV-ISI-8458        2     C     Active  314 x 1 Relief   RV     I1-i (D-2)     S     O/S                 SPT       10YR         1BVT 1.60.5 LHSI PP DISCH HDR TO COLD LEGS RELIEF RV-lSI-845C        2     C     Active  314 x I Relief   RV     11-1 (D-4)     S    Os                   SP'T      10OYR        1BVT 1.60.5 LHSl PP 1B DISCH RELIEF RV-lSI-857         2     C     Active  314 x 1 Relief   RV     11-1 ("-)      S    O/S                  SPT       10YR         1BVT 160.5 SIT RELIEF RV-ISI-858A        2     C     Active   I x2   Relief   RV     11-2 (A-2)     S     O/S                 SPT       10YR         1BVT 1.60-5 SI ACC 1A RELIEF RV.ISI,858B        2     C     Active   I x2   Relief   RV     11-2 (C-2)     S    OIS                  SPT       10YR         1BlVT 1.60.5 SI ACC 18 RELIEF                                                                                                                                                        CD RV-1SI.858C        2     C     Active   1x2    Relief   RV     11-2 (E-2)     S    OS                   SPT       10YR         1SVT 1.60.5 SI ACC IC RELIEF                                                                                                                                                        CD RV-1SI-894         2     C     Active  314 x I Relief   RV     11-2(0-5)      S     O/S                 SPT       10YR         1BVT 1.60.5 0.
THERMAL RELIEF VALVE FOR CNMT PENETRATION 20 TV-tSI-101.1       2     A     Active      1   Globe    TV     11-2(8-6)      S      S          S        LTJ       SP          18VT 1.47.5                           0)  0 SI ACC NITROGEN SUP ISOL                                                                                FS-S        a          1OST-47.3L ST-S        Q          1OST-47,31.
RPV    2YR/18MO        1OST-47.3L           18 months per Tech. Specs.

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Beaver Valley Power Station Unit 1IST Program                                                                            (D VALVE TABLE                                                                                 CD      <
SYSTEM NAME:        Safety Injection                                                                                                     SYSTEM NUMBER:        II Active I Size  Valve Aclualor  Drawing          positina           Required             Code                                              ~   0)
DOev. Procedure            Remarks                   (D Valve 101 Name  Clas  Cat. Passive  (In.) Type   Type     & Courd   Normal Safety   Fall-Safe   Test   Ffequeccy TV-ISI-101-2      2    A      Active    1   Globe   TV     11-2 (B-5)   S      S          S       LTJ        SP              18VT 1.47.5 SI ACC NITROGEN SUP ISOL                                                                          FS-S        0              1OST-47.3K
                                                                                                                                                                    -n ST-S        a             1OST-47.3K                             0 RPV    2YRJ18MO           IOST-47.3K           18 months per Tech. Specs.
TV.ISI-884A       2    6     Active     1   Globe   TV     11-1 (C-5)   0      S          S       FS-S        a             1OST-.473F
                                                                                                                                                                  -0       -
BIT RECIRC TO BORON INJ SURGE TK ISOL                                                             ST-S        Q              1OST-47.3F RPV       2YR              IOST-47.3F                            -L      Ci TV-ISI-884B       2     B     Active    1   Globe   TV     11-1 (C-5)   0      S          S       FS-S       0               1OST-47.3F                            <5      M ST-S        Q              1OST-47.3F X
BIT RECIRC TO BORON NJ SURGE TK ISOL RPV       ZYR              10ST-47.3F TV.lSI-884C       2     8     Active    1   Globe   TV     11-1 (C-4)   0      S          S       FS-S        Q             IOST-47.3F BORON RECIRC TO BIT ISOi                                                                          ST-S        a              IOST-,7.3F RPV       2YR              10ST-47.3F TV-1SI-889        2     A     Active   0.75 Gate    TV     11-1 (G-8)   S      S          S        LTJ       SP              1BVT 1.A7.5 SI ACC TEST UNE CGNMT  TRIP                                                                       FS-S      CSD    VCSJ -08  IOST-1.10 ST-S      CSD    VCSJ -08  !OST-11A (0
RPV    2YR118MO            iOST--110           18 months per    0) C Tech. Soecs, C) 0)
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Zn CD Beaver Valley Power Station Unit 1 IST Program                                                                      Q      WD VALVE TABLE                                                                                           CD 12  CD     C SYSTEM NAME: Containment Vacuum                                                                                                               SYSTEM NUMBER:
Active /  Size   Vale     Actualor  Drawlig          Position               liequirwd           Code                                         CD (in.)  Type      Type     & Coord   Normal Safet"   Fail-Saie        Test   Frequency Dev. Ptroedure            Rettaors Valve I1 1Name  Class Cat. Passive IIII 0
ICV-57            2    A    Passive  0,375   Globe             12-i (C-4)   SS     S                       LTJ       sP          1BVT 1.47.5 OPEN PRESS LINE DISCH ISOL                                                                                                                                               (0      0 ICV.58            2    A    Passive  0.375   Globe             12-1(8-4)    SS     S                       LTJ       SP          18Vr 1.47.5 OPEN PRESS LINE DISCH ISOI.
ICV-59            2    A    Passive  0.375   C-lobe            12-1 (B-4)   SS      S                       LTJ       SP         I8V'T 1.47.5                             -n    ~
OPEN PRESS LINE DISCH ISOL ICV-60            2    A    Passive  0.375   Globe             12-1(8-4)    SS      S                      LTJ       SID         1BVi 1.47.5 Co OPEN PRESS LINE DISCH ISOL CL HCV-ICV-161       2    A    Passive     8   Butterfly   HCV    12-1 (F-8)   LS      S                       LTJ      SP          1BVT 1.47,5 CNMT EJ SUCT CNMT ISOL a) 0 HCV-ICV-151.1    2    A    Passive     8   Butterfly   HCV    12-1 (F-7)   LS      S                      LTJ        SP         18VT 1.47.5 CD CNMT EJ SUCT CNMT ISOL TV-lCV-101A       2    A     Active     I    Globe       TV    12-1 (D-6)    0      S         S             LTJ       SP         18VT 1.47.5 CNMT ACTIV MONITOR SUCT CNMT ISOL                                                                          FS-S        a         1OST-47.3L ST-S        a         1OST-47.3L RPV    2YR/18MO       1OST-47.3L            18 months per Tech. Specs.
TV-1CV-101B       2    A     Active     1    Globe       TV    12.1 (0-7)    0      S         S             LTJ       SP         1BVT 1.47.5 CNMT ACTIV MONITOR SUCT CNMT ISOL                                                                          FS-S        a         1OST-47.3L ST-S        a         IOST-47.3L RPV    2YR/I8MO       1OST-47.3L            18 moniths per CD-N Tech. Specs,
                                                                                                                                                                           -4CD TV-ICV-102       2    A     Active     1    Globe       TV    12-1 (E-7)    0    OiS         S             LTJ       SP         IBVT 1.47.5 0F.
CNMT ACTIV MONITOR DISCH CNMT ISOL                                                                        FS-S        a         10ST-47,3L ST-O        a         1OST-47.3L ST-S        0         1OST-47.3L CD C RPV    2YR/18MO       1BVT IA7.5           IS months per Tech. Specs.

ET     CD U)     CD Beaver Valley Power Station Unit IIST Program CD VALVE TABLE                                                                             o0     -
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SYSTEM NAME: Containment Vacuum                                                                                                  SYSTEM NUMBER:         12 (D     C Actiedv Size Valve Actuator  Drawing          Postlton           Required           Code Valve ID / Name Class Cat. Passliw (i.) Type   Type    & Coord    Normal Safety   Fail-Safe   Test   Frequeacy Dev. Procedure            Remarks (0 0 TV.1CV-102-1      2    A   Active     1 Globe   TV     12-1 (E-8)   0     O/S         S       LTJ       SID         IBVT 1.47.5                            C/)    CD CNMT ACI"V MONITOR DISCH CNMT ISOL                                                           FS-S        a          1OST-47.3L 0          IOST-47.3L
                                                                                                                                                           -40    -
ST-O ST-S        Q          1OST-47.3L                             ~0     0)
RPV    2YR/18MO       1BVT 1.47.5           18 months per Tech. Specs.
TV.1CV-150A       2    A   Active     2 Globe    TV    12-1 (F-6)   0     C/S         S       LTJ       SP           1BVT 1.47.5                           3 CNMT VAC PP 1A GNMT ISOL                                                                     FS-S        0          1OST-47.3L                             -n 0
ST-O        a          IOST-47.3L ST-S        0          1OST-47.3L RPV    2YR/18MO       IB VT 1.47.5          18 months per    3 Tech. Specs, TV.ICV.10B        2    A   Active    2  Globe    TV    12-1 (F-7)   S     O/S         S       LTJ       SP          IBVT 1.47.5 CNMT VAC PP 1A CNMT ISOL                                                                     FS-S        a          1OST-47.3L ST-O        a          1OST-47.3L                             CDl ST-S         a         10ST-47.3L RPV    2YR/18MO       1BVT 1.47.5           18 months per Tech. Specs.
TlV.lCV-150C      2    A    Active    2 Globe    TV    12.1 (F-7)   0       S         S       LTJ        SP         1BVT 1.47.5 FS-S        a         IOST-47.3L CNMT VAC PP 18 CNMT ISOL ST-S        0          iOST-47.3L RPV    2YRJ18MO       IBVr 1.47.5           18 months per Tech. Specs.
TV-ICV.150D       2    A    Active    2 Globe    TV    12-1 (E-6)   S       S         S       LTJ        SP         1BVT 1,47.5 FS-S        0         IOST-47.3L CNMT VAC PP 18 CNMT ISOL ST-S        0          1OST-47.3L                               CD   -
RPV    2YR/18MO       IBVT 1.47.5          18 months per Tech. Specs-CDb 0(
00

Beaver Valley Power Station Unit 1 IST Program                                                                         CD     Ell VALVE TABLE                                                                                        _. C-D o      -'
SYSTEM NAME:        Containment Depressurization (Quench Spray & Recirc Spray)                                                                   SYSTIEM NUMBER:           13  (D     CD Active I  Siue       Valve   Actuator  Drawiag           Position           Required             Code                                               -C)    0)
Valve ID / Name Class Cat. Passive   (In.)       Type    Type     & Coerd   Normal Safety    Fall-Safe   Test   Frequency   Dev. Proctidure            Remarks              CfD    C 10S-3             2   AJC   Active     10       Check            13-1 (E-9)     S    O/S                 LTJ        SP               IBYT 1.47,5 IA CS PP DISCH CHECK                                                                                   CV-ME         R    VROJ- 31  lOST-L10 S    O/S                 LTJ SP               IBYT 1.47.5 10S-4             2   A/C   Active     10       Check            13-1 (E.9)
C0 IS QS PP DISCH CHECK                                                                                   CV-ME         R    VROJ - 31 lOST-1.10 IRS-100           2   AIC   Active    10        Check            13-2 (C-6)     S    O/S                 LTJ        SP               1BVT 1.47.5 2A OUTSIDE RECIRC SPRAY PP DISCH CHECK                                                                 CV-ME         R    VROJ- 31  lOST-1.10 IRS-101           2   AJC   Active     10       Check            13-2 (B-8)     s    O/S                 LTJ SID              1BVT 1.47.5                              (0 CV-ME R    VROJ - 31  IOST-1.10 2B OUTSIDE RECIRC SPRAY PP DISCH CHECK IRS-157           2    B    Active     6         Gale            13-2 (0-7)    LS     0                  MAN       2YR               1OST-47.3G           Perform wilt RPV 2A OUTSIDE RECIRC SPRAY PP TO HHSI PP ISOL                                                               RPV       2YR               1OST-47.3G           RPV of Reach Rod 1RS-158           2    C    Active     6        check            13-2 (D-7)     S     0                CV-DIS     CVCM    VROJ - 32  112CMP-75-VELAN      Samp4e CHECK-IM              Disassembly and 2A OUTSIDE RECIRC SPRAY PP TO HHS1 PP CHECK                                                                                                               Inspection with f1RS-160] per CVCM Program IR5-159           2    B    Active     6         Gate            13-2 (D-9)    LS     0                  MAN       2YR               IOST-47.3M           Perform with RPV 28 OUTSIDE RECIRC SPRAY PP TO HHSI PP ISOL                                                               RPV       2YR               IOST-4?.3M           RPV of Reach Rod 0)
IRS-160           2    C    Active     6        Check            13-2 (0-9)     S     0                CV-DIS     CVCM    VROJ - 32  I/2CMP-75-VELAN      Sample 28 OUTSIDE RECIRC SPRAY PP TO HHSI PP CHECK                                                                                         CHECK-1M              Disassembly and Inspection withs (I RS-158) per CVCM Proglram 0
MOV-IQS-400A      2    8   Passive     12        Gate     MIOV   13-1 (C-4)     0     0                  RPV       2YR              IOST-47.3G IA QUENCH SPRAY PP SUCT ISOL MOV-.QS41008      2    8   Passive     12        Gate     MOV    13-1 (0-4)     0     0                  RPV       2YR               1OST-47.3M                                (0~
1B I8 QUENCH SPRAY PIPSUCT 1301                                                                                                                                                   r') :3 0   CC
                                                                                                                                                                                    )

cn CD Beaver Valley PowerStation Unit 1 IST Program                                                           CD     W)
VALVE TABLE                                                                               CD
                                                                                                                                                             -0     0 SYSTEM NAME: Containment Depressurization (Quench Spray & Recirc Spray)                                                                SYSTEM NUMBER:     13 CD Active I Sin     Valve   Actuator Drawing           Position           Required           Code Valve 10 I Name Class Cal. Passive  (in.)   Type     Type    & Coord    Normal Safety   Fal-Sare    Trest  Frvquency Dev. Procedure           Remarks CD)    CD LTJ       SP         1BVT 1.47.5                              Cl)
MOV-1iS-101A      2    A    Active     10    Gate     MOV     13-1 (E-9)   S     O0s DIAG-ST-0    9YR         1/2-CMP-E-75-021    Per OMN-1 1A QUENCH SPRAY PP DISCH ISOL DIAG-ST-S    9YR         112-CMP-E-75-021    Per OMN-1 RPV       9YR         1/2-CMP-E-75-021    Per OMN-1         Cn ET    18M0 or R      IOST-473G            Per OMN-1 MOV.1QS-1018      2    A     Active    10    Gate     MOV     13-1 (F-9)   S     O/S                  LTJ       SP          1BVT 1475                        W OIAG-ST-0    9YR         1/2-CMP-E-75-021    Per OMN-1 18 QUENCH SPRAY PP DISCH ISOL DIAG-ST-S    9YR           W12-CMP-E-75-021  Per OMN-1
                                                                                                                                                             -TI 0
RPV       9YR         1/2-CMP.E-75021     Per OMN-1 ET    18MO or R      1OST-47.3M           Per OMN-1    C:
Active    3   Diaphragm  MOV     13-1 (E-3)   S      0               DIAG-ST-0    9YR          112-CMP-E-75-021   Per OMN-1     3 MOV.IQS-tO4A      2    B RPV       SYR         112-CMP-E-75-021    Per OMN-1 QS CHEM INJ PP 4A & 4C DISCH tSOL ET    18MO0orR        IOST-13.10A        Per OMN-1     Cn MOV.IOS.1048      2    8     Active    3   Diaphragm  MOV     13-1 (E-3)    S     0               DIAG-ST-O    9YR         1I2-CMP-E-75-021    Per OMN-1            C RPV       9YR         112-CMP-E-75-021     PerOMN-1 0S CHEM INJ PP 4B & 4D DISCH ISOL ET    18WO or R      1OST-13.108          Per OMN-1 CD 5     Active    12    Gale     MOV     13-2 (F-6)   0     OIS                 ST-0       a           1OST-47.3G                       Wn MOV.1RS-1*5A      2 2A OUTSIDE RECIRC SPRAY PP SUCT ISOL                                                                 ST-S        a          1OST-47.3G RPV       2YR          1OST-473G MOV-1RS-1555      2    8     Active    12    Gate     MOV     13-2 (F-6)   0     O/S                 ST-0       0           IOST-47.3M 2B OUTSIDE RECIRC SPRAY PP SUCT ISOL                                                                 ST-S       0           1OST-47.3M RPV       2YR         1OST-47.3M MOV.IRS.156A      2    B     Active    10     Gate    MOV     13-2(0-6)     0    01s              DIAG-ST-O    9YR          112-CMP-E-75-021    Per OMN-1 2A OUTSIDE RECIRC SPRAY PP DISCH ISOL                                                             DIAG-ST-S    9YR         112-CMP-E-54-021    Per OMN-1 RPV       9YR          112-CMP-E-75-021   Per OMN-1 ET    18MO oi R       tOST-47.3G          Per OMN-1 MOV-IRS-1568      2     B    Active    10     Gate     MOV    13-2 (D-8)    0    C/S              OIAG-ST-O    SYR          112-CMP-E-75-021    Per OMN.1 DIAG-ST-S    9YR          112-CMP.E-75-021    Per OMN-1 2B OUTSIDE RECIRC SPRAY PP DISCH ISOL RPV       SYR          1/2-CMP-E-75-021   Per OMN-I ET    18MO or R       IOST-47.3M         Per OMN-I (0CD CD.
                                                                                                                                                              -4 (
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SYSTEM NAME: Containment Depressurization (Quench Spray &,Recirc Spray)                                                              SYSTEM NUMBER:  13 CD      (
Activef    Size   Valve  A(tuator  Drawing          P"iltiou        Rtquired           Code Valve 0ID Name    Class Cat. Passive    (in.)  Type    Type     & Coord    Nonrmal Safety Fail-Safe   Test   Frequency De,. Procedure           Remarks (n      (
RV-IQS-100A         2    C   Active  1.5 x 2.5 Relief   RV     13-1 (('-3)   S   OIS               SPT      10YR         IBVT 1.60.5 0r (1OS-P-4BD) RELIEF RV-1QS-1008         2    C   Active  1.5 x 2.5 Relief   RV     13-1 (F-5)    S   O/S               SPT      1OYR         1BVT 1,60.5 (1QS-P-4B.D) RELIEF CC CL 0)
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Active /     Size  Valve  Actuator   Dnralng           Positioe           Required           Code
                                                                                                                                                                                ~  0)
Valve ID /Name     Class Cat. Passive      (in.) Type    Trype     & Coord   Normal Safety    Fail-Safe   Tert   Frequency Dev. Procedure            Remarks cD)     C RV-ISS-60S            2   A/C    Active     3/4 x I Relief   RV     14A-1 (E-3)   S     O/S                  LTJ       SP          1IBVT 1A7.5 Thermal Relief Valve For Cnmt Penetration 55-1                                                               SPT      1OYR         1BVT 1.60,5 1BVT 1.47.5
_n RV-ISS-606            2    A/C    Active    3W4x 1  Relief   RV     14A-1 (A-3)   S      O0S                 LTJ       SIP (0
Thermal Relief Valve For Cnmt Penetration 56-2                                                               SPT      1OYAR        1BVT 1i60.5 RV-ISS,607            2   A/C    Active     3(4 x I Relief   RV     14A-1 (D-3)   S     O/S                  LTJ       SP           1BVT 1.47.5 Thermal Relief Valve For Cnml Penetration 9"7.2                                                              SPT      10YR         1BVT 1.60.5 RV-1SS-4O             2 A/C       Active 3/4 x 1    Relief   RV     14A-1 (D.3)   S     0IS                  LTJ       SP          IBVT 1.47.5                             CL      C/
Thermal Relief Valve For Cnnml Penetration 56-I                                                              SPT      10YR         I BVT 1.60.5 RV-1SS-609            2   A/C    Active     3/4 x 1 Relief   RV     14A-1 (B-3)   S     O/3                  LTJ       SP          IBVT 1.47.5 (n
Thermal Relief Valve For Cnml Penetration 56-3                                                               SPT      1OYR         1BVT 1.60.5 RVAISS-610            2    A/C    Active    3/4 x I Relief   RV     14A-l (C-3)   S      O/S                 LTJ       SP          IBVT 1.47.5 Thermal Relief Valve For Cnmt Penetration 97-1                                                               SPT      10YR         IBVT 1.60.5 RV-lSS-611            2    NC     Active    3/4 x 1 Relief   RV     14A-1 (E-3)   S      O/S                 LTJ       SIP         1BVT 1.47.5 Thermal Relief Valve For CnntePenetration 105-2                                                              SPT      ICYR         1BVT 1,60.5 TV-ISS.IOGA1          2     A     Active      0.75  Globe    TV     14A-1 (D-3)   0       S          S        LTJ       SP         IBVT 1.47.5 PZR LIQUID SPACE SAMPLE LINE INSIDE CNMT ISOL TRIP                                                          FS-S        a          1OST-47.3K ST-S        Q          1OST-47.3K RPV    2YR/18MO       IOST-47.3K           18 months per Tech. Specs.       0)
TV.1S5-10DA2          2     A     Active      0.75  Globe     TV    14A-1 (D-3)   0       S          S        LTJ       SIP        1BVT 1.47.5 0
PZR LIQUID SPACE SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                         FS-S        Q          I 0ST-47,3J ST-S       0          1OST-47.3J RPV    2YR118MO       10ST-47_3J           18 moeths per Tech. Specs.
TV-sS-S102A1          2     A     Active      0.75  Globe     TV     14A-1(A-3)    S     O/S          S       LTJ       SP         1BVT 1.47.5                             0)   0.
RCS COLD LEG SAMPLE HDR INSIDE CNMT ISOL TRIP                                                                FS-S       0          tOST-47.30 ST-0       0          10ST-47.30 ST-S        0          1OST-47.30 RPV    2YR118MO       1CHM-SAM-3.25        18 months per Tel, Sp

Beaver Valley Power Station Unit I 1ST Program                                                                (D        0 CD VALVE TABLE                                                                                   _
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SYSTEM NAME: Reactor Plant Sample                                                                                                      SYSTEM NUMBER:        14A (D        C Actiwf    Size    Valve Actuator  Drawlin           Positiun           Required            Code Valve 10 / Name Class Cat. Panive    (in.)   Type   TYPe     & Coord    Normal Safety   Fail-Safe   Test    Frequenty Dv. Procedure           Remarks U))
TV.ISS.102A2     2     A    Active  0.75     Globe   TV     14A-1 (A-3)   S     O0S         S        LTJ       SP          1BVT 1-47.5 FS-S        0          1OST-47.3J                            (0         0 RCS COLD LEG SAMPLE HDR OUTSIDE CNMT ISOL TRIP ST-O        Q          1OST-47.3J ST-S        a          IOST-47.3J
                                                                                                                                                                 -n        -
RPV    2YRII8MO        1CHM-SAM-3.25       18 months per Tech. Specs.
1BVT 1.47.5
                                                                                                                                                                 -u      ~
TV.ISS-103AI     2     A    Active  0.75     Globe   TV     14A-1 (0-3)   0      S          S        LTJ       SP CO RHR OUT SAMPLE LINE INSIDE CNMT ISOL TRIP                                                           FS-S        a          IOST-47.3K ST-S        Q          IOST-47.3K RPV    2YPJ18MO        1OST-47.3K          18 months per
                                                                                                                                                                 -0 Tech. Specs.      07 TV-ISS-103A2     2     A    Active   0.75    Globe   TV     14A-1 (D-3)   0      S          S        LTJ       SP          1BVT 1.47.5 C
RHR OUT SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                          FS-S        0          1OST-47.3J ST-S        0          1OST-47.3J                            0)          X RPV    2YR/18MO        IOST-47.3J          18 months per Tech. Specs-TV-1SS-104A1     2     A    Active  0.75     Globe   TV     14A-1 (C-3)   0      $          5        LTJ       SP          1BVT `147.5 CD        -
RHR IN SAMPLE LINE INSIDE CNMT ISOL TRIP                                                            FS-S        0          IOST-47.3K ST-S        a          1OST-47.3K RPV    2YR118MO        1OST-47.3K          18 monlhs per Tech. Specs.
TV-ISS-104A2     2     A    Active  0.75     Globe   TV     14A-1 1C-3)   0      5          5        LTJ       SP          IBVT 1.47.5 RHR IN SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                           FS-S        0          1OST-47.3J ST-S        a          1OST-47.3.J RPV    2YRP18M0        IOST-47T3J          18 months per Tech. Specs, TV-ISS-105At     2     A    Active  0,75     Globe   TV     14A-1 (5-3)   S     O/S         S        LTJ       SP          IBVT 1.47.5 RCS HOT LEG SAMPLE HOR INSIDE CNMT ISOL TRIP                                                        FS-S        0          IOST-47.30 ST-O        0          1OST-47.30 ST-S        Q          IOST-47.30 RPV    2YR118MO        1CHM-SAM-3.25       18 months per Tech. Specs.
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                                                                                                                                                                  -4 CD
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                                                                                                                                                                    -- I' SYSTEM NAME:        Reactor Plant Sample                                                                                                SYSTEM NUMBER:         14A CD          C<
Active / Sire   Valve Actuator  Drawing             Position           Required            Code Valve I1D IName Class Cat,  Passive  (in.)  Type   Type     & Coord    Normnal Safety    Fall-Safe   Test   Freoquemcy Dev. Procedure           Remnarks (0 0 TV-1SS-105A2     2     A     Active  075    Globe    IV    14A-I (6-3)    S     O/S          S       LTJ        SP          1BVT 1.47.5                                    ~CD RCS HOT LEG SAMPLE HDR OUTSIDE CNMT ISOL TRIP                                                       FS-S         a          IOST-47.3J                                    -    C)
ST-O         0          1OST-47.3J ST-S         a          1OST.47.3J (0
RPV    2YRJ18MO        1CHM-SAM-3.25       18 months per Tech. Specs.
                                                                                                                                                                   -n TV.ISS.109AI     2     A     Active  0.75   Globe     V    14A-1 (E-3)    0      S           S       LTJ        SP          1BVT 1.47.5                            0)
SI ACCS SAMPLE HDR INSIDE CNMT ISOL TRIP                                                            FS-S         0          IOST-47.3F ST-S         a          1OST-47.3F                             3 RPV    2YR/I8MO        1OST-47.3F          18 months per      -0 Tech. Specs.
Cn TV.ISS-109A2     2     A     Active  0.75   Globe   TV     14A-1 (E-3)    0      S           S       LTJ        SIP         IVT 147.5 SI ACCS SAMPLE HDR OUTSIDE CNMT ISOL TRIP                                                           FS-S         Q          1OST-47.30 ST-S         a          1OST-47,30 RPV    2YR/18MO        1OST-47.30          18 months per      CD, Tech. Specs.
Ty-ISS-IlIAt      2    A     Active  0.75   Globe   TV     14A-I (D-3)    0      S           S       LTJ        SP          1BVT 1.47.5 PRT GAS SAMPLE LINE INSIDE CNMT ISOL TRIP                                                           FS-S         C          1OST-47,3F ST-S         0          1OST-47,3F RPV    2YR118MO        1OST-47.3F           18 months per Tech. Specs.
TV.1SS-111A2      2    A     Active  0.75   Globe   TV     14A-1 (D-3)    0      S           S       LTJ        SP          1BVT 1.47.5 PRT GAS SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                          FS-S         a          IOST-47.30 ST-S         0          1OST-47.30 RPV    2YRi1aMO        1OST-4730           18 months per Tech. Specs.
0C) CD 1BVT 1.47.5 CD       -A, TV.1SS.112AI      2    A     Active  0.75   Globe    TV    14A-1 (E-3)    0                  S       LTJ        SP PZR VAPOR SPACE SAMPLE LINE INSIDE CNMT ISOL TRIP                                                   FS-S         Q          1OST-47.3F ST-S         a          1OST-47.3F RPV    2YR/18MO        10ST-47.3F          18 months per Tech. Specs.
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VALVE TABLE                                                                             o0      -
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SYSTEM NAME:       Reactor Plant Sample                                                                                                  SYSTEM NUMBER:        14A CD       C Act'*e   Size      Valve Actuator   Drawing            Position           Required           Code                                        :3 vatw 111/ Name Cluss CaI. Pasive   (In.)     Type   Type      & Cooed    Nonnal Safety    Fail-S2af   Test   Frequency Dev. Procedure           Remarks               Ca 0 TV-ISS-112A2     2    A    Active   0.75     Globe    TV     14A-1 (E-3)    0      S            S      LTJ        SID        1BVT 1.47.5 PZR VAPOR SPACE SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                    FS-S        0          1OST-47.30 ST-S         Q         15T-47.30 RPV     2YR/18MO       1OST-47.30          18 months per Tech. Specs.              00 TV-1SS-117A      2    B    Active   0.75     Globe    TV     14A-1 (G-2)    0      S            S     FS-S        0          10ST-47,3M
                                                                                                                                                                   -n 1A SG BLDN SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                         ST-S        a          1OST-47.3M RPV     2YR/18MO       1OST-47,3M          18 months per     0 Tech. Specs.      -0 TV.1SS-1178      2    B    Active   0.75     Globe    TV     14A-1 (F-2)    0      S            5     FS-S        a          1OST-47,3M C
1  SG BLDN SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                         ST-S        0          1OST-47&#xfd;3M RPV    2YR118MO       1OST-47.3M          18 months per Tech, Specs.      -0 TV-1SS.117C      2    8    Active   075       Globe   TV      14A-1 (F-2)   0      S            S     FS-S        0          1OST-47.3M                             Q)      -
1C SG GLON SAMPLE LINE OUTSIDE CNMT ISOL TRIP                                                         ST-S        Q          1OST-47.3M RPV     2YR/tSMO       1OST-47.3M          18 months pee Tech. Specs.
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SYSTEM NAME: Reactor Plant Component Cooling Water                                                                                                 SYSTEM NUMBER:           15 CD  CD Attiv&#xa2;   Sizt      Valse    Actuator  Drawring           Position           Rtquirtd             Code                                              :3 Valve InD Namt   Class Cal. Passive  (in.)     lype      Tvpe     & Coard    Normal Safety    Fail-Safe   Test   Frequency   Dav. Procedure            Remarks             (a   0 ICCR-247           2     A   Active     18    Butterfly           15- (G-1)     LS     0                   LTJ        SID             1BVT 1,47.5                               Cn  CD (RH-E-1A) AND (RH-P.1A) SEAL CLR CCR SUP ISOL                                                              MAN      CSD     VCSJ - 14 IOM-I0.4.C MAN      CSD     VCSJ- 14  1OST-10A4 MAN      CS      VCSJ- 14  1OM-10,4.A
                                                                                                                                                                                -n ICCR-248           2     A   Active     18     Butterfly          15-5 (G-1)    LS     0                   LTJ        SP              1BVT 1,47.5 (RH-E-1B) AND (RH-P-1B) SEAL CLR CCR SUP ISOL                                                              MAN      CSD     VCSJ - 14 IOM-10,4,C MAN      CSD     VCSJ - 14 10ST-10A MAN      CSD     VCSJ- 14  1OM-10.4A                                  a- Cl ICCR-251           2     A   Active     18     Butealfly          15-5 (G-8)    LS      0                   LTJ       SP              1 BVT 1.47.5 (RH-E-1A) AND (RH-P-1A) SEAL CLR CCR RTRN ISOL                                                             MAN      CSD     VCSJ - 14 1OM-10.4-C MAN      CSD     VCSJ- 14  1OM-10,4A MAN      CSD     VCSJ - 14 1OS1-10.4 ICCR-252           2     A   Active     18     Butterfly          15-5 (G-8)    LS      0                   LTJ       SP              IBVT 1.47.5 (RH-E-1S) AND (RH-P-1B) SEAL CLR CCR RTRN ISOL                                                             MAN      CSD     VCSJ - 14 1OM-10.4.C MAN      CSD     VCSJ- 14  10ST-10.4 MAN       CSD    VCSJ - 14 1OM-10.4A 2       Check             15-5 (C-3)    0       S                CV-S-LT       R    VROJ .35  1BVT 1.60.7 1CCR-289           3    A/C  Active toC RCP 1A THERM BARR CCR IN CHECK                                                                           CV-BDT-O    NSO              ISTC-3550            During operation of CD RCP LT      2YR              1BVT 1.60.7 ICCR-290           3    A/C  Active      2      Check             15-5 (D-3)     0      S                 CV-S-LT      R    VROJ - 35  1BVT 1.60.7 0
RCP 1B THERM BARR CCR IN CHECK                                                                           CV-BDT-0   NSO               ISTC-3550            During operation of RCP LT      2YR              1BVT 1,60.7                               0C)
ICCR-291           3    A/C  Active      2      Check              15-5 (F-3)    0      S                 CV-S-LT      R    VROJ -35  1BVT 1.60.7 RCP 1C THERM BARR CCR IN CHECK                                                                           CV-BDT-0   NSO               ISTC-3550            During operation of RCP LT       2YR              IBVr 1.60.7 1CCR-4             3     C   Active     18      Check              15-1 (E-6)  G/S     OS                  CV-0        0              10ST-15.1 CCR PP 1A DISCH CHECK                                                                                      CV-S        0              1OST.15,2 CV-S        Q              1OST-15.3

Beaver Valley Power Station Unit I IST Program                                                                         (D CD         W VALVE TABLE 0~0 SYSTEM NAME: Reactor Plant Component Cooling Water                                                                                            SYSTEM NUMBER:  15 CD Code CD)
Active I su     Valve    Actuator  Drawing           Position           Rrquired 0o Valve 10 1 Name   Class Cat Passve   (in.)  Type      Type     & Coord   Normal Safety    Fail-Sgfe   Tell   Frequesncy    Dev*. Procedure           Remarks 1CCR-5              3    C  Active     18  Check              15-1 (E-7)  OIS    O/S                 CV-0        0                IOST-15.2                      C/)        CD CCR PP IB DISCH CHECK                                                                                CV-S        a                1OST-15.3                           -     C/)
CV-S        Q                IOST-15.1 ICCR-6              3    C  Active     18  Check              15-1 (E-8)  0/S    O/S                 CV-O        0                IOST-15.3 CCR PP 1C DISCH CHECK                                                                                CV-S        0                1OST-15.2                      -n CV-S        0                IOST-15.1                      0)
MOV.ICC-112A2       2    A  Active     18  Butterfly  MOV     15-5 (A-7)   S     O/S                  LTJ        SP               1BVT 1A7.5 (RH-E-1A) CCR IN CNMT ISOL                                                                           ST-O        a                10ST-47.3K ST-S        0                IOST-47.3K ST-O       CSD     VCSJ- 13  1OM-10.4.C ST-O       CSO     VCSJ- 13  1OM-10.4.A ST-O       CSO     VCSJ- 13  IOST-104 1OM-104.A                      CD ST-S       0S0     VCSJ- 13 ST-S       CSO     VCSJ- 13  1OST-10.4 ST-S       CSD     VCSJ- 13  1OM-10.4.C RPV       2YR               IOST-47.3K RPV       2YR               IOST-10.4 MOV.ICC-112A3       2    A  Active     18  Butterfly  MOV     15-5 (F-7)   S     0/S                   LTJ       SP               1BVT 1.47.5 (RH-E-1A) CCR OUT CNMT ISOL                                                                          ST-o        a                IOST-47.3K ST-S        0                10ST-47,3K ST-O       CSD     VCSJ - 13 1OM-10.4.A CD 4 ST-O       CSD     VCSJ - 13 IOST-10,4 ST-O       CSD     VCSJ- 13  IOM-10.4.C ST-S      CSD     VCSJ - 13 IOM-10.4.A                     0~
ST-S       CSD     VCSJ - 13 1OST-10i4 0-I ST-S       CSD     VCSJ- 13  IOM-10.4,C RPV       2YR               IOST-10.4 RPV       2YR               1OST-47.3K C:) CD)

Cn CD Beaver Valley Power Station Unit 1 IST Program                                                              CD        a)
VALVE TABLE                                                                                      CD CD        <
SYSTEM NAME:         Reactor Plant Component Cooling Water                                                                                       SYSTEM NUMBER:  15 -i        2)
CD        C Active I  Size    Valve    Actuator  Drawing          Posittin           Required             Code Valve ID /Name   Class Cat. Passive   (in.)   Type       Type    & Coord   Normal Safety   Faiil-Sac   'rest  Frequency   Dev. Pru-cdure             Remarks              0, MOV-ICC-112B2      2    A    Active      18   Butterfly   MOV    15-5 (A-8)   S     O/S                  LTJ       SP              1BVT 1.47.5 ST-O                        1OST-47.3F (RH-E-18)CCR IN CNMTISOL ST-S        a                1OST-47.3F ST-O      CSD     VCSJ- 13 1OM-10.4,C                              Co ST-O      CSD     VCSJ - 13 1OM-10.4.A                       0)
ST-O      CSO     VCSJ - 13 IOST-10.4 ST-S      CSD     VCSJ - 13 IOM-10*A                          3 ST-S      CSD     VCSJ - 13 1OST-10.4                        -n 0
ST-S      CSD    VCSJ - 13  IOM-10.4.C IOST-47.3F
                                                                                                                                                                    -0 RPV       2YR                                               C:
RPV       2YR                1OST-10.4                       3
                                                                                                                                                                    -0 MOV-1CC-112B3      2    A    Active      18   Butterfly    MOV   15-5 (F-8)    S    O/S                  LTJ       Sp               1BVT 1.47.5 (RH-E-1 B) CCR OUT CNM"T SSOL                                                                          ST-O        0                1OST-47.3F ST-S       0                1OST-47.3F                      CD, ST-O       CSD    VCSJ. 13 1OM-10.4.A ST-0       CSD    VCSJ- 13   1OST-10,4 ST-O       CSO    VCSJ- 13   1OM-104.C ST-S      CSD    VCSJ - 13  IOST-10.4 ST-S      CS0    VCSJ - 13  1OM-10.4.A ST-S      CSD    VCSJ- 13   1ON-10A.C RPV      2YR               1OST-47.3F RPV      2YR               1OST-10.4 RV-lCC-109         3    C    Active   3/4 x 1  Relief       RV   15-2 (E-?)    S    O/S                  SPT     10YR               IBVTr 1,60.5 0C)Q.
SEAL WATER HX (CH-E-l) CCR RELIEF CD        -
RV-ICC-116A        3    C    Active   3/4 x 1  Relief       RV   15-5 (C-3)    S    O/S                  SIT     10YR               18VT 1.60.5 Ni)<
RCP IA THERM BARR CCR RELIEF RV-ICC-1 168       3    C    Active   3/4 x 1  Relief       RV   15-5 (0-3)    S    OS                   SPT      10YR              1BVT 1.605 RCP 1B THERM BARR CCR RELIEF RV-1CC-1116C       3    C     Active  3/4 x 1  Relief       RV   15-5 (E-3)    S    OS                   SPT      10YR              18VT 1.60,5 RGP IC THERM BARR CCR RELIEF 0,
0 C:)    :

