ML20129F323
| ML20129F323 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/23/1996 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20129F320 | List: |
| References | |
| NUDOCS 9610290096 | |
| Download: ML20129F323 (76) | |
Text
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ATTACHMENT 3 i
PROPOSED AMENDED TECHNICAL SPECIFICATION PAGES I
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9610290096 961023 PDR ADOCK 05000010 ;
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l DRESDEN STATION l
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! UNIT 1 1
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(DPR-2)
4 TABLE OF CONTENTS TOC ,
DEFINITIONS SECTION PAGE Section 1.0 DEFINITIONS OFFSITE DOSE CALCULATION MANUAL (ODCM) . . . . . . . . . . . . . . 1-1 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . ............ . 1-1 REPORTABLE EVENT . . . . . . . . . . . . . . . ...... ............ 1-1 SAFETY LIMITS and LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE Section 2.0 SAFETY LIMITS and LIMITING SAFETY SYSTEM SETTINGS 2d SAFETY LIMITS ................................. { DELETED) la LIMITING SAFETY SYSTEM SETTINGS ................. (DELETED}
BASES Zl SAFETY LIMITS .................... ... . ..,.
{ DELETED}
22 LIMITING SAFETY SYSTEM SETTINGS ........... ....
{ DELETED}
DRESDEN - UNIT 1 i Amendment Nos.
TABLE OF CONTENTS TOC LIMITING CONDITION FOR REQUIRED EQUIPMENT and SURVEILLANCE REQUIREMENTS SECTION PAGE i I
Sections 3/4 LIMITING CONDITION FOR REQUIRED EQUIPMENT AND SURVEILLANCE l REQUIREMENTS l 3/4.1 through 3/4.7 ........................................ (DELETED}
3/4.8 PLANT SYSTEMS 3/4.8. A through 3/4.8.F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..
....(DELETED}
3/4.8.G Scaled Source Contamination .......... ....... ....... 3/4.8-1 3/4.8.H ...................... ... ... . ... ..
....(DELETED}
3/4.8.1 ............................ ........ .. . . . . . Not used 3/4.8.J Radioactive Waste Storace . . ......... ...... . ....... 3/4.8-2 3/4.9 ......................................... .. .. ..(DELETED) j 3/4.10 FUEL HANDLING AND STORAGE . . . . . . . . . . . . . . . ..... . 3/4.10-1 i j
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i DRESDEN - UNIT 1 ii Amendment Nos.
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TABLE OF CONTENTS TOC LIMITING CONDITION FOR REQUIRED EQUIPMENT and SURVEILLANCE REQUIREMENT BASES i SECTION PAGE i
B 3/4.1 through B 3/4.7 ......................................(DELETED}
B 3/4.8 PLANT SYSTEMS B 3/4.8.A through B 3/4.8.F ............................. .....(DELETED} ,
l B 3/4.8.G Sealed Source Contamination .......................... B 3/4.8 1 B 3 /4. 8. H . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ( D E L ET E D }
B 3/4.8.1 ..................................................Notused B 3/4.8.J Radioactive Waste Storaae . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4.8-1 B 3/4.9 ...................................... ..... .....{ DELETED} l B 3/4.10 FUEL HANDLING AND STORAGE .......... ... . . . , . . B 3/4.10-1 t
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l DRESDEN - UNIT 1 iii Amendment Nos.
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. .- . . _ . ._ . . . _ . . . _ _ . _ . . - _ = _ _ . . _ _ _ _ _ . _ - _ _ _ . _ . - _ . . _ _ ._
TABLE OF CONTENTS TOC DESIGN FEATURES SECTION PAGE Section 5.0 DESIGN FEATURES M SITE 5.1.A Site and Exclusion Area ............................ .... 5-1 :
5.1 B Low Population Zone . . . . . . . . . ........... ............. 5-1 5.1.C Radioactive Gaseous Ef fluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 1
5.1.D Radioactive Liquid Ef fluents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 ;
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L2 CONTAINMENT ..................................(DELETED} I M REACTOR CORE ...................................... 5-1 M REACTOR COOLANT SYSTEM ........................(DELETED} ,
i M [lNTENTIONALLY BLANK]
M FUEL STORAGE i
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5.6. A K ,n . . . . . . . . . . . . . . . . . . . . . . . . . . .... ......... ...... .... 5-1 1
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i DRESDEN - UNIT 1 iv Amendment Nos.
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TABLE OF CONTENTS TOC i I
ADM'NISTRAT!VE CONTROLS SECTION PAGE Section 6.0 ADMINISTRATIVE CONTROLS f S.J. RESPONSIBILITY l
6.1.A Unit 1 Decommissioning Plant Manager ......... ............ 6-1 l
6.1.B Station Manager ........... .......................... 6-1 6.1.C Shif t Manager . . . . . . . . . . . . . .... ...... 6-1 l
t DJ ORGANIZATION ;
1 6.2.A Onsite and Offsite Organizations . . . . . . . . . . . . .., .......... 6-2 ,
6.2.B U nit S t a f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6- 3 ,
6.2.C Shift Technical Advisor - (DELETED} . . . . . . . . . . ... ..... . 6-3 SJ 1) NIT STAFF QU ALIFIC ATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 l
f4 TRAINING........................................... 6 -4 l
SJ ll NTE NTIO N ALLY B LA N K] . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 I 33 IINTE NTIO N ALLY B LAN K] . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-4 6.7 SAFETY LIMIT VIOLATION - (DELETED} . ........... ..... . 6-4 DRESDEN - UNIT 1 v Amendment Nos.
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TABLE OF CONTENTS TOC 1 t
ADMINISTRATIVE CONTROLS SECTION PAGE El PROCEDURES AND PROGR AMS . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 6.8.A Pr oced u r e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 i
6.8.8 ( D E L ET E D } . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . -. 6-5 6.8.C ( D E L ET E D ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-5 I t
6.8.D Programs ...................................... . . . . 6- 5 SJ REPORTING REQUIREMENTS 6.9.A Routine Reports . . . . . . . . . . . . . . . . . .. ..................68 6.9.B S pecial Reports . . . . . . . . . . . . . . . . . . . . . . . ..............6-9 6.10 llNTENTION ALLY BLANKl . . . . . . . . . . . . . . . . . . . . . . . . . ......6-9 HJ,j. RADIATION PROTECTION PROGRAM .......................6-9 fj_2 HIG H R ADI ATIO N AR E A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6- 10 i
Sd3 PROCESS CONTROL PROGR AM . . . . . . . . . . . . . . . . . . . . . . . . . . 6-12 514 OFFSITE DOSE CALCULATION MANUAL . . . . . . . . . . . . . . . . . . . . 6-13 LIST OF TABLES ............................... .{ DELETED}
LIST OF FIGURES .................................... NONE l
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! DRESDEN - UNIT 1 vi Amendment Nos.
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Definitions 1.0 1.0 DEFINITIONS !
t The following terms ara defined so that uniform interpretation of these specifications may be achieved. The defined terms appear in capitalized type and shall be applicable throughout these Technical Specifications.
OFFSITE DOSE CAlfULATION MANUAL (ODCM) ;
The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by ;
Specification 6.8 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent ~
Release Reports required by Specification 6.9.
The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analysis, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial 1 ground requirements, and other requirements governing the disposal of solid radioactive waste.
I REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
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I DRESDEN - UNIT 1 1-1 Amendment Nos. j
Sealed Sources 3/4.8.G 3.8 - LIMITING CONDITIONS FOR REQUIRED 4.8 - SURVEILLANCE REQUIREMENTS EQUIPMENT PLANT SYSTEMS i G. Sealed Source Contamination G. Sealed Source Contamination Each sealed source containing radioactive 1. Test Requirements - Each sealed material either in excess of 100 Ci of beta source shall be tested for leakage and/or gamma emitting material or 5 Ci of and/or contamination by:
alpha emitting material shall be free of 20.005 pCi of removable contamination, a. The licensee, or
- b. Other persons specifically APPLICABILITY: authorized by the Commission or an Agreement State.
At all times.
The test method shall have a detection sensitivity of at least ACTION: 0.005 Ci per test sample.
- 1. With a sealed source having removable 2. Test Frequencies - Each category of contamination in excess of the above limit, sealed sources, excluding startup withdraw the sealed source from use and sources and fission detectors either: previously subjected to core flux, shall be tested at the frequency described
- a. Decontaminate and repair the sealed below.
source, or
- a. Sources in use - At least once per 6
- b. Dispose of the sealed source in months for all sealed sources accordance with Commission containing radioactive material:
- Regulations.
- 1) With a half-life > 30 days,
- 2. With a sealed source leakage test revealing excluding Hydrogen 3, and the presence of removable contamination in excess of the above limit, a report shall be 2) In any form other than gas.
prepared and submitted to the Commission on an annual basis, b. Stored sources not in use - Each sealed source shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources transferred without a certificate j indicating the last test date shall be tested prior to being placed into use.
DRESDEN - UNIT 1 3/4.8-1 Amendment Nos.
Sealed Sources 3/4.8.J 3.8 - LIMITING CONDITIONS FOR REQUIRED 4.8 - SURVEILLANCE REQUIREMENTS EQUIPMENT PLANT SYSTEMS J. Liquid Radioactive Storage J. Liquid Radioactive Storage The maximum amount of radioactivity in A sample from each of the above grade liquid storage in all Dresden Station's above liquid waste tanks shall be taken, analyzed, grade tanks shall not exceed 90 curies. All and recorded every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if no additions tanks located within the seismic portion of to a tank have been made since the last the Chemical Cleaning Building are not sample, the tank need not be sampled until considered above grade storage. the next addition.
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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> reduce the tank contents to within the limit by recycling the stored liquid to below grade tanks.
DRESDEN - UNIT 1 3/4.8-2 Amendment Nos.
Pool Water Level 3/4.10A l 1
3.10 - LIMITING CONDITIONS FOR 4.10 - SURVEILLANCE REQUIREMENTS f REQUIRED EQUIPMENT i 1
FUEL HANDLING AND STORAGE i
A. Fuel Storage Pool Water Level and Quality A. Fuel Storage Pool Water Level and Quality
- 1. Water Level - Fuel Storage Pool 1. Water Level - Fuel Storage Pool The Fuel Storage Pool water level shall be The water level in the Fuel Storage Pool j maintained at a level of 218 feet, shall be determined to be at least at its minimum required depth at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .
- 2. Water Quality - Fuel Storage Pool
- 2. Water Quality - Fuel Storage Pool
- a. Cl less than or equal to 0.5 ppm The Fuel Storage Pool Water shall be
- b. Conductivity less than or equal sampled and analyzed at least once per 30 to 10.0 micrombos per cm at days.
