ML20054D162
| ML20054D162 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/13/1982 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20054D158 | List: |
| References | |
| 3858N, NUDOCS 8204220396 | |
| Download: ML20054D162 (13) | |
Text
O ATTACHMENT Proposed change to Facility Operating License Nos. DPR-39 and DPR-48 for Zion Station Units 1 and 2 3858N 0204220396 820413 PDR ADOCK 05000295 P
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COMPOSITE LICENSE FOR ZION Unit 1 NRC DOCKE T NO. 50-295 FACILITY OPERATING LICENSE - OPR-39 (originally issued 4/06/73) 1.
Nuclear Regulatory Commission Findings:
(Omitted) 2.
Facility Operating License No. OPR-39:
A.
This license applies to the Zion Nuclet Power Station, Unit 1, a pressurized, light water moderated and cooled reactor and associated electric generating equipment (the facility).
The facility is located on the applicant's 250 acre site on the west shore of Lake Michigan in Zion, Lake County, Illinois, approximately midway between Milwaukee, Wisconsin and Chicago, Illinois, as described in the Final Safety Analysis Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Commonwealth Edison:
(1)
Pursuant to Section 104b o f the Atomic Energy Act o f 195 4, a s amended, and 10 CFR Pa r t 50,
" Licensing o f Production and Utilization Facilities," to possess, use, and operate the f acility as a u tilization f acility at the designated location; (2)
Pursuant to the Act and 10 CFR Part 70, "Special Nuclea r Material," to receive, possess, and use a t any time in connection with the operation o f the facility, that amount of uranium enriched in the isotope U-235 in accordance with the limitations for storage and amounts required for reactor operation as described in the Zion Station Final Safety Analysis Report as supplemented and amended, or as described in any amendment to this license; (revised 8-09-76; Am. 2 3 )
(3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentalon, and radiation monitoring equipment calibration, and as fission detectors in amounts as required;
DPR-39 (4)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear material as may be produced by the operation o f the f acility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 o f 10 CFR Part 30, Section 40.41 o f 10 CFR Pa rt 40, Sections 50.54 and 50.59 o f 10 CFR Part 50 and bection 70.32 o f 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations and orders o f the Commission now or hereaf ter in effect; and is subject to the additional conditions specified below.
(1)
Maximum Power Level Commonwealth Edison Company is authorized to operate the Zion Nuclear Power Station Unit No. 1 at steady state reactor core power levels not to exceed 3250 megawatts thermal. (revised 6-25-76 ; Am. 21)
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications. (revised 2-09-82; Am. 73)
(3)
This license is subject to the following conditions for the protection of the environment:
(a)
Radiological and non-radiological Technical Specifications have been established by the Regulatory staff.
These Technical Specifications cover, but are not limited to, the following:
9 DPR-39 (1)
An extended operational monitoring program to determine the environmental impacts of Station operation.
The program should determine the size, shape, and location o f l
the thermal plume during different wind and weather conditions.
The program should
-define the effects o f f acility operation on the aquatic ecosystem, including data on impingement o f aquatic organisms on the bar racks and traveling screens.-
l t
(2)
A basis for starting the deicing operation (pumping heated discharge water to the intake structure) only after there are positive indications that icing of the of fshore intake structure is in f act taking place.
(b)
Commonwealth Edison shall develop design modifications to the condenser cooling water intake structure to reduce the e ffective water intake velocity to less than 1 foot per second l
(under winter deicing operations the present velocity is calculated to be over 3.7 fps; during non-winter operation it is calculated to be over 2.4 fps); or to otherwise minimize fish entrainment.
Commonwealth Edison will be prepared to install the modifications within a specified time period if excessive numbers of juvenile or-adult fish mortalities result from operation of-the condenser cooling water system. (revised l
8-09-73 ; Am. 1) j f
(c)
If important adverse effects or evidence of
_ irreversible damage are detected by the monitoring programs, Commonwealth Edison will provide to the i
Commission an analysis of the problem and a plan
.i of action to be taken to eliminate or acceptably l
reduce the detrimental effects or damage.
