ML20128B817
| ML20128B817 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 01/26/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128B787 | List: |
| References | |
| NUDOCS 9302030182 | |
| Download: ML20128B817 (8) | |
Text
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DOCKli fig. 50-285 FORT CALHOUN STATIOl. UNIT NO. 1 6tiENDMENT TO FACILIT' OPERATING LICENSE Amendment No '1491 License No.- OPR-40 1.
The Nuclear Regulatory Commission (the-Commission) has found-that:-
A.
The application for amendment by the Omaha Public Power District (the licensee) dated February 12,-1992, as supplemented by letter dated December 14, 1992, 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; 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 -(ti) that such activities will be conducted in compliance with the Commission's regulations;-
D.
The issuance of this license amendment will not be Linimical: to the common defense and security or:to the_healthLand 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.
1 9302030182'930126 P
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Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this i
license amendment, and paragraph 3.B. of facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
149, are hereby incorporated in the license.
The 1.censee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 90 days from date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dbbM 9:q George T. Hubbard, Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 26, 1993 l
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ATTACHMENT TO IICENSE AMENDMENT NO. 149 FACILITY OPERATING LICENSE NL DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
4 REMOVE PAG 1]i INSERT PAGES 5-4 5-4 5-5 5-5 5-9 5-9 5-9a 5-10 5-10
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5.0 ADhilNISTRATIVE CONTROLS Emponsibilities 5.5.1.6 The Plant Review Committee shall be responsible for:
a.
Review of (1) Administrative Controls Standing Orders and changes thereto, (2) procedures required by Specification 5.8 and requiring a 10 CFR 50.59 safety evaluation, and (3) proposed changes to procedures required by Specification 5.8 and requiring a 10 CFR 50.59 safety evaluation; b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to the Technical Specifications, d.
Review of all proposed changes to the Core Operating Limits Report.
c.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, f.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Division Manager - Nuclear Operations and to the Chairman of the Safety Audit and Review Committee, g.
Review of facility operations to detect potential safety hazards.
h.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Safety Audit and Review Committee, i.
Review of the Site Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Safety Audit and Review Committee, j.
Review of the Site Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Safety Audit and Review Committee.
k.
Review of all Reportable Events.
Authority 5.5.1.7 The Plant Review Committee shall:
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a.
Recommend in writing to the Manager - Fort Ca!houn Station approval or disapproval of items considered under 5.5.1.6(a) through (e) above.
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l-5-4 Amendment No. 9,49,64,99,115,141, 149
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5.0 ADMINISTRATIVE CONTROlE 5.5.1.7
'b.-
Render determinations in writing with regard to whether or not each item 1
- /.
considered under 5.5.1.6(b) through (f) above constitutes an unreviewed l
-l safety question.
q c.
Provide immediate written notification to the Division Manager - Nuclear Operations and the Safety Audit and Review Committee of disagreementu
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between the Plant Review Committee and the Manager i Fort Calhoun Station; however, the Manager - Fort Calhoun Station shall have i
responsibility for resolution of such disagreements pursuant to 5.1.1 above.
' Records 1
5.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and _
copies shall be prov_ided to the Division Manager - Nuclear Operations and Chairman of the Safety Audit and Review Committee. -
5.5.2 Safety Audit and Review Committee (SARC)
Function 5.5.2.1 The Safety Audit and Review Committee shall function to provide the independent review and audit of designated activities in the areas of:
a.-
nuclear power plant operation b.
nuclear engineering e.
chemittry and radiochemistry d.
. metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering -
h.
quality assurance Commlillion 5.5.2.2 The Safety Audit and Review Committee shall be composed of:
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- Chairman:
Division Manager - Nuclear Services Member:
Senior Vice President-Member:
Division Manager -_ Nuclear Operations
- Member:
- Division Manager Production Engineering -
Member:
Manager - Fort Calhoun Station Member:
Manager y Radiological Services Member:
- Qualified Consultants as Required and as Determined by SARC.
Chairman 55 Amendment No. 86,93,99[
401,446,419,132,141,;
-149
5.0 ADh11NISTRATIVE CONTROLS l
5.6 Reportable Event Action 5.6.1 The following actions shall be taken in the event of a REPORTABLE EVENT:
a.
The Commission shall be notified pursuant to the requirements of 10 CFR 50.72, if applicable.
b.
Each Reportable Event shall be reviewed by the Plant Review Committee and submitted to the Chairman of the Safety Audit and Review Committee and the Division blanager - Nuclear Operations.
c.
Submit reports of Reportable Events pursuant to the requirements of Specification 5.9.2.
. 5.7 Safety Limit Violatica 5.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The 'mit shall be placed in at least liOT SHUTDOWN within I hour, b.
