ML20114D002
| ML20114D002 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities, LaSalle  |
| Issue date: | 08/21/1992 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114D004 | List: |
| References | |
| NUDOCS 9209040071 | |
| Download: ML20114D002 (21) | |
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COMMONW1A.1TH EDISON LOMPANY WD J0WA-11LIN015 GAS AND ELECTRIC COMPANY DOCKET NO, 50-254
@ AD CITLLS NUCLEAR POWER STATIONuVNIT 1 MENDMENT TO FACILITY OPERATJf1G LILENS[
Amendment No. 136 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Co,nmission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 31. 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rule:; and regulations set forth in 10 CfR Chapter 1; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Conmission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR l
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of facility Operatino License No. DPR-29 is hereby amended to read as follows:
9209040071 920021 PDR ADOCK 05000254 P
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P t i 8.
Technical SEtrifications The Technical Specifications contained in Appendices A and D. as revised through Amendment No.136, are hereby incorpors.ted in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NOCLEAl; REGULATORY COMMISSION
/
isnt Richa J. Barrett, Director Project Directorate 111-2 Division of_ Reactor P'ciects - Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance:
August 21, 1992 P
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1 ATTACHMENT 10 llCENSE AMENQBENT NO. 136-FACILITY OPERATING llCENSE NO. DPR-29 DOCI:ET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT vi-vi 6.6-2 6.6-2 6.6-3 6.6-3 6.6-4 6.6-4 6.6-5 6.6-5 6.6-6
QUAD CITIES DPR-29 LIST OF TABLES (Cont'd)
Number Title Page 4.8-2 Haximum Permissible Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 3.8/4.8-29 4.8-3 Radioactive Liquid Waste Sampling and Aralysis Program 3.8/4.8-30 4.8-4 Radiological Environmental Monitoring Program 3.8/4.8-32 4.8-5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3.8/4.8-35 4.8-6 Practical Lower Limits of Detection (LLD) for Standard Environmental Radiological Monitoring Program 3.8/4.8-36 4.11-1 Surveillance Requirements for High Energy Piping Outside Containment 3.11/4.11-3 3.12-1 Fire Detection Instruments 3.12/4.12-11 3.12-2 Sprinkler Systemt 3.12/4.12-12 2 Syst3ms 3.12/4.12-12 3.12 3 CO 3.12-4 Fire Hose Stations 3.12/4.12-13 6.6-1 Special Reports 6.6-6 vi Amendment No. 136
QUAD-CITIES OPR-29 whole body dose received from external sources shall be assigned to specific major work functions.
3.
Monthly Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, DC 20555, with a copy to the appropriate Regional Office, to arrive no later than the 15th of each month following the calendar month covered by the report.
In addition, any changes to the ODCM shall be submitted with the Monthly Operating Report within 90 days of the effective date of the change.
A report of major change to the radioactive waste treatment systems shall be submitted with the Monthly Operating Report for the period in which the evaluation was reviewed and accepted by the onsite review function.
If such change is re-evaluated and not installed, notification of cancellation of the change should be provided to the NRC.
4.
Core Operating Limits Report a.
Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
(1) The Rod Withdrawal Block Monitor Upscale Instrurkntation Setpoint for Table 3.2-3 of Specification 3.2.C and for Specification 3.6.H.
(2) The overall average of the 20% insertion scram time data for Specification 3.3.C.
(3) The Average Planar Heat Generation Rate (APLHGR) for Specification 3.5.I.
(4) The Linear Heat Generation Rate (LHGR) for Specifica-tion 3.5.J.
(5) The Minimum Critical Power Ratio (MCPR) for Specifica-tion 3.5.K and 3 6.H.
(6) The K, core flow MCPR adjustment factor for Specifica-tion 3.5.K.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the latest approved revision or supplement of the 6.6-2 Amendment No. 136
QUAD-CITIES DPR-29 topical reports describing the methodology.
For Quad Cities Unit 1, the topical reports are:
(1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved revision).