(d)
Commonwealth Edison shall perform fish population studies in the offshore control areas to provide base line population statistics for all seasons of the year.
Commonwealth Edison shall monitor the quantity and quality of fish population in these areas and shall assure that these control areas are outside the influence of the thermal plume.
. Commonwealth Edison shall submit this fish population. study program to the Commission for review by January 15, 1974. (added 10-19-73 ; Am. 3)
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(4).
The licensee shall not operate the reactor at power 4
Jleve-14 above P-7 (as defined in Section 7.2 o f the Zion Figa'l Safety Analysis Report) with less than four (4) s reactor coolant loops in operation until sefety analyshs for less than four loop operation have been submitted and approval for less than four loop s
operation at power levels above P-7 has been granted by the Commission by amendment to this license. (added 5-12-76; Am. 20)
(5).The li=censee may proceed with and is required to i
. complete the modifications indicated in Paragraphs 3;1.'1 farough 3.1.20 o f the NRC's Fire Protection t
Evaluation (SE) on the Zion Nuclear Power Station dated March ~10, 1978 cnd supplements thereto.
These modifications shall be completed as specified in Table 3rl of Supplement No.1 or in subsequent supplements to s
tha t S E.
In addition, the licensee shall submit the additional information identified in Table 3.2 o f the l
above cited SE in accordance with the schedule l contained therein.
In the event these dates for t
(submittal'cannot be. met, the licensee shall submit a
' report explaining the circumstances, together with a reviued schedule. (added 4-13-79; Am. 4 8 )
- c (6)' Pursuant to the requirements of 10 CFR 50.34(c),10 CFR 50.54(p) and 10 CFR 73.55, as applicable, the licensee
)
shall fully implement and maintain in e ffect all provisions and changes to the following plans: (revised 1-15-81; Am. 61)
(a)
Zion Station Unit Nos.1 and 2 Physical Security Plan, approved March 14, 1979; (b)
Zion Nuclear Power Station Safeguards Contingency Plan, approved November 17, 1980 and to be fully implemented within-30 days; i
(c)
Zion Nuclear Power Station Guard Training and Qualification Plan approved January 15,1981 and to be fully implemented within 60 days.
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i DPR-39 5-(7)
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated April 13, 1978, as supplemented October 24, November 8 and 29, 1978, January 24 and 26, February 23, March 7 and March 19, 1979. (revised 1-15-81; Am. 61)
(a)
Fuel stored in the spent fuel pool shall have a U-235 loading less than or equal to 40.6 grams per axial centimeter. (added 2-28-80; Am. 52)
+
-l (b)
No loads heavier than the weight of a single spent f
fuel assembly plus the tool for moving that assembly shall be carried over fuel stored in the spent fuel pool.
The spent fuel handling tool, the burnable poison tool, the rod cluster control changing fixture and the thimble plug shall not be carried at heights greater than two feet over fuel stored in the spent fuel pool. (added 2-28-80; Am.
52)
(8)
The licensee shall implement a secondary water l
chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include: (added 4-28-8 0 ; Am. 5 4)
(a)
Identification o f a sampling schedule for the critical parameters and control points for these parameters; (b)
Identificatiod o f the procedures used to quantify parameters that are critical to control points; (c)= Identification of process sampling points; (d)
Procedure for the recording and management of data; 1
(e)
Procedures -defining corrective actions for off control point chemistry conditions; and (f)
A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.
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1 DPR-39 i (9)
The Licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
This program shall include the following:
. (added 4-20-81; Am. 6 3)
):
1.
Provisions establishing preventive maintenance and
~
periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency' not to exceed refueling cycle intervals.
(10) The Licensee shall implement a program which will ensure the capability to accurately determine the airborn iodine concentration in vital areas under i-accident conditions.