0(D Beaver Valley Power Station Unit I IST Program VALVE TABLE                                                                          (9 <
SYSTEM NAME:          Reactor Plant Compone nt Cooling Water                                                                               SYSTEM NUMBER:  is   --4     M)
Valve    Actuator  Drawing          Position         Required           Code (D     ~
Active I  Size Valve ID I Name   Class Cat. Passive   (n.)     Type        Type   & Coord   Normal Saftty Fail-Safe   Test   Frequeney Dev. Procedure            Remarks Co 0 RV.ICC-119A        3     C    Active   3/4 x I   Relief       RV   15-5 (F-5)   S     OIS               SPT      1OYR         1BVT 1860.5
                                                                                                                                                              .-       CD)
(RH-Ev1A) CCR RELIEF RV.ACC-1198        3     C    Active   3/4 x I   Relief       RV   15-5 (G-5)   S     OS                SPT      l0YR         1BVT 1,60.5 (RH-E-1B) CCR RELIEF
                                                                                                                                                                -n RV-1CC-136A         3    C    Active   3/4 x I   Relief       RV   15-5 (G-3)   S     O0S               SPT       1OYR        18VT 1.60.5 0)
SEAL. CLR (RH-P-1A) CCR RELIEF RV-1CC-136B         3    C    Active   3/4 x 1   Relief       RV   15-5 (G-3)   S     OS                SPT      10YR         1BVT 1.60.5 SEAL CLR (RH-P-1B) CCR RELIEF                                                                                                                                   r-1 RV-1CC-139A         3    C    Active   314 x I   Reflef       RV   15-4 (B-6)   S     O0S               SPT       IOYR        16VT 1.60.5                       3 CNMT PEN 52 OUTER CLG COIL CCR REUEF RV-1CC-1398         3    C    Active   314 x 1   Relief       RV   15-4 (B-6)   S     O.1               SPT       I OYR       I8VT 1.60.5 CNMT PEN 39 OUTER CLG COIL CCR REUEF                                                                                                                            CD, RV-1CC-139C         3    C    Active   314)x 1   Relief       RV   15-4 (B-6)    S    O/S               SPT       I YR        1BVT 1.60.5 CNMT PEN 51 OUTER CLG COIL CCR REUEF RV.1CC-1390         3    C    Active   3/4 x 1   Relief       RV   15-4 (C-6)    S    O/S               SPT       I OYR        1BVT 1.60.5 CNMT PEN 41 OUTER CLG COIL CCR RELIEF RV.1CC-139E         3    C    Active   314 x 1   Relief       RV   15-4 (D-6)    S    O/S               SPT       1OYR        1BVT 1.60.5 CNMT PEN 40 OUTER CLG COIL CCR RELIEF RV-1CC-13OF         3    C    Active   314 x 1   Relief       RV   154 (E-8)     S    O/S               SPT       IOYR        18VT 1.60.5 CNMT PEN 28 OUTER CLG COIL CCR RELIEF RV-ICC-139G         3    C    Active   314 x 1   Relief       RV   15-4 (E-6)    S    OIS               SPT       IOYR        1BVT 1.60.5                      0.
CNMT PEN 76 OUTER CLG COIL CCR RELIEF RV-ICC-139H         3    C    Active   3/4 x 1   Relief       RV   15-4 (E-6)    S    OS                SPT       10YR        1BVT 1.60.5 CNMT PEN 73 OUTER CLG COIL CCR RELIEF RV-ICC-1391         3    C    Active   314 x 1   Relief       RV   15-4 (F-6)    S    O/S               SPT       1 YR        18VT 1.605 CNMT PEN 77 OUTER CLG COIL CCR RELIEF C: C)

CD     0)
Beaver Valley Power Station Unit 1 IST Program CD <
VALVE TABLE SYSTEM NAME:        Renctor Plant Component Cooling Water                                                                                  SYSTEM NUMBER:  15 CD Active 1   Size    Valve   Actuator  Drawing           Position           Reqtzred           Code Valve ID / Name Class Cat. Pmsive     (in.)   Type      Type   & Coord    Normal Safety    Fail-Safe   "'est  Frequency Dev. Procedure            Remarks           00 S      O0S                 SPT      10YR         1BVT 1.60.5                     Cj)    CD RV-lCC.139J       3    C    Active   314 x 1  Relief      RV    15-4 (F-6)
CNMT PEN 74 OUTER CLO COIL CCR RELIEF                                                                                                                         -4     -
RV-tCC-139K      3     C    Active   3/4 x I  Relief      RV    15-4 (F-6)   S      O/S                 SPT      10YR         1BVT 1.60.5 CNMT PEN 78 OUTER CLG COIL CCR RELIEF                                                                                                                         -n    ~
RV-ICC-139L       3    C    Active   314 x 1  Relief      RV    15-4 (G-6)   S      c/S                 SPT      10YR          1BVT 1.60.5 CNMT PEN 75 OUTER CLG COIL CCR RELIEF IOYR         IBVT 1.60.5 Cn RV-1CC1395M       3    C    Active   34 x 1   Relief      RV    15-4(0-6)    S      O/S                 SPT CNMT PEN 56 OUTER CLG COIL CCR RELIEF                                                                                                                         <
RV-ICC-139N       3    C    Active   314 x 1   Relief     RV    15-4 (D-6)   S      O/S                 SPT      10YR          18VT 1.60.5 CNMT PEN 97 OUTER CLG COIL CCR RELIEF RV-tCC.139P       3    C    Active   3/4 x 1  Relief      RV    15-4 (C-6)   S      OS                  SPT      1OYR         1BV' 1.60.5 CNMT PEN 105 OUTER CLG COIL CCR RELIEF RV-ICC-139R       3    C     Active  3/4 x 1   Relief     RV    15-4 (C-6)   S      O/S                 SPT      10YR          18VT 1.60.5 CNMT PEN 110 OUTER CLG COIL CCR RELIEF RV-1CC-261        2   ANC    Active  3/4 x 1   Relief     RV    15-5 (F-2)    S     CIS                  LTJ       SP         18VT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 1                                                                   SPT      lOYR         1BVT 1.60.5 RV-ICC.262        2   ANC    Active  3/4 x 1   Relief     RV    15-5 (G-7)   S      OS                   LTJ       SI          18VT 1.47.5 SPT       10YR         18VT 1.60.5                    CD THERMAL RELIEF FOR CNMT PENETRATION 2 RV-ICC-263        2   A/C    Active  3/4 x 1   Relief     RV    15-5 (G-2)    S     O/S                  LTJ       SP          18VT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 5                                                                   SPT      1OYR         18VT 1.60.5 0.
RV-11CC-264       2   ANC    Active  3/4 x 1   Relief     RV    15-5 (F-7)    S     O/S                  LTJ       SP         1BV'  1.47.5 SPI       10YR         18VT 1.60.5                    (J) 0    .
THERMAL RELIEF FOR CNMT PENETRATION 4 "D :3 RV-ICC-265        2   A/C    Active  3/4 x 1   Relief     RV    15-5 (E-9)    S     OS                   LTJ       SI          1BVWT1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 8                                                                   SPT      10YR          18VT 1.60.5 RV-ICC-266        2   ANC    Active  3/4 x 1   Relief     RV    15-3 (F-4)    S     O/S                  LTJ       SP         1BVT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 9                                                                   SPT       1OYR         1BVT 1.60.5 C:) CD)

Beaver Valley Power Station Unit 1 IST Program VALVE TABLE SYSTEM NAME:        Reactor Plant Component Cooling Water                                                                                      SYSTEM NUMBER:             15     D   0)
Atifve/   Size    Valve    Actuator  Drawing           Position         Required              Code                                                   _   CD Valve ID/Name   Class Cai. Passive   (1i.)   Type        Type   & Coord    Normal Safe"ty Fa2-Safe   Tets    Frequency   Dev. Procedure                 Remarks RV-ICC-267        2   A/C   Active  3f4 x 1   Relief       RV   29-2 (E-9)    S     O/S                LTJ        SP              IBVT 1,47.5
                                                                                                                                                                              -n     -
THERMAL RELIEF FOR CNMT PENETRATION 11                                                                SPT       10YR               1BVT 1.60.5 CD RV-1CC-268        2   A/C   Active  3/4 x I   Relief       RV   29-2 (A-3)    S     O/S                LTJ        SP              1BVT 1.47.5
                                                                                                                                                                             -4      0 THERMAL RELIEF FOR CNMT PENETRATION 14                                                                SPT       10YR              1BVT 1.60.5 RV-ICC-269        2   A/C   Active  3/4 x 1   Relief       RV   15-3(S-8)     S     O/S                LTJ        SP               1BVT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 16                                                                SPT       10YR               10VT 1.60.5                                CD   ~
RV-tCC-270        2   AIC   Active  3/4 x 1   Relief       RV   15-5 (C-2)    S     O/S                LTJ        SP               1BVT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 17                                                                SPT       10YR               1BVT 1.60.5 RV.1CC-271        2 A/C Active      3/4 x I   Relief       RV   15-5 (E-2)    S     O/S                LTJ        SP              IBVT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 18                                                                SPT       10YR              18VT 1.60.5 RV-1CC-272        2   A/C   Active  3/4 x I   Relief       RV   15-5,(0-9)    S     O/S                LTJ        SP               1BVT 1,47.5 THERMAL RELIEF FOR CNMT PENETRATION 25                                                                SPT       10YR               1BVT 1.60.5 RV.lCC-273        2   A/C   Active  3/4 x 1   Relief       RV   15-5(8.9)     S     O/S                LTJ        SP              IBVT 1.47.5 THERMAL RELIEF FOR CNMT PENETRATION 26                                                                SPT       10YR               iBVT 1.60Z RV-1CC-274        2   ANC   Active  314 x 1   Relief       RV    15-5 (A-9)   S     01S                LTJ        SP              IBVT 1.47.5
                                                                                                                                                                              ~CD THERMAL RELIEF FOR CNMT PENETRATION 27                                                                SPT       10YR              IBVT 1.60.5                                     Ul <
RV.lCC.275        2   A/C   Active  3/4 x 1   Relief       RV    15-5 (B-2)   S     O/S                LTJ        SP              16VT 1.47.5 SPT       10YR               1BVT 1.60.5                                 (0 THERMAL RELIEF FOR CNMT PENETRATION 58 Globe        TV   15.5(B-1)     0       S        S       LTJ        SP              1BVT 1.47,5 0C:)
TV-ICC-103A       2    A    Active      6 RCP 1A CCR IN CNMT ISOL                                                                                ET      CSD or R VROJ - 33  IOST-1.10                PerOMN-12 FS-S     CSD or R VROJ - 33 IOST-..10 DIAG-ST-S    6YR               1/2M[-75-Uitracheck A-l1 Per OMN-12 RPV     2YRJI8MO             lOST-l1D                 18 monlhs per Tech. Specs.

(n         CD Beaver Valley Power Station Unit I 1ST Program                                                                                CD         0)
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SYSTEM NAME:         Reactor Plant Component Cooling Water                                                                                           SYSTEM NUMBER:              15 (D         C Active I Size     Valve     Actuatur  Drawing           Position            Required              Code Remoarks
_U Valve ID01 mune  Class Cal. Passive  (in.)    Type        Type    & Coord    Normal Safety   Fail-Safe    Tet     Frequency   Dev. Procedure (a          0 6      Globe        TV    15-5 (B-3)    0      S          S        LTJ        SP               I   VT 1,47.5 TVAICC-1O3A1      2     A    Active VROJ - 33 1OST-1.10                  Per OMN-12 C/)        CD RCP IA CCR IN CNMT ISOL                                                                                     ET     CSO or R FS-S    CSD or R  VROJ - 33 IOST-1-O                                           -     C)
DIAG-ST-S     6YR               12MI-75-U1trachech A-il   Per OMN-12                    0)
RPV    2YRJ18MO             1OST-t.10                  18 months per     (a Tech. Specs.
TV.ICC-1031       2     A     Active    6      Globe        TV    15-5 (-p)     0      S           S        LTJ        SP              18VT 1.47.5                                   71 0)
ET     CSD or R  VROJ - 33 1OST-1.10                  Per OMN-12 RCP 19 CCR IN CNMT ISOL FS-S    CSDor R   VROJ. 33  IOST-1.10 DIAG-ST-S    6YR               1W2MI-75-Ultracheck A-11   Per OMN-12 RPV    2YRII,8MO             1OST-1.10                 18 months per Tech Specs.
0      S           S        LTJ        SP              1BVT 1.47.5                                   (n TV-1CC-103B1       2    A    Passive    6      Glob:e       TV    15-5 (C-3)
ET     CSD or R  VROJ - 33  IOST-1.10                 Per OMN-12 RCP 18 CCR IN CNMT ISOL FS-S    CSDorR    VROJ. 33   IOST-1,10                                    =3 DIAG-ST-S     6YR               112M1-75-UltracheckA-11   PerOMN-12 RPV    2YR/1 8MO             I OST-1 10                18 months per Tech. Specs.
TV-CC-103C        2    A     Active    6      Globe        TV    15-5 (E-1)    0       S          S        LTJ        SP               1IVT 1.47.5 Er    CSDorR    VROJ - 33  1OST-1.10                 PerOMN-12 RCP IC CCR IN CNMT ISOL FS-S    CSO or R  VROJ- 33   10ST-1.10 DIAG-ST-S     6YR               1,2MI-75-UPracheck A-1I   PerOMN-12 RPV    2YR118MO              1OST-1.10                  18 months per Tech. Specs.
MTICC-103C1       2    A     Active    6      Globe        TV     15-5 (E-3)   0       S          S        LTJ        SP               1BVT 1.47.4 ET    CSDorR    VROJ - 33  1OST-1.10                 PerOMN-12             CD RCP 1C CCR IN CNMT IOL                                                                                                                                                                         -
FS-S    CSD or R  VROJ- 33   1OST-110 DIAG-ST-S     6YR               1/2M1I-75-Ultracheck A-1I Per OMN-12 RPV   2YRI18MO              1OST-1,10                  18 months per Teca. Specs 0)<
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Beaver Valley Power Station Unit IIST Program                                                                              CD       Q)
CD VALVE TABLE                                                                                          0.       -
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SYSTEM NUMBER:             15  -- i     a SYSTEM NAME: Reactor Plant Component Cooling Water                                                                                                                          CD Actvel  Size   Valve Actustor  Drawing           Position            kRtquired             Cod&
Valve ID IN amoe Class Cat. Passive (in.)  Type    Type    & Coord    Normal Safety   Fati-Safe    Test    Frequency   Dew. Procedure                  Remarks Cn TV.ICC,105D1      2     A   Active    6    Globe    TV    15-5 (E-8)    0      S          S         LTJ        SP              IBVT 1.47.5 RCP MOTORS IB AND 1C CCR OUT HDR CNMT ISOL                                                         FS-S     CSD or R VROJ - 33 IOST-1.10                                   (0         0 ST-S     CSDorR   VROJ - 33 1OST-I.10 RPV     2YR/t8MO            lOST-1.10                  18 months per Tech. Specs.      -n       -
TV-ICC-105D2       2    A   Active    6    Globe    TV     15-5 (E-9)   0      S          S         LTJ        SP              1BvIr 1,47.5                                -C        Ci RCP MOTORS 18 AND 1C CCR OUT HOR CNMT ISOL                                                         FS-S     CSD or R VROJ - 33 lOST-I.10 ST-S     CSDorR   VROJ - 33  lOST-1.10 RPV     2YRf18MO            IOST-I.10                  18 months per Tech. Specs. CL TV-1CC.105E1       2    A   Active    4    Globe    TV     15-5 (A-8)   0      S          S         LTJ        SP                BVT' 1.47.5 RCP MOTOR 1A CCR OUT HOR CNMT ISOL                                                                 FS-S     CSD or R VROJ - 33  IOST-t.10 ST-S     CSD or R VROJ-33   lOST-I.10 RPV     2YR/18MO            lOST-1.10                  I8 months per Tech. Specs.
TV.ACC-105E2       2    A   Active    4    Globe    TV    15-5 (A-10)   0      S          S         LTJ        SP              IBVT 1.47.5 RCP MOTOR 1A CCR OUT HOR CNMT ISOL                                                                 FS-S     CSD or R VROJ - 33 IOST-l.10 ST-S     CSD or R VROJ - 33 lOST-1l10 RPV     2YR1l1MO            IOST-!.10                  18 months per Tech. Specs.
TV-ICC-107A        3    A   Active    2    Globe    TV    15-5 (C-6)    0      S          S         ET      CSDorR   VROJ- 34   lOST-li0                  Per OMN-12 RCP 1A THERM BARR CCR OUT ]SOL                                                                     FS-S     CSD or R VROJ - 34  lOST-t,10 DIAG-ST-S     6YR              112MI-75-Ultracheck A-1I   Per OMN-12        00D RPV        6YR              t/2MI-75-Ultracheck A-1I   Per OMN-12 LT       2YR               IBVT 1.60.7                                *0 TV.ICC-107B        3    A   Active    2    Globe    TV    15-5 (D,-6)   0      S          S         ET      CSD or R VROJ - 34  IOST-i.10                 Per OMN-12 tOST-l.10 0~
RCP lB THERM BARR CCR OUT ISOL                                                                     FS-S     CSDorR   VROJ - 34 OIAG-ST-S     6YR               SI2MI-75-JJtracheck A-1 I Per OMN-12             0 0 RPV        6YR               112MI-75-Utlracheck A-l   Per OMN-12 LT       2YR               IBVT 1.60.7

5       wo to      CD Beaver Valley PowerStation Unit 1 IST Program                                                                             CD      0)
VALVE TABLE                                                                                              CD D 0~0 SYSTEM NAME:         Reactor Plant Component Cooling Water                                                                                        SYSTEM NUMBER:             15  CD Active / Size     Valve    Actuator  Drawing           Position           Required             Code                                                 (D      C Valve ID I Name Class Cat,   Passive  (in.)    Type        Type   & Coord   Normal Safety    Fail-Saf    Test   Frequency   Dev. Procedure                  Remarks 00 TV-ICC-107C       3     A    Active     2      Globe        TV   15-5 (F-8)   0      S           S        ET     CSD or R VROJ - 34  1OST-1,10                 Per OMN-12 RCP IC THERM BARR CCR OUT ISOL                                                                           FS-S    CSD or R VROJ - 34  1OST-1.10                                   C-      CD, DIAG-ST-S    6YR               1/2M1I-75-UIhracheck A-II Per OMN-12 RPV       6YR               1/2MI-75-Ultracheck A-1I  Per OMN-12 LT       2YR               1BVT 1.60.7                                (0       =
TV-1cC-10701      2     A    Active     3      Globe        TV   15-5 (E-8)   0      S           S        LTJ       SP               1VST 1.47.5 1OST-l.10                 Per OMN-12 3
RCP 18 AND IC THERM BARR CCR OUT CNMT ISOL                                                                ET     CSDorR   VROJ -33 FS-S    CSO or R VROJ - 33  1OST-1,10                                   0 DIAG-ST-S    6YR               1,2MI-75-Ultracheck A-11  Per OMN-12 RPV    2YRJ18MO             IOSr-1.10                 18 months per Tech. Specs,      Cn TV-ICC-tOTD2      2     A    Active     3      Globe        TV   15-5 (E-9)   0       S          S        LTJ       SP               1BVT 1.47.5 RCP IB AND IC THERM BARR CCR OUT CNMT ISOL                                                                ET     CSD or R VROJ - 33  lOST-110                  Per OMN-12 FS-S    CSDorR   VROJ - 33  10ST-110 DIAG-ST-S    6YR               1/2MI-75-Ultracheck A-lI  Per OMN-12        0)      C M-RPV    2YR/18MO             lOST-1,10                 18 montis per             X.
Tech. Specs.
TV-1CC-10TE1      2     A    Active     2      Globe        TV   15-5(8-8)    0      S           S        LTJ       SP               IBVT 147.5 ET     CSD or R VROJ - 33 lOST-1.10                  Per OMN- 12 RCP IA THERM BARR CCR OUT CNMT ISOL FS-S    CSDorR   VROJ - 33  lOST-1,10 DIAG-ST-S    6YR               1/2M1- 75-Ultracheck A-1I PerOMN-12 RPV    2YRI18MO             lOST-1.10                 18 months per Tech. Specs.
TV-ICC-107E2      2     A     Active    2      Globe        TV   15-5 (B-9)   0       S          S        LTJ       SP               1BVT 1.47.5 RCP IA THERM BARR CCR OUT CNMT ISOL                                                                        ET    CSD or R VROJ - 33  lOST-110                  Per OMN-12 FS-S    CSD or R VROJ - 33  lOST-1A10 DIAG-ST-S    6YR               1/2MI-75-Ultracheck A-I1  Per OMN-12 RPV    2YR'1SMO             1OST-1A0                  18 months per Tech. Specs.
TV-1CC-110D       2     A     Active    8      Globe        TV   29-2 (E-9)   0       S          S        LTJ       SP               1BVT 1.47.5 CNMT RECIRC CLG COILS CHILLED WATER OUT CNMT ISOL                                                        FS-S      CSD    VCSJ - 11  lOST-D10 ST-S      CSD    VCSJ - 11  1OST-l1,0 RPV       2YR               lOST-1,10                                   -U0 SCD CD .0 00CD 0(0 00

cn CD Beaver Valley Power Station Unit I IST Program                                                                        (D       a)
_   CD VALVE TABLE CD       <
SYSTEM NAME:        Reactor Plant Component Cooling Water                                                                                         SYSTEM NUMBER:         15 CD       CD Active I Size     Valve     Actuator   Ora*ing           position          Required              Cade 00 Valve ID / Name Class Cat. passive  (in.)    Type       Type      & Coord   Normal Safety   Fall-Safe   Test    Frequency   Dev. Procedure            Remarks TV.ICC-110E2     2     A    Active     8      Globe       TV      29-2 (A-2)   0      S          S       LTJ        SP               1BVT 147.5                             Cf5 CD CNMT RECIRC COO*ING COILS AC CHILLED WATER SUP CNMT ISOL                                                FS-S       CSD     VCSJ -11  1OST-1.10 ST-S       CSD     VCSJ- 11 IOST-I.10 RPV       2YR                lOST-i.10 TV-ICC-110E3      2    A    Active     8      Globe       TV      29-2 (A-3)   0      S          S       LTJ        SP               1BVT 1-47.5                            -n CNMT RECIRC COOLING COILS AC CHILLED WATER SUP CNMT ISOL                                                FS-S       CSD     VCSJ - 11 IOST-1.10 0)
ST-S       CSD     VCSJ- 11  lOST-l10 RPV       2YR               1OST-1.10 31 7V-ICC-II0F1      2    A    Active     8      Globe       TV     29-2 (E-10)   S      S          S       LTJ        SP               IBVT 1.47.5                            -0 CNMT RECIRC COOLING COILS OUTLET TO RW CNMT ISO.                                                        FS-S       CSD     VCSJ -lo  IOST-I.10                              Cn ST-S       CSD     VCSJ- 10  IOST-110 RPV       2YR               IOST-I, 10 TV-ICC-11OF2      2    A    Active     8      Globe       TV     29-2 (F-10)   0                 S       LTJ        SP               18VT 147.5 CD CNMT RECIRC COOLING COILS AC CHILLED WTR RTRN CNMT [SOL                                                 FS-S       CSD     VCSJ - 11 lOST-1.10 ST-S       CSO     VCSJ- 11  IOST-1.10 RPV       2YR                 tOST-1.10 TV-ICC-111AI      2    A    Active     6      Globe       TV      15-3 (B-8)   0      5          S       LTJ        SP               IBVT I47.5 CROM SHROUD CLG COILS CCR INCNMT ISOL                                                                   FS-S       CSD     VCSJ - 12 IOST-1.10 ST-S       CSD     VCSJ- 12  lOST-1.10 RPV    2YRI18MO             IOST-1.10             I8 months per Tech. Specs.
W TV-1CC-111A2      2    A    Active     6      Globe       TV      15-3 (B-8)   0      S          S       LTJ        SP               IBVTr 1.47.5 CROM SHROUD CLG COILS CCR INCNMT ISOL                                                                   FS-S       CSD     VCSJ - 12 1OST-1.10 ST-S       CSO     VCSJ - 12 IOST-1-10 0.
RPV    2YR/18MO             1OST-1.10            IS months per Tech. Specs,         0)    -
TV-1CC-11101      2    A    Active     6      Globe       TV      15-3 (F-4)   0            S            LTJ        SP               1BVT 1.47.5 CRDM SHROUD CLG COILS CCR OUT CNMT ISOL                                                                 FS-S       CSD     VCSJ - 12 IOST-1.10 ST-S       CSD     VCSJ- 12  lOST-1,10 RPV    2YRJ18MO             loST-1.10            18 months per Tech. Specs, 0    0D

cn co Beaver Valley Power Station Unit I IST Program                                                                       CD D0 D
VALVE TABLE SYSTEM NUMBER:        is (D      <
SYSTEM NAME:       Reactor Plant Component Cooling Water Active J Site     Valve    Actuator  Drawing          Potiton          Required              Code                                         CD     ~
Valve TDOName  Class Cat. Passive  (in.)     Type      Type    & Coord   Normal Safely Fail-Sare   Test    Frequency   Dev. Procedure           Remarks TV-1CC-11102     2    A    Active     6      Globe       TV    15.3 (G-4)   0      S        S       LTJ         SP              1BVT 1.47.5 CRDM SHROUD CLG COILS CCR OUT CNMT ISOL                                                            FS-S       CSD     VCSJ - 12 1OST-1.10                             0o     0 ST-S       CSD     VCSJ- 12 1OST-1.10 RPV    2YR~i8MO             1OST-110            18 months per    ~3C Tech. Specs.
V-ICC4121-1     3    8    Ac;tve     2      Globe       TV    15-5 (B-1)   0      S        S      FS-S         a                1OST-47.3H REFUEL WATER REFRIG UNITS CCR IN ISOL                                                              ST-S         a                IOST-47.3H                          (0 RPV        2YR               1OST-47&#xfd;3H TV-ICC-121-2     3    B    Active     2      Globe       IV    15-5 (F-2)   0      S        S      FS-S         a               1OST-47,3H REFUEL WATER REFRIG UNITS CCR OUT ISOL                                                             ST-S         a                IOST-47.3H                          -0 RPV        2YR               iOST-47.3H 3    B    Active     6      Globe       TV    15-2 (A-3)   0      S        S      FS-S          0               1OST-47.3J                          Cn TV-1CC-125 DEGAS EQUIP CCR INISOL                                                                             ST-S         a                1OST-47.3J RPV        2YR               1OST-47.3J TV.ICC-125-1     3    8    Active     6      Globe       TV    15-1 (F-5)   0      S        S      FS-S         a                1OST-47.3J DEGAS EQUIP CCR OUT ISOL                                                                           ST-S          0               1OST-47.3J                          a,)
RPV        2YR               1OST-47,3J TV-ICC-125-2     3    B    Active     6      Globe       TV    15-1 (F-5)   0      5        S      FS-S         a                IOST-47.3J DEGAS EQUIP CCR OUT ISOL                                                                           ST-S         a                1OST-47.3J RPV        2YR               IOST-47.3J TV-ICC-126       3    B    Active     8      Globe       TV    15-2 (A-4)   0      S        S      FS-S         Q                IOST-47.3J BORON EVAP 1A EQUIP CCR IN ISOL                                                                    ST-S          0               1OST-47.3J RPV        2YR               1OST-47.3J                             Z' TV-1CC-126-1     3    B    Active     8      Globe       TV    15-1 (G-7)   0      S        S      FS-S         0                1OST-47.3J BORON EVAP 1A EQUIP CCR OUT ISOL                                                                   ST-S          0               1OST-47,3J RPV        2YR               IOST-47.3J TV-ICC-126-2     3    B    Active     8      Globe       TV    15-1 (0-8)   0      S        S      FS-S         0                IOST-47.3J BORON EVAP 1A EQUIP CCR OUT ISOL                                                                   ST-S         a                1OST-473J RPV        2YR               iOST-47.3J (0 CD CD CA)<
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(n      (D Beaver Valley PowerStation Unit 1IST Program                                                             CD       0)
VALVE TABLE                                                                                CD SYSTEM NAME:        Reactor Plant Component Cooling Water                                                                                   SYSTEM NUMBER:  15  (D      (D Active I Size     Valve    Actuator  Drawing            Position           Required           Code
                                                                                                                                                                    ~   0)
Valve ID NIame  Clais Cat. Passive  (in.),    Type       Type   & Coord    Normal Safety    Fall-Safe   Test   Frequency Dev. Frocedure            Remarks    CD       C (is TV-CC-127         3    B    Active     8      Globe        TV   15-2 (B-5)    0      S           S      FS-S        a           1OST-47.3J BORON EVAP 18 EQUIP CCR IN ISOL                                                                         ST-S        a           1OST.47.3J                     (0       0 RPV       2YR         IOST-47.3J                      cc       C TV.ICC.1 27.1     3    B    Active     8      Globe        TV    15-1 (F-9)   0      S           S      FS-S        Q           IOST-47.3J BORON EVAP 1B EQUIP CCR OUT ISOL                                                                        ST-S        a           1OST-47.3J 0)
RPV       2YR          1OST-47,3J 3
TV-1CC-127-2      3    B    Active     8      Globe        TV   15-1 (E-9)    0      S           S      FS-S        a           10ST-47,3J                      -n 0
BORON EVAP lB EQUIP CCR OUT ISOL                                                                        ST-S        Q           IOST-47.3J RPV       2YR          1OST-473J                       -0 C:
TV-1CC.129        3    B    Active     6      Globe        TV   15-2 (A-10)   0      S           S      FS-S        0           1OST-47.3H                      3 LIQUID WASTE EQUIP CCR IN ISOL                                                                          ST-S        a           1OST-47.3H RPV       2YR          10ST.47.3H 6      Globe        TV   15-2 (6.10)   0      S           S       FS-S       Q           IOST-47.3H TV-ICC-129-1      3    B    Active                                                                                                                                      c:
LIQUID WASTE EQUIP CCR IN ISOL                                                                          ST-S        Q           1OST,47.3H DO6 RPV       ZYR          1OST-473H CD TV-ICC-129-2      3    B    Active     6      Gkobe        TV   15-2 (E-10)   0       S           S      FS-S       0           1OST-47.3H                      Cn LIQUID WASTE EQUIP OCR OUT ISOL                                                                          ST-S       a           1OST-473H RPV       2YR          1OST-47.3H TV-ICC4133.2      3    B     Active   1.5     Globe        TV   15-2 (G-9)    0      S           S       FS-S       0           1OST-47.3H SAMPLE CLR CCR OUT ISOL                                                                                 ST-S        Q           IOST-47.3H RPV       2YR          1OST-47.3H TV-ICC-433-3      3    B     Acaive    6      Globe        TV   15-2 (F-10)   0       S           S      FS.S       0           1OST-47.3H LIQUID WASTE HX CCR OUT COMB RTRN ISOL                                                                  ST-S        0           1OST-47.3H RPV       2YR          1OST-47.31-1 TV.iCC-134.1      3    B     Active    3      Globe        TV    15-2 (A-7)   0       S          S       FS-S       0            OST-47.3H SAMPLE CLR CCR IN ISOL                                                                                   ST-S       Q           1OST-47.3H RPV       2YR          1OST-47.31-(0C CD~
SCD 00

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Beaver Valley Power Station Unit 1 IST Program                                                      CD VALVE TABLE                                                                    Z?       <
0~       TI SYSTEM NAME: Reactor Plant Component Cooling Water                                                                                  SYSTEM NUMBER:  15 CD Active / Size    Valve  Acluator  Drawing           Posltio0        Required            Code Valve ID I Name Class Cat. Passive  (in.)    Type   Type     & Coord   Normal Safety Fail-Safe   Test   Freequency Dev. Procedure           Remarks 00 TV-1CC-134-2      3    8   Active     3     Globe    TV     15-2 (B-7)   0       S       S       FS-S       0           1OST-47.3H SAMPLE CLR CCR IN [SOL                                                                           ST-S       Q           IOST-47.3H                         ~Cn RPV       2YR          1OST-47.3H                     -0       -
TV-1CC-1 34-3     3    B   Active    1.5    Globe    TV     15-2 (G-B)   0       S       S       FS-S       a           IOST-47.31-SAMPLE CLR CCR OUT ISOL                                                                          ST-S       a           1OST-4723H                     -n     ~
RPV       2YR          1OST-47.3H                     0 3    B   Active    12     Globe    TV     15-2 (A-5)   0       S       S       FS-S       a           1OST-47.3J                     C:
TV-1CC-136 BORON RCVY EQUIP OCR IN ISOL                                                                     ST-S        a          lOST-47,3J                     3 RPV       2YR          1OST-47,3J
                                                                                                                                                       -0 TV-1CC-137        3    B   Active     2     Globe    TV     15-5 (B-1)   0       S       S       FS-S        0          1OST-47.3H REFUEL WATER REFRIG UNrTS COMMON CCR IN ISOL                                                     ST-S        a          IOST-,7.3H RPV       2YR          i OST-47.3H TV-1CC-137A       3    B   Active    1.5    Globe     TV    15-5 (0-2)   0       S       S       FS-S        0          IOST-47.3H ST-S        a          IOST-47.3H REFUEL WATER REFRIG UNIT (OS-MR.1A) CCR oUr ISOL RPV      2YR          10ST-47.3H TV-1CC-137B       3     B   Active   1.5     Globe    TV    15-5 (E-1)    S      S       S       FS-S        0          1OST-47.3H REFUEL WATER REFRIG UNIT (0S-MR-1B) CCR OUT ISOL                                                 ST-S        0          IOST-A7,3H RPV       2YR          1OST-47.3H (D
CD     -N CD CD
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SYSTEM NAME:        Fuci Pool Cooling and Purification                                                                                      SYSTEM NUMBER:   20 CID    (D Actlve /  Size       Valve Actuator  Draling            Position           Required           Code Valve to0I Name Class Cat. Pagsive   (in.)      Type   Type     & Coord   Nlormal Safety    Faid-Safe   Tet-   frequency Dev. Procedure            Remjark.
IPC-1O            2    A    Passive     6         Ball          20.1 (D-7)   LS      S                   LTJ        SP          IBVT 147.5                       Cf5    CD REFUEL CAV SUCT CNMT PEN ISOL 0      0 IPC-37            2    A    Passive     6         Ball          20-1 (D-8)   LS      $                   LTJ        SP         1BVT 1.47.5 REFUEL CAV SUP CNMT ISOL
                                                                                                                                                                 -n     ~
IPC-38            2    A    Passive     6         Ball          20-1 (0-7)   LS      S                   LTJ        SD         IBVT 1.47.5 0)
REFUEL CAV SUP CNMT ISOL 1PC.9             2    A    Passive     6         Bali          20-1 (0-8)   LS      S                   LTJ        Sp          1BVT 1.47.5 REFUEL CAV SUCT CNMT PEN ISOL                                                                                                                                   'a CL CD)
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CD CD VALVE TABLE                                                                                  CD
                                                                                                                                                                       *o C
SYSTEM NAME:         Main Steam                                                                                                         SYSTEM NUMBER:           21  %V       <
C Active /  Size  Volve Acftrntar  Drawirt           Paoshio           Required            Code Valve ID I Name  Class Cat. Passive  (in.) Type   Type      & Coord   Normal Safety   Fail-Safe   Test   Frequeoy   0ev. Procedure          Remarks                   *CD 0D~
&#xb6;MS-15            2     B    Active     3   Gate            21-1 (0-3)  LO     0/S                MAN       2YR              IOST-24.4 iA S/G STEAM SUPPLY TO (1FW-P-2) ISOLATION
                                                                                                                                                                     -0       0 IMS-16            2     B    Active     3   Gate            21-1 (F-3)  LO     OIS                MAN       2YR              1OST-24.4 1I S/G STEAM SUPPLY TO (I FW-P-2) ISOLATION IMS-17           2     B    Active     3   Gate            21.1 (F-3)   LS     O/S                MAN      2YR              1OST-24,4 ccW-D     =
IC S/G STEAM SUPPLY TO (IFW-P-2) ISOLATION                                                                                                                          0)
IMS-1a            2     C    Active     3   Check           21-1 (G-4)    S    O/S                CV-0        R    VROJ - 36 IOST-24.9 1C SIG STEAM SUPPLY TO (1FW-P-2) CHK VLV                                                        CV-DIS    CVCM    VROJ -36 112CMP-75-ENERTECH  Sample CHECK-AM            Disassemntby and Inspection with 3
(1MS-19, 20] per
                                                                                                                                                                    -0 CVCM Program as       CA tied to TOAFWP Overspeed Trip Test (IOST-24.13).
PMT     CVCM    VROJ -36   1OST-24.9         Stroke oapre during CPT after Dlsassembly and Inspection.
IMS-19            2    C    Active     3   Check           2t-1 (G-4)    S     OtS               CV-O        R    VROJ-36    1OST.24.g 1B S/G STEAM SUPPLY TO (tFW-P-2) CHK VLV                                                        CV-OIS    CVCM    VROJ -36  1/2CMP-75-ENERTECH Sample CHECK-1M            Disassembly and Inspection with
[1MS-IB, 20] per CVCM Program as tied to TOAFWP Overspeed Trip (D
Test (IOST-24.13).
PMT      CVCM   VROJ -36  1OST-24.9          Stroke open during CPT after           0.
Disassembly and inspection C: CD)

