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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999
Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs
ML20210M6171999-08-0404 August 1999
Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys
ML20210B5121999-07-15015 July 1999
Pbnp Simulator Four-Yr Rept
ML20209C1831999-07-0101 July 1999
Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS
ML20205R6741999-04-12012 April 1999
Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR
ML20203A2261999-02-0202 February 1999
Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design
ML20202F6521999-01-29029 January 1999
Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes
ML20154G5601998-10-0707 October 1998
Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility
ML20154H4231998-10-0505 October 1998
Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis
ML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20154C1941998-09-28028 September 1998
Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels
ML20153G7361998-09-23023 September 1998
Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers)
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20236W7861998-07-30030 July 1998
Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability
ML20249C3811998-06-22022 June 1998
Proposed Corrected Tech Specs Pages Re Radiological Effluents
ML20248C6651998-05-28028 May 1998
Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses
ML20248G1671998-05-27027 May 1998
Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1
ML20203K9571998-02-26026 February 1998
Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12
ML20203K2981997-12-15015 December 1997
Proposed Tech Specs Re Administrative Controls
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20247P2681997-09-23023 September 1997
Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles
ML20210M5151997-08-14014 August 1997
Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test
ML20210J0331997-08-0707 August 1997
Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording
ML20140C9111997-06-0303 June 1997
Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1
ML20141C5931997-05-0909 May 1997
Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140D7251997-04-14014 April 1997
Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c
ML20140D7091997-04-14014 April 1997
Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20137N6451997-04-0202 April 1997
Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20137C8331997-03-20020 March 1997
Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
ML20137P8441997-02-14014 February 1997
Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews)
ML20140G9351997-02-14014 February 1997
Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling)
ML20140G8921997-02-14014 February 1997
Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown)
ML20140G9401997-02-0707 February 1997
Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing
ML20138K2991997-01-31031 January 1997
Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory
ML20138K2031997-01-31031 January 1997
Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1
ML20138K2551997-01-31031 January 1997
Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1
ML20138K2411997-01-31031 January 1997
Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1
ML20138K3231997-01-31031 January 1997
Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode)
ML20137P8551997-01-31031 January 1997
Brine Tank Standpipe Mod
ML20138K3071997-01-31031 January 1997
Rev 38 to OP 9C, Containment Venting & Purging
ML20138K2901997-01-31031 January 1997
Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2
ML20138K2641997-01-31031 January 1997
Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2
ML20138K4991997-01-31031 January 1997
Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2
ML20138K3181997-01-31031 January 1997
Rev 33 to RP 1B, Recovery from Refueling
ML20138K3031997-01-31031 January 1997
Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes
ML20138K2251997-01-31031 January 1997
Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2
ML20138K4791997-01-31031 January 1997
Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1
ML20138K4701997-01-31031 January 1997
Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1
ML20138K5041997-01-31031 January 1997
Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2
ML20138K5161997-01-31031 January 1997
Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2
ML20138K4751997-01-31031 January 1997
Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1
ML20138K5231997-01-31031 January 1997
Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2
ML20138K7311997-01-31031 January 1997
Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly)
ML20138K7171997-01-31031 January 1997
Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1
ML20138K3121997-01-31031 January 1997
Rev 43 to RP 1A, Preparation for Refueling
1998-09-30
[Table view] |
Text
-_a -_ w. & 6-+ - _.m- a - L -W--.,,: A s.: an. . Je w- , - - - - - , - , - -A---seme- A,,eaSm,b-l NUCLEAR POWER BUSINESS UNIT IT 525B
< INSERVICE TESTS MAJOR
- .' Revision 8 l LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 i MAINTENANCE PROGRAM TEST OF 2SI-896A&B, SI PUMP SUCTION VALVES (REFUELING) 1
- UNIT 2 Date RECORD PROCEDURE VERIFIED CURRENT AND CHECKED FOR 1TMPORARY CllANGES. IF FIELD DSS COPIES REQUIRED. USE PDF-0026i IAW NP 114 AND DO M COMPLETE THIS BLOCK.
BY: DATE:
1.0 PURPOSE To detect and quantify leakage through 2SI-896A&B, SI pump suction isolation valves.
l 1.1 This test is part of the Leakage Reduction and Preventive Maintenance Program required
, by NUREG-0578, Item 2.1.6a.
! l i
1.2 This test is part of the program to evaluate the integrity of post-accident recovery systems outside containment as required by Technical Specification Table 15.4.1-2(22).
2.0 REFERENCES
2.1 P&lDs 2.1.1 110E035, Sheet 2, SIS 2.1.2 110E029, Sheet 1, ACS 2.2 EDS Nuclear Report, Leakage Reduction and Preventive Maintenance Program at Point Beach Nuclear Plant, dated 07-24-80.