This program shall include the following: (added 4-20-81; Am. 63) 1.
Training o f personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment 3.
This amended license is issued without prejudice to subsequent licensing' action which may be taken by the -
Commission. (revised 8-09-73 ; Am. 1) 4.
This amended license is effective as of the date of issuance and shall expire at midt.ight on December 26, 2008. (revised l
10-19-73; Am. 3) b-3858N i
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COMPOSITE LICENSE FOR ZION Unit 2 NRC DOCKE T NO. 50-304 FACILITY OPERATING LICENSE - DPR-48 (originally issued 11/04/73) 1.
Nuclear Regulatory Commission Findings:
(Omitted) 2.
Facility Operating License No. DPR-48:
A.
This license applies to the Zion Nuclear Power Station, Unit 2, a pressurized, light water moderated and cooleo reactor and associated electric generating equipment (the facility).
The facility is located on the applicant's 250 acre site on the west shore of Lake Michigan in Zion, Lake County, Illinois, approximately midway between Milwaukee, Wisconsin and Chicago, Illinois, as described in the Final Safety Analysis Report, as supplemented and amended.
B.
Subject to the conditlons and requirements incorporated herein, the Commission hereby licenses Commonwealth Edison:
(1)
Pursuant to Section 104b o f the Atomic Energy Act o f 195 4, as amended, and 10 CFR Part 50,
" Licensing o f Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location; (2)
Pursuant to the Act and 10 CFR Part 70, "Special Nuclea r Material," to receive, possess, 4ad use a t any time in connection with the operation of the facility, that amount of uranium enriched in the U-235 in accordance with the limitations for storage and amounts required for reactor operation as described in the Zion Station Final Safety Analysis Report as supplemented and amended, or as described in any amendment to this license; (revised 8-09-76 ; Am. 20)
(3)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source and special nuclear material as sealted neutron sources for reactor startup, sealed sources for reactor instrumentation, and radiation montioring equipment calibration, and as fission detectors amounts as required;
DPR-48 (4)
Pursuant to the ' Act and 10 CFR Pa rts 30, 40, and 70, to receive, possess, and use in amounts as required by any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5)
Pursuant to the Act and 10 CFR Parts 30 and -70, to possess, but not separate, such byproduct and special nuclear material as may be produced by the operation of the f acility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations:
10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Sections 50.54 and 50.59 of 10 CFR Part 50 and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below.
(1)
Maximum Power Level Commonwealth Edison Company is authorized to operate the Zion Nuclear Power Station Unit No. 2 at_ steady state reactor core power levels not to exceed 3250 megawatts thermal. (revised 6-25-76; Am. 18)
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment
-No. 66, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(revised 2-09-82 ; Am. 67)
(3)
This license is subject to the following conditions for the protection of the environment:
DPR-48 (a)
Radiological and non-radiological Technical Specifications have been established by the Regulatory staff.
These Technical Specifications cover, but are not limited to, the following:
(1)
An extended operational monitoring program to determine the environmental impacts o f Station operation.
The program should determine the size, shape, and location o f the thermal plume during different wind and weather conditions.
The program should define the effects of facility operation on the aquatic ecosystem, including data on impingement of aquatic organisms on the bar racks and traveling screens.
(2)
A basis for starting the deicing operation (pumping heated discharge water to the intake structure) only af ter there are positive indications that icing of the of fshore intake structure is in f act taking place.
(b)
Commonwealth Edison shall develop design.
modifications to the condenser cooling water intake structure to reduce the effective water intake velocity to less than 1 foot per second (under winter deicing operations the present velocity is calculated to be over 3.7 fps; during non-winter operation it is calculated to be over 2.4 fps); or to otherwise minimize fish entrainment.
Commonwealth Edison will be prepared to install the modifications within a specified time period if excessive numbers of juvenile or adult fish mortalities result from operation of the condenser cooling water
- system, i
(c)
If important adverse effects or evidence of irreversible damage are detected by the monitoring programs, Commonwealth Edison will provide to the Commission an analysis of -the problem and a plan of action to be taken to eliminate or acceptably reduce the detrimental effects or damage.