25'C l
- c. pH 5.3 to 8.6 APPLICABILITY:- i Whenever irradiated fuel assemblies are in .
the Fuel Storage Pool.
ACTION:
- 1. With the requirements of Fuel Storage Pool water level specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the Fuel Storage Pool area after placing the fuel assemblies and crane load in a safe condition, and restore pool level.
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- 2. If any of the water quality specification limits are exceeded, prepare and l submit to the NRC, within 30 days, a Special Report which identifies the cause(s) for exceeding the limit (s) and i define the corrective actions to be ;
taken to ensure that future water j quality is in compliance. !
I DRESDEN - UNIT 1 3/4.10-1 Amendment Nos.
l PLANT SYSTEMS S 3/4.8.G l
BASES l
PLANT SYSTEMS '
3/4.8.A through 3/4.8.F - { DELETED}
1 3/4.8 G Sealed Source Contamination I
The limitations on removable contamination for sources requiring leak testing, including i alpha emitters,is based on 10 CFR 70.39(c) limits for plutonium. This limitation will l ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources, including startup sources and fission detectors, are classified into three groups according to their use, with surveiliance j requirements commensurate with the probability of damage to a source in that group. '
Those sources which are frequently handled are required to be tested more of ten than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.8.H - { DELETED}
3/4.8.1 - Not used i 3/4.8.J Liauid Radwaste Storaae The maximum gross radioactivity in liquid storage in the specified tanks has been limited on the basis of an accidental spill from all stated tanks due to a seismic event great enough to damage them. The Chemical Cleaning Building is seismically designed and designed to contain a simultaneous spill from all the contaminated liquid storage tanks housed within. Assuming a low river flow of 3100 ft'/sec, a day period over which the radioactive liquid wastes are diluted in the river, and consumption of the water by individuals at standard man consumption rate (3000 ml/ day), the single intake by an individual would not exceed one-third the yearly intake allowable by 10 CFR 20 for unidentified radioisotopes (1 x 104 uCi/ml). The factor of 3 was applied to 10 CFR 20 limits as recommended for situations in which population groups could be exposed.
The sampling frequency has been established so that if the maximum amount of gross radioactivity is exceeded, action can be taken to reduce the radioactivity to a level below the specified limit.
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DRESDEN - UNIT 1 B 3/4.8-1 Amendment Nos.
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1 Pool Water Level 3/4.10A BASES 1
l 3/4.10.A Fuel Storaae Pool Water Level And Quality I To assure there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minirnum pool water level is established. The minimum water level of 18 ;
feet is established because it would be a significant change from the normal level, well i above a level to assure adequate cooling (just above active fuel) and above the level at t
which the GSEP action is initiated (5' uncontrolled loss of level with level decreasing).
To prevent the growth of micro-organisms and concern about corrosion of metallic pool structures, quality limits for fuel pool water chemistry ha/e been established.
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l DRESDEN - UNIT 1 B 3/4.10-1 Amendment Nos.
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! SITE 5.1 1
5.0 DESIGN FEATURES
.6.d. SLT.E 5.1.A Sita and Exclusion Area Dresden Unit 1 is located at the Dresden Nuclear Power Station which 1 consists of a tract of land of approximately 953 scres located in the '
Northwest quarter of the Morris 15-minute quadrangle (as designated by the U.S. Geological Survey), Goose Lake Township, Grundy County, Illinois. An Exclusion Area is shared with Units 2 and 3.
5.1.B Low Population Zone - { DELETED}
5.1.C Radioactive Gaseous Effluents Information regarding radioactive gaseous effluents shall be located in the OFFSITE DOSE CALCULATION MANUAL.
5.1.D Radioactive Liquid Effluents information regarding radioactive liquid ef fluents shall be located in the OFFSITE DOSE CALCULATION MANUAL.
M CONTAINMENT - { DELETED}
M REACTOR CORE 5.3.A Nuclear Fuel shall not be loaded into the reactor core. This is to ensure that a critical assembly of nuclear fuel is no longer possible in the reactor core.
M REACTOR COOLANT SYSTEM - (DELETED}
l M [lNTENTIONALLY BLANK]
l M FUEL STORAGE l
l 5.6.A The K.,, of the spent fuel storage pool shall be less than or equal to 0.90.
I DRESDEN - UNIT 1 5-1 Amendment Nos.
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Responsibility 6.1 6.0 ADMINISTRATIVE CONTROLS SJ RESPONSIBILITY 6.1.A _ The Unit 1 Decommissioning Plant Manager shall have overall responsibility for the Unit 1 Facility and shall delegate in writing the succession to this responsibility during his absence.
6.1.B The Unit 1 Decommissioning Plant Manager shall delegate to the Unit 2/3 Station Manager the responsibility to provide site support activities such as the PROCESS CONTROL PROGRAM, the OFFSITE DOSE CALCULATION MANUAL, Site Fire Protection Program, the Radioactive Effluent Controls Program and Emergency Preparedness.
6.1.C The Unit 2/3 Shif t Manager shall be responsible for directing and commanding the safe overall operation of the Dresden Station Site under all conditions. This shall include immediate notification of the NRC if required for a REPORTABLE EVENT.
1 DRESDEN - UNIT 1 6-1 Amendment Nos.
Organization 6.2 ADMINISTRATIVE CONTROLS SJ ORGANIZATION 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 shallinclude the positions for activities affecting the safe storage of the irradiated fuel.
- 1. Lines of authority, responsibility, and communication shall be 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 appropriate, in the form of organization charts, functional descriptions of departmental 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.
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- 2. The Unit 1 Decommissioning Plant Manager shall have overall responsibility for Unit 1 and shall have control over those Unit 1 i activities necessary for operation and maintenance of structures and ;
systems necessary for the safe storage of irradiated fuel.
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- 3. The Chief Nuclear Officer (CNO) shall have the corporate responsibility for overall plant nuclear safety and shall take any measures needed to l ensure acceptable performance of the staff in operating, maintaining, t and providing technical support to the plant to ensure nuclear safety, i
- 4. The individuals who train the 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.
4-j Unit Staff Qualification 6.3 '
ADMINISTRATIVE CONTROLS ?
6.2.B UNIT STAFF h a
The Unit Staff organization shall be as follows 1, One of the non-licensed operators required for Unit 2/3 shall be !
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assigned responsibility for Unit 1 while fuelis stored in the Unit 1 Fuel {
- Storage Pool. i i
- 2. One of the persons qualified to stand watch in the Unit 2/3 control ,
room shall be assigned responsibility for Unit 1 while irradiated fuel is ;
stored in the Unit 1 Fuel Storage Pool. '
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- 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 de. eloped 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 l 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 an active Unit 2/3 Senior Reactor Operators !
License. ;
6.2.C SHIFT TECHNICAL ADVISOR - (DELETED}
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(8) A Qualified Unit 1 Supervisor is a person who has a vahd Senior Reactor Operators Ucense on Unita 2(3), (SRO or SRO-U or a person certified to an approved traininD prograrn as a Quahfied Unit 1 Supervisor. {
P DRESDEN - UNIT 1 6-3 Amendment Nos. !
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Unit Staff Qualification 6.3 ADMINISTRATIVE CONTROLS M UNIT STAFF OUAllFICATIONS Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, " Selection and Training of Nuclear Plant Personnel", dated March 8,1971, except for the Radiation Protection Manager, who shall meet or exceed the qualifications of the Radiation Protection Manager as specified in Regulatory Guide 1.8, September 1975. NRC licenses are not required for Unit 1 staff as noted in the Order Authorizing Decommissioning dated September 3,1993.
S4 TRAINING A retraining and replacement program for the unit staff shall be maintained under the direction of the appropriate onsite manager. Training shall be in accordance with ANSI N18.1-1971 for appropriate designated positions and shall include familiarization with relevant industry operational experience.
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SJ [lNTENTIONALLY LEFT BLANK]
6.7 SAFETY LIMIT VIOLATION - (DELETED}
DRESDEN - UNIT 1 6-4 Amendment Nos.
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Procedures and Programs 6.8 ADMINISTRATIVE CONTROLS 1
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fa PROCEDURES AND PROGRAMS I l
6.8.A Written procedures shall be established, implemented, and maintained j covering the activities referenced below: l
- 1. The procedures applicable to the safe storage 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, and
- 7. Fire Protection Pro 0 ram implementation.
i 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}
l DRESDEN - UNIT 1 6-5 Amendment Nos.
Radioactive' Effluent Control Program 6.8.D.4 ADMINISTRATIVE CONTROLS '
- 4. Radioactive Effluent Controls Program j A program shall be provided conforming with 10 CFR 50.36a for the contro; of radioactive effluents and for maintaining the doses to 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 actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
- a. Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and set-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.
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM,
- 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 l 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, I
- f. Limitations on the operability and use of the liquid and gaseous >
effluent treatment systems to ensure that the appropriate portions I of these systems are used to reduce releases of radioactivity i when the projected doses in a 31-day period would exceed 2 per- I cent of the guidelines for the annual dose conforming to Appendix j i to 10 CFR Part 50, 1
l DRESDEN - UNIT 1 66 Amendment Nos.
. - . . . . - - - - . - .. .. ~ - -- . - .- -._ -. ..- - __ - - .-
i Radioactive Effluent Control Program 6.8.D.4 j
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l ADMINISTRATIVE CONTROLS 1 '
- g. Limitations on the dose rate resulting from radioactive materials l released in gaseous effluents from the site to areas at or beyond j the site boundary shall be limited to the following:
{ a) For noble gases:less than or equal to a dose rate of 500 ,
j mrem /yr to the whole body and less than or equal to a dose rate of 3000 mrem /yr to the skin, and ]
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l b) For lodine-131, lodine-133, tritium, and for all radionuclides in
- l. particulate form with half-lives greater than 8 days: less than j or equal to a dose rate of 1500 mrem /yr to any organ.
i h.
Limitations on the annual and quarterly air doses resulting from j noble gases released in gaseous effluents from each Unit to areas
- beyond the site boundary conforming to Appendix 1 to 10 CFR ;
- Part 50, j i !
j i. Limitations on the annual and quarterly doses to a member of the ;
public from lodine-131, lodine-133, tritium, and all radionuclides in i particulate form with half-lives greater than 8 days in gaseous l
effluents released from each Unit conforming to Appendix I to 10 CFR Part 50, ;
i I j j. Limitations on the annual dose or dose commitment to any !
member of the public due to releases of radioactivity and to i
I radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
- 5. Primary Containment Leakage Rate Testing Program - (DELETED}
DRESDEN - UNIT 1 6-7 Amendment Nos.