(2) Commonwealth Edison Toaical Pep' ort NFSR-0085, " Benchmark of BWR Nuclear Design Aethods, (latest approved revision).
(3) Commonwealth Edison Topical Repoit NFSR-0085, Supplement 1,
" Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons," (latest approved revision).
(4) Commonwealth Edison Topical Report NFSR-0085, Supplement 2,
" Benchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses," (latest approved revision).
The core operating (e.mits shall be determined so that all li c.
applicable limits g., fuel thermal-mechanical limits corethermal-hydrauliclimits,ECCSlimits,nuclearlimits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met, d.
-The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle to the NRC Document Control DeskwithcopiestotheRegionalAdministratorandResident inspector-,
B.
Unique Reporting Requirements 1.
Radioactive Effluent Release Report (Semi-Annual)
A semi-annual report shall be submitted to the Commission within 60 days after January I and July 1 of each year specifying the quantity of each of the radionuclides released to unrestelcted areas in liquid and gaseous effluerits during the previous 6 nonths.- The format and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June, 1974.
Any changes to the PCP shall be included in this report.
2.
Environmental Program Data (Annual Report)
An annual report containing the data talon in the standard radiological monitoring program (Table 4.8-4) shall be submitted prior to May 1 of each year.
The content of the report shall include:
a.
Resultr of all environmental measurements summarized in the
. format of the Regulatory Guide 4.8 Table 1 (December 1975).
(Individual sample results will be retained at the Station).
6.6-3 Amendment No. 136
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QUAD-CITIES l
DPR-29 In the event that somt results are not available for inclusion with the report, the re. port shall be submitted noting and explaining the reasons for the missing results.
Summaries, interpretations, and analysis of trends of the results are to be provided.
b.
An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of radioactivity including the maximum noble gat gamma and beta air doses in the unrestricted area.
The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM).
c.
Results of the census to determine the locations of nearest residences and of nearby animals producing milk for human consumption (Table 4.8-4).
d.
The reason for the omission if the nearest dairy to the station is not in the monitoring program (Table 4.8-4).
e.
An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of jcint frequency distributions of wind speed, wind directicn, and atmospheric stability, f.
The results of the Interlaboratory Comparison Program described in section 3.8.D.7.
g.
The reselts of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year.
h.
A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the Station.
3.
If a confirmed measured radionuclide concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 4.8-5 a
and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Administrator of the NRC Regional Office, with a copy to the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter.
a.
When more than one of the radionuclides in Table 4.8-5 are detected in the medium, the reporting level shall have been exceeded if Ci 1
I R. L.1 6.6-4 Amendment No. 136
th where Ci is the average quarterly concentration of the i radionuclide in the medium and RL is the reporting level of radionuclide i.
b.
If radionuclides other than those in Table 4.8-5 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR 50, Appendix 1.
c.
This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous effect.
4.
Special Reports Special Reports shall be submitted as indicated in Table 6.6-1.
6.6-5 Amendment No. 136
QUAD-CITIES i
DPR-29 t
i TABLE 6.6-1
$PECIAL REPORTS Specification Area Reference Submittal Date a.
Secondary containment leak rate
- 4. 7. C Upon completion of each test (1)
- test, b.
Summary status of fuel performance 1.1 Bases After each refueling outage, c.
Materials radiation surveillance
- 4. 6. B. 2 After each specimen removal specimens and completion of analyses.
d.
Radioactive Source Leak Testing (2) 4.8.F Annual report.
e.
Special Effluents Reports 3.8.A 30 days following
- 3. 8. 8 occurrence.
3.8.D 6.6.C.3.
Notes 1.
Each integrated leak rate test of the secondary containment shall be the subject of a summary technical report.
This report should include data on the wind speed, wind direction, outside and inside-temperatures during the test, concurrent reactor building pressure, and emergency ventilation flow rate.
The report shall also include analyses and interpretations of those data which demonstrate compliance with the specified leak rate limits.