CD CD Beaver Valley Power Station Unit 1 IST Program                                                                       CD       0)
I'CD VALVE TABLE CD       <
SYSTEM NAME:         Main Steam                                                                                                          SYSTEM NUMBER:             21 -- j      0)
CD Active / Size  Valve Attuator  Drawing           Position           Required             Codr Valve ID I Namne Class Cat. Passive  (In.f Type   Type     & Coerd   Normal Safety    Fail-Safe   Test   Frequoacy   Dev. Procedure          Remarks CD 1MS-20            2     C     Active    3   Check          21-1 (G-4)   S     O/S                 CV-O        R     VROJ - 36 1OST-24.9 IA S/G STEAM SUPPLY TO (IFW-P-2) CHK VLV                                                         CV-DIS     CVCM    VROJ - 36 1/2CMP-75-ENERTECH  Sample CHECK-IM            Disassembly and (0       0 Inspection with (1MS-IS. 19] per CVCM Program as tied to TDAFWP Overspeed Tnp
                                                                                                                                                                       ~0 Test (1OST-24 13).
PMT      CVCM    VROJ - 36 1OST-24.9           Stroke open during CPT after CD Disassembly and      3 Inspection.
IMS-23             3    B     Active    4   Gate           21-1 (B-5)   0     O/S                  MAN       2YR              1OST-1I10 1A SIG ATMOS DUMP ISOLATION VLV                                                                                                                                        0)
IMS-24             3    B     Active    4   Gate           21-1 (C-5)   0     0/S                  MAN       2YR              1OST-1.10 IS S/G ATMOS DUMP ISOLATION VLV 1MS-25             3    B     Active    4   Gate           21-1 (E-5)   0     0/S                  MAN       2YR              iOST-I.1O 1C SJG ATMOS DUMP ISOLATION VLV IMS-80             2    C     Active    3   Check          21.1 (C-7)   0      O/S               CV-DIS     CVCM    VROJ - 37 1CMP-75-ENERTECH    Sample lA S/G RESIDUAL HEAT RELEASE CHECK                                                                                            CHECK-IM            Disassembly and 1Inspeclon with
[IMS-8l. 82] per CVCM Program-PMT      CVCM    VROJ - 37 IOM-504.L           Partial Stroke Open Ui) during S/U after disassembly and inspecdon tMS-81             2    C     Active    3   Check          21-1 (C-l)   0      01S               CV--IS     CVCM    VROJ - 37 ICMP-75-ENERTECH    Sample CHECK-IM            Disassembly and         CD 18 SiC RESIDUAL HEAT RELEASE CHECN                                                                                                                Inspection with
[I MS-80, 821 per CVCM Program.
PMT      CVCM    VROJ -37  IOM-504.L           Partial Stroke Open during S/U after disassembly and inspection CD 20CDC C:) CD

cn CD Beaver Valley Power Station Unit I IST Program                                                                       CD       8)
_   CD VALVE TABLE                                                                                      (D       <
SYSTEM NAME:         Main Steam                                                                                                          SYSTEM NUMBER:             21 CD        C Active I Size  Valve Actuator  Drawing          Positlon           Required             Code Passive  (in.) Type   Type     & Coord   Normal Safety   Fail-Safe   Test   Frequency   Dev. Procedure           Remarks Valve ID / Name  Class Cat.                                                                                                                                            I=
1MS-82             2    C    Active     3   Check          21-1 (E-7)   0     O/S                CV-DIS    CVCM    VROJ - 37  iCMP-75-ENERTECH   Sample                Ct)       CD CHECK-iM            Disassemnbty and I C 5/G RESIDUAL HEAT RELEASE CHECK                                                                                                               Inspection with (1MS-0. 81j per CVCM Program.
PMT      CVCM    VROJ - 37  IOM-5O4.L          Partial Stroke Open    -3      ~
during S/I after disassembly and inspection MOV.1MS-IDIA       2    B     Active     2  Globe  MOV     21-1 (C-8)   S      S                  ST-S      CSD    VCSJ -15   IOST-t.Oei (TV-1MS-101A) BYPASS                                                                              RPV       2YR               10ST-1.10
                                                                                                                                                                       -0 MOV-llMS.t01B      2    B     Active     2  Globe  MOV     21-1 (E-8)   S      S                  ST-S      CSD    VCSJ- 15   1OST-1.10 RPV       2YR               1OST-1.10                                 0-(TV-1MS-101B) BYPASS MOV-1MS-101C       2    8     Active     2  Globe  MOV     21-1 (G-8)   S      S                  ST-S      CSD    VCS.J-15   lOST-1.10 RPV       2YR              lOST-1.10 (TV-1MS-101C) BYPASS                                                                                                                                                     <.        M MOV-1MS-105        3    B     Active     3  Gate   MOV     21-1 (G-4)   0     O/S                 ST-O      CSO    VCSJ - 19  1OST-.1O                                  a)       -
AFW TURB STEAM ISOL VLV                                                                           ST-S      GSD    VCSJ - 19  1OST-1.10                                 CD       -
RPV       2YR               1OST-1.A0 NRV-IMS-I01A       2   B/C    Active    32  Check   NRV    21-1 (8-8)   0      S                CV-BDT-O    NSO               ISTC-3550          During steam flow to S/Gs IA SG NRTRN VLV                                                                                   ST-S      CSD    VCSJ - 16  lOST-110           Stroklng & timing NRV shut verifies closure (CV-S) of non-retum check valve.
RPV       2YR               IOST-1AO NRV-1MS-101B       2   B/C    Active    32  Check   NRV    21-1 (D-8)   0      S                CV--0T-O    NSO               ISTC-3550          During steam flow to S/Gs IB SG NRTRN VLV                                                                                  ST-S      CSD    VCSJ - 16  lOST-1.10          Sl'oAng & timing NRV shut verifies closure (CV-S) of non-retum check valve.
RPV       2YR               1OST-1.10 ci)
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CD VALVE TABLE CD      <
SYSTEM NAME:         Main Steam                                                                                                            SYSTEM NUMBER:                21 CD Active/  Size  Valve  Actuator  Drawing          Psitlion          Required            Code Valve 1D I Name  Class Cat. Passive  (in.) Type    Type     & Coord   Normal Safety Fail-Safe    Test   Frequency   Dew. Procedure                 Remarks Cn      0 NRV-IMS-IOIC       2   BIC   Active     32  Check   NRV     21-1 (F-8)   0      S              CV-BDT-0     NSO              ISTC-3550                 During steam flow to SIGs              (0 IC SG NRTRN VLV                                                                                  SI-S       CSD    VCSJ - 16 1OST-1.10                 Stroking &tOning NRV shut verifies closure (CV-S) of non-return check     -n      -
valve.
RPV       2YR              1OSTi.10                                       -U    ~
PCV-lMhS-01A       2    B     Active    6   Globe   PCV     21-1 (A-5)   A     OIS        S        ET    CSD or R  VCSJ - 17 lOST-i.10                 Per OMN-12 IA SIG ATM DUMP VLV                                                                              FS-S       CSD    VCSJ - 17 lOST-l.10 DIAG-ST.O    6YR              1I2MI-75-Ultracheck A-11  Per OMN-12
                                                                                                                                                                            -0 OIAG-ST-S    SYR               1i2MI-75-Ultracheck A-11 Per OMN-12 Cn RPV       6YR              1r2MI-75-Ultracheck A-11  Per OMN-12 PCV-IMS-101B       2    8     Active    6   Globe   PCV     21.1 (C-5)   A     OS         S        ET    CSDorR    VCSJ- 17  lOST-1l10                 PerOMN-12 IS SIG ATM DUMP VLV                                                                               FS-S      CSD    VCSJ - 17  1OST-1.10 DIAG-ST-O    6YR               1/2Mt-75-Ultracheck A-1l Per OMN-12           CD DIAG-ST-S    6YR              112MI-75-Ultracheck A-11  PerOMN.12 RPV       6YR               1/2MI-75-UIlracheck A-li Per OMN-12 PCV-IMSI101C       2    8     Active    6   Globe   PCV     21.1 (E-S)    A    O/S        S        El    CSDorR    VCSJ- 17  10ST-1.10                 PerOMN-12 IC SIG ATM DUMP VLV                                                                              FS-S      CSO    VCSJ - 17 lOST-1.10 DIAG-ST-O    6YR               l/2M1-75-Ultraciack A-li Per OMN-12 DIAG-ST-S    6YR               l/2M,-75-Utracheck A-11  Per OMN-12 RPV       6YR               1/2M1-75-Ultracheck A-1l PerOMN-12 SV, MS-iOIA        2    C     Active 6x 10  Safely   SV     2-1 (6-4)     S    OrS                SPT       SYR               IVI"1.21.2 1A SIG SAFETY VALVE                                                                               SPT       SYR               1BVT 1.60.5 CD   -
SV-1MS-1018        2    C     Active 6x10   Safety    SV    21-1 (D-4)    S    OS                 SPT       SYR               1BVT 1.21.2 1B S/G SAFETY VALVE                                                                               SPT       SYR               I BVT 1.60.5 SVWIMS-101C        2    C     Active 6 x 10 Safety    SV    21-1 (E-4)    S    0W$                SPT       SYR              1BVT 1.60.6 IC SIG SAFETY VALVE                                                                              SPT       SYR               18VT 1.21.2 SV-IMS-102A        2    C     Active 6 x 10 Safety   SV     21-1 (B-4)    S    0IS                SPT       SYR               18VT 1.21.2 IA SG SAFETY VALVE                                                                               SPT       SYR              1VT 1.60.5 (DnA Co CD 4 <
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Beaver Valley Power Station Unit 1 IST Program                                                            ~ 0)
VALVE TABLE                                                                            CD SYSTEM NAME:         Main Steam                                                                                                          SYSTEM NUMBER:  21       CD Valve                                                                   Code Active I   Site          Actuatar  Drawing           Posilioa          Required
                                                                                                                                                                ~ 0)
Vidv- ID I Name  Class Cat. Passie    (in.)   Type     Type    & Courd   Normal Safet. Fal-Sale   Test   Frequency 0ev, Procedure            Remarki          CD I
SV-IMS-1028        2    C    Active   6 x 10   Safety    SV    21-1 (D-4)   S      O/S                SPT       SYR         1BVT 1.60.5 SPT       SYR         1BVT 1.21.2                     (a IB SIG SAFETY VALVE SV-1MS-102C        2    C    Active   6 x 10   Safety    SV    21-1 (E-4)   S      OS                 SPT       SYR         18VT 1.60.5 18VT 1.21.2                     0D IC SIG SAFETY VALVE                                                                                   SPT       SYR SV-IMS-103A        2    C    Active   6 x 10   Safety    SV    21-1 (B-4)   S      OIS                SPT       5YIR        1BVT 1.21.2 SPT       SYR         1BVT 1.60.5 IA SIG SAFETY VALVE SV-1MS-1038        2    C    Active   6x 10    Safety    SV    21-1 (D-4)   S      OiS                SPT       SYR         1 VT t21.2 1B SIG SAFETY VALVE                                                                                  SPT       5YR         1BVT 1.60.5 SV-I MS-103C       2    C    Active   6 x 10   Safety    SV    21-1 (E-4)   S      OIS                SPT       SYR         1BVT 1.60.5                     CD 1C S/G SAFETY VALVE                                                                                   SPT       SYR         16BV 1.21.2 SV-IMS-104A        2    C    Active   6 x 10   Safety    SV    21.1 (B-3)   S      OIS                SPT       SYR         1BVT 1.21.2 1A S/G SAFETY VALVE                                                                                  SPT       SYR         1BVT 1.60.5 SV-IMS-1048        2    C    Active   6 x 10   Safely    SV    2!-1 (D-3)   S      OS                 SPT       5YR         16BVT 1.21.2 18 StG SAFETY VALVE                                                                                  SPT       SYR         IBVT 1.60.5 SV.IMS-104C        2    C    Active   6x 10    Safely    SV    21-1 (E-3)   S      O/S                SPT       SYR         1WVT 1.21.2 1C S/G SAFETY VALVE                                                                                  SPT       5YR         IBVr 1.60.5 SV-IMS-105A        2    C    Active   6x10     Safety    SV    21-1 (B-3)   S      OIS                SPT       SYR         1BVT 1.21.2                     (0)C 1A SIG SAFETY VALVE                                                                                  SPT       5YR         1BVT 1.60.5 SV-1MS-105B        2    C    Active   6x-10    Safety    SV    21-1 (D-3)   S      OIS                SPT       5YR         1WVT 1.21.2                       0 18 SIG SAFETY VALVE                                                                                  SPT       SYR         16BV'1.60,5 SV-IMS-105C        2    C    Active   6x 10    Safety    SV    21-1 (E-3)   S      OIS                SPT       SYR         1BVT 1.60.5 iC S/G SAFETY VALVE                                                                                  SPT       SYR         IBV'T 1.21.2                    0   0

CO      CD Beaver Valley PowerStation Unit I IST Program CD VALVE TABLE                                                                                               _
CD      <
SYSTEM NAME:        Main Steam                                                                                                                   SYSTEM NUMBER:                2!
Code CD     ~
Actlve I Sir*      Valve     Actuator  Drawing           Position          Required Valve D0/Name   Class Cat. Passive (in.)      Type      Type     & Coard   Normal Safety. Fail-Safe    Test    Frequency   13v. Procedure                Remarks                      0, TV-IMS-1OIA      2    B/C   Active    32  Inverse Check   TV     21-1 (B-8)   0      S         S        FS-S      CSD     VCSJ- 18  1OST-21,4 LOOP 1A MAIN STEAM TRIP VALVE                                                                          ST-S-A     CSO     VCSJ - 18 101T-21.4                Stroking and timing   0~      0 trip valve open and shut verifies opening and closure  ~3C of inverse check     -n      -
valve.
ST-S-a     CSD     VCSJ- 18 IOST-21.4                                      -0     ~
RPV        2YR              10$T-21.4 TV-IMS-1019       2   B/C   Active    32  Inverse Check   TV     21.1 (0-8)   0      S         S        FS.S       CSD    VCSJ- 18  IO$T-21,5 IOST-21.5                Stroking and timing oL        C LOOP IB MAIN STEAM TRIP VALVE                                                                          ST-S-A     CSD     VCSJ - 18 trip valve open and shut verifies        CD opening and closure of inverse check valve, ST-S-B     CSD     VCSJ - 18 1OST-21.5 RPV        2YR              IOST-21.5 TV-1MS-101C      2    B/C   Active    32  Inverse Check    TV    21-1 (F-8)   0      S         S        FS-S      CSD     VCSJ - 18 IOST-21.6 LOOP IC MAIN STEAM TRIP VALVE                                                                          ST-S-A     CSD     VCSJ -18  1OST-21.6                Stroking and timing trip valve open and shut verifies           0O) opening and closurE of inverse check valve, ST-S-B      CSD    VCSJ - 18 1OST-21.6                                      CD-N RPV        2YR              1OST-21.6                                        CD TV-IMS-105A       3    B     Active    3       Gate        TV    21-1 (G-4)    S     0         0     DIAG-ST-O     6YR              l/2Mt-75-Ulracheck A-1I Per OMN-12 AFW TURB STEAM SUP A TRN TRIP VLV                                                                       RPV        SYR              1/2MI-75-UlItacheck A-lI Per OMN-12            0.<
ET    18MO or R            I OST-24.9               Per OMN-12
                                                                                                                                                                                          .-0 FS-O    18MOorR             IOST-24.9 C')
ITV-MS-105B   3    B     Active    3       Gate        TV    21.1 (G-5)    S     0         0     OIAG-ST-O     SYR              1/2MI-75-Ultracheck A-11  Per OMN-12 AFW TURB STEAM SUP B TRN TRIP VLV                                                                       RPV        6YR              1/2M[-75-Ultracheck A-11 Per OMN-12 ET    i8MO or R            IOST-24.9                 Per OMN-12 FS-O   18MO or R            10ST-24.9 C:) CD)

w   D Beaver Valley Power Station Unit 1 IST Program                                                       CD      0)
VALVE TABLE                                                                             CD (D     <
SYSTEM NAME: Main Steam                                                                                                             SYSTEM NUMBER:  21 -4      ID (D
Active f Size    Valve Actuator  Draling           Polithlo          Requir-d           Code Valve ID N Name   Class Cat. Passive  (In.)   Type   Type     & Coord   Nortual Safetyr FaIl-Ssfe  Test    Frequency Dev. Procedure           Renmrks U) 1.5    Gate    TV     26-4 (E-1)   0       S         S      FS-S        a          1OST47.3L TV.1MS.tIIA       2    B   Active 1OST-47.3L 0
iA MAIN STEAM LINE PRE-NRTRN DRAIN ISOL VLV                                                      ST-S        Q RPV       2YR         1OST-47.3L (0
TV-IMS-111B       2    B   Active    1.5    Gate    TV     26-4 (C-1)   0       S         S      FS-S        Q          IOST-47.3L IB MAIN STEAM LINE PRE.NRTRN DRAIN ISOL VLV                                                      ST-S        Q          IOST-47,3L                     (j      C RP'V       2YR         1OST-47.3L TV.IMS-111C       2    8   Active    1.5    Gate    TV     26.4 (A-1)   0        S        S      FS-S        a          1OST-47.3L
                                                                                                                                                       -L      C, ST-S        0          1OST-47.3L IC MAIN STEAM LINE PRE-NRTRN DRAIN ISOL VLV RPV        2YR          IOST-47,3L                            X
                                                                                                                                                       -&#xb6;D 6) 0 6:)   ) -.

cn co Beaver Valley Power Station Unit 1 IST Program                                                                    CD       D
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SYSTEM NAME:           Feedwater & Auxiliary Feedwater                                                                                       SYSTEM NUMBER:            24 CD       C Active /   Sie      Vaive Actuator  Drawing          Pesition          Required             Cade Valve DIOName     Cla.2  Cat. Passive   (-.)      Type   T"),     & Caeoud  Nurmal Safely Fail-Safe    Test   Frequency   De,. Procedure          Remarks IFW-156A            2     C    Active     16      Check          24-1 (B-7)   0      S               CV-S-LT      R     VROJ-41   1OST-24.14A                             Cj)      CD 1A SG MAIN FW ISOL CHK VLV                                                                           CV-S-LT      R     VROJ .41  1OST-24.8B                                   -   C)
CV-S-LT      R     VROJ - 41 1osT-24.8A CV-BDT-0     NSO              ISTC-3550          During main feedwater IRowto S/Gs.                 -n 1FW-156B            2     C    Active     16      Check          24-1 (0-7)   0      S               CV-S-LT      R     VROJ-41   1OST-24-14B 1OST-24.8B CD 1 SG MAIN FW ISOL CHK VLV                                                                            CV-S-LT      R     VROJ -41 CV-S.:LT     R     VROJ - 41 1OST-24.8A CV-BDT-O     NSO              ISTC-3550          During main teedwater flow to S/Gs.
1FW-156C            2     C    Active     16      Check          24-1 (F-7)   0      S               CV-S-LT      R     VROJ- 41  1OST-24.14C 1C SG MAIN FW ISOL CHK VLV                                                                          CV-S-LT      R     VROJ -41  1OST-24.88                              CD CV-S-LT      R     VROJ- 41  1OST-24.BA CV-8DT-O     NSO              ISTC-3550          During main feedwater flow to S/cs.
IFW-33              3     C    Active     6       Check          24-2 (E-7)   S     O/S               CV-0        R     VROJ - 36 1OST-24.9 (1FW-P-2) DISCH CHECK                                                                                 CV-S        R     VROJ- 38  1OST-24.8A 1FW-34              3     C    Active     4       Check          24-2 (E-2)   S     O/S               CV-O        R     VROJ - 38 IOST-24.8A (1FW-P-3A) DISCH CHECK                                                                                CV-S        R     VROJ - 38 1OST-24.88 2) iFW-35              3     C    Active     4       Check          24-2 (E-4)   S     OIS               CV-0        R     VROJ - 38 lOST-24.88 (1FW-P.3B) DISCH CHECK                                                                                CV-S        R     VROJ- 38  IOST-24.8A                              C) C IFW-36              3     B    Active     6       Gate           24-2 (0-7)  LO     O0S                MAN       2YR              I OST-24.4 (1FW-P-2) A HEADER DISCH ISOLATION 0~
: 0)   -
IFVW-37             3     B    Active     4       Gate           24-2 (0-2)  LO     OS                MAN        2YR              1OST.24.2 (1FW-P-3A) -A7 HEADER DISCH ISOLATION IFW-38              3     B    Active     4       Gate           24-2 (D-4)   S     OS                 MAN       2YR              1OST-24.3 (1FW-P-3B) -A"HEADER D1SCH ISOLATION C:) CD)

Wj      CD Beaver Valley PowerStation Unit 1 IST Program                                                                         CD       W VALVE TABLE                                                                                               CD CD       <
SYSTEM NAME:          Feedwater & Auxiliary Feedwater                                                                                            SYSTEM NUMBER:           24 CD        C Active I   Size   Valve Actuator  Drawing            Position           Reqtir*d             Code                                             CO)
Valve ID IuName   Class Cat. Pastive  (in.)   Type   Type     & Coord   Nursia] Safety    Fall-Safe  Tlsl    Frequency   Dtv. Procedure            1tiemrnaks (0 0 IFW-39              3     B     Active     6     Gate           24-2(0-7)    S      OIS                 MAN        2YR              1OST-24,4                                CI)      CD (1FW.P-2) "89 Header Discharge Isolation                                                                                                                                          ~Cj IFW.40              3     B     Active     A     Gate           24-2(0.2)    S       CIS                MAN        2YR               1OST-24.2
                                                                                                                                                                                     ~ -0 (1FW-P-3A) W HEADER DISCH ISOLATION 1FW.41              3     B     Active     4     Gate           24-2(0-5)    LD     OIS                 MAN        2YR              1OST-24.3 (0
(1FW-P-38) WBHEADER DISCH ISOLATION 1FW*42              2     C     Active     3    Check           24.1 (B-7)    S      O0S                CV-0        R     VROJ - 38  1OST-24.SA 1A SG AUX FEED CHECK                                                                                    CV-O        R     VROJ - 38 1OST-24,SB CV-S-LT      R     VROJ - 38  10ST-24,t 1 CV-S        a               1OM-54 PAB Log                            a-1FW.43              2     C     Active     3    Check           2A-1 (E-7)    S      O/S                CV-0        R     VROJ - 38 1OST-24.8                                 -U lB SG AUX FEED CHECK                                                                                   CV-S-LT      R     VROJ - 38 1OST-24.11                                CD CV-S        a               IOM-54 PAB Log CV-0       CSD    VROJ - 38 lOST-24.SA IFW-44              2     C     Active     3    Check           24-1 (G-7)   S       OS                 CV-0        R     VROJ - 38 I"OST-24.BB CD       -
iC SG AUX FEED CHECK                                                                                   CV-0        R     VROJ -38   1OST-24.8A CV-S-LT      R     VROJ - 38  IOST-24.11 CV-S        a               IOM-54 PAB Log IFW-50              3     C     Active     1     Check          24-2 (E-7)    S       0                CV-DIS     CVCM    VROJ - 39 "lCMP-7S-CRANE       Sample CHECK-4M             Disassembly and (I FW-P-2) COOLER CHECK                                                                                                                                  Inspection with f1FW-51, 52,68, 69, 70] per CVCM Program,                Ci)
PMT       CVCM    VROJ -39   IOST-24.9           Partial Stroke Open during CPT after Disassembly and Inspeeion ca CD CD 4&#xfd; oC:CD 00

Beaver Valley Power Station Unit 1 IST Program                                                                            CD       0 VALVE TABLE                                                                                             _   CD SYSTEM NUMBER:           24      0)
SYSTEM NAME:         Feedwater & Auxiliary Feedwater                                                                                                                                    CD       <
Active I     SiLe      Valve      Actuatler  Drawing           Position           Required                 Code (Dn      C Valve 101tNamt   Class Cat. Pasti-e      (rap       Type       Type      & Coord    Normal Safety   Fail-Safe   Test       Frequency   Dev. Procedure            Remarks
                                                                                                                                                                                        ~CD 1       Check                24-2 (E-2)    S      0                CV-DOS         CVCM    VROJ - 39 1CMP-75-CRANE        Sample IFW-51             3    C    Active                                                                                                                                                              -0 (1FW-P-3A) COOLER CHECK                                                                                                                        CHECK-4M             Disassembly and (I        F-P-3)                      COLER                      HECKInspection                                                    with             0) 11FW-50. 52. 68.
: 69. 70] per CVCM Program.
PMT          CVCM    VROJ - 39 1OST-24.8A           Partial Stroke Open (0 durng CPT after Disassembly and Inspection IFW.52             3    C    Active        1       Check                24-2 (E-5)    S      0                 CV-DIS        CVCM    VROJ -39  ICMP-75-CRANE        Sample (IF-P-B)   OOLR CECKCHECK-4M                                                                                                   Disassembly and     0 (I FW-P-3t) COOLER CHECK                                                                                                                                            Inspection with (1FW-50. 51 68.
C
: 69. 70) per CVCM Program, 3
PMT          CVCM    VROJ - 39 1OST-24.8B           Partial Stroke Open during CPT after Disassembly and Inspection C
1FW-622            2    C    Active        3       Check                24-2 (C-4)    S     O/S                CV-O            R     VROJ - 38  1OST-248A CV-S           R     VROJ - 38  IOST-24.8B IC SG AUX FEED CHECK FROM "A' HEADER                                                                                                                                                    CD 24-2 (C-4)    S     O/S                 CV-O           R     VROJ - 38  IOS'I-24.88                              (1) 1FW.623            2    C    Active        3       Check CV-S           R     VROJ - 38  1OST-24.8A IC SO AUX FEED CHECK FROM 'S' HEADER 1FW-624            2    C    Active        3       Check                24.2 (B-4)    S     O/S                 CV-O           R     VROJ - 38  1OST-24.8A CV-S           R     VROJ - 38  1OST-24.88 IB SG AUX FEED CHECK FROMI WAHEADER IFW-625            2    C    Active        3       Check                24-2 (8-4)    S     O/S                 CV-O            R    VROJ - 38  1OST-24.S8 CV-S           R     VROJ - 38  IOST-24.8A 1B SG AUX FEED CHECK FROM "B" HEADER 1FW-626            2    C    Active        3       Check                24-2 (A-4)    S     O/S                 CV-O            R    VROJ - 38  1OST-24.8A CV-S            R    VROJ - 38  IOST-24.88 1A SG AUX FEED CHECK FROM A HEADER 1FW-627            2    C    Active        3       Check                24-2 (A-4)    S     CIS                 CV-O            R    VROJ - 38  1OST-24.88 CV-S            R    VROJ -38   10ST-24.8A 1A SG AUX FEED CHECK FROM "S" HEADER CD)
C)CD 0(l 0~5 00C:

cn CD CD        l Beaver Valley Power Station Unit 1 IST Program
_  CD VALVE TABLE                                                                                       F5      -
CD       <
SYSTEM NAME:        Feedwater & Auxiliaty Feedwater                                                                                                SYSTEM NUMBER:            24 CD Cn
                                                                                                                                                                                        ~
Active /  Size      Vilve     Actuator  ora.ing           Posatioa         Required                  Code Valve ID / Name Class CAL. Paslive   (in.)     Type         Type   & Coord    Normal Safety Fa2.-Safe   Test       Frequency    De*. Procedure          Remarks (0 0 iFW-68            3    C    Active     1      Check               24-2 (E-8)    S      0              CV-OlS         CVCM     VROJ - 39 ICMP-75-CRANE      Sample                Cn CD (1FW-P-2) COOLER INLET CHECK                                                                                                            CHECK-4M           Disassembly and Inspectlon with
([FW-50,51, 52.      -0        0
: 69. 70] per CVCM Program.              3~(1 PMT          CVCM     VROJ -39  1OST-24.9          Partial Stroke Open  -171 during CPT after Disassembly and      0)
Inspection IFW-69            3    C    Active     1      Check               24-2 (E-2)     S     0              CV-DIS         CVCM     VROJ -39  1CMP-75-CRANE CHECK-AM Sample Disassembly and 3
(IFW-P-3A) COOLER INLET CHECK                                                                                                                              Inspection with
[1FW-50.5t1 52, 68, 70] per CVCM Program.
PMT          CVCM     VROJ -39  1OST-24.aA         Partial Stroke Open during CPT after      CD Disassembly and Inspection 1FW-70            3    C    Active     1      Check               24-2 (E-5)     S     0              CV-DIS         CVCM     VROJ -39  1CMP-?S-CRANE       Sample (1FW.Po35) COOLER INLET CHECK                                                                                                           CHECK-4M            Disassembly and (11         W-P-8)                  OOLE             INET             CECKInspection                                           with (IFW.50, 51, 52.
: 68. 69] per CVCM Program, PT           CVCM     VROJ - 39 1OST-24.8B          Partial Stroke Open during CPT after Disassembly and Inspection CD FCV.1FWo102       3    B   Passive     3       Gate         FCV   24-2 (E-7)     S      S       S       RPV           2YR               1OST-24.9 TURB DRIVEN AFW PUMP RECIRC VLV 0~
FCV-IFW-103A      3    B   Passive     2       Gate         FCV   24-2 (F-1)     S      S        S      RPV           2YR               1OST-24.8A
: 0)    -
3A AFW PUMP RECIRC VLV FCV-1FW-1038      3    B   Passive     2       Gate         FCV   24-2 (F-4)     S      S        S      RPV            2YR              10ST-24.8 39 AFW PUMP RECIRC VLV 0 CD)

B CD Beaver Valley PowerStation Unit 1 IST Program
_   CD VALVE TABLE CD      <
SYSTEM NAME:         Feedwater & Auxiliary Feedwater                                                                                          SYSTEM NUMBER:  24 CD      CD ActiveI   Size      Valve Actuator  Drawing           Position           Required             Code Valve 101 Name   Class Cal. Passive   (in.)     Type   Type     & Coord   Normal Safety    Fail-Safe   lest   Frequency   Dew. Procedure           Remarks Ci)
FCV.1FW.478       2     8    Active     16     Globe   FCV     24-1 (B-4)   A      S           S      FS-S      CSD     VCSJ - 21 10ST-1.10 IA SG MAIN FW FEED REG VLV                                                                           ST-S-A     CSD     VCSJ .21  lOST-1l10                      (0      0 ST-S-B     CSD     VCSJ- 21  lOST-1i10 RPV      2YR               lOST-l,10
                                                                                                                                                                 -n      -
FCV-iFW-479       2     B    Active     4      Globe   FCV     24-1 (A-4)   A      S           S      FS-S        a               IOST-47.3P IA SG FW BYPASS FCV                                                                                   FS-S        0               IOST-47,3N ST-S-A       0               1OST-47.3P ST-S-B       0               IOST-47,3N                     0 RPV       2YR              IDST-47.3P.
RPV       2YR              IOST-47.3N Co FCV-IFW.488       2     B    Active     16     Globe   FCV     24-1 (D-4)   A      S           S      FS-S      CSD     VCSJ - 21 10ST-1.10 18 SG MAIN FW FEED REG VLV                                                                           ST-S-A     CSD     VCSJ- 21  10ST-1I10 ST-S-B     CSD     VCSJ - 21 1OST-i.10 RPV       2YR              1OST-1.10 0.
FCV-1FW-48         2    8    Active     4      Globe   FCV     24-1 (0-4)   A      S           S      FS-S        0               1OST-47.3P 1B SG FW BYPASS FCV                                                                                   FS-S        a               IOST-,7.3N ST-S-A       a               IOST-47.3P                     Co ST-S-B       a               10ST-47.3N RPV       2YR              10ST-47,3N RPV       2YR              10ST*-47.3P FCV-IFW.498        2    8    Active     16     Globe   FCV     24-1 (F-4)   A      S           S      FS-S      CSD     VCSJ - 21 10ST-1l10 IC SG MAIN FW FEED REG VLV                                                                          ST-S-A     CSD     VCSJ - 21 1OST-1.10 ST-S-B     CS0     VCSJ- 21   1OST-1.10 RPV       2YR               1OST-1.10 FCV-1FW-499        2    B    Active     4      Globe   FCV     24-1 (F-4)   A      S           S       FS-S       0               1OST-47,3P 1C SG FW BYPASS FCV                                                                                   FS-S       0               lOST-.7.3N ST-S-A       0               IOST-47.3P ST-S-B       0               lOST-47.3N RPV       2YR              lOST-47 3P RPV       2YR              IOST-47.3N
: 2) CD CD0iCD CD 00

o~co 0CD Beaver Valley PowerStation Unit I IST Program                                                               CD       a)
VALVE TABLE CD       <
SYSTEM NAME:        Feedwater & Auxiliary Feedwater                                                                                       SYSTEM NUMBER:    24 CD Active I  Size     Valve Actuator  Drawing          Position          Requircd             Cede                                      Ci, Valve I 1 Name  Class Cat. Pesivv   (in.)     Type  Type     & Coord   Normal Safety Fail-Safe    Test   Frequency   0ev. Procedure           RemarkLs (0 0 HYV-IFW-IOCA      2    8    Active     16      Gate  HYV     24-1 (B-7)   0      $                 ST-S     CSO     VCSJ - 20 1OST-1.10                         C/       CD 1A STEAM GENERATOR MAIN FEEDWATER CNMT ISOL VALVE                                                  RPV       2YR              1OST-1110 HYV-1FW-100B      2    B    Active     16      Gate   HYV    24-1 (D-7)   0      S                 ST-S     CSD     VCSJ-20   IOST-1.10 IB STEAM GENERATOR MAIN FEEDWATER CNMT ISOL VALVE                                                  RPV       2YR              1OST-1.10                         -n HYV.1FW-I00C      2    B    Active     16      Gate   HYV    24-1 (F-7)   0      S                 ST-S     CSD     VCSJ-20   1OST-1.10                        (0 1C STEAM GENERATOR MAIN FEEDWATER CNMT ISOL VALVE                                                  RPV       2YR               1OST-1.10 MOV-1FW.151A      2    B    Active     3      Globe  MOV     24-2 (C-3)   0     O/S             OIAG-ST-O    9YR               1/2-CMP-E-75-021   Per OMN-1
                                                                                                                                                                -0 IC SG AFW THROTTLE VLV (8 HDR)                                                                  DIAG-ST-S    9YR               1.2-CMP-E-75-021   Per OMN-1 C
RPV       9YR               112-CMP-E-75-021   Per OMN-1     3 ET    18MO or R            1OST-24.1          Per OMN-1 MOV-IFW-151B      2    B    Active     3      Globe  MOV     24-2 (C-3)   0     OS              DIAG-ST-O    9YR               1/2-CMP-E-75-021   Per OMN-1 IC SG AFW THROTTLE VLV (A HDR)                                                                  DIAG-ST-S    SYR               112-CMP-E-75-021   Per OMN-1 RPV       SYR               112-CMP-E-75-021   Per OMN-1 ET    18%Mor R            IOST-24-1           Per OMN-1 MOV-1FW-I$1C      2    B    Active     3      Globe  MOV     24-2 (B-3)   0     O/S             DIAG-ST-O    9YR               112-CMP-E-75-021   Per OMN-1 18 SG AFW THROTTLE VLV (B HDR)                                                                  DIAG-ST-S    SYR              1/2-CMP-E-75-021    Per OMN-1 RPV      9YR               112-CMP-E-75-021    Per OMN-1 ET    18MOorR              1OST-24.1          Per OMN-1 MOV-lFW-151D      2    B    Active     3      Globe  MOV     24-2 (B-3)   0     01S             DIAG-ST-O   SYR               ir2-CNMP-E-75-021   Per OMM-1 I B SG AFW THROTTLE VLV (A HDR)                                                                 DIAG-ST-S    9YR              12-CMP-E-75-021     Per OMN-1 RPV       SYR              112-CMP-E-75-021    Per OMN-1 ET    18MO or R           1OST-24,1           Per OMN-1    0, MOV-IFW-IS1E      2    B    Active     3      Globe  MOV     24-2 (A-3)   0     Os              DIAG-ST-O    SYR              1/2-CMP-E-75-021    Per OMN-1       0.
1A SG AFW THROTTLE VLV (B HOR)                                                                  OIAG-ST-S    9YR              112-CMP-E-75-021    Per OMN-I    0) =.
RPV       9YR              1/2-CMP-E-75-021    Per OMN-1 ET    18MO or R           !OST-24.1           Per OMN-1 (0    C)