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Reporting Requirements 6.9 ADMINISTRATIVE CONTROLS DJ REPORTING REQUIREMENTS l
In additior. :o the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional l
- Administrator of the appropriate Regional Of fice of the NRC unless other*/ise noted. '
6.9.A. Routine Reports
- 1. {D'LETED}
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- 2. Annual Report Annual reports covering the activities of the Unit for the previous )
calendar year, as described in this section shall be submitted prior to May 1 of each year. l The reports required shall include: l
- a. Tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem / year and their associated person rem exposure according to work and job functions, e.g., surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and fuel handling.The dose assignments to various duty functions may be estimated based on pocket dosimeter or TLD. Smali exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate,
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at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions. j
- b. Specific Reactor Coolant Activity - { DELETED}
The Annual Radiological Environmental Operating Report covering the decommissioning activities during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
1 DRESDEN - UNIT 1 6-8 Amendment Nos.
l
Reporting Requirements 6.9 6.0 ADMINISTRATIVE CONTROLS
- 4. Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the decommissioning activities during the previous calendar year shall be submitted prior to April 1 of each year. The report shallinclude a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix l to 10 CFR Part 50.
- 5. Monthly Operating Report - (DELETED}
- 6. Core Operating Limits Report - (DELETED}
6.9.B Special Reports l
Special reports shall be submitted to the Regional Administrator of the NRC I Regional Office within the time period specified for each report.
i I
$_dQ IINTENTIONALLY LEFT BLANKl i 52 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
DRESDEN - UNIT 1 6-9 Amendment Nos.
High Radiation Area 6.12 [
l ADMINISTRATIVE CONTROLS i L ,
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! 6.12 HIGH RADIATION AREA :
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j- 6.12. A Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of paragraph l l 20.1601 of 10 CFR Part 20, each high radiation area in which the intensity l of radiation is greater than 100 mrem /hr at 30 cm (12 in.) shall be l
barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit -l (RWP)*8 (or equivalent document). Any individual or group of individuals l permitted to enter such areas shall be provided with or accompanied by i one or more of the following: !
- 1. A radiation monitoring device which continuously indicates the ;
radiation dose rate in the area.
- 2. A radiation monitoring device which continuously integrates the l radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been j established and personnel have been made knowledgeable of them; or i
- 3. An individual qualified in radiation protection procedures with a !
radiation dose rate monitoring device, who is responsible for providing !
positive control over the activities within the area and shall perform l periodic radiation surveillance at the frequency specified in the RWP l (or equivalent document). !
i i
(b) - Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requiremente during the performance of their assigned Radiation Protection duties, provided they are otherwise following ;
plant Radiation Protection Procedures for entry into High Radiation Areas. ;
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- DRESDEN - UNIT 1 6-10 Amendment Nos.
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ADMINISTRATIVE CONTROLS i
) 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 radiation source or from any surface which the radiation penetrates shall require the following: 3
! 1. Doors shall be locked to prevent unauthorized entry and shall not
! prevent individuals from leaving the area. In place of locking the door, l direct or electronic surveillance that is capable of preventing l unauthorized entry may be used. The keys shall be maintained under '
i the administrative control of the Shift Manager on duty and/or health
! physics supervision.
- 2. Personnel access and exposure control requirements of activities being l performed within these areas shall be specified by an approved RWP.
I I
- 3. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation i dose rate (such as an electronic dosimeter.) Surveillance and radiation monitoring by a Radiation Protection Technician may be substituted for an alarming dosimeter. {
- 4. { DELETED} l f
- 5. For individual HIGH RADIATION AREAS accessible to personnel with t 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 i the individual areas, then such individual areas shall be barricaded, I conspicuously posted, and a flashing light shall be activated as a warning device.
DRESDEN - UNIT 1 6-11 Amendment Nos.
l
_ - . _ - _ _ _i
Process Control Program 6.13 I ADMINISTRATIVE CONTROLS i
6,13 PROCESS CONTROL PROGRAM (PCP) 6.13. A Changes to the PCP: l
- 1. Shall be documented and records of reviews performed shall be i retained. This documentation shall contain:
I
- a. Sufficient information to support the change together with the !
appropriate analyses or evaluations justifying the change (s) and,
- b. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- 2. Shall become effective af ter review and acceptance including approval by the Unit 2/3 Station Manager as delegated by the Unit 1 Decommissioning Plant Manager.
l l
DRESDEN - UNIT 1 6-12 Amendment Nos.
4
l Off Site Dose Calculation Manual 6.14 l 1
1 ADMINISTRATIVE CONTROLS SE OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.A Changes to the ODCM:
- 1. Shall be docurnented and records of reviews performed shall be retained. This documentation shall contain:
- a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and,
- b. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302,40 CFR 1 Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- 2. Shall become effective after review and acceptance, including approval I by the Unit 2/3 Station Manager as delegated by the Unit 1 Decommissioning Plant Manager.
- 3. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shallindicate the date (e.g., month / year) the change was implemented.
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l DRESDEN - UNIT 1 6-13 Amendment Nos.
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ATTACHMENT 4 1 1
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I MARKED UP CURRENT TECHNICAL SPECIFICATION PAGES 1
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l DRESDEN STAT ON t
l UNIT 1 l
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j Copy bm bool<.
Appendix A ,
to l
Amended Facility License DPR-2 l
t Technical Specifications and Bases For Dresden Nuclear Power Station Unit 1 l
Cn=dy Cet=ty, Illin' ois >
l Cc==enwealth Edison Company
)
' Docket No. 50-10 Date: Septea6er 3, 1993- .
Tt6s page np(xed by w pas' L -
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TABLE OF CONTENTS P_ASE .
1.0 a Definttlons . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.1 Safety Limits - Deleted 1.2 Safety Limits - Deleted '3
/W 2.1 LSSS - Deleted M8b OU 2.2 LSSS - Deleted h#I N 3.0 O W LIMITING CONDITION FOR REOUIRED EOUIPMENT Sections 3.1 through 3.7 - deleted i 3.8
- Radioactive Materials . . . . . . . . . . . . . . . . . . .
3/4.8-1 3
i Oggrdd C6LGTtC l 3.8 C. Deleted i
3.8 D.
Radioactive Waste Storage . . . . . . . . . . . . . . . . 3/4.8-3 w e- en Q$LtT60 f 3.8 F. Deleted
\
j 3.8 G.
i Miscellaneous Radioactive Waste Sources . . . . . . . . . 3/4.8-4 i
Q&LdT60 3.9 Auxiliary Electric Systems - Deleted 3.10 Fuel Hand 11ng and Storage . . . . . . . . . . . . . . . . 3/4.10-1 3.10.A. and 3.10.B - Deleted 3,10 C.
Fuel Storage Pool Water Level . . . . . . . . . . . . 3/4.10-1 3.10 D. Deleted 3.10 E.
Nuclear Fuel. . . . . . . . . . . . . . . . . . . . . 3/4.10-1 3.11 High Energy Piping Integrity - Deleted 3.12 Fire Protection Systems . . . . . . . . . . . . . . . . . 3/4.12-1 Sections 3.12.A through 3.12.H - Deleted per Generic Letters 86-10 and 88-12 (Amendment 101) ii 0353T:16
SURtMfLLANCE REOUTREMENT TABLE OF CONTENTS (Cont'd) P.b.GI Sections 4.1 through 4.7 - Deleted 4.8 Radioactive Haterials . . . . . . . . . . . . . . . . . . . 3/4.8-1 h - '. 14 rtrdi n, r.rriurn u. - . . . . .=. , . . e . . . . ;/ .;_;
9FLETf0
% -- S . L ; q u i-d E h- T . . . ....h- '" " '
DaFl.e7ED 4.8 C. Deleted .
4.8 D. Radioactive Waste Storage. . . . . . . . . . . . . . . . 3/4.8-3 A W adiva M fli; ens nuo;is,iny Ave M . . . . r__ 3,r e_+ MENN 4.8 F. Deleted I 4.8 G.
. Miscellaneous Radioactive Materials Sources . . . . . . 3/4.8-4 AH! M "-a h ............... m ....Ji.i.;_3_Oo M 4.9 Auxiliary Electrical Systems - Del'eted 4.10 Fuel Handling and Storage . . . . . . . . . . . . . . . . . 3/4.10-1 4.10 A. through 4.10.B. Deleted 4.10 C. Fuel Storage Pool Water Level . . . . . . . . . . . . . 3/4.10-1 4.10 D. Deleted 4.10 E.
Nuclear Fuel . . . . . . . . . . . . . . . . . . . . . .
3/4.10-1 4.11 High Energy Piping Integrity - Deleted 4.12 Fire Protection Systems - Deleted
-- n p- m-5.0 Design Features. . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.1
/
i Site . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 Sections 5.2 - 5.4 Deleted i 5.5 Fuel Storage . . . . . . . . . . . . . . . . . . . . . . . . . 5-1 5.6 Selsmic Design - Deleted ~~
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Reotsed en me f^98 V gg 9, ill auJ iu pr rsd pay oro*r titi fjer Tfu/ />*1# *'y 0353T:
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DRESDENI DPR.2 Amendment No. 38 ADMINISTRATIVE CONTROLS TABLE OF CONTENTS (Cont'd) EAgg
._. p- -
6.0 Administrative Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 6.1 O rg a niza tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-1 6.2 Plant Operating Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 11 6.3 Action To Be Taken in the Event of a Reportable Event in Plant Operation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 1
6.5 Plant Operating Record
..................... ................. 6-13 6.6 Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-14
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p ,ptetenf <.dth vttw /A44 per T.ru p #as e** l I
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LIST OF TABLES Page I
Table 6.6.1 4 m Shift Manning Chart . . . . . . .... . . . 6-4 l
l Table 6.6.1 Special Report . . . .......... . . . . . . 6-22 I
LIST OF I
None
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. .O se e o e = ee a . se e e e ens , eee as em m *e e++ee+ e e e, ee ea e e. . g e e a
.- 1.0 Definitionn -
f'GViIt i - Tb3 cucco ding fraqusntly ussd terms cre explicitly defined so that a tg 75(48 uniform interpretation of the specifications may be achieved.
i
'~
- a. I--coin te - ImmediaWmeans cuat~ the required action will be a
i
[
- initiated as soon as practicable considering the safe operation of the unit and the importance of the required action.
- 3. Instrument calibratien - An instrument calibration means the a ustment of an instrument signal output so that it correspo s, wit acceptable range, and accuracy, to a known value(s) the i param ter which the instrurnent monitors. Calibration sha ,
encompa the entire instrument including actuation, ala , or trip.
C.