2.
This report is required only if the tests reveal _the prosence of the 0.005 microcuries or more of removable contamination.
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6.6-6 Amendment'No. 136
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UNITED STATES n
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NUCLEAR REGULATORY COMMISSION
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W ASHINGTON, D.C. 20tE6 COMMONWEALTH EDISON COMPANY NtD 1GW_hllLIN0lS GAS AND ELECTRIC COMPANY QQ2LT NO. 50-16 OVAD CITlfS_ NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 132 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the li:ensee) dated March 31, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commi.csion's rules and re.3ulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities aitthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public:
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all appiicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of facility Operating License No. OPR-30 is hereby amended to read as follows:
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. B.
Technica,1 Specification 1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
132, are hereby incorporated in the license.
The licensee shal' perate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION f,
W.i Richard)J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Tec1nical Specifications Date of issuance:
August 21, 1992 t
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ATTACHMENT 10 LICENSE AMENDMENT NO, 132 FACILITY OPERATING _LLCENSE NO, DPR-10 DOCKET NO. 50-215 Revise the Aopendix A Technical Specift:ations by removing the page identified below and inserting the attached page.
The revised page is identified by the captioned amendment number and contains marginal lines indicating the area of change.
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I OLAD CITIES
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DPR 30 b.
The analytical met.Mds used to determine the core operating limits shall be those previously feviewed and approved by the NRC in the latest approved revision or supplement of the topical reports describing the methodology.
For Quad Cities Unit 2, the topical reports are:
(1) NEDE 24011 P-A, ' General Electric Standard Application for Reactor Fuel,' (latest approved revision).
(2) Commonwealm Edison Topical Report NFSR 0085, ' Benchmark of BWR Nuclear Design Methods,' (latest approved revision).
(3) Commonwealth Edison Tonical Report NFSR 0085, Supplement 1,
' Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons * (latest approved revision).
(4) Commonwealth Edison Topical Report NFSR 0085, Supplement 2,
' Benchmark of BWR Nuclear Design Methods Neutronic Licensing Analyses," (latest approved revislor;).
- c. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and i,ccident analysis limits) of the safety analysis are met,
- d. The CORE OPERATING LIMITS REPORT, including any mid cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident inspector.
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6.6 2a Araendment No. 132 l
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UNITED STATES M /ni NUCLEAR REGULATORY COMMISSION j
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[0MMONWEALTH EDISON COMPANY DOCKET NO. 50-373 (6SALLE_C_WRLLSJAT10N. 010T 1
/MMMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No NPF-ll 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee) dated March 31, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisicns of the Act, and the regulations of the Commission; f.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or te the health :nd safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No NPF-ll is hereby amended to read as follows:
4 (2)
Itchnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REG LATORY COMMISSION v)ps'4 Richard
. Barrt t Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 1992
Alla.HMENT 10 LICENSE AMENDMENT NO. 84_
[AClllTY OPERATING LICENSE NO. NPF-11 DOCKET tiQ.u 50-371 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the area of change.
RuiOE l!$El 6-25 6-25 0
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______.---a_
___.___m___m
ADMINI5TRAT!VE CONTROLS Semiannual Radioactive Effluent Release Report (Continued)
(1) The Average Planar Linear Heat Generation Rate (APLHGR) for Technical Specification 3.2.1.
(2) The minimum Critical Power Ratio (MCPR) (including 20%
scram time, tau (1), dependent MCPR limits, and K, core flow MCPR adjustment actors) for Technical Specification 3.2.3.
(3) The Linear Heat Generation Rate (LHGR) for Technical Specification 3.2.4.
(4' The Rod Block Monitor Upscale Instrumentation Setpoints for Technical Specification Table 3.3.6-2.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the latest app.oved revision or supplement of the topical reports describing the raethodology.
For LaSalle County Station Unit 1, the topical reports are:
(1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved revision).
