ML20214M511
| ML20214M511 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/04/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Central Iowa Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20214M515 | List: |
| References | |
| DPR-49-A-136 NUDOCS 8609110150 | |
| Download: ML20214M511 (12) | |
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET N0. 50-331 DUANE ARN0LD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 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 September 24, 1985, as clarified by letter dated June 26, 1986, 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 It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
l 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 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 Tecnnical Speciff-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-49 is hereby amended to read as follows:
8609110150 860904 DR ADOCK 0500 1
'. (2) _ Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.136, 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 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/d Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMENDMENT N0. 136 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET N0. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 6.1-1 i
6.2-1 6.2-3 6.2-4 6.5-1 6.5-3 6.5-4 6.6-1 6.7-1 l
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l N
DAEC-1 i
6.0 ADMINISTRATIVE CONTROLS 6.1 MANAGEMENT - AUTHORITY AND RESPONSIBILITY 6.1.1 The Plant Superintendent-Nuclear has primary responsibility for the safe operation of the DAEC, and reports to the Manager-Nuclear Division.
l 6.1.2 The overall responsibility for the fire protection program for DAEC is assigned to the Manager-Nuclear Division. The DAEC Plant l
Superintendent-Nuclear is responsible for directing the operating plant fire protection program.
6.1.3 The Quality Control Supervisor is responsible for implementation of the Quality Assurance Program at the DAEC and reports to the Manager-Corporate Quality Assurance.
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l Amendment No. 80, 136 6.1-1 t
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DAEC-1 6.2 PLANT STAFF ORGANIZATION 6.2.1 The plant staff organization shall conform to that shown in Figure 6.2-1.
6.2.2 The following manning requirements shall be met:
1.
All CORE ALTERATIONS shall be directly supervised by either a Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has
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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.
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b.
A reactor operator shall be in the control room.
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Two reactor operators shall be in the control room during startup, c.
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scheduled shutdown, and during recovery from trips caused by transients or emergencies.
d.
Minimum operating shift crew compositions shall confonn to those shown in Table 6.2-1.
Amendment No. 69, 136 6.2-1
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g TABLE 6.2-1
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i MINIMUM SHIFT CREW PERSONNEL AND LICENSE REQUIREMENTS a
y Reactor Mode g
I, Other Than DAEC Job Title i
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Cold Shutdown Cold Shutdown "A" Operations Shift Supervisor
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1 - SR0(1)
"B" Operations Shift Supervisor 1 - SR0(1)(2)
Nuclear Station Operating Engineer 1-R0 1-R0
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Assistant Nuclear Station Operating Engineer 1 - R0 Second Assistant Nuclear Station Operating Engineer 1
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Nuclear Station Auxiliaries Engineer 1
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1(2)
None Required o.
w Minimum Total Personnel W
7 3
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SRO - Senior Reactor Operator l
RO - Reactor Operator I
Substitutions - without changing minimin total personnel requirenents:
Individuals with senior reactor operator license may substitute for reactor a.
operator or nonlicensed position, l
b.
Individuals with reactor operator license may, if otherwise qualified, substitute for nonlicensed position.
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NOTES
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(2) Not required while in the Refuel Mode.(1) Does not include the SRO or SRO Limited to F l
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g ag Manager Quality Control Nuclear Olvision g
Su pervi sor l
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Quality Control Plant Superintendent Personnel N
Nuc l ear *
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' Assistant Plant Superintendent Assistant Plant Superintendent Operations **
Radiation Protection and Plant Services Technical Services Training Secur ity *
- Supervi sor Su perintendent*
- Superintendent j
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cn Maintenance Opera tions i Assistant Radiation Security Support Techn ical Plant Instructors j
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, Superintenden t Supervisor Operations Protection Supervisor Services Support Performance g
SHO Supervisor Supervi sor
, Supervi sor Su pervi sor Supervi sor a
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SRO y
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Mechanical Electrical Malntenance Radiation-Security I
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Mstntenance Malntenance Engineer l Operations Protection Sh i f t Support Technical Plant Reactor b
o Supervisor Supervisor Shlft Personnel Supervisor Services Support Performance Engineers j
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g Su pervisor l
y Personnel Engineers Engineers Mechanical Electrical Maintenance Secur ity Maintenance Maintenance Engineering
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Personnel Personnel
, Personnel Personnel
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Nuclear Station Second Asslstant i
and Assistant Operating Engineer Engineers (RO) and Auxillary Engineer Duane Arnold Ener<y Center toma Electric 1.lght and Power Company 1
i Technical SpectfIcatlons SRO - Senior Reactor Operator DAEC Nuclear Plant Staffing RO - Reactor Operator Figure 6.2-1
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- - According to ANS) N18.1-1971, alther the Plant Superintendent or one of his designated principal alternates shall have the e9erlence and training normally required for a Senior Heactor Operator's license examinatlon. (At least one of the people in the i
i positions noted above shall meet that requirement. )
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DAEC-1 6.5 REVIEW AND AUDIT 6.5.1 Operations Connittee 6.5.1.1 Function The Operations Connittee shall function to advise the Plant Superintendent - Nuclear on all matters related to nuclear safety.
