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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
1 3 NUCLEAR POWER BUSINESS UNIT ORT 6 ,
OPERATIONS REFUELING TESTS MAJOR
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- Revision 16 CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 UNIT 2 Date RECORD 1 DSS PROCEWRE NmMM AND CHMED FOR TEMPORARY CHANGES. IF FIE!.D COPIES REQUIRED. USE PDF-0026i IAW NP 1.2.4 AND DO M COMPLETE Tills DLOCL Operations Manager gy; 947g 1.0 PURPOSE To test the actuation of the containment spray system as required by Technical Specification 15.4.5.I.B.1 and 2.
INITIALS 2.0 INITI AL CONDITIONS 2.1 Unit 2 is in cold or refueling shutdown condition. j l
2.2 Spray pump breakers in test. j 2.3 Purge supply and exhaust valve cleaning NOT in progress.
2.4 Four stopwatches available.
Stopwatch ID #1 Stopwatch ID #2 Stopwatch ID #3 Stopwatch ID #4 2.5 Perform the following valve lineup:
2SI-868A Spray isolation Shut 2SI-868B Spray isolation Shut 2SI-831 A Spray additive tank isolation Shut 2SI-831B Spray additive tank isolation Shut 2SI-870A 2P14A Suction from RWST Shut SI-870B 2P14B Suction from RWST Shut 2S'l-871 A 2P14A Suction from RIIR Shut 2SI-871B 2P14B Suction from RIIR Shut i
e 2.6 Controllers for 2SI-836A and 2SI-836B are in AUTO and NORMAL /powc on.
' l 9705120261 970505- Page 1 of 9 CONTINUOUS USE i PDR ADOCK 05000301 P PDR;
. NUCLEAR POWER BUSINESS UNIT ORT 6 '
OPERATIONS REFUELING TESTS MAJOR Revision 16 ,
CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 ,
UNIT 2 INITIALS 2.7 I&C Group notified for relay verification.
2.'8 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 3.0 PROCEDURE l NOTE: Timing 2SI-836A& B using the C-01 status lights.
3.1 Station individuals to time 2P-14A&B and 2SI-836A&B.
3.2 At time zero, push the manual spray buttons for Unit 2 and start the ,
stopwatches for pump and valve timing.
3.3 Verify the following:
r 3.3.1 2SI-860A Open 2SI-860B Open 2SI-860C Open 2SI-860D Open l 3.3.2 Record as-found time delay for closing of containment spray pump breakers.
2P-14A seconds 2P-14B seconds ,
l 3.3.3 Record as-found time delay for opening of 2SI-836A and 2SI-836B.
2SI-836A seconds 2SI-836B seconds 3.3.4 Containment spray and containment ventilation isolation annunciators alarm.
l Page 2 of 9 CONTINUOUS USE
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. NUCLEAR POWER BUSINESS UNIT OPERATIONS REFUELINO TESTS MAJOR Revision 16 y March 17,1997 CONTAINMENT SPRAY SEQUENCE TEST UNIT 2 INITIALS 3.4 Reset both trains of containment spray (Rear C-01) and containment ventilation isolation (Rear 2C-04).
/
l 3.5 Check acceptability of spray components: __
Acceptable Rance (Circle One) 2B52-38A 2P-14A breaker close time 9.0 see to 11.5 see SAT /UNSAT 2B52-27A 2P-14B breaker close time 9.0 see to 11.5 see SAT /UNSAT
- 2SI 836A NaOH addition AOV open time 108 see to 144 see SAT /UNSAT
- 2SI-836B NaOH addition AOV open time 108 see to 144 see SAT /UNSAT l
- includes operator response time 3.6 I&C adjust the associated time delay per ICP 5.58 for any components that are outside the acceptable range. Repeat Steps 3.1 through 3.5 as required to obtain acceptable time delay (s). Record as-left time delays.
