Rev 3 to Procedure RDW 5.9, Documentation of Radioactive Matl Shipping Package Insp,Certification & Safety Analysis (49CFR173.24)| ML20204H828 |
| Person / Time |
|---|
| Site: |
Point Beach  |
|---|
| Issue date: |
05/11/1984 |
|---|
| From: |
WISCONSIN ELECTRIC POWER CO. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20204H448 |
List: |
|---|
| References |
|---|
| RDW-5.9, NUDOCS 8411120394 |
| Download: ML20204H828 (4) |
|
|
|---|
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
F t
x ,.
RDW 5.9 MINOR Revision 3 05-11-84
~
DOCUMENTATION OF RADIOACTIVE MATERIAL SHIPPING PACKAGE INSPECTION, CERTIFICATION & SAFETY ANALYSIS (49 CFR 173.24) 1.0 GENERAL' This procedure outlines the documentation requirements for packages used to transport radioactive materials. These documents are in addition to the shipping papers required. Files must be maintained for the documents.
2.0 REFERENCES
2.1 10 CFR Part 71, Packaging Radioactive Material for Transport 2.2 49 CFR Part 173, Shippers - General Requirements for Shipments and Packagings 2.3 File HP 2.6, Package QA Documents 2.4 Mound Facility Report MLM-2228, Packaging Compliance with DOT Spec. 7A. See file HP 2.6.7 3.0 FILE ENTRIES 3.1 File HP 2.6 will be used to maintain a copy of the certificate of Compliance or other approval authorizing use of a package. All documents referred to in the license, or other aporoval, will also be maintained in file HP 2.6.
3.2 User registration letters to NRC, when requiren, will be filed in HP 2.6.
3.3 Package inspection documents will be maintained with the shipping papers pertaining to the shipment for which the package was used.
These are filed in HP 2.1.1 or 2.1.4, as appropriate.
4.0 REQUIRED DOCUMENTS 4.1 Preliminary determinations of quality assurance and quality control l should be performed by the package vendor. An NRC Certificate of Compliance maintained in file HP 2.6 will be sufficient evidence that the preliminary determinations required prior to the first use of the package have been performed by the package manufacturer.
4.2 The table below lists all the possible radioactive waste hantities authorized for shipment. Beside each quantity is a notation showing i that documentation is required ("yes") or is not required ("no"). A series of nusabers indicates which documents are required. The key is at the bottom of the table.
8411120394 841105 PDR ADOCK 05000 P
f RDW 5.9 Page 2 Package
~~
Quantity Packaged Documentation Required Limited quantity No Radioactive instrument or article No LSA, not greater than Type "A" quantity, transported in a sole use vehicle No LSA. not transported in a sole use vehicle Yes (1)
LSA, > Type "A" quantity Yes (1, 2, 4, 5)
Type "A" Quantity in a shipping cask Yes (1, 2, 4, 5)
Type "A" Quantity in a drum or liner Yes (1, 3, 4)
Type "B" Quantity Yes (1, 2, 4, 5)
Highway Route Controlled Quantity Yes (1, 2, 4, 5)
KEY:
(1) Routine inspection (2) NRC Certificate of Compliance (3) Vendor certification (4) Safety Analysis j (5) User registration letter to the NRC NOTE: FISSILE MATERIALS ARE NOT LISTED. NO FISSILE MATERIAL MAY BE SHIPPED WITHOUT SPECIFIC AUTHORIZATION FROM THE SUPERINTENDENT - CHP.
4.3 Foreign-made packages and packages intended for international shipment require additional documents. Such packages and shipments are not expected to be used at PBNP. Contact the Nuclear Plant specialist or engineer assigned to radwaste for details if necessary.
5.0 DESCRIPTION
OF DOCUMENTS ,
5.1 Routine Inspections 5.1.1 Routine inspections of cask packages are performed with the use of cask checkoff forms, the CHP-131 series. These forms are unique in that they are part of the shipping papers and a copy is sent with the shipment.
