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 1ML20148K614 |
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Dresden ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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06/05/1997 |
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COMMONWEALTH EDISON CO. |
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ML20148K580 |
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References |
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NUDOCS 9706180214 |
Download: ML20148K614 (7) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20199E0361999-01-12012 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 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 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 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 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 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits 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 ML20058L9381990-07-31031 July 1990 Proposed Tech Specs Reflecting Nonoperating Status of Facility & Clarifying Section 3.10.F ML20137C2401986-01-0707 January 1986 Proposed Tech Specs,Deleting Authority to Operate Unit & Sys Requirements & Surveillances No Longer Applicable ML20052C0761982-04-29029 April 1982 Proposed Changes to Licenses DPR-19,DPR-25,DPR-29 & DPR-30 Re Surveillance Requirements to Test Automatic Pressure Relief Valves Daily When HPCI Subsystem Is Inoperable ML17194A4181982-01-12012 January 1982 Revised Tech Spec Tables 4.2.1 & 3.2.4 Re Restoring Inoperable Indication Prior to Startup ML17194A4061982-01-11011 January 1982 Proposed Tech Specs Re Reload Fuel & Core Design,Transients & Accident Analyses & LOCA Analysis ML18025B6791981-10-19019 October 1981 Proposed Revisions to Tech Spec 4.7.A Re Surveillance Requirements,Primary Containment ML19343D1181981-04-0303 April 1981 Proposed Revision to Tech Spec Table 3.6.1 ML19309H8901980-05-15015 May 1980 Proposed Changes to Tech Specs,Deleting Requirement to Maintain at Least Three Counts Per Second on Each Source Range Monitor When Only Two Fuel Assemblies Are in Quadrant ML17174A1051979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility ML17174A1061979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3 to Permit Reactor Power Ascension to Proceed Along Modified Power/Flow Line,For Dresden Facility ML17174A1071979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility ML17174A1081979-11-0101 November 1979 Proposed Tech Spec Changes 1.1-3.2.3.,for Quad-Cities Facility ML20084D2751974-01-30030 January 1974 Proposed Tech Spec 15.4.11 Re Hydraulic Shock Suppressors 1999-01-12
[Table view] 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
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i ATTACHMENT 2 REPLACEMENT PAGES 3/4.8-2,6-2,6-3,6-5,6-6, AND 6-11 OF f!
TECHNICAL SPECIFICATIONS
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W i 9706190214 970605
- i. PCR ADOCK 05000010 l W PDR.
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, Sealed Sources 3/4.8.J l
3.8 - LIMITING CONDITIONS FOR REQUIRED 4.8 - SURVEILLANCE REQUIREMENTS EQUIPMENT PLANT SYSTEMS J. Liquid Radioactive Storage J. Liquid Radioactive Storage i The maximum amount of radioactivity in A sample from each of the above grade liquid storage in all Dresden Station's liquid waste tanks shall be taken, above grade tanks shall not exceed 90 analyzed, and recorded every 7 days. If 1
- curies. All tanks located within the no additions to a tarik have been made seismic portion of the Chemical Cleaning since the last sample, the tank need not Building are not c nsidered above grade be sampled until the next addition.
storage.
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APPLICABILITY:
At all times.
ACTION:
With the quantity of radioactive material in the tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tanks and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit by recycling the stored liquid to below grade tanks.
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l DRESDEN - UNIT 1 3/4.8-2 Amendment Nos. 39 r
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l Organization 6.2 l ADMINISTRATIVE CONTROLS fL2 QRGANIZATION 6.2.A Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safe storage of the irradiated fuel.
- 1. Lines of authority, responsibility, and communication shall be i established and defined for the highest management levels through intermediate levels to and including all operating organization positions;. These relationships shall be documented and updated, as l appropriate, in the form of organization charts, functional descriptions of departrnental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the Quality Assurance Manual. l
- 2. The Unit 1 Decommissioning Plant Manager shall have overall responsibility for Unit 1 and shall have control over those Unit 1 activities necessary for operation and maintenance of structures and systems necessary for the safe storage of irradiated fuel.
- 3. A Corponte Vice President shall have corporate responsibility for the safe storage of irradiated fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure the safe storage of irradiated fuel.
- 4. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
DRESDEN - UNIT 1 6-2 Amendment Nos. 39 l
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Unit Staff Qualification 6.3 :
l ADMINISTRATIVE CONTROLS 6.2.B UNIT STAFF The Unit Staff organization shall be as follows:
- 1. One of the non-licensed operators required for Unit 2/3 shall be assigned responsibility for Unit 1 while fuelis stored in the Unit 1 Fuel Storage Pool.
One of the persons qualified to stand watch in the Unit 2/3 control 2.
room shall be assigned responsibility for Unit 1 while irradiated fuelis '
stored in the Unit 1 Fuel Storage Pool. !
