ML20140C015

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Issue 2,Rev 0 to 2nd Ten-Year Interval Update of BVPS-2 IST Program
ML20140C015
Person / Time
Site: Beaver Valley
Issue date: 05/30/1997
From:
DUQUESNE LIGHT CO.
To:
Shared Package
ML20140C007 List:
References
PROC-970530, NUDOCS 9706090077
Download: ML20140C015 (800)


Text

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SUMMARY

OF CHANGES THIRD 10 YEAR INTERVAL UNIT 2 IST PROGRAM i { l^ , i i t !O 9706090077 970530 . PDR ADOCK 05000412 p PDR

l ENCLOSURE 1

SUMMARY

OF CHANGES ,,3 2ND TEN-YEAR INTERVAL UNIT 2 IST PROGRAM d The 2nd ten-year interval for the BVPS Unit 2 IST Program will begin on November 18, 1997. The new program is based on the following:

             . American Society of Mechanical Engineers (ASME)/ American National Standards Institute (ANSI) Operational and Maintenance (OM) Standard, Part 6, " Inservice Testing of Pumps in Light Water Reactor Power Plants" (OM-6),

and Part 10, " Inservice Testing of Valves in Light Water Reactor Power Plants" (OM-10), OMa-1988 Addenda to the OM-1987 Edition, in accordance with the ASME Boiler and Pressure Vessel Code, Section XI,1989 Edition.

             . Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs," April 3,1989.
             . NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants,"

April 1995. There were significant changes in the regulations between the 1983 Edition of the ASME XI Code, (the present Code in effect) and the 1989 Edition (the Code for the new program). These changes necessitated several changes to the BVPS-2 IST Program. In addition, to support this 10-year interval update, an IST Program Basis Document (] U was developed. The Basis Document examined every Category 1 pump and valve to determine whether it should be included in, or excluded from the BVPS-2 IST Program and if the testing performed is adequate. As a result of the review several other changes were also made to the BVPS-2 IST Program. The following is a summary of all of the changes made to the Program.

1) The following are changes to Section I of the BVPS-2 IST Program " Pump Testing Requirements."

a) The new edition and addenda of the Code were referenced. In addition, where IWP or ASME had been referenced, OM-6 is now referenced and the correct tables from OM-6 have been incorporated. b) Note that the inservice test parameters for testing pumps under OM-6 has deleted the requirements for obtaining inlet pressure, proper lubricant level or pressure, and bearing temperatures. It is the IST Groups intent, however, that these parameters still be obtained for information as a good practice during pump testing. Also note that broader ranges for flow and l delta-p now exists under OM-6, particularly for the upper end. l

g c) Pumps are now only required to run for at least 2 minutes under i tg conditions as stable as the system permits prior to measurement of the i

specified parameters. The old requirement was for 5 minutes. I

i < ! l ENCLOSURE 1 l

SUMMARY

OF CHANGES ! A V d) A former relief request for not including " mar,ufacturer supplied skid- , mounted pumps" in the BVPS-2 IST Program has now been recognized l l by the NRC in NUREG-1482, Section 3.4, " Skid-Mounted Components  ! and Component Subassemblies." Therefore, a statement documenting  ! this approach has been included in this section as required by the NUREG. e) A " Cold Shutdown Justification" Section and a " Refueling Outage Justification" Section were added to the BVPS-2 IST Program for those i pumps tested only during cold shutdowns or refueling outages as permitted by Paragraphs 5.3,5.4 or 5.5 of OM-6.

2) The following are changes to Section 11 of the BVPS-2 IST Program " Pump  !

Outlines." l a) All of the pump outline sheets were revised to delete the testing  ; requirements for suction pressure (Pi), bearing temperature (Tb) and lubricant level observation (L). As stated earlier, OM-6 does not require these parameters to be measured. I

 ,r                                                                                      !

The " Remarks" column for all of the pumps was expanded to state how b) l the pump was tested. (i.e., Pump is tested quarterly on recirculation flow and at full flow during refueling outages.) Any pump relief requests (PRRs), cold shutdown justifications (PCSJs) and refueling outage . justifications (PROJs) that apply are also listed. l 1 c) The " Comments" Column was expanded to include details on how the l I parameters are being measured, and to specifically mention the sections of OM-6, Generic Letter No. 89-04 or NUREG-1482 that may apply. 1

3) The following are changes to Section 111 of the BVPS-2 IST Program " Pump Cold l Shutdown Justifications."

a) Pump Cold Shutdown Justification No.1 (PCSJ1) was written for the l Residual Heat Removal Pumps [2RHS*P21 A and B], to document that the pumps will be tested quarterly during cold shutdowns. This is permitted by OM-6, Paragraph 5.4, " Pumps in Systems Out of Service." This PCSJ l is RR1 in the current revision of the BVPS-2 IST Program (Issue 1 j Rev.16). ? 2

 . _-      -                 ~                             .-         -               --   . -.

, ENCLOSURE 1

SUMMARY

OF CHANGES t n iU

4) The following are changes added to new Section IV of the BVPS-2 IST Program
         " Pump Refueling Outage Justifications."

a) Pump Refueling Outage Justification No.1 (PROJ1) was written for the j Recirculation Spray Pumps, [2RSS*P21 A, B, C and D] to document that l the pumps will be tested during refueling outages, because a temporary l dike must be installed in containment around the sump. This is in accordance with OM-6, Paragraph 5.5, " Pumps Lacking Required Fluid inventory." This PROJ is RR2 in the current revision of the BVPS-2 IST Pcogram (issue 1, Rev.16). 5

5) The following are changes to Section V of the BVPS-2 IST Program " Pump Relief Requests." Note that all of the following relief requests require NRC approval prior to implementation.

! a) Pump Relief Request No.1 (PRR1)is a new relief request written to allow the use of spectral analysis in lieu of placing a pump on double frequnncy testing when the vibration levels are outside of the acceptable range. This request is based on a later edition of the ASME XI Code; ASME OMc iV Q Code-1994, Subsection ISTB, Paragraph 4.6, "New Reference Values " which would allow analysis. , 1 b) Pump Relief Request No. 2 (PRR2) was written for various instruments which do not meet the requirements of OM-6, Paragraph 4.6.1.2(a),

                " Range," however the accuracy of the instruments is more conservative than the requirements of OM-6, Paragraph 4.6.1.1, " Quality." 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 OM-6. This is in accordance with NUREG-1482, l                Section 5.5.1," Range and Accuracy of Analog Instruments." This PRR is l                RR10 in the current revision of the BVPS-2 IST Program (Issue 1, f                Rev.16). In addition, [2CHS-F1122A] was deleted from the relief request because it is no longer used during full flow Charging Pump testing at refueling. [2CHS-Fl943] was deleted from the relief request because the full flow Charging Pump testing at refueling is now pe: formed with the reference flow greater than one third of the range. [2SWS-Pl105A-C]

were deleted from the relief request because seal water pressure is no l longer required to be observed per OM-6, Table 2, " Inservice Test Parameters." c) Pump Relief Request No. 3 (PRR3) was written for the Component l O Cooling Water Pumps, [2CCP*P21 A, B and C], to allow the use of a pump curve. The basis for this request is NUREG-1482, Section 5.2, "Use of i 3 l

ENCLOSURE 1

SUMMARY

OF CHANGES l l (3 1 Variable Reference Values for Flow Rate and Differential Pressure During Pump Testing." This PRR is RR7 in the current revision of the BVPS-2 i IST Program (Issue 1, Rev.16). I l d) Pump Relief Request No. 4 (PRR4) was written for the Service Water Pumps [2SWS*P21 A, B and C), to allow the use of a pump curve. The basis for this request is NUREG-1482, Section 5.2, "Use of Variable Reference Values for Flow Rate and Differential Pressure During Pump Testing." This PRR is RR8 in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16). e) Pump Relief Request No. 5 (PRR5) is a new relief request written for the i Service Water Pumps [2SWS*NI A, B and C]. OM-10, Paragraph 4.6.4, l

     " Vibration Measurements," part (b) requires for vertical line shaft pumps that vibrations be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction. Since this is not possible due to the non-rigid metal top hat installed on top of the Service Water Pump motors, relief from this requirement has been requested.           l Instead, an axial vibration reading will be obtained at the lower motor       l bearing housing, which is the method currently being performed. The O     position taken previously was that the axial orthogonal direction was not C/    accessible at the upper motor bearing housing, and was therefore not          !

required. In total, vibration measurements in two orthogonal directions l will continue to be obtained at the upper motor bearing housing and vibration measurements in three orthogonal directions will continue to be obtained at the lower motor bearing housing. f) Pump Relief Request No. 6 (PRR6) was written for the Emergency Diesel Generator Fuel Oil Transfer Pumps (2EGF*P21 A, B, C and D], to allow the flow rate of the pumps to be calculated based on a level change over time in the Fuel Oil Day Tank. Relief is being requested since there is no installed instrumentation to directly measure flow rate. This PRR is RR4 in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16). g) The following Relief Requests in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16) were deleted for the following reasons: RR3 - Relief had previously been requested not to measure suction pressure for the Service Water Pumps [2SWS*P21 A, B and C], because no installed instrumentation existed. However, NUREG-1482, Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure," states that the use of tank level or rivar elevation to obtain the suction pressure for measurement of pump differential pressure is permissible. 4

ENCLOSURE 1 , i

SUMMARY

OF CHANGES < LJ RRS- Relief had previously been requested not to measure suction pressure for the the Emergency Diesel Generator Fuel Oil Transfer l Pumps (2EGF*P21 A, B, C and D], because no installed instrumentation existed. However, NUREG-1482, Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure," states that the use of tank level or river elevation to obtain the , suction pressure for measurement of pump differential pressure is  ! permissible. RR6 - Relief had previously been requested to use pump discharge pressure instead of differential pressure (AP) for the Quenen Spray Chemical Injection Pumps (20SS*P24A and B]. However, OM-6, Table 2, " Inservice Test Parameters," no longer requires AP to be. measured for positive displacement pumps, but rather discharge pressure. RR9 - Relief had previously been requested to obtain pump vibration i measurements in accordance with OM-6 instead of ASME XI, IWP. i Since OM-6 is now being used in the 2nd ten-year interval update of the BVPS-2 IST Program, this relief request is no longer . required. i O) ( 1

6) The following are changes to Section VI of the BVPS-2 IST Program " Pump l Minimum Operating Point (MOP) Curves."

I a) The MOP Curves for the Charging Pumps [2CHS*P21 A, B and C] were revised to include instrument uncertainties and diesel generator frequency variations while still maintaining the injection flow requirements of the safety analyses per Calculation 10080-N-747, Rev.0, dated 9/20/96. b) The shape of the MOP Curves for the Residual Heat Removal Pumps [2RHS*P21 A and B] were revised based on new pump performance curves obtained on 11/15/96 following overhaul of the pumps. The MOP was not changed and the MOP curve still meets the most current calculation for the pumps (BV2-SET-024, dated 2/3/87). c) The shape of the MOP Curve for the "B" Component Cooling Water Pump l [2CCP*P21B] was revised based on a new pump performance curve ! obtained on 1/16/97 following overhaul of the pump. The MOP was not ' r~s changed and the MOP curve still meets the most current calculation for j () the pump (10080-N-740, A.1, dated 1/26/96). 5

ENCLOSURE 1

SUMMARY

OF CHANGES iO V d) The MOP's and MOP Curves for the Turbine-Driven and Motor-Driven i

             , .uxiliary Feedwater Pumps [2FWE*P22,23A and 238) were revised to          I provide additional margin for pump operation while still maintaining the    l minimum required flow in an accident per Calculation 10080-N-684, Rev.0, dated 8/17/93. To support this change, Operating License Change Request No. 213/80 was submitted to the NRC on 9/6/96 for review.           l Approval of this Change Request is required prior to implementation of these MOP Curves contained in Issue 2, Rev.0 of the BVPS-2 IST Program.

e) MOP Curves were added for the Emergency Diesel Generator Fuel Oil l Transfer Pumps [2EGF*P21 A, B, C and D) based on verification of Calculation 12241-MT-224, Rev.1, dated 10/31/86.

7) The following are changes to Section Vil of the BVPS-1 IST Program " Valve Testing Requirements."

i a) The new edition and addenda of the Code were referenced. In addition, where IWV or ASME had been referenced, OM-10 is now referenced and O v the correct tables from OM-10 have been incorporated. b) The paragraphs describing the requirements of the ASME XI Code for valves were revised to reflect OM-10. For example:

             .        The limits for stroke time testing have been changed and are now based on a reference or baseline time instead of the previous stroke time.
             .        Increased frequency (monthly) retesting has been eliminated and more stringent rules for declaring a valve inoperable or operable based on analysis are included.
             .        Local remote position verification should be supplemented by other indications such as use of flow meters or other suitable instrumentation to verify disk position, where practicable.

c) Safety and relief val e testing is required to be conducted in accordance with the requirements of OM-1, " Requirements for lnservice Performance Testing of Nuclear Power Plant Pressure Relief Devices." The test frequency for most safety and relief valves, except for the Main Steam Safety Valves and Pressurizer Code Safety Valves, will be once every 10 (,) (~N years instead of once every 5 years. The Main Steam Safety Valves and Pressurizer Code Safety Valves will remain on a once every 5 year 6

ENCLOSURE 1 1

SUMMARY

OF CHANGES V . frequency, however. In addition to setpoint testing being required within 13% of the set pressure, a seat tightness test will also be required. Any l valves that fail their set pressure test will require two (2) additional valves to be tested for each valve failure up to the total number of valves form the same group. d) A former relief request for not including " manufacturer supplied skid-mounted valves" in the BVPS-2 IST Program has now been recognized by l the NRC in NUREG-1482, Section 3.4, " Skid-Mounted Components and Component Subassemblies." Therefore, a statement documenting this l approach has been included in this section as required by the NUREG. ' e) A " Refueling Outage Justification" Section was added to the BVPS-2 IST Program for those valves tested only during refueling outages as permitted by paragraphs 4.2.1.2 and 4.3.2.2 of OM-10. l

8) The following are changes to Section Vill of the BVPS-2 IST Program " Valve Outlines."
 ]v    a)     General changes made throughout the Valve Outline sheets include:
              .       Drawing coordinates were revised to reflect the most current OM Drawings in effect.

The referenced surveillance test (s) were revised where needed

              .      The Valve Cold Shutdown Justifications (VCSJ's), Valve Refueling Outage Justifications (VROJ's) and Valve Relief Request (VRR's) numbers listed on the Valve Outline sheets for each valve were revised to reflect the corresponding VCSJ's ,VROJ's or VRR's listed in the back sections. These will be discussed later in more detail for each individual valve.
              .       The testing frequency listed for valves that are leak tested, not in accordance with the 10CFR50 Appendix J (Option B) Program, was revised to 2 years (2YR). For PlV's, the testing frequency listed is (2YR / CSD or R per Tech Specs). Containment isolation valves tested per the 10CFR50 Appendix J Program are tested at the frequency required by Option B of Appendix J. They are listed as a "Special Frequency" (SP) in the " Comments" column with a fq                   " Test Requirement" of "LTJ."

V 7

ENCLOSURE 1

SUMMARY

OF CHANGES (3 V b) The " Valve Type" column for the Pressurizer Code Safety Valves and the Main Steam Safety Valves was revised to say " Safety" instead of " Relief." In addition as stated earlier, the test frequency for these safety valves will remain at 5 years (5YR), however, the remaining relief valve test frequencies have been revised to 10 years (10YR) in accordance with OM-1 and as tested per 2BVT 1.60.5. c) As a result of the BVPS-2 IST Basis Document review, a fail-safe test to the closed position was added for the Reactor Vessel Head Vent Valves (2RCS*HCV250A and B), and for the Pressurizer Power Operated Relief Valves (PORV's)(2RCS*PCV455C,455D and 456]. In addition, the NSA position for the PORV's was corrected to " shut and in automatic" - S(A). d) The NSA positions for the following valves were corrected from automatic (A) to " shut and in automatic" - S(A):

     .       [2CHS*FCV113A), Boric Acid to Boric Acid Blender FCV
     .       {2CHS*LCV115B and D], Charging Pump Suction from RWST

, e) The NSA positions for the following valves were corrected from automatic (A) to "open and in automatic" - O(A):

     .       [2CHS*LCV115C and E], Charging Pump Suction from VCT
     .       [2SWS*SOV130A and B], Service Water Supply to Strainers f) As a result of the BVPS-2 IST Basis Document review, Primary Grade Water to Boric Acid Blender Flow Control Valve [2CHS*FCV114A] was added to the BVPS-2 IST Program to be stroked and timed quarterly in the closed direction.

g) As a result of the BVPS-2 IST Basis Document review, Charging Pump Suction from VCT [2CHS*LCV115B and D) will be stroked and timed in both the open and closed directions. They have always been stroked in both directions, but only timed in the open direction. 1 h) As a result of the BVPS-2 IST Basis Document review, a fail-safe test to the closed position was added for the RHR Letdown Flow Control Valve [2CHS*HCV142]. Although this valve is stroked and timed quarterly in the closed direction, the fail-safe test can only be performed during refueling outages as discussed later in VROJ50. O i) As a result of the BVPS-2 IST Basis Document review, Charging Pump V Miniflow Isolation Valves [2CHS*MOV275A, B and C) were deleted from the BVPS-2 IST Program because they are maintained in the open 8

l I l l ENCLOSURE 1

SUMMARY

OF CHANGES O position and are not required to change positions during an accident. Therefore, they do not perform a specific function in shutting down a , reactor to the cold shutdown condition, in maintaining the cold shutdown  ! condition or in mitigating the consequences of an accident. l j) The NSA positions for the following valves were changed or corrected from open (O) to " shut" (S): l . [2DAS*AOV100A], CNMT Sump Pumps inside CNMT Disch Isol l . [2DGS*AOV108A), Pri Drains Xfer Pumps Inside CNMT Disch Isol

        .        [2SSR*AOV102A1 and A2], RCS Cold Leg Sample CNMT Isol
        .        [2SSR*SOV128A1 and A2], RCS Hot Leg Sample CNMT Isol
        .        [2SSR*SOV129A1 and A2], RHR/CNMT Sump Sample CNMT isol l
        .        [2SWM*MOV562, 563, 564 and 565), Chlorine inj lsolation to SWS k)  As a result of the BVPS-2 IST Basis Document review, Residual Heat Removal Supply and Return Loop Isolation Valves (2RHS*MOV701 A & B,       !

