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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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RDW 3.4 MINOR Revision 4 05-11-84 XYLENI-BASED SCINTILLATION FLUID PACKAGING AND DISPOSAL 1.0 GENERAL This procedure defines the method to be used to dispose of xylene-based scintillation fluids. It shall remain in effect no longer than December 31, 1984 (
Reference:
U. S. Ecology Washington License WN-1019-2, paragraph 27b). Scintillation fluids will be packaged for disposal at Richland, Washington, until that time.
Packages of scintillation fluids will usually be shipped as radioactive LSA material and, therefore, the guidelines in RDW 5.3 apply.
2.0 REFERENCES
2.1 " Absorbents Approved for Use in Packaging Radioactive Wastes,"
undated memorandLa from E. Lee Gronemeyer, In-Charge Transportation and Waste' Management, Department of Social and Health Services, State of Washington 2.2 49 CFR Parts 100 to 178 2.3 10 CFR Part 61, Licensing Requirements for Land Disposal of Radioactive Waste 2.4 10 CFR Part 71, Packaging of Radioactive Material for Transport 2.5 U. S. Ecology State of Washington Radioactive Materials License WN-1019-2 3.0 PRECAUTIONS 3.1 'This procedure applies to xylene based scintillation fluids for shipment to Richland, Washington, only.
3.2 Handle scintillation fluids in accordance with procedures for flammable and hazardous liquids as appropriate.
3.3 Leave the fluid in its original vial.
4.0 REQUIRED SHIPPING MATERIALS O P
4.1 55-gallon steel drum, DOT specification 17H (49 CFR 178.118, 173.119b,c,d).
4.2 Hi-Dri absorbent, 40-pound bags.
( 4.3 Plastic bag, 4 mil minimum thickness, large enough to line a 55-gallon drum.
4.4 Adhesive tape 4.5 " Sharpie" pen and "Sanford" marker, or equivalent indelible ink pens and markers
C) .
RDW 3.4 Page 2
)
5.0 PACKING THE DRUM 5.1 Line a 55-gallon drum with a large plastic bag.
5.2 Empty a bag of Hi-Dri into the drum.
5.3 Put 400 counting vials of scintillation fluid on top of the Hi-Dri.
Vials should be left in their cardboard packing box. The caps of the vials shall be upward. The vials should form a layer 56' thick.
5.4 Repeat Steps 5.2 and 5.3 two times.
5.5 Put half a bag of Hi-Dri in the drum.
5.6 Put 100 vials on top of the Hi-Dri.
5.7 Put the remaining half bag of Hi-Dri over the vials.
The total material in the drum will be 1300 vials and four bags of Hi-Dri.
5.8 Twist the bag shut and seal it with tape.
5.9 Ensure that the drum lid gasket is in place and not damaged. Put the lid on, tighten, and seal.
5.10 Obtain a waste permit number from the control room. Tell the control room the amount of liquid and Hi-Dri that is in the drum.
5.11 Fill out a drum processing tag with weatherproof ink. A " Sharpie"
! pen is suitable. Affix the tag to the drum top.
5.12 Write the weight on the drum lid in large numbers using weatherproof ink. A "Sanford" marker is suitable. (40 CFR 172.310) 6.0 MARKING AND LABELING 6.1 r _k the following proper shipping names on two sides and the top of the drum. (49 CFR 172.301)
RADIOACTIVE LSA, N.O.S. UN-2912 WASTE XYLENE, UN-1307 CLASS A WASTE
, UNSTABLE l
6.2 Mark the follewing words near 'he top of the drum. (49 CFR 172.312) k "THIS END UP" l
r l
. m ,
RDW 3.4 Page 3 6.3 Mark the name and address of Point Beach Nuclear Plant in an l appropriate spot. (49 CFR 172.306)
Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, WI 54241 6.4 Survey the drum for radiation and contamination levels. Refer to RDW 5.6 for applicable limits.
6.5 Place a " Flammable Liquid" label next to each " RADIOACTIVE LSA UN2912" marking.
7.0 PLACARDING 7.1 The " Radioactive" placard must be used on the transport vehicle in the following situations (172.504).
7.1.1 Any package on the truck is labeled " Radioactive Yellow III."
7.1.2 The truck is assigned for exclusive use.
1 7.2 The "Flasunable" placard must be used if the total gross weight loaded on the truck is 1,000 pounds or greater. (49 CFR 172.504(c)).
8.0 ACTIVITY CALCULATION 8.1 Obtain the average isotopic distribution of the fluids from chemistry.
If necessary, initiate a Special Radiological Analysis form, CHP-24, for completion by chemistry.
8.2 Assume 16 cc liquid per vial and 0.1 pCi/cc activity to calculate total activity.
8.3 For example, if there are 1,300 vials in a drum, Total Activity = 1300 via,1 X 16 cm3/ vial X 0.1 pCi/cm3 = 2.08E-03 Ci.
9.0' SHIPPING PAPERS Refer to procedure RDW 5.8 for proper shipping paper entries.
,-.w,- ,-wm_,-. m_., -..-,._.,,-,.,m,..- m,, .,--,-.-_._.,,_,-.v.,,i,c-,-.. w-,,
RDW 3.4 Page 4 ATTACHMENT "A" 1.0 CALCULATION OF HI-DRI NEEDED TO PACKAGE XYLENE-BASED SCINTILLATION FLUID IN ACCORDANCE WITH 49 CFR 173.393(q)(2) 1.1 Hi-Dri absorbency measurement:
1 0 ml Fluid Absorbency = 178 gr. Hi-Dri 1.2 volume of fluid in a scintillation vial = 16 al 1.3 Weight of a bag of Hi-Dri = 40 pounds 1.4 Number of vials that could be absorbed by a bag of Hi-Dri:
150 ml fluid "'" 454 ar. X 40 pounds i*18 X X = 956 " bag 178 gr. Hi-Dri 16 al Ib. bag 1.5 Number of vials per bag allowed by regulation:
vials 956 bag X 21 = 478 #I" bag 2.0 ESTIMATED ACTIVITY OF SCINTILLATION FLUIDS 2.1 The highest activity fluid is made from reactor coolant samples.
.2.2 Unit I reactor coolant activity is 52.0 pCi/cc; Unit 2 reactor coolant activity is 50.3 pCi/cc.
2.3 Unit 1 and Unit 2 are sampled with equal frequency. Thus, the average coolant activity is (2.0 + 0.3) + 2 = 1.15 pCi/cc.
2.4 Since the coolant is diluted by a factor of 16 to 1, the activity of the scintillation fluid is 1.15 + 16 = 0.072 pCi/cc.
2.5 The 0.1 pCi/cc figure used to estimate activity is very conservative, especially since the bulk of the fluid is much less active than reactor coolant samples.
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