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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
( .
7- RDw 5.10 MINOR
' Revision 2 05-11-84 SELECTING PACKAGES FOR RADIOACTIVE MATERIAL SHIPMENTS
1.0 REFERENCES
1.1 10 CFR Part 71 1.2 49 CFR Parts 100 to 178 1.3 Health Physics file HP 2.6, Package QA Documents 1.4 Radioactive Material Handling Manual 1.5 IE Information Notice 80-32 and 80-32, Revision 1 2.0 DEFINITIONS (49 CFR 171.8) 2.1 Ove rpack Overpack means an enclosure not intended for reuse that is used by a single shipper to consolidate two or more packages for convenience in handling. This definition does not apply to shielded containers if the shielding is required to reduce radiation levels to allowable limits. -
For example, suppose four 55-gallon drums each meeting DOT Specifi-cation 7A and each containing a Type "A" quantity of material were to be shipped. The drums could be shipped separately. The drums could also all be put in a large wooden box and shipped even though the box was not qualified as a Type "A" package. The box is an overpack in this case and is not intended or expected to provide containment of the radioactive material. The drums provide the containment.
Occasionally, a 55-gallon drum will be placed within an 83-gallon drum for shipment. An 83-gallon drum containing a single 55-gallon drum does not constitute an overpack. The 83-gallon drum is merely a strong, tight container and must be marked " Radioactive LSA, UN2912."
A truck is never an overpack since it is intended to be reused.
2.2 Package or Outside Package This means a packaging plus its contents.
P
- '* RDW 5.10 Page 2 2.3 Packaging This metns the assembly of one or more containers and any other ccaponents necessary to assure compliance with the minimum packaging requirements of Federal regulations. It does not include overpacks.
For example, an empty 55-gallon drum is a " packaging". When the drum is filled, it becomes a " package", assuming that it meets radiation limits.
2.4 Strong Outside Container or Strong Tight Container This means the outermost enclosure which provides protection against the unintentional release of its contents under conditions normally incident to transportation. A strong wooden box can fit this definition.
2.5 Liner A liner is a large container intended to be used as an inner containment within a shielded shipping cask.
3.0 QUANTITY LIMITATIONS OF PACKAGINGS 3.1 There are three levels of packages. Listed in order from minimum to maximum capability, they are: strong tight container, Type A packages (DOT Specification 7A), and Type B packages. A package can be used at less than its full capability; i.e., a package authorized for use in transporting Type A quantities can be used as a strong tight container. Whenever a shielded shipping cask is used, review its Certificate of Compliance to be sure it is properly applied.
Refer to file HP 2.6 for the certificate.
3.2 Container Construction There are 7 types of containers used at PBNP: wooden boxes; 30-gallon j steel drums; 17H steel drums, 55-gallon; 83-gallon steel drums; steel
- liners; polyethylene liners; shielded shipping casks.
3.3 Strong Tight Containers 3.3.1 Wooden boxes, 30-gallon steel drums and 83-gallon steel drums may be used as strong tight containers only. Liners and 55-gallon drums may also be used as strong tight containers. .
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RDW 5.10 Page 3 3.3.2 A strong tight container may be used to ship only the following quantities of radioactive material:
- a. Limited quantity
- b. Radioactive devices
- c. LSA material if less than Type "B" quantity and only when shipped in an exclusive use vehicle.
3.4 Type "A" Quantity Package (DOT Specification 7A) 3.4.1 17H steel drums, 55-gallon size, and steel liners, if certified as 3 Type "A" package, may be used to meet DOT Specification 7A. These drums may weigh no more than 840 pounds when loaded.
3.4.2 In addition to the quantities authorized for a strong tight container, a 17H drum, 55-gallon size, or Type "A" steel liner may also be used to ship the following quantities:
- a. LSA material, not greater than Type "A" quantity, shipped in a nonexclusive use vehicle.
- b. Type "A" quantities.
3.5 Shielded Shipping Casks (> Type "A" Package) 3.5.1 These packages are licensed by the NRC. Before they can be used to transport radioactive materials, special documentation must be obtained. See pror edure RDW 5.9, Radioactive Material Shipping Package Documentation, to determine which documents are required.