702A & B, and 720A & B] will be stroked and timed in both the open and  ! closed directions. They have always been stroked in both directions, but l ! only timed in the closed direction, l !f% k 1) The NSA position for [2 SIS *41], Combined Supply Line Isolation Valve to the Sl Accumulators, [2 SIS *41), was corrected from shut (S) to " locked shut" (LS), m) As a result of the BVPS-2 IST Basis Document review, a full-stroke 1 exercise in the closed direction was deleted for Recire Spray Pump Discharge to LHSI Pump Discharge Check Valves [2 SIS *46 and 47] even though they will continue to be full-cycled open and closed using their external weighted arms. n) As a result of the BVPS-2 IST Basis Document review, a part-stroke exercise in the open direction during cold shutdown RHR Pump testing was added for SI Accumulator Discharge Check Valves to Loop B and C Cold Legs [2 SIS *141 and 145). o) As a result of the OVPS-2 IST Basis Document review, a fail-safe test to l the closed position was added for the HHSI Discharge to Cold Leg l Injection Valves [2 SIS *HCV868A and B). l l p) As a result of the BVPS-2 IST Basis Document review, a full-stroke ! exercise in the open direction was added for Containment Activity

' Radiation Monitor Return Check Valve [2CVS*93] as discussed later in 9

ENCLOSURE 1

SUMMARY

OF CHANGES A l U VROJ31. This check valve is already being full-stroke exercised in the closed direction. q) As a result of the BVPS-2 IST Basis Document review, a full-stroke l exercise in the closed direction was added for Recirc Spray Pump l Discharge Check Valves (2RSS*29,30,31 and 32]. These check valves l are already being full-stroke exercised in the open direction. i r) As a result of the BVPS-2 IST Basis Document review, the following l

           " thermal" relief valves have been added to the BVPS-2 IST Program in accordance with OM-1, to be tested per 2DVT 1.60.5 every 10 years:
           .       [2CCP*RV109), Seal Water H/X CCP Relief
           .       [2CCP*RV110], Non-Regen H/X CCP Supply Relief 6       [2CCP*RV111 A and B), Fuel Pool H/X CCP Supply Reliefs           !
           .       [2CCP*RV113A, B and C],CRDM Shroud Cooling Coil CCP Reliefs
           .       [2CCP*RV115A, B and C), Reactor Coolant Pump CCP Reliefs
           .       [2CCP*RV117], Neutron Shield Tank Cooler CCP Supply Relief
           .       [2CCP*RV118], Excess Letdown H/X CCP Supply Relief
           .       [2CCP*RV119A and B], RHR H/X CCP Return Reliefs
           .       [2CCP*RV136A and B], RHR Seal Cooler CCP Supply Reliefs
           .       [2CCP*RV139B, D-L), CNMT Penetration Cooling Coil CCP Reliefs
           .       [2FWE*RV102], Emergency Service Water Supply Relief
           .       [2SWS*RV101 A, B, C and D], Recire Spray H/X SWS Inlet Reliefs
           .       [2SWS*RV102A, B and C), Comp Cooling Water H/X SWS Reliefs s)    As a result of the BVPS-2 IST Basis Document review, Primary Component Cooling Water Containment Isolation Valves

[2CCP*MOV150-1,-2], [2CCP*MOV151-1,-2], [2CCP*MOV156-1,-2] and [2CCP*MOV157-1,-2] will be stroked and timed in both the open and closed directions. They have always been stroked in both directions, but only timed in the closed direction. t) The NSA positions for CCP Surge Tank Surge Line Isolation to CCP Pump Suction Valves [2CCP*321, 322, 323 and 326], were corrected from open (O) to " locked open" (LO). u) As a result of the BVPS-2 IST Basis Document review, a fail-safe test to i the closed position was added for the Main Steam isolation Valves I (MSIV's) [2 MSS *AOV101 A, B and C) as recommended by NUREG-1482, Section 4.2.4, " Main Steam isolation Valves" f 10

ENCLOSURE 1

SUMMARY

OF CHANGES f} v) As a result of a change to the Containment Penetrations Table (Rev.4) which now recognizes that the downstream SOV's in the steam supply line to the Turbine-Driven Auxiliary Feedwater Pump (TDAFWP) may be used as the contain-ant isolation valves, TDAFWP Steamline Isolation Valves [2 MSS *SOU 05D, E and F] will be stroked and timed in both the i open and closed d mctions. They have always been stroked in both l directions, but on( imed in the open direction. w) As a result of the BVPS-2 IST Basis Dcaument review, a fail-safe test to l the closed position was added for the M ain and Bypass Feedwater l Regulating Valves (2FWS*FCV478,479 488,489,498 and 499]. In addition, the NSA position for the Bypass Feedwater Regulating Valves i [2FWS*FCV479, 489 and 499] was changed from throttled (T) to " shut" (S). Therefore, these valves are now required to be stroked, timed and failed closed each quarter rather than during cold shutdowns. l 1 x) Clarified that the following valves are only required to be exercised  ; quarterly per OM-10, even though they may be exercised more often (i.e., ) per technical specifications or with some other testing): j p V [2FWE*90,91 and 92], AFW Pump Supply from Service Water [2FWE*FCV122,123A and B), AFW Pump Discharge Check /FCV's  !

       .       [2SWS*111 and 112], Dier 21 Generator H/X Supply Hdr Checks
       .       [2EGF*7,8,9 and 10], EDG Fuel Oil Transfer Pump Disch Checks y)  As a result of the BVPS-2 IST Basis Document review, Recire Spray H/X Service Water Supply Header Isolation Valves [2SWS*MOV103A and B]

will be stroked and timed in both the open and closed directions. They have al ways been stroked in both directions, but only timed in the open direction. z) The NSA positions for Recirc Spray H/X Cooling Water Discharge Valves [2SWS*MOV105A-D] were corrected to "open in a throttled position" O(T). aa) As a result of the BVPS-2 IST Basis Document review, Component Cooling Water H/X Service Water Supply Header Isolation Valves (2SWS*MOV106A and B] will be stroked and timed in both the open and closed directions. They have always been stroked in both directions, but only timed in the closed direction. bb) As a result of the BVPS-2 IST Basis Document review, a full-stroke p exercise in the open direction was deleted for these Fire Protection Containment Isolation Check Valves [2FPW*382, 388, 753 and 761], (~) even though they will continue to be full-cycled open and closed using i1

i l ! ENCLOSURE 1 l

SUMMARY

OF CHANGES (3 their external weighted arms. l l 9) The following are changes to Sections IX and X of the BVPS-2 IST Program for

        " Valve Cold Shutdown Justifications" and " Valve Refueling Outage Justifications" (new section).

a) The majority of the new Valve Cold Shutdown Justifications (VCSJ's) and Refueling Outage Justifications (VROJ's) were converted from the existing Cold Shutdown Justifications or Relief Requests in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16). Specific references to OM-10, Generic Letter No. 89-04 and/or NUREG-1482 were l added to all of the VCSJ's and VROJ's with additional basis added as  ! appropriate. In addition, the applicable " system number and description" and any " references" were also added. I b) In addition, the following " existing" Cold Shutdown Justifications (CSJ's) and Relief Requests (RR's) were deleted for the following reasons:

                . CSJ56        [2FWS*FCV479,489 and 499] can now be tested quarterly due to an NSA change to shut (S). Therefore, this CSJ is no

(~N longer required. O

                . RR1          OM-10, Paragraph 4.2.2.2, " Containment isolation Valves,"   !

allows containment isolation valves to be tested in i accordance with the 10CFR50 Appendix J (Option B) Program. Therefore, this relief request is no longer required.

                . RR2          Was previously deleted.
  • RR30 OM-10, Paragraph 4.2.1.8(e) has specific instructions for
                               " rapid acting valves," therefore, this relief request is no longer required.
                . RR23,24,25,26,27,28,31,32 and 33 - OM-10, Paragraph 4.2.2.3(e),
                               " Analysis of Leakage Rates," allows assigning a maximum permissible leakage rate for the entire penetration.

Therefore, these relief requests are and no longer required. c) The following is a brief description of changes or the basis for changes made to each VCSJ and VROJ from previous Cold Shutdown Justifications (CSJ's) or Relief Requests (RR's) from the current revision l -Q of the BVPS-2 IST Program (Issue 1, Rev.16). 12

ENCLOSURE 1

SUMMARY

OF CHANGES q\ New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VCSJ1 CSJ1 2RCS*68 This check valve is located inside containment and is not accessible for cycling using it's weight arms during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). VCSJ2 CSJ2 2RCS*72 This check valve is located inside containment and is not accessible for cycling using it's weight arms during plant operation. Deferring testing to CSD is permitted by OM-

10. Paragraph 4.3.2.2(c).

VCSJ3 CSJ4 2RCS*PCV455C The PORV's have a high probability of sticking open. 2RCS*PCV455D NUREG-1482. Section 4.4.1 does not recommend testing 2RCS*PCV456 them during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ4 CSJ7 2CHS*84 Check valve exercising during plant operation would 2CHS*136 result in injection of boric acid solution into the RCS 2CHS*141 causing an undesirable negative reactivity addition and a subsequent power reduction. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c) VCSJS CSJ18 2RHS*3 These check valves can only be tested with the RHR 2RHS*4 Pumps which are not tested during plant operation.

 ,- 3                                     Deferring testing to CSD is permitted by OM-10,

( V) VCSJ6 CSJ19 2RHS*FCV605A Paragraph 4.3.2.2(c). These valves are located inside containment and are not 2RHS*FCV605B accessible for testing by local observation during plant operation. Defening testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ7 CSJ20 2RHS*MOV701A,B These valves are interiocked closed during plant 2RHS*MOV702A,B operation to prevent overpressurization of RHS piping 2RHS*MOV720A,B from higher pressure RCS. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.12(c). VCSJ8 CSJ21 2RHS*HCV758A These valves are located inside containment and are not 2RHS*HCV758B accessible for testing by local observation during plant operation. Deferring testing to CSD is permitted by OM-

10. Paragraph 4.2.1.2(c).

VCSJ9 CSJ59 2 SIS *MOV865A NUREG-1482, Section 3.1.1 does not recommend testing 2 SIS *MOV865B these valves during plant operation since they could fail in 2 SIS *MOV865C a non-conservative position and cause a loss of system function. Deferring testing to CSD is permitted by OM-10,

Paragraph 4.2.1.2(c).

I VCSJ10 CSJ52 2CVS*SOV102 Must enter Tech Spec action for CNMT Airbome Activity Radiation Monitor, and with failure of the valve to reopen, would result in a plant shutdown per Tech Specs. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ11 CSJ52 2CVS*SOV153A Must enter Tech Spec action for CNMT Airbome Activity 2CVS*SOV1538 Radiation Monitor, and with failure of the valve to reopen, g would result in a plant shutdown per Tech Specs. ( Deferring testing to CSD is permitted by OM-10, N Paragraph 4.2.1.2(c). l 13 l l

i l ENCLOSURE 1

SUMMARY

OF CHANGES I ( (N) v .- New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Edef Descripio. 000R Jasis for Changes VROJ's Requests VCSJ12 CSJ29 2QSS*SOV100A ail[ro of . We a nr..^19se wouii divert NaOH injection 2OSS*SOV100B  : Now '.way Ovn tiw h ch Spmy Pumps following a CIB P- rm ang W Chucd 'njection System inoperable.

                                          ! D wng te "a b C ~O N : ennitted by OM-10, VCSJ13  CSJ34                                  .               Esk. es cycling 2QSS*EI 2OSS90t       ~ l ;2~ % S J.400A u ' SJ m.:h M only be don CS7 cw. . " .0SJ V (@ ' i "ferrQ testing to CSD is 1 yrynggd Dy 0% W%g,142.2(c).

VCSJ14 CSJ31 2RSS*29 i Me @m PMs R Y %d inside containment and 2RSS*30 > m ecess de: 4 , 3 to ;ineir weight arms 2RSS*31 l0 m9 . owan J mning 4%; to CSD is 2RSS*32 , rm 9; r y 04 K Hngg, 3.4, 3 2.2(c). VCSJ15 CSJ54 2CCP*27A j Oki , .; a ce vaives wring p,% m.,eration would 2CCP*278 . &C 'x caolina , uns ^s Pain A/B cooling loads 2CCP*354 reu.iting m :,1 u3 mali

  • ansi # and Wtential plant trip.

2CCP*355 Defernrg wsting to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ16 CSJ12 2 MSS *18 These check valves can only be full-stroke exercised 2 MSS *19 open during full flow testing of the Turbine-Driven (~^j 2 MSS *20 Auxiliary Feedwater Pump, which can only be full flow 2 MSS *196 tested during CSD's to prevent thermal shock to the 2 MSS *199 Steam Generators. Deferring full-stroke testing to CSD is 2 MSS *352 permitted by OM-10, Paragraph 4.3.2.2(b). VCSJ17 CSJ35 2 MSS *AOV101 A The MSIV's cannot be full-stroke exercised closed during 2 MSS *AOV101B plant operation without causing a reactor trip. Deferring 2 MSS *AOV101C full-stroke testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(b). VCSJ18 CSJ36 2SVS*80 in order to exercise these check valves during plant l 2SVS*81 operation, a reduction in power would be required to l 2SVS*82 prevent exceeding full powerlimitations. Deferring ' testing to CSD is permitted by OM-10, Para. 4.3.2.2(c). VCSJ19 CSJ37 2SVS*PCV101 A Exercising these valves during plant operation could 2SVS*PCV101 B cause a reactor powertransient. Isolation of manual 2SVS*PCV101C isolation valves is not practical. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c) VCSJ20 CSJ38 2SVS*HCV104 Exercising these valves during plant operation could cause a reactor power transient. Isolation of manual isolation valves is not practical. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c) VCSJ21 CSJ39 2FWS*HYV157A Exercising these valves during plant operation would 2FWS*HYV1578 isolate feedwater flow to the Steam Generators and result i 2FWS*HYV157C in a plant trip. Defening testing to CSD is permitted by ! OM-10. Paragraph 4.2.1.2(c). l VCSJ22 CSJ55 2FWS*FCV478 Exercising these valves during plant operation would

Q l

A) 2FWS*FCV488 2FWS*FCV498 isolate feedwater flow to the Steam Generators and result in a plant trip. Deferring testing to CSD is permitted by ! OM-10. Paragraph 4.2.1.2(c). 14

ENCLOSURE 1

SUMMARY

OF CHANGES O b New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VCSJ23 CSJ40 2FWE*42A,B Exercising these check valves cannot be performed 2FWE*43A,B during plant operation because this would inject cold 2FWE*44A,8 water and thermal shock the Steam Generators. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). VCSJ24 CSJ41 2FWE*99 Exercising these check valves cannot be performed 2FWE*100 during plant operation because this would inject cold 2FWE*101 water and thermal shock the Steam Generators. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). VCSJ25 CSJ42 2FWE*FCV122 Exercising these FCV/ check valves cannot be performed 2FWE*FCV123A during plant operation because this would inject cold 2FWE*FCV123B water and thermal shock the Steam Generators. Deferring testing to CSD is permitted by OM-10, Paragraphs 4.2.1.2(c) and 4.3.2.2(c). VCSJ26 CSJ43 2SWS*S7 These check valves will be tested quarterly unless one 2SWS*58 Sewice Water Pump is OOS for maintenance, then 2SWS*59 testing cannot be performed until the OOS pump is retumed to service, but at least at CSD. This is permitted by OM-10, Paragraph 4.3.2.2(c). O

 \

VCSJ27 CSJ44 2SWS*MOV102A These valves will be testad quarterly unless one Service 2SWS*MOV102B Water Pump is OOS for maintenance, then testing cannot 2SWS*MOV102C1 be performed until the OOS pump is retumed to service, 2SWS*MOV102C2 but at least at CSD, This is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ28 CSJ47 2SWS*MOV107A Exercising these valves during plant operation would 2SWS*MOV1078 interrupt flow of cooling water to Train A/B cooling loads 2SWS*MOV107C resulting in undesirable thermal transients, operational 2SWS*MOV107D concems or stability problems and a potential plant trip. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). VCSJ29 CSJ48 2SWS*486 These check valves will be tested quarterly unless one 2SWS*487 Service Water Pump is OOS for maintenance, then 2SWS*488 testing cannot be performed until the OOS pump is retumed to service, but at least at CSD. This is permitted by OM-10, Paragraph 4.3.2.2(c). VCSJ30 CSJ49 2FPW*382 These check valves are located inside containment and 2FPW*388 are not accessible for cycling using their weight arms 2FPW*753 during plant operation. Deferring testing to CSD is 2FPW*761 permitted by OM-10, Paragraph 4.3.2.2(c). l VCSJ31 CSJ51 f.MVR* MOD 23A These MOD's are required to be locked shut during plant ! 2HVR* MOD 23B operation per Tech Specs and cannot be cycled. I 2HVR* MOD 25A Deferring testing to CSD is permitted by OM-10, 2HVR* MOD 25B Paragraph 4.2.1.2(c). k I 15

j

ENCLOSURE 1

SUMMARY

OF CHANGES

New Existing i VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes

! VROJ's Requests , VCSJ32 N/A 2CHS*HCV142 This is a new CSJ added for fail-safe testing this valve l ! during cold shutdowns. Fail-safe testing during plant  ; i operation is not possible since a local observation is  ; l required and the valve is located inside containment. } Deferring testing to CSD is permitted by OM-10, , Paragraph 4.2.1.2(c).

XXXXXX XXXXXX XXXXXXXXXXXXXX VROJ1 RR29 2RCS*SOV200A,B Conditions necessary for testing these valves will not i 2RCS*SOV201A,8 support cycling during plant operation and may not be i 2RCS*HCV250A,B obtainable during each CSD which could delay plant s

startup. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.1. i VROJ2 RR3 2CHS*22 The Charging Pumps will not develop the required flow to 2CHS*23 full-stroke exercise these check valves during plant 2CHS*24 operation. Exercising during CSD could result in low-temperature overpressurization of the RCS. Defening testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ3 CSJ5 2CHS*31 This check valve is located inside containment and is not accessible for cycling using it's weight arm during plant i operation. Defening testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. VROJ4 CSJ6 2CHS*LCV115C Exercising these suction valves during plant operation 2CHS*LCV115E could damage a Charging Pump or affect normal charging system functions. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. VROJS CSJ8 2CHS*AOV204 Exercising this valve during plant operation could result in a thermal shock to the Regen H/X. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482. Section 3.1.1.4. VROJ6 CSJ9 2CHS*MOV289 Exercising this valve during plant operation could result in a thermal shock to the Regen H/X. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP cperation. Deferring O testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482. Section 3.1.1.4. 16

__ _ ._ _ _ _ _ . _ _ _ ~. . _ . _ . _ . ._ .. l l ENCLOSURE 1  !

SUMMARY

OF CHANGES I O New Existing l VCSJ's CSJ's or Valve Nurnber(s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VROJ7 CSJ10 2CHS*MOV308A Exercising these valves during plant operation could 2CHS*MOV308B result in damage to the RCP seals. Deferring testing to 4 2CHS*MOV308C CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring l testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. VROJ8 CSJ11 2CHS*MOV310 Exercising this valve during plant operation could result in a thermal shock to the Regen H/X. Deferring testing to CSD is permitted by OM 10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the j charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. VROJ9 CSJ13 2CHS*MOV378 Exercising these valves during plant operation could 2CHS*MOV381 result in damage to the RCP seals. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, O) ( VROJ10 CSJ14 2CHS*LCV460A Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. Exercising these valves during plant operation could 2CHS*LCV460B result in a thermal shock to the Regen H/X. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. VROJ11 CSJ15 2CHS*473 This check valve is located inside containment and is not accessible for cycling using it's weight arm during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. VROJ12 CSJ16 2CHS*474 These check valves are located inside containment and 2CHS*475 are not accessible for cycling using their weight arms l 2CHS*476 during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482. Section 3.1.1.4. O I i 17 l

