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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] |
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f3.3 L /Allliquids must be drained tirom piping subsystem prior to attaching the test rig. .
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This system may contain contaminated gases and liquids and the plant areas being entered y >
may be high radiation areas. Appropriate health physics practices should be observed.
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4 INITIALS 4
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, LORT501 :c i 4 KOPERATIONS REFUELING '
TESTSi , ,
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' ' sThe con' ditions requifed by this test are consistent with required planti
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i: DSS i ' Time Dats ,
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f5.1a t Recosd the as-found position of components and valves on the attached ,
, q; " , c data sheet.'
~ NOTE: Forpost maintenance testing or operability checks when only one i
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! valve or gwp of valves is being tested,' omit steps: -
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13.1 through 5.3.3 when tesdng valve 1RG538 l ]
55.2.1 through 5.2.3 when tendng valve 1R&539 and IRC-1419B i g44 , ,. , s. . ,
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4 z7 1-5.2- Perform the primary test of IRC-538, if required, as follows:. ~
~
5.2.1 ? ' Align valves per dwg B-IVLT-34A-P. <
r 5.2.2 L : Attach test rig at' 1RC-1419A. ,
573 Pressurize the wion ofpipe to 65 psig and test per 01-58.
- n i 5.3
Perform the secondary test ofIRC-539 and IRC-1419B, ifrequired, as
' follows: '
.w W[B 15.3.1 Align valves per dwg B-IVLT-34A-S. ,Q
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!5.3.24 Attach test rig at IRC-1419A. ~
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,.4 , ~ f5.4 Vent'and~ detach the test rig.1 '
h5.5$ fReturricomponents andialves to positions as directed by the DSS, and
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.I 1 Date RECORD DSS PROCEDURE VERFED CURREMND C}ECKED FOR TEMPORARY CWNGES F FE1D COPES REQUIRED, USE PRF.0026i 1AW NP 1.2 4 AND DO EQI COMPLETE TFUS BLOCK BY: DATE:
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1 1.0 PURPOSE The purpose of ORT 50 is to perform a refueling shutdown seat leakage test of valves IRC-538 [
and IRC-539, as required by ASME Boiler and Pressure Vessel Code,Section XI, " Rules for the Inservice Inspection of Nuclear Power Plant Components," and 10 CFR 50, Appendix J. ;
- i.
2.0 REFERENCES
i
, IR 96 006, NRC Inspection Report, NRC Commitment for Operations procedure PMT/QC ,
4 reviews.
i 3.0 PRECAUTIONS ANDLIMITATIONS 3,1 Locate the volumetrics tester in an area which will limit personal exposure.
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'4 3.2 Do not allow liquids to enter the volumetrics tester or damage may occur.
[- 3.3 All liquids must be drained from piping subsystem prior to attaching the test rig.
4
! 3.4 This system may contain contaminated gases and liquids and the plant areas being entered
- may be high radiation areas. Appropriate health physics practices should be observed.
J INITIALS .
- 4.0 INITIAL CONDITIONS i ....
4.1 The unit is in a cold or refueling shutdown condition.
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- 4.2 Theleak rate test rig is available.
' . - 25 4.3 Remove the last page (Attachment A) from the ORT and place it in the '
" Penetration Open" section of the Containment Penetration Closure 4
' Notebook.
5 i- NOTE: The containment isolation valve (s) may be shut during the
- performance ofsome ORTS. (
$ 4.4 ~ Complete the " Penetration Open" section of CL-lE (containment closure '
j checklist).
9702180353 970210 Page 1 of 7 CONTINUOUS USE* -
PDR P
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NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 UNIT 1 INITIALS <
4.5 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 Record the as-found position of components and valves on the atoched ;
data sheet.
l 1
NOTE: Forpost maintenance testing or operability checks when on;; .uu
+
l valve orgroup of valves is being tested, omit steps: j L3.1 through 53.3 when testing valve IRC-538 52.1 through 32.3 when testing ulve 1RC-539 and IRC-1419B 5.2 Perform the primary test of IRC-538, if required, as follows:
5.2.1 Align valves per dwg B-IVLT-34A-P.
5.2.2 Attach test rig at IRC-1419A.
5.2.3 Pressurize the section of pipe to 65 psig and test per 01-58.
5.3 Perform the secondary test of 1RC-539 and 1RC-1419B, ifrequired, as l follows: ~
f.
