ML20055F353
| ML20055F353 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/06/1990 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055F354 | List: |
| References | |
| NUDOCS 9007160320 | |
| Download: ML20055F353 (13) | |
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y UNITED 8TATES 4
7 NUCLEAR REGULATORY COMMISSION i
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- f W ASHINGTON, D. C. 20555 g....+f IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE i
CORN BELT POWER C00 PERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY' CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.166 License No. DPR-49 1.
The Nuclear Regulatory Comissior. (the Commission) has found that:
A.-
The' application for amendment by Iowa Electric Light and Power Company, et al., dated November 3,1989, as supplemented-February 26, 1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the 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 provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regulations; D.
The
'suance 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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:
9007160320 900706 ADOCK03OOggi DR.
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-2 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Anendment No.166, 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 2 years of the date of issuance, t
FOR THE NUCLEAR REGULATORY COMMISSION John N. Hannon, Director l
Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
l' Changes to the Technical Specifications Date of Issuance:
July 6, 1990 l
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. 4 ATTACHMENT TO LICENSE AMENDMENT NO. 166 1
FACILITY OPERATING LICENSE M0. DPR-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.
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viii 6.1-1 6.2-1 6.2-2 i
6.2-4 6.3-1 6.4-1 6.5-1 6.9-1 4
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DAEC-1 PAGE NO.
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1 5.0 Design Features 5.1-1
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l 5.1 Site 5.1-1 5.2 Reactor 5.2-1 5.3 Reactor Vessel 5.3-1 5.4 Containment 5.4-1 5.5 Spent and New Fuel Storage 5.5-1 l
6.0 Administrative Controls 6.1-1 6.1 Management - Authority and Responsibility 6.1-1 6.2 Organization 6.2-1 l
l 6.3 Plant Staff Qualifications 6.3-1 6.4 Retraining and Replacement Training 6.4-1 6.5 Review and Audit 6.5-1 6.6 Reportable Event 6.6-1 6.7 Action to be Taken if a Safety limit is Exceeded 6 7-1 6.8 Plant Operating Procedures 6.8-1 6.9 Radiological Procedures 6.9-1 L
6.10 Records Retention 6.10-1 6.11 Plant Reporting Requirements 6.11-1 6.22 Deleted 6.13 Deleted E
l' Amendment No. 105,733,166 iv i
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1 DAEC-1 FIGUREIM2ER IIILE l
3.12-10 Flow-Dependent Maximum Average Planar Linear Heat Generation i
Rate (MAPLHGR) Multiplier (MAPFAC,)
t 3.12-11 Power-Dependent Maximum Average Planar Linear Heat Generation j
Rate (MAPLHGR) Multiplier (MAPFAC,)
i 3.12-12 Flow-Dependent Maximum Average Planar. Linear Heat Generation Rate (MAPLHGR) Multiplier (MAPFAC,) for SLO 6.2-1 Deleted l
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Amendment No.120,H2,166 Viii
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DAEC-1 6.0 ADMINISTRATIVE CONTROLS 6.1 MANAGEMENT - AUTHORITY AND RESPONSIBILITY 6.1.1 The Plant Superthsendent-Nuclear has primary responsibility for the safe operation of the DAEC, and reports to the Manager-Nuclear Division.
6.3.2 The overall responsibility for the fire protection program for DAEC is I
assigned to the Manager-Nuclear Division.
The DAEC Plant Superintendent-Nuclear is responsible for directing the operating plant fire protection program.
6.1.3 The Manager, Corporate Quality Assurance is responsible for l
implementation of the Quality Assurance Program at the DAEC.
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Amendment No. E0,J36,166 6.1-1
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DAEC-I 6.2 ORGANIZATION 6.2.1 ONSITE R t OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.
The onsite and offsite organizations shall include positions for activities affecting the safety.
of the nuclear power plant.
a.
Likes of authority, responsibility, and communication shall be established and defined from 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 l
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of documentation.
These requirements shall be documented in the Duane I
Arnold Energy Center Updated Final Safety Analysis Report and updated in accordance with 10 CFR 50.71(e).
b.
The Plant Superintendent-Nuclear shall be responsible for overall unit safe operation and shall have-control over those onsite activities necessary for safe operation and maintenance of the plant.
The Manager-Nuclear D' vision shall have corporate responsibility for c.
overall plant 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, d.
