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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
_ _ . . ._ . _ . _ _.
RDW 5.3 !
MINOR Revision 3 05-11-84 SHIPMENT OF LOW SPECIFIC ACTIVITY RADIOACTIVE MATERIALS -
49 CFR 173.425 & 10 CFR 71.52 1.0 GENERAL Shipments of low specific activity radioactive materials (LSA) may be made under the " exclusive use" or " nonexclusive use" provisions of 49 CFR 173.425.
This procedure will address the requirements for each of these provisions.
2.0 REFERENCES
2.1 10 CFR 71, Packaging of Radioactive Material for Transportation 2.2 49 CFR Parts 100 to 199, Transportation 2.3 Specifically 49 CFR 173.425 2.4 IE Information Notice 80-32, Revision 1, Clarification of Certain Requirements for Exclusive Use Shipments of Radioactive Materials 2.5 File No. HP 2.6, Package Certificate of Compliance 2.6- State of Washington Radioactve Materials License No. WN-IO19-2, issued to U.S. Ecology, expiration date November 30, 1985 2.7 Barnwell Waste Management Facility Site Disposal Criteria for Chem I
Nuclear Systems, Inc., Barnwell Office. Document No. S20-AD-010 3.0 EXCLUSIVE USE VEHICLE SHIPMENT OF RADIOACTIVE LSA MATERIAL (49 CFR 173.425b & 10 CFR 71.52)
The following provisions must be fulfilled for each shipment of low specific activity radioactive material by exclusive use vehicle.
3.1 shipment must meet the requirements for low specific activity radio-active material. See RDW 5.1, Section 3.4.
3.2 LSA radioactive materials which are transported in a transport l
vehicle (except aircraft) consigned as exclusive use are exempt from specification packaging, marking, and labeling provided the shipment meets the following requirements.
3.2.1 Material must be packaged in strong, tight packatjes, so that there will be no leakage of radioactive material under conditions normally incident to transportation.
8411120376 841105 DR ADOCK 05000266 PDR
o .
RDW 5.3 Page 2 3.2.2 Pyrophoric materials (highly flammable, spontaneously com-bustible, or water reactive) require special handling and will not be included in shipments from PBNP without the specific approval of the Superintendent - CHP. See 49 CFR 173.418 & 10 CFR 61.56 for packaging requirements.
In addition, any shipment of pyrophoric material to the Richland, WA burial site first requires the approval of the State of Washington while the Barnwell, SC site criteria states that pyrophoric material will be treated, prepared and packaged to be non-flammable and rendered non-pyrophoric prior to shipment.
3.2.3 Packages of radioactive waste sent to a waste burial site
- will contain no free standing liquids. Burial site licenses require PBNP to certify that each package contain no more than 0.5% liquid by volume or one gallon, whichever is less.
In lieu of this requirement, waste sent in a high integrity container to the Chem Nuclear burial site at Barnwell, South Carolina may contain up to 1% liquid by volume or one gallon, whichever is less. (10 CFR 61.56) 3.2.4 The outside of each package must be marked " Radioactive -
LSA UN2912". Remove labels that read " CAUTION RADIOACTIVE l MATERIAL."
3.2.5 Contact the Nuclear Plant Specialist or engineer assigned
. to radioactive waste to determine whether Class "A," "B" or
- "C" waste markings should he placed on the package in accordance with RDW 3.8. These markings should be placed on the top and two opposite sides of each package within 6 inches of the other DOT markings and labels. ,
In addition, unless directed otherwise, each Class "A" i marking should have the word " UNSTABLE" marked adjacent to it.
l All lettering should be at least 1/2" in height.
Packages must be checked to ensure that the levels of t
3.2.6
, removable surface contamination do not exceed the limits
! given in RDW 5.7, Section 5.
3.2.7 The radiation dose rate for each package must no,t exceed the limits specified in RDW 5.7, Section 6.
3.2.8 Shipment must be loaded by consignor and unloaded by l consignee from the transport vehicle in which originally
- loaded.
l l
-. m . - -e,--..+y,,,p, ,
4 i
l 4 . l RDW 5.3 Page 3 3'.2.9 There must be no loose radioactive material in the vehicle.
3.2.10 Shipment must be braced so as to prevent leakage or shift'of lading under conditions normally incident to transportation.
3.2.11 The transport vehicle must be placarded " Radioactive" on all four sides (49 CFR 172.500).
3.2.12 Specific instructions for maintenance of exclusive use shipment controls (Form CHP-138) must be provided to the carrier with the shipping paper information (per RDW 5.8).
3.2.13 Transportation by aircraft is prohibited.
I 4.0 NONEXCLUSIVE USE VEHICLE SHIPMENTS OF RADIOACTIVE LSA MATERIAL (49 CFR 173.425a & 10 CFR 71.52)
Packages of low specific activity radioactive material shipped under the
" nonexclusive" provisions of 49 CFR 173.425a must meet the following
, requirements.
4.1 Shipment must meet the requirements for low specific activity radio-active material. See RDW 5.1, Section 3.4.
4.2 Each pac'kage must meet the requirements of 49 CFR 178.350 for a DOT Specification 7A Type "A" package.
NOTE: A 17H STEEL DRUM, 55-GALLON SIZE, CERTIFIED AS A DOT SPECIFICATION 7A, TYPE "A" PACKAGE, MAY WEIGH NO MORE THAN 840 i
POUNDS WHEN LOADED.
4.3 Pyrophoric materials require special handling and will not be j included in shipments from PBNP without the specific approval of the Superintendent - CHP. See 49 CFR 173.418 for packaging requirements.
4.4 The removable radioactive surface contamination levels of each package must not exceed the limits specified in RDW 5.7, Section 5.0.
4.5 The external radiation readings from each package must not exceed the limits specified in RDW 5.7, Section 6.0.
4.6 Package must be marked " Radioactive Material LSA, n.o.s. UN2912" and labeled with the applicable Radioactive White I, Yellow II, or Yellow III label. See RDW 5.6, Section 4.0.
4.7 The transport vehicle must be placarded " Radioactive" on all four
- sides if it contains a package bearing the Yellow III label.
l 4.8 The shipment must be secured to prevent shifting during normal transportation conditions. (49 CFR 173.448a) f l
e RDW 5.3 Page 4 5.0 Instructions for completing the necessary s' hipping papers are contained in
,RDW 5.8.
6.0 GREATER THAN TYPE "A" QUANTITY OF LSA MATERIAL 6.1 If the total activity of a package of LSA material exceeds the limits for a Type "A" quantity, then the material must be shipped in accordance with 10 CFR 71. See RDW 5.4.
6.2 If the package qualifies as a highway route controlled quantity, then appropriate notifications must be made before and after the shipment in accordance with RDW 5.8, Section 7.0.
7.0 BULK SHIPMENTS OF LSA MATERIAL (49 CFR 173.425(c) & 177.843)
In some cases, it is permissible to make unpackaged bulk shipments of LSA materials. Shipment must be accomplished via an exclusive use closed transport vehicle. Refer to the NPS or engineer assigned to radwaste for instructions on applicable requirements.
8.0 SHIPMENT NOTIFICATIONS In the following situations, appropriate notifications must be made before and af ter each shipment in accordance with RDW 5.8, Section 7.0.
8.1 Any shipment involving a greater than Type "A" quantity of radioactive material.
8.2 Depending on the amount of radioactive material involved, each shipment of radioactive waste across state lines to a burial site. Notifications are required only when the radioactive material is required by 10 CFR 71 to be in Type "B" packaging for transportat*on purposes. .
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