ML20064N379
| ML20064N379 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/22/1994 |
| From: | Pulsifer R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064N381 | List: |
| References | |
| NUDOCS 9403290288 | |
| Download: ML20064N379 (8) | |
Text
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y ne d
h UNITED STATES
[ kf[/j iOE NUCLEAR REGULATORY COMMISSION
- t WASHINGTON, D.C. 20555-0001 IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE
._0RN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 196 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al., dated July 28, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and regulations of the Commission, l
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 1
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 attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
9403290288 940322 PDR ADOCK 05000331 P
(2) - Technical Specifications The Technical Specifications contained in Appendix A, as -revised through Amendment No. 196, are hereby incorporated in-the license.
The licensee shall operate the facility in accordance.with'the Technical Specifications.
3.
The license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION tlk c
Rober M. Puls er, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: fiarch 22, 1994 l
4 ATTACHMENT TO LICENSE AMENDMENT NO. 196 FACILITY OPERATING LICENSE NO. OPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
REMOVE INSERT 6.11-3 6.11-3 6.11-4 6.11-4 6.11-5 6.11-5 6.11-7 6.11-7 6.14-1 6.14-1
DAEC-1 c.
Monthly Operatina Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the NRC to arrive no later than the 15th of each month following the calendar month covered by the report'.
d.
Other Reports Table 6.11-1 lists some of the routine reports required by 10 CFR Parts 20, 40, 50 and 70, including those listed in Specification 6.11.1.
e.
Annual Safety / Relief Valve Challence A report documenting safety / relief valve challenges shall be submitted within 60 days of January 1 each year.
f.
Annual Radioactive Material Release Report The Annual Radioactive Material Release Report covering the operation of the unit during the previous calendar year shall be submitted on or before May 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODAM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10.CFR.Part 50.
g.
Annual Radioloaical Environmental Report The' Annual Radiological Environmental Report covering the operation of the unit during the previous calendar year shall be submitted on or before 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.
j The material provided shall be consistent with the objectives outlined in (1) the ODAM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
h.
1-131 Dose Eauivalent Exceeding 50% of Eauilibrium Value A report of the results of specific activity analysis in which the primary coolant exceeded the limits of specification 4.6.B.I.h shall be submitted on an annual basis within 60 days after January 1.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; Amendment No. 109,184.196 6.11-3
DAEC-1 i
(2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and radiciodine concentrations; (3) Cleanup systen, operating status starting-48 hours prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
6.11.2 CORE OPERATING LIMITS REPORT a.
Core cycle-dependent limits shall be established prior to each reload cycle, or prior to any remaining part of a reload cycle, for the following:
1)
Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) -
Specification 3.12.A.
2)
Linear Heat Generation Rate (LHGR) - Specification 3.12.B.
3)
Minimum Critical Power Ratio (MCPR) - Specification 3.12.C.
4)
MAPFAC and MAPFAC Specifkcation 3.3.I. Factors which multiply the MAPLHGR limits -
4.a.
These limits shall be documented in the CORE OPERATING LIMITS REPORT.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Standard Application for Reactor Fuel, NEDE-240ll-P-A, (GESTAR II).*
c.
The core operating limits shall be determined such that all applicable limits (e a. 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.
I
- Approved revision number at time reload fuel analyses are performed.
Amendment No. 107,728,I67,I70,184, 6.11-4 196 t.
DAEC-1 I
d.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.11.3 UNIOVE REPORTING RE0VIREMENTS Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
a.
Reactor vessel base, weld and heat affected zone metal test specimens (Specification 4.6.A.2).
b.
deleted c.
Inservice inspection (Specification 4.6.G.).
d.
Reactor Containment Integrated Leakage Rate Test (Specification 4.7.A.2.f).
e.
deleted f.
deleted 9
deleted h.
Radioactive Liquid or Gaseous Effluent - calculated dose exceeding specified limit (0 DAM Sections 6.1.3, 6.2.3 and 6.2.4).
- i. Off-Gas System inoperable (0 DAM Section 6.2.5).
i j.
Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period (00AM Section 7.3.2.2).
k.
Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose limit (0 DAM Section 6.3.1.1).
1.
Radioactive liquid waste released without treatment when activity
)
concentration exceeds 0.01 pci/ml (0 DAM Section 6.1.4.1).
m.
Explosive Gas Monitoring Instrumentation Inoperable (Specification 3.2.I.1).
n.
Liquid Holdup Tank Instrumentation Inoperable (Specification 3.14.B.1).
Amendment No. }W,196 6.11-5
DAEC-1 TABLE 6.11-1 (cont)
REPORTING
SUMMARY
- ROUTINE REPORTS Reouirement Egpprt Timina of Submittal 50.59(b)
Changes, Tests, Within 6 months after each and Experiments REFUELING OUTAGE.
670.53 Special Nuclear Within 30 days after March 31 Material Status and September 30 of each year.
570.54 Transfer of Special Promptly upon transfer Nuclear Material S70.54 Receipt of Special Within 10 days after Nuclear Material material is received Appendix G Fracture Toughness On an individual-case basis to 10 CFR at least 3 years prior to Part 50 the date when the predicted fracture toughness levels will no longer satisfy section V.B. of Appendix G to 10 CFR Part 50.
Appendix H Reactor Vessel Completion of tests after to 10 CFR Material Surveillance each capsule withdrawal.
Part 50 Appendix I Annual Radioactive On or before May 1.
to 10 CFR Material Release Part 50 Report Appendix I Annual Radiological On or before May 1.
to 10 CFR Environmental Report Part 50 Appendix J Reactor Containment Approximately 3 months to 10 CFR Building Integrated following conduct of test.
Part 50 Leak Rate Test Amendment No. 109,J79,JE4,196 6.11-7 j
1
- +
DAEC-1 6.14 0FFSITE DOSE ASSESSMENT MANUAL (0 DAM) 6.14.1 Changes to the ODAM a.
Shall be _ documented and records of reviews performed shall be retained as required by Specification 6.10.2.14.-This documentation shall contain:
1)
Sufficient ~information to support the change together with appropriate analyses or evaluations justifying the change (s) and 2)
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR'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 o: setpoint calculations.
b.
Shall become effective after review and acceptance by the Operations Committee and approval.by the Plant Superintendent, Nuclear.
c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODAM as a part of or concurrent with the Annual Radioactive Material l-Release Report for the period'of the report in which any change to the ODAM was made.
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 shall indicate-the date the change was implemented.
Amendment No. kQ7JAA,J$A,196 6.14-1-