- 3. An individual qualified in radiation protection procedures shall be on- I site and assigned to Unit 1 during Unit 1 fuel handling operations.
- 4. All fuel handling operations shall be directly supervised by a Qualified Unit 1 Supervisor. #
- 5. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform operations on the Unit 1 irradiated fuel, e.g, Qualified Unit 1 Supervisor, health physicists, auxiliary operators, key maintenance personnel and fuel handlers.
The amount of overtime worked by unit staff members who perform work on Unit 1 irradiated fuel shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).
- 6. The Unit 2/3 Operations Manager or Unit 2/3 Shift Operations Supervisor shall hold a Unit 2/3 Senior Reactor Operator Licer.se.
6.2.C SHIFT TECHNICAL ADVISDB - { DELETED}
I (a) A Qualified Unit 1 Supervisor is a person who has a valid Senior Reactor Operators License on Units 2(3). (SRO or SRO-L) or a person certified to an approved training prograrn as a Qualified Unit 1 Supervisor, DRESDEN - UNIT 1 6-3 Amendment Nos. 39 l
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Procedures and Programs 6.8 ADMINISTRATIVE CONTROLS SE EllOCEDURES AND PROGRAMS 6.8.A Written procedures shall be established, implemented, and maintained covering the activities referenced below:
- 1. The procedures applicable to the safe storage and handling of irradiated fuel recommended in Appendix A, of Regulatory Guide 1.33, Revision 2, February 1978;
- 2. Emergency Operating Procedures, -
{ DELETED}
- 3. Station Security Plan implementation,
, 4. Generating Station Emergency Response Plan implementation,
- 5. PROCESS CONTROL PROGRAM (PCP) implementation,
- 6. OFFSITE DOSE CALCULATION MANUAL (ODCM) implementation,
- 7. Fire Protection Program implementation, and
- 8. Winterization Program applicable to the safe storage and handling of irradiated fuel.
6.8.B { DELETED}
6.8.C { DELETED}
6.8.D The following programs shall be established, implemented, and maintained:
- 1. Reactor Coolant Sources Outside Primary Containment - { DELETED}
- 2. In-Plant Radiation Monitoring - { DELETED}
- 3. Post Accident Sampling - { DELETED}
DRESDEN - UNIT 1 6-5 Amendment Nos. 39 I _ _ _ _ _
, R diorctiva Efflu:nt Control Program 6.8.D.4 ADMINISTRATIVE CONTROLS _.
- 4. Radioactive Effluent Controls Program i
A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to l members of the public from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by station procedures, and (3) shall include remedial 1 actions to be taken whenever the pr gram limits are exceeded. The program shall include the following elements:
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- a. Limitations on the operability of radioactive liquid and gaseous l monitoring instrumentation including surveillance tests and set- j point determination in accordance with the methodology in the ODCM,
- b. Limitations on the instantaneous concentrations of radioactive material released in liquid effluents to unrestricted areas conforming to ten (10) times the concentration values in 10 CFR Part 20, Appendix B, Table 2, Column 2 to 10 CFR Part 20.1001 -
20.2402,
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with i the methodology and parameters in the ODCM, l
- d. Limitations on the annual and quarterly doses to a member of the public from radioactive materials in liquid effluents released from each Unit conforming to Appendix i to 10 CFR Part 50,
- e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days,
- f. Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose conforming to Appendix I to 10 CFR Part 50, l
DRESDEN - UNIT 1 6-6 Amendment Nos. 39
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- t a High R distion Area 6.12
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ADMINISTRATIVE CONTROLS 6.12.B in addition to the requirements of 6.12.A, areas accessible to personnel ,
with radiation levels greater than 1000 mrem /hr at 30 cm (12 in.) from the i radiation source or from any surface which the radiation penetrates shall I require the following:
4 l 1. Doors shall be locked to prevent unauthorized entry and shall not l prevent individuals from leaving the area. In place of locking the door, -
direct or electronic surveillance that is capable of preveniing ;
l unauthorized entry may be used. The keys shall be maintained under t l the administrative control of the Shift Manager on duty and/or health !
physics supervision. ,
- 2. Personnel access and exposure control requirements of activities 'seing !
performed within these areas shall be specified by an approved RWP l (or equivalent document), t i
i 3. Each person entering the area shall be provided with an alavning radiation monitoring device that continuously integrates the radiation !
dose rate (such as an electronic dosimeter.) Surveillance and radiation monitoring by a Radiation Protection Technician may be substituted for i an alaiming dosimeter. 1
- 4. (DELETED) l
- 5. For individual HIGH RADIATION AREAS accessible to personnel with i
radiation levels of greater than 1000 mrem /h at 30 cm (12 in.) that are located within large areas where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual areas, then such individual areas shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device.
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DRESDEN - UNIT 1 6-11 Amendmen: Nos. 39 1