3.5.2 Check file HP 2.6 to verify that the documents have been obtained. If the required documents are not on file, the cask may be used only as a strong tight container.
3.5.3 If the required documents specified in procedure RDW 5.9 are l on file, a shielded cask is authorized to transport radio-active material quantities listed in Sections 3.3.2 above.
Depending on the limitations of the particular cask Certificate of Compliance, it may also be authorized to transport the following quantities:
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RDW 5.10 Page 4
- a. Type "A" quantities
- b. LSA material in greater than Type "A" quantities
- c. Type "B" quantities
- d. Highway route controlled quantities NOTE: ALWAYS CHECK THE CERTIFICATE OF COMPLIANCE BEFORE USING A SHIELDED CASK. DIFFERENT CASKS ARE AUTHORIZED TO TRANSPORT DIFFERENT QUANTITIES.
4.0 SELECTING A SHIPPING PACKAGE 4.1 Determine the quantity in Curies of radioactive material to be packaged.
4.2 Determine whether the package will be shipped via exclusive use or nonexclusive use vehicle.
4.3 Using the table below, select the proper packaging.
{
7 kDW 5.10 Page 5 TABLE 1 SHIPPING PACKAGE SELECTION CHART Motor Vehicle Use Acceptable Restrictions Packagings
. Quantity to (See 4.3.1 & Minimum Required (See 4.3.3 &
be Packaged 4.3.2 below) Packaging Category 4.3.4 below)
Limited Quantity None Strong, tight cor.ainer a. Wood box Radioactive Device b. 30-gal steel drum
- c. 55-gal steel drum
- d. 83-gal steel drum
- e. steel liner
- f. cardboard box Type "A" Shielded vehicles: Type "A" a. 17H steel drum,55-gal (Maximum loaded weight-840 pounds) exclusive usc b. Type A steel liner Others: None c. Liner or drums inside a shipping cask i
- Type "B" Exclusive use Type "B" Liner or drums inside a shipping cask Highway Route Controlled Exclusive Use Type "B" Liner or drums inside a shipping cask LSA material, not None Type "A" a. 17H steel drum,55-gal greater than Type b. Type A steel liner "A" quantity LSA material, not Exclusive use Strong, tight a. Wood box greater than container b. 30-gal steel drum Type "A" quantity c. 55-gal steel drum
- d. 83-gal steel drum
- e. steel liner
, f. liner or drums inside a shipping cask 4
LSA Material Exclusive Use Variable, See liner or drums inside i greater than Section 4.3.3 below a shipping cask i Type "A" quantity ,
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- , --y - . --.., ry---- 7-,-v__,7----,-__m-,-, -,--,,,----e._,.,-y.-_,.-.,,,_.,,.,y 3 _.,..-,,.,y.,cm,, _ . ,y -,,-,,ree-*=wn 'ww-r---*c-- y =rw-e,-w==w--
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RDW 5.10 Page 6 4.3.1 Radioactive material or devices in greater than limited quantities may not be transported in commercial passenger carrying vehicles.
4.3.2 Packages put on vehicles must conform to the radiation and contamination limits specified in RDW 5.7.
4.3.3 Shipping casks have specific criteria for use which vary according to the cask model. Refer to the appropriate Certificate of Compliance in file HP 2.6 for specific information regarding the cask's package category and acceptable contents.
4.3.4 Liners for use inside a cask may be either steel or polyethylene. In some cases, such as the CSN 6-75 cask operated by Chem-Nuclear Systems, liner must be a certified Type "A" package. Refer to file HP 2.6, procedure RDW 5.9 and burial site criteria to determine which liner is appropriate for a given case.
4.3.5 Refer to file HP 2.6 and procedure RDW 5.9 to determine if a liner is certified as a Type "A" package.
4.4 If a shipping cask is selected, estimate the dose rate at the cask surface and 2 meters (6.6 feet) from the surface. Contact the Nuclear Plant Specialist or Engineer assigned to radwaste for assistance. If estimated dcse rates are above 200 mR/ hour contact or 10 mR/ hour at 2 meters (6.6 feet), select a different cask and make a new radiation level estimate.
Packagings other than those shown in Table 1 above may be used with 4.5 approval from the Superintendent - CHP.
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