6.5.1.2 Composition The Operations Comittee shall be composed of selected Assistant Plant Superintendents, Superintendents, Supervisors and personnel from the following departments: Operations, Maintenance, Plant Performance, Radiation Protection, Quality Control, and Technical Support.
The Assistant Plant Superintendent - Operations shall act as the Chairman. One or more of the members shall be designated as Vice Chainnan.
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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4 Amendment No. 80,136 6.5-1
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DAEC-1 I
- e..!nvestigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and reconnendations to prevent recurrence to the Managar-Nuclear Olvision and to the Chairman of l
the Safety Cometttee.
I f.
Review of all Reportable Events.
Review of facility operations to detect potential safety hazards.
g.
h.
Performance of speciai reviews, investigations or analyses and reports thereon as requested by the Chairman of the Safety Cosmittee, i.
Review of the Plant Security Plan and implementing procedures.
J. Review of the Emergency' Plan and implementing procedures.
k.
Review of every unplanned release of radioactivity to the environs for which a report to the NRC is required.
1.
Review of changes to the Offstte Dose Assessment Manual and changes to the Process control Program.
6.5.1.7 Authority The Operations conmittee shalls Reconnend to t'he Plant Superintendent-Nuclear written approval or disapproval a.
of items considered under Specification 6.6.1.6 (a) through (d) above.
Amendm'ent No. 109, 136 0*I*3 4
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DAEC-1 b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6 (a) through (e) above constitutes an unreviewed safety question.
l c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Manager-Nuclear Division and the Safety Comittee of disagreement between the Operations Consnittee and the Plant Superintendent-Nuclear; however, the Plant Superintendent-Nuclear shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1 above.
6.5.1.8 Record The Operations Comittee shall maintain' written minutes of each meeting and copies j
shall be provided to the. Manager-Nuclear Division and the Chairman of the Safety Comittee.
6.5.2 Safety Committee 6.5.2.1 Function The Safety Comittee shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear Engineering.
6.5-4 Amendment No. 59, 136
DAEC-1 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS.
a.
Each REPORTABLE EVENT shall be reviewed by the Operations Comittee, and a report shall be submitted to the Safety Committee and the Manager-Nuclear Division and l
b.
The Comission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50.
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Amendment No. 105, 136 6.6-1 1
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DAEC-1 6.7 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED 6.7.1 If a safety limit is exceeded, the reactor shall be shut down and reactor operation shall only be resumed when authorized by the NRC.
6.7.2 An immediate report shall be made to the Manager-Nuclear Division-l and the Safety Committee. The Manager-Nuclear Division shall l
promptly report the circumstances to the NRC as specified in Subsection 6.11, Plant Reporting Requirements.
6.7.3 A complete analysis of the circumstances leading up to and resulting from the situation together with recommendations to prevent a recurrence shall be prepared by the Operations Connittee.
This report shall be submitted to the Manager-Nuclear Division and to the l
Safety Committee. Appropriate analyses or reports will be submitted to the NRC by the Manager-Nuclear Division as specified in l
Subsection 6.11, Plant Reporting Requirements.
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i Amendment No. fld,136 6.7-1
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