ML20033F977
| ML20033F977 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/19/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20033F978 | List: |
| References | |
| NUDOCS 9004040176 | |
| Download: ML20033F977 (9) | |
Text
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e UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION
.e W ASHINGTON, D. C. 20666 i
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. DPR-46 1.
The Nuclear Regulatory Connission (the Consission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensce) dated July 31, 1989 as suppleniented December 13, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Consission's rules and regula-tions set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Consission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized 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 Consnission'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 1
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have I
been satisfied.
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2.
Accordingly, the license is anended 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-46 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.132, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
'AY c.
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Frederick J. Hebdon, Director Project Directorate IV Division of Reactor Projects - Ill, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Chenges to the Technical Specifications Date of Issuance:
March 19, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO 132 j
FACILITY OPERATING LICENSE NO. DPR-46 l
DOCKET NO. 50-298 Replace the'following pages of the Appendix A Technical Specifications with the. enclosed pages. The revised pages are identified by Amendment number and L
contain vertical lines indicating the area of change, Paoes i
219 219a 220 221 223 234 t
L D
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t 6.0 eMtNISTRATIVE CONTRott 6.1 OPCANIZATION 6,1,1 Petrensibility The Division Manager of Nuclear Operations shall have the over.all fulltime onsite responsibility for the safe operation of the Cooper Nuclear Station.
During periods when the Division Manager of Nuclear Operations is unavailable, this responsibility automatically shifts to either the Senior Manager of Operations, or the Senior Manager of Technical Support Services (in that order).
During periods when none of these individuals are available, the responsibility may be delegated in writing'to one of the managers in the Nuclear Operations Division.
)
6.1.2 Offsite and Onsite Orranizations 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 from the highest management levels through intermediate levels to and including all operating organization positions.
These relationshi'ps 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 of documentation.
These requirements shall be documented in the USAR.
B.
The Division Manager of Nuclear Operations shall be responsible for overall unit safe operation and shal) have control over those ensite activities necessary for safe operation and maintenance of the plant.
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C.
The Nuclear Power Group Manager shall have corporate responsibility for l-overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and t
providing technical support 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 apprcpriate onsite manager; howeve r, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.1.3 Plant Staff Shift comelement The shift complement at the station shall at all times meet the following 1
requirements. Note: Higher grade licensed operators may take the place of lower grade licensed or unlicensed operators.
A.
A licensed senior reactor operator (SRO) shall be present at the station at all times when there is any fuel in the reactor.
B.
A licensed reactor operator shall be in the control room at all times I
when there is any fuel in the reactor.
C.
Two licensed reactor operators shall be in the control room during all startup, shutdown and other periods involving significant planned control red manipulations. A licensed SRO shall either be in the Control Room or immediately available to the Control Room during such periods.
Amendient No. 66,82,55,99, M,132 219-
D.
A lic:nsed sent:r r0 ct3r operat:r (SRO) with no cther sencurt;nt dutics chsil be directly in th:rge af cny refueling cperation, cr citeratien cf the react 3r esto.
4 A Iftensed reactor operator (RO) with no other concurrent duties shall be directly in charge of operations involving the handling of irradiated fuel other than refueling or reactor core alteration aparations.
E.
An individual who has been trained and qualified in health physics techniques shall be on site at all times that imi is on site, i
T.
Minimum crew site during reacter operation shall consist of four licemed i
reactor operators (rvo of whom shall be licensed SRO) and three unlicensed operators. Minimum crew sise during reactor sold shutdown conditions shall consist of two licensed reactor operators (one of whom shall be licensed SRO) and one unlicensed operator.
1
. In the event that any member of a minimum shift crew is absent or incapacitated due to 111mse or injury a qualif designated to report onsite within two hours..ied replacement shall be C.
A Fire Brigede of at least 5 members shall be maintaimd at all times.
This excludes the 3 members of the minimus shift crew necessary for safe shutdowns, and other personnel required for other essential functions during a fire emergency. Three fire Brigade members shall be from the Operations Department and 2 support sesbers may be from other departments inclusive of Security personnel,.