3.0 P_RECAUTIONS AND LIMITATIONS 3.1 Liquids leaking from any components of the high head SI system will be mildly radioactive, and appropriate Health Physics practices should be observed.
3.2 Since the allowable leakage rates per the LRPMP are small, accurate measuring and timing techniques and calculations are mandatory to provide realistic data.
INITIALS 4.0 INITIAL CONDITIONS 4.1 The RCS is in the cold shutdown or refueling shutdown condition.
4.2 Both trains of HHSI may be removed from service for the test.
970512o241 97o5057 Page 1 of 7 CONTINUOUS USE PDR ADOCK 05000301 P PDR
i NUCLEAR POWER BUSINESS UNIT IT 525B -
l INSERVICE TESTS MAJOR l
Revision 8 a i
LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, l
SI PUMP SUCTION VALVES (REFUELING)
UNIT 2 i INITIALS 4.3 Test equipment required:
4.3.1 Three plastic buckets 4.3.2 Stopwatch Record ID No.
4.3.3 2 gpm hydro pump 4.3.4 Test pressure gauge calibrated for 150 psig.
4.4 Permission to Perform Test The conditions required by this test are consistent with required plant conditions including equipment operability. Permission is granted to perform this test.
DSS Time Date 5.0 PROCEDURE 5.1 System Pre-Test Alienment and Data 5.1.1 Align the following components: POSITION 2A52-74 2P-15A Bkr. Racked-Out 2A52-68 2P-15B Bkr. Racked-Out 2SI-866A 2P-15A discharge MOV Shut 2SI-866B 2P-15B discharge MOV Shut 2SI-825A SI pump RWST suction MOV Shut 2SI-825B SI pump RWST suction MOV Shut 2SI-826A SI pump BAT suction MOV Shut 2SI-896A 2P-15A suction MOV Shut 2SI-896B 2P-15B suction MOV Shut 2SI-876A 2P-15A mini-recire Shut 2SI-876B 2P-15B mini-recire Shut 2SI-D8C 2PI-974 gauge isolation Shut 5.1,2 With 2SI-825C open, verify a leak-off flow path that is air free by momentarily opening 2SI-D8B and observing a solid stream of water to a container, then shut 2SI-D88.
Page 2 of 7 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 525B INSERVICE TESTS MAJOR Revision 8 LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, SI PUMP SUCTION VALVES (REFUELING)
UNIT 2 INITIALS 5.1.3 Depressurize 2P-1SA&B pump casings by opening 2SI-V14A
& 15A respectively to a container. .
5.1.4 Record SI pump pressure:
2P-15A per 2PI-923 psig 2P-15B per 2PI-922 psig 5.1.5 Installjumper between 2SI-D8B and calibrated sight glass.
5.1.6 Verify shut SI-912C sight glass drain.
Verify open SI-912B sight glass vent.
5.1.7 Crack open 2SI-D8B to establish a level in the bottom of the calibrated sight glass.
5.1.8 Shut 2SI-825C,2P-15A&B mini-suction AOV.
5.1.9 Depressurize the leak-off volume by opening 2SI-D8B.
NOTE: Allow sufpcient timefor leakage to stabilize, ifpresent.
NOTE: 1 cm change in level equals I seem volume.
5.1.10 Measure and record the background leak rate at 2SI-D8B.
seem 5.1.11 Shut 2SI-D8B.
5.2 Seat Leakane Test of 2SI-896A 5.2.1 Shut 2SI-V14A,2P-15A casing vent.
5.2.2 Attach hydro pump to 2SI-V14A.
I I
l Page 3 of 7 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 525B
~
INSERVICE TESTS MAJOR Revision 8 LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, SI PUMP SUCTION VALVES (REFUELING)
UNIT 2 INITIALS
- DO NOT PRESSURIZE 2P-15A SUCTION TO
>110% OF DES.tGN PRESSURE (165 PSIG).
5.2.3 Start hydro pump and pressurize hydro hose to 100 psig, then open 2SI-V14A.
5.2.4 Operate hydro pump as required to maintain test system pressure at 130-150 psig per hydro pump test gauge.
5.2.5 Record 2P-15A pressure per: Test gauge psig 2PI-923 psig NOTE: Allow sufficient timefor leakage to stabilize before measuring andrecordingjlow.
NOTE: 1 cm change in level equals 1 sccm volume.
5.2.6 Slowly open wide 2SI-D88 to a container. When leakage has stabilized, measure and time the leakage rate and record.
scem 5.2.7 Shut 2SI-V14A, then secure the hydro pump.