(2) Commonwealth Edison Topical Report NFSR 0085, " Benchmark of BWR Nuclear Design Methods," (latest approved revision).
(3) Commonwealth Edison Topical Report NFSR-0085, Supplement 1,
" Benchmark of BWR Nuclear Design Methods - Quad Cities Gama Scan Comparisons," (latest approved revision).
(4) Commonwealth Edison Topical Report NF3R-0085, Supplement 2,
" Benchmark of SWR Huclear Desigr Matnods - Neutronic Licensing Analyses," (latu approved revision).
c, The core operating limits shall be determined so that all applicable limits (e.g,, fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of i
the safety analysis are met.
i d.
The CORE OPERATING LI. F REPORT, including any mid-cycle revisions or supplement. thereto, shall be prov!ded upon issuance, for each reload cycle, to the U.S. Nuclear Regulatory Commission Document Control Desk with co,nies to the Regional l
Administrator and Resident Inspector.
B.
Deleted l
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LA SALLE UNIT I 6-25 Amendment No. 84
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UNITED STATES c
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WAMNoToN. o C. NA (D&t0NWEAllH EDISON C0tiPANY DQLKET NO. 50-374 LMAllE COUNTY STATION. UNIT 2 AMENDMENT TO FACillTY OPERt. TING LICQEL Amendment No. 68 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee) dated March 31, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (t'le Act), and the Commission's regulations set forth in 10 CfR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonab!e assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be canducted in compliance with the Commissisn's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accord;ngly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment and 3aragraph 2.C.(2) of t;ie Facility Operating License No. NPF-18 i.;
here)y amended to read as follows:
2 (2)
Technica_1 Specifications and E.ivironmental Protection Plan The Technical Specific;tions contained in Appendix A, as revised through Amendment No. 68, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR RE ULATORY COMMISSION 0
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Richard J. Barrett, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV/V Office of Nuclear Reactor Pegulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 21, 1992 e
i mimo
ATTACHMENT TO LICENSE AMEJ1Q!iB1 NO. 68 FAClllTY OPERATING llCINSE NQ tiPJ-1.B DOCKET N0 __50-374 Replace the following page of the Appendix "A" Technical Specifications witn the enclosed page.
The revised page is identified by amendment number and contains vertical lines indicating the area of change.
EltiQy1 INSERT 6-25 6-25 u-M
i ADMINISTRATION CONTROLS Semiannual Radioactive Ef fluent Release Report (Continued)
(1) The Average Planar Linear Heat Ger,eration Rate (APLHGR) for Technical Specification 3.2.1.
(2) The minimum Critical Power Ratio (MCPR) (including 20%
scram time, tau (t), dependent MCPR limits; and Kf core ficw MCPR adjustment factors) for Technical Specification 3.2.3.
(3) The Linear Heat Generation Rate (LHGR) for Technical Specification 3.2.4.
(4) The Rod Block Monitor Upscale Instrumentation Setpoints for Technical Specification Table 3.3.6-2.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the latest approved revision or supplement of the topical reports describing the methodology.
For LaSalle County Station Unit 2, the topical reports are:
(1) NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (latest approved revision).
(2) Commonwealth Edison Topical Report NFSR-0085, " Benchmark of BWR Nuclear Design Methods," (latest approved revision).
(3) Commonwealth Edison Topical Report NFSR-0085, Supplement 1,
" Benchmark of BWR Nuclear Design Methods - Quad Cities Gamma Scan Comparisons," (latest approved revision).
(4) Commonwealth Edison Topical Report NFSR-008S, Supplement 2,
" Benchmark of BWR Nuclear Design Methods - Neutronic Licensing Analyses," (latest approved revision).
c.
The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS Limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
d.
The CORT OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the U.S. Nuclear Regulatory Commission Document Control Desk with copies to the Regional Administrator and Resident Inspector.
B.
Deleted.
LA SALLE - UNIT 2 6-25 Amendment No. 68 l
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