Tire 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 immediate action is taken to restore the Fire Brigade to within the minimum requirements.
H.
The Operations Supervisor, Shif t Supervisor and Control Room Supervisor shall hold a senior reactor operator-license. The Unit Operators shall hold, at a minimum, a reactor operator license.
l.
A Shift Technical Advisor shall be available, except during cold l
shutdown conditions, to serve in an advisory capacity to the shift crew on satters pertaining to the engineering aspects assuring safe operation of the plant.
6.1.4 Plant Staff. Qualificariana i
The minimum qualifications, training, replacement training, and retraining of plant personnel at the time of fuel leading or appointment to the active positions shall met the requirements as described in the Anerican National Standards Institute N.18.1 1971
" Selection and Training of Personnel for Nuclear Power Plants".
The Radiological Manager shall meet or exceed the qualifications of Regulatory Guide 1.8 Sept. 1975, personnel qualification equivalency as stated in the Regulatory Guide may be proposed in selected cases.
The minimum frequency of the retraining program shall be every two years.
The training program shall be under the direction of the Training Manager.
).
A.
A training program for the fire brigade will be maintained under the L
direction of the Training Manager and shall meet or exceed the I
iequirements of Section 27 of the NTPA Code 1976, except for Fire Brigade training sessions which shall be held at least quarterly.
The training program requirements will be provided by a qualified fire protection engineer.
8.
The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in plant design, and response and analysis of the plant for transients and accidents.
h Amendment No. 80,E2,85,f37, 2198-132 l
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j 6,2 trvirW AND AUDIT I
6.2.1 The organization and duties of committees for the review and audit of station operation shall be as outlined below:
A.
Statien Deerations Review Committee (SORC) 1.
SORC shall have a minimum of eight voting members comprised of the following:
a.
Chairman: Division Manager of Nuclear Operations, or alternate b.
Individuals from the following disciplines:
Operations Radiological (Chemistry / Health Physics)
Maintenance Engineeping Reactor Engineering Instrumentation and Control The above, according to individual job title, shall meet the requirements as described in Sections 4.2, 4.3.1, or 4.4 of the American National
Standards Institute N.18.11971. " Selection and Training of Personne1~ for Nuclear Power Plants."
Non voting members may also serve on SORC to broaden its expertise in other areas (e.g., Quality Assurance).
All alternate members shall be appointed in writing by the SORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SORC at any one time.
- 2. Meeting Frequency: Monthly, and as required on call of the Chairman.
3.
Quorum:
SORC chairman plus such a number as to constitute a majority of the voting members.
4 Responsibilities:
a.
Review all proposed normal, abnormal, maintenance and emergency i
operating procedures specified in 6. 3.1, 6. 3. 2, 6.3. 3, and 6. 3.4 and proposed changes thereto:
and any other proposed procedures or changes thereto determined by any member to effect nuclear safety.
b.
Review all proposed tests and experiments and their results, which involve nuclear hazards not previously reviewed for conformance with technical specifications.
Submit tests which may constitute an unreviewed safety question to the NPPD Safety Review and Audit Board for review.
Review proposed changes to Technical Specifications.
c.
d.
Review proposed changes or modifications to station systems or equipment as discussed in the USAR or which involves an unreviewed safety question as defined in 10CTR50.59(c).
Submit changes to equipment or systems having safety significance to the NPPD Safety Review and Audit Board for review.
Review station operation to detect potential nuclear safety hazards.
e.
Amendment No. 80,82,85,77,100,132 2:0
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. 6,2 -(c:nt'd) f.
Investigate all violations of Technical Specifications, including s
reporting evaluation and recommendations to prevent recurrence, to the Nuclear Power Group Manager and to the Chairman of the NPPD l,
Safety Review and Audit Board.
g.
Perform special reviews and investigations and render reports-thereon as requested by the Chairman of the Safety Review and Audit
- Board, h.
Review all reportable events specified in Section 50.73 to 10CTR Part 50.
P i.