CA      CD Beaver Valley Power Station Unit 1 IST Program                                                            (D     a1)
(D VALVE TABLE CD      <
SYSTEM NAME:         Fecdwater & Auxiliary Feedwater                                                                                       SYSTEM NUMBER:    24  ... 0 CD Active/   Size      Valve  Actualtr  Drawing            Positiou            Required           Code Valve 1f) Naame  Class Cat. Passive   (i.j      Type    Type     & Courd    Normal Snfely    FolI-Sfte    Test   Frequency Dev. Procedure          Remarks 00 MOV-1FW-15iF      2     8    Active    3       Globe    MOV     24-2 (A-3)    0     OS                 OIAG-ST-O    9YR         1f2-CMP-E-75-021   Per OMN-1         ~CD 1A SO AFW THROTTLE VLV (A HDR)                                                                         DIAG-ST-S    9YR         lr2-CMP-E-75.021   Per OMN-1
                                                                                                                                                                 -0 RPV       9YR         1/2-CMP-E-75-021   Per OMN-1      0     0)
ET    18MO or R      1OST-24,1          Per OMN.1 RV-IFW.155        2     C    Active  3x4        Relief   RV     24-2 (F-7T)   S     O0s                   SPT      10YR         1BVT 160.5                       -n   ~
(1FW-P-2) RELIEF Co
                                                                                                                                                                '0 CM C,)
(a-C CD N -.
(=) CD o: CD)

ul)    (D Beaver Valley Power Station Unit 1 IST Program                                                                      (D    a)
CD VALVE TABLE                                                                                   0 CD     <
SYSTEM NAME:       Steam Generator Blowdown                                                                                                SYSTEM NUMBER:         25 ActiveI   Size    Vahle Aetuator  Drawineg           Position           Required             Code                                                 CD Fail-Safe   Test   Frequency   13. Procedure           Remarks
:3 Valve 1D1 Name Class CIt. Passive   (in.)   Type   Type     & Coerd    Normal Safety CC)    0 TV-1B0-100A     2     8   Active      3     Globe   TV     25s-1 (-4)    0      S           S       FS-S     CSD     VCSJ - 22  1OST-1.10                                   C'D Cl)
STM GEN IA SLOWDOWN TRIP                                                                            ST-S     CSD     VCSJ - 22  1OST-1,1O RPV    2YR/18MO            lOST-.10            18 mnonthsper Tech. Specs.
0)
TV-SD-o00B       2     B  Active       3    Globe   TV     25-1 (D-4)    0      S           S       FS-S      CSD    VCSJ -22   IOST-1.10                            CC)
STM GEN 18 BLOWDOWN TRIP                                                                            ST-S      CSD    VCSJ - 22  IOST-1.10 RPV    2YR/18MO            lOST-l,10           I8 months peM Tech. Specs.      -n TV-1SD-100C      2     B  Active       3    Globe    TV    25- (F-4)     0      S           S       FS-S      CSD    VCSJ -22   1OST-1.10                            0 STM GEN 1C BLOWDOWNTRIP                                                                             ST-S      CSD    VCSJ - 22  IOST-1.10 RPV    2YR818MO             IOST-1.i0          18 monaths per    -0 Tech. Specs.
TV-1BO-IOIAI     2     8  Active       3    Gate    TV     25-1 (B-2)    0      S           S       FS-S     CSD     VCSJ- 22   lOST-1.10 BLOWDOWN TEMPERATURE ISOLATION. A S/G                                                               ST-S      CSD    VCSJ - 22  lOST-1l10 CD RPV       2YR                  $OST-1.10 TV-IBD-101A2     2     8  Active       3     Gate    TV    25-1(8-2)     0      S            S      FS-S      CSD    VCSJ - 22  lOST-1l10 SLOWDOWN TEMPERATURE ISOLATION. A SIG                                                               ST-S      CSD    VCSJ - 22  iOST-1i10 RPV       2YR              lOST-l,10 TV.1BD-1OB1      2     B  Active       3     Gate    TV    25-1 (D-2)    0      5            S      FS-S      CSD    VCSJ - 22  IOST-1,10 BLOWDOWN TEMPERATURE ISOLATION, 1 SIG                                                              ST-S      CSD    VCSJ - 22  lOST-1.10 RPV       2YR               IOST-1.10 TV-1B0-101B2     2     8  Active       3     Gate    TV    25-1 (D-2)    0      S            S      FS-S      CSD    VCSJ - 22  lOST-110 BLOWDOWN TEMPERATURE ISOLATION. 8 &SG                                                              ST-S      CSD    VCSJ - 22  lOST-1.10 RPV       2YR               lOST-1.10 TV.IBD-101CI     2     B   Active      3     Gate    TV     25-1 (F-2)   0       S           S      FS-S      CSD    VCSJ - 22  lOST-1.10 0~
SLOWDOWN TEMPERATURE ISOLATION. C SIG                                                              ST-S      CSD    VCSJ - 22  1OST-I.10 RP`V      2YR               lOST-1.10 TV-lBD-111C2    2     B   Active      3     Gate    TV     25-1 (F-2)   0       S           S      FS-S      CSD    VCSJ -22   lOST-1.10 SLOWDOWN TEMPERATURE ISOLATION. C SIG                                                              ST-S      CSD    VCSJ - 22  1OST-1.10 RPV       2YR               lOST-1l10 0)
C0 0

c  CD Beaver Valley Power Station Unit 1 IST Program                                                                        CD      0)
CD VALVE TABLE CID     <
SYSTEM NAME: Main Turbine and Condenser                                                                                                     SYSTEM NUMBER:         26  --I    L)
CD      CD Active I Size  Valve Actualor   Dra.iiinp        Position             Required             Code Vlive [01 Name  CIzs Cat. Passive  (in.) Type   Type      & Coord   Normal Safety   FaJil-Su.fv    Test  Frequency   Dev. Procedurc             Remarks 00 IAS-278           2   AtC  Active     6   Check          26-6 (D-10)   S     OfS                    LTJ      SP                1BVT 1.47.5                            (jn     CD AIR EJECTOR AIR DISCH TO CNMT                                                                     CV-ME       R     VROJ - 42  lOST-1 10                                      C',
TV-1SV-100A       2    A   Active     6   Globe   TV      26-6(0-9)    S     O/S         S          LTJ      SP                I BVT 1.47.5 FS-S      CSD    VCSJ - 23  lOST-1 10                              (0      0 AIR EJECTOR AIR DISCH TO CONT ST-O      CSD    VCSJ-23   lOST-1.10 ST-S      CSD    VCSJ .23   lOST-tO10 RPV    2YR118MO             1OST-110              18 months per Tech, Specs.      0
                                                                                                                                                                      -U C:
3 Cf Cfl SCD CD A CID 00

                                                                                                                                                           ~n CD CD     0)
Beaver Valley Power Station Unit 1 IST Program                                                            _  CD VALVE TABLE                                                                      o0     -
CD     <
SYSTEM NAME:       Auxiliary Steam                                                                                                  SYSTEM NUMBER:  27 CD     CD (n
Active I  Size  Vahle Actuatir  I)rawing          I'Psitiun          Required           (:ode Valve In/ Name Class Ca. Pa-ssive (in.) Type   Type     & Ccord   Nornal Sarety    Fail-Safe   Test   Frequency  Dur. Prucedurre         Remarks        CD 0 Ct)    CD HYV.1AS-101A     3    B     Active     8   Gate           27-I (D-3)    O      S                 ST-S        a           IOST-47,3G AUX STEAM ISOL VLV                                                                                RPV       2YR          1OST-47.3G HYV-1AS-10183    3    8     Active     8   Gate           27-1 (D-2)   0       S                  ST-S       a           1OST-47.3G                    cc     0 AUX STEAM ISOL VLV                                                                                RPV       2YR           IOST-47.3G 0) 3
                                                                                                                                                        -n 0
U3 CD CD C) C)

UCD CD      0)
Beaver Valley Power Station Unit I IST Program (D
VALVE TABLE                                                                                       CD      <
SYSTEM NAME:        Reactor Plant River Water                                                                                                SYSTEM NUMBER:            30          (D Actv*e I  Size    Vslve Actuator  Drawing           Position            Required              Code Valve ID I Name Class Cat,  Passive   (in.)   Type   Type     & Coord   Normal Safety    Fail-Safe    Test   Frequ ency    Iev. Procedure          Remarks                       00 (J)     CD 1RW-106           3    C     Active    24     Check          30-1 (A-9)   0     O/S                  CV-O        0                1OST.30,2 RW SUPPLY A HDR CHECK                                                                                CV-O        a                1OST-30.6A                                       C,)
CV-DIS     CVCM     VROJ - 43 1I2CMP-75-WAFER    Sample CHECK-1M           Disassembly and Inspection with
[1RW-107) per          -n     -
CVCM Program.        (0 PMT      CVCM     VROJ - 43 1OST-30,4JAC       Partial stroke open   C5 during return of      03 River Water Header to service after Disassembly and            2 1RW-107           3    C     Active    24     Check          30-1 (D-9)   0     OS                   CV-O        0                1OST-3065                                0)
RW SUPPLY B HDR CHECK                                                                                CV-O        Q                1OST-30,3 CV-DIS     CVCM     VROJ - 43 1/2CMP-75-WAFER    Sample CHECK-IM           Disassembly and Inspection with
[1RW-1061 per CVCM Program.
PMT      CVCM     VROJ - 43 1OST-304AC         Partial stroke open during return of River Water Header to service after Disassembly and Inspection.
IRW.133          3     C    Active      3     Check          30-2 (C-4)  O/S     S                 CV-BDT-O      0                IOST-30.148
                                                                                                                                                                           -0 CONT ROOM AC COND BOOSTER PMP (1VS-P-3A) INLET CHECK                                                 CV-S        a                1OST-30,14A 1RW.134          3     C    Active      3     Check          30-2 (D-4)  O/S     S                 CV-BDT-O      0                1OST-30. 14A CONl ROOM AC COND BOOSTER PMP (1VS-P-3B) INLET CHECK                                                 CV-S        a                1OST-30.14B IRW-142          3     B    Active      3      Ball          30-2 (C-4)   S      0                    MAN       2YR               1OST-30.14A CONT ROOM CLG COIL (1VS-E-14A, INLET ISOL IRW-143          3     B    Active      3      Ball          30-2 (D-4)   S      0                    MAN       2YR               IOST-30.14B CONT ROOM CLG COIL (1VS-E-14B) INLET ISOL (0 CD CD~
SCD 00 00

U) CD Beaver Valley Power Station Unit 1 IST Program                                                                    CD       0)
VALVE TABLE                                                                                          CD CD       C
                                                                                                                                                                            --I&#xb6; SYSTEM NAME:        Reactor Plant River Water                                                                                               SYSTEM NUMBER:             30 CD       CD Active/   Size     Valvc    Actuator   Drawing           position           Required           Code
                                                                                                                                                                                 ~  0)
Valve ID / Nainc Class CAL   Passite   (in.)    T)pt      Type      & Coord   Normal Safety    Fail-Sare   Test   Freqaency Des. Procedure           Remarks               CD       C IRW.150          3     B    Active      3       Ball              30-2 (C-5)   S      0                  MAN        2YR          1OST-30.14A CONT ROOM CLG COIL (1VS-E-14A) OUTLET ISOL
                                                                                                                                                                            -n 1RW-151           3     B    Active      3       Ba"l              30-2 (0-5)   S      0                  MAN        2YR          1OST-30,14B                              0 CONT ROOM CLG COIL (lVS-E-148) OUTLET ISOL C:
IRW-152           3     B    Active      3       Ball              30-2 (C-3)   0       S                 MAN       2YR           IOST-30.14A CONT ROOM AC COND (I VS-E-4A) OUTLET HDR ISOL IRW-153           3     B    Active      3       Ball              30-2 (D-3)   0       S                 MAN        2YR          1OST-30.14B CONT ROOM AC COND (1VS-E-4B) OUTLET HOR ISOL                                                                                                                               CD       C IRW-158           3     C    Active      3      Check              30-2 (E-5)  OlS     OfS                CV-O        R           1OST-30.12B CHARGING PUMP COOLER B SUPPLY HEADER CHECK                                                                CV-O        0           1OST-30.14A CV-S        a           IOST-30.14B 1RW-159           3     C    Active      3      Check              30-2 (C-5)  01S    OtS                 CV-O        R           10ST-30.12A CHARGING PUMP COOLER A SUPPLY HEADER CHECK                                                                CV-O        a           1OST-30.14B CV-S        a           IOST-30.14A IRW.206           3     B    Acive       6     Butterfly          24-2 (F-10)  LS      0                  MAN       2YR           IOST-24.10         Position Verification STEAM GEN AUX FW Pp EMER SUPPLY HDR ISOL                                                                                                             31 Days per Tech.
Specs.
IRW-207           3     B    Active      6     Butterfly          24-2 (G-9)    S      0                  MAN       2YR          IOST-24.10          Position Verification STEAM GEN AUX FWPP EMER SUPPLY HDR ISOL                                                                                                                                      CD 31 Days per Tech.
0)
STEAM GEN AUX FW PP (1FW-P-2) EMER SUP HOR ISOL                                                                                                      Specs, 00 IRW-209           3     8    Active      4     Butterfly          24-2 (G-2)    S      0                  MAN       2YR          1OST-24.10          Position Verification 31 Days per Tech.
STEAM GEN AUX FW PP (1FW-P-3A) EMER SUP HOR ISOL                                                                                                     Specs.
1RW-21 0          3     B    Active      4     Butterfly           24-2 (F-5)   5      0                  MAN       2YR           1OST-24.10         Position Verf'ication 31 Days per Tech.
STEAM GEN AUX FW PP (1 FW-P-3B) EMER SUP HIR ISOL                                                                                                    Specsp 1RW-46            3     C    Active      3     Check               30-1 (A-2)   S     O/S                 CV-O        Q           IOST-30.2 RP RW PP 1A VACUUM BKR                                                                                   CV-S-LT      a          IOST-30.2

cn  CD Beaver Valley Power Station Unit 1 IST Program                                                                      CD      0)
P_      CIS
                                                                           'VALVE TABLE CD      <
SYSTEM NAME:          Reactor Plant River Water                                                                                             SYS. TEM NUMBER:          30 CD      C Active I  Size    Valve Actuator  Drawing          Position           Required             Code Valve 1WI Nrame  Class  Cat. Passive   (in.)   Type   Type     & Coord   Normal Safety   Fail-Safe   Test   Frequnmcy   Dev. Procedure            Remarks                     0)
IRW-487            3     C    Active      3     Check          30-1 (C-2)    S    OiS                CV-0        a                1OST-30.3 RP RVVPP 1B VACUUM BKR                                                                              CV-S-LT      a               1OST-30.3                               (0       0 1RW-488            3     C    Active      3     Check          30-1 (D-2)    S    O/S                CV-0        0               1OST-30.6B RP RW PP IC VACUUM BKR                                                                               CV-0        a               1OST-30.6A
                                                                                                                                                                          -4      -
CV-S-LrT     a               1OST-30.6B                               ~0 CV.S-LT      a                1OST-30,6A (0
1RW-57             3     C    Active     20     Check          30-1 (A-3)    0    O/S                CV-S    0 or CSD  VCSJ -24   1OST-30.6A                              a)
RP RW PP (IWR.P-1A) DISCH CHECK                                                                      CV-0        a               1OST-30.2                                3 1 RW-58            3     C    Active     20     Check          30-1 (C-3)    0    O/S                CV-S    Q or CSD  VCSJ *24   1OST-30.6B                             -0 CA RP RW PP (IWR-P-1B) DISCH CHECK                                                                      CV-0        a                105T-30.3 C
1RW-S9             3     C    Active      20    Check          30-1 (D-3)    0    OS                 CV-S    Q or CSD  VCSJ -24   1OST-30.6A RP RW PP (1WR.P-1C) DISCH CHECK                                                                      CV-S    Q or CSD  VCSJ - 24 1OST-30.68 CV-0        a               1OST-30.6A CV-0        a               1OST-30.66 1 RW-615           2     B    Active      1      Bail          43-2 (D-2)    0     S                 MAN        2YR               1OST-47.3N RAD MONITOR (RM-1RW-100A) INLET ISOL 1RW-621            2     8    Active      1      Ball          43-2 (D-7)    0     S                 MAN        2YR               1OST-47.3N RAD MONITOR (RM-1RW-100B) INLET ISOL 1RW-627            2     B    Active      1      Ball          43-2 (F-2)   0      S                 MAN        2YR              iOST-47,3N RAD MONITOR (RM-1RW-100C) INLET ISOL CD 1RW-633            2     B    Active      1      Bag           43-2 (F-7)    0     S                 MAN        2YR               IOST-47.3N RAD MONITOR (RM-1RW-IOOD) INLET ISOL                                                                                                                                      0.
1WT-383            3     C    Active      3     Check          30-2 (8-2)    S     S                CV-DIS     CVCM    VROJ .44  112CUP-75-WEST       Sample                  0)   -
CHECK-1 M            Disassembly and         090
[CV.562] OUTLET CHECK                                                                                                                                 Inspection with 1lWT-388] per CVCM Prooramr

CD   C Beaver Valley PowerStation Unit 1 IST Program
_  D VALVE TABLE                                                                                  CD   <
SYSTEM NAME:         Reactor Plant River Water                                                                                                SYSTEM NUMBER:           30  CD   C Cn ActiveI   Size     Valve    Artmarar  Drawlng           Position         Required             Code ValveIDIName     Class CPL    Passive  (L0.)    Type      Type     &Coord    Normal Sarety Fail-S.re    Test   Frequency   D". Procedure          Remarks 1WT-388            3    C     Aclive     3     Check              30-2 (G-2)   S      S                CV-DIS    CVCM    VROJ -44  1I2CMP-75-WEST     Sample                  CD )
(CJ-563] OUTLET CHECK                                                                                                              CHECK-IM           Disassembly and Inspection with     0    0D
[1WT-3831 per CVCM Program.
MOV.IRW-102A1      3    B    Passive    20     Butterfly  MOV     30-1 (8.4)   S      S                 RPV       2YR              1OST-1b0                               -n    C1 0
IA RP RW PUMP DISCH VLV TO B-HOR MOV-tRW-102A2      3    B     Active    20     Buttedry   MOV     30-1 (A-4)   0      0                  ET         Q              1OST-30.2          Per OMN-1 IA RP RW PUMP OISCH VLV TO A-HDR                                                                     DIAG-ST-O     9YR             112-CMP-75-Quartet Per OMN-1           Co Tum-lE RPV       9YR              1/2-CMP-75-Cuarter Per OMW-1            CL Tum-lE                                  <
MOV-IRW.10281      3    B     Active    20     Butterfy   MOV     30-1 (C-4)   S      0                  ET         a              1OST-30.3          PerOMN-1 CD 1B RP RW PUMP DISCH VLV TO B-HDR                                                                     OIAG-ST-O    9YR              1/2-CMP-75-Ouarter Per OMN-1 Tum-lE RPV       9YR              112-CMP-75-Ouarter Per OMN-1 Tum-lE MOV-IRW-10262      3    B    Passive     20    Butterfly  MOV     30-1 (C-4)   S      S                 RPV       2YR              IOST-1.10 16 RP RW PUMP DISCH VLV TO A-HDR MOV.IRW-ID2CI      3    B     Active    20     Butierfly  MOV     30-I (D-4)   S      0                  ET    QorCSD    VCSJ - 25 1OST-30,6B         PerOMN-1 IC RP RW PUMP DISCH VLV TO B-HDR                                                                     DIAG-ST-O    9YR              112-CMP-75-Cuarter Per OMW-I Tum.1E RPV       9YR              1"2-CMP.5-Quarter  Per OMN-I Tum-lE                                    CD MOV.IRW.102C2      3    B     Active    20     Butterfly  MOV     30-1 (0-4)   S      0                  ET    Oor CSO   VCSJ - 25 1OST-30.6A         Per OMW-i 1C RP RW PUMP DISCH VLV TO A.-DR                                                                     DIAG-ST-O    9YR              1/2-CMP-75-Cuarter Per OMN-I              CD Tum-lE RPV       9YR              1/2-CMP-75-Quarter Per OMN-I Tum-lE                                  0.
MOV-IRW-103A       3    B     Active    24     Butterfly  MOV     30-3(8-2)    S     OIS                 ET         Q              1OST-30.4          Per OMN-i IA HDR RP RW TO RECIRC SPRAY HXS ISOL VLV                                                            OIAG-ST.O   4.SYR             1/2-CMP-75-uarter  Per OMN-I Tum-IE                                  0Cd)
DrAG-ST-S   4.SYR             112-CMP-75-Quarer  Per OMN-1 Turn-lE RPV      4.5YR             1V2-CMP-75-Ouarter Per OMN-1 Tum-lE

(a    D CD       0)
Beaver Valley Power Station Unit 1 IST Program                                                              _     D VALVE TABLE                                                                        (D     <
SYSTEM NAME: Reactor Plant River Water                                                                                                 SYSTEM NUMBER:    30  (D      (
Aclive /  sue    Valve    Actuator  Drawling          Poeition         Required            Code                                  (a Valve 1D/ Name  Class Cat. Passlsc (in.)    Type      Type     & Coord   Normal Safety Fail-Safe    Test    Frequency Dev. Procedure           Remarks               00 MOV-IRW-1038      3    B    Active   24    Butterfly  MOV     30-3 (B-2)   S     OfS                 ET          Q          1OST-30.4          Per OMN-I IA HDR PP RW TO RECIRC SPRAY HXS ISOL VLV                                                       DIAG-ST-O    4.SYR        1/2-CMP-75-Ouarter  Per OMN-I Turn-i E DIAG-ST-S    4.SYR         1/2-CMP-75-Ouarier Per OMN-I    -0       0 Turn-1 E RPV       4.SYR        1U2-CMP-75-Quarter  Per OMN-1 Turn-1 E MOV-IRW-103C      3    B    Active   24    Butterfly  MOV     30-3 (C-2)   S     O/S                 ET          a          1OST-30.S          Per OMN-1    -n 18 HOR RP RW TO RECIRC SPRAY HXS ISOL VLV                                                        DIAG-ST-O    4.6YR        1/2-CMP.75-Ouarter  Per OMN-i    0 Tum-1E DIAG-ST-S    4.5YR        1/2-CMP-75-Ouarlet  Per OMN-I Turn-1 E RPV       4.SYR        1i2-CMP-75-Guarter  Per OMN-1 Turn-l E MOV-1RW-103D      3    8    Active   24    Butterfly  MOV     30-3 (0-2)   S     O/S                 ET          0          1OST-30.5          Per-OMN-1 CD 16 HDR PP RW TO RECIRC SPRAY HXS ISOL VV                                                         ODAG-ST-O    4.5YR         t/2-CMP-75-Ouauter Per OMN-I Turn-1E OIAG-ST-S    4.$YR        1/2-CMP-75-Ouarter  Per OMN-1 Turn-iE RPV       4.5YR        1/2-CMP-75-Quarter  Per OMN-1 Turn-lE MOV.IRW-104       3    B   Passive   24    Butterfly  MOV     30-3 (E-6)   S       S                RPV        2YR         lOST-1.10 IAHDR TO 18 HDR RP RW CROSS CONN VALVE MOV-IRW-104A      2    6    Active    14   Butterfly  MOV     30-3 (C-6)   0       S             DIAG-ST-S     9YR         1/2-CMP-75-Guarter  Per OMN-1 Turn-IE IA RECIRC SPRAY HX INLET ISOL VLV                                                                   RPV        9YR         1/2-.CMP-75-Quarter Per OMN-I       Ci)
Turn-I E ET     t0MOorR        IOST-30.4           PerOMN-1 MOV-.RW.104B      2    B    Active    14   Butterfly  MOV     30-3 (F-6)   0       S             DIAG-ST-S     9YR         112-CMP-75-Ouarter  PerOMN-1 Turm-I E 16 RECIRC SPRAY HX INLET ISOL VLV                                                                   RPV        9YR         1f2-CMP-75-Ouarter  Per OMN-1       CD   -
Tunm-IE ET    I8MO or R       IOST-30.5           Per OMN-1 MOV-IRW-104C      2    8    Active   14    Butaerfly  MOV     30-3 (0-6)   0      S              DIAG-ST-S    4.5YR        1/2-CMP-5-Ouarter   Per OMN-1 Tum-1E IC RECIRC SPRAY HX INLET ISOL VLV                                                                   RPV       4.SYR        112-CMP-75-Ouarter  Per OMN-i Tum-lE ET    18MO or R       1OST-30A            Per OMN-1 C: CD)

Beaver Valley Power Station Unit 1 IST Program                                                               CD D0 CD VALVE TABLE CD D SYSTEM NUMBER:     30 -0       0 SYSTEM NAME:       Reactor Plant River Water                                                                                                                   CD     ~
Active I  Size     Valve    Actuator  Drawing           Posiion          Required            Code Val-e IDI Name Class CaL   paive     (in.)    Type      Type     & Coord   Nornul Safety Fail-Safe    Test    Frequency Deo. Procedure           Remarks                0, MOV-1RW-1040     2    8    Active      14    Butterfly  MOV     30-3 (G-61   0      S              DIAG-ST-S     9YR         1,2-CMP-75-Ouarter  Per OMN-1 Tum-lE 1D RECIRC SPARY HX RW INLET ISL VLV                                                                   RPV        9YR         112-CMP-75-Ouarte   Per OMN-1     0o Tum-lE ET     18MOcrR        tOST-30.5           Per OMN-1 MOV-1RW-105A     2    8    Active      14    Butterfly  MOV     30-3 (C-9)   0      S              DIAG-ST-S     9YR         t-CMP-75-Quarter    Per OMN-1     -n Turn-1E IA RECIRC SPRAY HX OUTLET ISOL VLV                                                                    RPV        9YR         1/2-CMP-75-Quarter  Pe" OMN-1     -0      ~
Turn-lE                           Co ET     18MO or R      IOST-30.4           Per OMN-1     3~
MOV-1RW-1058     2    8    Active      14    Butterfly  MOV     30-3 (E-9)   0      S              DIAG-ST-S     9YR         1r2-CCMP-75-Ouarter Per OMN-1 Turn-lE iB RECIRC SPRAY HX OUTLET ISOL VLV                                                                    RPV        9YR         112-CMP-75-Ouaerter Per OMN-1     a)
Turn-lE ET     18MO of R      IOST-30.5           Per OMN-1     Z MOV.IRW-iosC     2    B    Active      14    Butterfly  MOV     30-3 (O-9(   0      S              DIAG-ST-S     9YR         1/2-CMP-75-Quarter  Per OMN-1 Turn-lE un1 1C RECIRC SPRAY MXRW OUTLET 1501 WVV                                                                  RPV        9YR         112-CMP-75-Quarter  Per OMN-1 Turm-1E                                CD ET     IBMOorR        1OST-30.4           Per OMN.1 MOV-IRW-1050     2    B    Active      M4    Butterfly  MOV     30-3 (F-9)   0      S              DIAG-ST-S     9YR         112-CMP-75-Ouarler  Per OMN-1 Turn-lEE ID RECIRC SPRAY HX OUTLET ISOL VLV                                                                      PumR1 RPV        9YR          112-CMP-75-Ouarter Per OtAN-1 Turn-1E ET     18MO or R       1OST-30.5          Per OMN-1 MOV-1RW-106A     3    8    Active      24    Butterfly  MOV     30-3 (C-i)   0     OIS                 ET         a          1OST-30.4           Per OUN-1 CCR HX RW SERIES SOL VLV                                                                           DIAG-ST.O    4.5YR         112-CMP-75-Ouarter Per OMN-1 Turn-1E DIAG-ST-S    4.5YR         112-CMP-75-Ouarter Per OMN-1 Tum-lE                               CD    -
RPV       4,fVR         112-CMP-75-ouarter Per OMN-1 Turn-lE                                .0, MOV-1RW-106B     3    B    Active     24     Bultedly   MOV     30-3 (F-1)   0     OfS                 ET         a           IOST-30.5          Per OMN-1 CCR HX RW SERIES LSOL VLV                                                                          DIAG-ST-O    4.5YR         1t2-CMP-75-Ouarter Per OMN-1 Turn-iE DtAG-ST-S    4.SYR         112-CMP-75-Ouarter Per OMN-1 Turn-IE RPV       4.SYR        1r2-CMP-75-Quarter  Per OMN-1 Tum-lE 0
00

5-     CD (n      CD Beaver Valley Power Station Unit 1 IST Program                                                                  CD VALVE TABLE CD       <
SYSTEM NAME:        Reactor Plant River Water                                                                                                  SYSTEM NUMBER:    30 (D      C Active    Size     Valve    Actuator   Drawing            Position            Required           Code 0)
VaIVe ID Name   Class Cal. Pasuive   (0.)      Type     Type      & Coord   Nortlnz Safety    Fail-Safe    Test   Frequency Dev. Procedure           Remarks MOV-1.RW-113A     3     B     Active     4       Gate     MOV     30-1 (F-10)   S       0                     ET         a         1OST.30.4           Per OMN-i     0       0<
DIESEL GEN HX (1EE-E-1A) INLET IA SUPPLY HDR ISOL                                                         DIAG-ST-0    SYR         112-CMP-E-75-I022   Per OMN-1 RPV       SYR         1t2-CMP-E-75-021    Per OMN-1    =       -1 (0
MOV-IRW-113B      3     B     Active     4       Gate     MOV     30-1 (F-10)   S       0                     ET         a         1OST-30.4           Per OMN-1 DIESEL GEN HX (IEE-E-1A) INLET 1A SUPPLY HDR ISOL                                                         DIAG-ST-O    9YR         lr2-CMP-E*75-021    Per OMN-1 RPV       9YR         112-CMP-E-75-021    Per OMN-I    -4      -
MOV.IRW-113C      3     B     Active     4       Gate     MOV     30-1 (G-10)   S       0                     ET         a         10ST-30.5           Per OMN-1 CL     C/
DIESEL GEN HX (1EE-E-1 B) INLET 1B SUPPLY HDR ISOL                                                        DIAG-ST-0    9YR         1/2-CMP-E-75-021    Per OMN-1 RPV       9YR         1r2-CMP-E-75-021    Per OMN-1 MOV-1RW-41301     3     B     Active     4       Gate     MOV      30-1 (G-9)   S       0                     ET         a         1OST-30.5           Per OMN-1    (0 DIESEL GEN HX (IEE-E-1 B) INLET 18 SUPPLY HDR ISOL                                                        DIAG-ST-O    9YR         1m2-CMP-E-75-021    Per OMN-1 RPV       9YR         142-CMP-E-75-021    Per OMN-1 MOV-1RW-114A      3     B     Active    24     Butterfly  MOV      30-3 (B-1)   0      O/S                    ET         0         1OST-30.4           Per OMN-1 CCR HX RW SERIES ISO VLV                                                                                  DIAG-ST-O   4.SYR        1t2CMP-75-Ouarter   Per OMN-1 Tum-lE DIAG-ST-S   4.5YR        1/2CMP-75-Quarter   Per OMN-1 Tum-lE RPV      4.SYR        1l2-CMP-75-Guarter  Per OMN-i Tum-IE                           0)
MOV-1RW.114B      3     B     Active    24     Butterfly  MOV      30-3 (F-i)   0      O/S                    ET         a         10ST-13,5           Per OMN-I CCR HX RW SERIES ISOL VLV                                                                                 DIAG-ST-O   4.5YR        1,2CMP-75-Ouarter   Per OMN-1 Tum-1E DIAG-ST-S   4.5YR        112CMP-75-Quanter   PerOMN-I     0 Tum-lE RPV      4.SYR        1i2-CMP-75-Ouarter  Per OMN-1 Tum-lE                              0)
MOV-1RW-116       3     B    Passive     8     Butterfly  MOV      30-3 (D-1)    S      S                    RPV       2YR         IOST-1,10                             :3 1A HDR RP RW SUP TO CNMT AIR RECIRC CLRSICMPR C: CD)