1 DPR-48 (d)
Commonwealth Edison shall perform fish population studies in the o ffshore control areas to provide base line population statistics for all seasons o f the year.
Commonwealth Edison shall monitor the quantity and quality of fish population in these areas and shall assure that these control areas are outside the influence of the thermal plume.
Commonwealth Edison shall submit this fish population study program to the Commission for review by January 15, 1974.
(4)
The licensee shall not operate the reactor at power levels above P-7 (as defined in Section 7.2 of the Zion Final Safety Analysis Report) with less than four (4) reactor coolant loops in operation until safety analyses for less than four loop operation have been submitted and approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment to this license. (added 5-12-76; Am. 17)
(5)
The licensee may proceed with and is required to complete the modifications indicated in Paragraphs 3.1.1 through 3.1.20 o f the NRC's Fire Protection Evaluation (SE) on the Zion Nuclear Power Station dated March 10, 1978 and supplements thereto.
These modifications shall be completed as speci-fled in Table 3.1 of Supplement No.1 or in subsequent supplements to that SE.
In addition, the licensee shall submit the additional infor-mation identified in Table 3.2 o f the above cited SE in accordance with the schedule contained i
therein.
In the event these dates for submittal cannot be met, the licensee shall submit a report explaining the circumstances, toqether with a revised schedule. (revised 4-13-79 ; Am. 48)
(6)
Pursuant' to the requirements o f 10 CFR 50.34(c),
10 CFR 50.54(p) and 10 CFR 73.55, as applicable, the licensee shall fully implement and maintain in ef fect all provisions and changes to the following plans: (revised 1-15-81; Am. 58)
n DPR-48 (a)
Zion Station Units Nos.1 and 2 Physical Security Plan, approved March 14, 1979; (b)
Zion Nuclear Power Station Safeguards Contingency Plan, approved November 17, 1980 and to be fully implemented within 30 days; (c)
Zion Nuclear Power Station Guard Training and Qualification Plan approved January 15, 1981 and to be fully implemented within 60 days.
(7)
Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated April 13, 1978, as supplemented October 24, November 8 and 29, 1978, January 24 and 26, February 23, March 7 and March 19, 1979. (revised 1-15-81; Am. 58)
(a)
Fuel stored in the spent fuel pool shall have a U-235 loading less than or equal to 40.6 grams per axial centimeter. (added 2-28-80; Am. 49)
(b)
No loads heavier than the weight of a single spent fuel assembly plus the tool for moving that assembly shall be carried over fuel stored in the spent fuel pool.
.The spent fuel handling tool, the burnable poison tool, the rod cluster control changing fixture and the thimble plug shall not be carried at heights greater than two feet over fuel stored in the spent fuel pool.
(added 2-28-80; Am. 49)
(8)
The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.
This program shall include: (added 4-28-80; Am. 51)
(a)
Identification of a sampling schedule for the critical parameters and control' points for these parameters; (b)
Identification o f the procedures used to quantify parameters that are critical to control points; 1
r DPR-48 r l
(c)
Identification of process sampling points; (d)
Procedure for the recording and management of data; (e)
Procedures defining corrective actions for-of f control point chemistry conditions; and (f)
A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing o f administrative events required to initiate corrective action.
(9)
The Licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive. fluids during a serious transient or accident to as low as practical levels.
This program shall include the following: (added 4-20-81; Am. 60) 1.
Provisions establishing ~ preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
(10) The Licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following: (added 4-20-81; Am. 60) 1.
Training of personnel, l
2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment 8
3.
This amended l license is issued without prejudice to subseouent licensing action which may be taken by the o
Commission.
(revised 8-02-74; Am. 1) 4.
This amended license is effective as of the date of issuance
.and shall' expire at midnight on December 26, 2008.
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