5.3.1 Align valves per dwg B-IVLT-34A-S.
5.3.2 Attach test rig at IRC-1419A. ~3l ?
5.3.3 Pressurize the section of pipe to 65 psig and test per OI-58.
, 5.4 Vent and detach the test rig.
5.5 Return components and valves to positions as directed by the DSS, and record the positions on the attached data sheet. -
l Page 2 of 7 CONTINUOUS USE
- - _ _ - . - .. .=. . ...- . -- . . - - . . - .
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 7 UNIT 1
'k INITIALS 5.6 Shut and cap the following valves:
5.6.1 1RC-1419A 5.6.2 1RC-1419B i
1 5.7 Notify the DSS / DOS that the ORT is complete. I 5.8 Remove the drawing from the " Penetration Open" section of the I Containment Penetration Closure Notebook and discard the drawing.
5.9 - Complete the " Penetration Closed" section of CL-lE (containment closure checklist).
PMT 5.10 Leak check tubing downstream ofIRC-539 when the PRT is at operating -
pressure.
6.0 EVALUATION n%s 1 TO BE COMPLETED BY SUPERINTENDENT - OPERATIONS OR HIS REPRESENTATIVE.
6.1 Individual leakages compared to allowable value and included in tabulation of totalleak rate (Index 16).
.6.2 ' Results acceptable, no limits exceeded.
Yes No (If no, give details in the Remarks section and notify the Regulatory Services manager to determine reportability.)
- 6.3 Data Analyzed By
^~
Date .
Remarks:
O V .
. Page 3 of 7 - CONTINUOUS USE
\
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 UNIT 1 ,
LEAK TEST DATA SHEET As-Found Final Valve Number Position Initials Position Initials 1RC-538 1RC-539 1RC-540 1RC-1419 & Cap 1RC-1419A & Cap 1RC-1419B & Cap Tubing downstream IRC-539 _
1RC-538 (Index 72)
Pressure Leak Rate Ilms (Raig) (scem)
Test Instrument ID Range
, 1RC-539 (Index 74)
Pressure Leak Rate ,
Ilms (psig) (sccm) '
i Test Instrument ID Range Comments:
Completed By ass /pos Page 4 of 7 CONTINUOUS'USE
_..m . . - _ _ _ _ ._
m . - .. . _ . .
NUCLEAR POWER BUSINESS UNIT ORT 50
. OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 UNIT 1 k
coerrAIMMDrr AUX BUZI. DING l i
3 r1 j[1Rc-1419 .
m a 1N-540 1
i l
i l l l nas A ulyser P34A i
i i tusInc oIscoseractuo !
inc-1419k !
h
- test at, l 1 - 39 s
2ac-j[
14198 w
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1 8 Valve Lineun To Test Vahe IRC-538 '
' f, Shut fahes: IRC-540, IRC-1419, IRC-538, W
.t j and IRC-1419B '
_ _af.
Open valves: 1RC-1419A and IRC-539 and disconnect tubing dc*.suv in of IRC-539. ,
1 Showing: PRT to GA Location: Pipeway #1 Drawn By: JRM a .
\ Date: 08-23-86 t
V Drawing No.: B-IVLT-34A-P
- 1 Page 5 of 7 CONTINUOUS USE
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NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 UNIT 1 CONTAINMENT AUX BUILDING ti
{ 1RC-1419 m W]
1RC-540 i I .
l Gas Analyser P34A i
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1RC-1419A[
T.. . b_. $
IRC-5 1E-539 l 1RC-1419B][ l i
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- l Valve Lineuo To Test Valves 1RC-539 and IRC 1419B
-.g Shut valves IRC-540, IRC-1419, IRC-539,
., i and IRC-1419B Open valves: 1RC-1419A and IRC-538, - -
disconnect tubing downstream of1RC-539 and remove cap at {
i IRC-1419B Showing: PRT to GA '
Location: Pipew3y #1 l
Drawn By: JRM Date: 08-23-86 {;
Drawing No.: B-IVLT-34A-S j 9
I Page 6 of 7
. CONTINUOUS 'USE )
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 9 PRT TO GAS ANALYZER SAMPLE LINE January 31,1997 A. UNIT 1
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Date: 08-23-86 Drawing No.: B-IVLT-34A-ATT A fh e . .
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