ENCLOSURE 1

SUMMARY

OF CHANGES n O New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes { VROJ's Requests VROJ13 CSJ17 2CHS*MOV8130A B Exercising these suction and discharge valves during 2CHS*MOV8131 A,B plant operation could damage a Charging Pump or affect 2CHS*MOV8132A,B normal charging system functions. Deferring testing to 2CHS* MOB 8133A,B CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, l Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. i VROJ14 RR4 2 SIS *6 The LHSI Pumps will not develop enough head to 2 SIS *7 ovorcome RCS pressure for exercising these check valves during plant operation. Exercising during CSD requires injection to the RCS where there is not sufficient volume to receive the additional inventory. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ15 RR5 2 SIS *27 The Charging Pumps will not develop the required flow to , full-stroke exercise these check valves open during plant j operation. Exercising during CSD could result in low- l temperature overpressurization of the RCS. In addition, q n NUREG-1482, Section 4.1.4 permits leakage testing to i verify check valve closure during refueling outages. f -} Deferring testing to refueling outages is permitted by OM- l 10, Paragraph 4.3.2.2(e). { VROJ16 CSJ22 2 SIS *42 This check valve is located inside containment and is not accessible for cycling using it's weight ami during plant operation. Deferring testing to CSD is permitted by OM- . 10 Paragraph 4.3.2.2(c). Due to possible backleakage l through adjacent MOV's if the Accumulators are still pressurized, exercising during CSD could delay plant startup in order to set up proper test conditions for bleeding off trapped pressure. Deferring testing to I refueling outages is permitted by OM-10, Paragraph I 4.3.2.2(e) and NUREG-1482, Section 3.1.1.1. VROJ17 CSJ53 2 SIS *46 Exercising the weight arms of these check valves againsI 2 SIS *47 the head of water created by the RWST is not recommended. The amount of potentially contaminated l water required to be drained from the system in order to i bleed off pressure would create additionalliquid waste for disposal which is not practical during plant operation or during CSD. Deferring testing to refueling outages is permitted by OM-10. Paragraph 4.3.2.2(e). l l l O h l 18

ENCLOSURE 1

SUMMARY

OF CHANGES O New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VROJ18 CSJ23 2 SIS *83 These check valves are located inside containment and 2 SIS *84 are not accessible for cychng using their weight arms 2 SIS *94 during plant operation. Deferring testing to CSD is 2 SIS *05 permitted by OM-10, Paragraph 4.3.2.2(c), Due to possible backleakage through adjacent check valves if the RCS is still pressurized, exercising during CSD could delay plant startup in order to set up proper test conditions for bleeding off trapped pressure. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.1. VROJ19 RR6 2 SIS *107 The LHSI Pumps will not develop enough head to 2 SIS *108 overcome RCS pressure for exercising these check 2 SIS *109 valves during plant operation. Exercising during CSD requires injection to the RCS where there is not sufficient volume to receive the additionalinventory. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ20 RR7 2 SIS *122 The Charging Pumps will not develop the required flow to 2 SIS *123 full-stroke exercise these check valves during plant 2 SIS *124 operation. Exercising during CSD could result in low-O d 2 SIS *125 2 SIS *126 temperature overpressurization of the RCS. Deferring testing to refueling outages is permitted by OM-10, 2 SIS *127 Paragraph 4.3.2.2(e). VROJ21 RR8 2 SIS *128 The LHSI Pumps will not develop enough head to 2 SIS *129 overcome RCS pressure for exercising these check valves during plant operation. Exercising during CSD requires injection to the RCS where there is not sufficient volume to receive the additionalinventory. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). l VROJ22 CSJ24 2 SIS *130 This check valve is located inside containment and is not accessible for cycling using it's weight arm during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). Due to possible backleakage through adjacent check valves if the RCS is still pressurized, exercising during CSD could delay plant l startup in order to set up proper test conditions for l bleeding off trapped pressure. Deferring testing to l refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482. Section 3.1.1.1. i io 19

ENCLOSURE 1 l l

SUMMARY

OF CHANGES l !A I g New Existing VCSJ's CSJ's or Valve Number (s) l and, Relief Brief Description of OR Basis for Changes l VROJ's Requests , VROJ23 CSJ24 2 SIS *132 This check valve is located inside containment and is not ! 2 SIS *133 accessible for cycling using it's weight arm during plant ! operation. Deferring testing to CSD is permitted by OM- 1 ! 10, Paragraph 4.3.2.2(c). Due to possible backleakage  ; through adjacent check valves if the RCS is still  ! pressurized, exercising during CSD could delay plant  ! startup in order to set up proper test conditions for I bleeding off trapped pressure. Deferring testing to i l refueling outages is permitted by OM-10, Paragraph 4.3 2.2(e) and NUREG-1482, Section 3.1.1.1. VROJ24 RR9 2 SIS *134 The LHSI Pumps will not develop enough head to 2 SIS *135 overcome RCS pressure for exercising these check 2 SIS *136 valves during plant operation. Exercising during CSD 2 SIS *137 requires injection to the RCS where there is not sufficient 2 SIS *138 volume to receive the additional inventory. Deferring 2 SIS *139 testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ25 RR11 2 SIS *545 The LHSI Pumps will not develop enough head to 2 SIS *S46 overcome RCS pressure for exercising these check g valves during plant operation. Exercising during CSD J requires injection to the RCS where there is not sufficient volume to receive the addrtionalinventory. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ26 RR11 2 SIS *547 The Charging Pumps will not develop the required flow to full-stroke exercise these check valves during plant . operation. Exercising during CSD could result in low- l temperature overpressurization of the RCS. Deferring testing to refueling outages is permitted by OM 10, Paragraph 4.3.2.2(e). i l VROJ27 RR12 2 SIS *548 The LHSI Pumps will not develop enough head to 2 SIS *S50 overcome RCS pressure for exercising these check 2 SIS *552 valves during plant operation. Exercising during CSD requires injection to the RCS where there is not sufficient volume to receive the additionalinventory. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ28 CSJ25 2 SIS *MOV836 Exercising this valve during plant operation could result in a thermal shock to the RCS cold legs. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NLREG-1482. Section 3.1.1.4. 20

ENCLOSURE 1

SUMMARY

OF CHANGES A V New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VROJ29 CSJ26 2 SIS *MOV869A Exercising these valves during plant operation could 2 SIS *MOV869B result in a thermal shock to the RCS cold legs. Deferring testing to CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD cannot be performed if the charging system is supporting RCP operation. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. VROJ30 CSJ27 2 SIS *MOV8889 Failure of this valve in the open position during cycling during plant operation could result in overpressuritation of the low pressure LHSI piping if downstream check valves are leaking. Deferring testing to CSD is permitted by OM-10 Paragraph 4.3.2.2(c). This same condition could still exist during CSD if the RCS is still pressurized, therefore, exercising during CSD could delay plant startup in order to set up proper RCS conditions (pressure) to prevent overpressurizing the LHSI piping. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.1. (3 k) VROJ31 RR13 2CVS*93 Check valve closure can only be verified by leakage testing which is permitted by NUREG-1482, Section 4.1.4 to be performed during refueling outages. Deferring testing to refueling outages is permitted by OM-10, Paranraph 4.2.1.2(e). VROJ32 CSJ28 2QSS*3 These check valves are located inside containment and 2QSS*4 are not accessible for cycling using their weight arms during plant operation. Exercising the weight arms of these check valves against the head of water created by equalization of level with the RWST is not recommended. The amount of potentially contaminated water required to be drained from the system in order to bleed off pressure would create additional liquid waste for disposal which is not practical during CSD. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). VROJ33 CSJ57 2OSS*MOV102A Exercising these valves during plant operation or during 2OSS*MOV1028 CSD requires flushing NaOH solution out of downstream piping. This creates additionalliquid waste for disposal l which is not practical and could also delay plant startup l from CSD. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG- ! 1482, Section 3.1.1.1. l VROJ34 CSJ30 2OSS*267 This check valve is located inside containment and is not accessible for cycling using it's weight arm during plant operation. Because scaffolding needs erected to gain access to this check valve, it is not practical to perform n during CSD since this could delay plant startup. Deferring ( testing to refueling outages is permitted by OM-10, k Paragraph 4.3.2.2(e) and NUREG-1482. Section 3.1.1.1. 21 l l

ENCLOSURE 1

SUMMARY

OF CHANGES O New Existing VCSJ's CSJ's or Valve Number (s) j and, Relief Brief Description of OR Basis for Changes VROJ's Requests VROJ35 CSJ58 2CCP*4 Full-stroke exercising these check valves during plant 2CCP*5 operation requires entry into containment (which is not 2CCP*6 accessible), to provide additional flow through the RHR H/X's. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). During CSD, additional CCP cooling to the RHR H/X's could reduce RCS temperature below required RCP operational requirements. Deferring l testing to refueling outages is permitted by OM-10, Paragrapn 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4. ( VROJ36 CSJ32 2CCP*AOV107A Exercising these valves during plant operation could 2CCP*AOV1078 result in damage to the RCP seats. Deferring testing to 2CCP*AOV107C CSD is permitted by OM-10, Paragraph 4.2.1.2(c). Exercising during CSD also cannot be performed if the RCP's are operating. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. VROJ37 CSJ33 2CCP*MOV150-1,2 Exercising these valves during plant operation could 2CCP*MOV151-1,2 result in damage to the RCP seals. Deferring testing to 2CCP*MOV156-1,2 CSD is permitted by OM-10, Paragraph 4.2.1.2(c). 2CCP*MOV157-1,2 Exercising during CSD also cannot be performed if the O RCP's are operating. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.4. VROJ38 RR14 2CCP*289 Check valve closure can only be verified by leakage 2CCP*290 testing which is permitted by NUREG-1482, Section 4.1.4 2CCP*291 to be performed during refueling outages. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). VROJ39 RR15 2CCP*352 Check valve closure can only be verified by leakage testing which is permitted by NUREG-1482, Section 4.1.4 l to be performed during refueling outages. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). VROJ40 RR16 2 MSS *18 Check valve closure can only be verified by leakage 2 MSS *19 testing which is permitted by NUREG-1482, Section 4.1.4 2 MSS *20 to be performed during refueling outages. Deferring i 2 MSS *196 testing to refueling outages is permitted by OM-10, 2 MSS *199 Paragraph 4.2.1.2(e). 2 MSS *352 . VROJ41 RR17 2SVS*80 Check valve closure can only be verified by leakage 2SVS*81 testing which is permitted by NUREG-1482, Se : tion 4.1.4 i 2SVS*82 to be performed during refueling outages. Deferring i ! testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). O 22

l ENCLOSURE 1

SUMMARY

OF CHANGES t")

 'V New   Existing VCSJ's CSJ's or Valve Number (s) and,   Relief                       Brief Description of OR Basis for Changes VROJ's Requests VROJ42   RR18        2FWS*28      Check valve closure can only be verified by leakage 2FWS*29     testing which is permitted by NUREG-1482, Section 4.1.4 1

2FWS*30 to be performed during refueling outages. Defening i testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). VROJ43 RR19 2FWE*09 Check valve closure can only be verified by leakage 2FWE*100 testing which is permitted by NUREG-1482, Section 4.1.4 2FWE*101 to be performed during refueling outages. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). l VROJ44 CSJ3 2SWS*S7 Full-stroke exercising these check valves during plant 2SWS*58 operation or during CSD requires additional H/X's to be 2SWS*59 placed into service which are maintained clean and in reserve, or isolated for biota control to prevent fouling. Placing them into service could cause fouling which could reduce reliability in meeting required flows during an accident, or delay plant startup if in CSD. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.1.

      """     ""      '***       """~"****"*'"***'"*'*"*'"**"*"""""

(j~' 2SWS*107 plant operation or during CSD requires additional H/X's to be placed into service which are maintained clean and in reserve, or isolated for biota control to prevent fouling. Placing them into service could cause fouling which could reduce reliabil:ty in meeting required flows during an accident, or delay plant startup if in CSD. Closure testing requires all Service Water Pumps to be shutdown and the headers cross-connected which cannot be done during plant operation, or during CSD (to support diesel operability). Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 3.1.1.1. VROJ46 RR20 2SWS*MOV103A A plant shutdown would be required if the valves failed to 2SWS*MOV1033 re-close during testing because the SWS system cannot simultaneously support normal plant operations and full flow to the RSS H/X's. Stroking during CSD also places flow through the RSS H/X's which are maintained isolated for biota control to prevent fouling. Placing them into service could cause fouling which could reduce reliability in meeting required flows during an accident, or delay l plant startup if in CSD. Deferring testing to refueling l outages is permitted by OM-10, Paragraph 4.2.1.2(e) and I NUREG-1482. Section 3.1.1.1.

 /%

V) 5 i 23 l

ENCLOSURE 1

SUMMARY

OF CHANGES O v New Existing VCSJ's CSJ's or Valve Number (s) and, Relief Brief Description of OR Basis for Changes VROJ's Requests VROJ47 CSJ46 2SWS*MOV106A Failure of these valves to re-open while exercising during 2SWS*MOV106B plant operation or during RCP operation during CSD would cause thermal transients in the SWS and CCP systems which could ultimately affect RCP operation and require the RCP's to be shutdown. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e) and NUREG-1482, Section 3.1.1.4.. VROJ48 RR21 2SWS*1103 Check valve closure can only be verified by leakage 2SWS*1104 testing which is permitted by NUREG-1482, Section 4.1.4 to be performed during refueling outages. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.2.1.2(e). VROJ49 CSJ50 21AC*22 This check valve is located inside containmer;t and is not accessible for cycling using it's weight arm during plant operation. Deferring testing to CSD is permitted by OM-10, Paragraph 4.3.2.2(c). Exercising during CSD cannot be performed if the instrument air system is operatir.g. Deferring testing to refueling outages is permitted by OM-10, Paragraph 4.3.2.2(e). (O/

10) The following are changes to Section XI of the BVPS-2 IST Program " Valve Relief Requests." Note that the following relief requests require NRC approval prior to implementation.

a) Valve Relief Request No.1 (VRR1) was written to allow exercising the Safety i Injection Accumulator Discharge Check Valves [2 SIS *141,142,145,147,148 l and 151] using the Fort Calhoun test method which measures a flow coefficient value (Cv) during a blowdown at reduced accumulator pressure during refueling outages. Relief has been requested to use a similar method in accordance with the SER for the Fort Calhoun test method as permitted by NUREG-1482, Section 4.1.2, " Exercising Check Valves with Flow and Noninstrusive Techniques." In addition, deferring testing to refueling outages was also justified because exercising the Si Accumulator Discharge Check Valves [2 SIS *141,142,145, l 147,148 and 151] during plant operation is not possible since the RCS is at a l greater pressure than the Sl Accumulators. Cold shutdown (CSD) testing is also not possible because of a lack of installed instrumentation and an uncontrolled t est volume change if the SI Accumulator discharge MOV isolation valves are r,pened at low RCS pressure. Therefore, deferring testing to refueling outages m is permitted by OM-10, Paragraph 4.3.2.2(e) and NUREG-1482, Section 4.1.2. h This VRR is RR10 in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16). l l 24 l l l

ENCLOSURE 1

SUMMARY

OF CHANGES

 ,(]

b) Valve Relief Request No. 2 (VRR2) was written because the Diesel Air Start SOV's (2EGF*SOV202-1,202-2,203-1 and 203-2] are quick acting and do not have position indication, therefore, they cannot be timed directly. Relief has been requested to monitor operation of these valves by timing the starting time to rated speed of each Emergency Diesel Generator in accordance with NUREG-1482, Section 4.2.8, " Solenoid-Operated Valves." This VRR is RR22 in the current revision of the BVPS-2 IST Program (Issue 1, Rev.16). O O 25

1 i !O i ! i

1 1

l ENCLOSURE 2 ( l 2nd Ten-Year Interval Update of the i O Beaver Valley Power Station, Unit No. 2 Inservice Testina (IST) Proaram for Pumps and Valves O

 . . _ - . _ . _ . .         --. .  .- _-._. -_ .._-.- - -. -                  . - --.   .-....-. _  __,_ - .=_-._.- -.-.

l l !O DUQUESNE LIGHT COMPANY ' 4 Beaver Valley Power Station 4 i Unit 2 i t 3 a INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES j lO j lasue 2 Revision 0 PagesIssued OSC Review Date Effective Date

                      $ fha Manager, System and Performance 54, 99     2-y           BV-ose.-17-47                ,,j,,jyy Date
                                                                          /- 277             Y[Jd[97 Engineeringepartment Review General Manager,
                                               #               $97 Nuclear Operations Approval                  Date O
    - -   .     . . _ . - . _ _ .   . ..        -. _-                     --- --     . . - . . . - _ . . .       .         .. .~.

Barvar Vallsy Powsr Station Unit 2 issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page i O l V List of Effective Paaes Page Revision Page Revision i 0 40 0 li 0 41 0 I lil 0 42 0 l iv 0 43 0 i v 0 44 0 i 1 0 45 0 . 2 0 46 0 3 0 47 0 4 0 48 0 5 0 49 0 l 6 0 50 0 l 7 0 51 0 l 8 0 52 0 9 0 53 0 10 0 M 0 11 0 55 0 12 0 56 0 i 13 0 57 0 14 0 58 0 lp 15 16 0 0 59 60 0 0 17 0 61 0 18 0 62 0 19 0 63 0 l 20 0 64 0 21 0 65 0 22 0 66 0 23 0 67 0 24 0 68 0 25 0 69 0 26 0 70 0 27 0 71 0 , 28 0 72 0 1 29 0 73 0 l l 30 0 74 0 31 0 75 0 l 32 0 76 0 l l 33 0 77 0 l l 34 0 78 0 1 35 0 79 0 36 0 80 0 ! 37 0 81 0 38 0 82 0 39 0 l

l i Baavsr Vellsy Powsr Station Unit 2 Issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page il List of EWective Paces (Continued) Page Revision Page Revision 83 0 126 0 84 0 127 0 85 0 128 0 l 86 0 129 0 87 0 130 0 88 0 131 0 89 0 132 0 90 0' 133 0 91 0 134 0 i 92 0 135 0 l 93 0 136 0 94 0 137 0 95 0 138 0 96 0 139 0 97 0 140 0 98 0 141 0 99 0 142 0 - 100 0 143 0 101 0 144 0 m, 102 0 145 0 lQ 103 104 0 0 146 147 0 0 105 0 148 0 106 0 149 0 107 0 150 0 108 0 151 0-109 0 152 0 110 0 153 0 l 111 0 154 0 112 0 155 0 113 0 156 0 114 0 157 0 l l 115 0 158 0 ) l 116 0 159 0 ' l 117 0 160 0 118 0 161 0 119 0 162 0 120 0 163 0 121 0 164 0 l 122 0 165 0 ! 123 0 166 0 124 0 167 0 4 125 0 168 0 o \ l

      . . . _ . . ..         -   . . . . . . - . . . . . - . - . _ . . - - . . . = . - . . - . - . _ . - . - . - . - - - - .      .     .     -     -- ..

Batvar Vallsy Powtr Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page lii

  %J                                                               List of EWective Paces (Continued)

Page Revision Page Revision l 169 0 212 0 170 0 213 0 171 0 214 0 ! 172 0 215 0 l 173 0 216 0 l 174 0 217 0 ! 175 0 218 0 176 0 219 0 177 0 220 0 178 0 221 0 179 0 222 0 180 0 223 0 181 0 224 0 182 0 225 0 183 0 226 0 184 0 227 0 185 0 228 0 i 186 0 229 0 187 0 230 0 0 188 189 190 0 0 0 231 232 233 0 0 0 i 191 0 234 0 192 0 235 0

                                                                                                                                                           )

1 193 0 236 0 1 194 0 237 0 195 0 238 0 196 0 239 0 197 0 240 0 198 0 241 0 199 0 242 0 200 0 243 0 201 0 244 0 202 0 245 0 203 0 246 0 204 0 247 0 205 0 248 0 206 0 249 0 207 0 250 0 l 208 0 251 0 l 209 0 252 0 210 0 253 0 211 0 254 0 l l

_._.___.___._._.___...___.-...__.-_._..._._--.-._.-_._._.._._.._.m..____. P l l Baavar Vallsy Powar Station Unit 2 Issue 2 l Revision 0 i . INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page iv List of EWective Paces (Continued) Page Revision Page Revision 255 0 256 0 257 0 258 0. 259 0 260 0 261 0 262 0 263 0  ; 264 0 l 265 0 266 0 267 0 268 0 269 0 270 0 271 0 ., ,- 272 'O 273 0 0 274 275 276 0 0 0 277 0 278 0 279 0 i LO  !

