ML20150A992
| ML20150A992 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/01/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150A974 | List: |
| References | |
| NUDOCS 8807110197 | |
| Download: ML20150A992 (13) | |
Text
'
/
'o UNITED STATES
[
f::,,g NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D. C. 20555 l;
e
%,...../
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALH0UN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. DPR-40 1
1.
The Nuclear Regulatory Comission (the Cormiission) has found that:
A.
The application for amendment by the Omaha Public Power District (thelicensee)datedMay 23, 1988 as supplemented June 7, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission, 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 l
conducted in compliance with the Comission's regulations; D.
The issuance of this license 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 1
of the Comission's regulations and all applicable requirements have been satisfied.
8807110197 880701 PDR ADOCK 05000285 P
l
=
l
. 2.
Accordingly, Facility Operating License No. DPR 40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.115, are here'uy incorporated in the license. The licensee shall operate the facility in accordance with th6 Technical Specifications.
3.
The license amendment is effective 30 days from date of issuance in order to fully implement the revised specifications.
FOR THE NUCLEAR REGULATORY COMMISSION f,.
Jose A. Calvo, Directer Project Directorate - IV Division of Reactor Projects - III.
IV, V and Special Projects Office of Nuclear Reactor Pegulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 1, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.115 F.aCILITY OPERATING LICENSE NO. DPR-40 DOCKET N0. 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.
Remove Pages Insert Pages
~
5-1 5-1 5-la 5-la 5-lb 5-3 53 5-4 5-4 5-5 E-5 5-8 5-0 5-9 5-9 Figure 5-1 Figure 5-2
5.0 ADMINISTRATIVE CONTR01.S 5.1 Responsibility 5.1.1 The Manager - Fort Calhoun Station shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
5.2 Organization 5.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intertrediate levels to and including all operating organization positions. These relationships shall be documented and updated.
as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the USAR.
b.
The Manager - Fort Calhoun Station shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation ar.d raintenance of the plar,t.
c.
The Senior Vice President - Nuclear Operations, Production Opera-tions, Production Engineering, and Quality and Environmental Affairs shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical sJpport to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to-the appropri te onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Plant Staff The plant staff organization shall be as described in Chapter 12 of the USAR function as follows:
a.
The minimum number and type of licensed and unlicensed operating personnel required onsite for each shift shall be as shown in Table 5.2-1.
5-1 Amendment No. E3,7f,75,J0J,115
1 5.0 ADMINISTRATIVE CONTROLS 5.? Organization (Continued) b.
An Operator or Technician qualified in Radiation Protection Procedures shall be onsite when fuel isein the reactor, c.
All core alterations shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling who has no other concurrent responsi-bilities during the operation.
o.
Fire protection program responsibilities are assigned to those positions and/or groups designated by asterisks in USAR 12.1-1 through 12.1-4 according to the procedures specified in Section 5.8 of the Technical Specifications, Afirebrigadgconsistingof5membersshallbemaintainedonsite e.
at all times.
The fire brigade shall not inc1;de the minimum shift crew necessary for safe shutdcwn of the unit (2 merbers).
f.
Administrative procedures shall be developed and implemented to limit the working hours of plant staff who perform safety-related functions. Administrative procedures shall reflect the personnel whose working hours will be affected.
Shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a n0rmal 8-hour day, 40-hour week while the plant is operating.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extenced periods of shutdown for refueling, major maintenance, or ma,iw plant modifica-tions, on a temporary basis, the guidelines identified in the administrative procedures shall be followed.
Deviations from the guidelines shall be authorized by the Depart-ment Manager, Plant Manager, or their designated alternates, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Routine deviation from the administrative guidelines shall not be authorized.
g.
The Supervisor - Operations, the Shift Supervisors and Licensed Senior Operators shall hold a senior reactor operator license.
The Licensed Operators shall hold a reactor operator license.
- Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of Fire Brigade members provided irranediate action is taken to restore the Fire Brigade to within the minimum requirements.
5-la Amendment No. 7P, 54, PE,115
1 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualification 5.3.1 Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, with the exception of the Supervisor - Radiation Protection (SRP) and the Shift Technical Advisor (STA).