J Instrument unctionni Test - An instrument functional est means the I l injection of a simulated signal into the instrument rimary sensor to verify the er instrument response, alarm, d/or initiating action. The prima sensors of radiation monitor are excepted from this definition. F'r these monitors the functio 1 test will consist of injecting a simulated electrical si 1 into the measuremeht channel.
. D. Inst ument check - An in trument check is
\ litative detemination k of acceptable operability y observation o instrument behavior during operation. This de rmination sha 1 include, where possible, t comparison of the instrumen with other odependedt ins truments /
- I measuring the same variable.
l
$ E. k
( Orerable - A system, subsystem, t in componen t , or device shall be
,g operable when it is capable of perdra,ing its specified 1
j function (s).
i that all necessary attendant inspr(umenImplicit tion, controls,in normal this deand IA tion shall be the l emergency electrical power so tes, cool' g or seal water, lubrication or other auxilia equipment hat are required for the system, subsystem, train, e ponent or de ce to perform its function (s) are also capab e of performing eir reisted support function (s).
l y.
l Deeratine - Operating eans that" a system, subsy tem, train, (j component or device a performing its intended f etions in its required manner.
i !
G. Su-vellinnae Tn e-val - Each surveillpnce requirement hall be i performed wit the specified surveillance interval vi :
- a. A allowable extension not to exceed 257. of th 4
eillance interval.
e.
V i
1
- b. A total maximum combined interval time for any 3 consecutiv tervals not to exceed 3.15 times the specified surveillance
[ "
interval.
. - . h t$(MNO 1.0-1 WF+4144 4
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'4 m es e es ge- e g , , , , , p
--~-
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. H. Offnite Dose caletilation Mantini (ODcM ) - Contain0 th2 cath dolrgy
/f # and prramstare ussd in th] c31culttiona ef cf fsita dos 2s dua t:
radiecetiva g2cccus and liquid offlu:nts, and in ths cc.lcul tiin ef g canus and liquid effluent nonitor alarm / trip setpoints.
I I. Process Control Procram (PCP) - Contains the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.
Q f l, h ((f)) Oth TSMP cke$nshong G
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1.1 Sefoty Limits-Fusi Cicdding Integrity 2.1 Limiting Sr.fety System Ssttin Fuil Cledding Integrity Del sd
'li Delotsd ,
l Daletsd 1.2 Safety Limits-Rea tor Coolant System 2.2 Limiting ety System Settings -
Reactor oolant System Leleted Deleted 4
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- =- . _ - - .- . .. . . - - .. . ~ _ . - . .
6!
3.0 LIMITING CONDITION FOR REQUIPID 4.0 SURVEILIANCE REQUIREM 4 .
EQUIPMENT 1
1 Reactor Protection System 4.1 Reactor Protect n System '
( Deleted Delet
- 3.2 Prote tive Ins'trumentation 4.2 Protect e Instrumentation
) De ted -
Deleted 3.3 Reactivity C rol 4.3 eactivity Control 1 Deleted De).eted '
3.4 Standby Liquid Control stem 4.4 Standby Liquid control System 3 Deleted Deleted I
3.5 Core and Containment Cooling S s ens 4.5 Core and Containment cooling Systems I
Deleted Deleted' 3.6 Primary System Bound 4.6 rimary System Boundary Deleted lated 3.7 Containment Sys a 4.7 Contai t Systems Deleted Deleted Page del " A
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'3,3 Itim4 tine condition For Recuired Eeuimnt 4.8 Survel11ance Recuirement '
3.8 Ra '
etive Materials 4.8 Radioactive Materials Aeolic fifty:
Aeolicability:
Applies to radioactive effluents Applies to the periodic monito ng and from the plant recording of radioactive efflu ts.
Ob4ective: Ob4ective:
To assure that radioac ive effluents are To ascertain that radioac* ve releases kept as low as practica le, and, in any are kept as low as prac cab'le and are event, are not released o the within allowable values.
environment in an uncontro manner and to assure that any material released Soeeffication:
is within the limits of 10 CFR .
Srecification:
A. Airborne Efflu ts
- 1. The main chimney monitoring A. Airborne Effluents I system hall have a daily
- 1. Radioactive gases released instr ent check, monthly sour check, quarterly from the Dresden hit 1 fun tien test and once per 18 chimney shall be continuously th calibration.
monitored. To accomplish this, the chimney monitoring 2. in Chimney activity analysis system shall be operable at shall be perferned at the all times except as noted in specified frequencies.
Specification 3.8.E.
- 2. a. Main chimney noble 1/menth Airborne effluents from Unit 1 gas (tritium end shall be added to those from principal gama Unita 2 and 3 and be included emitters).
in the site dose rate as calculated from prescribed b. hin chimney parti- 1/menth*
samples and following methods ate (principal prescribed in the approved Dresder. ODQt.
g emitters).
- c. Maine \imney 1/ month
- iodine. '
- d. Main ch parti- 1/qtr.
culate comp ite (Sr-89, St-9 gross alpha).
Note
- Analysis frequene hall be increased to 1/ week release rates exceed of any applicable limit gemud .fo 00cH referenced in Section
)
fage del.G rGD 3.8.A.2.
>L144 3/4.8-1
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Dreadsn I DPR-2 AmIndstut No. 37
{
J.8 Limitine Condition For Remiired _ 4.8 Eaulemen t (Cont'd) Surveillance Recuirement (Cont'd) l 3 A l
. Liquid Effluents
. quid Effluents
(
1.
- 1. a. The service water radia on '
Radioactive effluents shall '
not be released from Unit i monitor shall have an nat- l storage tanks.directly to the rument check perform d daily, a functiona check fl environment (release can be f de through D2/3 Radwaste performed quarte y, and a
.. source check {
4
} Sys ). Radioactive / I efflu a may be released from calibration pe formed once every 18 mont f I Units 2 d 3 by way of the ,
' ' Unit i d scharge canal only b. The opera i
when disc rges are controlled ity of the on a radionue discha canal sampler basis in shal I
{'
accordance with A endiz 3, e verified prior to f Table II, Column 2 of 10 CFR per rming and once a day
}
' 20 and all applicab e limits dur ng planned discharge.
listed in DPR-19 an PR-25. c.
Additionally, the disc "ge ation records of batch canal sampler shall be releases ~from Units 2 and 3 operable at any time a ra o- shall be maintained in
- j active discharge is occurr accordance with the
j isimediately suspendeds
/ 2. a. Activity analysis of conti-
- 2. The service water discharge nuous service water discharge shall be M
U 4
shall be continuously monitored and the performed monthly for i pCCM I-131, principal samma concentration (above background) in the cond ser h t, g y emitters dissolved and en-cooling water disc canal trained gases, B-3, and shall not ascoed limits g as alpha activity.
- stated below un1 the Add ional analysis for discharge is
=
3r-89 r-90 and Fe-55 trolled on a shall be rformed
' radionuclid basis in ;
accord with Appendix S quarterly.
- i
- Tab I, Column 2 of 10 CFR b. In the event o failure of 2 and Note 1 thereto
the service va r monitor, Ma=iras Concentration effluents may e inue to be released via this l 1 x 10-7 pCi/ml pathway if a service va er grab sample. is taken on C. Deleted -
every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and analyz
.4 3/4.8-2 m e =-e . = , *
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'3.8 f.fmitine Condition For Recuired Ecultwent 4.8 Sui 9re111ance Recuirement (Cont'd)
(Cont'd)
Radioactive Waste Storage D. Radioactive Waste Storage The maximum amount of radioactivity A sample from each of the in liquid storage in all Dresden above-grade liquid waste tanks .
3
! I Stations above grade tanks shall shall be taken, analyzed, and not exceed 90 curies. If these recorded every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. If no conditions cannot be met the stored additions to a tank have been made liquid shall be recycled within 24 since the last sample, the tank l bours to below grade tanks. All need not be sampled until the next J tanks located within the seismic addition.
j i
portion of the Chemical Cleaning Building are not considered above 8tMfb#d 3 *gj 7p9 grade storage. -
_ m _ #
Radioactive Efflu~nt e Monitoring E. Radioactive Effluent Monitoring
, ilability Availability
- 1. The tire maig chimney 1. a. The main chimney oble gas monito Ng system, including monitor may b ut-of-the part Ntefiltersand service fe calibratien and charcoal cartri es, may be mainten a e provided that a out of service fo ibration . noble s grab sample is or maintenance provide hat t . daily and analy:ed.
the requirements listed in 4.8.E. are satisfied.
- b. The main chimney particulate.and iodine k ikdMY6O N out-o se. ce f mainten e n nvided that particulate and . dine \'
sampler shall be co ected using alternate filter holders and pumps connected to the main chi =ney sa:ple stream.
F. Deleted T. Deleted ,
, 3/4.8-3
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3.8 timitine Condition For Recuired_ 4.8 Surveillance Recuirement (Cont'd)
Eeuloment (Cent'd) -
x l
. Miscellaneous Radioactive Materials C. Miscellaneous Radioactive Materials Sources Sources I
q source 1.eakare Test Each sealed source shall be tested for leakage and/or contamination by j Soeelfication the licensee or by other persons specifically authorized by the t Each sealed source containing Comission or an Agreement State.
radioactiv'e material in excess of The test method shall have a 100 microcuries of beta and/or detection sensitivity of at least gansna emi.tting material or 5 0.005 microcuries per test sample.
k microcuries of alpha emitting material shall be free of 2 0.005 Each category of sealed sources f microcuries of removable shall be tested at the frequency j contamination. described below. f
\
Each sealed source with removable 1. Sources in use (excludine 1
i
} contamination in exdess of the startue sources creviousiv i I
above limit shall be i= mediately subieeted to cere f1 x) - At withdrawn from use and either least once per six months for decontaminated and repaired or all sealed sources containing disposed of in accordance with radioactive material:
Consnission regulations. ,
- a. With a half-life greater j A complete inventory of radioactive than 30 days (excludin.
1 materials in the licensee's -
Hydrogen 3), and possession shall be maintained f current at all times. b. In any form other than gas.
- 2. Stored neureen not in use -
Each sealed source shall be ggggd Ya 75C4h
- tested prior to use or transfer to ar.cther licensee unless gggd soM,643 4 tested within the previous six
/
months. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed into use.
A Special Report shall be prepared and submitted to the Commission I
pursuant to Specification 6.6.C.3 1
if source leakage testa reveal.the
. presence of 2 0.005 microcuries of
- removable cantaminetion.