  . . _ . _ _ . ..          _ _ _ _ _ _ _ . _ _ . _            _ _ . _ _ - _ . . . . . _ _ _ . _ . -__           _ _ . . . _ _ _ _ _ _ . ~                    _ . _ . . . _ _ .

l I , Beaver Valley Powsr Statipn Unit 2 issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page v  ; l v TABLE OF CONTENTS SECTION I PUMP TESTING REQUIREMENTS 1 SECTION 11 PUMP OUTLINES 7 l- SECTION 111 PUMP COLD SHUTDOWN JUSTIFICATIONS 38 SECTION IV PUMP REFUELING OUTAGE JUSTlFICATIONS 40 SECTION V PUMP RELIEF REQUESTS 42 SECTION VI PUMP MINIMUM OPER ATING POINT (MOP) CURVES 54 SECTION Vil VALVE TESTING REQUIREMENTS 83 SECTION Vill VALVE OUTLINES 93 SECTION IX VALVE COLD SHUTDOWN JUSTIFICATIONS 166 , 1 I l' SECTION X VALVE REFUELING OUTAGE JUSTIFICATIONS 202 { SECTION XI VALVE RELIEF REQUESTS 276 f j l

                                                                                                                                                                                 )

I 1 iO

                   , .                               - - , . ,                _ - - - ,                     -- -        - . - - . - - - ~ . - , -

l l Beaver Valley Powsr Station Unit 2 Issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 1 of 279 l f SECTION 1: PUMP TESTING REQUIREMENTS l l l I 1 l l l n U l I l L .

1 Bsavsr Vallsy Powsr Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 2 of 279 (~'s , Q The Inservice Testing (IST) Program for pumps at Beaver Valley Power Station (BVPS), Unit 2, is based on the following: j

  • American society of Mechanical Engineers (ASME)/American National Standards institute (ANSI) Operational and Maintenance (OM) Standard, Part 6, " Inservice Testing of Pumps in Light Water Reactor Power Plants" (OM-6), OMa-1988 addenda to the '

l OM-1987 edition, in accordance with the ASME Boiler and Pressure Vessel Code, Section XI,1989 edition (the Code).

  • Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing l Programs".  !
  • NUREG-1482, " Guidelines'for Inservice Testing at Nuclear Power Plants".

i The pumps included in this program are all ASME Class 1,2, or 3 centrifugal and positive l displacement pumps that are provided with an emergency power source, which are l required in shutting down a reactor to the cold shutdown condition, maintaining the cold I shutdown condition, or mitigating the consequences of an accident, at BVPS, Unit 2. The requirements of the Code and Generic Letter No. 89-04 including Supplement 1 ) (NUREG-1482) will be followed at all times unless specific relief has been granted by the i NRC. An inserv' ice test, run quarterly, to measure or observe the test quantitles listed in Table 2 of OM-6, below, is required for all pumps in the IST Program. I (g TABLE 2 l lNSERVICE TEST PARAMETERS Quantity Remarks Speed: N if variatne speed Differential Pressure: AP Centrifugal Pumps, including vertical line shaft pumps Discharge Pressure: P Positive Displacement Pumps Flow Rate: Q vibration: velocity, v, Peak Table 3b of OM-6, below, shows the allowable ranges for test results that will be used to determine if corrective action is required following performance of BVPS-2 Surveillance Tests. The test data will be compared to the ranges applied to the reference values for each test quantity. l O

Baavar Vallsy Powsr Station Unit 2 issus 2 Revision 0

      , INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES                                                                   Page 3 of 279 O

TABLE 3b RANGES FOR TEST PARAMETERS (PRESSURES AND FLOWS) Required Acceptable Range Action Range Test parameter Range Low High Low High P (Positive displacement 0.93 to 1.10P r 0 90 to < .93P r - < 0.90P r > L10P r pumps) AP (Vertical line shaft 0 95 to 1.10AP, 0 93 to < .96 Ap r - < 0 93 AP, > 1.10 A P, pumps) Q (Positive dispiacoment 0 95 to 1.10Q, 0.93 to <.96Qr -

                                                                                                                        < 0.93Qr           > 1.10Qr vertical line shaft pumps)

AP (Centribgal pumps) 0.90 to 1.10AP r - - < 0.90A P, > 1.10A P, Q (Centrifugal pumps) 0 90 to 1.10Qr - -

                                                                                                                        < 0.90Qr           < 1.10Q, oENERAL NOTE: The subscript r denotes reference value.

The limits for vibration readings are taken from Table 3a of OM-6, below. TABLE 3a1 RANGES FOR TEST PARAMETERS (VIBRATIONS) Pump Pump Test Acceptable Alert Required Type Speed parameter Range Range Action Range L CentriNgal and 2600 rpm V, $2.5 V r >2.5 Vr to 6 Vr or > 6 V, or I vertical line > 0.325 inisec. > 0.70 indsec. shaft Heciprocating V, $2.5 V, > 2.5 Vr to 6 V, >6V r NOTES: (1) Vibration parameter per Table 2. V, is vibration reference value in inisec. Corrective action shall be taken if necessary using the folicwing:

1. If deviations fall within the " Alert Range" of Tables 3a and 3b of OM-6, the frequency of testing shall be doubled until the cause of the deviation is  ;

determined and the condition corrected.  !

2. If the deviations fall within the " Required Action Range" of Tables 3a and 3b of
    .                      OM-6, the pump shall be declared inoperable immediately until the cause of the deviation has been determined and the condition corrected. An evaluation of the pump's condition with respect to system operability and technical specifications shall also be made as follows:
a. If the inoperable pump is specifically identified in the technical specifications, then the applicable technical specification action statements shall be followed.  ;
b. If the inoperable pump is in a system covered by a technical specification, an i 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 action statements shall be followed, i

Bsavsr Vality Powsr Station Unit 2 1ssue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 4 of 279 C' c. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.

3. When tests show deviations outside of the acceptable range of Table 3a or 3b of OM-6, the instruments involved may be recalibrated and the test rerun. This is an alternative to replacement or repair, not an additional action that can be taken before declaring the pump inoperable.
4. The pump shall not be returned to service until the condition has been corrected.

The corrective action shall be considered completed when a satisfactory inservice test has been conducted in accordance with Paragraph 4.4 of OM-6. Per Paragraph 5.6 of OM-6 each pump shall run at least 2 minutes under conditions as stable as the system permits prior to measurement of the specified parameters. Utilization of a pump curve in the BVPS-2 IST Program for performing testing and establishing acceptance criteria requires cpecific relief approved by the NRC prior to usage. The following guidance provided by NUREG-1482, Sectioh 5.2 relating to the use of a pump curve shall be followed:

1. A pump curve shall be developed, or manufacturer's pump curve validated, when j the pump is known to be operating acceptably. l
2. The reference points used to develop or validate a pump curve shall be measured p
 \

using instruments at least as accurate (accuracy and range) as required by OM-6, Paragraphs 4.6.1.1 and 4.6.1.2. l

3. A pump curve shall be based on an adequate number of reference points, with a minimum of five (5).
4. Sufficient reference points shall be beyond the " flat" portion (Iow flow rates) of the pump curve in a range which includes or is as close as practical to the design basis flow rate.
5. Acceptance criteria based on a pump curve shall not conflict with technical specifications or UFSAR operability criteria (minimum operating peint/ curve) for flow rate and differential pressure, for the affected pump.
6. 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.
7. 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.

Manufacturer supplied skid-mounted pumps which are integral sub-components of, and are required to support operation of a parent pump or other component, are often times not designed to be tes:ed in accordance with the ASME XI Code, regardless of their ASME Code class. Therefore, ASME Code class manufacturer supplied skid-mounted pumps are p not included in the BVPS Unit 2 IST Program because it has been recognized by the NRC in U NUREG-1482, Section 3.4, that the test of the parent pump or other component itself challenges the operability of the sub-components. This ensures that the skid-mounted pumps operate acceptably commensurate with their safety functions provided satisfactory

Bravar Vality Pow:r Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 5 of 279 (O / performance of the parent pump or other component is demonstrated by an applicable surveillance test. Records of the results of inservice tests and corrective actions as required by Paragraph 7 of OM-6 are trended in tabular form. Pump performance characteristics will be examined for trends. The following five sections of this document are the " Pump Outlines", " Pump Cold Shutdown Justifications", " Pump Refueling Outage Justifications", " Pump Relief Requests", and " Pump Minimum Operating Point (MOP) Curves" sections. The " Pump Outlines" section is a listing of all the pumps in the IST Program, their testing requirements, and their specific pump cold shutdown justification, refueling outage justification, and/or relief request reference numbers. The pumps are arranged according to system and pump mark number. The following abbreviations and designations are used on the Pump Outlines and throughout the IST Program for pumps: N - Speed P - Discharge Pressure AP - Differential Pressure Q - Flowrate

 /~'        V         - Vibration k-)s       2BVT      - Unit 2 Beaver Valley Test 2OST - Unit 2 Operating Surveillance Test Q         - Quarterly Test Frequency CSD       - Cold Shutdown Frequency R        - Refueling Test Frequency PRR      - Pump Relief Request PCSJ     - Pump Cold Shutdown Justification PROJ - Pump Refueling Outage Justification X        - Meets or exceeds OM-6 requirements NA       - Not Applicable The " Pump Cold Shutdown Justifications" section contains the detailed technical description of conditions prohibiting the required testing of safety-related pumps and an j  -          alternate test method to be performed during cold shutdowns. Beaver Valley Unit 2 reactor

! containment is maintained subatmospheric as required by technical specifications. The subatmospheric condition presents a hazardous working environment for station personnel and is considered inaccessible for surveillance testing. Surveillance testing that requires a n reactor containment entry will be performed at cold shutdown aild refueling. The pump Q cold shutdown justification (s) for a specific pump are referenced by the number (s) listed on the pump's outline sheets.

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Beaver Valley Powsr Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 6 of 279 The " Pump Refueling Outage Justifications" section contains the detailed technical

                               - description of conditions prohibiting the required testing of safety-related pumps and an alternate test method to be performed.during refueling outages. The pump refueling outage justification (s) for a specific pump are referenced by the number (s) listed on the pump's outline sheets.

The " Pump. Relief Requests" section contains the detailed technical description of particular [ conditions and equipment installations prohibiting the testing of some of the characteristics l of safety-related pumps. An alternate test method and the frequency of revised testing is  ; 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. 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 2 IST Program. i O t V e I l LO re - . , .- .. --- ,, c. - . r- - - , - . - . . . -

Beavsr Valley Pow:r Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 7 of 279 i I SECTION 11: PUMP OUTLINES l I i l l V(x 1 l i l [

N i

Beavsr Valley Power Station Unit 2 Issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 8 of 279 l ('\ BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 7-Chemical and Volume Control Name: 21 A Charging Pump Number: 2CHS*P21A Class: 2 Function: To provide normal RCS inventory makeup, seal Type: Centrifugal Dwg. OM No.: 7-1 A injection and high head safety injection' Dwg. Coord.: C-4 Remarks: Pump is tested quarterly on recirculation flow and at full flow dunng refueling outages. Albo see PRR1 and PRR2. Parameter 20ST- Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 7.4 (O) X Calculated using Pump Discharge Pressure Indicator [2CHS-Pl1518] (PRR2) and Pump Suction Pressure Indicator [2CHS Pl151 A], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CHS-Pl151 A]. 11.148 (R) X Calculated using Pump Discharge Pressure Indicator [2CHS-Pl151B] (PRR2) and Pump Suction Pressure Indicator [2CHS-P1151 A], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CHS-P1151 A] Q 7.4 (O) X Summation of flow rates from Flow Indicators [2CHS-Fl122A,124A, 127A,130A,160], Control Room, and [2CHS-Fl170], local.

  ,x

( 4 11.14B (R) X Flow Indicator [2 SIS-Fl943], Control Room.

 \',,)        V                             X        Portable monitoring equipment using velocity units.

7.4 (O) 11.148 (R) X Portable monitoring equipment using velocity units. s l A l

Beaver Vallsy Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 9 of 279 BVPS-2 IST PUMP OUTLINE Pump Pump Code System: 7-Chemical and Volume Control j Name: 21B Charging Pump Number: 2CHS'P218 Class: 2 I Function: To provide normal RCS inventory makeup, seal Type: Centrifugal Dwg. OM No.: 7-1 A injection and high head safety injection. Dwg. Coord.: D-4 Remarks: Pump is tested quarterly on recirculation fkaw and at full flow during refueling outages. Also see PRR1 and PRR2. l Parameter 20ST. Req'd Comments ' l (Frequency) ! N NA NA Constant speed induction motor. AP 7.5 (O) X Calculated using Pump Discharge Pressure Indicator [2CHS P1152B] (PRR2) and Pump Suction Pressure Indicator [2CHS-Pl152A], local. See PRR2 for range and accuracy of Pump Suction Pressure indicator [2CHS Pl152A]. 11.14B (R) X Calculated using Pump Discharge Pressure Indicator [2CHS Pl152B] i (PRR2) and Pump Suction Pressure Indicator [2CHS-Pl152A], local. See l PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CHS-Pl152A] Q 7.5 (O) X Summation of flow rates from Flow Indicators [2CHS-F1122A,124A, 127A,130A,160], Control Room, and [2CHS-Fl170], local. 11.148 (R) X Flow Indicator [2 SIS-FIS43], Control Room. V 7.5 (0) X Portable monitoring equipment using velocity units. 11.14B (R) X Portable monitoring equipment using velocity units.

Beaver Valley Power Station Unit 2 Issue 2 Revision 0 l' INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 10 of 279 BVPS 2 IST

                                                                                                                                                                    )

PUMP OUTLINE I Pump Pump Code System: 7-Chemical and Volume Control (- I i Name: 21C Charging Pump Number: 2CHS* P21C Class: 2  ; Function: To provide normal RCS inventory makeup, seal Type: Centrifugal Dng. OM No.: 71 A  ; injection and high head safety injecticn. Dwg. Coord.: E-4

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Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. Also see PRR1 and PRR2. ' Parameter 2OST. Req'd Comments i (Frequency) j N NA NA Constant speed induction motor. l i AP 7.6 (0) X Calculated using Pump Discharge Pressure Indicator [2CHS Pl153B] and Pump Suction Pressure Indicator [2CHS-P1153A], local. See l I (PRR2) PRR2 for range and accuracy of Pump Suction Pressure Indicator l [2CHS-P1153A]. i 11.148 (R) X Calculated using Pump Discharge Pressure indicator [2CHS-Pl153B] l (PRR2) and Pump Suction Pressure Indicator [2CHS-Pl153A], local. See PRR2 for range and accuracy of Pur@ Suction Pressure Indicator [2CHS-P1153A]. Q 7.6 (O) X Summation of flow rates from Flow Indicators [2CHS-Fl122A,124A, 127A,130A,160], Control Room, and [2CHS Fl170], local. 11.148 (R) X Flow Indicator [2 SIS-Fl943], Control Room. V 7.6 (0) X Portsble monitoring equipment using "elocity units. 11.14B (R) X Portable monitoring equipment using velocity units. l l I I I l

Bsavar Vallsy Powsr Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 11 of 279  ; BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 7-Chemical and Volume Control l Name: 22A Boric Acid Number: 2CHS* P22A Class: 3 , Transfer Pump i Function: Chemical shim and emergency boration supply. Type: Centnfugal Dwg. OM No.: 7-2 Dwg. Coord.: C-2 ' Remarks: Pump is tested quarterly at full flow by recirculating the Boric Acid Tank. Also see PRR1 and PRR2. l Parameter 2OST. Req'd Comments , (Frequency)  ; N NA NA Constant speed induction motor. AP 7.1 (O) X Calculated using Pump Discharge Pressure Indicator [2CHS-P1105] (PRR2) and Pump Suction Pressure Indicator [2CHS-Pl123A], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CHS-Pl123A]. Q 7.1 (0) X Flow Indicator [2CHS-Fil23A(B)], local. V 7.1 (O) . X Portable monitoring equipment using velocity units. l , O i l se l l i

_ -m - . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ . _.- _ . Bsavar Valley Powsr Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 12 of 279 l BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 7-Chemical and Volume Control Name: 22B Boric Acid Number: 2CHS'P228 Class: 3 , Transfer Pump l i Function: Chemical shim and emergency boration supply. Type: Centrifugal Dwg. OM No.: 7-2

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Dwg. Coord.: F2 ) Remarks: Pump is tested quarterly at full flow by recirculating the Boric Acid Tank. Also see PRR1 and PRR2. Parameter 2OST. Req'd Comments * (Frequency) l N NA NA Constant speed inductiori motor. 1 AP 7.2 (0) X Calculated using Pump Discharge Pressure Indicator [2CHS-P1110] (PRR2) and Pump Suction Pressure Indicator [2CHS-P1123B], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CHS-Pl123B]. Q 7.2 (O) X Flow indicator [2CHS-Fl123B(A)], local. I l I V 7.2 (0) X Portable monitoring equipment using velocity units. , ! i ( 1 l l l I l i l I { r I i l r, S 4 I I

Baavar Valley Power Station Unit 2 issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 13 of 279 O BVPS 2 IST l PUMP OUTLINE Pump Pump Code System: 10-Residual Heat Removal , Name: 21 A Residual Heat Number: 2RHS*P21 A Class: 2 ( Removal Pump Function: Long term decay heat removal. Type: Vertical Dwg. OM No.: 10-1 i Dwg. Coord.: B-3 Remarks: Pump is tested quarterly at full flow during cold shutdowns and refueling outages per PCSJ1. Also see FRRt. Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor, AP 10.1 X Calculated using Pump Discharge Pressure Indicator [2RHS Pl602A] (CSD,R) and Pump Suction Pressure Indicator [2RHS-Pl603A], Control Room. Q 10.1 X Summation of flow rates from Flow Indicators [2RHS-Fl607A], (CSD,R) [2RHS-Fl605A], and [2CHS-Fl150]. Control Room. V 10.1 X Portable monitoring equipment using velocity units. Motor bearing (CSD,R) vibrations will be obtained because the pump bearings are in the , driver. 1 0 1 1 l , O , i b l 1

  .. .     . . . . . .    . - ..              -.    - - - . ~ -             - -          .    - ~ . - = . . - . . - . . .- . . ~ . _                .

Beaver Vallay Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 14 of 279  ! g i Q BVPS 2 IST [ l PUMP OUTLINE Pump Pump Code System: 10-Residual Heat Removal , Name: 21B Residual Heat - Number: 2RHS P21B Class: 2 Removal Pump Function: Long term decay heat removal. Type: Vertical Dwg. OM No.: 10-1  ; Dwg. Coord.: E-3 i Remarks: Pump is tested quarterly at full flow during cold shutdowns and refueling outages per PCSJ1. Also see PRRI. !' Parameter 2OST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 10.2 X Calculated using Pump Discharge Pressure Indicator [2RHS-P1602B] (CSD,R) and Pump Suction Pressure Indicator [2RHS-Pl603B], Control Room. l Q 10.2 X Summation of flow rates from Flow Indicators [2RHS-Fl607B], l (CSD,R) [2RHS-Fl605B], and [2CHS-Fl150], Control Room. V 10.2 X Portable monitoring equipment using velocity units. Motor bearing (CSD.R) vibrations will be obtained because the pump bearings are in the driver. a i [ r

       .._._. ,_.. _. ___ _                 _    . . . _ _ _      _ _ . ... -             .m   .__ _ _ .._ _ _ . _ ._ _ . _ _ _ ._ _                ___. . . . _ .

l Beavsr Vallsy Powsr Station Unit 2 issue 2 Revision 0 . INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 15 of 279 l (' i BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 11-Safety injection Name: 21 A Low Head Safety Number: 2 SIS

  • P21 A Class: 2 injection Pump l Function: Low pressure'. high volume safety injection. Type: Centrifugal Dwg. OM No.: 11-1 l Dwg. Coord.: E-2 l

Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. Also see  ; PRR1 and PRR2. , Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 11.1 (O) X Calculated using Pump Discharge Pressure Indicator [2 SIS-Pl943] (PRR2) and Pump Suction Pressure Indicator [2 SIS Pl938], local. See PRR2 l for range and accuracy of Pump Suction Pressure Indicator [2 SIS-Pl338]. 11.14A (R) X Calculated using Pump Discharge Pressure Indicator [2 SIS-Pl943] (PRR2) and Pump Suction Pressure Indicator [2 SIS-Pl938], local. See PRR2 l for range and accuracy of Pump Suction Pressure Indicator i (2 SIS-Pl938). Q 11.1 (O) X Flow indicator [2 SIS-FIS970A], local. ! 11.14A (R) X Flow indicator [2 SIS-Fl945], Control Room. l V 11.1 (O) X Portable monitoring equipment using velocity units. j 11.14A (R) X Portable monitoring equipment using velocity units.