Th,' dne shall meet the requirements set forth in Regulatory Guide 1.0 dated September 1975, entitled "Personnel Selection and Training". The SRP is considered to meet the educational i
and experience qualifications set forth in Regulatory Guide 1.8 with at least five years of experience in applied radiation protection and extensive formal training in radiation protection. The Shift Technical Advisor shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and anal"sis of the plant for transients and accidents.
5-1b Amendment No.115
1 Figure 5-1 This Figure has been deleted.
1 Amendment No. 7E,M,93,99,115
1 figure 5-2 This figure has been deleted.
I Amendment No. $p,78.E/.101.115
5.0 ADMINISTRATIVE CONTROLS 5.4 Training 5.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Manager - Training and l
shall meet or exceed the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
(
5.4.2 A training program for the fire brigade shall be maintained under the Manager - Training and shall meet or exceed the requirements of l
Section 27 of NFPA Code-1975, except that the meeting frequently may be quarterly.
5.5 Review and Audit 5.5.1 Plant Reviev Comittee (PRC)
Function 5.5.1.1 The Plant Review Comittee shall function to advise the Manager - Fort Calhoun Station on all natters related to nuclear safety.
Composition 5.5.1.2 The official Plant Review Comittee shall be composed of the:
Chairman:
Manager - Fort Calhoun Station Member:
Supervisor - Operations Member:
Manager - Training
(
Member:
Supervisor - Maintenance Member:
Supervisor - System Engineering Member:
Manager - Safety Review Group Member:
Supervisor - Radiation Protection Member:
Plant Chemist Member:
Manager - Quality Assurance and Quality Control Alternates 5.5.1.3 Alternate members shall be appointed in writing by the Plant Review Comittee Chairman to serve on a temporary basis; however, no more than two alternates shall participate in Plant Review Committee i
activities at any one time.
Meeting Frequency 5.5.1.4 The Plant Review Comittee shall meet at least once per calendar month and as convened by the Plant Review Comittee Chairman.
Quorum 5.5.1.5 A quorum of the Plant Review Comittee shall consist of the Chairman and four members including alternates.
5-3 Amendment No. 9, JP, 3E, SA,115
5.0 ADMINISTRATIVE CONTROLS Responsibilitie-5.5.1.6 The Plant Review Comittee shall be responsible for:
a.
Review of 1) all procedures required by Specification 5.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Manager - Fort Calhoun Station to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposdd changes to the Technical Specifications, d.
Review of all proposed changes or modifications to plant systems or equipuent that affect nuclear safety.
e, investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recomendations to prevent recurrence to the Division Manager -
Nuclear Operations and to the Chaiman of the Safety Audit and l
Review Comittee, f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chaiman of the Safety Audit and Review Comittee, h.
Review of the Site Security Plan and inplementing procedures and shall submit reconmended changes to the Chaiman of the Safety Audit and Review Comittee.
i.
Review of the Site Emergency Plan and implementing procedures and shall submit recomended changes to the Chairman of the Safety Audit and Review Comittee.
j.
Review of all Reportable Events.
Authority 5.5.1.7 The Plant Review Comittee shall:
a.
Recommend in writing to the Manager - Fort Calhoun Station approval or disapproval of items considered under 5.5.1.6(a) through(d)above.
4 5-4 Amendment No. 9,19, Ef, 99,115
l 5.0 ADMINISTRATIVE CONTROLS 5.5.1.7 b.
Render determinations in writing with regard to whether or not eachitemconsideredunder5.5.1.6(a)through(e)above constitutes an unreviewed safety question.
c.
Provide immediate written notification to the Division Manager -
Nuclear Operations and the Safety Audit and Review Comittee of l
disagreement between the Plant Review Comittee and the Manager -
Fort Calhoun Station; however, the Manager - Fort Calhoun Station shall have responsibility for resolution of such disagreements pursuant to 5.1.1 above.
Records 5.5.1.8 The Plant Review Comittee shall maintain written minutes of each meeting and copies shall be provided to the Division Manager - Nuclear Operations and Chairman of the Safety Audit and Review Comittee.