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3,8 , timitine Condition For Reeuired 4.8 Surveillance Recuirement (Cont'd)
Eeulement (Cont'd)
&- -w General H. General It is etert that releases of 1. Operating procedure 11 be t radioactive erial in effluents developed and usef, and I l will be kept at sm etions of equipment whic as-been
( the limits specified in S ion -
L 20.106 of 10 CDt Part 20. Th installed t aintain control over radi active materials in licensee will exert his best gaseous and liquid effluents i
efforts to keep levels of produ d during normal activity
{ radioactive material in effluents a be maintained and used, as low as is reasonably achievable. o keep levels of radioactive material in effluents released o unrestricted areas as low as '
f p p r5 0 9 00cM i= re adir achievable. The I
i environme.. al monitoring l
program'giv in the ODCM shall i . be conducted.
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BASES
, Airbome Effluents - The basis for airborne effluents from the si are contained in the Off-Site Dose Calculation Manual.
- 3. Lieuf i fluents - Liquid effluent release rate vi terms of tlDNHancentration in the discharge c be controlled in unidentified mixtur ,such concentratio In the case of
- assumption that the ent t is based on
' isotope in accordance with 10 CFR t
made up of the most restrictive if a person obtained all of h daily water Such a limit assures that even int e from such a source, the resultant
- 20. Since no sue e would not exceed that is madecifiedan in 10 CFR consider se of the discharge canal ,
dose atural dilution occurs prior to any location wh re such l I
ould occur, this assures that off-site doses from this s be far less than the limits specified in 10 CFR 20. )
t C. Deleted D.
Radiometive Lieufd Waste Sterare - The maximum gross radioactivity in liquid storage in the specified tanks has been limited on the basis of an accidental spill from all stated tanks due to a seismic event great enough to damage them.
j The Chemical Cleaning Building is seismically designed and designed to contain a simultaneous spill from all the contaminated liquid sto3 age tanks hous' e d within.
Assuming a low river flow *of 3100 f t /sec, a day period over which the radioactive liquid wastes are diluted in the river, and j
t rate (3000 al/dsy), the single intake by an individual would n
/ exceed one-third the yearly intake unidentified radioisotopes (1 x 10 gliowable by 10 CFR 20 for L pCi/ml). The factor of 3 was applied to 10 CFR 20 limits as reccmmended for situations in which population groups could be exposed.
j The sampling frequency has been established so that if the maximum amount of gross radioactivity is exceeded, action can be taken to reduce the radioactivity to a level below the specified limit.
E.
Rad 4eactive Effluent Monitorine A *
- F. Deleted .
G.
Miscellaneous Radiemetive Materinta Sources The objective of this specification is to assure that leakage from byproduct, source and special nuclear material sources does not exceed s.llowable limits.
The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is !
hased on 10 CFR 70.39(c) limits for plutonium. j d
B.
Invironmental Radfolorfemi Monitorine'Prorram - The bases for the environmental monitoring program are contained in the ODCM. 3gggy WF+4144 s.3/4.8-6 .
. ...... - ..... _ _ ....,,,,,. ? . ~ . ,.
3.9 ti , ins-cendition For R.eut red rouf ment 4.9 surve111ance Recuirem *
.9 Atrellimrv E triani Systemn 4.9 Aircilia Systems
- Deleted eleted
)
' i
, C8 C t
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- '+4144 .
I /
. ~. - - --. .. .. . .. ........ . _.. ._. .. . _.
N nas .
ted i
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<s j B.3/4.9-2 WF+4144 E /
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3.10 Limit 4ne condiQion For Recuired Eaudement 40 10 Surveillance Recuirement
~
Fuel Handline and Storare Fuel Handline an'd Storare Aeplicability Anelleability Applies to fuel handling and fuel Applies to the recording of the fuel storage. pool water level and water quality parameters.
Obiective Obieetive To prohibit fuel from being loaded into To verify the fuel pool wate'r level is the reactor core and ensure adequate maintained as spcrified in 3.10.C and fuel pool water level and quality. water quality parame u.s as specified in 3.10.T.
Soeelficatien Soecificatien A. and B. , Deleted A. and B. - Deleted L.
C. Tuel Storage Pool Water Level C. Fuel Storage Pool Water Level Whenever irradiated fuel is stored Whenever irradiated fuel is stored in the fuel storage pool, the pool in the fuel storage pool, the pool water level shall be maintained at water level shall be recorded daily.
a level of at least 18 feet. , .
g D. DELETED _ __ _
N W M *fMf E. Nuclear Tuel shall m;ti be loaded ^%_ D . DE L.ET M OVed f , geggo,, 5 into the reactor core. EM#I'04# #TUH8f6f fd be Const h t 60 44 T $lA P l
T. Tuel Storage .'ool Water Quality T. Tuel Storage Pool Water l
Once initial fuel pool cleanup is 1. Sample and analyze monthly. ;
completed: 1 j
- 1. C1 4 0.5 ppm j
- 2. Conductivity J. 10.0 paho/cm GM d 8Hb f 0[ [ A.f 925'C
- 3. pH 5.3 to 8.6 (COLS SOO TS(AA & MAh
- If any cf the above limits are
/1llsonsecr % rand o
exceeded, prepare and submit to the $(4 / 0L4 l/A H uf A+f Alet das j(pal l l
coassission within 30 days, a Specisi Report which identifies the cause(s),for exceeding the limit (s) and defines the corrective actions - - - -
to be taken to ensure that future water quality is in compliance with specification 3.10.T. This is in lieu of a Licensee Event Report.
. 3/4.10-1 WP+4144 . !
Amendment No. 37
^
< RAREE %
f M Id TS&4N M p k t.e d 6 ' '
- C. Fuel Storare Pool Water f.evel -
To assure that there is adequate water to shield and cool the irradiated fuel assemblies stored in the pool, a minimum pool water level is established. The minimum water level of 18 feet is j established because it would be a significant change from the normal j level, well above a level to assure adequate cooling (just above i active fuel) and above the level at which the GSEP action is I initiat_ed l5' uncontrolled _ loss of_ level with level decreasing)
F~ . .... e,c.r. e n u m -t m , osuu n w j
' IM8'M E N M *s(so8ishv6 wsM TT4s# [Wmd To assure that a critical assembly of nuclear fuel is no longer l possible in the reactor core, the placement of nuclear fuel into the reactor core is specifically prohibited. ^
g . Fuel Storare Pool Water Duality 1
l In December 1983, the Unit 1 Fuel Pool Water cooling and Clean-up System j 3l was taken out of service because of operational problems. This did not '
- adversely affect the fuel shielding or cooling since the Pool Water level j was maintained and the latest discharged fuel had been in the pool for ;
- greater than five years. However, four years of stagnation led to the !
growth of micro-organisms and the concern for microbial influenced
! corrosion (MIC) of pool structures. A Pool Water Treatment Program was initiated in December of 1987 which includes hydrogen peroxide addition. !
i vacuuming, and filtration. This clean-up ef fort will continue until the I I desired cleanliness level has been reached and a Domineralization System I j can be put in-service to maintain water quality.
l hSecD Mdo 76 M h u4 d M [ d M 84 d. N4. O i
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- l l,
I y,g B.3/4.10-2 i
e e
.=su =cus nu. .e , .
x 3.11 t 4w ein e conditionn for oeeration - 4.11 Survef11mnee Recuf rements Efrh M inine Interrity
- Hirh Enerry Pfefne In er. tv Deleted Del t rkes pay de dea
- i. .
- 41 4 -
i t
1 I
,wsu -. . ... . ..
l .
5.0 Dealen Features l 5.1 Sit.t Dresden Unit 1 is located at the Dresden Nuclear Power Station which consists of a tract of land of approximately 953 acres located in the Northwest quarter of the Morris 15-minute quadrangle (as designated by
! the U.S. Geological Survey), Goose 14ke Township, Grundy County, '
Illinois. The tract is situated in portions of Sections 25, 26, 27, 34, 35, and 36 of Township 34 North, Range 8 East of the Third Principal Meridian.
5 7 - 5.4 - DELETED '
5.5 ruel storane J Keff of the spent fuel storage pool shall be less than or equal to
'b 3EISMIC DEslGM - del.E r.a.O f eforweitad page de Tsu(2 s Me.
l 5 ,l, 13 ( cSe' ) -
/ Ec[ed :
G,I,C Rcuboachve 6 a m"s E 4*fi d l, g ; , n gaboachse Lip etkuk 5,2 ( M c Nc0 l 5,4 (deJefeJ) !
gm s/4.,10 a nd 6 5/4sID 1 J.wfor uahm a gc ,i k h is roacre as 5.3
( g D 0 i
w c14 T5 TAP (fs 5 gc.h on G$ leN M$COMII')
5-1 WP+4144 i
l
. I DRESDENI DPR-2 Amendment No. 38 I
J 6.0 ADMINISTRATIVE CONTROLS i 6.1 Oro ization g { t A. Onsite and offsite organizations shall be established for the unit operation and corporate
, management, respectively. The onsite and offsite organizations shallinclude the positions j for activities affecting the safety of the nuclear power plant.
- 1. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through the intermediate levels to and including all operating organization positions. These relationships shall be documented and 1 updated, as appropriate, in the form of organization charts, functional descriptions of .
l f department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation. The requirements shall be
- documented in the Quality Assurance Manual.
- 2. The Station Manager shall be responsible for overall unit safe operation and shall have i control over those onsite activities necessary for safe operation and maintenance of 1 j plant.
k 3. The Chief Nuclear Officer (CNO) shall have the corporate responsibility for overall plant l -
4 nuclear safety 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 nuclear safety.
- 4. The individuals who train the operating staff and those who carry out health physics l and quality assurance functions may report to the appropriate onsite manager; I however, they shall have sufficient organizational freedom to ensure their independence from operational pressures.
B. D I C. The shift manning for the station shall be as shown in Table 6.1.1. The Operations )
Manager or Shift Operations Supervisor, Shift Managers, Unit Supervisors, and Field i i Supervisors shall have a Senior Operating License. The Fuel Handling Supervisors shall have a limited Senior Operating License. The Site Vice President on the corporate level has responsibility for the Fire Protection Program. An Operations Manager at the station )
will be responsible for implementation of the Fire Protection Program. I
()e[e.{ed - replaced by ciescor> hon in 6.2. 5 UM7 staff.
\
Fore pro &ecktos covend by 6. l. B t
AcGei sees .cecw 6.1 esvo'>s'a'wv 6-1
- bb DRESDENI DPR-2 6.0 ADMINISTRATIVE CONTROLS (Cont'd.y_
f t.pft./#/C/yky/Mf" NIT C134ff ~
f[50VCf D. Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8,1971, with the exception of the Radiation Protection Manager who shall meet or exceed the qualifications of Radiation Protection Manager of l Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. The individual filling the position of Site Engineering Manager shall meet the minimum l
acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971.
. Retraining and repCment t nnei ance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8,1971.