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Beavsr Valley Powsr Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 16 of 279 , SVPS 2 IST l [ l PUMP OUTLINE ! l l Pump Pump Code System: 11-Safety injection l l Name: 218 Low Head Safety Number: 2 SIS'P21 B Class: 2 j injection Pump l Function: Low pressure high volume safety injection. Type: Centrifugal Dwg. OM No : 11 1 Dwg. Coord.: G-2 Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. Also see PRR1 and PRR2. l l Parameter 2OST- Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 11.2 (0) X Calculated using Pump Discharge Pressure Indicator [2 SIS-PIS44] (PRR2) and Pump Suction Pressure Indicator [2 SIS-Pl939], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2 SIS-Pl939]. 11.14A (R) X Calculated using Pump Discharge Pressure Indicator [2 SIS-Pl944] (PRR2) and Pump Suction Pressure Indicator [2 SIS-Pl939], local. See PRR2 for range and accuracy of Pump Suction Pressure indicator [2 SIS-Pl939]. Q 11.2 (O) X Flow indicator [2 SIS-FIS970B], local. 11.14A (R) X Flow indicator [2 SIS-F1946], Control Room. V 11.2 (O) X Portable monitoring equipment using velocity units. 11.14A (R) X Portable monitoring equipment using velocity units. I i ! G

_ -_.__.--___.._._.__._._._.__.__.__.m.__ _._ _ . - -- . _ ~ _ _ . _ _ _ . . Beavsr Vclity Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 17 of 279  ; BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21 A Quench Spray Number: 20SS P21A Class: 2 i Pump Function: To provide borated water from the RWST to the Type: Centrifugal Dwg. OM No.: 13-2 containment spray header for containment depressurization following a DBA. Dwg. Coord.: A-9 Remarks: Punip is tested quarterly at full flow by recirculating the RWST. Also see PRR1. Parameter 20ST. Req'd Comments I (Frequency) N NA NA Constant speed induction motor. l AP 13.1 (O) X Calculated using Pump Discharge Pressure Indicator [20SS-P1101 A] l and Pump Suction Pressure Indicator [20SS-P1102A]. Control ! Room. Q 13.1 (O) X Flow Indicator [20SS-FIS101 A or 102A], local. I V 131(0) X Portable monitoring equipment using velocity units. l l , I 1 l 1 I l l I t [ I l

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 . - . . - . . - ~ . . - .               ,.       . . .       . . .- -          - _       . _          -      - . . - _ . ~ . _ _ - - - . . - . . ..-

Beaver Valley Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 18 of 279 b BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21B Ouench Spray Number: 20SS*P21 B Class: 2 l Pump Function: To provide borated water from the RWST to the Type: Centrifugel Dwg. OM No.: 13-2 containment spray header for containment Dwg. Coord.: G-9 depressurization following a DBA. Remarks: Pump is tested quarterly at full flow by recirculating the RWST. Also see PRR1. Parameter 2OST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 13.2 (O) X Calculated using Pump Discharge Pressure Indicator [20SS-Pl101B] ' and Pump Suction Pressure Indicator [20SS Pl1028]. Control Room. Q 13.2 (0) X Flow Indicator [20SS-FIS1018 or 1028), local. V 13.2 (O) X Portable monitoring equipment using velocity units. i f f !b l l --

Baavar Vallay Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 19 of 279 I

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d BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 24A Chemical Number: 20SS*P24A Class: 2 Injection Pump l Function: Chemicalinjection to the Quench Spray System Type: Positive Dwg. OM No.: 13 2 during containment depressurization. Displacement Dwg. Coord.: C-6 ( Remarks: Pump is tested quarterly at full flow by recirculating the RWST Also see PRRI. Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. P 13.10A (O) X Pump Discharge Pressure Indicator [20SS-Pl111 A], local. Q 13.10A (O) X Flow Indicator [2OSS-FIS105A] local. l V 13.10A (O) X Portable monitoring equipment using velocity units. i I ) l l l i l F b V t I l l l - . . - .

    - ~ . .        _ . .             ..        .    . -      . ~     - . - - ~ . -              - .. - - . - - - . _ ..-. - - . .. - .

I Beaver Vallay Powar Station Unit 2 issue 2  : l Revision 0 j INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 20 of 279 l BVPS 2 IST l l PUMP OUTLINE 1 l Pump Pump code System: 13-Containment Depressurization  !

Name: 24B Chemical Number: 20SS*P248 Class: 2 Injection Pump l Function: Chemical injection to the Quench Spray System Type: Positive Dwg. OM No.: 13-2 l
- during containment depressurization. Displacement Dwg. Coord.
E-6 Remarks: Pump is tested quarterly at full flow by recirculating the RWST. Also see PRR1, l

Parameter 2OST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. I i P 13.10B (O) X Pump Discharge Pressure Indicator [20SS-P1111B], local. I Q 13.108 (0) X Flow Indicator [20SS-FIS105B], local. l V 13.10B (O) X Portable monitoring equipment using velocity units. l O 1 l 1 l I l l I O Q 1

Beavsr Vallsy Power Station Unit 2 issua 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 21 of 279 BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21 A Recirculation Number: 2RSS* P21 A Class: 2 Spray Pump Fonction: Circulate containment sump water for long term Type: Vertical Dwg. OM No.: 13-1 containment depressurization. Dwg. Coord.: F-3 Remarks: Pump is tested during refueling outages at full flow through a test loop per PROJ1. Also see PRR1 and PRR2. Parameter 2OST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 2BVT 1.13.5 X Ca!culated using Pump Discharge Pressure indicator (R) (PRR2) [2RSS-Pl156A]. Control Room, and local temporary suction pressure test gauge. See PRR2 for range and accuracy of temporary suction pressure test gauge. Q 2BVT 1.13.5 X Flow indicator [2RSS-Fl157A]. Control Room. (R) V 2BVT 1.13.5 X Portable monitoring equipment using velocity units. (R) . i I

_ _ . . _ _ _ - _ . _ . _ . . _ . . . ~.. _ ._ _ __. . _ i Beavsr Valley Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 22 of 279

 %                                                                   BVPS 2 IST                                                                               )

PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21B Recirculation Number: 2RSS*P21 B Class: 2 I Spray Pump Function: Circulate containment sump water for long term Type: Vertical Dwg. OM No.: 13-1 containment depressurization. Dwg. Coord.: E-8 Remarks: Pump is tested during refueling outages at full flow through a test loop per PROJ1 Also see PRR1 and PRR2. Parame.er 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 2BVT 1.13.5 X Calculated using Pump Discharge Pressure Indicator (R) (PRR2) [2RSS Pl1568], Control Room, and local temporary suction l pressure test gauge. See PRR2 for range and accuracy of temporary suction pressure test gauge. Q 2BVT 1.13.5 X Flow Indicator [2RSS Fl157B], Control Room. (R) l

V 2BVT 1.13 5 X Portable monitoring equipment using velocity units. l l

(R) c 9 l I i J t

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_ . _ __ ~ _ _ _ - ._ . __. _ _--_.________._.__..-_-____m..__ . Beavsr Vallsy Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGPAM FOR PUMPS AND VALVES Page 23 of 279 1 BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21C Perirculation Number: 2RSS*P21C Class: 2 Spray Pump Function: Circulate containment sump water for long term Type: Vertical Dwg. OM No.: 13-1 i containment depressurization and long term core recirculation. Dwg. Coord.: E-S Remarks: Pump is tested during refueling outages at full flow through a test loop per PROJ1. Also see PRR1 and PRR2. . Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 2BVT 1.13.5 X Calculated using Pump Discharge Pressure Indicator - (R) (PRR2) [2RSS-Pl156C], Control Room, and local temporary suction pressure test gauge See PRR2 for range and accuracy of temporary suction pressure test gauge. Q 2BVT 1.13.5 X Flow Indicator [2RSS-Fl157C], Control Room. (R)' V 2BVT 1.13.5 X Portable monitoring equipment using velocity units. (R) O i 1 i l I 4

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 .. m _ . . . . . _ . _             . _ _ _ _ . - ~ . . . _ _ - . -             . . _        __       ..       ._     . _ _ _ _ _    _.        . _ _ _ _ _ _ _ . _ _ _ .

l Baavar Valley Powar Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 24 of 279 l BVPS-2 IST PUMP OUTLINE Pump Pump Code System: 13-Containment Depressurization Name: 21D Recirculation Number: 2RSS* P21 D Class: 2 l Spray Pump ' l Function: Circulate containment sump water for long term Type: Vertical Dwg. OM No.: 13-1 containment depressurization and long term core Dwg. Coord.: E-6 recirculation. Remarks: Pump is tested during refueling outages at full flow through a test loop per PROJ1. Also see PRR1 i and PRR2. ' Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 2BVT 1.13.5 X Calculated using Pump Discharge Pressure Indicator  ! (R) (PRR2) [2RSS-P1156D], Control Room, and local temporary suction pressure test gauge. See PRR2 for range and accuracy of l temporary suction pressure test gauge. Q 2BVT 1.13.5 X Flow Indicator [2RSS-Fl1570], Control Room. (R) . V 2BVT 1.13.5 X Portable monitoring equi 9 ment using velocity units. (R) i , I

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I 4

 .- -        _.. . _ _ _ .                       -       -           .- - . . -       - ~ . - -                - - _ .     . . .  . . - - . _ _

Bsavsr Valley Power Station Unit 2 issue 2 i j Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 25 of 279 BVPS 2 IST i t i PUMP OUTLINE l Pump Pump Code System: 15-Primary Component Cooling Name: 21 A Component Number: 2CCP P21 A Class: 3 Water l Cooling Water Pump l Function: Provide cooling water to Residual Heat Removal Type: Centrifugal Dwg. OM No.: 15-1 l Heat Exchangers and reactor plant components. Dwg. Coord.: B-4 Remarks: Pump is tested quarterly using a pump curve per PRR3. Also see PRR1 and PRR2. Parameter 20ST. Req'd Comments (Frequency) a l N NA NA Constant speed induction motor. AP 15.1 (0) X Calculated using Pump Discharge Pressure Indicator (PRR2) [2CCP-Pl145A], Control Room, and Pump Suction Pressure Indicator l [2CCP-P1150A], local. See PRR2 for range and accuracy of Pump ( Suction Pressure Indicator [2CCP F1150A]. i Q 15.1 (0) X Flow Indicator [2CCP-Fl117A1], Control Room. V 15.1 (O) X Portable monitoring equipment using velocity units. l _ ) l l l I 1 I l l l i

_ _ _ _ _ . _ . _ . _ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . . _ . . . . _ . _ _ - - _ . _ _ . . ~ Baavsr Valley Powar Station Unit 2 1ssue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 26 of 279 BVPS 2 IST PUMP OUTLINE t Pump Pump Code System: 15-Primary Component Cooling Name: 21B Component Number: 2CCP* P21 B Class: 3 Water Cooling Water Pump Function: Provide cooling water to Residual Heat Removal Type: Centnfugal Dwg. OM No.: 15-1 Heat Exchangers and reactor plant components. Dwg. Coord.: F-4 Remarks: Pump is tested quarterly using a pump curve per PRR3. Also see PRR1 and PRR2. Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 15.2 (O) X Calculated using Pump Discharge Pressure Indicator (PRR2) [2CCP-Pl145B], Control Room, and Pump Suction Pressure indicator  ! [2CCP-Pl150B], local. See PRR2 for range and accuracy of Pump Suction Pressure Indicator [2CCP-Pl150B]. Q 15.2 (0) X Summation of flow rates irom Flow Indicators [2CCP-Fl117B1], f Control Room, [2CCP-F1103] and [2CCP Fl102], local. V 15.2 (0) X Portable monitoring equipment using velocity units. 1

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i. i i

                . - -          - - . .    -.   .    .-           - - - . . - -     . . . - . -.-          - -.           -.- - -~.. ~ --

l . _ . -_ , t Beavsr Valley Powsr Station Unit 2 issue 2  ; Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 27 of 279 O V BVPS 2 IST , i PUMP OUTLINE Pump Pump Code System: 15-Primary Component Name: 21C Component Number: 2CCP'P21C Class: 3 Cooling Water  ! Cooling Water Pump Function: Provide cooling water to Residual Heat Removal Type: Centrifugal Dwg. OM No.: 15-1 Heat Exchangers and reactor plant components. Dwg. Coord.: D-4 , Remarks: Pump is tested quarterly using a pump curve per PRR3. Also see PRR1 and PRR2. Parameter 20ST. Req'd Comments - (Frequency)  ; N NA NA Constant speed induction motor. i AP 15.3 (O) X Calculated using Pump Discharge Pressure Indicator (PRR2) [2CCP-Pl145C], Control Room, and Pump Suction Pressure Indicator , l [2CCP-Pl150C]. local. See PRR2 for range and accuracy of Pump j Suction Pressure Indicator [2CCP-Pl150C]. 1 Q 15.3 (0) X Flow Indicator [2CCP Fl117A1], Control Room O_R summation of flow rates from Flow Indicators [2CCP-Fl117B1], Control Room, [2CCP-Fl103] and [2CCP-Fl102], local. V 15.3 (O) X Portable monitoring equipment using velocity units. i O t 1 i l l l i f (

 . - _ ._ .        . - -            - . . - . - . - .       . . - - -                      - - . - .             - -                  . . ~ -      ~ . ~ . - ~

Bsavar Valley Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND val.VES Page 28 of 279 BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 24-Auxiliary Feedwater I Name: Turbine Driven Number: 2FWE*P22 Class: 3 Auxiliary Feedwater Pump Function: Provide emergency makeup to Steam Generators Type: Centrifugal Dwg. OM No.: 24-3 during loss of normal feedwater. Dwg. Coord.: E-4 Remarks: Pump is tested quarterly on recirculation flow and at full flow when in Mode 3 during startup from refueling outages. It will also be tested at full flow when in Mode 3 during startup from a cold i shutdown, if associated check valves are also tested, or if the pump is on double freqt.ency testing in accordance with Paragraph 6.1 of OM-6. Also see PRR1. Parameter 2OST. Req'd Comments (Frequency) N 24 4 (O) X No installed rpm indication. Use portable monitoring equipment - Stroboscope. 24.4 X No installed rpm indication. Use portable monitoring equipment - (CSD R) Stroboscope. AP 24.4 (O) X Calculated using Pump Discharge Pressure indicator [2FWE-Pl155] I and Pump Suction Pressure Indicator [2FWE-Pl156], local. 24.4 X Calculated using Pump Discharge Pressure Indicator [2FWE-P1155] (CSD,R) and Pump Suction Pressure Indicator [2FWE-Pl156], local. ' Q 24.4 (0) X Flow Indicator [2FWE-F1155], local. 24.4 X Summation of flow rates from Flow Indicators [2FWE-F1100A,B,C], (CSD,R) Control Room. i V 24.4 '(O) X Portable monitoring equipment using velocity units. 24.4 X Portable monitoring equipment using velocity units. (CSD,R) l l t 1 1 G

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Beavsr Vallsy Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 29 of 279 s O) t V BVPS 2 IST

  • l PUMP OUTLINE l Pump Pump Code System: 24-Auxiliary Feedwater Name: 23A Motor Driven Number: 2FWE* P23A Class: 3 Auxiliary Feedwater Pump

( Function: Provide emergency makeup to Steam Generators Type: Centrifugal Dwg. OM No.: 24-3 during loss of normal feedwater. Dwg. Coord.: F-4 l Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. It will also I ( be tested at full flow dunng cold shutdown, if associated check valves are also tested, or if the i pump is on double frequency testing in accordance with Paragraph 6.1 of OM-6. Also see PRR1 and PRR2, l Parameter 2OST. Req'd Comments i (Frequency) [ N NA NA Constant speed induction motor. AP 24.2 (O) X Calculated using Pump Discharge Pressure Indicator [2FWE-P1155A] and Pump Suction Pressure Indicator [2FWE-P1156A], local. 24.6 X Calculated using Pump Discharge Pressure Indicator [2FWE-P1155A] l (CSD,R) and Pump Suction Pressure. Indicator [2FWE Pl156A], local. Q 24.2 (O) X Flow Indicator [2FWE Fl155A], local.  ; 24 6 X Summation of flow rates from Flow Indicators [2FWE-Fl100A,B,C], (CSD,R) (PRR2) Control Room. See PRR2 for range and accuracy of Flow Indicators j

    \                                                   [2FWE-Fl100A,B,C].                                                       ;

V 24.2 (0) X Portable monitoring equipment using velocity units. 24.6 X Portable monitoring equipment using velocity units. l (CSD,R) 1 1 i 1 . t C l 4

Beavsr Valley Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 30 of 279 im (V) BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 24-Auxiliary Feedwater Name: 23B P/oter Driven Number: 2FWE* P238 Class: 3 Auxiliary Feedwater Pump Function: Provide emergency makeup to Steam Generators Type: Centrifugal Dwg. OM No.: 24-3 during loss of normal feedwater. De CM G4 Remarks: Pump is tested quarterly on recirculation flow and at full flow during refueling outages. It will also be tested at full flow during cold shutdown, if associated check valves are also tested, or if the pump is on double frequency testing in accordance with Paragraph 6.1 of OM-S. Also see PRR1 and PRR2. Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed ifiduction motor. AP 24.3 (O) X Calculated using Pump Discharge Pressure ladicator [2FWE-Pl155B] and Pump Suction Pressure Indicator [2FWE-P1156B], local. 24.6 X Calculated using Pump Discharge Pressure Indicator [2FWE-P1155B] (CSD.R) and Pump Suction Pressure Indicator [2FWE-Pl156B], local. Q 24.3 (O) X Flow Indicator [2FWE-Fl155B], local.

