|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20199E0361999-01-12012 January 1999
Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS
ML20196F6451998-11-30030 November 1998
Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20216C6381997-08-29029 August 1997
Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20196G8781997-07-18018 July 1997
Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program
ML20148K6141997-06-0505 June 1997
Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML17187A7991997-02-17017 February 1997
Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20135B0581996-11-25025 November 1996
Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3231996-10-23023 October 1996
Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS
ML20129C2391996-10-16016 October 1996
Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage
ML20129D3981996-09-20020 September 1996
Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20113B6001996-06-20020 June 1996
Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20112E6341996-05-22022 May 1996
Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage
ML20086D4741995-06-30030 June 1995
Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20087H8651995-05-0202 May 1995
Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20125D6381992-12-0808 December 1992
Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20106A6221992-09-15015 September 1992
Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20099D7791992-07-29029 July 1992
Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity
ML20096F1161992-04-24024 April 1992
Proposed Ts,Changing OL Section 2.G Re Reporting Requirements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
1999-04-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
ML20058E8601990-04-30030 April 1990
Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1
ML20055C3401990-02-13013 February 1990
Revised Dssp Procedures,Consisting of Rev 2 to Dssp 100-B, Rev 2 to Dssp 100-B1 & Rev 3 to Dssp 100-A2/B2
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20150C1171988-02-29029 February 1988
Rev 1 to Dresden Nuclear Power Station Process Control Program
ML20237J8081987-08-31031 August 1987
Rev 0 to Emergency Plan Implementing Procedure EPIP 200-T4, Containment Radiation Time Dependent Correction Factors
ML20235S3091987-07-31031 July 1987
Rev 0 to NSHP-RP Guidance 1100-2, Radiation Chemistry Foremen Shift Coverage
ML20203L3551986-04-30030 April 1986
Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor
ML20205C8311986-04-30030 April 1986
Rev 11A to Offsite Dose Calculation Manual
ML20099D0241984-09-30030 September 1984
Rev 7 to Dts 1600-7, Unit 2/3 Integrated Primary Containment Leak Rate Test
ML20090H7611984-03-31031 March 1984
Procedure INPO 84-010(NUTAC), Vendor Equipment Technical Info Program
ML20070J0071982-10-0101 October 1982
IE Bulletin 79-14 & Tap Piping Evaluation,Quad Cities Units 1 & 2 & Dresden Units 2 & 3, Revision 0
ML20070H9951982-09-30030 September 1982
EDS-NUTECH Interface Control Instructions, Revision 0
ML20199E3821982-07-0707 July 1982
Rev 0 to Emergency Plan Implementing Procedure EPIP 500-9, Operational Check of Notification Phone List
ML20062B4351982-07-0707 July 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C7, Security Director & Revision 0 to EPIP 500-9, Operational Check of Notification Phone List
ML20062B1761982-06-30030 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C8, Rad/Chem Director. Revised Index of Station Group Director Duties Encl
ML20054J8691982-06-0202 June 1982
Public Version of Revised Generating Station Emergency Plan Environ Director Emergency Plan Implementing Procedures, Including Revision 2 to Procedure ED-3 Re Demand Polling of Meteorological Data
ML20054H1521982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
ML20054H4291982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
1999-04-30
[Table view] |
Text
,
DRESOEM NUCLEAR POWER STATION PROCESS CONTROL PROGRAM Revision 1 FEBRUARY, 1988 0
R
e INDEX A. Purpose B'. References C. Vendor Process System (s)
D. Liquid Waste Processing System (Stock System)
E. Dry Active Waste (DAW)
F. Secondary Wa'ste Streams s
C. Inspection H. Shipment i
/
\
0801a 2 of 6
s i 1 Dresden Nuclear Power Station Process Control Program A. Pu rpose.
The purpose of the Dresden Nuclear Power Station (DWPS) Process Control Program is to establish the process parameters which will provide a reasonable assurance that all low-level radioactive waste (LLRW) processed at Dresden Station will meet or exceed any and all acceptance criteria for processing, packaging, and shipment of LLRW to licensed burial facilities.