Review drills on emergency procedures (including plant evacuation) and adequacy of communication with off site groups.
J.
Periodically review procedures required by Specifications 6.3.1, 6.3.2, 6.3.3, and 6.3.4 as set forth in administrative procedures.
5.
Authority The Station Operations Review Committee shall be advisory.
a.
b.
The Station Operations Review Committee shall recommend to the 50RC Chairman approval or disapproval of proposals under items 4, a through e and j above.
In case of disagreement between the recommendations of the Station Operations Review Committee and the Division Manager of Nuclear Operations, the course determined by the Division Manager of Nuclear Operations to be the more conservative will be followed. A written summary of the disagreement will be sent to the Nuclear Power Group Manager and to the NPPD Safety Review and l
Audit Board, The Station Operations Review Committee shall report to the Chairman c.
of the NPPD Safety Review and Audit Board on all reviews and investigations conducted under items 4.f. 4.g. 4.h, and 4.1, d.
The Station Operations Review Committee shall make determinations l
regarding whether or not proposals considered by the Committee l
involve unreviewed safety questions.
This determination shall be l
subject to review by the NPPD Safety Review and Audit Board.
6.
Records:
L Minutes shall be kept for all meetings of the Station Operations Review Committee and shall include identification of all documentary material i
l reviewed. Copies of the minutes shall be forwarded to the Chairman of I
the NPPD Safety Review and Audit Board and the Nuclear Power Group Manager within one month.
L 7.
Procedures:
1-Written administrative procedures for Committee operation shall be l
prepared and maintained describing the method for submission and content i
of presentations to the committee, provisions for use of subcommittees, review and approval by members of written Committee evaluations and recorr endations, dissemination of minutes, and such other matters as may be appropriate.
221 Amendment No. 80,82,85,86,100, 102,132
F
'6.2, (cent'd)
Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CPR.
d.
Proposed changes to Appendix A Technical Specifications or the l
CNS Operating License.
Violations of applicable codes, regulations, orders. Technical e.
Specifications, license requirements, or of internal procedures I
or instructions having nuclear safety significance, j
f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
All reportable events specified in Section 50.73 to 10CPR Part I
50.
h.
Any indication of an unanticipated deficiency in some aspect of l
design or operation of safety related structures, systems, or components, i.
Minutes of meetings of the Station Operations Review Committee...
J.
Disa&reement between the recommendations of the Station Operations Review Committee and the 50RC Chairman.
l' '
k.
Review of events covered under e,f,g, and h above include reporting to appropriate members of management on the results of investigations and recommendations to prevent or reduce the i
probability of recurrence.
5.
Authority: The NPPD Safety Review and Audit Board shall report to and be acvisory to the Nuclear Power Group Manager on those areas of
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responsibility specified in Specifications 6.2.1.S.4 and 6.2.1.B.7.
6.
Records:
Minutes shall be recorded for all meetings of the NPPD Safety Review and Audit Board and shall identify all documentary material reviewed. Copies of the minutes shall be forwarded to the Nuclear Power Group Manager and
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the Division Manager of Nuclear Operations, and such others as the Chairman may designate within one month of the meeting.
7.
Audits:
t Audits of selected aspects of plant operation shall be performed under the cogni:ance of SRAB with a frequency commensurate with their safety significance. Audits performed by the Quality Assurance Department which meet this specification shall be considered to meet the SRAB audit i
requirements if the audit results are reviewed by SRAB.
A representative j
portion of procedures and records of the activities performed during the audit period shall be audited and, in addition, observations of performance of operating and maintenan:e activities shall be included.
These audits shall encompass:
. Amendment No. 80,82,85,102,132 223' I
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6.5.2 Petertable Events l,
A Reportable Event shall be any of those conditions specified in Section l
50.73 to 10CTR Part 50. The NRC shall be notified and a report submitted pursuant to the requirements of Section 50.73.
Each Reportable Event j
shall be revieved by SORC and the results of this review shall be submitted to SRAB and the Nuclear Power Croup Manager.
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. Amendment No. 86,87,102,132 234
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