8 CD Beaver Valley PowerStation Unit I IST Program CD VALVE TABLE (D     <
SYSTEM NAME: Reactor Plant River Water                                                                                                             SYSTEM NUMBER:    30 (D     C Active I   Size   Valve       Adtualor   Drawring          Position            Required           Code Valve IDJName   Class Cal. Passive    (In,   Type         Tvpe      & Coord   Normal Safety    Fall-Safe    Tea    Frequency Dev.. Procedure            Remarks (a      0 MOV.IRW.IIEA       3    8     Active     24   Butterfly     MOV     30-1 (6-10)   S     O/S                    ET                    1IoST-30,lA           Per OMN-1
                                                                                                                                                                              &3 D ARW PUMP SUP TO A HDR RP RW                                                                                OIAG-ST-O    9YR            112CMP-75-Ouarter   Per OMN-t Tum-lE DIAG-ST-S    9YR            I12CMP-75-Quarler   Per OMN-1            0)
Tum-l1E                           0      0 RPV       9YR             1/2-CMP.75-Quarter Per OMN-1 Turn-1E MOV-IRW-1168       3    B     Active     24   Butterfly     MOV     30-1 (D-10)   S     01S                    ET        a             1OST-301B           Per OMN-1 ARW PUMP SUP TO B HDR RP RW                                                                                OIAG-ST-0    9YR            II2CMP-75-Ouader    PerOMN-1 Turn-lE                            0 DIAG-ST-S    9YR            1I2CMP-75-Ouefter   Per OMN-1 Tum-lE RPV       9YR            112-CMP-75-Ouarter  Per OMN-1
_____Tum-lE                                                                                                        3 MOV-1RW.117        3    B    Passive      8   Butterfly     MOV      30-3 (F-1)   S       S                   RPV       2YR            1OST-110 1B HOR RP RW SUP TO CNMT AIR RECIRC CLRSICMPR RV-IRW-101A        2    C     Active  3/4 x 1  Relief        RV      30-3 (C-8)   S     O/S                   SPT      1OYR            1BVT 1.60.5                       <      0 RECIRC SPRAY HX (IRS-E-1A) OUTLET RELIEF                                                                                                                                 a)     X.
RV.IRW.10tB        2    C     Active  3/4 x 1  Relief        RV      30-3 (E-8)   S     OIS                   SPT      IOYR           .IBVT 1.60Z                        CD RECIRC SPRAY HX (1RS-E-1B) OUTLET REUEF RV.1RW-I11C        2    C     Active  3/4 x 1  Relief        RV      30-3 (D-8)   S      O/S                  SPT      1OYR            1BVT'1,60.5 RECIRC SPRAY HX (IRS-E-IC) OUTLET RELIEF RV-1RW-1OID        2    C     Active  3/4 x I  Relief        RV      30-3 (F-8)   S     O'S                   SPT      IOYR            1BVT 1.60.5 RECIRC SPRAY HX (1RS-E-1D) OUTLET RELIEF RV-IRW-102A        3    C     Active  314 x 1  Relief        RV      30-3 (C-2)   S     OS                    SPT      lOYR            iBVT 1.60.5 RP CCCW HX (1CC-E.IA) RELIEF RV-1RW-1028        3    C     Active  314 x I  Relief        RV      30-3 (D-2)   S     O/S                   SPT      1OYR            IBVT 1.60.5 AP CCW HX (1CC-E-11B) RELIEF RV-IRW-102C        3    C     Active  3/4 x I  Relief        RV      30-3 (E-2)   S     O/S                   SPT      10YR            1BVT 1.60.5 RP CCW HX (1CC-E-1 C) RELIEF (D
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SYSTEM NAME:         Reactor Plant River Water                                                                                          SYSTEM NUMBER:  30 CD Active I  Size    Valve  Actuator  I)ro~.ing        Position         Required.           Code Vahe ID / Name   CIass Cat. pasiv*e   (in.)   Type    Type     & Coord   Normal Safety Fail-Soae   Test    Frequency I)ev. Procedurt           Remarks          0 RV-1RW-106A        3    C     Acive   314 x 1  Relief   RV     30-1 (E-8)   S     0/S               sPT       10YR          1BVT 1.60.5 (0    0 DIESEL GEN FX (i EE-E-1A) RELIEF RV-1RW-1068        3    C   . Acthie  34 x 1   Relief   RV     30-1 (E-7)   S     O/S               SPT       10YR          1BVT t60.5
                                                                                                                                                            -n DIESEL GEN HX (1EE.E-18) RELIEF (0
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Beaver Valley PowerStation Unit 1 IST Program
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SYSTEM NAME: Fire Protection                                                                                                         SYSTEM NUMBER:        33 -- I     0 CD Activel Size  Valve Actuator  Drawing          Position         Required              Code Valve ID I Name Class Cal. Passive (in.) Type   Type     & Ceord   Normal Safely Fail-Safe   Test    Frequency   Dev. Procedure           Remarks 1FP-800          2    A/C  Active    3   Check          33-2 (D-4)  :S      S                LTJ        SP               18VT 1.47L5                          (n       CD WEIGHT LOADED CHECK VALVE                                                                  CV-ME       CSD     VCSJ -26  10ST-!.10                                     C/)
1FP-804           2   AMC Active     3   Check          33-2 (D-5)   S      S                LTJ        SP               18VT 147.5 WEIGHT LOADED CHECK VALVE                                                                  CV-ME       CSD     VCSJ.- 26 lOST-1.10 0) 1FP8"27           2   A/C  Active    4   Check          33-2 (D-4)   S      S                LTJ        SP               18VT 1.47,5
                                                                                                                                                              -U WEIGHT LOADED CHECK VLV                                                                    CV-ME       CSD     VCSJ- 26  1OST-1,10                            C:
TV.1FP-105        2    A   Active    4   Gale    TV     33-2 (C-5)   S      S        S       LTJ        SP               1BVT 1.47.5 CABLE PENET DELUGE ISOL TRIP VLV                                                            FS-S         0               10ST-47.3P ST-S         a               1OST-47-3P RPV    2YR/18MO             1OST-47.3P          18 months per    0l)
Tech. Specs.
LTJ        SP               1BVT 1.A7.5 TV     33-2 (0-4)   S      S        S 2    A   Active    4   Gale TV.IFP.106 RHR AREA DELUGE ISOL TRIP VALVE                                                             FS-S         a               1OST-47.3P ST-S         0               1OST47.3P RPV    2YPR18MO             1OST-47.3P          18 months per Tech. Spes TV.IFP-107        2    A   Active    4   Globe   TV     33-2 (C-4)   S      S        S       LTJ        SP               1BVT 1.47.5 CNMT HOSE REELS ISOL TRIP VALVE                                                             FS-S         0               1OST-47.3P                                C/
ST-S         a               1OST-4?.3P RPV    2YRJISMO             1OST-47.3P          18 months per Tech. Specs.
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SYSTEM-NAME:          Compressed Air                                                                                                            SYSTEM NUMBER:            34 (D
Active I Size     Valve  Actuator   Drawing           Position            Required             Code Valve ID I Name   Class Cat. Passive (in.)    Type    Type      & Coord   Normal Safety    Fail-Safe    Test   Frequency   Dev. Procedure           Remarks CD IIA-116             3   AJC   Active  0,75    Check             11-2 (F-7)   S      S                 CV-BDT-O      R               1OST-6.12           During cycling of PORV with (PCV-1 RC.455D) AIR SUPPLY ISOL CHECK                                                                                                                   instrument air.
CD CV-S-LT      R     VROJ- 46  1OST-6.12 LT       2YR              1OST-6.12                                     0))
IIA-117             3   A/C   Active  0.75    Check             11-2 (G-7)   S      S                 CV-BDT-O      R               1OST-6.12           During cycling of PORV with (PCV-1RC-455C) AIR SUPPLY ISOL CHECK                                                                                                                    instrument airt CV-s-LT      R     VROJ - 46 1OST-6.12 1-n 0
LT       2YR              1OST-6.12 I1A-378             3   A/C   Active   0.5    Check             11-2 (G-8)   S      S                 CV-BDT-O      R               1OST-6.12           During cycling of     C:
(PCV-1RC-456) AIR SUPPLY ISOL CHECK PORV with instrument air.
3
                                                                                                                                                                              'a CV-S-LT      R     VROJ - 46 IOST-6.12 LT       2YR              1OST-6.12                                 CL C
11A.90              2    A   Passive    2      Gate             34-2 (E-2)  LS      S                    LTJ        SP              18VI 1.47.5 INSTR AIR TO CNMT INSTR AIR ISOL                                                                         RPV       2YR              IOST-47.30 ILA-91              2   AtC   Active    1     Check             34-2 (E-3)   0      S                  CV-S-LT      SP    VROJ - 45 16VT 1.47.5         Per CVCM Program INSTR AIR TO CNMT INSTR AIR CHECK                                                                        LTJ        SP              1BVT 1.47.5                               Q')
CV-BDT-O      R               1OST-6.12           During cycling of PORV with instrument air.
ISA-14              2    A   Passive    2      Gate            34-1 (B-10)  LS      S                    LTJ        SP              1BVT 1.47.5 STATION AIR TO CONTAINMENT ISOLATION ISA-I5              2   A/C  Passive    2     Check            34-1 (B-10)   S      S                    LTJ        SP              1BVT 1.47.5 STATION AIR TO CONTAINMENT CHECK 1VS-108                   C    Active   0.5    Check             34-8 (E-9)   S      0                 CV-BDT-S    CVCM              120ST-30.218        Per CVCM Program INTAKE STRUCT WTR TIGHT DOOR #6 (PCV-1 IA-107F) CHECK                                                    CV-O     CVCM                M12OST-30.21B      Per CVCM Program IVS-42                    C    Active   0.5    Check             34-8 (B-8)   S      0                 CV-BDT-S   CVCM               1t2OST-30.21A       Per CVCM Program INTAKE STRUCT WTR TIGHT DOOR #1 (PCV-1]A-107A) CHECK                                                     CV-O     CVCM               112OST-30.21A       Per CVCM Program IVS-.46                   C    Active   0.5    Check             34-8 (8-9)   S      0                 CV-BDT-S   CVCM                i120ST.30.21A      Per CVCM Program INTAKE STRUCT WTR TIGHT DOOR #2 (PCV-1 IA-1 07B) CHECK                                                   CV-O     CVCM               1/20ST-30.21A       Per CVCM Program (a CD CD~
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cn CD Beaver Valley Power Station Unit 1 IST Program                                                                  (D       Q)
_   CD VALVE TABLE SYSTEM NAME: Compressed Air                                                                                                                SYSTEM NUMBER:         34           CD Active1  Size    Valve   Actuator  Drawing            Position            Required           Code Valve ID / Name    Class CaL Passive  (in.)   Type     Type     & Coerd    Normal Safety    Fall-Safe    Test   Frequency Dev. Procedure           Remarks                     CD 1VS-5C                    C  Active    0.5    Check            34-8 (D-8)    S       0                CV-BOT-S    CVCM         1/2OST-30.218        Per CVCM Program INTAKE STRUCT WTR TIGHT DOOR #3 (PCV-1 IA-107C) CHECK                                                   CV-O      CVCM         1/20ST-30.218        Per CVCM Program (n
1VS-54                    C  Active    0.5    Check            34-8 (D-9)    S       0                CV-BDT-S    CVCM         1/2OST-30.218        Per CVCM Program  0 INTAKE STRUCT WTR TIGHT DOOR #4 (PCV-1 IA-107D) CHECK                                                   CV-O      CVCM         1/20ST-30.21B        Per CVCM Program IVS-58                    C  Active    0.5    Check            34-8 (E-8)            0                CV-BbT-S    CVCM         1/2OST-30.21A        Per CVCM Program Cn CV-O INTAKE STRUCT WTR TIGHT DOOR #5 (PCV-11A-107E) CHECK                                                              CVCM         1/2OST-30.21A        Per CVCM Program RV.I1A-107A          3    C  Active  112 x I  Relief    RV     3"-(8-8)            O!S                   SPT      1OYR         1BVT 1.60.5 CM        CD (lIA-TK-4A) RELIEF                                                                                                                                                    -n RV-1IA-107B          3    C  Active  112 x 1  Relief    RV     34-8 (B-9)          OS                    SPT      10YR         1BVT 1.60.5 (llA-TK-4B) RELIEF RV-1IA-107C          3    C  Active  1/2 x 1  Relief    RV     34-8 (C-8)           O/S                  SPT      10YR         1BVT 1.60,5 (IlA-TK-4C) RELIEF RV-11A-1070          3    C  Active  1/2 x 1  Relief    RV     34-8 (C-9)           0/S                  SPT      10YR         1BVT 1.60.5 (1 A-TK-40) RELIEF RV-11A-I07E          3    C  Active  112 x 1  Relief    RV     34-8 (E-8)           O0S                  SPT      10YR         1BVT 1.60.5
[I1A-TK-4E] RELIEF RV-liA-107F          3    C  Active  1/2 x 1  Relief    RV     34-8 (E-9)           O1S                  SPT      1OYR         1BVT 1.60.5                           (0 (1IA-TK-4F] RELIEF RV-1IA-108           3    C  Active  1 x 1.5  Relief    RV     11-2 (E-9)           O0s                  SPT-     10YR         1BVT 1.60.5                              0
                                                                                                                                                                        -5 RELIEF VALVE AFTER PCV-11A-108                                                                                                                                       C:      :
RV-1IA-109           3    C  Active  1 x 1.5  Relief    RV      11-2 (F-9)          0/S                  SPT      10YR         1BVT 1.60.5 RELIEF VALVE AFTER PCV-11A-109 SPT      10OYR        liVT 1.60.5 RV-1IA-117           3    C  Active  1 x 1.5  Relief    RV     11-2 (G-9)           01S RELIEF VALVE AFTER PCV-1 IA-117

cn CD Beaver Valley Power Station Unit IIST Program                                                        CD       C VALVE TABLE                                                                              CD SYSTEM NAME:        Compressed Air                                                                                                                       CD SYSTEM NUMBER:  34 CD       CD Active/ Size  Valve Actuator  Drawing          Position           Required           Code                                 (n Valve IV / Name Class Cal. Passive (in.) Type   Ty"pe    & Coord   Normal Safety   Fail-Safe   Test   Frequency Dev. Procedure           Remarks
(   0 TV-1A.,400        2    A   Active    2   Gate    TV     34-2 (E-2) -0       S          S       LTJ        SP         18VT i.47.5
                                                                                                                                                         ~CD CNMT INSTR AIR OUTSIDE ISOL VALVE                                                             FS-S        0          1OST-47.30.
ST-S-A        a         1OST.47,30 ST-S-8        0         1OST-47.30 RPV       2YR         10ST-47.30
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SYSTEM NAME:         4KV Station Service         .                                                                              .            SYSTEM NUMBER:               .36  --I     R CD Active/   Suze  Valve   Actuator. Drawing          PosttIo    "       Required           Cede Valve DtI Name   Class Cat. Pasive    (in.) Type  . Type       & Coord   Normal Safety  Fal-,Sate  . Tst   Frequency Dev. Proctedure          Remarks C/A IDA-100            3     C      Active   0,75   Check              36.1 (A-2)   Of$    S                   CV.S      0            1OST-36.1 1A AIR COMP DISCH CHECK                                                                                CV-BDT-O    NSO            ISTC-3550            Wuring filling of Air Start Tanks
_________________________                        ..                                                                                       sting. Diesel following IDA,101            3     C      Active   0.75   Check              36-1 (A-41   OIS     S                  CV.S      a            IOST-36.1                                   -n     ~
2A AIR COMP DISCH CHECK                                                                                CV-BDT-O     NSO           ISTC-3SSO           During fling of Air Slart Tanks             0) following Diesel testing:               3 IDA.130            3     C      Aclive   0.75   Check              36-1 (A-7)   OIS    S                   CV-S      0            IOST-36-2                                   -0 18 AIR COMP DISCH CHECK                                                                                CV4BDT-O     NSO           ISTC-3550.          During filing of Air    Zn Stan Tanks following Diesel                 C testing.
1D0-131            3     C      Active   0.75   Check              36.1 (A-9)   OIS    S                   CV-S      O            1OST-36.2 CD CV-.ST-O     NSO           ISTC-3550           Durng filling of Air 21 AIR COMP DISCH CHECK                                                                    ~Start                                                             Tanks
                                                                              *                                                                      ~following Diesel.       (n testing, 11FO-10            3     C      Actve    0,75   Check              36-2 (E-5)    S    OIS                  CV-O      0            1OST-36.2 1D TRANS PUMP DISCH CHECK                                                                                  CV-S      0            !OST-36.2 IFO-116            3     8      Active     2    Gate               36-2(8-1)    LS     0                   MAN      2YR           1OST-47.3G FUEL OIL PP SUCTION CROSSCONNECT NO. I DG ISOL IFO-117            3     B      Active      2   Gate               36-2 (F-1)   LS     0                   MAN      2YR           1OST-47.30 FUEL OIL PP SUCTION CROSSCONNECT NO. 2 DG 1SOL 1CMP-75-CRANE       Sample                     CD    -
IFO.35             3     C      Active     2    Check              36-2 (B-3)    S      )                 CV-OIS   CVCM CHECK-4M            Disassembly and.
1A/1B TRANSPUMP SUCT CHECK                                                                                                                            Inspection with
[1FO46 per CVCM Program.
10ST&36.1 CV-O    CVCM PMT     CVCM           "OST-36.1           Partial suoke open per IOST-36. l after Disassembly and Inspection,:
(0 D 00

(D Beaver Valley Power Station Unit 1 IST Program                                                                          0) CD 0D        0 VALVE TABLE                                                                                      CD SYSTEM NAME:         4KV Station Service                                                                                                SYSTEM NUMBER:            36  CD        CD Active /   Size  Valve  Actuator    Drawing          Position           Required           Code                                                 ~   0)
Valve ID I Name  Clam Cat. Passive    (in.) Type    Type       & Coord   Normal Safety   Fail-Safe   Test   Frequency Dev. Procedure           Remarks               WD        (D Cla 1FO-36             3   C     Active      2   Check             36-2 (E-3)   S      0                CV-DIS     CVCM         ICMP-75-CRANE       Sample C/1D TRANS PUMP SUCT CHECK CSInspection CHECK-4AM           Disassembly and with 0      ~0
[1FO-35] per CVCM Program.
CV-0      CVCM         IOST-36.2 PMT      CVCM         1OST-36,2           Parlial stroke open   ~0 per OST-36.2 after Disassembly and
                                                                                                                                                                     -0 Inspection.
IFO-7              3   C     Active   0.75   Check             36-2 (6-5)   S     01S                CV-O        0          IST-36.1 1A TRANS PUMP DISCH CHECK                                                                            CV-S        a          iOST-36.l CD 1FO-8              3   C     Active   0.75   Check             36-2 (A-5)   S     O/S                CV-0        a          1OST-36.1 IB TRANS PUMP DISCH CHECK                                                                            CV-S        a          IOST-36.1 1FO-9              3   C     Active   0.75   Check             36-2 (E-5)   S     OS                 CV-O        Q          1OST-36.2 1C TRANS PUMP DISCH CHECK                                                                            CV-S        a          1OST-36.2 RV-IEE-101A        3   C     Active  3/4 x 1 Relief   RV       36-2 (B-4)   S     cis                 SPT       1OYR        1BVT 160.5 IA TRANS PUMP RELIEF RV-IEE-IOIB        3   C     Active  3/4 x I Relief   RV       36.2 (A-4)   S     ciS                 SPT      1OYR         1BVT 1.60.5                                 10)W 1B TRANS PUMP RELIEF 2)
RV-IEE-1OIC        3   C     Active  3/4 x 1 Relief   RV       36-2 (E-4)   S     OiS                 SPT      1OYR         1BVT .60.5 1C TRANS PUMP RELIEF                                                                                                                                                  0 RV.IEE-101D        3   C     Active  3/4 x I Relief   RV       36-2 (E-4)   S     0/S                 SPT      10YR         1BVT 1,63.5 1D TRANS PUMP RELIEF O/S                 SPT      1OYR         IBVT 1.60.5 0.
RV.IEE-201A        3   C     Active    0.5   Relief   RV       36-1 (C-1i   S 3A AIR TANK RELIEF                                                                                                                                                    0) 0 RV-IEE-2018        3   C     Active    0.5   Relief   RV       36-i (D-i)   S     O/S                 SPT      IOYR         1VT 1,60.5 38 AIR TANK RELIEF RV-IEE-201C        3   C     Active    0.5   Relief   RV       36-1 (D-If   S     0/S                 SPT      1OYR         1BVT 1.60.5 3C AIR TANK RELIEF

(n CD Beaver Valley Power Station Unit 1 1ST Program                                                                 (D    0)
:2   D VALVE TABLE CD    <
SYSTEM NAME: 4KV Sttion Service                                                                                                               SYSTEM NUMBER:  36 (D    C Active J Size  Valve   Actuator   Orawing           Position           Required                 Code Valve 10 / Name  Class Cat. Passive  (in.) Type     Type      & Ceerd   Normal Safety    fait-Safe   Test         Frequecay Dev. Procedure.           Remarks Program IIST Unit Station VALVE Power Valley Beaver                                                U)    CD RV-1EE-202A        3    C   Active    0.5  Relief    RV      36-1 (C-5)   S     O/l                  SPT            1OYR         1BVT 160.5 3D AIR TANK RELIEF RV.1EE-202B        3    C   Active    0.5  Relief    RV      36-1 (D-5)   S     O/S                  SPT            I OYR        1BVT 1.60.5                         0) 3E AIR TANK RELIEF                                                                                                                                               (a R*4ef e   RV      36-1 (D-5)   S     O/S                  SPT           1OYR          I8VT 1.60.5 RV-IEE-202C        3    C   Active    0.5 0) 3F AIR TANK RELIEF RV-IEE-203A        3    C   Active    0-5  Relief     RV     36-1 (C-6)   S     O/S                  SPT           10YR          18VT 1,60.5                      3 4A AIR TANK RELIEF                                                                                                                                               -0 RV-IEE-203B        3    C   Active    0,5  Relief     RV     36-1 (D-6)   S     O/S                  SPT           IOYR          1BVT 1.60.5 48 AIR TANK RELIEF RV.1EE-203C        3    C   Active    0.5  Relief     RV     36-1 (D-6)   S     OS                   SPT           lOYR          1BVT 1.60.5                      CD 4C AIR TANK RELIEF RV-IEE-204A        3    C   Active    0.5  Relief     RV    36-1 (C-10)   S     OS                   SPT           10YR          1BVT 1.60.5 4D AIR TANK RELIEF RV-1EE-2048        3    C   Active    0.5  Relief     RV    36-1 (D-10)   S     O/S                  SPT            lOYR         1BV'r 1.60.5 4E AIR TANK RELIEF RV-IEE-204C        3    C   Act"e     0.5  Relief     RV    36-1 (D-10)   S     O/S                  SPT           10VR          1SVT 1.60.5 4F AIR TANK RELIEF (D
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wh        CD Beaver Valley Power Station Unit 1 IST Program                                                      CD        B VALVE TABLE CD        <
SYSTEM NAME:       Control Area Ventilation                                                                                             SYSTEM NUMBER:  44A CD        (
Active I  Size      Valve    Actuator   Drawing          Position         Required           Code                                Cn Valve I / Name Class Cat. Passive   (in.)     Type      Type      & Coord   NorWal Safe4y Fail-Safe   Test   Frequency DIv. Procedure          Remarks 1VS-544          3   A/C   Active   0.25       Check             44A-2 (F.7)   S     O/S             CV-O-PR      Q          IJZOST-.44A.12A 00 CHECK VALVE FOR AIR SUPPLY TO [IVS-D-40-IA) BLADDER                                                  CV-S-LT      0          1/2OST-44A.16 LT       2YR         1/2OST-44A.16 lVS-545          3   A/C   Active   0.25       Check             44A-2 (G-7)   S     O/S             CV-O-PR      a          1/2OST.44A.12B                 (0        0 CHECK VALVE FOR AIR SUPPLY TO [1VS-D-40-1BJ BLADDER                                                  CV-S-LT      a          1/2OST-44A.16 LT       2YR         12OST44A,16                     3 1/2OST-44A.12A                  1-n 1VS-546          3   A.C   Active   0.25       Check             44A-2 (E-7)   S     OIS             CV-O.PR      a 0
CHECK VALVE FOR AIR SUPPLY TO I1VS-O-40-1Cl BLADDER                                                  CV-S-LT      a          1I2OST-44A.16 LT       2YR         1i2OST-44A.16 1VS.547          3   A/C   Active   025        Check             44A-2 (F-7)   S     ciS             CV-O-PR      Q          1i2OST-44A.12B                  3 CHECK VALVE FOR AIR SUPPLY TO [IVS-O--40-1D] BLADDER                                                 CV-S-LT      a          12OST-44A.16 LT       2YR         1i2OST-44A.16                       -o 0       S              ST-S        0          1/2OST-44A.11A                  z)
IVS-1-,40-1A     3    B    Active     48      Butterfly    D     44A-4 (C-2)
ST-S        a          1J2OST-.44A.12A                 CD CONTROL ROOM AIR INTAKE DMPR                                                                                                                                 (n RPV       2YR         1/2OST-44kA1IA RPV       2YR         1/2OST-44A.12A IVS-O40-1B       3    B    Active     48      Butterfly    D     44A-4 (C-3)   0      S               ST-S        0          1/2OST-44A-12B CONTROL ROOM AiR INTAKE DMPR                                                                          ST-S        0          112OST-44A.11B RPV       2YR         1/20ST-44AA11B RPV       2YR         12oST-44A.128 IVS.D-40-1C      3    8    Active     48      Butterfly    D     44A-4 (8-5)   0       S              ST-S        a          1/20ST-4AA.12A CONTROL ROOM AIR EXHAUST DMPR                                                                         ST-S        a          1120ST-44A.1IA CD     -
RPV       2YR         1/2OST-44A.12A                       (1)
RPV       2YR         112OST.44A.11A IVS-D-40-1O      3    B    Active     48      Butterfly    D     44A-4 (B-5)   0       S               ST-S       0          1,2OST-44AI1B CONTROL ROOM AIR EXHAUST DMPR                                                                          ST-S       0          1/2OST-44A.128 RPV       2YR         li2OST-44A.12B RPV       2YR         1t2OST.4AA11B CD 00

Cln     CD Beaver Valley Power Station Unit I [ST Program                                                                 CD       0 VALVE TABLE                                                                                        (D 44C CD       <
SYSTEM NAME: Containment Area Ventilation                                                                                                    SYSTEM NUMBER:
CD      CD Active I Size    Valve    Actuator  Drawling         Posilton            Required             Code Valve I0/ Name Class Cat. Passive  (in.)   Type      Type     & Coord   Normal Safety   Fail-Safe    Test   Frequency   Dev. Procedure            Remarks cn      C-D IVS-D-5-3A       2    A    Active   42    Butterfly    D     16-1 (D-5)   LS     S                   LTJ        SP              1BVT 1.47.5 CNMT PURGE & EXHAUST OUTSIDE CNMT ISOLATION                                                           ET    CSO or R  VCSJ - 27 lOST-110             Per OMN-1          WCD DIAG-ST-S    9YR               112CMP-75-Quarter   Per OMN-1      H       -
Tum-IE RPV       9YR              1/2CMP.75-Ouarter Tum-lE Per OMN-1 oc       0 1VS-D-5-3B       2    A    Active   42    Butterfly    D     16-1 (0-5)   LS     S                   LTJ        SP              IBVT 1.47.5                         -TI     =
ET    CSDcrR    VCSJ - 27 lOST-1.10            Per OMN-1     0)
CNMT PURGE & EXHAUST INSIDE CNMT ISOL DIAG-ST-S    SYR              12CMP-75-Ouafter     Per OMN-l Tum-lE
                                                                                                                                                                     -13 RPV       2YR               1OST-1i0 C
1VS-O-5-SA      2    A    Active    42   Butterfly    D     16-1 (E-5)   LS     S                   LTJ        SP              1BVT 1.47.5                         3 CNMT PURGE SUPPLY OUTSIDE CNMT ISOL                                                                  ET          0SD VCSJ - 27  lOST-1li0           Per OMN-1 DIAG-ST-S    9YR               1/2CMP-75-Ouarter   Per OMN-t Tum-1E CLn RPV       9YR              112CMP-75-Ouarter    Per OMN-1 Tum-lE lVS-.05-58       2    A    Actve     42   Butterfly    D     16-1 (E-S)   LS     S                   LTJ        SP               1BVT 1.47.5 ET       CSD    VCSJ - 27  1OST-lI,0           PerOMN-I       CD CNMT ISOL PURGE SUP DAMPER DIAG-ST-S    9YR               1/2CMP-75--uarter   Per OMN-I      cn Tum-lE RPV       SYR               1/2CMP-75-Ouarler   Per OMN-l Tum-lE 1VS-D-6-6       2    A   Passive     8     Ball       D     16-1 (E&5)   LS     S                    LTJ       SP               1BVT 147.5 CONTAINMENT PURGE VACUUM BREAK En 0C (D
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SYSTEM NAME:         Post DBA Hydrogen Control                                                                                             SYSTEM NUMBER:         46 (D       CD Activet   Size     Valve  Actuator  Drawing           Position            Required           Code Valve ID t Name Clas   Cat  Passive   (in.)    Type    Type     & Coord    Normal Safety   Fail-Safle    Test  Frequency Dev. Procedure            Remarks (0 0 IHY-101          2      A   Passive     2       Ball           46&1 (A-3)    LS     S                    LTJ       SP         IBVT I.47o5                            Cj)      CD RECOMBINER 1A CONTAINMENT UPSTREAM ISOLATION.                                                            RPV      2YR         1OST-47.30           RPV of Reacth Rod IHY.102          2      A   Passive     2       Ball.          46-1 (E-3)    LS     S                    LTJ       SP         1BVT 1.47.5                            cc RECOMBINER 18 CONTAINMENT UPSTREAM ISOLATION                                                             RPV      2YR         1OST-47,3t           RPV of React) Rod 1HY-103          2      A   Passive     2       BaSl           46-1 (A-3)    LS     S                   .LTJ       SP         1BVT 1.47.5 REOCMBINER 1A CONTAINMENT DOWNSTREAM ISOLATION                                                           RPV      2YR         1OST-47.30           RPV oi Reach, Rod tHY-104         2      A   Passive     2       Ball           46-1 (E-3)    LS     S                    LTJ       SP         I BVT 1,47.5 RECOMBINER 1B CONTAINMENT DOWNSTREAM ISOLATION                                                           RPV      2YR         1OST-47.3t           RPV of Reach Rod  -0 tHY-110          2      A   Passive     2       Ball           46-1 (C,2)   LS      S                    LTJ       SP         1BVT 1.47.5 RECOMBINER IA CONTAINMENT RETURN ISOLATION                                                                                                                            <        0 11"W-I11         2      A   Passive     2       Ball           46-1 (G-2)   LS      S                 ILTJ         SP         1BVT 1.47.5                             CD RECOMBINER 1B CONTAINMENT RETURN ISOLATION                                                                                                                            CD, IHY-196          2      A   Passive. 2       Banl           46-1 (C-3)   LS      S                    LTJ       SP         1BVT 1.47,5
'A&#xfd; H2 RECOMBINER OUTLET ISOL IHY-197          2      A   Passive     2       BaIl           46-1, (G-3)  LS      S                    LTJ       SP         1BVT 1,47.5 B* H2 RECOMBINER OUTLET ISOL SOV-tHY-102A1    2      A   Active   0.375     Globe   SOV     46-2 (A-3)    S     OS          S         LTJ       SP         1BVT 1.47.5 A H2 ANALYZER CNMT DOME INLET FLOW SAMPLE                                                               FS-S       0          1OST-47.30 ST-O        0          1OST-47.30 ST-S       0          1OST-47.30 RPV      2YR          1BVT 1,47,5 CD       -4 SOV-IHY-102A2    2      A   Active   0.375     Globe   SOV     46-2 (1-4)    S     01S         S         LTJ       SP         1BVT 1,47.5 A H2 ANALYZER CNMT DOME INLET FLOW SAMPLE                                                               FS-S       0          1OST-47.30 ST-O        0          1OST-47.30 ST-S       0          1OST-47.30 RPV      2YR          1BVT 1.47.5 0,
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cn CD Beaver Valley Power Station Unit 1 !ST Program                                                      CID VALVE TABLE                                                                             CD SYSTEM NAME:       Post DBA Hydrogen Control                                                                                        SYSTEM NUMBER:  46 CD        <
                                                                                                                                                       --  I     0 CD Active I  Size    Valve Actuator. Drawing           Position     . Required "         Code Valve I I Name Class Cat.. Passive  (in.)   Type   Type      & Coord   Normal Safety Fail-Safe   Test   Frequency Dev. Procedure           Remarks 00 Sov.1HY-102B1    2    A     Active  0.375    Globe  SOV      46-2 (E-3)   S     O/S       S-      LTJ        SPI        1BVT 147.5 EnCD B H2 ANALYZER CNMT DOME INLET FLOW SAMPLE                                                        FSwS         0         1OST-47.31 ST-O         0         10ST-47-31
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                                                                                                 +ST-S        0         1OST-47.31                     ~0        0)
RPV       2YR ,       1BVT 1.47.5
                                                                                                                                                       "-n SOV-IHY-10282    2    A    'Active  0.375    Globe  SOV      46-2 (E-4)   S     OIS       S,      LTJ        SP         18VT 1.47.5                    (0 B H2 ANALYZER CNMT DOME INLET FLOW SAMPLE                                                        FS-S         0Q        1OST-47.31                     -U ST-o         Q         1OST-47.31                     C)
ST-S         a         1OST-47.31 3
RPV       2YR         18VT 1.47.5 SOV-1HY-103A1    2    A     Active  0.375    Globe  SOV      46-2 (8-3)   S     OIS       S       LTJ        SP         1BVT 1.47.5 A H2 ANALYZER PRZR CUBICLE INLET FLOW SAMPLE                                                     FS-S         a         1OST-47.30 ST-0         a         1OST-47.30 ST-S         a         1OST-47.30 RPV       2YR         1BVT 1.47.5 SOV-1HY-103A2    2    A     Active  0.375    Globe  SOV      46-2 (B-4)   S     O/S       S       LTJ        SID        1BVW1.47.5 A H2 ANALYZER PRZR CUBICLE INLET FLOW SAMPLE                                                     FS-S         a         1OST-47T30 ST-0         0         1OST-47.30 ST-S         0         1OST-47.30 RPV       2YR         1BVT 1,47,5 CD SOV-1HY-10381    2    A     Active  0.375    Globe  SOV      46-2 (F-3)   S     O/S       S       LTJ        SIP        IBVT 1 47.5 B H2 ANALYZER PRZR CUBICLE INLET FLOW SAMPLE                                                     FS-S         0         1OST-47.31 ST-O         a         1oST-47.31 ST-S         0         1OST-47.31                     0~
RPV       2YR         IBVT 1.47.5
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SOV-1HY-103B2    2    A     Active  0-375    Globe  SOV      46-2 (F-4)   S     O/S       S       LTJ        SP         1BVT 1.47.5 B H2 ANALYZER PRZR CUBICLE INLET FLOW SAMPLE                                                     FS-S         a         1OST-47.31 ST-0         0         1OST-47.31 ST-S         0         1OST-47.31 RPV       2YR         1BVT 1.47.5 0       0

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Beaver Valley Power Station Unit I IST Program                                                      CD     C VALVE TABLE                                                                           CD SYSTEM NAME: Post DBA Hydrogen Control                                                                                            SYSTEM NUMBER:  46 CD Active I  Size  Valve Actuator  Drawing           Posiltion       Required           Code 0,
Valve ID I Name Class Cat. Passive   (in.) T)ye   Type     & Coord   Normal Safety Fall-Safe   Test   Frequency Dev. Procedure            Remarks SOV.1HY-104AI    2     A   Active   0.375  Globe  SOV     46-2 (C-3)   S     O/S       S       LTJ        SP         1BVT 1.475 A H2 ANALYZER FLOW SAMPLE OISCH                                                                FS-S       a          10ST-47.30                      (0      0 ST-O        a          10ST-47.30 ST-S       a          1OST-47.30
                                                                                                                                                     -4     -
RPV        YR         1BVT 1.47.5
                                                                                                                                                     ~0 SOV.IHY-104A2    2     A   Active   0.375  Globe  SOV     46-2 (C-4)   S     O/S       S       LTJ        SP         IBVT 1.475 A 1H2ANALYZER FLOW SAMPLE DISCH                                                                FS-S       a          1OST-47.30 ST-0        a          1OST-47.30                       -0 ST-S       a          1OST-47.30 C
RPV       2YR         18VT 1,475                      3 SOV-IHY-104B1    2     A   Active   0.375  Globe  SOV     46-2 (G-3)   S     OIS       S        LTJ       SP         IBVT 1.47 5 S K2 ANALYZER FLOW SAMPLE DISCH                                                                FS-S       0          IOST-47.31 ST-0         0         10ST-47.31 ST-S       0          1OST-47.31 RPV      2YR           IBVT 1.47,5 SOV-tHY.104B2    2     A   Active   0,375  Globe  SOV     46-2 (F-4)   S     O/S       S        LTJ      SP           1BVT 1.47.5 B H2 ANALYZER FLOW SAMPLE DISCH                                                                FS-S        a          1OST-47.31 ST-O         0          10aST47.31 ST-S        0          1OST-47.31 RPV      2YR           1BVT 1.47.5 CD  -
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SYSTEM NAME: Containment                                                                                                            S VSTEM NUMBER:    47  -- j      0)
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Active / Size  Valve Actuator  Drawing           Position          Required             Code Vale IDI Name  Class Cat. Passiv   (in.) *rype  Type     & Coord   Normal Safety    Fai-Safe   Tets   I-retquimey I)ev. Procedure            Remarks Ci, 1VS-167         2     A   Passive   1I5   Gall          47-1 (B-9)   S      S                  LTJ         SP           1BVT 1.47.5 (0
PH-P-I DOOR EQUALIZING VALVE 01       0 1VS-168         2     A   Passive   1.5   Ball          47-1 (B-9)   S      S                  LTJ         SP           1BVT 1.47.5 PH-P-i DOOR EQUALIZING VALVE 1BVT 1.47.5
                                                                                                                                                           -n      ~
IVS-169         2     A   Passive   1.5   Ball          47-1 (B-7)   S      S                  LTJ         SP (0
PH-P-i DOOR EQUALIZING VALVE                                                                                                                               0u MVS-170        2     A   Passive   1.5   Ball          47-1 (B-7)   S      S                  LTJ         SP           1BVT 1.47.5 3
PH-P-1 DOOR EQUALIZING VALVE
                                                                                                                                                           -a-IVS-183          2    A   Passive    2    Ball          47-1 (F-7)   S      S                  LTJ         SP           1BVT 1.47.10         Type B LT     Cn EQUIPMENT HATCH AIRLOCK EQUALIZING VALVE                                                                                                                   =3 IVS-184          2    A   Passive    2    Bell          47-1 (F-5)   S      S                  LTJ         SP           1BVT 1.47.10         Type 8 LT EQUIPMENT HATCH AIRLOCK EQUALIZING VALVE                                                                                                                   CD CD       -
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Beaver Valley Power Station                    Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                              Page 233 of 320 SECTION VII:    VALVE COLD SHUTDOWN JUSTIFICATIONS (VCSJ)
AND INDEX VCSJ         SYSTEM NO.      COMPONENT(S)
VCSJ 1              6        SOV-1 RC-1 02A, SOV-1 RC-1 02B SOV-1 RC-1 03A, SOV-1 RC-1 03B SOV-1 RC-1 04, SOV-1 RC-1 05 VCSJ2               7        1CH-75, 1CH-76 VCSJ3               7        MOV-11CH-142 VCSJ4              10        1RH-3, 1RH-4 VCSJ5              10        MOV-1 RH-700, MOV-1 RH-701, MOV-1 RH-720A, MOV-1 RH-720B VCSJ6              11        MOV-1SI-860A, MOV-1 SI-860B VCSJ7              11        MOV-1SI-865A, MOV-1SI-865B, MOV-1SI-865C VCSJ8              11        MOV-1SI-842, TV-1 SI-889 VCSJ9              11        MOV-1SI-890C VCSJ10             15        TV-1CC-110F1 VCSJ11             15        TV-1CC-1I10E2, TV-1 CC-1I10E3, TV-1CC-11 OD, TV-1CC-1l10F2 VCSJ12             15        TV-1 CC-111 Al, TV-1 CC-1 11A2, TV-1CC-111D1, TV-1 CC-1 11D2 VCSJ13             15        MOV-1 CC-11 2A2, MOV-1 CC-1i12A3, MOV-1 CC-1i12B2, MOV-1 CC-1 12B3 VCSJ14             15        1CCR-247, ICCR-248, 1CCR-251, 1CCR-252 VCSJ15             21        MOV-1MS-101A, MOV-1MS-101B, MOV-1MS-101C VCSJ16             21        NRV-1MS-101A, NRV-1MS-101B, NRV-1MS-101C VCSJ 17            21        PCV-1MS-101A, PCV-1MS-101B, PCV-1MS-101C VCSJ18             21        TV-1MS-101A, TV-1MS-101B, TV-1MS-101C VCSJ19             21        MOV-1 MS-1 05 VCSJ20             24        HYV-1 FW-1 O0A, HYV-1 FW-1 00B, HYV-1 FW-1 OC VCSJ21             24        FCV-1 FW-478, FCV-1 FW-488, FCV-1 FW-498 VCSJ22             25        TV-1 BD-1 OOA, TV-1 BD-1 00B, TV-1 BD-1 00C, TV-1BD-101A1, TV-1BD-101B1, TV-1BD-101C1 TV-1BD-101A2, TV-1BD-101B2, TV-1BD-101C2 VCSJ23             26        TV-1SV-1OA VCSJ24             30        1 RW-57, 1 RW-58, 1 RW-59 VCSJ25             30        MOV-1RW-102C1, MOV-1RW-1i02C2 VCSJ26             33        1FP-800, 1FP-804, 1FP-827 VCSJ27            44C        1VS-D-5-3A, 1VS-D-5-3B, 1VS-D-5-5A, 1VS-D-5-5B VCSJ28              7        1CH-84, 1CH-136, 1CH-141

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 234 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                   1 Valve No(s):           SOV-1RC-102A SOV-1RC-102B SOV-1 RC-1 03A SOV-1RC-103B SOV-1 RC-1 04 SOV-1 RC-105 Category:     B        Class:     1 System:                6 - Reactor Coolant System Function:              These reactor vessel head vent valves must open to vent non-condensable gasses from the reactor vessel head to Containment or the Pressurizer Relief Tank (PRT). They must close to minimize RCS pressure boundary leakage.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally closed operation during plant operation. Their safety positions are closed to minimize RCS pressure boundary leakage, and open to vent the RCS in an emergency to assure that core cooling during natural circulation will not be inhibited by a buildup of non-condensable gases.
Periodic full or part-stroke exercising in the open and closed directions during normal plant operation could degrade this system by repeatedly challenging the downstream valves due to a phenomenon known as "burping." This phenomenon has been previously described in ASME report "Spurious Opening of Hydraulic-Assisted, Pilot-Operated Valves - An Investigation of the Phenomenon." The phenomenon involves a rapid pressure surge buildup at the valve inlet caused by opening the upstream valve in a series double isolation arrangement or closing a valve in a parallel redundant flow path isolation arrangement. The pressure surge is sufficient enough to lift the valve plug until a corresponding pressure increase in a control chamber above the pilot and disc can create enough downward differential pressure to close the valve. PerISTC-3521 (c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed open and closed and fail-safe tested closed at cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510, ISTC-3521(c) and ISTC-3560.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 235 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                   2 Valve No(s):            1CH-75 1CH-76 Category:     C        Class:      3 System:                7 - Chemical and Volume Control Function:              These discharge check valves for the Boric Acid Transfer Pumps must open to allow boric acid to be supplied to the blender for normal reactivity control and to the Charging Pumps for emergency boration.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for CSJ:         These check valves may be open during power operation. They must open to provide a flow path of 4% boric acid solution from the Boric Acid Tanks via the Boric Acid Transfer Pumps to the suction of the Charging Pumps for emergency boration. They can only be full-stroke exercised by initiating the maximum required accident condition flow, in accordance with ISTC-5221 and NUREG-1482, Rev.1 Section 4.1.3, through either the emergency boration flow path and verifying it using the installed flow instrumentation in this flow path, or through the recirculation line which does not have installed instrumentation.
Testing through the emergency boration flow path would cause an undesired reactivity transient through the direct injection of 7,000 ppm borated water to the suction of the Charging Pumps. The resultant over-boration of the RCS would cause a temperature transient as Tavg dropped to compensate and could cause a plant shutdown.
The recirculation line is not instrumented, and in order to use it, a temporary flow instrument must be installed. In order to install the temporary flow instrument, the insulation and heat trace must be moved away from where the transducers and tracks must be installed. Moving the heat trace elements places stresses on them which could cause them to break. Therefore, it is not practical to use the recirc line for either quarterly or cold shutdown full-stroke testing. This is further justified by the guidance in NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," which states: "Check valves that can be stroked quarterly, but must be monitored by a non-intrusive technique to verify full stroke, may be full-stroke tested during cold shutdowns or refueling outages if another method of verifying full-stroke exists at these plant conditions. Also, the NRC would not require a licensee to invest in non-intrusive equipment for the purpose of testing check valves quarterly in lieu of testing during cold shutdowns or refueling outages, though the use of non-intrusive techniques is recommended where practical."