F t -
w ,
RDW 5.9 Page 3 5.1.2 Routine inspections of other packages are performed, if necessary, using form CHP-78. They are filed with the shipping paper, but no copy is sent with the shipment.
5.1.3 The routine inspection is normally performed by personnel authorized by a CHP Supervisor. Cask inspections will be done by operations in the normal course of loading.
5.2 Certificate of Compliance 5.2.1 This document is required for a cask shipment unless exempted by Section 4.2 above. It is 1. sued by the NRC. It contains the package identification number, a physical description of the package, authorized contents, and other special instructions. The Certificate of Compliance normally contains references to other documents. All such references must be filed with the certificate.
5.2.2 The Certificate of Compliance should always be consulted before shipment to verify compliance with its conditions.
5.3 vendor certification 1
5.3.1 This is required for Type "A" quantities (DOT Specification
.7A). Typically, it is a certification for a 55-gallon drum.
It states that the containers meet the requirements of DOT Spec. 7A. The manufacturer of the package must supply this.
5.3.2 In the special case of 55-gallon drums, this requirement is satisfied if the drums are certified as meeting DOT Spec. 17H.
A 17H steel drum, 55-gallon size, ce-tified as a DOT Specification 7A, Type "A" package, may weigh no more than
[ 840 pounds when loaded.
5.3.3 If the manufacturer has marked the container with a U.S. DOT specification marking, this is acceptable as a certification.
l (49 CFR 173.22) 5.4 Safety Analysis 5.4.1 A Type A package must be provided with a safety analysis by its manufacturer. It must demonstrate that the package complies with the specification set forth in 49 CFR 178.350 (DOT Specification 7A). It must also demonstrate that the package will pass the tests specified in 49 CFR 173.465 &
173.466. The manufacturer is exempted from this requirement if a generic safety analysis for the packaging is already on file at PBNP. Refer to reference 2.4 above for generic safety analyses which are applicable to 55 gallon drums.
l
- e. . , -
m.- - - - - . - , , , _ - - . , , , , - , . - - - , ,._,,-,,,.-..._-w..,,----.,,,,,.,.,,,,,---n,-.--,--,,.-.,-,,,n,,--.,,,--vc,,+n _m, - . . , , , , - --,,-e.-,+
r
~ . o RDW 5.9 Page 4 49 CFR 173.415 provides a list of Type "A" packages which are acceptable to the DOT.
5.4.2 Packages to be used for shipping greater than Type "A" quantities must be provided with a safety analysis by the manufacturer. This also applies to packages transporting LSA material if the package contains greater than Type A quantities. The nalysis is more extensive than for a Type "A" package. It must show compliance with the following regulations:
10 CFR 71.85-91 10 CFR 71 Subpart E 10 CFR 71 Subpart H 49 CFR 173.465 & 173.471 If the package is used for LSA material and is shipped via a sole use vehicle, the safety analysis ooes not need to comply with 10 CFR 71.51. [10 CFR 71.52(a))
49 CFR 173.416 provides a list of Type "B" packages acceptable to the DOT.
i 5.5 User Registration Letter A package used to transport greater than Type "A" quantities, even if the material meets LSA requirements, needs a user registration letter.
The letter informs the Director of Nuclear Material Safety and Safeguards of the intent to use a particular package. See 10 CFR 71.12 for details to be contained in the letter.
5.6 Reports (10 CFR 71.95) 5.6.1 Notification must be made to the NRC within 30 days to report the following:
- a. Any incident in which there is significant reduction in the effectiveness of any authorized package during use.
- b. Details of any defects with safety significance in the packaging after first use and the steps taken to repair the defects and prevent their recurrence.
5.6.2 The notification must be made to the Director, Nuclear Material Safety & Safeguards, U.S. Nuclear Regul'atory Commission, Washington, DC 20555.
,,m., ,_ .., ,,_ _ . . , _ _ , _
, , __