( A training program for the fire brigade shall be maintained under the direction of an Operations Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for fire brigade training sessions which shall be held at least quarterly.
F. Retraining shall be conducted at intervals not exceeding two years.
G. Deleted. Q () g g G C lA) $ ~of "TtMINM l
l
- l '
6-2
. . . . . . _ - - - . ~ . _ . . ~ . . ~ . . - , - - ~ ~ - - - . _ - . - - . -- - - . . . . . . - , .~ -
DRESDENI DPR-2 Amendment No. 38 TABLE 6.1.1 MINfMUM SHIFT M ANNING CHART (1)
UNITS CONDITION oF NUMBER oF MEN IN EACH Po loN WITH No N- o l FUEL FIRST UNfT SEcoND UNIT THIRD UNTT SRoo' g {T,A, gg g l
\ 3 Cold 56 down Cold Shutdown Cold Shutdown 1 1 o 5 1 oNE Above !
Cold Shutdown Cold Shutdown Cold Shutdown 2 2 5 1 i
Cold Shutdown Co hutdown Co4 Shutdown 1- 2 o 5 1 ,
Two Above
- Cold Shutdown Cold Shutdown Cold Shutdown 2 3 1 5 1 L
Above Above Cold Shutdown Cold Shutdown Id Shutdown 2 3 1 5 1 i SRO Senior Reactor Operator. At least ne SRO st remain in the Control Room at all times when one or more Units is above cold shutdo n. T person may, however leave the Control Room for periods not to exceed 10 minutes, pr ed another SRO acts as relief operator. l l .
RO Reactor Operator (For each react cent fuel, one RO will be in the Control Room at all times.)
STA Shift Technical Advisor, ;
fdON-LIC Equipment Operator nd Equipment Attendants.
I RAD MEN Radiation Protecti Men.
)
1 NOTES: (1) Shift crew co osition may be less than the minimum requirements for a period of time not to exceed 2 rs in order to accommodate unexpected absence of o uty shift crew members provid immediate action is taken to restore the shift crew composit n to within the minimum requi ments, ;
j (2) Do not include the licensed Senior Reactor Operator or Senior Reactor or limited to fuel l ha diing, supervising alteration of the reactor core.
(3) all not operate units on which they are not licensed. l ADDITIO L REQUIREMENTS A. SRO can be RO at controls.
B. SRO in Control Room cannot provide relief to SRO/RO at controls.
C. SRO in Control Room must be in sight of or audible ranDe of operator at all times or be in audible range of Delefel- coaambu 6. 2.6 uur srev i
la n a udive .
s -
i I
4 6-4 .
, - . . . . ~ .- . - . . - . . - ,. -... - . - .. ..- .- - . _
. . . . . . - . - . - . . . - _ . . _ . . . . . . ~ . ~ .
- I I' l
I DRESDENI DPR-2 Amendment No. 38 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
I
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DRESDEN1 DPR 2 l Amendment No. 38 j
. r 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
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l' 6-3 t
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I I-DRESDENI DPR-2 Amendment No. 38 6.0 ADMINfSTRATfVE CONTROLS (Cont'd.)
6.2 Plant Ooeratino Procedures A. Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to: .
j 1. Systems and components involving nuclear safety of the facility.
- 2. Deleted.
, 3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or
- components including responses to alarms.
4 Emergency conditions involving potential or actual release of radioactivity " Generating Stations Emergency Plan
- and station emergency and abnormal procedures.
- 5. Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventive and corrective maintenance operations which could have an effect on the safety of the l facility.
- 7. Surveillance and testing requirements.
N 1
Replaced in proposed <sociton l sechon 6 8. A wder PRO'N"" \
AND Pto G RAMS '
6-13
h I' DRESDENI DPR-2 Amendment No. 38 p __
6.0 ADMfNISTRATfVE CONTROLS (Cont'd.)
- 8. Tests and experiments.
[G d.Ced by fM OI'*
- 9. Deleted b , h, d
$tf ed744 i
- 10. Station Security Plan and implementing procedures.
I
- 11. Fire Protection Program implementation.
4 12. ODCM implementation.
13, PCP implementation.
- 14. Working hours of the Shift Manager, Unit Supervisor, Field Supervisor, and Nuclear Station Operator l job classifications such that the heavy use of overtime _is not routinely requirnd.
l B. Radiation control procedures sha!! be maintained, made available to a!! station personnel and adhered to. l These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20. This radiation protection program shall be organized to meet t.ie requirements of 10 CFR 20. pp[M
~_ _ , . -
ppgM g +
gj/ __
- C. 1. Procedures for items identified in Specification 6.2.A and any changes to such procedures shat! be reviewed and approved by an Operations Manager and the Technical Superintendent in the areas of operation, fuel handling, or instrument maintenance, and by the Maintenance Superintendent and-Technical Superintendent in the areas of plant maintenance and plant inspection. Procedures for items identified in Specification 6.2.B and any changes to such procedures shall be reviewed and approved by the Radiation Protection Manager. At least one person approving each of the above
\ procedures shall hold a valid senior reactor operator's license. In addition, these procedures and l
changes thereto must have authorization by the Station Manager (or designee) before being fi implemented. .
- 2. Work and instruction type procedures which implement approved maintenance or modification procedures shall be approved and authorized by the Maintenance Superintendent where the written
(
authority has been provided by an Operations Manager. The " Maintenance / Modification Procedure" I utilized for safety related work shall be so approved only if procedures referenced in the
- Maintenance / Modification Procedure" have been approved as f2 QLQb f0fD$Qb SGCh0M 0
- 0* b
- 4
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i 6-14
I!
DRESDENI DPR-2 Amendment No. 38 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
required by 6.2.A. Procedures which do not fall within the requirements of 6.2.A t'r 6.2.8 may be approved by the Department Heads.
D. Temporary changes to procedures 6.2.A and 6.2.8 above may be made provided:
- 1. The intent of the original, procedure is not altered.
TG '
- 2. The chance is approved by two members of tne plant management staff, at least one of whom holds a Senior Reactor Operator's License for Units 2 and 3.
, 3. The change is documer.ted, reviewed by the Onsite Review and investigative Function and approved by the Station Manager (or designee) within 14 days of implementation. 1 E.
Drills of the emergenDocefures described in Specification 6.2.A 4 shall be conducted at the !
' frequency specified in the Generating Station Emergency Plan. These drills will be planned so that during the course of the year communication links are tested and outside agencies are contacted.
h_ hfbeOOSON $$tCh O *1 he To beh
~6.3 Action to be Taken in the Event of a REPORTABLE EVENT in Plant Operation Any reportable event shall be promptly reported to the Site Vice President or his designated alternate. The -
( incident shall be promptly reviewed by the Onsite Review and investigative Function and a separate report for i each reportable event shall be prepared in accordance with the requirements of Specification 6.6.B.
DELETE 0 -
6.4 Deleted. ~ . .
6.5 Plant Operating Records A.
Records and/or logs relative in the following items shall be kept in a manner convenient for review and shall be retained for at least five years.
t DELE *T&$ 0.S TT I64%()f90t WY 8Y*1 l
6-15
31-DRESDENI DPR-2
~
Amendment No. 38 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
- 1. DC 2.
Records of standby operations and principal maintenance activities, including inspection and repair, regarding principalitems of equipment pertaining to nuclear safety.
- 3. Rec rds and reports of reportable and safety limit events.
4 {
Record and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirem See Section 4 of these Specifications) are being met. All equipment failing to. et surveillance requi ments and the corrective action taken shall be recorded.
- 5. Records of changes de to the equipment or reviews of tests and experiments to e ply with ~
- 6. Records of radioactive s ments. f
- 7. Records of tests pertaining ear safety.
- 8. Records of changes to operating proc ures
- 9. Shift Managers Logs . .
- 10. By-product material inventory records and source I test results.
B.
Records and/or logs relative to the following item 4ha!! bey corded in a manner convenient for review and shall be retained for the life of the plant, i
1.
Substitution or replacement of pri palitems of equipment ertaining to nuclear safety.
i.
- 2. t is described in the Safety An lysis Report.
Changes made to the plan 7t
! 3. Records of spent fuelinventory and assembly histories.
- 4. Deleted.
/ k
- 5. Updated, corrected, and as-built drawings of the plant.
- 6. Record '6f plant radiation and contamination surveys.
- 7. ords of off-site environmental monitoring surveys.
\
Deleded as TS mprooe ound 14s+1 1
I
-- ~
~- __
%m 6-16
3ll DRESDENI DPR.2 ,
Amendment No. 38 6.0 ADMINISTR ATIVE CONTROLS _ (Cont'd.)
f i-m -
- 8. ords of radiation exposure for all plant personnel, including all contractor d visitors to the I
[ plant rdance with 10 CFR 20. l l l
- 9. Records of radioactivity in i and gaseous wastes rele to the environment.
/
- 10. Deleted.
~
l
) I
- 11. Records of individual staff ers indicating qualificat t expes:ence, training and retraining.
- 12. Deleted.
- 13. Minutes f meetings and results of reviews performed by the Offsite and Onsite. Review invadigstive Functions.
. Deleted.
w-NC OS Y $$ UWC
..n. - - -
M
-~
n ,
6.6' REPORTING REQUIREMENTS . . -
'I in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following
.k' identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the i
NRC unless otherwise noted.
)
}
A. Routine Reoorts
- 1. De!ated.
k
- 2. A tabulation shall be submitted on an annual basis of the number of station, utility and other personnel (inclucing contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions (See Note); e.g., reactor operations and surveillance, inservice inspection, routina r.*aintenance, special maintenance (describe maintenance), -
waste processing, and refueling. The dose assignment to various duty functions may be estimated -
based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than j 20% of the individual total dose need not be accounted for, in the aggregate, at least 80% of the 1
total whole body dose received from external sources shall be assigned to specific major work functions.
- 3. Deleted. ft W fM * * *
- N:te: This tabulation supplements the requirements of 20..,07 of 10 CFR Part 20.
l l
l 6-17 . !
I
6.0 ADMINISTRATTVE CONTROI.S (Cont'd.)
~
B. Reeortable Events g g[Jjgfgg Reportable events'will be submitted as required by 10 CyR 50.73.
C. Unleue Renertine Recuirements
~1. R Reoort { Annus I
I hfA dCsd k A report shall be submitted to the Commission within 60 days I po poses afee, annuary 1 of each year specifying the quantity of each of the principal radionuclides released to unrest'ricted b $Ec.b OM areas in liquid and gaseous effluents during the previous 12 months. The format and content of the report shall be in be k*
- accordance with Regulatory Guide 1.21 (Revision 1) dated June ostd occN 1974. Any changes to the PCP shall be included in this report.
