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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
_ _ _ _ _ _ _ _ . _ . _ _ . _ . _ __ _ _ _ _ _ _ _ . . . . . _ _ . _ . .
NUCLEAR POWER BUSINESS UNIT IT 585 l- INSERVICE TESTS MAJOR .
~ Revision 13 LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING)
UNIT 2 Date RECORD DSS PROCEDURE VERIFIED CURRENT AND CllECKED FOR TEMPORARY CHANGF3. IF FIELD COPIES REQUIRED, USE PBF@26i IAW NP 1.2.4 AND DO M COMPLETE T11'.S BLOCK BY: DATE:
1.0 PURPOSE The purpose of this test is to detect and quantify leakage from the post-accident containment atmospheric sampling system as required by Technical Specifications Table 15.4.1-2 (22) and NUREG-0578.
2.0 REFERENCES
2.1 P&lD M-2215, Sheet 2, RE-211&212 2.2 01-58, " Leak Testing of Containment Isolation Valves - Unit I and 2 General Instructions and Information" 2.3 EDS Nuclear, " Post-Accident Containment Atmospheric Sampling System Leakage Test," dated 12-80 2.4 EDS Nuclear Report, " Leakage Reduction and Preventive Maintenance Program at PBNP," dated 07-24-80 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Gases leaking from various components of the post-accident containment atmospheric sampling system may be radioactive and appropriate health physics practices should be -
observed.
3.2 Do not pressurize the system to a pressure greater than required for the test.
3.3 Figure 1 is an informational drawing only.
INITIALS 4.0 INITIAL CONDITIONS 4.1 2RE-211&212 may be taken OOS for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to perform this test.
4.2 An RWP is available, if required.
9705120256 970505 Page 1 of 9 CONTINUOUS USE PDR ADOCK 05000301 P PDR
5 NUCLEAR POWER BUSINESS UNIT IT 585 ,
INSERVICE TESTS MAJOR .
Revision 13 .
"~
LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING)
UNIT 2 INITIALS 4.3 Staging and pretest of Volumetrics test rig.
4.3.1 Station the Volumetrics test rig in an area not subject to draft or cold weather.
4.3.2 Route P-tubing from the test rig to the 2RM-211/212 cubicle at valve 2RM-3200Y but do not connect to 2RM-3200Y.
4.3.3 Install a Swageloc cap at the extreme end of the tubing.
4.3.4 Adjust the pressure regulator of the test rig for a supply pressure of 15 psig and pressurize the test rig and P-tubing.
4.3.5 When a stable test system leak rate is achieved: l
- a. Correct any substantial leak paths in the test system. The l leakage at the end fitting of the P-tubing should be zero.
l
- b. Record the as-left baseline test system leak rate on the test '
data sheet for the 15 psig test.
4.3.6 Adjust Volumetrics test pressure for 4.0j psig in preparation for the low pressure test.
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 I 5.0 PROCEDURE 5.1 Place the control switch for 2P-707B, containment forced air blower, to
" PULLOUT."
Page 2 of 9 CONTINUOUS USE
' NUCLEAR POWER BUSINESS UNIT IT 585 I INSERVICE TESTS MAJOR 1
^
Revhion 13 j J
~
LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 ;
3 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT l CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM i
(REFUELING) '
UNIT 2
- INITIALS 1
NOTE: Ifunit is atpower, LCO entrypoint.
4 5.2 Secure 2P-707A sample pump.
5.3 Position the " MODE SELECTOR" on 2C-20 for the containment air sampling system to the " CONTAINMENT" position.
{
5.4 Align the system per Attachment A.
5.5 Connect the Volumetrics test rig to 2RM-3200Y, septum SA purge test connection.
,
- THE TEST PRESSURE OF 65 PSIG PER OI-58 DOE'S NOT APPLY TO THIS TEST. DO NOT EXCEED 5 PSIG l TEST PRESSURE, THE DESIGN PRESSURE OF THE i, MYLAR WINDOW OF 2RE-211&212.
- 5.6 Open 2RM-3200Y and raise the system pressure to 4.0 psig per 01-58.
5.7 When a stable pressure and leak rate condition is achieved, record data on the test data sheet.
i 5.8 When the 4 psig test is complete, position the " MODE SELECTOR" on '
2C-20 to the " SEPTUM" position.
, 5.9 Shut the following valves:
1 2RM-1,2P-707A bypass regulator inlet isolation
. 2RM-3200K,2RE-211&212 inlet manual isolation 4
i 5.10 Slowly unscrew the glass bowl of the 2RE-211/212 bypass line filter to i vent 2RE-211/212 to atmosphere. When 2RE-211/212 is depressurized,
- then remove the bowl to protect 2RE-211/212 from an overpressure condition in the subsequent test.
t 4
Page 3 of 9 CONTINUOUS USE
l NUCLEAR POWER BUSINESS UNIT IT 585 :
l . INSERVICE TESTS MAJOR ,
i l Revision 13 '
LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING) !
UNIT 2 1
( INITIALS 5.11 Using the Volumetrics test rig, raise system pressure to 15 j psig per OI-58. l 5.12 When a stable pressure and leak rate condition is achieved:
i i 5.12.1 Check with Snoop and correct any leakage to atmosphere at mechanicaljoints, fittings, valve bonnet and packing gland, etc.
within the test volume.