This criteria includes all Department of Transportation (DOT),
Nuclear Regulatory Cor. mission (NRC), State, and licensed burial f acilities rules and regulations for the processing, packaging, and shippir$ of LLRW.
Although a Stock Equipment Company cement solidification systea was installed during 1919 DNPS currently uses commercial, vender supplied, processing systems for the processing of the primary liquid
LLRW streams generated by the Station.
Com.monwealth Edison requires that all vendors used to procers liquid LLRW at DNPS must meet all applicable Commonwealth Edison Co quality standards and shall have submitted a Process System Topleal Report to the NRC. Fu rthe rmo re , the vendor solidlfication/ stabilization media must be approved by the licensed burial sites.
B. References.
1.
The following references were used as guidelines in preparing the Dresden Station Process Conten1 Program,
- a. Dresden Tcebnical Specifications.
(1) 3.8.F. and 4.8.F., Solid Radioactive Waste.
(2) 6.9., Process Control Program
- b. Dresden Procedures.
(1) DOP 2000 Series, Radwaste operating Procedores.
(2) Special Procedures (as needed).
- c. Commonwealth Edison Program for Implementation of 10 CFR Part 61 and 10 CFR Part 20.311 Dated December 22, 1983. {
j
- d. Commonwealth Edison Quality Assurance Manual. l t
- e. 10 CFR Part 20.311 Transfer for Disposal and Manifests. I
{
f.
10 CFR Part 61 Licensing Requirements for the Land Disposal of Radioactive Waste.
)
l 0801a s
3 ofi%
l
s, lI
,,I y .)
. . 'r,
- g. I NRC Branch Technical Position on Waste Form.
h.
Stock Equipment company Process Control Program for BWRs.
2.
The following referencer. are utilized in this PCP for information only.
a.
EUREG 0133 Preparation of Radiological Effluent Technical Specifications for Nuclear Fower Plants - October 1978.
- b. Dresden Final Safety Analysis Report. '
s I '..
Section on Solid Waste Management System.
,r C. Vendor Process System (s).
DNPS currently uses commercial, vendor supplied, processing systems for the the processing of the primary liquid LLRW streams generated by Station.
/i Commonwealth Edison requires that all vendors used to process lig>id LLRW at DNPS must meet all applicable Cc7monwealt] Edison Co. quality '
standards the NRC. and shall have submitted a Proiyas System Topical Report to Furthermore, the vendor solidi'4catich/ stabilization media must be approved by the licensed burial rites. '
D.
Liquid Waste Processing System (Stock Sys: tem).
The Stock Equipment Solidification Jystem method of solidification involves putting a specified amount of solidifying agent (Portland or masonry cement) f into a modified type 11-C drum. A mixing weight is I added to the drun and it is transferred to the drum filling station At the filling station the drum is opened, a prescribed charce of waste is added to the drum and it is capped and tumbled. This operation is repeated a second time to complete the waste drum fill.
The Stock Solidification System is operated in accordance with ,-
procedures developed by Stock.
The formulas used to fill waste and cement into a drum are those developed in the Stock Process Control Program. Tumbling timeI are es recommended by Stock.
- 1. Spent resins.
Spentholding resin resins are pumped f rom the'r service units to a spynt; tank.
sampled. Thecontents'ofthistankareperloolcal;h,
Spent resins are slu',lced to a decanting tank where ,
they are allowed to sett:a, und the appropriate amount of water is adjusted. Drume are fille 4 by pumping from this tank f directly to drums.
A completU description of the transfad. '
decanting and drum filling operation can be found in DOP 2000-33, 35 and 36.
mixture is used in the drumming process.The Mixing Stock parameters PCP4th formula i for waste as recommended by Stock. ' '
i
/
/
s 0801a 4 of 6
. 2. Concentrated Licuids.