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 236 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  2 Basis for CSJ:         Per ISTC-3522(b), "Ifexercising is not practicable during operation at power, it shall be performed during cold shutdown."
Alternate Test:        Full-stroke exercised open at cold shutdowns through the instrumented emergency boration flow path per lOST-1.10 (Cold Shutdown Valve Exercise Test). In addition, these check valves may be full-stroke exercised open during the biennial full-flow Comprehensive test of the Boric Acid Transfer per 1OST-7.13 & 7.14 (Boric Acid Transfer Pump Full Flow Tests). (See PRR6).
NOTE: Bi-directional exercising to the non-safety related closed position will be performed once per cycle per 1OST-7.TBD (TBD).

==References:==
ISTC-3510, ISTC-3522(b) and ISTC-5221.
NUREG-1482, Revision 1, Sections 3.1.1 and 4.1.3.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 237 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 3 Valve No(s):           MOV-1CH-142 Category:     A        Class:     2 System:                7 - Chemical and Volume Control System Function:              This Residual Heat Removal (RHR) system letdown flow control valve must close to provide containment isolate of Penetration No. 28.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         This valve is normally closed during plant operation and must remain closed at power. Its safety position is closed for containment isolation of Penetration No. 28. Opening it during normal operation would divert normal RCS letdown back into the RHR system because there is no other isolation valve to the RHR system, and could cause a pressure shock in the RHR system. This valve would only be opened when the RHR system is in service. RHR is normally placed in service in Mode 4 when preparing to enter Mode 5 and remains in service upon exiting Mode 5 during plant start-up. Tech. Specs.
require Containment Isolation capability in Mode 4; therefore, this valve would have to be able to close if containment isolation was required. Therefore, because this valve cannot be opened during power operations, it will be stroked and timed closed during cold shutdowns. Per ISTC-3521(c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: Since this is a low safety significant valve, its exercise frequency may be extended to refueling per OMN-1 Paragraph 3.6.1.

==References:==
ISTC-3510 and ISTC-3521(c).
OMN-1 Paragraphs 3.6.1 and 3.6.3(b).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 238 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 4 Valve No(s):           1RH-3 1RH-4 Category:     C        Class:     2 System:                10 - Residual Heat Removal Function:              These Residual Heat Removal (RHR) Pumps discharge check valves must open to support RHR system operation and must close to prevent reverse flow through the standby RHR Pump.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for CSJ:         During normal plant operation, the RHR system is isolated from the reactor Coolant System (RCS) and these check valves are normally closed. Their safety position is open to support RHR system operation and closed to prevent reverse flow through the standby RHR Pump. They can only be full-stroke exercised in the open direction by initiating the maximum required accident condition flow in accordance withISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, when the RHR Pumps are in operation. However, during plant operation, the RHR system is isolated from the Reactor Coolant System (RCS) and the RHR Pumps are not required for operation. The RHR Pumps are only operated during cold shutdowns and refueling outages. In addition, the pumps and valves in the RHR system are also located inside the slightly subatmospheric containment and are inaccessible during normal operation.
Since the radiation levels and air temperature inside containment are higher than normal during power operation, this would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. Therefore, it is not practical to full-stroke exercise these check valves quarterly. Per ISTC-3522(c), "If exercising is not practicable during operation at power, it shall be performed during cold shutdowns."
Alternate Test:        Full-stroke exercised open and closed during cold shutdowns per 1OST-10.1 (Residual Heat Removal Pump Performance Test).

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1 Section 4.1.3.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 239 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 5 Valve No(s):           MOV-1   RH-700 MOV-1   RH-701 MOV-1   RH-720A MOV-1   RH-720B Category:     A        Class:     I System:                10 - Residual Heat Removal Function:              These Residual Heat Removal (RHR) System Inlet and Outlet Isolation Valves must open to place the RHR System in service to cool down the plant and must close and be leak tight during normal plant operation.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         During normal plant operation, the RHR System is isolated from the Reactor Coolant System (RCS) and these valves are normally closed and de-energized. They cannot be cycled at power without subjecting the RHR system (a low pressure system) to RCS pressure, and cannot be opened due to pressure interlocks. Per ISTC-3521(c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
The RHR system is configured such that the parallel discharge isolation valves, [MOV-1 RH-720A, B], can be stroked without the loss of system function during cold shutdown. However, the two series isolation valves on the pump suction, [MOV-1RH-700, 701], cannot be stroked without shutting down both RHR pumps. A failure of one of these valves to re-open after testing would render the entire RHR system inoperable. Therefore these valves can only be stroked if both RHR pumps are shutdown.
Alternate Test:        [MOV-1RH-700, 701] - Full stroke exercised and timed open when placing the RHR System into service during station shutdown to cold shutdown, and timed closed when removing the RHR system from service during station startup from cold shutdown or when the plant is defueled, not more often than once per 92 days, per 1OST-1 0.4 (Residual Heat Removal System Valve Exercise) as part of the cold shutdown valve population.
[MOV-1RH-720A, 720B] - Full stroke exercised and timed open and closed during cold shutdowns per 1OST-1 0.4 (Residual Heat Removal System Valve Exercise) as part of the cold shutdown valve population.

==References:==
ISTC-3510 and ISTC-3521 (c).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 240 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  6 Valve No(s):           MOV-1 SI-860A MOV-1SI-860B Category:     A        Class:      2 System:                11 - Safety Injection Function:              These Low Head Safety Injection (LHSI) Pump containment sump suction valves must open on low Refueling Water Storage Tank (RWST) level to align the suction of the LHSI Pumps to the containment sump. They are also required to close for containment isolation of Penetration No's. 68 and 69.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally closed during plant operation. They are containment isolation valves which are exposed to containment atmosphere.
During an accident, this flow path would be in service and filled with water; not in contact with the atmosphere. Failure of these valves in the open position during plant operation would compromise containment integrity. NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (2), states that valves whose failure to close during a cycling test that would result in a loss of containment integrity would typically be excluded from testing during plant operations. Per ISTC-3521(c),
                         "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns per 1OST-I 10 (Cold Shutdown Valve Exercise Test).

==References:==
ISCT-3510 and ISTC-3521 (c).
NUREG-1482, Rev.1, Section 3.1.1.
OMN-1 Paragraph 3.6.3(b).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 241 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  7 Valve No(s):           MOV-1SI-865A MOV-1SI-865B MOV-1SI-865C Category:     B        Class:     2 System:                11 - Safety Injection Function:              These Safety Injection (SI) Accumulator Discharge Isolation Valves must remain open to allow the SI Accumulators to discharge to the reactor coolant system (RCS) in the event of a loss of coolant accident (LOCA). They must close during a small break LOCA to prevent nitrogen from being injected into the RCS.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency", Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         During plant operation, these valves are de-energized (shorting bars are removed) in the open position which is their passive safety position. Their safety position is also closed during a small break LOCA to prevent nitrogen from being injected into the RCS. Full-stroke exercising in the open direction is not required per Table ISTC-3500-1, "Inservice Test Requirements," since the valves are passive in this direction. Full-stroke exercising in the closed direction cannot be performed during plant operation because these valves are required to be open with power removed from the Accumulator Isolation Valve operator control circuit per Technical Specification 3.5.1.5. In addition, NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (1) lists the SI Accumulator discharge valves in PWR's as one specific example of valves whose failure in a non-conservative position during the cycling test would cause a loss of system function. Therefore, these valves will not be stroked and timed during plant operation. ISTC-3521(c) states, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 when the SI Accumulators are isolated from the RCS on the way to cold shutdowns per 1OM-52.4.R.1.F (Station Shutdown from 100% Power to Mode 5), or during cold shutdowns perlOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521(c), and Table ISTC-3500-1.
NUREG-1482, Rev.1, Section 3.1.1.
Technical Specification 3.5.1.5.
OMN-1 Paragraph 3.6.3(b).

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 242 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 8 Valve No(s):           MOV-1SI-842 TV-1 SI-889 Category:     A        Class:      2 System:                11 - Safety Injection Function:              These inside and outside containment isolation valves in the SI Accumulator test line must close to provide containment isolation of Penetration No. 106 Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are shut during normal operation and are required to close for containment isolation of Penetration No. 106. Because Containment Penetration No. 106 does not have relief protection, it is required to remain drained. When these isolation valves are opened so that they can be stroke timed shut during normal operations, the Containment Penetration fills up with water and must be drained subsequent to testing. Draining the Penetration is an Operator Work Around that requires three Operators two hours to perform due to component locations. This drain down also requires entry into the four hour Required Action of Tech. Spec. 3.6.3 for an inoperable containment isolation valve in Modes 1-4. This is because vent and drain valves within the Penetration boundary must be opened to complete the drain down. Therefore, it is not practicable to test these valves during Modes 1-4. Per ISTC-3521(c),
                         "Ifexercising is not practicable during t operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        [TV-1SI-889] is full-stroke exercised and timed closed and fail-safe tested closed at cold shutdowns per 1OST-1.10 (Cold Shutdown Valve Exercise Test).
[MOV-1SI-842] is full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns per 1OST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: Since [MOV-1 SI-842] is a low safety significant valve, its exercise frequency may be extended to refueling per OMN-1 Paragraph 3.6.1.

==References:==
ISTC-351 0, ISTC-3521(c) and ISTC-3560.
Technical Specification 3.6.3.
OMN-1 Paragraphs 3.6.1 and 3.6.3(b).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 243 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  9 Valve No(s):           MOV-1SI-890C Category:     A        Class:     2 System:                11 - Safety Injection Function:              This Low Head Safety Injection (LHSI) Pump discharge valve is required to remain open in order to supply flow to the Reactor Coolant System (RCS) cold legs in an accident. It is also required to close for containment isolation of Penetration No. 61 and for transfer to hot leg recirculation should either [MOV-1SI-864A or B] fail to close.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         This valve is open during normal plant operation and is required to remain open to supply flow to the RCS cold legs in an accident. It must also be capable of closing for containment isolation of Penetration No. 61 and for transfer to hot leg recirculation should either [MOV-1SI-864A or 864B] fail to close. Since this valve is in the single flow path from the LHSI Pumps to the RCS cold legs, failure of this valve to reopen after testing would render LHSI cold leg injection from both trains inoperable. NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage,"
Example (1) states that all valves whose failure in a non-conservative position during the cycling test that would result in a loss of system function would typically be excluded from testing during pant operations. Per ISTC-3521(c),
                         "Ifexercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(c).
NUREG-1482, Rev.1Section 3.1.1.
OMN-1 Paragraph 3.6.3(b).

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 244 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 10 Valve No(s):           TV-1CC-11 OF1 Category:     A        Class:     2 System:                15 - Reactor Plant Component Cooling Water Function:              This containment air recirculation fan cooling coil river water return isolation valve must close to provide containment isolation of Penetration No. 11.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         This valve is normally closed to isolate the chilled water system from the river water system, and is required to close on a CIB signal for containment isolation of Penetration No. 11. The chilled water system is a closed loop system, and there is no other isolation valve downstream of [TV-1CC-11 OF1].
Therefore, the upstream isolation valves [TV-1 CC-1 10D and 100F2] must be closed in order to prevent loss of chilled water inventory to the river water system when [TV-1CC-110F1] is opened for stroking. However, this would require isolating cooling water to all three containment air recirculation fan coolers. If either of these valves failed to re-open or if [TV-1CC-110F1] failed to re-close, then this would result in loss of cooling for containment. Technical Specification 3.6.5 requires plant shutdown if average containment air temperature exceeds 105F. NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (1) states that all valves whose failure in a non-conservative position during the cycling test that would result in a loss of system function would typically be excluded from testing during plant operations. Per ISTC-3521(c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed and fail-safe tested closed at cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521 (c) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.
CA 03-07515-16.
Tech Spec 3.6.1.5.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 245 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  11 Valve No(s):           TV-1 CC-1 10E2 TV-1CC-110E3 TV-1CC-11OD TV-1 CC-1 10F2 Category:     A        Class:      2 System:                15 - Reactor Plant Component Cooling Water Function:              These containment air recirculation fan cooling coil water supply and return containment isolation valves must close to provide containment isolation of Penetration No's. 11 and 14.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open during power operation to supply cooling water to the containment air recirculation fan coolers. Their safety position is closed for containment isolation of Penetration No's. 11 and 14. Since the two inlet and outlet isolation valves are in series with one another, failure of one of them to re-open during stroke time testing in the closed direction would isolate cooling water to all three containment air recirculation fan coolers and would result in loss of cooling for containment. Technical Specification 3.6.5 requires plant shutdown ifaverage containment air temperature exceeds 105F.
NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (1) states that all valves whose failure in a non-conservative position during the cycling test that would result in a loss of system function would typically be excluded from testing during pant operations. Per ISTC-3521(c), "Ifexercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed and fail-safe tested closed at cold shutdowns per iOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521 (c) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.
Technical Specification 3.6.5.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 246 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 12 Valve No(s):           TV-1CC-1 11Al TV-1CC-111A2 TV-ICC-111D1 TV-ICC-111 D2 Category:     A        Class:     2 System:                15 - Reactor Plant Component Cooling Water Function:              These inlet and outlet containment isolation valves for the Control Rod Drive Mechanism (CRDM) Shroud coolers are required to close for containment isolation of Penetration Nos. 9 and 16.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open during power operation to supply cooling water flow to the CRDM Shroud Coolers, and must close upon receipt of a CIB signal for containment isolation of Penetration Nos. 9 and 16. Since these valves are in series with each other, exercising them in the closed direction would isolate cooling water flow to the CRDM Shroud Coolers. Failure of any of these valves to re-open while the control rods or shutdown rods are energized and the plant is above 250F would result in a loss of cooling ventilation to the CRDMs. NUREG-1482, Rev.1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (1) states that all valves whose failure in a non-conservative position during the cycling test that would result in a loss of system function would typically be excluded from testing during pant operations. Per ISTC-3521 (c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed and fail-safe tested closed at cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521(c) and ISTC-3560.
NUREG-1842, Rev.1, Section 3.1.1.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 247 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 13 Valve No(s):           MOV-1CC-112A2 MOV-1CC-112A3 MOV-1CC-112B2 MOV-1CC-112B3 Category:     A        Class:     2 System:                15 - Reactor Plant Component Cooling Water Function:              These RHR Heat Exchanger CCR supply and return containment isolation valves must open to supply component cooling water to the RHR heat exchangers and the RHR pump seal water coolers. They must close for containment isolation of Penetration Nos. 1, 2, 4 and 5.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are stroked and timed quarterly during power operation. During cold shutdowns, however, the quarterly testing frequency will not be maintained.
During cold shutdowns, these valves are opened to place the RHR System in service. Once the RHR System is in service, the safety function of these valves is to remain open to supply cooling water to the RHR heat exchangers and to the RHR pump seals. Per NUREG-1449, "Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States," at PWRs, the RHR System is essential to maintaining shutdown safety. In order to maintain the "Defense in Depth" strategy for shutdown safety, these valves cannot be stroked quarterly during cold shutdowns. In addition, if the RHR system is inservice as the operable RCS loops per Tech Spec 3.4.6, 3.4.7, or 3.4.8 as applicable, these valves cannot be tested without entering the required action statement which requires immediate restoration of the RCS loop. Failure of these valves during testing at that time would cause loss of cooling flow for one of the required RCS Loops.
Once the RHR system is not required to be inservice as the operable RCS loops, Tech Specs would permit the exercising of these valves. However, these valves can only be stroked and timed if their associated RHR pump is not operating. Therefore, while the plant is in mode 5 or 6, the RHR pumps would have to be swapped to exercise all of the valves. However, as a result of excessive seal leakage on a RHR pump at Unit 2 during 2R6, the Maintenance Rule (a)(1) Disposition Review recommended that a review of operating practices/procedures be performed to determine a means to reduce the frequency of pump cycling. Therefore, in order to minimize the number of pump cycles, these valves will not be stroked if either of the RHR pumps is operating. They will be stroked and timed prior to placing the RHR system in service and when removing the system from service or when the plant is defueled, not more often than once per 92 days.

Beaver Valley Power Station                      Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                  Page 248 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                13 Alternate Test:        Full stroke exercised and timed open and closed quarterly per 1OST-47.3F and 3K (Containment Isolation and ASME Section XI Tests), during power operation. Full stroke exercised and timed open and closed when placing the RHR System in service per 1OM-10.4.A (Startup of the RHR System), when removing it from service per 1OM-10.4.C (Residual Heat Removal System Shutdown (Plant Startup)) during cold shutdowns or when defueled, not more often than once per 92 days. They may also be exercised during cold shutdown per 1OST-1 0.4 (Residual Heat Removal System Valve Exercise).

==References:==
ISTC-3510.
NUREG-1449.
Technical Specification 3.4.6, 3.4.7 and 3.4.8.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 249 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 14 Valve No(s):           1CCR-247 1CCR-248 1CCR-251 1CCR-252 Category:     A        Class:     2 System:                15 - Reactor Plant Component Cooling Water Function:              These outside containment manual isolation valves must open to supply component cooling water to the Residual Heat Removal (RHR) heat exchangers and the RHR pump seal water coolers. They are required to close for containment isolation of Penetration Nos. 1, 2, 4 and 5.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally locked closed during power operation and must remain closed during an accident for containment isolation of Penetration Nos.
1, 2, 4 and 5. The valves are only required to open to place the RHR system in service. They cannot be stroked quarterly without the possibility of violating containment operability per Tech Spec 3.6.3. Therefore, per ISTC-3521 (c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdown." In addition, during normal operation, the RHR system is not required to be in service and these valves are not required to be opened; they only remain closed to fulfill their containment isolation function. Per ISTC-3570, "Valves in Systems Out of Service," for a valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within 3 months prior to placing the system in an operable status, the valves shall be exercised and the schedule followed in accordance with the requirements of Subsection ISTC.
During cold shutdowns, these valves are opened to place the RHR System in service. Once the RHR System is in service, the safety function of these valves is to remain open to supply cooling water to the RHR heat exchangers and to the RHR pump seals. Per NUREG-1449, "Shutdown and Low-Power Operation at Commercial Nuclear Power Plants in the United States," at PWRs, the RHR System is essential to maintaining shutdown safety. In order to maintain the "Defense in Depth" strategy for shutdown safety, these valves cannot be exercised every 92 days during cold shutdowns. In addition, ifthe RHR system is inservice as the operable RCS loops per Tech Spec 3.4.6, 3.4.7, or 3.4.8 as applicable, these valves cannot be tested without entering the required action statement which requires immediate restoration of the RCS loop. Failure of these valves during testing at that time would cause loss of cooling flow for one of the required RCS Loops.

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 250 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                14 Basis for CSJ          Once the RHR system is not required to be inservice as the operable RCS loops, Tech Specs would permit the exercising of these valves. However, these valves can only be exercised if their associated RHR pump is not operating. Therefore, while the plant is in mode 5 or 6, the RHR pumps would have to be swapped to exercise all of the valves. However, as a result of excessive seal leakage on a RHR Pump at Unit 2 during 2R6, the Maintenance Rule (a)(1) Disposition Review recommended that a review of operating practices/procedures be performed to determine a means to reduce the frequency of RHR Pump cycling. Therefore, in order to minimize the number of pump cycles, these valves will not be stroked if either of the RHR pumps is operating. They will be full-stroke exercised prior to placing the RHR system in service, when removing the system from service or when the plant is defueled, not more often than once per 92 days.
Alternate Test:        Full-stroke exercised open and closed prior to placing the RHR system in service per Operating Manual Chapter 1OM-10.4.A (Startup of the RHR System). Full-stroke exercised open and closed when removing the RHR System from service per 1OM-10.4.C (Residual Heat Removal System Shutdown (Plant Startup)), but may also be full-stroke exercised open and closed during cold shutdown per 1OST-1 0.4 (Residual Heat Removal System Valve Exercise Test) or when defueled not more often than once per 92 days.

==References:==
ISTC-3510, ISTC-3521(c) and ISTC-3570.
Tech Spec 3/4.6.1.1, 3/4.4.1.3.
NUREG-1449.

Beaver Valley Power Station                      Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 251 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 15 Valve Asset No(s):     MOV-1MS-101A MOV-1MS-101B MOV-1MS-101C Category:     B        Class:      2 System:                21 - Main Steam Function:              The Main Steam Trip Valve Bypass Valves must close to provide containment isolation of Penetration No's. 73, 74 and 75.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency", Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally closed during plant operation, but may be opened during Main Steam System startup prior to normal plant operation. Their safety position is closed for containment isolation of penetration no's. 73, 74 and 75.
Since, each valve is a single isolation valve without redundancy, failure to reclose during a stroke test at power could result in a loss of containment integrity. NUREG-1482, Rev.1, Section 3.1.1., "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage", lists as an example of valves to be specifically excluded from exercising (cycling) tests during plant operations: (2)
All valves whose failure to close during a cycling test and could result in loss of containment integrity. ISTC-3521(c) states, "Ifexercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed during cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521 (c).
NUREG-1482, Rev.1, Section 3.1.1.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 252 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 16 Valve No(s):           NRV-1MS-101A NRV-1MS-101B NRV-1MS-101C Category:     B/C      Class:     2 System:                21 - Main Steam Function:              These Steam Generator (S/G) non-return valves prevent reverse flow if their associated S/G is faulted or a line break occurs to prevent blowing down the intact S/Gs.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be exercised nominally every 3 months Basis for CSJ:         These valves are standard swing check valves with motor operators used to assure positive seating of the disc. The motor operator is not capable of closing the non-return valve against normal steam flow. Full or part-stroke testing of these valves at power is not possible because these valves must be open to allow steam to flow from the steam generators to the turbine. Per ISTC-3521(c) (Category B valves) and ISTC-3522(b) (Category C valves, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        The valves are exercised in the closed direction on a cold shutdown frequency. The function of the valves is to close if their associated S/Gs are faulted or if a line break occurs between the S/Gs and the main steam trip valves. The motor operators are an operating convenience only and are used as a maintenance isolation boundary point for the S/Gs. To meet the requirements of both ISTC-5221 and ISTC-3530, the time required to drive the valve stem onto the back of the valve disk using the control room lights is measured. This is sufficient because the maximum design stem force that can be exerted by this motor operator, is only 44,900 lbf. Calculations show that the maximum force against the disc during a MSLB accident would rapidly exceed this value, reaching a value of 500,000 lbf. Also, while the dP across the check valve in the faulted line would be expected to exceed 1000 psid, a very small dP would only be required for accident forces to exceed the maximum stem force that can be exerted by the motor operator. Therefore, the testing performed without a motor trip does prove valve closure on reversal of flow. The valves are full-stroke exercised and timed closed at cold shutdowns per 1OST-1.10, "Cold Shutdown Valve Exercise Test." Bi-directional exercising in the non-safety related open direction is satisfied by normal system operation.

==References:==
ISTC-351 0, ISTC-3521 (c), ISTC-3522(b), ISTC-3530 and ISTC-5221.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 253 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  17 Valve No(s):           PCV-1MS-101A PCV-1 MS-101B PCV-1 MS-101C Category:     B        Class:      2 System:                21 - Main Steam Function:              These Steam Generator atmospheric steam dump valves must open to regulate steamline pressure in the event of loss of Condenser steam dump availability and to control Steam Generator pressure after a reactor trip. They must close to isolate a faulted Steam Generator.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally closed during plant operation . Their safety positions are open to control Steam Generator pressure after a Reactor trip and closed to isolate a faulted Steam Generator. They are also required to fail closed on a loss of control power. Full or part-stroke exercising in the open and closed directions cannot be performed during plant operation because a reduction in power would be required in order to prevent exceeding full power limitations. If they were full or part-stroke exercised in the open direction during plant operation, steam would be released into the atmosphere, thereby causing a Reactor power transient. In order to prevent this, manual isolation valves would first have to be closed prior to exercising these valves. However, the manual isolation valves could be damaged when they are re-opened against a high differential steam pressure (approximately 1000 psid AP). In addition, they are located in a potentially hazardous area (high heat and humidity) which would place an unacceptable risk to station personnel each quarter. ISTC-3521 (c) states, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-12 and fail-safe tested closed at cold shutdowns per 1OST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: Since these are low safety significant valves, their exercise frequency may be extended to refueling per OMN-12 Paragraph 5.5.1.

==References:==
ISTC-3510, ISTC-3521(c) and ISTC-3560.
OMN-12 Paragraph 5.5.1.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 254 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                   18 Valve No(s):           TV-1MS-101A TV-1MS-101B TV-1MS-101C Category:     B/C      Class:      2 System:                21 - Main Steam Function:              These Main Steamline Isolation Valves (MSIV's) must close to prevent blowdown of the Steam Generators in the case of a high energy line break (HELB) accident, and to provide outside containment isolation of Penetration Nos. 73, 74 and 75.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves and Category C check valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open during plant operation. Their safety position is closed for HELB isolation, and to provide outside containment isolation of Penetration Nos. 73, 74 and 75. They are also required to fail closed on a loss of control power. Full-stroke exercising in the closed direction cannot be performed during plant operation because this would cause a reactor trip with the possibility of a safety injection. In addition, NUREG-1482, Rev.1, Section 4.2.6, "Main Steam Isolation Valves," notes that several plants do not perform a partial stroke exercise of their MSIV's during power operations because this increases the risk of full valve closure when the unit is operating. A review of plant history indicates that several forced plant shutdowns have resulted from part-stroke testing these valves at power due to their inadvertent closure for reasons not related to valve operability. For these reasons, full and part-stroke testing is not considered practical and will not be performed. This change is consistent with Technical Specification Amendment No. 162, which deleted the TS requirement to part-stroke the valve. Per bothlSTC-3521(c) and ISTC-3522(b), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed at cold shutdowns per 1OST-21.4, 5 and 6 (Main Steam Trip Valve Full Closure Test). In addition, fail-safe testing in the closed direction, as discussed in NUREG-1482, Rev.1, Section 4.2.6 and in accordance with ISTC-3560, "Fail-Safe Valves," is also performed during cold shutdowns each time a valve is full-stroke exercised to the closed position. Bi-directional exercising in the open direction is satisfied by normal system flow

==References:==
ISTC-3510, ISTC-3521(c), ISTC-3522(b) and ISTC-3560.
NUREG-1482, Rev.1, Section 4.2.6.
BVPS-1 Technical Specification 4.7.1.5 (Amendment No. 162).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 255 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  19 Valve No(s):           MOV-1 MS-1 05 Category:     B        Class:     3 System:                21 - Main Steam Function:              This Auxiliary Feedwater Turbine Steam Isolation Valve is normally open and must remain open to supply steam to the Turbine-Driven Auxiliary Feedwater (TDAFWV) Pump. This valve must also close in response to the uncontrolled depressurization of the steam generators accident.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         This valve is normally open during power operation and remains open to allow steam to be supplied to the Turbine-Driven Auxiliary Feedwater Pump. This valve must also close in response to several postulated accidents by the EOPs. Since, this is a single isolation valve without redundancy, if it failed to re-open after a stroke test, the station would lose all cooling capability in the event of a station blackout. NUREG-1482, Rev.1, Section 3.1.1 "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage" lists as an example of valves to be specifically excluded from exercising (cycling) tests during plant operations: (1) All valves whose failure in a non-conservative position during the cycling test would cause a loss of system function. Per ISTC-3521 (c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercise and time open and closed at cold shutdowns per 1 OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(c).
NUREG-1482, Rev.1, Section 3.1.1.

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 256 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 20 Valve Asset No(s):     HYV-1 FW-100A HYV-1FW-100B HYV-1 FW-1 0OC Category:     B        Class:     2 System:                24 - Main Feedwater Function:              The Steam Generator main feedwater containment isolation valves must close in the event of a main steam line break or safety injection system actuation to prevent overfeeding the Steam Generators, for a feedwater line break down stream of the valves and to provide outside containment isolation of penetration no's. 76, 77 and 78.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency", Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open during plant operation providing feedwater flow to the Steam Generators. Their safety position is closed for Train "A" feedwater isolation to the Steam Generators, and to provide outside containment isolation of penetration no's. 76, 77 and 78. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because this would isolate or reduce feedwater flow to the Steam Generators resulting in a plant shutdown. ISTB-3521(c) states, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed during cold shutdowns per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(c).
ECP 02-0183 (1R16).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 257 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  21 Valve No(s):           FCV-1 FW-478 FCV-1 FW-488 FCV-1 FW-498 Category:     B        Class:     2 System:                24 - Main Feedwater Function:              These Steam Generator main feedwater regulating valves must close in the event of a high energy line break (HELB) or safety injection system actuation to prevent overfeeding the Steam Generators.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open during plant operation providing feedwater flow to the Steam Generators. Their safety position is closed for feedwater isolation to the Steam Generators and they are also required to fail closed on a loss of control power. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because this would isolate feedwater flow to the Steam Generators resulting in a plant shutdown. ISTC-3521(c) states. "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised and timed closed fail-safe tested closed during cold shutdown per OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510, ISTC-3521(c), and ISTC-3560.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 258 of 320 VALVE COLD SHUTDOWN JUSTIFICATION 22 Valve No(s):           TV-1BD-100A                     TV-1BD-101A1              TV-1BD-101A2 TV-1BD-100B                     TV-1BD-101B1              TV-1BD-101B2 TV-1 BD-100C                    TV-1BD-101C1              TV-1BD-101C2 Category:     B        Class:     2 System:                25 - Steam Generator Blowdown Function:              These inside and outside containment Steam Generator blowdown isolation valves must close in the event of a high energy line break (HELB) outside of containment. [TV-1 BD-1 OOA, B and C] must also close for containment isolation of Penetration Nos. 39, 40 and 41.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves are normally open in order to provide a flow path for the normal processing of blowdown from the secondary side of each Steam Generator.
Their safety positions are closed in the event of a HELB or for containment isolation of Penetration No's 39, 40 and 41. Since the three valves from each Steam Generator blowdown flow path are in series with one another, failure of one of them to re-open during stroke time testing in the closed direction would isolate the blowdown flow path. With blowdown isolated, the affected Steam Generator secondary chemistry would begin to deteriorate to a point, where if it exceeded administrative limits, the Unit would have to shutdown. NUREG-1482, Rev. 1, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage," Example (1) states that all valves whose failure in a non-conservative position during the cycling test that would result in a loss of system function would typically be excluded from testing during plant operations. Per ISTC-3521(c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdown."
Alternate Test:        Full-stroke exercised and timed closed and fail-safe tested closed during cold shutdown per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510, ISTC-3521(c) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 259 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  23 Valve No(s):           TV-1SV-100A Category:    A         Class:      2 System:                26 - Main Turbine and Condenser System Function:              The containment isolation air ejector air discharge trip valve must open to direct steam to containment if high radiation levels are present in the main condenser.
It also must close for containment isolation of Penetration No. 89.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         This valve is required to open to provide a flow path for radioactive gases from the Condenser Air Ejector effluent line into containment in the event of a S/G tube leak with subsequent contamination of the steam systems. It is also required to close for containment isolation of Penetration No. 89. If the trip valve was opened at power, the slightly subatmospheric Containment building pressure would begin to increase toward the Tech Spec 3.6.4 limit. If the trip valve could not be re-closed after stroking it open, Containment pressure would continue to rise and could result in exceeding the 1-hour Technical Specification 3.6.4 limit requiring the plant to shutdown with 6 hours. NUREG-1482, Section 3.1.1, "Deferring Valve Testing to Each Cold Shutdown or Refueling Outage" lists as an example of valves to be specifically excluded from exercising (cycling) tests during plant operations: (1) All valves whose failure in a non-conservative position during the cycling test would cause a loss of system function. Per ISTC-3521(c), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns.
Alternate Test:        Full-stroke exercised and timed open and closed and fail-safe tested closed at cold shutdowns per 1OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510, ISTC-3521(c) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.
Tech Spec 3.6.4.

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 260 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  24 Valve No(s):           1 RW-57 1 RW-58 1 RW-59 Category:     C        Class:      3 System:                30 - River Water Function:              These River Water (RW) Pump discharge check valves must open to allow cooling water from the river to flow to station loads required during an accident. They must close to prevent reverse flow through an idle RW Pump.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for CSJ:         These check valves are normally open when a River Water pump is in service.
Their safety positions are open to provide RW cooling to station loads required during an accident, and closed to prevent reverse flow through an idle RW Pump. Full-stroke exercising in the open direction is performed quarterly. In order to test these valves in the reverse direction, two of the three pumps must be cross-connected. This can only be done with pumps on the same electrical bus or during a Cold Shutdown Outage when RW is not required to be operable. Quarterly full-stroke exercising in the closed direction may not be possible if one RW Pump is out of service for maintenance. ISTC-3522(b) states, "If exercising is not practicable during operation at power, it shall be performed during cold shutdowns."
Alternate Test:        Full-stroke exercised closed quarterly per 1OST-30.6A or 6B (Reactor Plant River Water Pump 1C Tests). If not able to be tested quarterly, the valve(s) will be full-stroke exercised closed when the idle RW Pump is returned to service, or at least during cold shutdowns per 1OST-30.6A and B (Reactor Plant River Water Pump 1C Tests). Check valves are also full-stroke exercised open quarterly per 1OST-30.2, 3 and 6A (Reactor Plant River Water Pump Tests).

==References:==
ISTC-3510 and ISTC-3522(b).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 261 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 25 Valve No(s):           MOV-1 RW-102C1 MOV-1RW-102C2 Category:     B        Class:     3 System:                30 - River Water Function:              These discharge isolation valves for the 1C River Water (RW) Pump must open to permit the river water to be supplied to the station loads required during an accident.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for CSJ:         These valves open to align the 1C River Water pump to the appropriate RW header. Their safety positions are open to provide RW cooling to station loads required during an accident. In order to test these valves, two of the three pumps must be cross-connected. This can only be done with pumps on the same electrical bus or during a cold shutdown outage when RW is not required to be operable. Quarterly full-stroke testing may not be possible if one RW Pump is out of service for maintenance. ISTC-3521 (c) states, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns".
Alternate Test:        Full-stroke exercised quarterly in accordance with ASME OM Code Case OMN-1 per 1 OST-30.6A or 6B (Reactor Plant River Water Pump 1C Tests). If not able to be tested quarterly, the valve(s) will be full-stroke exercised and timed open when the idle RW Pump is returned to service, or at least during cold shutdowns per 1OST-30.6A and B (Reactor Plant River Water Pump 1C Test).