- 2. Environmental Radioactivity Data (Annual Re
- a. I Standard Radiological Monitoring Program -
(1) 'Non-Routine Report -
(a) If a confirmed measured radionuclide 4 concentration in an environmental sampling
' medium averaged over any; calendar quarter
,i sampling period exceeds the reporting level
, i given in Table 4.8-1 and if the radioactiv y is
\ attributable to plant operation, a writt l i
repo Nehall be submitted to the Regi al Administtstor of the NRC Regional ice, with a j -
i copy to th Director, Office of clear Reactor Regulation, thin 30 days fr the end of the j quarter. When re than on the
. . radionucildes in T .$ are detected in the medium, the reporting 1 shall have been j asceeded if, ,
a u .
I I(Cg/(RL)g) is qual to or g ster than 1 where C 1 he concentration o ith j radiopuc ide in the medium and RL is e J reporting level of radionuclide i.
(b) f radionuclides other than those in Tabl 4.8-1 are detected and are due to plant effluents, a reporting level is exceeded if toe I potential annual dose te an individual is equal to or greater than the design objective doses of 10 CFR 50 Appendiz I.
n.
Rwou4 auhtaud m occn
~ ~ - -~ J' e
M ee en
- _ _ _ __m . . . _ . . . _ _ _ _ . _ _ _. _ _ _._ _ _ _ _ _ _ __ . _ _ _ _ _ _
i -
- 6.0 AMINIKTRATIVE CONTROI.M (Cont 'd. )
j
~, gg g gg/ ag/ (c) This rapsrt shall include an oveluaticn of any i
release conditions, environmental factors, or i
[" #
other aspects necessary to explain the anomalous j w _ 8-Sci. ~
__~- -
(2) Annual Operating Report I
[ An annual report containing the data taken in the !
standard radiological monitoring program (Table 4.8-1) shall be submitted by March 31 of the next l 1
year. The content of the report shall include: I -
i (a) Results of environmental sampling sununarized on ,
a quarterly basis following the format of j
!, I s
!t Regulatory Guide 4.8 Table 1 (December 1975); t I
i:
(individual sample results will be retained at I the station); '
jl .
1 In the event that some results are not available j
1 for inclusion with the report, the report shall be submitted noting and explaining the reasons i
j for the missing results. Summaries, j intarpretations, and analysis of trends of the j
, results are to be provided.
~
}
(b) An assessment of the monitbring results and
' radiation dose via the principal pathways of
~* exposure resulting from plant emissions of radioactivity inclu'ing d the maximum noble gas gamma and beta air doses in the unrestricted area. The assessment of radiation doses shall be performed in accordance with the ODCM.
/
l f
- (c) Results of the census to determine the i
locations of animals producing milk ior human l
j j consumption, and th'e pasture season feeding
{
t, i practices at dairies in the monitoring program. i 4 (d) The reason for the omission if the nearest /
j dairy to the station is not in the monitoring
- i program. (Table 4.8-5) i
- j j
(e) An annual susesary of meteorological conditions
[
i concurrent with the releases of gaseous !
effluents in the form of joint frequency distributions of wind s, peed, wind direction, and atmospheric stability.
ppd by proposed sec{im 6.9. A.5 I
and 00cm 4-19
-- M #48 PS W4MS,Sep,9% _ m-
6.0 AM INISTRATIVE CONTROLM (Coated,) '
(f) The results of the interlaboratory comparison eg/acad [tf program described in Section 3.8.E.7.
[efo/0Id (g) The results of the 40 CF1t 190 uranium fuel cycle 5, c.a..- dose analysis for each calendar year g,q,4 y (h) A sussnary of the monitoring program, including maps showing sampling locations and tables d4H4 00cd giving distance and dir.ction of sampling locations from the station.
- 3. Special Reports g, gg,,[ b'/ /7(Dt78f8d 5ecfrog
- 8. 9. 8 Special reports shall be submitted as indicated in Table 6.6.1.
6.7 Deleted. _ N-W
' l siter D6se Calculation Manual (ODCM) ~
l A.
The CDCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and 1 liquid effluents,and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in th*ese Technical Specifications. Methodologies and calculational geplaceel 69 proposed sectron 6.14. 4 .T -
1
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e e
0 a
, 6-20 e
. .'=8 9
TABLE 6.6.1 w._,'---
SPECTAT. REPORTS SPECIFICATION O RFrERDICE SUEMITTAT DATE
- s. Radioactive Source Leak Testing (1) 3.8.T Annual Report NOTES: .
- 1. The report is required enly if the tests reveal the presence of 0.005 microcuries or more of removable contamination.
eea a % m eaas u s,a s. 9. e i- alle OfLE7ED
...g_ , _
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6-21 ete S em so m e ee +esee a mele- meeeeet me e see ease
- 4eGeeer9 m es e 4 .
4
- lt DRESDEN1 DPR-2
] Amendment No. 38 6.0 ADMINISTA ATIVE CONTROLS (C pt'd 1 :-
J-
' P AwJ bg neposed subon 6.l4. A.T procedures acceptable to the Commissionlre contained in NUREG-0133.
The ODCM shall be submitted to the Commission at the time of proposed Radiological Effluent Technical Saecifications and shall be subject to review and approval by the Commission prior to implementation.
] B. Licensee initiated changes to the ODCM may be made provided the change:
1.
' Shall be submitted to the Commission by inclusion in the Monthly Operating Report within 90 days of the date the change (s) was made effective and shall contain: [
i a. Sufficiently deta!!ed information to sJpport the change. Information submitted should consist of a package of those pages of the ODCM to be changed together with appropriate analyses or f*
j evaluations justifying the change (s); ,
- b. A determination that the change will not reduce th'e accuracy or reliability of dose calculations or setpoint determinations; and i
- c. Documentation of the fact that the change has been reviewed and found acceptable by the Onsite Review and investigative Function.
2.
Replaced by proposed swebou 6.(4.A./ o d.2 l Shall become effective upon review and acceptance by the OnSite Review and investigative Function. l ,
i 6.9 Process Control Program (PCD l
I A. The PCP shall contain the sampling, analysis, and formulation determination by which solidification of 4 radioactive wastes from liquid systems is assurnd. .
B. The PCP shall be approved by the Commission prior to implementation.
C. Licensee initiated changes may be made to the PCP provided the change: '
k
- 1. Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change was made and shall contain: '
hlgh byfVOliOW SC0 O*f *!
6-22
a I$
- DRESDENI DPR 2 Amendment No. 38 6.0 ADMINISTR ATIVE CONTROLS (Cont'd.)
I -
- a. Sufficiently detailed information to support the change;
, b. A determination that the change did not reduce the overalf conformance of the solidified wasto product to existing criteria for solid wastes: and
- c. Documentation that the change has been reviewed and found acceptable by the Onsite Review and investjgative Function.
2.
laced by propored $echem 6o/3 Shall ecome effective upon review and acceptance by the Onsite Review and investigative Function.
.10 Major Changes to Radioactive Waste Treatment Systems (Uquid, Gaseous, Solid)
(See note below)
A. censee initiated major changes to the radioactive waste systems may be made provided:
- 1. The noe is reported in the Monthly Operating Report for the period in which the evaluation was/
reviewe the Onsite Review and investigative Function.. The discussion of each change shalP contain:
- a. A summary of the eva ion that led to the determination that the c5.)ange~could be made in accordance with 10 CFR 59, f b.
/
g Sufficient detailed information ta support the reaso for the change;
- c. A detailed desenption of the equipment, ents, and process involved and the interfaces with other plant systems;
- d. An evaluation of the chan which shows the predicte eleases of radioactive materials in
) liquid and gaseous 3ffice'nts and/or quantity of solid wasthtjiffer from those previously predicted in th ifcense application and amendments;
\
- e. A com ison of the predicted releases of radioactive materials in liquid and gase us effluent and solid waste to the actual releases for the period in which the changes were de; I
j f. An estimate of the exposura to plant operating personnel as a result of the change; and
$siocaied4v 0DcM
-v ~ - - _ _ . . _ _ _ --
Note: Licensee may choose to submit this information as part of 1Ni annai 7$AD. *.:;::':tc.
6-23
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DRESDENI DPR 2 Amendment No. 38 i
, 6.0 ADMINISTRATIVE CONTROLS (Cont'd.) ---
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- g. Documentation of the fact that the change was reviewed and found accept y the nsite -
eview and Investigative Function. ,
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- 2. The change s al become effect swewa eptance by the Onsite Review and ;
investigative Functio
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ATTACHMENT 5 J
EVALUATIONS NO SIGNIFICANT HAZARDS ENVIRONMEN FAL IMPACT ASSESSM5NT IRREVERSIBLE CONSEQUENCES l
ATTACHMENT 5 EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility, in accordance with the proposed amendment would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3) Involve a significant reduction in a margin of safety.
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because:
In general the proposed amendment represents the conversion of current requirements to a more generic format, or the addition of requirements which are based on the current safety analysis (Decommissioning Plan). Implementation of these changes will not reduce reliability of equipment assumed to operate in the current safety analysis (Decommissioning Plan), or will provide continued assurance that specified parameters remain within their acceptance limits, and as such, will not significantly increase the probability or consequences of a previously evaluated accident.
Some of the proposed changes represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. The proposed amendment for Dresden Station Unit l's Technical Specifications in general is based on STS guidelines or NRC accepted changes to other facilities such as Trojan or San Onofre Unit 1. Any deviations from STS requirements do not significantly increase the probability or consequences of any previously evaluated accidents for Dresden Station Unit 1. The proposed amendment is consistent with the current safety analysis (Decommissioning Plan) and has been previously determined to represent sufficient requirements for the assurance and reliability of equipment assumed to operate in the safety analysis (Decommissioning Plan), or provide continued assurance that specified parameters remain within their acceptance limits. As such, these changes will not significantly increase the probability or consequences of a previously evaluated accident.
l ATTACHMENT 5 Create the possibility of a new or different kind of accident from any previously evaluated because:
In general, the proposed amendment represents the conversion of current requirements to a more generic format, or the addition of requirements which are based on the current safety analysis (Decommissioning Plan). Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. These changes do not involve revisions to the design of the station. Some of the changes may involve revision in the operation of the station; however, these provide additional restrictions which are in accordance with the current safety analysis (Decommissioning Plan).
The proposed amendment for Dresden Station Unit l's Technical Specifications in general is based on STS guidelines or NRC accepted changes to other facilities such as Trojan or San Onofre Unit 1.