5.12.2 Record data on the test data sheet.
5.13 If the corrected leak rate, as determined by subtracting the baseline l leakage of Step 4.3.5.b, is >10 scem, then locate the source of the leakage
- by systematically isolating portions of the system using l valves 2RM-3200W,3200Z,3200J,3200L,3200JJ and 3200LL. Record
)
trouble shooting results in the Remarks section of the test data sheet.
l 5.14 When the test is complete, then shut 2RM-3200Y and disconnect the Volumetrics test rig.
l 5.15 Verify open,2RM-3200J, JJ, LL, L, W and Z, then depressurize the test volume by opening 2RM-3200A.
5.16 When the system is depressurized: !
5.16.1 . Screw on firmly the glass bowl of the 2RE-211/212 bypass line filter assembly.
i 5.16.2 Shut 2RM-3200JJ and 3200LL.
5.16.3 Open 2RM-1,3200K,3200EE and 3200FF.
5.16.4 Open 2RM-3200B and 3200C.
4 i
Page 4 of 9 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 585 INSERVICE TESTS MAJOR ,
Revision 13
~
LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING)
UNIT 2 INITIALS 5.16.5 Lock open the following:
l 2RM-3200J Lock No. /
l 2RM-3200L Lock No. /
5.16.6 Perform an independent operator verification of the system valve alignment per CL-8A.
5.17 Return the system to the mode of operation determined by the DSS.
NOTE: Ifunit is atpower, LCO exitpoint.
6.0 ACCEPTANCE CRITERION The leakage criteria of the Leakage Reduction and Preventive Maintenance Program are used to evaluate the leakage from the post-accident atmospheric sampling system. The check against Criterion 1 or Criterion 2 does not apply for this system as it is not located in the auxiliary building. The total post-accident system leakage from all areas of the plant is limited by Criterion 3. Thus, the acceptance of these test results require their evaluation together with the results of the other post-accident system leakage tests.
Page 5 of 9 CONTINUOUS USE
NUCLEAR PbWER BUSINESS UNIT IT 585 INSERVICE TESTS MAJOR ,
Revision 13 LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING)
UNIT 2 INITIALS 7.0 ANALYSIS TO BE COMPLETED BY THE OPERATIONS MANAGER OR IIIS REPRESENTATIVE.
7.1 Comparison with allowable ranges of test values and analysis of deviations complete.
7.2 Any requirements for corrective action?
Yes No If yes, give details in the remarks section and MWR No.
7.3 Data analyzed. By Date Remarks: l Page 6 of 9 CONTINUOUS USE x
6
, NUCLEAR POWER BUSINESS UNIT IT 585 INSERVICE TESTS MAJOR ,
f Rrrision 13 LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM (REFUELING)
UNIT 2 TEST DATA SHEET 1.0 LOW PRESSURE TEST NOTE: This leak test data is not compensatedfor test apparatus leakage and is informational only.
Test pressure psig Leak rate seem Test Inst. ID Test Inst. Range scem Time /Date /
2.0 HIGH PRESSURE TEST. SEPTUM SYSTEM ONLY 2.1 Test apparatus baseline leak rate (Step 4.3.5.b) = seem 2.2 Test pressure psig Leak rate (total) seem Test Inst. ID Test Inst. Range seem Time /Date /
2.3 Compensated system leakage = total leak rate (2.2 above) minus test apparatus baseline leak rate (2.1 above).
Compensated system leakage = - =
seem Remarks:
Page 7 of 9 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT IT 585 INSERVICE TESTS .
MAJOR Revision 13 l"
l-LEAKAGE REDUCTION AND PREVENTIVE February 14,1997 MAINTENANCE PROGRAM TEST OF POST-ACCIDENT l CONTAINMENT ATMOSPHERIC SAMPLING SYSTEM i
(REFUELING) l UNIT 2 l ATTACHMENT A l
Valve No. Description Position initials l 2RM-3200A Return to containment .. ...... ... ........ ...... ... . . ...... . S l 2RM-3200B Sample from containment..... . . .. .. . ... . .. ... ..S l 2RM-3200C Sample from containment.. .... .. ....... .. . ... ..... . ... . S
' 2RM-3200EE Purge exhaust sample, manual isolation.. ... ... .. .. ... S i 2RM-3200FF Facade sample manual isolation. ...................S l 2RM-3200J Sample septum inlet.. ................................O 2RM-3200K RE-211/212 isolati on . . . . . . . . . . . . . . . . . .. . . . .......O 2RM-3200L Sample septum outlet... .. ... . .. ...... ...... ....... .. . . O i l 2RM-3200N Forced vent blower inlet ......... . ... .. ........... ... .. ..... S i 2RM-3200Q Natural vent isolation.... . . ...... .. ............S ,
l 2RM-3200R Supply test connection.. . ... . . ... .... ... ......... S & Capped 2RM-3200V Return test connection . . . .. .. .... . . ........ ........ S & Capped 2RM-3200W Purge exhaust stack inlet .... .. .. .... .. . ..... ...... . . . . O 2RM-3200Y Service air purge.. ....................................S 2RM-3200Z Manual retum to containment.... . .. .... . ..... ..... ...... O 2RM-3200JJ Sample septum inlet series isolation.... ......... . ... .. . O
, 2RM-3200LL Sample septum outlet series isolation..... .......... .... O t
L l l
l i
i l
Page 8 of 9 CONTINUOUS USE
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