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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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iPOINT. BEACH NUCLEAR PLANT-UNITS 1 AND 2- l y.- -
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3 APRIL 1990
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Revision 1
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PROCESS CONTROL PROGRAM MANUAL Revision:1 LAL C4-24-90 j or -i 1.0L PURPOSE During normal operation of the Point Beach Nuclear Plant, radioactive-materials are generated in the form of spent: resins, filter' sludge, ,
evaporator concentrates, and spent cartridge filter elements. These wastesL
' require processing in appropriate portions of the solid waste management
-system prior to-shipment offsite for disposal. Liquid wet wastes are -
either solidified or dewatered. Spent cartridge filters may be packaged' with suitable absorbers or solidified prior to' shipping. procedures and
- practices are implemented to establish process parameters within which- ,
radwaste! systems are.to be operated. The procedures,and parameters providef assurance that proper waste form' characteristics are achieved.
z 2.0 PROGRAM ADMINISTRATION' 1he? primary respons'ibility for the beplementation of;the PBNP Process
' Control Program'and'any actions required by the program resides'with_the manager - PBNP'and the PBNP staff. Plant and vendor procedures used for; 1 the processing of radwaste shall'be reviewed and approved'in-accordance with-the_ applied 31efrequirements of QP and PBNP procedures.
The Nuclear Plant' Engineering and Regulation Section (NPERS).will provide technical, regulatory, and administrative support necessary to-fulfill the requirements of'the Process' Control Program.
^
3.0. REGULATORY REQUIREMENTS-Radioactive wastes ' generated at' Point Beach Nuclear' Plant shall be shipped' to a licensed. burial site for disposal in ~accordance with applicable
- Nuclear Regulatory Commission, Department of Transportation, State, and burial site' regulations. .Waste containers, shipping casks, and packaging methods shall comply with epplicable l federal regu1 Ations.
Radioactive waste processing and handling activities shall'be conducted consistent with PBNP ALARA principles and practices.
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, Radioactive waste shipment from PBNP shall be suspended if the provisions of the~ Process Control Program are not satisfied.
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' Y 74.0 SOLIDIFICATION j
The solidification of liquid wastes shall be' assured by.the implementation.
- of approved procedures. .The radioactive waste solidification program at-PBNP. shall be- conducted in accordance with the ' following provisions: . ,
4 .11 A-set of process parameters shall b'e established which provide' boundary conditions within which reasonable assurance'can be provided ;
that waste solidification is accomplished. Typical process ;
parameters include pH, oil content, water content, ratio of solidification _ agent to influent waste, and ratio of r.olidification
~
agent to chemical additives.
L I 4.2 Procedures shall prov'ide assurance that the solidification process lis ,
conducted within the established process parameters, i
4.3 Procedures'shall provide assurance that the' final waste product meets the appropriate waste characteristic requirements for-solidified -I wastes.
4.4- 1Rer,rds shall be maintained for individual solidification batches denonstrating conformance with established process parameters.
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-( 4.5. A solidification-test sampling program shall be utilized to verify K> the solidification of at least one representative test specimen from l,' every. tenth batch of,each type of liquid wet radioactive waste-(e.g.,1 p filter sludge, spent resin, evaporator bottoms, boric acid solution).
If a test specimen fails to solidify, further solidification activities'shall.be suspended-until'such time es additional test- 1 specimens ~can be obtained, alternate solidification parameters
detennined,> and a subsequent test verifies solidification. Process !
control parameters shall be modified as required to. ensure proper solidification of, subsequent-batches.
L L
1 5.0. DEWATERING' Spent resins and filter sludges may be shipped for disposal as dewatered waste if acceptable to the receiving burial' site. The dewatering of
. radioactive waste.shall be assured by the implementation of approved <
' procedures. The radioactive waste dewatering program at PBNP shall be-
- conducted in accordance with the following provisions
1 5.1- A set'.of process parameters shall be established to provide boundary 1 conditions within which reasonable assurance can be provided that i dewatering is accomplished. Typical process parameters include i settling time, drain time, and drying time.
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5.2- Procedures shall-provide assurance that the-dewatering process is f conducted in accordance with the established parameters.
p 5.3
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Procedures shall provide assurance that the final waste produce meets-
- the appropriate waste characteristic requirements for dewatered' j wastes. The. dewatered wastes shall comply with; federal and burial ;l
. site free liquid requirements at the time of receipt at the burial ->
site.
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5.4 Records will be maintained demonstrating conformance to establishedt cdewatering process parameters. !
5.5-
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If excess water.is detected upon completion.of the-dewatering- <
process,'the waste shall be reprocessed through the-dewatering.
(7
. system. ,
g 5.6 Dewatered wastes shall be packaged in appropriate containers. Thei .;
l- activity. level of the dewatered wastes and receiving burial site L criteria dictate the type of container to be used. High Integrity
. Containers (HICs)-approved by the specific burial sites which
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y V 3 satisfy 10 CFR 61 waste form stability requirements shall be used, l
- as appropriate.
O1 WASTE ~ CLASSIFICATION
{ f -650 N - .
The. waste classification program at PBNP shall comply with the provisions:
- of 101CFR 20 and 10 CFR 61. H q
-. Waste classification requirements may be accomplished using a scaling factor l methodology. . The concentration of alpha and beta emitting _ .-
% , radionuclides!may be determined by indirect methods using scaling factors which.related the' inferred concentration of one'radionuclide to another-that is^ measured. Scaling factors shall be detennine'd from a1 sampling .
analysis program of radioactive waste streams. Waste streams will'
.[ s typically be- analyzed annually for the detennination of- scaling factors -
T unless' alternate sampling frequencies are warranted by available data.
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