  ,,                         24 6             X       Summation of flow rates from Flow Indicatots [2FWE-Fl100A,B,C],
     \

[V (CSD,R) (PRR2) Control Room, See PRR2 for range and accuracy of Flow Indicators [2FWE-Fl100A,B,C]. V 24.3 (0) X Portable monitoring equipment using velocity units. 24.6 X Portable monitoring equipment using velocity units. (CSD,R) l t'3 l l I

(. . - . . ~ . - . - Bsaver Valley Powsr Station Unit 2 issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 31 nf 279 O BVPS 2 IST j l PUMP OUTLINE  ! Pump Pump Code System: 30-Service Water Name: 21A Service Water Number: 2SWS*P21 A Class: 3 Pump Function: Provide cooling water to Recirculation Spray Heat Type: Vertical Dwg. OM No.: 30 1 Exchangers and reactor plant components under normal and emergency conditions. Dwg. Coord.: C-2 ! Remarks: Pump is tested quarterly using a pump curve per PRR4. Also see PRR1 and PRR5. i Parameter 20ST- Req'd Comments (Frequency) N NA NA Constant speed induction motor. 1 AP 30.2 (O) X Calculated using Pump Discharge Pressure Indicator  ; [25WS-Pl101 A] and river water elevation from Ohio River Level Recorder [LR-1CW-101], local, as permitted by NUREG-1482, i Section 5.5.3. 'Use of Tank or Bay Level to Calculate Differential ( Pressure". l l Q 30.2 (0) X Flow Indicator [2SWS-FIT 100]. local. l - V 30.2 (O) X Portable monitring equipment using velocity units. The motor (PRRS) outboard axial (MOA) vibration measurement is not accessible and ( ( will not be obtained per PRR5. l 1 1 l 1 l l l b j b i

_ __ _ _. _ . . _ _ . . _ _ _ _ _ _ _ . - _ . _ - . . . . _ _ . _ _ _ , _ _ _ . - _..m_ Bsaver Valley Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 32 of 279 [ l BVPS 2 IST PUMP OUTLINE I Pump Pump Code System: 30-Service Water  ! Name: 21B Service Water Number: 2SWS'P21 B Class: 3 Pump , Function: Provide cooling water to Recirculation Spray Heat Type: Vertical Dwg. OM No.: 30-1 l Exchangers and reactor plant components under normal and emergency conditions. Dwg. Coord.: D-2 Remarks: Pump is tested quarterly using a pump curve per PRR4. Also see PRR1 and PRRS. ' Parameter 20ST. Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 30.3 (O) X Calculated using Pump Discharge Pressure in.dicator [2SWS-Pl101B] and river water elevation from Ohio River Level Recorder [LR ICW-101], local, as permitted by NUREG-1482, - Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure". Q 30.3 (0) X Flow Indicator [2SWS-FIT 100S]. local. l V 30.3 (0) X Portable monitoring equipment using velocity units. The motor (.PRRS) outboard axial (MOA) vibration measurement is not accessible and , will not be obtained per PRRS. l (,

_ _ _ . ._ .m - _. .__ __..__ _ _ _ __.--.__._ - ._ _ -_ _. __ - . _.-_ i i  ; i I Baavar Vallsy Powsr Station Unit 2 Issue 2 i Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 33 of 279 [

 \

BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 30-Service Water Name: 21C Service Water Number: 2SWS* P21C Class: 3 Pump

  • Function: Provide cooling water to Recirculation Spray Heat Type: Vertical Dwg. OM No.: 30-1 ,

Exchangers and reactor plant components under normal and emergency conditions. Dwg. Coord.: G-2 i Remarks: Pump is tested quarterly using a pump curve per PRR4. Also see PRR1 and PRR5.

                                                                                                                                                       )

! Parameter 2OST- Req'd Comments ! (Frequency) l l N NA NA Constant speed induction motor. l AP 30 6 (O) X Calculated using Pump Discharge Pressure Indicator ! [2SWS-P1101C] and river water elevation from Ohio River Level l Recorder [LR 1CW-101], local, as permitted by NUREG-1482, Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure". Q 30.6 (O) X Flow Indicator [2SWS-FIT 100(S)], local, V 30.6(0) X Portable monitoring equipment using velocity units. The motor (PRRS) outboard axial (MOA) vibration measurement is not accessible and j , will not be obtained per PRR5. O i f

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I f Bsaver Valley Power Station Unit 2 Issue 2 I i Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 34 of 279 f k BVPS 2 IST PUMP OUTLINE l Pump Pump Code System: 36-Diesel Fuel Oil Name: 21 A Fuel Oil Transfer Number: 2EGF'P21A Class: 3 Pump , Function: Transfer fuel fmm the underground storage tank to Type: Vertical Dwg. OM No.: 36-1 l the day tank. Dwg. Coord.: F-3 Remarks: Pump is normally tested bi monthly at full flow from the storage tank to the day tank. Also see , PRR1, PRR2 and PRR6. l l Parameter 2OST. Req'd Comments ! (Frequency) l l N NA NA Constant speed induction motor, I i AP 36.1 (O) X Calculated using Pump Discharge Pressure indicator [2EGF-Pl201 A] and Fuel Oil Storage Tank level from [2EGF LIS201 A], local, as permitted by NUREG-1482, Section 5.5.3. 'Use of Tank or Bay Level to Calculate Differential Pressure.* See PRR2 for range and accuracy of Pump Discharge Pressure Indicator [2EGF-Pl201 A].

        ^

Q 36.1 (O) X No instrumentation is provided for flow. A level change over time ) (PRR6) in the day tank will be measured using Level Gauge [2EGF*LG201], local, and converted to flowrate per PRR6. V 36.1 (O) X Portable monitoring equipment using velocity units. i l i I i 1 l l I i i r i 5 l 4 ( ' 1 l l

1 i Bsaver Vallsy Powar Station Unit 2 issue 2 Revision 0 i j INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 35 of 279 O I l BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 36-Diesel Fuel Oil Name: 21B Fuel Oil Transfer Number: 2EGF'P21 B Class: 3 l Pump Function: Transfer fuel from the underground storage tank to Type: Vertical Dwg. OM No.: 36-1 the day tank. Dwg. Coord.: E-3 Remarks: Pump is normally tested bi-monthly at full flow from the storage tank to the day tank. Also see PRR1, PRR2 and PRR6. Parameter 20ST. Req'd Comments I (Frequency) N NA NA Constant speed induction motor. AP 36.1 (0) X Calculated using Pump Discharge Pressure Indicator [2EGF-Pl201B] and Fuel Oil Storage Tank level from [2EGF-LIS201 A], local, as j permitted by NUREG-1482, Section 5.5.3, "Use of Tank or Bay Level I to Calculate Differential Pressure.' See PRR2 for range and l accuracy of Pump Discharge Pressure Indicator [2EGF-P1201B]. ' Q 30.1 (O). X No instrumentation is provided for flow. A level change over time l (PRR6) in the day tank will be measured using Level Gauge [2EGF*LG201], l local, and converted to flowrate per PRR6. 1 V 36.1 (O) X Portable monitoring equipment using velocity units. ' t t A l l l l l i i ~ O

Banysr Valley Powsr Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 36 of 279 O BVPS 2 IST PUMP OUTLINE Pump Pump Code System: 36-Diesel Fuel Oil Name: 21C Fuel Oil Transfer Number: 2EGF*P21C Class: 3 Pump Function: Transfer fuel from the underground storage tank to Type: Vertical Dwg. OM No.: 36-1 the day tank. D% Cood F-8 Remarks: Pump is normally tested bi-monthly at full flow from the storage tank to the day tank. Also see PRR1, PRR2 and PRR6. Parameter 2OST- Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 36.2 (Q) X Calculated using Pump Discharge Pressure Indicator [2EGF-Pl201C] and Fuel Oil Storage Tank level from [2EGF-LIS201 B], local, as permitted by NUREG-1482, Section 5.5.3, "Use of Tank or Bay Level to Calculate Differential Pressure.' See PRR2 for range and accuracy of Pump Discharge Pressure Indicator [2EGF-Pl201C]. Q 36.2 (0) X No instrumentation is provided for flow. A level change over time (PRR6) in the day tank will be measured using Level Gauge [2EGF*LG202]. local, and converted to flowrate per PRR6. i l p V 36.2 (0) X Portable monitoring equipment using velocity units. i 1 l I 4 0

Bravar Valizy Powsr Station Unit 2 issun 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 37 of 279

 ,Q U                                                      SVPS 2 IST PUMP OUTLINE Pump                           Pump                   Coda        System: 36-Diesel Fuel Oil Name: 21D Fuel Oil Transfer Number: 2EGF*P21 D        Class: 3 Pump Function: Transfer fuel from the underground storage tank to Type: Vertical                Dwg. OM No.: 36-1 the day tank Dwg. Coord.: E-8 Remarks: Pump is normally tested bi-monthly at full flow from the storage tank to the day tank. Also see PRR1, PRR2 and PRR6.

Parameter 20ST- Req'd Comments (Frequency) N NA NA Constant speed induction motor. AP 36.2 (O) X Calculated using Pump Discharge Pressure Indicator [2EGF Pl201D] and Fuel Oil Storage Tank level from [2EGF-LIS201B], local, as permitted by NUREG-1482, Section S.5.3, 'Use of Tank or Bay Level to Calculate Differential Pressure." See PRR2 for range and accuracy of Pump Discharge Pressure Indicator [2EGF Pl201D]. Q 36.2 (O) X No instrumentation is provided for flow. A level change over time (PRR6) in the day tank will be measured using Level Gauge [2EGF*LG202], local, and converted to flowrate per PRR6. V 36.2 (0) X Portable monitoring equipment using velocity units. ("]

 %)

l l l t l t l l l iO

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l. Beaver Valley Power Station- Unit 2 issue 2 Revision 0 F INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 38 of 279  !

i. P SECTION lil: PUMP COLD SHUTDOWN JUSTIFICATIONS . i  ! i i l

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f f  ; t I i l l i l k l l l l 4 I l I i 4 4 6e i 4' i i e l _ ~ _ , - -. - _ - . , - . . . , , n.. , ,.- ,, .. _ , , , . , - _ _ _ __ _ _ _ _ . _ , - , , , _ , _ , - . - - , . . . . - . .

Baavar Valley Power Station Unit 2 Issue 2 l Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES 3 age 39 of 279 PUMP COLD SHUTDOWN JUSTlFICATION 1 Pump Mark No(s): 2R HS* P21 A Code Class: 2 l 2R HS* P218 l System: 10 - Residual Heat Removal 1 Function: To provide long term removal of decay heat from the reactor core l and sensible heat from the RCS in order to achieve and maintain the plant in a cold shutdown condition. Test Requirement: Per OM-6, Paragraph 5.1, " Frequency of Inservice Tests", an inservice test shall be run on each pump, nominally every 3 months. Basis for CSJ: These pumps are not required to be run at power and are considered out of service. They are not returned to service until RCS temperature is $350F and RCS pressure is $360 psig. Per OM-6, Paragraph 5.4, " Pumps in Systems Out of. Service", the test schedule need not be followed fer pumps in a system not required to be operable. , in addition, these pumps are located inside containment. If tested at power, test personnel would have to make a containment entry to

 ,Q                             properly monitor pump operation. However, Beaver Valley Unit 2

(/ reactor containment is maintained subatmospheric as required by technical specifications. The subatmospheric condition presents a hazardous working environment for station personnel and !s considered inaccessible for surveillance testing. Alternate Test: These pumps will be tested quarterly at fu's flow only during cold shutdowns and refueling outages per 20ST-10.1 and 20ST-10.2 (Residual Heat Removal Pump Performant,e Tests).

References:

OM-6, Paragraphs 5.1 and 5.4. I i l

O,

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I l-  : l [ ! Beaver Valley Power Station Unit 2 issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 40 of 279 i ! SECTION IV: PUMP REFUELING OUTAGE JUSTlFICATIONS l i I I I l I-l 1 I l i I' t l I I I e l- I l l l  : i l l- . . _ . _ . _ _ . . - ~ - . .-.- ._ , -- _ - . . . _ _ - - . _ _ _ . _ . . - . __ . . - . _ . . . . . _ . . ~ . .-

Beavsr Valley Powar Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 41 of 279 PUMP REFUELING OUTAGE JUSTIFICATION 1 Pump Mark No(s): 2RSS* P21 A Code Class: 2 2RSS*P21B 2RSS* P21C 2RSS* P21 D System: 13 - Containment Depressurization Function: To circulate water from the reactor containment sump to the spray rings at the top of the containment dome for the purpose of removing heat from the containment atmosphere thereby depressing and holding containment pressure subatmospheric for the long term following a DBA. In addition, the "C" and "D* Recirculation Spray Pumps also take suction from the containment sump to provide water to the High Head Safety injection Pumps for long term core recirculation. 1 Test Requirement: Per OM-6, Paragraph 5.1, " Frequency of inservice Tests", an l Inservice test shall be run on each pump, nominally every 3 months. l I Basis for ROJ: These vertical suction well centrifugal pumps are located outside of 1 g containment in the safeguards building, but take suction from the containment sump. They are not operated during normal plant ( I operation and are maintained in a " dry" layup condition between refueling outages along with their associated heat exchangers. The only time that water is introduced to the suction of these pumps is for testing purposes and following an accident resulting in a containment isolation phase B signal, when the pumps start after an approximately 628 second time delay to allow for the containment sump to be filled by the Quench Spray System and any primary plant leakage. In order to test these pumps, a temporary dike must l be erected inside reactor containment around the containment l sump with enough water added to ensure an adequate NPSH for ) l each pump. Per OM-6, Paragraph 5.5, " Pumps Lacking Required j l 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. Alternate Test: These pumps will be tested at full flow once during each refueling outage per 2BVT 1.13.5 (Recirculation Spray Pump Test). j

References:

OM-6. Paragraphs 5.1 and 5.5. l l i [O

Beaver Valley Power Station Unit 2 se2 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 42 of 279 O SECTION V: PUMP RELIEF REQUESTS O l 1

O

Besysr Valley Power Station Unit 2 Issue 2 [ Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 43 of 279 O- PUMP RELIEF REQUEST 1 Pump Mark No(s): All of the pumps in the IST Prograrn. Code Class: 2. 3 System: Various , Function: Various Test Requirement: Per OM-6, Paragraph 6, " Analyses and Evaluation", if deviations fall within the alert range of Table 3a for vibrations, the frequency of testing specified in Paragraph 5.1, shall be doubled until the cause of the deviation is determined and the condition corrected. Basis for Relief: In accordance with 10CFR50.55a(a)(3)(i), relief is requested on the , basis that the proposed alternatives would provide an acceptable level of quality and safety. The ASME OMc Code-1994, Subsection ISTB, Paragraph 4.6, "New Reference Values," states in cases where a pump's test parameters are within the alert or required action ranges and the pump's continued use at the changed values is supported by an analysis, a new set of reference values may be established. Paragraph 4.6 goes on to say that this analysis shall include verification of the f 5 pump's operationaI readiness. The analysis shall also include both a pump level and 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.

                                 , Spectral analysis may be used to determine the mechanical condition of a pump. The reason for testing a pump on double frequency is to obtain additional information so that the condition of the pump may be determined. 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. O l

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i l , Beaver Vallsy Powsr Station Unit 2 Issue 2 l Revision 0  ! INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 44 of 279 ) PUMP RELIEF REQUEST 1 1' ! t Alternate Test: BVPS-2 proposes to implement ASME OMc Code-1994, Subsection  ; l ISTB, Paragraph 4.6 for vibration measurements for all of the pumps  ; in the IST Program. Spectral vibration data is currently being l obtained for each vibration measurement on all of the pumps. Each I time a pump enters the alert range for vibration, an analysis of the i spectral vibration data will be performed to determine the cause of , the higher vibrations. If the analysis supports continued operation, l the pump will be removed from double frequency testing and a new set of reference valves may be obtained. However, to avoid stair-stepping to failure, a new set of reference values may only be obtained once prior to performing corrective maintenance. If the cause of the higher vibrations cannot be determined, or if the data shows a continuing trend such that the condition of the pump may l continue to degrade until it can no longer fulfill its function, the pump will remain on double frequency testing until the condition is corrected.

References:

OM-6. Paragraphs 5.1 and 6, and Table 3. ISTB, Paragraph 4.6. , O t i I r - p-

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Basvar Vallsy Power Station Unit 2 Issun 2 Revision 0 t INSERVICE TESTING iiST) PROGRAM FOR PUMPS AND VALVES Page 45 of 279 l PUMP RELIEF REQUEST 2 i l Pump Mark No(6): See the attached Table. Code Class: 2. 3 l System: Various l l l l Function: Various  ! l Test Requirement: Per OM-6, Paragraph 4.6.1.2(a), " Range", the full-scale range of each l analog instrument shall be not greater than inree times the , l reference value. , Basis for Relief: In accordance with 10CFR50.55a(a)(3)(i), relief is requested on the basis that the proposed alternatives would provide an acceptable  ! level of quality and safety. I The pumps listed on the attached table use instruments which do not meet the requirements of OM-6, Paragraph 4.6.1.2(a), however, the accuracy of the instruments used is more conservative than the , requirements of OM-6, Paragraph 4.6.1.1, " Quality", and Table 1, j

                                                " Acceptable instrument Accuracy". Per the attached table, the combination of higher range and better accuracy for each instrument yields a reading at least equivalent to the reading p                                              achieved from instruments that meet OM-6, Paragraph 4.6.1.1 and                     l
 \j                                             Table 1 requirements. Therefore, relief is requested in accordance                  j with NUREG-1482, Section 5.5.1, " Range and Accuracy of Analog                      '

instru ments". l Alternate Test: Use the instruments listed on the attached table as long as the combination of the higher range and better accuracy for each instrument yields a reading at least equivalent to the reading achieved from instruments that meet OM-6 requirements.

References:

OM-6, Paragraphs 4.6.1.1 and 4.6.1.2(a), and Table 1. NUREG-1482, Section 5.5.1. l , O

5 .j i PUMP REUEF REQUEST 2

  • E M $

m < , 2 @ IST PUMP INSTRUMENTATION h(

  • PumpID# Instrument ID# Condition Requiring Relief Basis for Relief / Alternate Test jQ rn

{ 2CHS*P21 A 2CHS-Pl151 A The range of the gauges is These gauges are the suction pressure gauges for the Charging Pumps. They are -f 8

  • 2CHS*P21B 2CHS-P1152A greater than three times the sized for all modes of pump operation including accident conditions (i e., can take ] g suction from the Recirculation Spray Pumps) with a range of 0-160 psig. Dunng '

2CHS*P21C 2CHS-P1153A reference pressures during _  ; quarterly recirculation flow testing recirculation flow testing, the suction pressures are approx. 25% of the range. y and during full flow testing at " During full flow testing, the suction pressures are approx.10% of the range. Their - e refueling. calibration accuracy is 0.5%, which would yield a reading more accurate than OM-6 j S requirements. O O 2CHS*P22A 2CHS-P1123A The range of the gauges is These gauges are the suction pressure gauges for the Boric Acid Transfer Pumps. g 2CHS*P228 2CHS-P1123B greater than three times the They are sized for all modes of pump operation and Boric Acid Storage Tank levels g reference pressures during with a range of 0-30 psig. During quarterly testing, the suction pressures are n quarterly testing. approx.10-15% of the range. Their calibration accuracy is 0.5%, which would yield Q a reading more accurate than OM-6 requirements. y 2 SIS

  • P21 A 2 SIS-PIS38 The range of the gauges is These gauges are the suction pressure gauges for the Low Head Safety injection g h 2 SIS *P21 B 2 SIS-Pl939 greater than three times the Pumps. They are sized for recirculation and full flow testmg with a range of 0-160 $ C reference pressures during psig. During recirculation flow testing, the suction pressures are approx. 20% of p 2, quarterly recirculation flow testing the range. During full flow testing, the suction pressures are approx.10% of the z [

U and during full flow testing at range. Their calibration accuracy is 0.5%, which would yield a reading more refyeling. accurate than OM-6 requirements. $ r-g 2RSS*P21A Test Gauges The range of the gauges may be A test gauge is installed on the suction line of each Recirculation Spray Pump 2RSS* P218 (Suction Pressure) greater than three times the during testing at refueling A test dam is erected and filled with water to provide In 2RSS*P21C reference pressures during NPSH. The gauges are sized for varying levels of water in the test dam with - 2RSS*P21D testing at refueling. suction pressures varying typically between 5-30 IWC. Test gauges of varying i ranges and accuracies may be used; however, the combination of range and accuracy would yield a pressure readmg within i 0.3 IWC. Therefore, their better calibration with a larger range would yield a reading more accurate than OM-6 requirements. j 2CCP-P21A 2CCP-Pl150A The range of the gauges is These are the suction pressure gauges for the Component Cooling Water Pumps.  ; 2CCP*P218 2CCP-P1150B greater than three times the They are sized for all modes of pump operation with a range of 0-60 psig. A pump 2CCP* P21C 2CCP-P1150C reference pressures during curve is used during quarterly testing as approved by Pump Relief Request No 3. quarterly testing. The suction pressures vary between 24-37% of the range. Their calibration u accuracy is 0.5%, which would yield a reading more accurate than OM-6 $* l requirements. 3 i A

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oEN g c

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N s f PUMP RELIEF REQUEST 2 m E us @ m < k  % IST PUMP INSTRUMENTATION h( ' Pump ID# Instrument ID# Condition Requiring Relief Basis for Relief / Alternate Test y [ v) 2FWE*P23A 2FWE-F1100A The range of the gauges is These flow meters are located in the three lines to the Steam Generators from the -! 8 l 2FWE*P23B 2FWE-Fi100B greater than three times the Auxiliary Feedwater (AFW) Pumps. They are each sized with a range of 0-400 gpm y j 2FWE-F1100C reference flows during full flow testing at cold shutdown and refueling to measure accident flows from the Turbine-Driven AFW Pump [2FWE P22]. They are also used to measure accident flows from the Motor-Driven AFW Pumps [2FWE P23A and B], but at a lesser flow rate of approx. 30% of the range. Their y'y = calibration accuracy is 1.5%, which would yield a reading more accurate than OM4 3 0 6 requirements. O O 2EGF'P21A 2EGF-P1201A The range of the gauges is These are the discharge pressure gauges for the Emergency Diesel Generator Fuel g 1 2EGF'P21B 2EGF-Pl201 B greater than three times the Oil Transfer Pumps. They are sized for all modes of pump operation with a tange g 2EGF* P21C 2EGF-P1201C reference pressures during of 0-30 psig. During bi-monthly testing. discharge pressures are between 8.5 and n 2EGF P21D 2EGF-Pl201D bi-monthlv testing. 10.5 psig, slightly below 1/3 of the range Their calibration accuracy is 1.0%, which j l would yield a reading more accurate than OM-6 requirements. y C 5 A c z a  : O M , k m- ' uJ f [ f t l e 2 i e  !