The individuals who train the operating staff and those who carry out i
health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedor, to ensure their independence from operating i
pressures.
Amendment No. M,U 6,166 6.2-1 4
DAEC-1 6.2.2 PLANT STAFF ORGANIZATION-
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The following manning requirements shall be met:
U 1.
All CORE ALTERATIONS shall be directly supervised by either a Senior
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Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
2.
At all times when there is fuel in the reactor:
A senior reactor operator shall be on the plant site, a.
c b.
A reactor operator shall be in the control room.
Two reactor operators shall be in the control room during startup, c.
scheduled shutdown, and during recovery from trips caused by transients or emergencies.
d.
Minimum operating shift crew compositions shall conform to those shown in Table 6.2-1.
At least one member of each operating shift crew shall be qualified e.
to implement radiation protection procedures,
- f..A fire brigade of five members shall be maintained on site at all times.
This excludes two members of the shift crew.
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Amendment No. A3,166 6.2-2
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..c DAEC:2 L. -...
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Figure 6.2-1 DELETED Amendment No. JJA.136,166 6.2-4 i
DAEC-1 6.3 PLANT STAFF OUALIFICATIONS 6.3.1 The qualifications of individual members on the plant staff will meet or exceed qualifications referenced for comparable positions in ANSI /ANS 3.1-1978.
l 6.3.2 The Radiation Protection Supervisor shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
6.3.3 The Shift Technical Advisor 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 (effective 1/1/81).
6.3.4 Either the Plant Superintendent-Nuclear or one of his designated principal alternates shall have the experience and training normally required for a Senior Reactor Operator's license examination.
(ANSI /ANS 3.1-1978) 6.3.5 The Operations Supervisor shall hold a Senior Reactors Operator's license. (ANSI /ANS 3.1-1978)
Amendment No. RO,166 6.3-1
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DAEC-1 i
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6.4 RETRAINING AND REPLACEMENT TRAINING 6.4.1 A training program shall be established to maintain the overall proficiency of the Operating organization.
This program shall consist 3
of both retraining and replacement training elements and shall meet or i
exceed the minimum provisions outlined in ANS!/ANS 3.1-1978.
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6.4.2 A training program for the fire brigade shall be maintained under the direction of the Manager, Training and shall meet or exceed the l
requirements of Section 27 of the NFPA Code, except for fire brigade training sessions which shall be held at least quarterly.
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Amendment No. 80,166 6.4-1
DAEC-1 6.5 REVIEW AND AUDIT 6.5.1 Operations Committee 6.5.1.1 Function The Operations Committee shall function to advise the Plant Superintendent - Nuclear on all matters related to nuclear safety.
6.5.1.2 Composition The Operations Committee shall be composed of selected Assistant Plant Superintendents, Superintendents, Supervisors and personnel from the following departments: Operations, Maintenance, Reactor Performance, l
Radiation Protection, Quality Control, and Technical Support.
The Assistant Plant Superintendent-Operations and Maintenance shall I
act as the Chairman.
One or more of the members shall be designated as Vice Chairman.
6.5.1.3 Alternates All alternate members shall be appointed in writing by the Plant Superintendent-Nuclear to serve on a permanent basis; however, no more than three alternates shall participate as voting members in Operations Committee activities at any one time.
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Amendment No. E0,JM,166 6.5-1
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i DAEC-1
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RADIDLOGICAL PRDCEDURES l
6.9.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of *0 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.9.2 HIGH RADIATION AREA In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area.in which the intensity of radiation is greater than 100 arem/hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit.* Any individual l
or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
l a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area, b.
A radiation monitoring device which continuously integrates the 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 level in the area has been established and personnel have been made knowledgeable of them.
l c.
Ahealthphysicsqualifiedindividual(i.e.,qualifiedin.
radiationprotectionprocedures)witharadiationdoserate monitoring device who is responsible for providing positive I
control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physics Supervisor in the Radiation Work 1
Permit.
6.9.3 In addition to the requirements of 6.9.2, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour dose greater than 1000 arem shall be arovided with locked doors to prevent unauthorized entry, and the (eys shall be maintained under the administrative control of the Operations Shift Supervisor on duty and/or health physics l
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supervision.
Doors shall remained locked except during 1
s Amendment No. 73,i66 6.9-1 m
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