==References:==
ISTC-3510 and ISTC-3521 (c).
OMN-1 Paragraphs 3.6.1 and 3.6.3(b).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 262 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 26 Valve No(s):           1FP-800 1 FP-804 1 FP-827 Category:     A/C      Class:     2 System:                33 - Fire Protection Function:              These fire protection inside containment check valves from the deluge system to the RHR area, to the cable penetration area and to the containment hose reels must close to provide containment isolation of Penetration Nos. 13, 31 and 32.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for CSJ:         These check valves are normally closed and would only be opened in the event of a fire in containment. Their safety position is closed for containment isolation of Penetration Nos. 13, 31 and 32. Full-stroke exercising in the closed direction can only be verified by cycling the mechanical weight-loaded swing arms of each check valve open and then closed. Because these check valves are located inside the slightly subatmospheric containment, they are not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. Per ISTC-3522(b), "Ifexercising is not practicable during operation at power, it shall be performed during cold shutdowns.
Alternate Test:         Full-stroke exercised open using a manual mechanical exerciser attached to their mechanical weight loaded swing arms in accordance with ISTC-5221(b) and the guidelines provided in NUREG-1482, Rev.1, Section 4.1.7, and closed by observation of their mechanical weight loaded swing arms during cold shutdown per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3522(b).
NUREG-1482, Rev.1, Section 4.1.7.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 263 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                 27 Valve No(s):           1VS-D-5-3A 1VS-D-5-3B 1VS-D-5-5A 1VS-D-5-5B Category:     A        Class:     2 System:                44C - Area Ventilation - Containment Function:              These containment purge and exhaust inside and outside containment isolation dampers must close to provide containment isolation of Penetration Nos. 90 and 91.
Test Requirement:      Per ISTB-351 0, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for CSJ:         These motor-operated dampers (MOD's) are normally locked shut during plant operation and opened during refueling operations. Their safety position is closed for containment isolation of Penetration Nos. 90 and 91. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because the Containment Penetration Table requires the MOD's to be locked shut during plant operation. ISTC-3521(c) states, "Ifexercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdown per lOST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: Since [1VS-D-5-3A and 3B] are low safety significant MOD's, their exercise frequency may be extended to refueling per OMN-1 Paragraph 3.6.1.

==References:==
ISTC-3510 and ISTC-3521 (c).
LRM Table 3.6.1-1.
OMN-1 Paragraph 3.6.1 and 3.6.3(b).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 264 of 320 VALVE COLD SHUTDOWN JUSTIFICATION                  28 Valve No(s):           1CH-84 1CH-136 1CH-141 Category:     C        Class:     3 System:                7 - Chemical and Volume Control System Function:              These emergency and alternate emergency boration line check valves must open to provide a flow path for 4% boric acid solution from the Boric Acid Tanks via the Boric Acid Transfer Pumps to the suction of the Charging Pumps.
Test Requirement:      ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for CSJ:         These check valves are normally closed during plant operation. Their safety position is open for emergency and alternate emergency boration. They can only be full-stroke exercised in the open direction by initiating the maximum required accident condition flow in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3. However, testing in this manner at power would result in concentrated boric acid solution being injected in the reactor coolant system (RCS). This would cause an undesired negative reactivity addition resulting in a reduction in plant power. ISTC-3522(b) states, "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns."
Alternate Test:        Full-stroke exercised open during cold shutdowns per 1OST-I 10 (Cold Shutdown Valve Exercise Test).
NOTE: Bi-directional exercising in the non-safety related closed direction will be satisfied by a leak test of [1 CH-84] per 1OST-7.TBD (TBD) and by a leak test of [1CH-136 and 141] per 1BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.

==References:==
ISTC-3510, ISTC-3522(b), ISTC-5221 and ISCT-5222.
NUREG-1482, Rev.1, Sections 3.1.1 and 4.1.3.

Beaver Valley Power Station                     Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                           Page 265 of 320 SECTION VIII: VALVE REFUELING OUTAGE JUSTIFICATIONS (VROJ)
AND INDEX VROJ         SYSTEM NO.      COMPONENT(S)
VROJ1               6        1 RC-68 VROJ2               6        1 RC-72 VROJ3               7        1CH-22, 1CH-23, 1CH-24 VROJ4               7        1CH-31 VROJ5              N/A       N/A (NOT USED AS THIS TIME)
VROJ6               7        1CH-97 VROJ7               7        MOV-1 CH-1 15C, MOV-1 CH-1 15E VROJ8               7        ICH-181, 1CH-182, 1CH-183 VROJ9               7        TV-i CH-204, MOV-1CH-289 VROJ10              7        MOV-1CH-308A, MOV-1CH-308B, MOV-1CH-308C VROJ11              7        1CH-369 VROJ12              7        MOV-1CH-378, MOV-1CH-381 VROJ 13             7        MOV-1CH-310, LCV-1CH-460A, LCV-1CH-460B VROJ14             11        1S1-1, 1SI-2 VROJ15             11        1SI-5 VROJ16             11        1SI-6, 1SI-7 VROJ17             11        1SI-10, 1S1-11, 1SI-12 VROJ18             11        1SI-13, 1SI-14 VROJ19             11        1SI-15, 1SI-16, 1SI-17 VROJ20             11        1SI-20, 1SI-21, 1SI-22 VROJ21             11        1SI-23, 1SI-24, 1SI-25 VROJ22             11        1SI-27 VROJ23             11        1SI-48, 1SI-49, 1SI-50, 1SI-51, 1SI-52, 1SI-53 VROJ24             11        1SI-94 VROJ25             11        1SI-95 VROJ26             11        1SI-100, 1SI-101, 1SI-102 VROJ27             11        1S1-1 15, 1SI-116 VROJ28             11        MOV-1SI-836 VROJ29             11        MOV-1SI-867A, MOV-l SI-867B VROJ30             11        1NG-518, 1NG-519, 1 NG-520 VROJ31             13        1QS-3, 1QS-4, iRS-100, 1RS-101 VROJ32             13        1RS-158, 1RS-160

Beaver Valley Power Station                    Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                Page 266 of 320 VROJ         SYSTEM NO.      COMPONENT(S)
VROJ33             15        TV-1 CC-1 03A, TV-1 CC-1 03A1, TV-1 CC-1 03B, TV-1 CC-1 03B1, TV-iCC-103C, TV-1CC-103C1, TV-1CC-105D1, TV-1CC-105D2, TV-1CC-105E1, TV-1CC-105E2, TV-1CC-107D1, TV-1CC-105D2, TV-1 CC-1 07E1, TV-1 CC-1 07E2 VROJ34             15        TV-1 CC-1 07A, TV-1 CC-1 07B, TV-1 CC-1 07C VROJ35             15        1CCR-289, 1CCR-290, 1CCR-291 VROJ36          21 & 24      1FW-33, 1MS-18, 1MS-19, lMS-20 VROJ37             21        1MS-80, 1MS-81, iMS-82 VROJ38             24        1FW-33, 1FW-34, 1FW-35, 1FW-42, 1FW-43, 1FW-44, 1FW-622, 1FW-623, 1FW-624, 1FW-625, 1FW-626, 1FW-627 VROJ39             24        1FW-50, 1FW-51, 1FW-52, 1FW-68, 1FW-69, 1FW-70 VROJ40             N/A       N/A (NOT USED AS THIS TIME)
VROJ41             24        1FW-156A, 1FW-156B, 1FW-156C VROJ42             26        1AS-278 VROJ43             30        1RW-1 06, 1RW-107 VROJ44             30        1WT-383, 1WT-388 VROJ45             34        1 IA-91 VROJ46             34        1IA-116, 1IA-117, 1IA-378

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 267 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  I Valve No(s):           1RC-68 Category:     A/C      Class:     2 System:                6 - Reactor Coolant Function:              This inside containment isolation check valve on the N2 makeup line to the Pressurizer Relief Tank must close for containment isolation of Penetration No. 49.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency", Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed and must remain closed to fulfill its safety function of containment isolation of Penetration No. 49. It is only opened during nitrogen makeup to the PRT. Because this check valve is located inside the slightly subatmospheric containment, it is not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. Due to the physical location of this valve, the relative pressures of the N2 header and the lack of instrumentation, the only means for verifying closure is during the 10CFR50, Appendix J, Option B leak rate test performed at refuelings. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means are available. PerISTC-3522(c), "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Valve closure is verified by a leak test during refueling outages per 1BVT 1.47.5 (Type-C Leak Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.
NOTE: Bi-directional exercising in the non-safety related open direction will be satisfied by demonstrating the ability to provide nitrogen makeup to the PRT during station shutdown per 1OM-52.4.R.2.F.

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1 Section 4.1.6.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 268 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 2 Valve No(s):           1 RC-72 Category:     A/C      Class:     2 System:                6 - Reactor Coolant Function:              This inside containment isolation check valve on the primary grade water supply line to the Pressurizer Relief Tank must close for containment isolation of Penetration No. 45.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed and must remain closed to fulfill its safety function of containment isolation of Penetration No. 45. It is only opened during makeup to or while depressurizing the PRT. Because this check valve is located inside the slightly subatmospheric containment, it is not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. Due to the physical location of this valve, the only means for verifying closure is during the 10CFR50, Appendix J, Option B leak rate test performed at refuelings. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means are available. PerISTC-3522(c), "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Valve closure is verified by a leak test during refueling outages per 1BVT 1.47.5 (Type-C Leak Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.
NOTE: Bi-directional exercising in the non-safety related open direction will be satisfied by demonstrating the ability to provide primary grade water makeup to the PRT during station shutdown per 1OM-52.4.R.2.F.

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1, Section 4.1.6.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 269 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  3 Valve No(s):           1CH-22 1CH-23 1CH-24 Category:     C        Class:     2 System:                7 - Chemical and Volume Control Function:              These Charging Pump discharge check valves must open to provide a flow path from the Charging Pumps to the reactor coolant system (RCS) loops for a high head safety injection (HHSI). They must close to prevent reverse flow through an idle Charging Pump.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally open when their associated charging pump is in service. Their safety positions are open to allow charging/HHSI flow and closed to prevent reverse flow through an idle charging pump. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow, in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3 is not possible because the charging pumps will not develop the required flow.
Full-flow exercising in the open direction during cold shutdown cannot be performed because this could result in low-temperature over-pressurization of the RCS. ISTC-3522(c) states: "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages".
Exercising the non-running Charging pump discharge check valves in the closed direction is normally done during the quarterly pump test by virtue of pump delta-P being greater than the system minimum operating point (MOP) curve for the operating pump. The quarterly pump test, however, can only be performed at lower flow rates on a flat portion of the pump curve. Therefore, a large change in flow is required to cause the delta-P to drop below the MOP curve. This quarterly test provides assurance that the check valves are closed, preventing gross leakage. The substantial flow condition test, performed at refueling outages, verifies the adjacent pumps' check valves are closed and capable of fulfilling their function in the closed direction by ensuring that the performance of the operating pump exceeds minimum system requirements. Therefore, in order to ensure acceptable check valve closure, a functional test at substantial flow conditions will be performed in conjunction with the comprehensive pump test performed at refueling outages.
Alternate Test:        Full-stroke exercised open and closed at refueling outages per lOST-i 1 .14B (HHSI Full Flow Test). Also exercised closed quarterly per 1OST-7.4, 5 & 6 (Centrifugal Charging Pump Test).

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.
CR 01-0807 and CA 01-0807-02.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 270 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 4 Valve No(s):           1CH-31 Category:     A/C      Class:     2 System:                7 - Chemical and Volume Control Function:              This charging header inside containment isolation check valve must close to provide containment isolation of Penetration No. 15.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The safety function of this check valve is to close to provide containment isolation of Penetration No. 15. During plant operation, normal charging flow is present through this check valve and a reverse direction test cannot be performed. There is no installed instrumentation to monitor upstream pressure and the only method for testing this valve is by leak test. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Per ISTC-3522(c), "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Check valve closure is verified by a leak test during refueling outages per 1 BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test). Check valve is also full-stroke exercised open quarterly per 1OST-47.3K (Containment Isolation and ASME OM Code Test - Work Week 7)

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                        Page 271 of 320 VALVE REFUELING OUTAGE JUSTIFICATION            5  (NOT USED AT THIS TIME)
Valve No(s):
Category:     -        Class:
System:
Function:
Test Requirement:
Basis for ROJ:
Alternate Test:

==References:==

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 272 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   6 Valve No(s):           1 CH-97 Category:     C        Class:      2 System:                7-Chemical and Volume Control Function:              This Chemical Mixing Tank outlet check valve is required to close during an upstream non-Q class pipe break in order to prevent loss of Refueling Water Storage Tank (RWST) inventory that would otherwise be available to supply the Charging Pumps during a large break LOCA event.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency", Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally open while the Zinc Addition Skid is in service during plant operations. Its safety position is closed for isolation of upstream non-Q class piping. The Zinc Addition Skid is normally in service during plant operations and would have to be shutdown in order to test this check valve quarterly. In addition, full-stroke exercising in the closed direction can only be performed by leak testing because no other practical means is available to verify check valve closure. This involves the installation and removal of special test equipment in order to perform the leakage testing. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outages for Check Valves Verified Closed by Leak Testing", it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each refueling outage, if no other practical means is available. ISTC-3522(c) states, "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages".
Alternate Test:        Full-stroke exercised closed by leakage testing during refueling outages per 1OST-1 1.14B (HHSI Full-Flow Test).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied during normal system operation of the Zinc Addition System per ISTC-3550.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-3550.
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 273 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   7 Valve No(s):           MOV-1CH-115C MOV-1CH-115E Category:     B        Class:     2 System:                7 - Chemical and Volume Control Function:              These Volume Control Tank (VCT) outlet isolation valves must close on a safety injection signal to ensure the suction of the charging/high head safety injection (HHSI) system is switched from the VCT to the Refueling Water Storage Tank (RWST).
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open when the charging system is in service. Their safety position is closed to ensure the suction of the Charging Pumps is switched from the VCT to the RWST following a safety injection signal. Full or part-stoke exercising in the closed direction cannot be performed during plant operation without isolating the VCT from the Charging Pumps or potentially damaging the Charging Pumps due to inadequate suction flow. This would also result in loss of or limited pressurizer level control, normal reactor coolant system makeup, and loss of or limited seal injection flow to the Reactor Coolant Pump (RCP) seals resulting in seal damage. In addition, full or part-stroke exercising in the closed direction may not be possible during cold shutdown if the charging system is in service to support operation of a RCP.
Shutting down the charging system during RCP operation while in cold shutdown would secure seal injection water to the RCP seals, creating a challenge to long-term seal life. In order to stroke these valves, the charging system and RCP's would have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCP's need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCP's are secured and during refueling outages, but not more often than once every 92 days.
ISTC-3521(e) states, "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the RCP's are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521 (e).
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 274 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 8 Valve No(s):           1CH-181 1CH-182 1CH-183 Category:     A/C      Class:     2 System:                7 - Chemical and Volume Control Function:              These reactor coolant seal injection inside containment isolation check valves must close to provide containment isolation of Penetration Nos. 35, 36 and 37.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally open to supply the Reactor Coolant Pump (RCP) seals from the charging pumps during power operation, but are required to close to provide containment isolation of Penetration Nos. 35, 36 and 37. Closing the valves during power operation, or anytime the system is pressurized to greater than 100 psig, would secure seal injection water to the reactor coolant pump seals, resulting in seal damage. In addition, valve closure can only be checked by leak testing since they have no position indication or weighted arms. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Therefore, quarterly and cold shutdown exercising is not practical. Per ISTC-3522(c), "Ifexercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Valve closure is verified by a leak test during refueling outages per 1 BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test).
NOTE: Bi-directional exercising to the non-safety related open position is satisfied by normal system operation of a RCP per ISTC-3550.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-3550.
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 275 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   9 Valve No(s):           TV-1CH-204 MOV-1 CH-289 Category:      A       Class:       2 System:                7 - Chemical and Volume Control Function:              This Non-Regen Heat Exchanger inlet and letdown isolation outside containment isolation valve must close to secure letdown flow and limit inventory loss from the reactor coolant system (RCS) on receipt of a CIA.
This normal charging header makeup and outside containment isolation valve must close on a safety injection signal to ensure that flow from the high head safety injection (HHSI) system is switched from normal charging to the safety injection system. They must also close to provide containment isolation of Penetration Nos. 15 and 28.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open when the charging system is in service to provide a flow path for letdown flow from the RCS and normal charging to the RCS. Their safety positions are closed for containment isolation of Penetration Nos. 15 and 28, and also for letdown and normal charging isolation. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because this will result in a thermal shock to the Regenerative Heat Exchanger and associated component piping resulting in an increased probability of system and component failures. In addition, failure of this valve in the closed position could lead to a loss of pressurizer level control and require a plant shutdown. In addition, full or part-stroke exercising in the closed direction may not be possible during cold shutdown if the charging system is in service to support operation of a Reactor Coolant Pump (RCP). A failure of either valve in the closed position could require shutting down the charging system and unnecessary shutdown of a RCP.
Loss of normal charging or letdown flow results in minimum Charging Pumps flow which is restricted to less than 1 hour by P&L's. Shutting down the charging system during RCP operation while in cold shutdown would secure seal injection water to the RCP seals, resulting in seal damage. In order to stroke this valve, the charging system and RCP's would both have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCP's need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCP's are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521 (e) states, "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                    Page 276 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 9 Alternate Test:        [TV-1 CH-204] is full-stroke exercised and timed closed and fail-safe tested closed during cold shutdowns when the charging system and the RCP's are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).
[MOV-1CH-289] is full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the RCP's are secured, or a least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510, ISTC-3521(e) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 277 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  10 Valve No(s):           MOV-1CH-308A MOV-1CH-308B MOV-1CH-308C Category:     A        Class:     2 System:                7 - Chemical and Volume Control Function:              These Reactor Coolant Pump (RCP) seal injection outside containment isolation valves must close for containment isolation of Penetration Nos. 35, 36 and 37.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency, "Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open to provide seal water to the RCPs during power operation, but are required to close to provide containment isolation of Penetration Nos. 35, 36 and 37. Full-stroke exercising in the closed direction cannot be performed during plant operation because this would secure seal injection water to the RCP seals, resulting in seal damage. In addition, failure of these valves in the closed position will result in a plant shutdown. In addition, full-stroke exercising in the closed direction may not be possible during cold shutdown if the charging system is in service to support operation of a RCP. Shutting down the charging system during RCP operation while in cold shutdown would secure seal injection water to the RCP seals, resulting in seal damage. In order to stroke these valves, the charging system and RCP's would both have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCP's need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCP's are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521(e) states, "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the reactor coolant pumps are secured, or at least during refueling outages per 1OST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: Since these are low safety significant valves, their exercise frequency may be extended to refueling per OMN-1 Paragraph 3.6.1.

==References:==
ISTC-3510 and ISTC-3521 (e).
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraphs 3.6.1 and 3.6.3(c).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 278 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   11 Valve No(s):           1 CH-369 Category:     A/C      Class:     2 System:                7 - Chemical and Volume Control Function:              This containment Penetration No. 19 pressure relief check around [MOV-1CH-378] opens to allow excess pressure trapped in the containment penetration due to thermal expansion to be equalized with the pressure inside the seal return line, inside containment. In the reverse direction, this valve must close for containment isolation of Penetration No. 19.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed when the charging system is in service returning seal injection flow from the Reactor Coolant Pumps (RCP's). Its safety position is closed for containment isolation of Penetration No. 19, however, it will momentarily open if required to relieve pressure trapped in the containment penetration due to thermal expansion. It is located inside the slightly subatmospheric containment building on the RCP seal water return line. During power operation and any time the RCS is pressurized to greater than 100 psig, this line is in service with the RCP seal water. Valve exercising can only be checked by leak testing since this valve does not have position indication or a weighted arm. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. PerISTC-3522(c), "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Check valve is verified to open by unseating the valve prior to leak testing, while check valve closure is verified by a leak test during refueling outages per 1BVT 1.47.5 (Type-C Leak Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5222.
NUREG-1482, Rev.1, Section 4.1.6.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 279 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 12 Valve No(s):           MOV-1 CH-378 MOV-1 CH-381 Category:     A        Class:     2 System:                7 - Chemical and Volume Control Function:              These Reactor Coolant Pump (RCP) seal water return line inside and outside containment isolation valves must close for containment isolation of Penetration No. 19.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open when the charging system is in service to provide seal water return from the RCP's. Their safety position is closed for containment isolation of Penetration No. 19. Full-stroke exercising in the closed direction cannot be performed during plant operation because this would secure seal water return from the RCP's, resulting in seal damage.
Failure of these valves in the closed position will result in a plant shutdown. In addition, full-stroke exercising in the closed direction may not be possible during cold shutdown ifthe charging system is in service to support operation of a RCP. Shutting down the charging system during RCP operation while in cold shutdown would secure seal water return from the RCP's, resulting in seal damage. In order to stroke these valves, the charging system and RCP's would both have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the reactor coolant pump (RCPs) need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCPs are secured and at refueling outages, but not more often than once every 92 days. PerISTC-3521(e), "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the reactor coolant pumps are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(e).
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 280 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  13 Valve No(s):           MOV-1CH-310 LCV-1CH-460A LCV-1CH-460B Category:     B        Class:     i System:                7 - Chemical and Volume Control Function:              This Regenerative Heat Exchanger outlet isolation and normal charging system makeup valve must close on a safety injection signal to ensure that flow from the High Head Safety Injection (HHSI) system is switched from normal charging to the safety injection system. These Regenerative Heat Exchanger inlet letdown isolation valves must close to secure letdown flow and limit inventory loss from the reactor coolant system (RCS) on receipt of a low level signal derived from the pressurizer level control system.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open when the charging system is in service to provide a flow path for letdown flow from the RCS and normal charging to the RCS. Their safety position is closed for isolation of normal charging and for letdown isolation. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because this will result in a thermal shock to the Regenerative Heat Exchanger and associated component piping resulting in an increased probability of system and component failures. In addition, failure of these valves in the closed position could lead to a loss of pressurizer level control and require a plant shutdown. In addition, full or part-stroke exercising in the closed direction may not be possible during cold shutdown ifthe charging system is in service to support operation of a Reactor Coolant Pump (RCP). A failure of either valve in the closed position could require shutting down the charging system and unnecessary shutdown of a RCP. Loss of normal charging or letdown flow results in minimum Charging Pump, flow which is restricted to less than 1 hour by P&L's.
Shutting down the charging system during RCP operation while in cold shutdown would secure seal injection water to the RCP seals, resulting in seal damage. In order to stroke these valves, the charging system and RCP's would both have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing,"
the RCP's need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCP's are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521(e) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                   Page 281 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 13 Alternate Test:        [LCV-1 CH-460A and B] are full-stroke exercised and timed closed and fail-safe tested closed during cold shutdowns when the charging system and the RCP's are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).
[MOV-1CH-310] is full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the RCP's are secured, or at least during refueling outages per 1OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521 (e) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                         Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 282 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   14 Valve No(s):            1S1-1 1SI-2 Category:     C        Class:      2 System:                 11 - Safety Injection Function:              These LHSI pump suction check valves from the containment sump must open to allow the LHSI pumps to take suction off the containment sump.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during power operation but must open to fulfill their safety function for long-term core cooling. Full stroke exercising these valves with flow would involve simulating an actual safety injection long-term cooling event by taking suction from the containment sump and delivering contaminated/dirty water to RWST or RCS. BVPS-1 considers this activity impractical. Per ISTC-5221 (c), If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement.
Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4.
Alternate Test:        Maintenance is to disassemble and inspect one valve in the open (safety) direction and in the closed (bi-directional) direction (i.e., full-stroked) in accordance with the sample frequency requirements of ISTC-5221(c) per 1/2CMP-75-ALOYCO CHECK-1 M at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then the remaining valve in the group shall be disassembled and inspected during the same outage. Since a part-stroke exercise of these check valves after valve reassembly is not possible it will not be performed as permitted by ISTC-5221(c)(4).

==References:==
ISTC-3510 and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.4.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 283 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 15 Valve No(s):           1SI-5 Category:     C        Class:      2 System:                11 - Safety Injection Function:              This Low Head Safety Injection (LHSI) Pump LHSI suction check valve from the Refueling Water Storage Tank (RWST) must open to allow flow from the RWST to the LHSI pumps.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The function of this normally closed check valve is to open to permit flow from the RWST to the LHSI pump suctions. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. Cold shutdown full-stroke exercising is also not practicable because testing would require full flow injection to the RCS where there is insufficient volume to receive the additional inventory. Per ISTC-3522(c), "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroked exercised open at refueling outages per 1OST-11.14A (LHSI Full Flow Test).
NOTE: Bi-directional exercising in the non-safety related closed direction will be satisfied by performing a leakage test during per 1BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 284 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  16 Valve No(s):           1SI-6 1SI-7 Category:     C        Class:     2 System:                11 - Safety Injection Function:              These Low Head Safety Injection (LHSI) Pump discharge check valves must open to provide a flow path from the LHSI Pumps to the reactor coolant system (RCS) loops for LHSI. They must close to prevent reverse flow through an idle LHSI Pump back to the Refueling Water Storage Tank (RWST).
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation. Their safety positions are open for LHSI and closed to prevent reverse flow through an idle LHSI Pump. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. During cold shutdowns, full stroke exercising in the open direction cannot be performed because flow testing would require injection to the RCS where there is not sufficient volume to receive the additional inventory. ISTC-3522(c) states, "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed quarterly per 1OST-11.1 and 2 (Safety Injection Pump Tests). Full-stroked exercised open at refueling outages per lOST-11.14A (LHSI Full Flow Test).

==References:==
ISTC-3510, ISTC-3522(c), and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 285 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  17 Valve No(s):           1S1-10 1S1-11 IS1-12 Category:     AIC      Class:     1 System:                11 - Safety Injection Function:              These Low Head Safety Injection (LHSI) cold leg branch line check valves must open to allow LHSI discharge to the Reactor Coolant System (RCS) cold legs and must close to prevent high pressure RCS and High Head Safety Injection (HHSI) from entering the low pressure safety injection piping.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation and are pressure isolation valves (PIV's) that prevent reverse flow from the higher pressure RCS and High Head Safety Injection (HHSI) systems to the LHSI low pressure system. They are required to open in the event of a safety injection.
During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3. During cold shutdowns, full stroke exercising in the open direction cannot be performed because flow testing would require injection to the RCS where there is not sufficient volume to receive the additional inventory. In the reverse direction, these valves do not have installed instrumentation, or weighted arms. Therefore, the only way to verify closure is with a leak test. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Per ISTC-3522(c), "Ifexercising is not practicable during operation at power or cold shutdowns, itshall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open per lOST-11.14A (LHSI Full Flow Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program. Full-stroke exercised closed by leakage testing during refueling outages per lOST-11.16 (Leakage Testing RCS Pressure Isolation Valves).

==References:==
ISTC-3510, ISTC-3522(c), and ISTC-5221.
NUREG-1482, Rev.1, Sections 4.1.6 and 4.1.3.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 286 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 18 Valve No(s):           1S1-13 1SI-14 Category:     A/C      Class:     1 System:                11 - Safety Injection Function:              These low head safety injection (LHSI) inside containment isolation check valves must also close to provide containment isolation of Penetration Nos. 60 and 62. They must open for LHSI hot leg recirculation.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed to provide Reactor Coolant System (RCS) pressure boundary isolation as a Pressure Isolation Valve (PIV). Their safety position is closed for containment isolation of Penetration Nos. 60 and 62 and open for LHSI hot leg recirculation. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221(a) and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. During cold shutdowns, full-stroke exercising in the open direction cannot be performed because flow testing would require injection to the RCS where there is not sufficient volume to receive the additional inventory. In the reverse direction, these valves do not have installed instrumentation, or weighted arms. Therefore, the only way to verify closure is with a leak test. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open during refueling outages per 1OST-11.14A (LHSI Full Flow Test). Full-stroke exercised closed by leakage testing during refueling outages per 1 BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test).

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221(a).
NUREG-1482, Rev.1, Sections 4.1.3 and 4.1.6.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 287 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  19 Valve No(s):           1SI-15 1S1-16 1S1-17 Category:     A/C      Class:     1 System:                11 - Safety Injection Function:              These low head safety injection (LHSI) branchline check valves must open to provide a flow path from the LHSI Pumps to the Reactor Coolant System (RCS) hot legs during a safety injection.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation and they are Pressure Isolation Valve (PIVs) that isolate the LHSI piping from the higher pressure RCS. Their safety position is open for LHSI. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221(a) and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. During cold shutdowns, full-stroke exercising in the open direction cannot be performed because flow testing would require injection to the RCS where there is not sufficient volume to receive the additional inventory. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open per lOST-i 1.14A (LHSI Full Flow Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program. Full-stroke exercised closed by leakage testing during refueling outages per 1OST-1 1.19 (Leakage Testing Hot Leg RCS Pressure Isolation Valves).

==References:==
ISTC-351 0, ISTC-3522(c) and ISTC-5221 (a).
NUREG-1482, Rev.1, Section 4.1.3.
ASME OM Code, Appendix II(Check Valve Condition Monitoring Program).

Beaver Valley Power Station                      Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 288 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  20 Valve No(s):           1SI-20 1SI-21 1SI-22 Category:     A/C      Class:      1 System:                 11 - Safety Injection Function:              These low head safety injection (LHSI) branchline check valves must open to provide a flow path from the LHSI Pumps to the Reactor Coolant System (RCS) hot legs during a safety injection. High head safety injection to the RCS hot legs is no longer required in an accident per ECP 05-0280, therefore, their high head safety injection function is no longer required.
Test Requirement:      ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation. Their safety position is open for LHSI. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221(a) and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. In addition, full-stroke exercising in the open direction cannot be performed using the HHSI Pumps because they will not develop the required flow. During cold shutdowns, full-stroke exercising in the open direction cannot be performed using the LHSI Pumps because this would require injection to the RCS where there is not sufficient volume to receive the additional inventory. ISTC-3522(c)) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open per lOST-1 1.14A (LHSI Full Flow Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program. Full-stroke exercised closed by leakage testing during refueling outages per lOST-11.19 (Leakage Testing Hot Leg RCS Pressure Isolation Valves).

==References:==
ISTC-351 0, ISTC-3522(c) and ISTC-5221 (a).
NUREG-1482, Rev.1, Section 4.1.3.
ECP 05-0280.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 289 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 21 Valve No(s):            IS 1-23 1S 1-24 1SI-25 Category:    A/C       Class:      1 System:                 11 - Safety Injection Function:              These low head / high head safety injection (LHSI / HHSI) cold leg branch line header check valves must open to provide a flow path from either the LHSI Pumps or HHSI Pumps to the reactor coolant system (RCS) cold legs during a safety injection. The valves also serve as pressure isolation valves (PIVs).
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation. Their safety position is open for LHSI and HHSI. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, rev.1, Section 4.1.3, cannot be performed because the LHSI Pumps will not develop enough head to overcome RCS pressure. In addition, full-stroke exercising in the open direction cannot be performed using the HHSI Pumps because they will not develop the required flow. During cold shutdowns, full stroke exercising in the open direction using the HHSI Pumps cannot be performed because this could result in low-temperature overpressurization of the RCS. Full stroke exercising in the open direction cannot be performed during cold shutdowns using the LHSI Pumps because this would require injection to the RCS where there is not sufficient volume to receive the additional inventory. ISTC-3522(c) states, "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open per lOST- 1.14A (LHSI Full Flow Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM)
Program. Full-stroke exercised closed by leakage testing during refueling outages per lOST-1 1.16 (Leakage Testing RCS Pressure Isolation Valves).

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.
ASME OM Code, Appendix II(Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 290 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  22 Valve No(s):           1SI-27 Category:     A/C      Class:      2 System:                11 - Safety Injection Function:              This High Head Safety Injection (HHSI) Pump suction check valve from the Refueling Water Storage Tank (RWST) must open to provide a flow path from the RWST to the suction of the HHSI Pumps during an accident. It must close when the RWST is empty to prevent reverse flow of containment sump water from entering the RWST.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed during plant operation. Its safety position is open for HHSI and closed during transfer to recirc to prevent reverse flow to the RWST. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the Charging Pumps will not develop the required flow. During cold shutdowns, full flow exercising in the open direction cannot be performed because this could result in low-temperature overpressurization of the RCS. Full stroke exercising in the closed direction can only be performed by leak testing because no other practical means is available to verify check valve closure. This involves the installation and removal of special test equipment in order to perform the leakage testing. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each refueling outage, if no other practical means is available. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open during refueling outages per lOST-1 1.14B (HHSI Full Flow Test). Full-stroke exercised closed by leakage testing during refueling outages per 1 BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test).

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1, Sections 4.1.6 and 4.1.3.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 291 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  23 Valve No(s):           1SI-48                           1SI-51 1SI-49                           1S 1-52 1S 1-50                          1SI-53 Category:     A/C      Class:       I System:                11 - Safety Injection Function:              These Safety Injection (SI) Accumulator Series Discharge Check Valves are required to open upon depressurization of the Reactor Coolant System (RCS) to allow the water from the SI Accumulator to be injected into the RCS during a loss of coolant accident (LOCA). [1SI-52 and 53] must also open to provide a flow path for the Residual Heat Removal (RHR) System when it is placed into service for cool down of the plant to cold shutdown conditions. The valves also serve as pressure isolation valves (PIVs)
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed as pressure isolation valves (PIV's) during plant operation in order to isolate lower pressure Safety Injection (SI)
Accumulators from the high pressure RCS. In the reverse direction, these valves do not have installed instrumentation, or weighted arms. Therefore, the only way to verify closure is with a leak test. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Their safety position in the open direction is for passive low-pressure injection of the SI Accumulators into the RCS cold legs during a LOCA. An additional safety position for [1SI-52 and 53] is open to support RHR system operation during cool down of the plant to cold shutdown conditions. Full stroke exercising in the open direction cannot be performed during plant operation because the RCS is at a higher pressure than the SI Accumulators. Full-stroke exercising for all six check valves in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed during cold shutdowns because of a lack of installed instrumentation to measure flow, and due to a possibility of developing low temperature overpressurization of the RCS. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by leak test during refueling outages per I OST-11.4A and 4B (Accumulator Check Valve Leak Tests). Exercised open by measuring a level change over time as the SI Accumulators are dumped per 1OST-11 .TBD (TBD) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.

==References:==
ISTC-3510, ISTC-3522(c), ISTC-5221 and ISTC-5222.
NUREG-1482, Rev.1, Sections 4.1.3 and 4.1.6.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 292 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   24 Valve No(s):           1SI-94 Category:     A/C      Class:      1 System:                11 - Safety Injection Function:              This Boron Injection Tank (BIT) injection line inside containment isolation check valve to the cold legs must open to permit High Head Safety Injection (HHSI) flow to the Reactor Coolant System (RCS). It must close for containment isolation Penetration No. 113.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed. Its safety position is closed for containment isolation of Penetration No. 113 and open for HHSI cold leg recirculation. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the Charging Pumps will not develop the required flow. In addition, they also cannot be full-stroke exercised with flow in the open direction during plant operation due to the potential for thermal shock of the injection nozzles from a cold water injection. In addition, full-stroke testing at cold shutdowns also cannot be performed since this could result in a low temperature overpressurization of the RCS. Valve exercising in the closed direction can only be verified by a leak test since this valve does not have position indication or a weighted arm.
Per NUREG-1482, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Per ISTC-3522(c), "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open during refueling outages per 1OST-11.14B (HHSI Full Flow Test). Full-stroke exercised closed by leak test during refueling outages per 1BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test).

==References:==
ISTC-3510, ISTC-3522(c), and ISTC-5221.
NUREG-1482, Rev.1, Sections 4.1.6 and 4.1.3.
Tech. Spec. 3.5.4.1.2.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 293 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   25 Valve No(s):           1SI-95 Category:     A/C      Class:      1 System:                11 - Safety Injection Function:              This High Head Safety Injection (HHSI) cold leg inside containment isolation check valve must open to permit HHSI flow to the Reactor Coolant System (RCS). It must close for containment isolation of Penetration No. 96.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally closed. Its safety position is closed for containment isolation of Penetration No 96, and open for HHSI hot leg and cold leg recirculation. During plant operation when the reactor coolant system (RCS) is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the Charging Pumps will not develop the required flow. In addition, they also cannot be full stroke exercised with flow in the open direction during plant operation due to the potential for thermal shock on the injection nozzles from a cold water injection. During cold shutdowns full-flow testing could result in a low temperature overpressurization of the RCS.
In the reverse direction, this valve does not have installed instrumentation, or weighted arms. Therefore, the only way to verify closure is with a leak test.
Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage, if no other practical means is available. Per ISTC-3522(c) "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open during refueling outages per 1OST-11.14B (HHSI Full Flow Test). Full-stroke exercised closed by leakage testing during refueling outages per 1BVT 1.47.11 (Safety Injection and Charging System Containment Penetration Integrity Test).

==References:==
ISTC-3510, ISTC-3522(c), and ISTC-5221.
NUREG-1482, Rev.1, Sections 4.1.3 and 4.1.6.

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 294 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  26 Valve No(s):           1S1-100 1S1-101 1S1-102 Category:     A/C. Class:     I C
System:                11 - Safety Injection Function:              These high head safety injection cold leg branch line check valves must open to provide a flow path from the High Head Safety Injection (HHSI) Pumps to the reactor coolant system (RCS) cold legs during a safety injection.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation. Their safety position is open for HHSI in the event of a safety injection. During plant operation when the RCS is at normal operating pressure, full-stroke exercising in the open direction by initiating the maximum required accident condition flow rate in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, cannot be performed because the HHSI Pumps will not develop the required flow against reactor pressure. During cold shutdowns, full stroke exercising in the open direction cannot be performed because this could result in low-temperature overpressurization of the RCS. ISTC-3522(c) states, "If exercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open during refueling outages per 1OST-11.14B (HHSI Full Flow Test).
NOTE: Bi-directional exercising in the non-safety related closed direction will be satisfied in conjunction with leakage testing of [1SI-10, 11 & 12] per 1 OST-11.16 (Leak Testing RCS Pressure Isolation Valves).

