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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
.- - . -. . -- - . . . . - _ - . - . . - . . .-
l NUCLEAR POWERBUSINESS UNIT ORT 50
{
OPERATIONS REFUELING TESTS MINOR l Revision 7 !
PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 !
UNIT 2 d
d O Date RECORD DSS Pnocrouns vsamso cunRENT Axo cacxan rca TsuronAny cnAxoss tr risto l COPIE3 REQUIRED. USE PBFa2(u 1AW NP 1.24 AND DO EQI COMPLETE T103 BLOCK BY: DATE:
1 1.0 PURPOSE ,
l The purpose of ORT 50 is to perform a refueling shutdown seat leakage test of
- valves 2RC-538 and 2RC-539, as required by ASME Boiler and Pressure Vessel l Code,Section XI, " Rules for the Inservice Inspection of Nuclear Power Plant
- Components" and 10 CFR 50 Appendix J.
i 4
2.0 REFERENCES
IR 96-006, NRC Inspection Report, NRC Commitment for Operations procedure PMT/QC
, reviews.
4
- 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Locate the Volumetrics tester in an area which will limit personal exposure.
! 3.2 Do not allow liquids to enter the Volumetrics tester or damage may occur.
- 3.3 All liquids mast be drained from piping subsystem prior to attaching the l l test rig. l l
l l 3.4 This system may contain contaminated gases and liquids and the plant areas l j- being entered may be high radiation areas. Appropriate health physics i practices should be observed. '
INITIALS - 'l
! 4.0 INITIAL CONDITIONS 4.1 The unit is in a cold or refueling shutdown condition. _
j 4.2 _ The leak rate test rig is available inside containment.
4.3 Remove the last page (Attachment A) from the ORT and place it in the
" Penetration Open" section of the Containment Penetration Closure Notebook.
Q$2iggg[ pj$ i Page1 of8 ONTINUOUS USE P _
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 UNIT 2 INITIALS 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 Checidist).
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 1
5.1 Record the as-found position of components and valves on the attached data sheet.
NOTE: Forpost-maintenance testing or operability checks when only one valve orgroup of valves ifbeing tested, omit steps:
5.3.1 through 5.3.3 when testing valve 2RC-538.
5.2.1 through 5.2.3 when testing valve 2RC-539 and 2RC-1419B.
5.2 Perform the crimary test of 2RC-538. if reauired. as follows:
5.2.1 Align valves per drawing B-IVLT-34A-P.
5.2.2 Attach test rig at 2RC-1419. f l 5.2.3 Pressmize the section of pipe to 61 - 65 psig and test per OI-58.
O Page 2 of 8 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS - MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 UNIT 2 tj INITIALS 5.3 Perform the secondarv test of 2RC-539 and 2RC-1419B. if reauired. as follows:
5.3.1 Align valves per drawing B-IVLT-34A-S.
5.3.2 Attach the test rig at 2RC-1419.
l 5.3.3 Pressurize the section of pipe to 61 - 65 psig and test per OI-58.
5.4 Vent and detach the test rig.
5.5 Return components and valves to positions directed by the DSS. Record the positions on the attached data sheet.
5.6 Shut the followinn valves:
5.6.1 2RC-1419 (Gj 5.6.2 2RC-1419B 5.7 Notify the DSS / DOS that the ORT is complete.
5.8 Remove the drawing from the " Penetration Open" section of the Containment Penetration Closure Notebook and discard the drawing.
1 5.9 Complete the " Penetration Closed" section of CL-lE (Containment Closure Checklist).
.l fMI '
5.10 Leak check tubing downstream of 2RC-539 when PRT is at operating pressure.
f -_
9 P
1 i
, Page 3 of 8 CONTINUOUS USE ,
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997
_ UNIT 2 INITIALS 6.0 EVALUATION To be completed by Operations manager or his representative.
- 6.1 Individual leakages compared to allowable value and included in tabulation of total leak 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
. Page 4 of 8 CONTINUOUS USE 9
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS AUNOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 UNIT 2 C !
LEAK TEST DATA SHEET Valve Number Position Initials Position Initials 2RC-538 2RC-539 2RC-540 2RC-1419 2RC-1419B Tubing downstream 2RC-539 Cap at 2RC-1419 Cap at 2RC-1419B 2RC-538 (Index 72)
Pressure Leak Rate Tims fass) (sccm)
O V
Test Instmment ID Range (Circle one): Low Mid High i
2RC-539 (Index 74) !
Pressure Leak Rate Ilms (ggg) _ (scem) .
Test Instmment ID Range (Circleone): Low Mid High Comments:
.G U Completed By DSS / DOS Page 5 of 8 CONTINUOUS USE
.~ . . .
l
NUCLEAR POWER BUSINESS UNIT OR150 OPERATIONS REFUELING TESTS MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 UNIT 2 4 . ,
I PRT q
- l I
1 P 2RC-I J L 540 I
l GAS I ABIALVIER x P34A l' .
2RC-1419 l l 2RC-588 2RC-589
,' O vaer M
lJ"l 9 i
1 I2RC-l I k 141 M )
' /
W TUSNG TO TEST VALVE 2RC-538:
SifLT INITIALS 1
- 2RC-540 3RC-$38 2RC-1419B
)I om -
1 2RC-1419 il
' 2RC-$39 1 Disconnect tubing downstream from 2RC 539 l
PRT to Gas Analyzer Pipeway No. 4 1
No. B-IVLT-34A-P i
Page 6 of 8 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 i
.O UNIT 2
( l
,\_)
CONTAINMWff ,
PAS PRT l l
I P 2RC-1 J L 640 l
I i GAB i ANALVIER X pg ll 2RC-1410 l 1
4 2RC-638 2RC-580 4
I
, 1 Terr I ! I nie i 1 I2RC-l I k 141MB )
l
/
TUBING
^
DISCONNECTED O (CAP REMOVED TO TEST VALVE 2RC-539 AND 2RC-1419B:
SIEI. INITIALS PRT to Gas Analyzer 2RC 540 Pipeway No. 4 2RC 539 No. B-IVLT-34A-A 2RC-1419B DEEN l
1 2RC-1419 ~ i
! 2RC-538 Disconnect tubing downstream from 2RC-539 Remove cap from 2RC-1419B Page 7 of 8 CONTINUOUS USE
NUCLEAR POWER BUSINESS UNIT ORT 50 OPERATIONS REFUELING TESTS MINOR Revision 7 PRT TO GAS ANALYZER, SAMPLE LINE January 31,1997 UNIT 2 ATTACHMENT A CONTAINIAENT ,
PAB PRT l l
I 1 P 2RC-l J L 640 ,'
, I I IRAS I ANALVIWt x P84A lI 2RO-1419 l
, 1 2RC-688 2RC-680 8
1 i s ] 4 r
I I 2RC-l d k 14108 l
TUBING
^
DISOONNECTED CAP
. REMOVED TO SET CONTAINMENT CLOSURE:
ll SlHII* 2RC-538 PRT to Gas Analyzer .
Pipeway No. 4 a _
No. B-IVLT-34A ATT A Page 8 of 8 CONTINUOUS USE e
