|
|---|
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
. - - . . - -
o a 1 RDW 3.6 MINOR Revision 3 05-11-84 i
l PREPARATION OF RADWASrE LINERS FOR FILLING, STORAGE AND SHIPT 1ENT 1.0 GENERAL .
Disposable type liners can be used for shipping solidified liquid waste, filters and resin. Their preparation and filling is normally accomplished by Operations using procedures outlined in OP-9B and OI-8.
This procedure addresses the health physics requirements in preparing the liner for shipment to a burial site. The liners are normally shipped within shipping casks that are approved packages for Type "A," Type "B" or highway route controlled quantity radioactive materials. Liners must be cc,mpatible with the cask they are shipped in as specified by the particular cask certificate of compliance. The specific shipping package used is determined by the quantity of radioactive material and by transport group being shipped. The ,
liners may also be shipped, depending upon external radiation levels and
- the type and quantity of radioactive material it contains, without an external shipping package.
2.0 REFERENCES
2.1 RDW 5.1, Radioactive Material Shipments 2.2 CNSI specific cask handling procedures 2.3 Nuclear Regulatory Countission Certificate of Compliance for specific casks 2.4 OP-9B, Solid Waste Processing 2.5 OI-8, Waste Solidification i 2.6 Hittman Cask Handling Procedures t 2.7 CSO 22, Strontium 89/90 and Transuranic Samples for Radioactive Material Characterization og 3.0 ACTIVITY CALCULATION FOR CASK CURIE CONTENT
, ineo i O N G.
jgo 3.1 Health Physics is to ensure that a sample of the waste has been wo taken to Chemistry for analysis. This sample should be identified m$ by the waste permit number (CHP-16) of the liner into which the
( waste will be transferred.
"8 Oo Prior to transferring any waste to a liner or cask, the analysis 04 results should be received and reviewed by the Nuclear Plant
-e Specialist or engineer assigned to radwaste who will in turn
& determine whether the waste is compatible with the intended liner and shipping cask.
., . . - _ . _ _ . _ - _ _ . . _ _ . . , _ . . . . _ _ _ _ _ _ . _ _ _ _ _ . _ _ . --_ --._ _ . - .m _ . _ . _ . . _ . . - _ , , . - - - _-
RDW 3.6
( Page 2 3.2 Resin The total activity in a resin liner is typically determined by ;
isotopic analysis and by QADH calculation. The results from the two methods are compared and recorded on form CHP-157. If the results are not in reasonable agreement, then normally another resin sample will be taken and sent to chemistry for analysis.
3.2.1 Isotopic Analysis obtain the volume of resin transferred from Operations and the isotopic concentration from chemistry.
Total Liner Activity = Resin Volume x Isotopic Concentration Example: 70 ft3 of resin is transferred. Chemistry determines that the isotopic concentration is 10 pCi/cm3 Total Liner Activity = 70 ft3 x 10 pCi/cc3 x 28317 cm3/ft3 x 1 Ci IE+06 pCi ,
= 19.82 Ci 3.2.2 QADH Calculation QADH is a computer program that may be used to determine total liner activity. To use QADH, the isotopic concentration must be determined as well as the average radiation level around the liner.
The waste isotopic concentration is obtained from the resin sample sent to chemistry. !
t The average radiation level may be determined as follows: l l
- a. Determine the midplane of the resin within the liner. I For example, if the resin comes to a height of 4 feet, !
then readings will be taken at the 2 foot elevation. ;
}v
- b. Find the highest contact radiation reading around the liner at the midplane. This will be the starting .!
point.
- c. Determine the radiation level at four more equally spaced points. In all then, there will be 5 equally spaced points around the liner.
RDW 3.6 4 ! Page 3
- d. Record the contact readings and also determine the radiation levels at 0.5 meter, 1 meter, and 2 meters from the liner surface.
- e. Send all results'to the engineer or NPS assigned to radwaste.
3.3 Evaporator Bottoms Total Liner Activity = Evaporator Bottoms Volume x Isotopic Concentration 3.3.1 The volume of evaporator bottoms in a liner can be estimated by noting the waste feed speed and running time of the Atcor system when the liner is filled.
3.3.2 An alternate method of determining the volume of bottoms in
'the liner is to measure the level drop in the Atcor waste tank.
3.3.3 Conversion factors to be used to convert waste feed speed or tank level to volume can be obtained from charts in the Atcor cubicle.