The Safety Limit Violations shall be reported to the Division hianager -
Nuclear Operations and the Chairman of the Safety Audit and Review Committee (SARC) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.-
A Safety Limit Violation Report shall be prepared. The report shall be c.
reviewed by the Plant Review Committee, This report shall describe (1) applicable circ"mstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Chairman of the Safety Audit and Review Committee and the Division hianager -
Nuclear Operations within 14 days of the violation.
5.8 Procedures 5.8.1-Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the minimum requirements of sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1.33 except as provided in 5.8.2 and 5.8.3 below.
5.8.2 Each procedure of Specification 5.8.1, and changes thereto, and any other procedure or procedure change that the hianager - Fort Calhoun Station determines to affect nuclear safety, shall be reviewed and approved as described below, prior to implementation.
59 Amendment No. 9,49,38,84,99, 4 % 149
5.0 A11MINISTRATIVE CONTROLS l
5.8.2.1 Each procedure, or change thereto, shall be reviewed by a Qualified Reviewer (QR) who is knowledgeable in the functional area affected but is not the individual preparer. The QR may be from the same line organization as the preparer. The QR shall render a determination in writing of whether or not cross-disciplinary review of a procedure, or change thereto is necessary. If necessary, such review shall be performed by appropriate personnel.
5.8.2.2 Each procedure, or change thereto, shall be reviewed by the Department llead
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designated by Administrative Controls Standing Orders as the responsible i
Department licad for that procedure, and the review shall include a determination of whether or not a 10 CFR 50.59 safety evaluation is required. If a 10 CFH 50.59 safety evaluation is not required, the procedure, or change thereto, shall be approved by the responsible Department licad or the Manager-Fort Calhoun Station, prior to implementation. Administrative Controls Standing Orders, the Site Security Plan and implementing Procedures, and the Emergency Plan and Implementing Procedures shall be reviewed in accordance with Speci0 cation 5.5.1.6 and approved by the Manager Fort Calhoun Station.
5.8.2.3 If the responsible Department licad determines that a procedure, or change thereto, requires a 10 CFR 50.59 safety evaluation, the responsible Department licad shall render a determination in writing of whether or not the procedure, or change thereto, involves an Unreviewed Safety Question (USQ) and shall forward the procedure, or change thereto with the associated safety evaluation to the PRC for review in accordance with Specification 5.5.1.6.a. If a USQ is involved.
NRC approval is required prior to implementation of the procedure, or change.
5.8.2.4 Qualified Reviewers shall meet or exceed the respective qualifications for either Supervisors Requiring an AEC License, Professional. Technical Personnel, or Technical Support Personnel, as specified in ANSI N18.1 - 1971. Personnel recommended to be QRs shall be reviewed by the PRC and approved and designated as such by the PRC Chairman. The responsible Department liead shall ensure that a sufficient complement of QRs for their functional area is maintained in accordance with Administrative Controls Standing Orders.
5.8.2.5 Each procedure of Specification 5.8.1 shall be reviewed periodically as set forth in Administrative Controls Standing Orders.
l 5.8.2.6 Records documenting the activities performed under Specifications 5.8.2.1 through 5.8.2.4 shall be maintained in accordance with Specification 5.10.
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5-9a Amendment No.149 l
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5.0 ADMINISTRATIVE CONTROLS 0
5.8.3 Temporary changes to procedures of 5.8.1 above may be made provided:
a' a.
The intent of the original procedure is not altered.
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b.
The change is approved by two members of the plant supervisory staff, at
/
least one of * 'hom holds a Sen!or Reactor Operator's License, c.
The chrage is documented, reviewed by a Qualined Reviewer and approved by either the Manager Fort Calhoun Station or the Department licad designated by Administrative Controls Standirig Orders as the responsible Department liead for that procedure within 14 days of implementation.
5.8.4 Written procedures approved per 5.8.2 above shall be implemented which govern the selection of fuel assemblies to be placed in Region 2 of the spent fuel racks (Technical Speci6 cation 2.8). These procedures shall require an independent l
verincation of initial enrichment requirements and fuel burnup calculations for a fuel bundle to assure the " acceptance" criteria for placement in Region 2 are met.
This independent verification shall be performed by individuals or groups other than those who performed the initial acceptance criteria assessment, but v!ho may be from the same organization.
5.9 RepeniDE.RequircJnents in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identined reports shall be submitted to the Director of the appropriate Regional Of6ce of Inspection and Enforcement unless otherwise noted.
5.9.1 Holtiine Reports a.
Sar1DD_RtDDI1. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design er has been manufacture by a different fuel supplier, and (4) modifications that may have significantly.
altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identined in the USAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitm,nts shall be included in this report.
I 5 10 Amendment No. 9,49,35,75, 149
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