Concentrated wastes are pumped from the concentrator / evaporators through a holding tank to a concentrated waste tank. Samples of 7 each batch of evaporator bottoms are sampled every time the
concentrator is dumped. The prescribed amount of waste and concretc~ in a drum are determined from Stock pCP formulas.
1' Drums are filled according to procedures using the appropriate fo rmula t ion. The first drum from every batch is opened and ch ' examined for uniformity of mixing, solidification and presence ,
of f ece standing water. A complete description of the transfer, decanting, and drum filling operation can be found in DOP 2000-34, 35, 36 and 43.
- 3. Filter sludges.
Filter sludges are collected in a holding tank. When sludge is to be processed, it is pumped from the holding tank to a decanting tank where the amount of water is adjusted. Drums are filled by pumping from this tank directly to drums. Samples of sludge are taken for analysis either directly from a drum or during the transfer to decant tank. A complete description of the transfer, decanting and drum filling operation can be found in Dop 2000-32, 35 And 36. Stock system formulas are used to determine waste / concrete ratios and mixing times.
- 4. L Stock drums are capped prior to the second tumbling and ramain capped. Experience has demonstrated that no problems have developed due to the exothermic reaction during processing in this system. '
2
((, + E. Dry Active Waste (DAW). *
\
/
DAW is collected throughout the plant in various containers.
potentially clean items are surveyed and released. DAW items are 1 sorted for compactibio and non-compactible wastes. Non-compactible ;
items are further sorted into items that can be decor.taminated and items that cannot be decontaminated. Compactible wastes are precompacted into metal drums using the Station's commercial i
compactor and then shipped to a comme.'clal volume reduction facility
' for super-ccmpaction services. Commercial vendor decontamination services and facilities may be used for decontamination of bulk items. Non-compactible, non-recoverable items are volume r:fuced to the extent practical and placed into strong, tight container. and shipped to burial. Dresden personnel handle all collecting, Processing and shipping of DAW. .
I F. Secondary Waste Streams.
Y a
periodically, wastes are generated fecm such sources as decontaminations, tank cleaning, sump cleaning and waste oil. Wastes
^ generated in this manner are sampled on a batch basis. Appropriate !
formulas for ratioing solidification agent to waste are developed or. !
' ' small bench samples, or if the consistency of the waste is known.
from establis'hed formulas.
t y 0801a '
i' 5 of 6
~
Dresden Station ships large volumes of contaminated oil by utilizing the on-site vendor processing system and vendor oil solidification process Control program. Smal*. quantitles of oily wastos may be prepared for shipment to U.t. Ecology at Richland, WA., by absorbing the waste in an approved absorbent media in accordance with the U.S.
Ecology Burial license.
O. Inspection.
All shipping containers (drums and boxes) are inspected for compliance with DOT and burial site requirements prior to use, periodically, the Quality Assurance Department destructively examines filled containers. A random sample of each waste stream is chosen by the Quality Assurance Department. Drums are inspected for free standing water, quality of solidification and mixture. Samples are '
taken at least once in every ten batches. A batch is defined es:
Evaporator Bottoms Every concentrator dump is considered a batch.
Resins Every time Rad-Chem samples resin holding tank.
Sludge Annually.
If f ree standing water is observed, additional samples of the t particular series of batches are taken to establish a statistical '
base. Additional samples will be taken as warranted by this base.
process parameters in use during the production of these drums will be lavestigated and corrective actions taken as warranted.
Drums found to contain free standing liquid will be decanted, then r packaged in overpack drums and surrounded with approved absorbent prior to shipment. ,
l H. Shipment. '
i I i
All wastes shipped off site are packaged in DOT approved shipping i containers. All transport vehicles must meet the appropriate DOT and tTRC requirements prior to loading. Packages are inspected and shipments (vehicles) are inspected for compilance with DOT, NRC and f burial site criterion prior to leaving the site.
i l E
l 4
k 1
i
. 0801a '
l
. 6 of 5