==References:==
ISTC-3510, ISTC-3522(c), and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 295 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  27 Valve No(s):           1S1-115 1S1-116 Category:     C        Class:     2 System:                11 - Safety Injection Function:              These Boron Injection Recirc Pump Discharge Check Valves are required to close to isolate the BIT Recirc piping in an accident. The valves also serve as a Class 2 to non-Code boundary barrier.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The function of these check valves is to prevent reverse flow through the BIT recirc pumps during an accident when the HHSI is flowing through the BIT.
The normal test method to prove closure of these discharge check valves for parallel pumps is to monitor flow with one pump operating in NSA, isolate the non-running pump, then record flow again. If the check valve on the non-running pump is not seated, the flow will vary after the valve is isolated. If one of the recirc pumps is Out of Service (OOS) for an extended period, there is no method to prove closure of the operating check valve. The piping configuration does not contain vents, drains or test connections. Therefore, if one of the recirc pumps is OOS, testing in the reverse direction cannot be performed for either check valve. Per ISTC-3522(c), "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Perform full-stroke exercise closed quarterly per 1OST-47.3F (Containment Isolation and ASME OM Code Test) unless one of the recirc pumps is OOS. If one of the pumps is OOS, closure testing will be performed when the pump is returned to service, or at least during refueling outages per 1 OST-47.3F (Containment Isolation and ASME OM Code Test).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied by normal system operation of the Boron Injection Recirc Pumps per 1OST-47.3F (Containment Isolation and ASME OM Code Test).

==References:==
ISTC-3510 and ISTC-3522(c).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 296 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 28 Valve No(s):           MOV-1 SI-836 Category:     A        Class:      I System:                 11 - Safety Injection Function:              This outside containment isolation valve from the fill and charging headers to the Reactor Coolant System (RCS) hot and cold legs must open to provide a flow path to the RCS during cold leg recirculation. It must close for containment isolation of Penetration No. 96.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:         This valve is closed during normal operation. Its safety position is closed for containment isolation of Penetration No. 96, and open for cold leg recirculation. Full-stroke exercising in the open and closed directions cannot be performed during plant operation because this will inject relatively cold water into the RCS cold legs and cause thermal shock to system piping and components which will result in an increased probability of system and component failures. In addition, full-stroke exercising in the open and closed directions may not be possible during cold shutdown if the charging system is in service to support operation of a Reactor Coolant Pump (RCP). Cycling this valve open and closed with a Charging Pump operating to support RCP operation would cause significant changes in pressures and flows to the RCP seals, creating a challenge to long-term seal life. Shutting down the charging system during RCP operation while in cold shutdown would secure seal injection water to the RCP seals, resulting in seal damage. In order to stroke this valve, the charging system and RCPs would both have to be shutdown.
Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCPs need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCPs are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521 (e) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the RCPs are secured, or at least during refueling outages per 1OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(e).
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 297 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 29 Valve No(s):           MOV-1 SI-867A MOV-1SI-867B Category:     B        Class:      2 System:                11 - Safety Injection Function:              These Boron Injection Tank (BIT) inlet isolation valves must open to provide high head safety injection (HHSI) flow to the cold legs during a safety injection.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category B valves shall be tested nominally every 3 months.
Basis for ROJ:         During normal operations, the BIT is isolated from the charging system and reactor coolant system (RCS) by the BIT inlet and outlet isolation valves
[MOV-1 SI-867A, B, C and D]. They are required to open upon initiation of a safety injection to supply HHSI flow to the cold legs through the BIT. The normal operating pressure just upstream of BIT inlet isolation valves [MOV-1SI-867A and B] is approximately 2600 psig which is the discharge pressure of the Charging Pumps. The downstream pressure is approximately 150 psig.
The reason for this lower pressure is that the BIT boric acid solution is constantly recirculated by the relatively low pressure Boron Injection Recirculation Pumps. In order to cycle [MOV-1 SI-867A and B] open, the Boron Injection Recirculation Pumps must first be shutdown and isolated in order to prevent overpressurizing the subsystem. Once returned to the closed position, the piping downstream must be vented to less than 25 psig before the recirculation pumps can be unisolated and placed back into service. In addition, stroking these valves at power has historically caused leakage past the BIT manway flange and other valves in the system. Therefore, full or part-stroke exercising these valves at power is considered to be not practicable. In addition, stroking these valves at cold shutdown may not be possible if the charging system is in service to support operation of a Reactor Coolant Pump (RCP). With the charging system in service, the problems experienced by stroking these valves at power are also present during cold shutdowns. In order to stroke these valves, the charging system and RCPs would both have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCPs need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCPs and charging system are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521(e) states, "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                 Page 298 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 29 Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-1 during cold shutdowns when the charging system and the RCPs are secured, or at least during refueling outages per 1OST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-3510 and ISTC-3521(e).
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-1 Paragraph 3.6.3(c).

Beaver Valley Power Station                       Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 299 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 30 Valve No(s):           1NG-518 1 NG-519 1 NG-520 Category:     AIC      Class:     3 System:                11 - Safety Injection (Gaseous Nitrogen)
Function:              These Power Operated Relief Valve (PORVs) nitrogen supply check valves must remain closed to maintain nitrogen pressure in the back-up nitrogen accumulators to supply the control air for the PORVs.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The safety function of these check valves is to remain closed to maintain nitrogen pressure in the back-up nitrogen accumulators to supply the control air system for the PORVs. Because these check valves are located inside the slightly subatmospheric containment, it is not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. In addition, valve closure can only be verified by a leak test because no other practical means is available to verify check valve closure. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage if no other practical means is available. PerISTC-3522(c), "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by leakage testing during refueling outages per 1OST-6.12 (Power Operated Relief Valve Test).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied when nitrogen makeup is provided to the accumulators subsequent to exercising the PORVs on nitrogen during refueling outages per 1OST-6.12 (Power Operated Relief Valve Test).

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 300 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  31 Valve No(s):           1QS-3 1QS-4 1RS-100 1RS-101 Category:     AIC      Class:      2 System:                13 - Quench Spray System and Recirculation Spray Function:              These inside containment isolation discharge check valves for the quench spray and outside recirculation spray pumps must open to allow containment spray flow. They must also close for containment isolation of Penetration Nos.
63, 64, 70 and 71.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed weighted arm check valves. Their safety position is closed for containment isolation of Penetration Nos. 63, 64, 70 and 71, and open to allow containment spray flow. They cannot be exercised with flow without injecting water through the spray nozzles and spraying down containment. Therefore, full stroke exercising in the open and closed direction can only be verified by cycling the mechanical weight loaded swing arm of the check valves. Because these check valves are located inside the slightly subatmospheric containment, they are not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel.
This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. In order to exercise these weighted arm check valves in the open and closed direction during cold shutdown, scaffolding must be erected in order to gain access to the check valves which is considered to be an additional hardship that is not practicable during cold shutdowns. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open using a manual mechanical exerciser attached to their mechanical weight loaded swing arms in accordance with ISTC-5221(b) and the guidelines provided in NUREG-1482, Rev.1, Section 4.1.7, and closed by observation of their mechanical weight loaded swing arms during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).
NOTE: The check valves are also Type-C leakage tested per 1 BVT 1.47.5 (Type C Leak Test) at the Appendix J, Option B frequency.

==References:==
ISTC-351 0, ISTC-3522(c) and ISTC-5221(b).
NUREG-1482, Rev.1, Section 4.1.7.

Beaver Valley Power Station                          Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                          Page 301 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 32 Valve No(s):          1RS-158 1RS-160 Category:     C       Class:       2 System:               13 - Containment Spray Function:             These Low Head Safety Injection (LHSI) pump and outside recirc spray (RS) pump cross connection check valves must open to allow the outside recirc spray pumps to provide the High Head Safety Injection (HHSI) pumps with water from the containment sump if the LHSI pumps are inoperable.
Test                  Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves Requirement:          shall be exercised nominally every 3 months.
Basis for ROJ:        These check valves are normally closed during power operation but must open to fulfill their safety function in the unlikely event that the LHSI pumps are unable to supply the HHSI pumps. No practical method of testing these valves exists. The volume of water used to test the outside RS pumps is insufficient to full-stroke exercise the check valves even if it could be directed to the suction of the HHSI pumps. Per ISTC-5221(c), If the test methods in ISTC-5221(a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement. Part-stroke exercising these valves with flow subsequent to reassembly is also impractical. A part-stroke test would introduce PG water with entrained air into the Charging/RCS resulting in a potential chemistry problem. Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4.
Alternate Test:       Maintenance is to disassemble and inspect one valve in the open (safety) direction and in the closed (bi-directional) direction (i.e., full-stroked) in accordance with the sample frequency requirements of ISTC-5221 (c) per 1/2CMP-75-VELAN CHECK-1 M at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then the remaining valve in the group shall be disassembled and inspected during the same outage. Since a part-stroke exercise of these check valves after valve reassembly is not possible it will not be performed as permitted by ISTC-5221 (c)(4).

==References:==
ISTC-3510 and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.4.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 302 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  33 Valve No(s):            TV-1CC-103A                  TV-1CC-105D1                 TV-1CC-107E1 TV-1CC-103A1                 TV-1 CC-1 05D2               TV-1 CC-1 07E2 TV-1CC-103B                  TV-1CC-105E1 TV-1CC-103B1                 TV-1CC-105E2 TV-1 CC-1 03C                TV-1CC-107D1 TV-1CC-103C1                 TV-1 CC-1 07D2 Category:      A        Class:      2 System:                 15 - Reactor Plant Component Cooling Water Function:               These reactor plant component cooling water (CCR) supply to and return from containment inside and outside containment isolation valves must close to provide containment isolation of Penetration Nos. 8, 17, 18, 25, 26, 27 and 58.
Test Requirement:       Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:          These valves are normally open to supply cooling water to the Reactor Coolant Pump (RCP) stator, bearings, and thermal barrier. Their safety positions are closed for containment isolation of Penetration Nos. 8, 17, 18, 25, 26, 27 and 58. Full-stroke exercising in the closed direction cannot be performed during plant operation because this would interrupt flow of cooling water to the RCPs. Stroking these valves with the RCPs running could cause damage to the pump bearings, stator and thermal barrier if the valves would fail to reopen. Therefore, full or part-stroke exercising is not possible during power operation or during cold shutdowns when the RCPs are running. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCP's need not be stopped for cold shutdown valve testing. Therefore, these valves should only be tested during outages when the RCPs are secured and at refueling outages, but not more often than once every 92 days. Per ISTC-3521 (e), "If exercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:         [TV-1 CC-1 05D1, D2, El, E2] are full-stroke exercised and timed closed and fail-safe tested closed during cold shutdowns when the reactor coolant pumps are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).
[TV-1CC-103A, Al, B, B1, C, Cl] and [TV-1CC-107Di, D2, El, E2] are full-stroke exercised in accordance with ASME OM Code Case OMN-12 and fail-safe tested closed per ISTC-3560 during cold shutdowns when the reactor coolant pumps are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521 (e) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-12 Paragraph 5.5.1.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 303 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 34 Valve No(s):           TV-1CC-107A TV-1CC-107B TV-1CC-107C Category:     A        Class:      3 System:                 15 - Reactor Plant Component Cooling Water Function:              These Reactor Coolant Pump (RCP) Thermal Barrier Cooler reactor plant component cooling water (CCR) outlet isolation valves must close to isolate the lower pressure CCR system from the higher pressure reactor coolant system (RCS) in the event of a primary loop to CCR leak in the RCP Thermal Barrier Cooler.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category A valves shall be tested nominally every 3 months.
Basis for ROJ:         These valves are normally open to allow return of CCR cooling water from the RCP Thermal Barrier Coolers during RCP operation. Their safety position is closed in the event of a primary loop to CCR leak in the RCP Thermal Barrier Cooler. Full or part-stroke exercising in the closed direction cannot be performed during plant operation because this would interrupt or reduce flow of cooling water to the RCP thermal barrier coolers. The thermal barrier coolers limit heat transfer between the hot RCS water and the seal cooling water. Interruption of cooling water flow to the thermal barrier heat exchangers could result in damage to the RCP seals due to over heating. In addition, failure of these valves in the closed position could also result in a plant shutdown to avoid or due to RCP seal damage. In addition, full-stroke exercising in the closed direction may not be possible during cold shutdown if a RCP is operating. In order to stroke these valves without the potential risk in damage to the RCP seals, the RCP's would have to be shutdown. Per NUREG-1482, Rev.1, Section 3.1.1.4, "Stopping Reactor Coolant Pumps for Cold Shutdown Valve Testing," the RCP's need not be stopped for cold shutdown valve testing. The affected valves should be tested during outages when the RCP's are secured and during refueling outages, but not more often than once every 92 days. ISTC-3521 (e) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it may be limited to full-stroke during refueling outages."
Alternate Test:        Full-stroke exercised in accordance with ASME OM Code Case OMN-12 and fail-safe tested closed per ISTC-3560 during cold shutdowns when the RCP's are secured, or at least during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test).

==References:==
ISTC-351 0, ISTC-3521(e) and ISTC-3560.
NUREG-1482, Rev.1, Section 3.1.1.4.
OMN-12 Paragraph 5.5.1.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 304 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  35 Valve No(s):           1CCR-289 1CCR-290 1CCR-291 Category:     A/C      Class:      3 System:                15 - Reactor Plant Component Cooling Water Function:              These Reactor Coolant Pump (RCP) thermal barrier supply check valves must close to isolate the lower pressure Reactor Plant Component Cooling Water (CCP) system from the higher pressure Reactor Coolant System (RCS) in the event of a primary loop to CCR leak in the RCP Thermal Barrier Cooler.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally open during RCP operations to supply CCR cooling water to the RCP Thermal Barrier Coolers. Their safety position is closed in the event of a primary loop to CCR leak in the RCP Thermal Barrier Coolers. These valves cannot be stroked closed during power operation or during cold shutdowns when the reactor coolant pumps are operating. In addition, full stroke exercising in the closed direction can only be performed by leak testing because no other practical means is available to verify check valve closure. Because these check valves are located inside the slightly subatmospheric containment, they are not accessible to perform leak test during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. In addition, installation and removal of test equipment in order to perform leakage testing, if attempted during cold shutdowns, could result in a delayed plant startup. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each refueling outage, if no other practical means is available. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by leakage testing during refueling outage per 1BVT 1.60.7 (ASME OM Code Check Valve Reverse Flow Test).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied during normal system operation of the RCP's since temperature parameters associated with the RCPs are continuously monitored per ISTC-3550.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-3550.
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 305 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   36 Valve No(s):            1FW-33 1MS-18 1MS-1 9 1MS-20 Category:     C        Class:     2,3 System:                21 - Main Steam 24 - Auxiliary Feedwater Function:              The auxiliary feedwater (AFW) pump discharge check valve [1 FW-33] must open to allow auxiliary feed flow to the steam generators. It must close to prevent pump discharge flow from the motor-driven AFW pumps from being diverted through the out of service turbine-driven AFW pump. The main steam to the auxiliary feed pump check valves [1MS-18, 19 and 20] must open to allow steam flow to the turbine-driven AFW pump and must close to prevent multiple steam generator blowdown in the event of a high energy line break.
Test Requirement:      PerISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves support the Turbine-Driven Auxiliary Feedwater (TDAFW)
Pump. They must open to perform their various safety functions. Per ISTC-5221(a) and NUREG-1482, Rev.1, Section 4.1.3, a full-stroke exercise in the open direction may be achieved by initiating the maximum required accident condition flow. A full-stroke open exercise can only be verified by a full-flow test of the TDAFW Pump.
The full-flow test of the TDAFW Pump can only be performed in Mode 3, however, it is not practicable to perform this test in Mode 3 during shutdown for or during startup after each cold shutdown for several reasons. At that time, the introduction of relatively cold AFW into the S/Gs produces a potential for thermal shock to both the Main Feed Piping (Thermal Sleeves) and the secondary side of the S/Gs. Although the thermal sleeves and S/Gs are designed for thermal shock, exposure of the Station to these events shall be minimized in order to ensure that the benefits of plant life extension can be realized.
The AFW Pumps are designed to take suction from the demineralized water storage tank, [1WT-TK-10]. The water in [1WT-TK-10], however, is not treated for pH or Oxygen. Therefore, it could have some impact on the corrosion rates in the S/G. From a Chemistry perspective, it is preferred to minimize the use of this water while in Modes 1, 2 or 3.

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 306 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 36 Basis for ROJ:         In addition during startup, this test can only be performed once the steam pressure exceeds 600 psig. Testing at this time causes a temperature transient. The turbine draws steam from the S/Gs causing the RCS to cool down. In addition, the cold AFW is injected into the S/Gs, causing the RCS to cool even more. This cool down delays startup and is critical path time. At this point in the outage, the only heat source for the RCS is the RCPs.
Therefore, any cool down is costly in the amount of time required to heat back up again.
Therefore, performing the full-flow test of the TDAFW Pump at each cold shutdown is not practicable. Testing will be performed during refueling outages only. Therefore, the full-stroke open exercise of the check valves will also be performed at a refueling outage frequency. Per ISTC-3522(c), "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages".
[1MS-18, 19 and 20] do not have installed instrumentation or weighted arms to allow testing in the reverse direction. Therefore, the only way to verify closure is by disassembly during refueling outages. Per ISTC-5221(c), "As an alternative to the testing in ISTB-5221(a)and ISTC-5221(b), sample disassembly every refueling outage to verify operability of check valves may be used." Per ISTC-3522(c), "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        These valves will be full-stroke exercised in the open direction in Mode 3 during shutdown for or during startup after refueling outages when plant conditions permit directing flow to the S/Gs per 1OST-24.9 (Turbine-Driven AFW Pump Operability Test).
In addition, [1 MS-1 8, 19, 20] will be full-stroke exercised open and closed during refueling outages by way of a disassembly and inspection in accordance with the sample frequency requirements of ISTC-5221(c) per 1/2CMP-75-ENERTECH CHECK-1M at the frequency requirements of the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then all valves in the group shall be disassembled and inspected during the same outage. As a PMT following valve re-assembly, the inspected valve will be exercised in the open direction during the Comprehensive Pump Test of [1 FW-P-2] per 1OST-24.9 (Turbine-Driven AFW Pump Operability Test).
Closure testing of [1 FW-33] is discussed in VROJ38.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 307 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 37 Valve No(s):           1 MS-80 1MS-81 1 MS-82 Category:     C        Class:     2 System:                21 - Main Steam Function:              These A, B and C loop Steam Generator residual heat release reverse flow check valves must close to prevent steam generator cross connection in the event of a high energy line break.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed during plant operation. Their safety function is to close to prevent S/G cross connection in the event of a high energy line break. Exercising at power and cold shutdown testing in the reverse direction cannot be performed because there is no installed instrumentation to check for reverse flow and no way to isolate the normally cross-connected and pressurized headers. No way exists to isolate and systematically check operation of these valves. Per ISTC-5221 (c), "Ifthe test methods in ISTC-5221(a) and ISTC-5221(b) are impractical for certain check valves, or ifsufficient flow cannot be achieved or verified, a sample disassembly inspection program shall be used to verify valve obturator movement. Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4.
Alternate Test:        Maintenance is to disassemble and inspect one valve in the open and closed directions (full stroke) in accordance with the sample frequency requirements of ISTC-5221(c) per 1/2CMP-75-ENERTECH CHECK-1M at the frequency requirements of the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then all valves in the group shall be disassembled and inspected during the same outage. As a PMT following valve re-assembly, a part-stroke exercise in the open direction will be performed per 1OM-50.4.L (Plant Heat Up From Mode 5).

==References:==
ISTC-3510 and ISTC-5221(c).
NUREG-1482, Rev.1, Section 4.1.4.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 308 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 38 Valve No(s):           1 FW-33                1FW-42                1FW-622              1FW-625 1 FW-34                1FW-43                1 FW-623             1FW-626 1 FW-35                1FW-44                1 FW-624             1FW-627 Category:     C        Class:     3 System:                24 - Auxiliary Feedwater Function:              These auxiliary feedwater pump discharge and loop check valves must open to allow auxiliary feed flow to the steam generators. These check valves also must close to fulfill a safety function: [1 FW-33, 34, 35] must close to prevent pump discharge from being diverted through the non-running pump, [1 FW-42, 43, 44] must close to prevent main feedwater from flowing back into the auxiliary feedwater piping, and [1FW-622, 623, 624, 625, 626, 627] must close to separate the A & B auxiliary feedwater headers.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The safety position for these check valves is open for auxiliary feed system injection to the Steam Generators and closed to provide header separation.
These valves can only be full-stroke exercised open by initiating the maximum required accident condition flow, in accordance with ISTC-5221 and NUREG-1482, Rev.1, Section 4.1.3, by aligning auxiliary feedwater flow to the S/Gs.
This flow path would cause thermal shock at the auxiliary and main feedwater interface caused by the sudden injection of cold water into the S/Gs. Feeding the S/Gs with cold water also would result in large level transients in the S/Gs and cause a reactor trip. In addition, the reverse direction test for valves
[1 FW-33, 34, 35] and [1 FW-622 thru 627] can only be performed with auxiliary feed flow to the S/Gs. Therefore, it is not practical to full-stroke exercise these check valves quarterly. Per ISTC-3522(b), "If exercising is not practicable during operation at power, it may be limited to full-stroke exercising during cold shutdowns." Although, full-stroke exercising in the open direction during cold shutdown is possible it is more desirable to forward exercise the valves during refueling outages in conjunction with the comprehensive pump test since accident flow conditions are established during this test.
Alternate Test:        Check valves [1 FW-42, 43, 44] and [1 FW-622 thru 627] are full-stroke exercised in the open direction during refueling outages per 1OST-24.8A and 8B (Motor-Driven Auxiliary Feed Pump Check Valves and Flow Tests). Check valves [1 FW-33, 34 and 35] and [1 FW-622 thru 627] are also full-stroke exercised in the closed direction by these OSTs. Reverse direction testing of check valves [1 FW-42, 43, 44] is performed by monitoring the upstream temperatures at least quarterly in operator rounds and is supplemented by a leak test per 1OST-24. 11 (Auxiliary Feedwater Check Valve Exercise Verification) at refueling outages. Forward stroke testing of [1 FW-33] is discussed in VROJ36.

==References:==
ISTC-3510, ISTC-3522(b), and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.3.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                           Page 309 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 39 Valve No(s):            1 FW-50 1 FW-51 1 FW-52 1 FW-68 1 FW-69 1FW-70 Category:      C        Class:      3 System:                 24 - Auxiliary Feedwater Function:               These Turbine and Motor-Driven Auxiliary Feedwater (AFW) Pump Lube Oil Cooler Line Check Valves must open to allow cooling flow to the lube oil cooler for the Turbine and Motor-Driven AFW Pumps.
Test Requirement:       Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:          The function of these check valves is to open to allow cooling flow to the lube oil cooler for the Turbine and Motor-Driven AFW Pumps. Full-stroke capability can only be verified by establishing design flow through the line or by using a mechanical exerciser to open the valve. However, there is no installed flow instrumentation to measure flow and these check valves do not have external weight arms to exercise them by. Therefore, per ISTC-5221(c),
                         "If the test methods in ISTC-5221(a) and ISTC-5221(b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly inspection program shall be used to verify valve obturator movement." Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4.
Alternate Test:         Maintenance is to disassemble and inspect one valve in the open (safety) direction and in the closed (bi-directional) direction (i.e., full stroked) in accordance with the sample frequency requirements of ISTC-5221 (c) per 1CMP WAFER CHECK-4M at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then the remaining valves in the group shall be disassembled and inspected during the same outage. Following re-assembly, the inspected check valve will be PMT exercised in the open direction during the Comprehensive Pump Test (CPT) of [1 FW-P-2] per 1OST-24.9 (Turbine-Driven AFW Pump Operability Test) or during the CPT of [1 FW-P-3A and 3B]
per 1OST-24.8A and 8B (Motor-Driven AFW Pump Check Valves and Flow Tests).

==References:==
ISTC-351 0, ISTC-5221(c) and ISTC-5222.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                       Page 310 of 320 VALVE REFUELING OUTAGE JUSTIFICATION            40 (NOT USED AT THIS TIME)
Valve No(s):
Category:     C        Class:
System:
Function:
Test Requirement:
Basis for ROJ:
Alternate Test:

==References:==

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                     Page 311 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 41 Valve No(s):           1 FW-156A 1FW-156B 1 FW-156C Category:     C        Class:     2 System:                24 - Main Feedwater Function:              These A, B and C loop feedwater Containment isolation check valves must close for feedwater isolation of the Steam Generators in the event of a main steam line break, and to prevent reverse direction flow to non-safety related main feedwater system piping during operation of the Auxiliary Feedwater (AFW) Pumps in an accident.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months and per OM-1 0.
Basis for ROJ:         These check valves are normally open during plant operation to provide main feedwater flow to the Steam Generators. Their safety position is closed for feedwater isolation in the event of a main steam line break, and to ensure adequate AFW pump flow to the Steam Generators during an accident.
Because these valves must remain open to provide feedwater flow to the Steam Generators during normal operations, full-stroke exercising these valves to the closed position at power is not possible. The only method for verifying check valve closure is by a leak test. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each refueling outage, if no other practical means is available. ISTC-3522(c) states, "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by a leak test at refueling outages per 1 OST-24.14A, B and C (Main Feed Containment Isolation Valve Exercise Verifications) or 1OST-24.8A or 8B (Motor-Driven AFW Pump & Check Valves Full Flow Tests).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied by normal system operation with feedwater flow to the Steam Generators per ISTC-3550.

==References:==
ISTC-3510, ISTC-3522(c) and ISTC-3550.
NUREG-1482, Rev.1, Section 4.1.6.
ECP 02-0183 (1R16).

Beaver Valley Power Station                        Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 312 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   42 Valve No(s):           1AS-278 Category:     A/C      Class:      2 System:                26 - Main Turbine and Condenser System Function:              This containment isolation air ejector air discharge check valve must open to direct steam to containment if high radiation levels are present in the main condenser. It must also close for containment isolation of Penetration No. 89.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is required to open to provide a flow path for radioactive gases from the Condenser Air Ejector effluent line into containment in the event of a S/G tube leak with subsequent contamination of the steam systems.
It is also required to close for containment isolation of Penetration No. 89.
Full-stroke exercising in the open and closed direction can only be verified by cycling the mechanical weight loaded swing arm of the check valve. Because this check valve is located inside the slightly subatmospheric containment, it is not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line. In order to exercise this weighted arm check valve in the open and closed direction during cold shutdown, scaffolding must be erected in order to gain access to the check valve which is considered to be an additional hardship that is not practicable during cold shutdowns. ISTC-3522(c) states, "Ifexercising is not practicable during operation at power or cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised open using a manual mechanical exerciser attached to its mechanical weight loaded swing arms in accordance with ISTC-5221 (b) and the guidelines provided in NUREG-1482, Rev.1, Section 4.1.7, and closed by observation of its mechanical weight loaded swing arm during refueling outages per lOST-1.10 (Cold Shutdown Valve Exercise Test.
NOTE: The check valve is also Type-C leakage tested per 1 BVT 1.47.5 (Type C Leak Test) at the Appendix J, Option B frequency.

==References:==
ISTC-351 0, ISTC-3522(c) and ISTC-5221 (b).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 313 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   43 Valve No(s):           1RW-106 1RW-107 Category:     C        Class:      3 System:                30 - River Water Function:              These river water header supply check valves must open to supply river water to the safety-related components during an accident and must close to prevent reverse flow by the auxiliary river water pumps when they are supplying the river water headers.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally open during plant operation. Their safety function is to open to supply river water to the safety-related components during an accident and to close to prevent reverse flow from the Auxiliary River Water Pumps when they are supplying the river water headers. These check valves are full-stroke exercised in the open direction each quarter.
However, full-stroke exercising in the closed direction is not practicable for the following reasons:
                         " Local observation of check valve closure is not possible because the check valves do not have position indicating devices that would indicate closure.
* Measuring a change in system pressure across the check valves is not possible because upstream isolation valves are not leak tight and may allow pressure to equalize across the river water headers.
* Seat leakage measurement is not possible because a substantial leakage path does not exist. In order to create a large enough leakage path with an Auxiliary River Water Pump supplying the river water header, both river water headers must be cross-connected at the River Water Pumps. Since both river water headers are needed for the test, this limits the ability to perform work on the Reactor Plant River Water System. The Turbine Plant River Water (TPRW) System may also need to be placed into service in order to cool secondary side equipment. This limits the ability to perform work on the TPRW system. During testing, cooling water would have to be isolated to one train of the Charging Pumps, Control Room Air Conditioning Units and Reactor Plant Component Cooling Water System.
This would affect the availability of these components and systems along with the Residual Heat Removal System. In addition, there is no installed instrumentation to check for reverse flow. A temporary flow instrument would have to be installed to measure flow.

Beaver Valley Power Station                         Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 314 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                   43 Basis for ROJ:         Per ISTC-5221 (c), "If the test methods in ISTC-5221 (a) and ISTC-5221 (b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly inspection program shall be used to verify valve obturator movement." Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4.
Alternate Test:        Maintenance is to disassemble and inspect one valve in the open and closed direction (full stroke) in accordance with the sample frequency requirements of ISTC-5221(c) per 1/2CMP WAFER CHECK-1M at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then the remaining valve in the group shall be disassembled and inspected during the same outage. As a PMT following valve re-assembly, a part-stroke exercise in the open direction will be performed during return of the River Water header to service per 1OM-30.4.AC (Clearing River Water Headers A and B for Maintenance).

==References:==
ISTC-3510 and ISTC-5221 (c).
NUREG-1482, Rev.1, Section 4.1.4.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                         Page 315 of 320 VALVE REFUELING OUTAGE JUSTIFICATION 44 Valve No(s):           1WT-383 1WT-388 Category:     C        Class:     3 System:                30 - River Water Function:              These check valves must close to isolate the chlorine injection line from the river water header.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency," Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         These check valves are normally closed because the chlorine injection system is no longer in service. Their safety function is to remain closed to prevent river water from being diverted to the chlorine injection line during an accident.
Because of the physical arrangement of these check valves off each RW header with a series check valve (not in IST Program) located adjacent just upstream and without a vent or drain in between, the valves cannot be individually verified to close by using flow or by leak test. Per ISTC-5221 (c), If the test methods in ISTC-5221(a) and ISTC-5221(b) are impractical for certain check valves, or if sufficient flow cannot be achieved or verified, a sample disassembly examination program shall be used to verify valve obturator movement. Further guidelines for disassembly and inspection are provided in NUREG-1482, Rev.1, Section 4.1.4."
Alternate Test:        Maintenance is to disassemble and inspect one valve in the open (bi-directional) direction and in the closed (safety) direction (i.e., full-stroked) in accordance with the sample frequency requirements of ISTC-5221(c) per 1/2CMP-75-WEST CHECK-1M at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program. If the sample valve fails its inspection, then the remaining valve in the group shall be disassembled and inspected during the same outage. Because the Chlorine Injection System has been retired, a part-stroke exercise of these check valves after valve reassembly is not possible and will not be performed as permitted by ISTC-5221(c)(4).

==References:==
ISTC-3510 and ISTC-5221.
NUREG-1482, Rev.1, Section 4.1.4.
ASME OM Code, Appendix II (Check Valve Condition Monitoring Program).

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                        Page 316 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                 45 Valve No(s):            1IA-91 Category:     A/C      Class:       2 System:                34 - Compressed Air (Instrument Air)
Function:              This containment instrument air header inside containment isolation check valve must close to provide containment isolation of Penetration No. 47.
Test Requirement:      Per ISTC-351 0, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         This check valve is normally open and will remain open during operation of the containment instrument air system. Its safety position is closed for containment isolation of Penetration No. 47. The containment instrument air system is normally in service during plant operations and would have to be shutdown in order to test this check valve. In addition, full stroke exercising in the closed direction can only be performed by leak testing during the IOCFR50, Appendix J leak rate testing performed at refueling because no other practical means is available to verify check valve closure. This involves the installation and removal of special test equipment in order to perform the leakage testing. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outages for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak rate testing at each refueling outage, if no other practical means is available. Per ISTC-3522(c), "Ifexercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by leakage testing during refueling outages per 1 BVT 1.47.5 (Type-C Leak Test) at the frequency specified by the Check Valve Condition Monitoring (CVCM) Program.
NOTE: Bi-directional testing in the non-safety related open direction is satisfied during exercise testing of the PORVs during refueling outages per 1OST-6.12 (Power Operated Relief Valve Test).

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                       Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 317 of 320 VALVE REFUELING OUTAGE JUSTIFICATION                  46 Valve No(s):           1 IA-116 1IA-117 1 IA-378 Category:     A/C      Class:     3 System:                34 - Compressed Air Function:              These air supply isolation check valves for the Power Operated Relief Valves (PORVs) must close on loss of instrument air to allow the back-up nitrogen accumulators to supply the control air for the PORVs.
Test Requirement:      Per ISTC-3510, "Exercising Test Frequency, "Active Category C check valves shall be exercised nominally every 3 months.
Basis for ROJ:         The safety function of these check valves is to close to allow the back-up nitrogen accumulators to supply the control air system for the PORVs. These check valves are located inside the slightly subatmospheric containment, they are not accessible for testing during plant operation because the radiation levels and air temperature inside containment are higher than normal during power operation and would involve higher radiological dose rates and heat stress risk to plant personnel. This presents a working environment for station personnel that is not considered practicable for quarterly surveillance testing on a routine basis on-line.. In addition, valve closure can only be verified by a leak test because no other practical means is available to verify check valve closure. Per NUREG-1482, Rev.1, Section 4.1.6, "Extension of Test Interval to Refueling Outage for Check Valves Verified Closed by Leak Testing," it is acceptable to verify that check valves are capable of closing by performing leak-rate testing at each refueling outage if no other practical means is available. Per ISTC-3522(c), "If exercising is not practicable during operation at power and cold shutdowns, it shall be performed during refueling outages."
Alternate Test:        Full-stroke exercised closed by leakage testing during refueling outages per 1OST-6.12 (Power Operated Relief Valve Test).
NOTE: Bi-directional exercising in the non-safety related open direction is satisfied during exercise testing of the PORVs during refueling outages per 1OST-6.12 (Power Operated Relief Valve Test).

==References:==
ISTC-3510 and ISTC-3522(c).
NUREG-1482, Rev.1, Section 4.1.6.

Beaver Valley Power Station                  Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves               Page 318 of 320 SECTION IX:   VALVE RELIEF REQUESTS

Beaver Valley Power Station                        Unit I Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                       Page 319 of 320 VALVE RELIEF REQUEST 1 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.
Component(s)                Motor-operated valve assemblies currently included in the Beaver Valley Affected:                   Motor-Operated Valve Program Component/System            Various Function:
Applicable Code             ASME OM Code-2001 Edition, with Addenda through OMb-2003.
Edition and Addenda:
Applicable Code             ISTA-3130, "Application of Codes Cases", ISTA-3130(b) states, Code Requirement(s):             Cases shall be applicable to the edition and addenda specified in the test plan.
ISTC-5120, "Motor-Operated Valves", ISTC-5121 (a) states; Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500.
ISTC-3700, "Position Verification Testing" states in part, Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated.
Reason for Request:         NUREG-1482, Revision 1, Section 4.2.5 states in part; As an alternative to MOV stroke-time testing, ASME developed Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants" which provides periodic exercising and diagnostic testing for use in assessing the operational readiness of MOVs. Section 4.2.5 further states; The NRC staff recommends that the licensees implement ASME Code Case OMN-1 as accepted by the NRC (with certain conditions) in the regulations or RG 1.192, as alternatives to the stroke-time testing provisions in the ASME Code for MOVs. RG 1.192 allows licensees with an applicable Code of record to implement ASME Code Case OMN-1 (in accordance with the provisions in the regulatory guide) as an alternative to the Code provisions for MOV stroke-time testing, without submitting request for relief from their Code of record. Licensees with a Code of record that is not applicable to the acceptance of this Code Case may submit a request for relief to apply the Code Case consistent with the indicated conditions to provide an acceptable level of quality and safety. The Code of record for BVPS-1 Fourth 10-Year IST Interval is OM Code-2001 Edition with Addenda through OMb-2003 and the applicable Code for OMN-1, as stated in RG 1.192, was reaffirmed for OMa-1 999.

Beaver Valley Power Station                      Unit 1 Issue 4 Revision 0 Inservice Testing (IST) Program For Pumps And Valves                                      Page 320 of 320 VALVE RELIEF REQUEST I Proposed Alternative      Pursuant to the guidelines provided in NUREG-1482, Revision 1, Section and Basis for Use:        4.2.5, BVPS-1 proposes to implement 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. BVPS-1 also proposes to implement the provisions specified in ISTC-3700 in conjunction with the MOV diagnostic test frequency in lieu of once every 2 years.
Using the provisions of this relief request as an alternative to the MOV stroke-time testing requirements of ISTC-5120 and position verification frequency of ISTC-3700 provides an acceptable level of quality for the determination of valve operational readiness. Code Case OMN-1 should be considered acceptable for use with ASME OM Code-2001 through OMb-2003 as the Code of record. It is requested that the NRC evaluate this determination pursuant to 10 CFR 50.55a(f)(6)(i) and grant relief from the identified ISTC Code requirements by implementing Code Case OMN-1.
Duration of Proposed      The proposed alternative identified in this relief request shall be utilized Alternative:              during the Fourth Ten Year IST Interval.
Precedents:               None

==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" ISTA-3130, "Application of Code Cases" ISTC-5120, "Motor Operated Valves" ISTC-3700, "Position Verification Testing" Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in LWR Power Plants"}}