5.2.8 Open 2SI-876A mini-recire and depressurize 2P-15A, then reshut 2SI 876A.
5.2.9 Shut 2SI-D8B.
5.2.10 Disconnect hydro hose at 2SI-V14A, then open 2SI-V14A and vent 2P-15A to a container.
5.2.11 Subtract Step 5.1.10 background leakage from Step 5.2.6 total leakage and record leakage attributed to 2SI-896A.
seem 5.3 Seat Leakane Test of 2SI-8968 5.3.1 Shut 2SI-V15A,2P-1SB casing vent.
5.3.2 Attach hydro pump to 2SI-V15A.
Page 4 of 7 CONTINUOUS USE
l
~~ l NUCLEAR POWER BUSINESS UNIT IT 525B INSERVICE TESTS MAJOR
/ Revision 8 I
LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, S1 PUMP SUCTION VALVES (REFUELING)
UNIT 2 INITIALS
- DO NOT PRESSURIZE 2P-15B SUCTION TO
>110% OF DESIGN PRESSURE (165 PSIG).
5.3.3 Start hydro pump and pressurize hydro hose to 100 psig, then !
open 2SI-V15A.
J 5.3.4 Operate hydro pump as required to maintain test system pressure at 130-150 psig per hydro pump test gauge.
5.3.5 Record 2P-15B pressure per: Test gauge psig 2PI-922 psig NOTE: Allow sufficient timefor leakage to stabilize before measuring and recordingflow.
NOTE: 1 cm change in level equals 1 scem volume.
5.3.6 Slowly open wide 2SI-D8B to a container. When leakage has stabilized, measure and time the leakage rate and record.
seem 5.3.7 Shut 2SI-V15A, then secure the hydro pump.
5.3.8 Open 2SI-876B mini-recire and depressurize 2P-15B.
5.3.9 Shut 2SI-D88, drain sight glass, disconnect jumper, and install plug / cap on 2SI-D8B.
5.3.10 Disconnect hydro hose at 2SI-V15A.
5.3.11 Subtract Step 5.1.10 background leakage from Step 5.3.6 total leakage and record leakage attributed to 2SI-896B seem 5.3.12 Shut 2SI-V14A,2P-15A casing vent.
5.3.13 Open 2SI-876A,2P-15A mini-recire.
Page 5 of 7 CONTINUOUS USE
.i NUCLEAR POWER BUSINESS UNIT IT 525B -
- INSERVICE TESTS MAJOR Revision 8 -
LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, S1 PUMP SUCTION VALVES (REFUELING)
UNIT 2 INITIALS 5.4 Post-Test System Alienment
- 5.4.1 Position the following: POSITION 1
NOTE: S&Fmeans valve shut withflange, cap orplug installed ;
2SI-D8B Leak-off test connection S&F /
l 2SI-D8C 2PI-974 gauge isolation Shut
( 2SI-V14A 2P-15A casing vent S&F /
- 2SI-V15A 2P-15B casing vent S&F /
i 2SI-876A 2P-15A mini-recire LO /
! 2SI-876B 2P-15B mini-recire LO /
. 2SI-825C SI pump mini-suction AOV Open /
l 2SI-896A 2P-15A suction MOV Open /
2SI-896B 2P-15B suction MOV Open /
1 2
5.4.2 The DSS should prescribe the position of the following:
2SI-825A SI pump RWST suction MOV /
- 2SI-825B SI pump RWST suction MOV / I 2SI-866A 2P-15A discharge MOV /
2SI-866B 2P-15B discharge MOV / I 2A52-74 2P-15A Bkr. / i 2A52-68 2P-15B Bkr. /
6.0 ACCEPTANCE CRITERIA l
l 1
Valve through-leakage should not exceed 30 cc/hr per inch of valve diameter. l This is only to be used as a guideline, and may be changed to be consistent with l the "as-low-as-practicable" philosophy. 2SI-896A&B are 6 inch diameter valves, therefore seat leakage of each should not exceed 180 cc/hr or 3.0 scem. Consider i valve repair ifleakage exceeds 3.0 secm.
l 4
Page 6 of 7 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 525B INSERVICE TESTS MAJOR l
.' Revision 8 l LEAKAGE REDUCTION AND PREVENTIVE April 7,1997 MAINTENANCE PROGRAM TEST OF 2SI-896A&B, j S1 PUMP SUCTION VALVES (REFUELING)
UNIT 2 INITIALS 7.0 ANALYSIS TO BE COMPLETED BY THE OPERATIONS MANAGER OR IIIS REPRESENTATIVE.
i l
7.1 Comparison with allowable ranges of test values and analysis of ;
deviations complete. I i
7.2 Any requirements for corrective action?
Yes No l If yes, give details in the remarks section and WO No. .
]
7.3 Data analyzed. By Date Remarks:
l Page 7 of 7 CONTINUOUS USE
