ML20057A020
| ML20057A020 | |
| Person / Time | |
|---|---|
| Site: | Fermi  (NPF-43-A-091, NPF-43-A-91) |
| Issue date: | 08/27/1993 |
| From: | Bill Dean Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A021 | List: |
| References | |
| TAC-M86073, NUDOCS 9309100298 | |
| Download: ML20057A020 (7) | |
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UNITED STATES I
5; NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
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i DETROIT EDISON COMPANY DOCKET NO. 50-341 l
FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 -
License No. NPF-43 1.
The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment by the Detroit Edison Company i
(the licensee) dated March 23, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (tne Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this 3
amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance r
with the Comission's regulations; j
D.
The issuance of this amendment will not be inimical to the comon defense h
and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been i
satisfied.
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I 9309100298 930827 PDR ADDCK 05000341
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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. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan I
The Technical Specifications contained in Appendix A, as revised through t
Amendment No. 91
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance with full implementation within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION h{
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'h' William M. Dean, Acting Director Project Directorate III-l l
Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 27, 1993 i
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7, AlfACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT XX XX 6-15 6-15 6-18 6-18 6-24 6-24
- 0verleaf page provided to maintain document completeness. No changes contained on these pages.
INDf]
ADMINISTRATIVE CONTROLS SECTION PAGE REVIEW..............................................
6-10 AUDITS..............................................
6-11 REC 0RDS.............................................
6-12 6.5.3 TECHNICAL REVIEW AND CONTR0L........................
6-12 ACTIVITIES..........................................
6-12 REVIEW..............................................
6-13 SAFETY EVALUATIONS..................................
6-13 QUALIFICATIONS......................................
6-13 REC 0RDS.............................................
6-13 6.6 REPORTABLE EVENT ACTI0N....................................
6-13 6.7 SAFETY LIMIT V10LAT10N.....................................
6-14 6.8 PROCEDURES AND PR0 GRAMS....................................
6-14 6.9 REPORTING RE0VIREMENTS.....................................
6-16b 6.9.1 ROUTINE REP 0RTS.....................................
6-16b
-STARTUP REP 0RT......................................
6-16b ANNUAL REP 0RTS......................................
6-17 MONTHLY OPERATING REP 0RTS...........................
6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..
6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.......
6-18 l
6.9.2 SPECIAL REP 0RTS.....................................
6-21 6.9.3 CORE OPERATING LIMITS REP 0RT........................
6-21 6.10 RECORD RETENTION..........................................
6-21 6.11 RADIATION PROTECTION PR0 GRAM..............................
6-22a 6.12 HIGH RADIATION AREA.......................................
6-22a-6.13 PROCESS CONTROL PR0 GRAM...................................-
6-23 6.14 0FFSITE DOSE CALCULATION MANUAL...........................:
6-24 FERMI - UNIT 2 xx Amendment No,' JJ,- #f, JE,91 -
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.2 Each plant administrative procedure, and changes thereto, shall be reviewed in accordance with Specification 6.5.1.6, and approved by the Plant Manager prior to implementation, and shall be reviewed periodically thereafter as set forth in administrative procedures.
6.8.3 Each plant procedure required by Specification 6.8.1, other than administrative procedures, and changes thereto, shall be reviewed in accordance with 6.5.3, and approved by the Plant Maniger prior to implementation and shall be reviewed periodically thereafter as set forth in administrative procedures. The Plant Manager may delegate approval authority in writing for specific types of procedures to a management representative responsible for the functional area.
6.8.4 Temporary changes to procedures of Specification 6.8.1 may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on Fermi 1; and c.
The change is documented, and reviewed and approved in accordance with either 6.8.2 or 6.8.3 above, as appropriate, within 14 days of implementation.
6.8.5 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, reactor water sampling, containment sampling, reactor water cleanup, combustible gas control, control rod drive discharge headers, and standby gas treatment systems. The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less.
b.
in-plant Radiation Monitorino 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:
FEPJil - UNIT 2 6-15 Amendment No. JJ, D, 91
O ADMINISTRATIVF CONTR01S ANNUAL REPORTS (Continued)
(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; (2) results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, recults of analysis while limit was exceeded and results of ar-analysis after the radiciodine activity was reduced to. ss than limit (each result should include date and time of sampling and the radioiodine concentrations);
(3) clean-up system flow 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; (4) graph of the I-131 and one other radiciodine isotope concentrations 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.
MONTHLY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted
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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. The material provided shall be consistent with the objectives outlined in (1) the ODCH and
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(2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT l
6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation I
of the unit during the previous 12 months of operation shall be submitted l
within 90 days after January 1 of each year. The report shall include a l
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 ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
j FERMI - UNIT 2 6-18 Amendment No. JJ, EJ,91
. ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) (Continued) 1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 2)
A' determination that the change will maintain the overall conformance of the solidified waste product to existing' requirements of Federal, State, or other applicable i
regulations.
I b.
Shall become effective after review and acceptance by the OSR0 and the approval of the Plant Manager.
_6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
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6.14.2 Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation shall contain-l 1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and 2)
A determination that the change will maintain the level of '
radioactive effluent control required by.10 CFR 20.106, 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, or setpoint calculations.
b.
Shall become effective after review and acceptance by the OSR0 and the approval of the Plant Manager.
c.
Shall be submitted to the Commission in the form of.a complete, legible copy of the entire ODCM as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l.
report in which any change to the ODCM was made.
Each change l
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 (e.g., month / year) the change was implemented.
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i FERMI - UNIT 2 6-24 Amendment No. JJ, S/, 91