The proposed amendment has been reviewed for acceptability at the Dresden Nuclear Power Station considering similarity of system or component design versus the STS oflater operating plants. Any deviations from STS requirements do not create the possibility of a new of different kind of accident previously evaluated for Dresden Station, Unit 1. No new modes of operation are introduced by the proposed changes. The proposed changes maintain at least the present level of operability. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
Involve a significant reduction in the margin of safety because: !
In general, the proposed amendment represents the conversion of current requirements to a more generic format, or the addition of requirements which are based on the current safety analysis (Decommissioning Plan). Others represent minor curtailments of the current requirements which are based on generic guidance or previously approved provisions for other stations. Some of the later individual items may introduce minor reductions in the margin of safety when compared to the current requirements. However, other individual changes are the adoption of new requirements which will provide significant enhancement of the reliability of human performance assumed in the safety analysis (Decommissioning Plan), or provide enhanced assurance that specified parameters remain within their acceptance limits. These enhancements compensate for the individual minor reductions, such that taken together, the proposed changes will not significantly reduce the margin of safety.
)
l The proposed amendment to Technical Specification Section 6.0 implements present requirements, or '
the intent of present requirements in accordance with the guidelines set forth in the STS. Any deviations from STS requirements do not significantly reduce the margin of safety for Dresden Station.
The proposed changes are intended to improve readability, usability, and the understanding of technical specification requirements while maintaining acceptable levels of safe operation. The proposed changes have been evaluated and found to be acceptable for use at Dresden based on system design, safety analysis requirements and operational performance. Since the proposed changes are based on NRC accepted provisions at other operating plants that are applicable at Dresden and maintain necessary levels of system or component reliability, the proposed changes do not involve a significant reduction in the margin of safety.
1 ATTACHMENT 5 ENVIRONMENTAL ASSESSMENT Commonwealth Edison has evaluated the proposed amendment against the criteria for the identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.20. It has been determined that the proposed changes meet the criteria for a categorical exclusion as provided under 10 CFR 51.22 (c)(9). This conclusion has been determined because the changes requested do not pose significant hazards consideration or do not involve a significant increase in the amounts, and no significant changes in the types, of any effluent that may be released offsite. Additionally, this request does not involve a significant increase in individual or cumulative occupational radiation exposure. Therefore, the Environmental Assessment Statement is not applicable for these changes.
I 1RREVERSIBLE CONSEQUENCES ASSESSMENT Commonwealth Edison has evaluated this proposed amendment and determined that it involves no irreversible consequences. According to 10 CFR 50.92(b), the Commission will be particularly sensitive to a license amendment request that involves irreversible consequences (such as one that permits a significant increase in the amount of efiluents or radiation emitted by a nuclear power plant). This amendment is p.-imarily administrative in nature and does not involve any change in operation of any equipment that could change the amounts of effluents or radiation emitted or any other type ofirreversible efTects.
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ATTACHMENT 6 1
2 1 l 1
4 I
- 1 i 1 i INFORMATION ONLY MATRIXES !
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DRESDEN UNIT 1 VS TROJAN TS DRESDEN UNIT 1 TS VS ODCM PLACEMENT ;
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1
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l MATRIX - CURRENT TS TO ODCM Location in the OFFSITE DOSE CALCULATION MANUAL which cover l
t current Technical Specifications (Amendment 38).
Technical Specification ODCM Chapter 3/4.8 " Applicability" 2, various sections
! & " Objective"
! 3.8.A.1 10.1.2.1 3.8.A.2 Table 12.4-1 & footnote 6 l
! 3.8.B.1 10.2.1.1 !
3.8.B.2 10.2.3.2.1 l 3.8.E.1 Table 12.2-3 action 27 & 28 3.8.H 12.3.C liquid, 12.4.C gaseous 4.8.A.1 Table 12.2-4 l 4.8.A.2 Table 12.4-1 & footnote 6 i 4.8.B.1.a Table 12.2-2 l
l 4.8.B.1.b Table 12.2-2 i 4.8.B.1.c 12.6.1.2.2 (life of plant) l l
4.8.B.2.a Table 12.3-2 4.8.B.2.b Table 12.2-1 action 10 l
4.8.E.1 Table 12.2-3 actions 27 & 28 4.8.H.1 2.1.1.2 and 2.1.1.3 l B.3/4.8.A .Section E9 page E10 l
B.3/4.8.B Section E10 page E18 B.3/4.8.H Throughout ODCM i
i 12.6.2.1 6.6.C.1
- 6. 6.C.2.a . (1) . 12.6.2.3 (Table 12.5-2 ref.)
- 6. 6.C.2.a. (2) 12.6.2.2 6.10.A 12.6.4
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, COMPARISON BETWEEN UNIT 1 AND TROJAN TS 1
Proposed Trojan Notes None 1.0. Use and Application - D1 did not use due to TSUP format 1.0. 1.1 Definitions - Trojan used " Actions" and " Certified Fuel Handler"- D1 used Unit 2/3 TSUP None 1.2 Logical Connectors - Not used at Dresden Unit 1 which uses TSUP format l None 1.3 Completion Times - TSUP format has times under ACTION None 1.4 Frequency TSUP has frequency under SURVIELLANCE 2.0. 2.0. SAFETY LIMITS - same - N/A to decommissioned plants None 3.0. LCO Applicability - Dresden Unit 1 written into individual specifications l None 3.1 Defueled Systems l 3/4.8.G N/A Sealed Sources - Not in 7 ojan TS .
l 3/4.8.J 5.7.2.6 Liquid Radwaste Storage - Included in Trojan Administrative Controls 3/4.10.A.1 3.1.1 Spent Fuel Pool Water Level-None 3.1.2 Spent Fuel Pool Boron Concentration - N/A to BWRs None 3.1.3 Spent Fuel Pool Temperature - N'A to D1 - no cooling necessary due to fuel age '
None 3.1.4 Spent Fuel Pool Load Restrictions N/A to D1 - no previous specification 5.0. 4.0. DESIGN FEATURES 6.1 TITLE RESPONSIBILITY l 6.1.A 5.1.1 same Trojan has add'l words similar to QA Manual 6.1.B N/A Sta Mngr shall provide U1 support 6.1.C 5.1.2 same - Shift Mngr resp for operational command function #
6.2 TITLE ORGANIZATION 6.2.A 5.2.1 same _ )
6.2.A.1 5.2.1.a same !
6.2.A.2 5.2.1.b same - Unit 1 Decommissioning Mngr v. Gen Mngr 1 6.2.A.3 5.2.1.c same - A Senior Vice President vs VP and CNO l 6.2.A.4 5.2.1.d same - Trojan calls out Certified Fuel Handlers vs generic statement 6.2.B TITLE UNIT STAFF None 5.2.2.3 Crew composition table 5.2.2-1, D-1 uses words in 6.2.A.1 &.2. No manning relaxation 6.2.B.1 T 5.2.2-1 same - Trojan requires Shift Manager, D-1 Control room operator _
6.2.B.2 5.2.2.b same - non licensed operator for Unit 1 6.2.B.3 5.2.2.c same - HP on site during fuel handling 6.2.B.4 5.2.2.d same - Supervision of fuel handling 6.2.B.5 5.2.2.e same - GL 82-12 spelled out in detail for Trojan, referred to for D-1 6.2.B.6 5.2.2.g Shift Mngr Certified Fuel Handler 6.2.B.7 5.2.2.f Shift Mngr report to individual who is a Certified Fuel Handler 6.2.C N/A STA position 6.3. 5.3.1 UNIT STAFF QUALIFICATIONS Refers to no need for Unit i NRC licenses 6.4. 5.4.1 TRAINING - Trojan refers to Certified Fuel Handler, Dresden generic None 5.5 Reviews and Audits - This was removed from Unit 1 in Amendment 38 None 5.6 Tech Spec Bases Control- not in Dresden TS j l
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i U1 TROJN.XLS l
COMPARISON BETWEEN UNIT 1 AND TROJAN TS 1
Proposed Trojan Notes 6.5 N/A BLANK 6.6 N/A BLANK 6.7 N/A SAFETY LIMIT VIOLATION N/A to Unit 1 6.8 5.7 PROCEDURES AND PROGRAMS 6.8.A 5.7.1.1 same l ,6.8.A.1 5.7.1.1.a same - Reg Guide 1.33 procedures 6.8.A.2 N/A Deleted from Unit 1, refers to EOPs and NUREG 0737 6.8.A.3 5.7.1.1.b same - security plan None 5.7.1.1.d Trojan has QA program for rad effluent and rad monitoring. D-1 in QA Manual 6.8.A.4 5.7.1.1.c same - GSEP 6.8.A.5 5.7.1.1.f same PCP - Trojan 5.7.2.2, D-16.13 6.8.A.6 5.7.1.1.f same - ODCM - Trojan 5.7.2.3, D-16.14 6.8.A.7 5.7.1.1.e same - fireprotection 6.8.B 5.7.1.2 Deleted from Dresden TS and placed in Decommissioning Plan - Review and Approval 6.8.C 5.7.1.3 Deleted from Dresden - Temporary Changes 6.8.D 5.7.2 The following programs shall be .
6.8.D.1 N/A Deleted from Unit 1, not applicable to a shutdown plant 6.8.D.2 N/A Deleted from Unit 1, not applicable to a shutdown plant 6.8.D.3 N/A Deleted from Unit 1, not applicable to a shutdown plant 6.8.D.4 5.7.2.4 same - Dresden more restrictive and encompassing 6.8.D.5 N/A Deleted from Unit 1, not applicable to a shutdown plant 3.8.D 5.7.2.6 Storage Tank Radioactivity Monitoring Program - in 3/4.8.J for D1 3.10.F 5.7.2.8 Spent Fuel Pool Water Chemistry Program - in 3/4.10.A.2 for D1 None 5.7.2.9 Control Building Structural Monitoring - N/A for D1 6.9 TITLE REPORTING REQUIREMENTS 6.9.A TITLE ROUTINE REPORTS - Trojan talks about 50.4 6.9.A.1 N/A Deleted 6.9.A.2 N/A same - Radiation exposure report 6.9.A.3 5.8.1.2 same - Annual rad envir report 6.5.A.4 5.8.1.3 same - Rad effluent release report 6.9.A.5 N/A Monthly operating report, deleted from Unit 1 6.9.A.6 N/A COLR, deleted from Unit 1 None 5.9 Record Retention - D1 located in Decommissioning Plan 6.9.B N/A Special Reports 6.10. N/A BLANK _ _.
6.11 5.7.2.1 RADIATION PROTECTION PROGRAM 6.12 5.10. HIGH RADIATION AREA 6.13 5.7.2.2 PROCESS CONTROL PROGRAM 6.14 5.7.2.3 ODCM l
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U1.,.TROJN.XLS