                                                                                                                                                                                                                                                                                                                                                                                                          ~o A

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Bsaver Vallsy Powsr Station Unit 2 issue 2 Revision 0 [ INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 48 of 279 O PUMP RELIEF REQUEST 3 Pump Mark No(s): 2CCP'P21 A Code Class: 3 2CCP'P218 2CCP'P21C System: 15 - Primary Component Cooling Water l Function: To circulate cooling water through various reactor plant components during normal operation, and through the Residual Heat Removal i Heat Exchangers following an accident in order to achieve and maintain the plant in a cold shutdown condition. Test Requirement: Per OM-6, Paragraph 5.2, " Test Procedure", an inservice test shall be conducted with the pump operating at specified test reference conditions. Per Sub-Paragraph 5.2(b), 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. lg Basis for Relief: In accordance with 10CFR50.55a(f)(5)(iii), relief is requested on the l 'q basis that compliance with the code requirement is impractical at BVPS-2. The amount of Primary Component Cooling Water (CCP) System flow is dependent on tne Service Water System and on seasonal Ohio River water temperatures due to the design of the CCP temperature control system. During Primary Component Cooling Pump testing, additional flow is obtained by placing the Residual ! Heat Removal (RHR) System Heat Exchangers into service. The overall amount of flow may vary by several hundred gallons per l minute between cool winter months and warm summer months. In order to inc: ease flow to a reference value during cold winter months, the manual valves at the discharge of the RHR Heat Exchangers would require throttling in the open direction. These valves are located in the reactor containment building which is l maintained subatmospheric as required by technical specifications. The subatmospheric condition presents a hazardous working environment for station personnel (i.e., requires seit-contained breathing apparatus and entry via an airlock into an atmosphere of approximately 9 psia) and is considered inaccessible for surveillance testing. Surveillance testing that requires reactor containment entry is performed at cold shutdown and refueling. 1 1

Beaver Valley Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 49 of 279 PUMP RELIEF REQUEST 3 Basis for Relief: In order to throttle flow to a reference value during warm summer , months, a manual valve at the discharge of the pumps needs to be used since the RHR Heat Exchanger throttle valves are located inside containment. Operating experience has shown that any throttling of the pump discharge 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 resulting in low flow alarms. This could result in heatup of the Reactor Coolant Pumps to near required manual pump trip setpoints which could ultimately result in a plant trip. In addition, the added thermal cycling of these coolers for pump testing could prematurely degrade these heat exchangers. CM-6, Paragraph 4.5, "To Establisn an 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, requested to use a pump curve, which should provide an equivalent level of quality and safety in trending pump performance and degradation. Flow will be permitted to vary as system conditions require. Delta-P will be calculated and converted to a developed head for which OM-6 ranges will be applied. Alternate Test: A pump curve (developed per the guidelines in NUREG-1482, Section 5.2, "Use of Variat,le Reference Values for Flow Rate and

                             ' Differential Pressure During Pump Testing") will be used to compare flowrate with developed pump head at the flow conditions dictated by seasonal temperatures each quarter per 20ST-15.1,20ST-15.2 and 20ST-15.3 (Component Cooling Water Pump Tests). Since normal flow varies based on Component Cooling Water System requirements due to Service Water System and seasonal Ohio River water temperatures, 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.

References:

OM-6, Paragraphs 4.5 and 5.2 (including 5.2(b)). NUREG-1482, Section 5.2. O

 . ~ _ _ - -    .      . - - - - ..         .    .    - _. - .-        _ . _ - - - - - . -_             _ . - .         .. .

i Beaver Va!Ity Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 50 of 279 PUMP RELIEF REQUEST 4 Pump Mark No(s): 2SWS* P21 A Code Class: 3 l 2SWS* P218 2SWS* P21C System: 30 - Service Water l Function: To provide cooling water to various reactor plant components under normal and emergency conditions, and through the Recirculation Spray Heat Exchangers following a DBA.  ! i l Test Requirement: Per OM-6, Paragraph 5.2, " Test Procedure", an inservice test shall be conducted with the pump operating at specified test reference conditions. Per Sub-Paragraph 5.2(b), the resistance of the system l 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 j l equals the reference value and the flow rate shall be determined and compared to the reference flow rate value. Basis for Relief: In accordance with 10CFR50.55a(f)(5)(lii), relief is requested on the basis that compliance with the code requirement is impractical at BVPS-2. N Operating experience has shown that plant conditions due to heat loads requiring cooling by the Service Water System may preclude returning the Service Water Pumps to the exact flowrate or differential pressure during pump surveillance testing. The Service Water System is dependent on seasonal Ohio River water , temperatures and flow may vary from approximately 6,000 gpm in j i the cool winter months to approximately 14,000 gpm In the warm summer months. In order to increase flow to a reference value during cold winter months, idle heat exchangers would need to be placed into service or additional flow would be needed through heat exchangers already in service. Increased cooling flow through primary and secondary component cooling and chiller unit heat exchangers already in service could result in a thermal transient and a potential plant trip. Clean heat exchangers may require placement into service prematurely if additional flow is required to return to a reference value. Idle heat exchangers are normally held in reserve

       .                                following cleaning to improve plant reliability and safety until one of the inservice heat exchangers becomes fouled.

, m

k Beaver Valley Power Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 51 of 279 l 1 N_/ PUMP RELIEF REQUEST 4 Basis for Relief: In order to throttle flow to a reference value during warm summer

months, any inservice primary and secondary component cooling l and chiller unit heat exchangers would need flow reduced or l isolated which could interrupt flow of cooling water to Train A or l Train B cooling loads resulting in a thermal transient and potential l plant trip. In additior the added thermal cycling due to placement l and/or removal of heat exchangers from service for pump testing l could prematurely degrade the heat exchangers.

t l The thermal transients created by increasing or throttling Service Water System flow to the turbine plant cooling loads raises l operational concerns of stability problems. Changes in oil temperature from the turbine generator lube oil system create vibration problems. Changes in the Hydrogen gas cooler temperatures could imply problems or mask real problems with the generator. Chiller unit heat exchanger flow disturbances often result in a trip of the chiller unit causing reactor containment temperature risks of exceeding the technical specification limit. OM-6. Paragraph 4.5, "To Establish an Additional Set of Reference i Values", provides for multiple sets of reference values. A pump I p. 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 l measurement. Relief is, therefore, requested to use a pump curve, which should provide an equivalent level of quality and safety in i trending pump performance and degradation. Flow will be permitted to vary as system conditions require. Delta-P will be calculated and converted to a developed head for which OM-6 ranges will be applied. Alternate Test: A pump curve (developed per the guidelines in NUREG-1482, l Section 5.2, "Use of Variable Reference Values for Flow Rate and l Differential Pressure During Pump Testing") will be used to compare flowrate with developed pump head at the flow conditions dictated i by Service Water System loads each quarter per 20ST-30.2, ! 2OST-30.3, and 20ST-30.6 (Service Water Pump Tests). Since ! normal flow varies based on Service Water System requirements l due to seasonal Ohio River water temperatures, the most limiting i 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. l

References:

OM-6, Paragraphs 4.5 and 5.2 (including 5.2(b)). NUREG-1482, Section 5.2. i

Beaver Valley Power Station Unit 2 Issue 2 l Revision 0 l lNSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 52 of 279 O {. PUMP RELIEF REQUEST 5 l Pump Mark No(s): 2SWS

  • P21 A Code Class: 3 2SWS'P218 l

2SWS'P21C l System: 30 Service Water Function: To provide cooling water to various re. ctor plant components under j normal and emergency conditions, ano through the Recirculation ' Spray Heat Exchangers following a DBA. I Test Requirement: Per OM-6, Paragraph 4.6.4(b), " Vibration Measurements", on vertical line shaft pumps, measurements shall be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction. Basis for Relief: In accordance with 10CFR50.55a(f)(5)(iii), relief is requested on the basis that compliance with the code requirement is impractical at l BVPS-2. Access to the upper motor bearing housing on the vertical line shaft  ; ! Service Water Pumps for the purpose of measuring vibrations in the axial directioa, cannot be obtained due to the presence of a permanentl/ insialled non-rigid metal top hat covering the entire top of the motor housing. However, vibration measurements in the axial direction are accessible at the lower motor bearing housing of each pump which will provide additional information for trending of pump / motor performance, in addition, the vibration measurements in the orthogonal directions typically provide a better predictor of vibration problems for vertical line shaft pumps. Alternate Test: Measure vibrations on the upper motor bearing housing in two-orthogonal directions (excluding the axial direction), and measure vibrations on the lower motor bearing housing in three orthogonal directions (including the axial direction) each quarter per 20ST-30.2, l 20ST-30.3 and 2OST-30.6 (Service Water Pump Tests).

References:

OM-6, Paragraphs 4.6.4(b). l f O

Beavsr Valley Power Station Unit 2 Issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 53 of 279 O O PUMP RELIEF REQUEST 6 Pump Mark No(s): 2EG F* P21 A Code Class: 3 2EG F'P218 2EG F'P21C 2EG F'P210 ' System: 36 - Diesel Fuel Oil Function: To transfer fuel oil from the underground 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. Test Requirement: Per OM-6, Paragraph 4.6.5. " Flow Rate Measurement", and Table 2. ,

                                         " Inservice Test Parameters", flow rate shall be measured for all pumps. When measuring flow rate, use a rate or quantity meter                                 ,

installed in the pump test circuit if a meter does not indicate the flow rate directly, the record shall inc'.de the method used to reduce the data. Basis for Relief: In at,cordance with 10CFR50.55a(f)(5)(lii), relief is requested on the w basis that compliance with the code requirement is impractical at BVPS-2. 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 i 2% as required by OM-6, Paragraph 4.6.1.1, " Quality", and Table 1, " Acceptable Instrument Accuracy". Alternate Test: Flow rate will be calculated by measuring the level change over time in the Diesel Generator Fuel Oil Day Tank, and converting this data into Fuel Oil Transfer Pump flow rate at least quarterly per 2OST-36.1 and 2OST-36.2 (Emergency Diesel Generator and Fuel Oil Transfer Pump Tests). Referer.ces: OM-6, Paragraphs 4.6.1.1, 4.6.5 and 5.2, and Tables 1 and 2.

          .-_. - - . . . - = , .. - . - - _ - -          . - _ _      . . - . , - _       _ . _ . - - . . . _ _ _ _ _ _       - . . - . - - _ .

Beaver Valley Power Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 54 of 279 O SECTION VI: PUMP MINIMUM OPERATING POINT (MOP) CURVES 1 l 1 l l l O I l 1 4 asme. l I i !O

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Baavar Vgllay Powtr Station Unit 2 Issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 77 of 279 C Pump Name: 218 Service Water Pump Pump Number: 2SWS

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f Beaver Valley Power Station Unit 2 issue 2  ; Revision 0 i INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 83 of 279 i' SECTION Vil: VALVE TESTING REQUIREMENTS h h i e r l i l t F s i [ l 4 6 I l i l l 1 t..-

Bravar Valley Powsr Station Unit 2 Issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 84 of 279 O

 '] The Inservice Test (IST) Program for valves at Beaver Valley Power Station (BVPS), Unit 2, is based on the following:
  • American Society of Mechanical Engineers (ASME) / American National Standards Institute (ANSI) Operational and Maintenance (OM) Standard, Part 10. " Inservice Testing of Valves in Light Water Reactor Power Plants" (OM-10), OMa-1988 addenda to the OM-1987' Edition, in accordance with the ASME Boiler and Pressure Vessel Code, Section XI,1989 edition (the Code).
  • Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs"
  • NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants" 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 cold shutdown condition, in maintaining the cold shutdown condition, or in mitigating the consequences of an accident, at BVPS, Unit 2.

The requirements of the Code and Generic Letter No. 89-04 including Supplement 1 (NUREG-1482) will be followed at all times unless specific relief has been granted by the NRC. l A. 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 i function. Active Category A and B valves shall be full-stroke exercised nominally every i V three months to the position required to fulfill their function unless such operation is not  ! practicable during plant operation. If only limited operation is practicable during plant I operation, the valves may be part-stroke exercised during plant operation and full-stroke exercised during cold shutdowns. If exercising is not practicable during plant operation, the valves may be limited to full-stroke exercising during cold shutdowns, if exercising is nct practicable during plant operation 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 plant operation or cold shutdowns, it may be limited to full-stroke exercising during refueling outages. 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 normai 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 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.

                                                                                                  =    _ _ .

I l Bsav:r Valley Pow:r Station Unit 2 issue 2 l Revision 0 1 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 85 of 279 l The stroke time of all power-operated valves shall be measured 1 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/or an ASME limiting stroke time as follows:

1. Motor-operated valves (MOVs) with baseline stroke times greater than 10 seconds j shall exhibit no more than a i15% change in stroke time when compared to the j baseline time. MOVs with baseline stroke times less than or equal to 10 seconds shall exhibit no more than a i25% or i1 second change in stroke time, whichever j
     ,             is greater, when compared to the baseline time.
2. All other power-operated valves with baseline stroke times greater than 10 seconds shall exhibit no more than a 25% change in stroke time when compared to the baseline time. All other power-operated valves with baseline stroke times less than or equal to 10 seconds shah exhibit no more than a ISO % change in stroke time when compared to the baseline time.
3. Valves that stroke in less than 2 seconds may be exempted from 1 and 2 above. In such cases the maximum limit:ng stroke time shall be 2.0 seconds.
4. The ASME limiting stroke time is based on the following:
a. The Technical Specification value.

O b. ESF response time requirements. O c. The baseline stroke time times 2 for valves with baseline stroke times less than or equal to 10 seconds.

d. The baseline stroke time times 1.5 for valves with baseline stroke times greater than 10 seconds.
e. The design time listed in the UFSAR.

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 l locally at least once every 2 years 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 operr. tion. All valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power. All valves with fail-safe actuators (e.g., air operated valves or air operated control valves) that are applicable to this program are p(_/ tested from the Control Room by the remote operating switch. By placing the control switch to the closed position, or de-energizing the control power, air is vented off of the valve actuator thus positioning the valve in the fail-safe position.

l B: aver Vallay Power Station Unit 2 issue 2 l l Revision 0 INSERVICE TESTING (IST; PROGRAM FOR PUMPS AND VALVES Page 86 of 279 I ['

 \

Corrective action shall be taken if necessary, using the following: I l

1. If a valve fails to exhibit the required change of valve disk position or exceeds its I specified ASME limiting value of full-stroke time, then the valve shall be declared l

inoperante 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, I then the applicable technical specification action statements shall be followed.

O. If the inoperable valve is in a system covered by a technical specification, an i 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 action statements shall be l l followed. I

c. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to I supercede the requirements of any technical specification.
                                                                                                                 ]
2. Valves with measured stroke times which do not meet the acceptance criteria in OM-10, Paragraph 4.2.1.8 (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 of OM-10, Paragraph 4.2.1.8, the cause of the initial deviation shall be analyzed and the results documented in the test.

p> 1

b. If the valve is retested and the second set of data also does not meet the I acceptance criteria of OM-10, Paragraph 4.2.1.8, 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                      j 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 j 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 immediatejy if not removed from service, to demonstrate that the performance parameter which could be affected by the replacement, repair or maintenance is 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 l l the bonnet, stem assembly, actuator, obturator, or control system components. l A I \,_./

I l Barvsr Vall:y Powsr Station Unit 2 issue 2 Revision 0 l INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 87 of 279 , 0 l 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, per relief, are leak rate tested at the frequency specified in Option B of 10CFR50, Appendix J. If the 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. B. 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. l ASME Class 1,2 and 3 safety and relief valves are tested in accordance with ASME/ ANSI l Operations and Maintenance (OM) Standard, Part 1, " Requirements for Inservice l Performance Testing of Nuclear Power Plant Pressure Relief Devices"(OM-1). 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 " group" (i.e., same manufacturer, I type, system application and service media per NUREG-1482. Section 4.3.9,

        " Clarifications in OM-1") included in the BVPS-2 IST Program tested within any 24 months. All ASME Class 2 and 3 safety and relief valves are tested at least once every                  l 10 years, with at least 20% of the valves in each " group" included in the BVPS-2 IST Program tested with any 48 months. A test is defined as a set pressure test and a seat p      tightness test. If any safety or relief valves fail their set pressure test, additional valves          j b      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 group. If any of the additional valves fall, then all remaining valves in the same group shall be set pressure tested. Any safety or relief valve which exreeds its set pressure by 13% or greater shall be 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. Per NUREG-1482, Section 4.3.6, " Safety / Relief Valve Setpoint Adjustments", the NRC has determined that a setpoint 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. Check valves shall be exercised or examined nominally every three months in a manner which verifles obturator (disk) travel to the closed, full-open or partially open position required to fulfill their function unless such operation is not practicable during plant operation. If full-stroke exercising during plant operation is not practicable, it may be limited to part-stroke during plant operation and full-stroke during cold shutdowns. If exercising is not practicable during plant operation, it may be limited to full-stroke exercising during cold shutdowns. If exercising is not practicable during plant operation and full-stroke during cold shutdowns is also not practicable, it may be limited to l part-stroke during cold shutdowns, and full-stroke during refueling outages, if exercising is not practicable during plant operation or cold shutdowns, it may be limited to full-stroke during refueling outages. In the case of frequent cold shutdowns, these check 7 valves need not be exercised more often than once every three months. All check valve i (V testing required to be performed during a refueling outage shall be completed prior to returning the plant to operation. For a check valve in a system declared inoperable or not required to be operable, the exercising test schedule need not be followed. Within 3

  .   .   -.                   ._        _.       _ _ _ ___~ ._._- -.,_ _                        _ _ . _ . _ _               __

8aavsr Valley Power Station Unit 2 Issus 2 Revision 0 , INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 88 of 279 D  ; d months prior to placing the system in an operable status, the valves shall be exercised and the schedule resumed. Check valves that are normally open during plant operation and whose function is to prevent reversed flow shall be tested in a manner that proves that the disk travels to the , seat on cessation or reversal of flow. Check valves that are normally closed during plant , operation and whose function is to open shall be tested by proving that the disk opens to the position required to fulfill its function when flow through the valve is initiated, or when a mechanical opening force is applied to the disk. If the check valves cannot be , tested mechanically or with flow, they will be disassembled and inspected per the ! requirements of Generic Letter No. 89-04. These check valves will normally, but not. ! necessarily be inspected during refueling outages. If a check valve falls to exhibit the required change of disk position by this testing, 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 applicabic technical specification 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, if the condition of the check valve renders the system inoperable, then the applicable system technical specification action statements shall be followed. , 1 3. Corrective action (i.e., MWR) shall be initiated immediately for the check valve's repair or replacement.