[
5.5.2 Safety Audit and Review Comittee (SARC)
Function 5.5.2.1 The Safety Audit and Review Comittee shall function to provide the independent review and audit of designated activities in the areas of:
a.
nuclear power plant operation b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
instrumentation ar.d control f.
radiological safety 9
mechanical and electrical engineering h.
quality assurance Composition 5.5.2.2 The Safety Auc'it and Review Comittee shall be composed of:
Chairman:
Division Manager - Quality and Environmental Affairs Member:
Senior Vice President - Nuclear Operations, Production Operations, Production Engineering ard Quality and Environmental Affairs Member:
Division Manager - Nuclear Operations Member:
Division Manager - Production Engineering Member:
Manager - Fort Calhoun Station Member:
Manager - Emergency Planning Member:
Qualified Non-District Affiliated Consultants as Required and as Determined by SARC Chairman 5-5 Amendment N0. H 93,99,291,115
l i
l 5.0 ADMINISTRATIVE CONTROLS 5.5.2.8 e.
The Fort Calhoun Station Emergency Plan and implementing precedures at least once every twelve months.
f.
The Site Security Plan and implementing procedures at least once every twelve months.
g.
The Safeguards Contingency Plan and implementing procedures at least once every twelve months.
h.
The Radiological Effluent Program including the Radiological Environmental Monitoring Program and the results thereof, the Offsite Dose Calculation Manyal and implenenting procedures, and the Process Control Program for the solidifications of radioactive waste at least once per 2 years.
1.
Any other area of facility operation considered appropriate by the Safety Audit and Review Connittee or the Senior Vice President -
Nuclear Operations, Production Operations, Production Engineering, and Quality and Environmental Affairs.
Authority 5.5.2.9 The Safety Audit and Review Committee shall report to and advise the Senior Vice President - Nuclear Operations, Production Operations, Production Engineering, and Quality and Environmental Affairs on those areas of responsibility specified in Sections 5.5.2.7 and 5.5.2.8.
Records 5.5.2.10 Records of Safet) Audit and Review Comittee act'.vities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each Safety Audit and Review Comittee meeting shall be pre,,,ed approved and forwarded to the Senior Vice President -
Nuclear Operations, Production Oprations, Production Engineering, and Ouality Assurance and Environmental Affairs within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 5.5.2.7e, f, g, h, and i above shall be prepared, approved and forwarded to the Senior Vice President - Nuclear Operations, Production Operations, Production Engineering, and Quality Assurance and Environmental Affairs within 14 days following completion of the review, c.
Audit reports encom>assed by Section 5.5.2.8 above shall be forwarded to the Senior Vice ) resident - Nuclear Operations, Production Opera-tions, Production Engineering, and Quality Assurance and Environmental Affairs and to the responsible management positions designated by the Safety Audit and Review Comittee within 30 days after completion of the audit.
5-8 Amendment No. P/,8f,73,ISI,115
i 5.6 Reportable Event Action 1
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 Chaiman of the Safety Audit and Review Committee and the Division Manager - Nuclear Operations.
l c.
Submit reports of Reportable Events pursuant to the requirements of Specification 5.9.2.
5.7 Safety Limit Violation 5.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The unit shall be placed in at least HOT SHUTDOWN within I hour, b.
The Safety Limit Violations shall be reported to the Division Manager - Nuclear Operations and the the Chairman cf the Safety l
Audit and Review Comittee (SARC) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared. The report shall be reviewed b shall describe (1) y the Plant Review Comittee. This report applicable circumstances preceding the viola-tion, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taksn to prevent recurrence, d.
The Safety Limit Violation Report shall be submitted to the Chaiman of the Safety Audit atd Review Committee and the Division Manager - Nuclear Operations within 14 days of the violation.
l 5.8 Procedurec 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 and administrative policy of 5.8.1 above, and changes thereto, shall be reviewed by the Plant Review Comittee and approved by the Manager - Fort Calhoun Station prior to implementation and periodically as set forth in each document.
5.8.3 Temporary changes to procedures of 5.8.1 above may be made provided:
5-9 Amendment No. 9,I9,38,EA,99,115
. _.