3.3.4 The isotopic concentration (pci/cm3) can be obtained from Chemistry.
3.4 Mechanical Filters Filter activity is determined by two parameters, number of filters and type of filter.
l' .
3.4.1 The number and type of filters are obtained from Operations records or the waste permit log maintained by the Nuclear Plant Specialist or engineer assigned to radwaste.
3.4.2 The estimated activity per filter by filter type is tabulated below.
l
( Table 1 Activity of Filters
! Filter Type Activity per Filter Waste Evaporator Feed 5.1 mci Blowdown Evaporator Bottoms 5.2 mci Steam Generator Blowdown 0.00022 mci t
i
-,_,,.-,,,,m,.e-..,,---,,--r-n,,-- ,,-,.,,.n.,,,
,-__,-,,,,-,,,,,,.,,,,.-_._..,_,..._,,,_.,,,n,-,n,,,.,,__ - , , . . . _ , .
4 RDW 3.6 Page 4 3.4.3 Total Activity = Number of Filters X Activity per Filter Example: 60 blowdown evaporator filters are in a liner.
- Activity = 60 filters x 5.2 mci / filter = 312.0 mci 3.5 Mixture of Wastes The activity of a mixture of resins, bottoms, and/or filters is found by calculating the activity of each component and adding them together.
4.0 RADWASTE LINER FILLING AND STORAGE 4.1 Prior to issuing a radiation work permit for transferring waste into a liner, Health Physics should assure that the Nuclear Plant Specialist or engineer assigned to radwaste has approved the isotopic analysis and volume of the waste.
4.2 Before the liner is filled, cover the liner with plastic. This will make deconning easier.
('
4.3 After the liner is filled by Operations ud before it is placed in storage behind the Atcor cubicle shield wall, a thorough radiation survey is to be taken using form CHP-21 Area 36.
NOTE: THIS SURVEY IS NOT REQUIRED FOR LINERS WHICH ARE FILLED WHILE CONTAINED WITHIN A SHIPPING PACKAGE (CASK).
Survey each area as indicated on form CHP-21 Area 36 and record results. Ensure that the highest radiation level is recorded by location.
4.4 Perform a removable external contamination survey of the liner.
i Sufficient smears should be taken so that results will be representative of the total liner area. Record results on form CHP-21 Area 36.
! Liner External Contamination Limits Under normal conditions, liners which have external removable contamination in excess of 22,000 dpm/100 cm2 will be decontaminated I to below this limit.
l NOTE: LINERS IN EXCESS OF 22,000 DPM/100 CM2 SHALL NOT BE PLACED IN THE UNDERGROUND STORAGE VAULTS UNLESS AUTHORIZED BY A I -
CHP SUPERVISOR.
(
i l- _ _ .__ _ _ . _ _ , _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _
/
e c . .
RDW 3.6
( , Page 5 4.5 Record the following additional information on form CHP-21 Area 36.
i 4.5.1 Liner serial number 4.5.2 Liner waste permit number 4.5.3 Liner storage location 4.6 When completed, the yellow copy of form CHP-21 Area 36 is to be sent to the Nuclear Plant Specialist or engineer assigned to radwaste.
4.7 The Nuclear Plant Specialist or engineer assigned to radwaste should inspect the liners for solidificatior. (with proper consideration of ALARA) and verify the absence of free standing liquids. At this time the liner may be placed in the underground storage vaults if external contamination levels are less than 22,000 dpm/100 cm2, 5.0 PREPARATION FOR SHIPMENT 5.1 The Nuclear Plant Specialist or engineer assigned to radcaste should j
- schedule the liner for shipment to a burial site.
(
5.2 On arrival'of the shipping package (cask):
5.2.1 Complete incoming removable external contamination survey of vehicle, trailer and cask.
5.2.2 Prepare radiation work permit for loading liner into cask as required.
5.2.3 Complete the radiation and contamination surveys as required by the specific cask checkoff forms.
5.2.4 Upon completion of loading, refer to the applicable portions of Radioactive Material Handling Manual for preparing the shipping package (cask) and vehicle for shipment.
l
-w.-y-- ----m +7w-+e e g-w ~ F=- <-wy- -ow-m r-q-+--ee-w-www---g-----we,---m-g -
ww.yw.-ywww-wee---,-we g--= vyw s g =-w o--e w w w- e- www,w-w-=w--v-en-++mmipww-ww--weee-