2P-14A TDR is TDR-18 in 2C-156 seconds 2P-14B TDR is TDR-28 in 2C-166 seconds 2SI-836A TDR is 2/926A in C-01 seconds 2SI-836B TDR is 2/926B in C-01 seconds 3.7 I&C to verify automatic containment spray actuation:
3.7.1 Verify the following containment spray logic bistable trip switches are in NORMAL position.
(Red) P/945 (White) P/946 P/949 (Blue) P/947 P/948 (Yellow) P/950 3.7.2 At "A" Train Safeguards Cabinets 2C-156,2C-157, verify test switches are in normal position.
2PC-945B 2PC-946B (A2) 2PC-947B 2PC-948B (B2) 2PC-949B 2PC-950B
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NUCLEAR POWER BUSINESS UNIT ORT 6 OPERATIONS REFUELING TESTS MAJOR ,
Revision 16 CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 -
UNIT 2 INITIALS 3.7.3 At "B" Train Safeguards Cabinets 2C-166,2C-167, verify test switches are in normal position.
2PC-945B 2PC-946B (A2) 2PC-947B 2PC-948B (B2) 2PC-949B 2PC-950B 3.7.4 Place the following containment spray logic bistable trip switches to trip position.
1 (White) P/946 P/949 (Blue) P/947 P/948 1
3.7.5 Verify the following relays pulled in:
2-CSA in (2C-156) 2-CSB in (2C-166)
)' 3.7.6 Place the following containment spray logic bistable trip switches to normal position.
1 (White) P/946 P/949 i (Blue) P/947 P/948
- USE CARE TO AVOID ELECTRIC SIIOCK AND SilORTING TERMINALS WilEN CIIECKING AND ADJUSTING LATCil CLEARANCE.
- CilECK CLEARANCE WITII A PLASTIC i FEELER G AUGE.
3.7.7 Check relay latching clearance between 0.010" and 0.015" on the following relays.
Adjust as necessary.
Found Foundl 2-CSA 2-CSB l Page 4 of 9 CONTINUOUS USE l
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-' NUCLEAR POWER BUSINESS UNIT ORT 6 OPERATIONS REFUELING TESTS MAJOR
-Revision 16 CONTAINMENT SPRAY SEQUENCE TEST March 17,1997
- UNIT 2 _.
INITIALS 3.8 Reset both trains of containment spray.
NOTE: Ifadjustments were made in Step 3.7.7, then perform Step 3.9. Ifno adjustments were made, N/A Steps 3.9 through 3.10 and go to Step 3.11.
3.9 Recheck the latch clearance on 2-CSA and 2-CSB by performing the following:
3.9.1 Place the following containment spray logic bistable trip switches to trip position.
(White) P/946 P/949 i (Blue) P/947 P/948 3.9.2 Verify the following relays pulled in:
2-CSA in (2C-156) 2-CSB in (2C-166) 3.9.3 Place the following containment spray logic bistable trip switches to normal position.
t (White) P/946 P/49 (Blue) P/947 P/948
- USE CARE TO AVOID ELECTRIC SIIOCK AND SilORTING TERMINALS WilEN CIIECKING AND ADJUSTING LATCII CLEARANCE.
- CIIECK CLEARANCE WITII A PLASTIC FEELER G AUGE.
3.9.4 Check relay latching clearance between 0.010" and 0.015" on the following relays.
Adjust as necessary.
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NUCLEAR POWER BUSINESS UNIT ORT 6 OPERATIONS REFUELING TESTS MAJOR Revision 16 CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 l UNIT 2 INITIALS NOTE: If adjustments were made in Step 3.9, then repeat Steps 3.9 through 3.10. If no adjustments were made, go to Step 3.11.
3.9.5 Record as left clearance.
Left Left l i
2-CSA 2-CSB 3.10 Reset both trains of containment spray. i l
3.11 Return safeguard test switches to the test position.
2 3.11.1 At "A" Train Safeguards cabinets 2C-156,2C-157, place the j following switches to the test position.