4. Nothing in the ASME Boller and Pressure Vessel Code shall be construed to supercede the requirements of any technical specification.

Before returning the check valve to service after corrective action, a retest showing acceptable performance shall be run. C. 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 2, IST Program. All the inservice testing requirements for eacl- different category of valve in the IST Program are summarized in Table 1 of OM-10. This table lists the paragraphs of OM-10 that apply to  ! each different type of valve. 3 l l I 8 { 4 4

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Bsavsr Vallsy Powsr Station Unit 2 issue 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 89 of 279 , b TABLE 1 INSERVICE TEST REQUIREMENTS FROM OM-10 l l Special Test Position Category Valve Leakage Test Exercise Test Procedure indication (See Para.1.4) Function Procedure Procedure [ Note (1)] verification A Active See para. 4.2.2 See para. 4.2.1 None See para. 4.1 A Passive See para. 4.2.2 None None See para. 4.1 B Active None See para. 4.2.1 None See para. 4.1 B Passive None None None See para. 4.1 C (Safety Active None [ Note (2)] See para. 4.3.1 None See para. 4.1 l and Rehef)  ! C (Check) Active None [ Note (2)] See para. 4.3.2 None See para. 4.1 f o Active None None See para. 4.4 None l NOTES: (1) Note additional requirement for fail-safe valves, para. 4.2.1.6. (2) When more than one distinguishing category. characteristic is applicable, all requirements of each of the individual categories are applicable, although duplication or repetition of common testing requirements is not necessary. 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 requ! red to be exercised. Therefore, relief is not required from exercising any l passive valve and no testing requirement is listed in the Valve Outline Section except where remote position verification is required. Certain exemptions from the valve testing requirements of the ASME code defined by l [V] l Paragraph 1.2 of OM-10 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 i 4. External control and protection systems responsible for sensing plant conditions and providing signals for valve operation.

Manufacturer supplied skid-mounted valves (i.e., check valves, SOV's, TCV's, relief valves) which are integral sub-components of, and are required,to support the operation of a parent l pump or other component, are often times not designed to be tested in accordance with the 1 ASME XI Code, regardless of their ASME Code class. Therefore, ASME Code class manufacturer supplied skid-mounted valves are not included in the BVPS Unit 2 IST Program because it has been recognized by the NRC in NUREG-1482, Section 3.4, that the test of the parent pump or other component itself challenges the operability of the sub-components. i This ensures that the skid-mounted valves operate acceptably commensurate with their safety functions, provided satisfactory performance of the parent pump or other component is demonstrated by an applicable surveillance test or the valve is examined separately by a e preventive maintenance activity. !k Records of the results of inservice tests and corrective actions as required by Paragraph 6 of OM-10 are maintained in tabular form. Stroke times of valves will be reviewed for developing trends.

I l Beavsr Valley Power Station Unit 2 issue 2 Revision 0 {lNSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 90 of 279 O If a question on valve testability exists, the IST program should be the controlling document l since each component is individually assessed for testability and inclusion in the IST , l Program. If a valve is specifically called out in the Tech. Specs. (i.e., specific valve mark l l 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 I applicable. The following four sections of this document are the " Valve Outlines", " Valve Cold Shutdown Justifications", " Valve Refueling Outage Justifications" and " Valve Relief Requests" sections. l The "'.'elve Outlines" section is a listing of all the valves in the IST Program, their system l code class, category, size, type, NSA, drawing number and coordinates, testing requirements, specific cold shutdown justification, refueling outage justifications and/or relief request reference numbers, and test procedure numbers and comments.

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 l Paragraph 1.4 of OM-10. In addition, combinations of categories may be utilized. If the valve is not required to change obturator position to accomplish a required function, the fact that it is Parsive (P) will also be indicated. For example, a containment isolation check valve that does not change position would be a category A/C/P valve.
 .O        3. From the valve mark number given, the valve actuator can be determined from the O             list of abbreviations below:

l AOV - Air Operated Valve FCV - Flow Control Valve HCV - Hand Control Valve HYV - Hydraulic Valve LCV - Level Control Valve MOD - Motor Operated Damper MOV - Motor Operated Valve PCV - Pressure Control Valve RV - Relief Valve SOV - Solenoid Operated Valve SV - Safety Valve DMP - Damper (Manual)

4. The normal system arrangement (NSA) will be listed using the abbreviations below:

O - Open S - Shut A - Automatic T - Throttled LO - Locked Open l LS - Locked Shut SS - Sealed Shut ,V O 5. The drawing numbers and coordinates will be the ones used in the Operating l Manuals.  ;

Bsavsr Vallsy Powsr Station Unit 2 Issus 2 Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 91 of 279 p

6. The test requirements will be listed using the abbreviations below:

l QS - Quarterly Stroke l QST - Quarterly Stroke & Time l LT - Leak Rate Test l LTJ - Leak Rate Test per 10CFR50, Appendix J (Option B) SPT - Set Point Test LM - Leakage Monitoring POS - Position Verification NA - Not Applicable

7. The specific Valve Cold Shutdown Justification (VCSJ), Valve Refueling Outage l Justification (VROJ) and/or Valve Relief Request (VRR) reference number (s) will be I listed.
8. The specific test procedure number, required frequency, type of testing, and any comments will be listed using the abbreviations below:

20M - Operating Manual (Unit 2) 2BVT - Beaver Valley Test (Unit 2) 2OST - Operating Surveillance Test (Unit 2) CMP - Corrective Maintenance Procedure , 2 YR - Required every 2 years, but normally done at refueling 5 YR - Required every 5 years, but normally done at refueling

 .G            10 YR - Required every 10 years, but normally done at refueling U             CSD - Cold Shutdown Frequency R - Refueling Frequency SP - Special Frequency Q - Quarterly Frequency                                                                   l M - Monthly Frequency FS - Full Stroke PS - Partial Stroke                                                                       l FD - Forward Direction RD - Reverse Direction RPV - Remote Position Verification (Required every 2 years, but normally done at refueling)

The " Valve Cold Shutdown Justification" section contains the detailed technical description of l conditions prohibiting the required testing of safety-related valves and an alternate test method to be performed during cold shutdowns. Beaver Valley Unit 2 reactor containment is maintained subatmospheric as required by technical specifications. The subatmospheric condition presents a hazardous working environment for station personnel and is considered inaccessible for surveillance testing. Surveillance testing that requires a reactor containment entry will be performed at cold shutdown and refueling. Per OM-10, Paragraphs 4.2.1.2(g) anci 4.3.2.2(g), 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. V) 6 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. I i

l l l l l Beavsr Valley Power Station Unit 2 Issue 2 l Revision 0 INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 92 of 279 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 1 method to be performed during refueling outages. 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.  ! l l 1 l I 1 II a l l 1 l l i I I l O 1

Beavsr Valley Power Station Unit 2 issue 2 l Revision 0 l { INSERVICE TESTING (IST) PROGRAM FOR PUMPS AND VALVES Page 93 of 279 1 fx l l\ SECTION Vill: VALVE OUTLINES l l l l t' % L) i n) L

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VALVE OUTLINE , SYSTEM NAME- Chomscal and volume Control SYSTEM NUMSER: y m <  : 3 @ .l Velve Drawing VCSJ, VROJ < Vatwo Mark Valve Vatwe Size Vafwe Test or Relief - =[ Number Class Category (in-) Type NSA OM No. Coord. Requirement Requests Comments H @ M 2CHS-MOV308A 2 A 2 Gate O 7-3 B-3 QST VROJ7 2OST-l 10-Stro6 e & Time Closed (CSD or R)-(RPV) Q g T -

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2CHS*MOV8131B 2 B 8 Gate LO 7-1 A C-5 QST VROJ13 20ST 110 Stro6e & Time Closed (CSD or Rt(RPV) 2CHS*MOV8132A 2 8 4 Gate LO 7-1A D-2 QST VROJ t3 20ST-t t& Stroke & Time Closed (CSD or R).(RPV) 2CHS*MOV81320 2 B 4 Gate LO 71A D-2 QST VROJ t3 20ST-110 Stro6 e & Time Closed (CSD or R)(RPV) 2CHS*MOV8133A

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N VA OU LINE E [ W 03 SYSTEM NAME: fleactor Plant Vents and Drains (Aerated Drams) SYSTEM NUMSER: 9 A. < N O valve Drawing VCSJ, VROJ $- Valve Mark Valve Valve Size Valve Test or Relief O_ g N umber Class Category (in.) Type NSA OMMA Coord. Requirement Requests Comenents 2DAS*AOV100A 2 A 2 Gobe S F-4 QST M 9- 1 20ST-47 3A(38)-Stro6e & Time Closed (Q)(RPV)

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VALV U L NE E [ M ca SYSTEM MAME: Resedual Heat Remawat SYSTEM NUMBER: 10 m < 2 e Valve Drawing VCSJ, VROJ $ ' i Valve Mark Valve Valve Size Vane Test or Relief Number Class Category (in.) Type NSA OM No. Coord. Requirement ' Requests Comments h ' n<>= 2RHS*3 2 C 10 Check IO- l B-3 QS VCSJS 2OST-10 tfS FD (CSD) m x QS VCSJS 20ST-10 3 FS RD (CSD) 2 C. Check E3 QS VCSJ5 a

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2RHS*FCV605B 2 8 8 Butterfly T 10-1 F-5 QST VCSJ6 20ST-10 4-Stro6e, Time & Fait Closed (CSD).(RPV) 2RHS"MOV701A 1 A 12 Gate S 10 1 C-1 QST VCSJF 20ST 10 3-Stroke & Tame Open/ Closed (CSD)(RPV) l LT 20ST-10 5-Leak Test (2 YR)(R per Tech Specs) j i 2RHS*MOV7010 1 A 12 Gate S 10-1 E1 QST VCSJ7 20ST-10 4 Stro6e & Time Open/Csosed (CSD)(RPV) [ '{ l I LT 20ST 10 5-Leak Test (2 YR)(R per Tech Specs)  ; t 2RHS*MOV702A 1 A 12 Gate S 10-1 41 QST VCSJ7 2OST-10 3 Stro6e & Time Open/ Closed (CSD)(RPV) T, j 0 . En e LT 20ST to 5 Leak Test (2 VR)(R per Tech Specs) , t k_

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9 i BVpS-2 IST VALVE OUTLINE E SYSTEM MAME: Safety iniection SYSTEM NUMBER: II @ < 1 2 e talve Orasens VCSJ, VROJ $ or Relief t Valve Matt Valve Class Valve Category Size Watwe Type NSA OMNo. Coord- Requirement Test Requests Comments [

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2 SIS *130 2 A/C 10 Check I l-1 F-9 QS VROJ22 20ST-114-FS.FD.RD by Mechanecal Exerciser (CSD or R) O ,

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' > x Z O M LTJ 2BVT 147 5-Leak Test (SP) F 1 2 SIS *t32 2 A/C 10 Check 11-1 G-9 QS VROJ23 20ST-110-FS FD RD by Mechamcal Exerciser (CSD or R) < m y (D  ? I i LT 20ST-It 16. Leak Test (2 YR)(CSD or R per Tech Specs) , 1 I 2 SIS *t33 2 A/C 10 Check 11-1 E-9 QS VROJ23 2OST-114FS.FD.RD by Mechanecal Exerciser (CSD or R)  ; i LT 20ST 1116 teak Test (2 YR)(CSD or R per Tech Specs) 2 SIS *t34 1 C 2 Check 11-1 C-9 QS VROJ24 2OST It 14B FS.FD (R) 1 2 SIS 135 1 C 2 Check 11-1 D-9 QS VROJ24 2OST-11 14MS FD (R) n na O e , 2 SIS 136 1 C 2 Check 11-1 D-9 QS VROJ24 2OST t t 148-FS.FD (R) , [ Oe  ! a= < r i 2 SIS 13F I C 2 Chen I l-1 C-9 QS VROJ24 20ST-I t 14B-FS,FD (R) O E$_

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SYSTEM NAME: Safety injection SYSTEM NUMBER: gg m <

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Valve Mark . valve Valve Size Test o Relief [ N umber Class Category (in-) valve Type NSA OM No. Coord. Requirement R equests Comments Q = C 2 Chack C-9 QS VROJ24 20ST It 148-FS FD (R) T 2StS*138 1 ll-l

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2 SIS *139 1 C 2 Check 11-1 C-9 QS VROJ24 2OST 1114B FS FD (R) g e n~ CD (n - 2 SIS *l41 1 A/C 12 Check 6-1 E-6 QS VRRt 20ST-101-PS FD(CSD) _-0 Os i 2BVT t II 3-FS FD (R) y 6' M 3 LT 2OST-t14 Leak Test (2 YR)(CSD or R per Tech Specs) O O M 2 SIS *t42 1 A/C 12 Check I 1 -2 F- 9 QS VRR1 2BvT 1113 FS.FD (R) > ri LT 2OST-ti 5 Leak Test (2 YR)(R per Tech Spe(s) O M 0 2 SIS *145 1 A/C 12 Check 6- 1 DG QS VRRt 2 CST 10 2 PS FD(CSD) C 28VT I 1l 3 FS FD (R) E m LT 20ST-l14 Leak Test (2 YR)(CSD or R per Tech Specs) 2Si5 147 1 A/C 12 Check It 2 F-F QS VRRt 2BVT 1113 FS.FD (R) 5 ~ r-LT 20ST-115-Leak Test (2 YR)(R per Tech Specs)

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2 SIS *148 I A/C 12 Check It 2 F-4 QS VRRI 2BVT I 113 FS FD (R) LT 20ST-13 5 Leak Test (2 TR)(R per Tech Spets) - I 2 SIS 151 1 A/C 12 Check 6- l D-5 QS VRR1 28VT t.I13-FS FD (R) LT 2OST-t14 Leak Test (2 YR)(R per Tech Spets) 2 SIS-RvlF5 2 A/C %xt Reuer I t -2 Fl SPT 2BVT I 60 5-(13 YR) T tu o G LTJ 2BVT l 415-Leak Test (SP) , Oe O< _ 2 SIS *545 8 C 6 Check Il-8 l A-9 QS VROJ25 2OST-t114A FS FD (R) ,5$ 0 0 C f M 3 (D CD O N

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0 LT 2BVT I 4711-Leak Test (2 YR) C o r us C 2 SIS *MOV840 2 A I Globe S 11-1 D6 QST 20ST-47 3A(3B) Stro6 e & Time Open/Ciosed (Q)(RPV)

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g Z O M LT BVT 14711-Leak Test (2 YR)

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U3 $ 2 SIS-MOVS65C 2 B 12 Gate 0 11-2 F-9 OST VCSJ9 2OM-514 C & 20ST-I to-Strote & Time Closed d ED j (CSD) 2BVT 1113-(RPV) y 6 3 2 4 2 SIS-MOV967A 2 B 3 Gate S 11-1 B-2 QST 2OST-47 3A(3B)-Stro6 e & Time Open (Q) (RPV) O ' O i 2 ' 2 SIS Move 678 2 B 3 Gate S 11 1 C-2 QST 20ST-47 3A(38) Stroke & Time Open (Q)(RPV) M h 5 n i 2 SIS-MOV967C I A 3 Gate S 11-1 C-5 QST 20ST-47 3A(38)-Stro6e & Time Open/ Closed (Q)(RPV) O 1 3 i I T LT 2BVT I 47 Il-Leak Test (2 YR) C l 5 > T i un C i 2 SIS-Move 67D 2 A 3 Gate S 11-1 C-4 QST 20ST-471A(3B)-Stro6e & hme Open/ Closed (Q).(RPV) 3 z M 5 O L LT 2BvT 14711-Leak Test (2 YR) l~ I 2SISEV068A Globe 20ST-47 3A(38) Stroke & Time Open/ Closed and 2 B 1 S 11-1 D-5 QST Fail Closed (Q) g3 1 2OST 1 to(RPV) 2 SIS N B 2 B 1 Globe S 11-1 B-3 QST 20ST-47 3A(38) Stro6 e & Tsme Open/ Closed and [ Fait Closed (Q) v 20ST-l 10 (RPV) [ 2 SIS-MOV869A 2 A 3 Gate S 11-1 A-3 QST VROJ29 20ST-110-Stro6e & Time Open/ Closed (CSD or R)(RPV) f L LT 2BVT 1471l-Leak Test (2 YR) f 2 SIS-MOV8698 2 A 3 Gate S 11-1 B-3 QST VROJ29 20ST-114 Strobe & Time Open/ Closed (CSD or R)(RPV) O k tu y 5 LT 2BVT t 4711-Leak Test (2 YR)

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Z g $ I ] a g O f.83  ! (11 .- 2StS*895 2 C 4 Check 11 1 G-4 QS 20ST It 2-FS.FD (Q) H g m 5' 2 s  ; i QS 20ST-1 1 FS,RD (Q) g & O i 2StS-MOV8809A 2 A 14 Gate O I t-t E- 1 QST 20ST-47 3A(3B) Strobe & Time Closed (Q)(RPV) >

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LT 28VT 14711-Leak Test (2 YR) O r . 2 .i T r 2 SIS-MOV880S8 2 A 14 Gate O 11-1 G-2 QST 20ST-47 3A(38) Stro6e & Tame Closed (Q)(RPV) C  ; E T 1 h LT 2BVT t 471t-Leak Test (2 YR)-

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Z O M 2 SIS-Mov88 t t A 2 B to Cate S t t-t E-5 QST 20ST-47 3A(38)-Stro6e & Teme Open (Q)(RPV) r- , 2 SIS *MOV88118 2 B to Gate S 11 1 F-5 QST 20ST-47 3A(38) Strobe & Tame Open (Q)(RPV) < f m  ! M , 2 SIS *RV8864A 2 C. %xt Relief Il-1 F-7 SPT 28VT 160 5-(10 YR) I 2 SIS *RV88648 2 C %ut Relief 11-1 G-6 SPT 2BVT 160 5-(10 YR) 2 SIS *Rv8865 2 C %xt Reisef 11-9 F-7 SPT 28VT 160 5-(10 VR) 2 SIS *MOV8887A 2 B to Gate O 11-1 F-7 QST 2OST-47 3A(38) Stro6 e'& Tame open/CloseJ (Q) (RPV) 2 SIS-MOV8887B 2 0 10 Gate O t1-1 F-8 QST 20ST-47 3A(38) Stroke & Time Open/ Closed (Q)(RPV)

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