2PC-945B 2PC-946B l (A2) 2PC-947B 2PC-948B (B2) 2PC-949B 2PC-950B l l
3.11.2 At "B" Train Safeguards Cabinets 2C-166,2C-167, place the following switches to the test position. ;
1 2PC-945B 2PC-946B (A2) 2PC-947B 2PC-948B (B2) 2PC-949B 2PC-950B 3.12 Verify that 2SI-836A&B sodium hydroxide addition valves are shut.
l 3.13 Place control switches for BOTII containment spray pumps 2P-14 A and 2P-14B in PULLOUT.
l 3.14 Open breakers for BOTil containment spray pumps.
l 2B52-38A 2P-14A Breaker !
2B52-27A 2P-14B Breaker l
l l Page 6 of 9 CONTINUOUS USE l
e NUCLEAR POWER BUSINESS UNIT ORT 6 OPERATIONS REFUELING TESTS MAJOR Revision 16
_ CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 UNIT 2 INITIALS I'
3.15 Perform the following lineup, or as directed by DSS:
2SI-860A 2P-14A discharge MOV AUTO & SHUT /
2S1-860B 2P-14A discharge MOV AUTO & SHUT /
2SI-860C 2P-14B discharge MOV AUTO & SHUT /
2SI-860D 2P-14B discharge MOV AUTO & SHUT /
2SI-870A 2P-14A Suction from RWST OPEN /
2SI-870B 2P-14B Suction from RWST OPEN / i 2SI-871A 2P-14A Suction from RHR SHUT /
2SI-871B 2P-14B Suction from RHR SHUT /
2SI-836A NaOH addition AOV NORMAL / AUTO /(energized) /
2SI-836B NaOH addition AOV NORMAL / AUTO /(energized) /
2SI-868A Spray isolation LO /
2SI-868B Spray isolation LO /
2SI-831 A Spray add tank isolation LO /
2SI-831B Spray add tank isolation LO / .>
l 2B52-38H 2P-14A Breaker racked position IN /
l 2B52-27A 2P-14B Breaker racked position IN /
2P-14A Control switch AUTO /
2P-14B Control switch AUTO /
3.16 Inform I&C to schedule containment spray and containment ventilation isolation reset continuity checks per ICP 3.11, 4,0 ANALYSIS TO BE COMPLETED BY OPERATIONS MANAGER OR IIIS REPR.ESENTATIVE.
4.1 Comparisons of test data recorded in Steps 3.3.2,3.3.3, and 3.6 with the test criteria listed in 3.5 are within allowable tolerances.
4.2 Comparisons of test data recorded in Steps 3.7.7 and 3.9.5 with the test criteria listed in these steps are within allowable tolerances.
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NUCLEAR POWER BUSINESS UNIT ORT 6 '
OPERATIONS REFUELING TESTS MAJOR Revision 16 , )
_ CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 '
UNIT 2 INITIALS 4.3 Out of tolerance data forwarded to IPE/NPE for further analysis. (N/A if data within tolerance).
Results of analysis attached. .
4.4 Any requirements for corrective action?
Ye. No (if yes, give details in the remarks section.)
i j 4.5 Data Analyzed By:
Time and Date:
Remarks:
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1 NUCLEAR POWER BUSINESS UNIT ORT 6 OPERATIONS REFUELING TESTS MAJOR
,' Revision 16 CONTAINMENT SPRAY SEQUENCE TEST March 17,1997 UNIT 2 ATTACHMENT A MG-6 LATCH CLEARANCE ADJUSTMENT INSTRUCTIONS 1.0 Loosen the latch adjustment lock screw located on the upper front of relay between the two !
adjustment screws.
NOTE: Turning the latch adjustment screw CCWincreases latch clearance.
2.0 Adjust the latch clearance by turning the latch adjustment screw locatedjust above the lock screw (1/4 turn = -0.015").
3.0 Tighten the lock screw and check clearance using a nonmetallic feeler gauge.
4.0 Repeat Steps 1 through 3 until latch clearance is 0.012" to 0.015". Document as-left clearance in the appropriate space after electrical operation of relay.
j Page 9 of 9 CONTINUOUS USE
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