ML20034H226
| ML20034H226 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/11/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034H227 | List: |
| References | |
| NUDOCS 9303160204 | |
| Download: ML20034H226 (8) | |
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i UNITED STATES :
NUCLEAR REGULATORY COMMISSION
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E; WAStilNGTON,0. C. 20555 -
' ' R... f NEBRASKA PUBLIC POWER 01 STRICT DOCKET NO. 50-298.
COOPER NUCLEAR-STATION-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.160 c,
License No. DPR-46 ti 1
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated October 8, 1992, complies with the standards and
.i requirements of the Atomic Energy Act of 1954, as amended (the.Act),-
- l and the Commissian's rules and regulations s~et forth in 10 CFR -
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Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and. regulation; of the.
Commission;--
,j 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
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' conducted in compliance with the. Commission'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
~l public; and 1
E.
The issuance of this amendment is in accordance.with 10 CFR Part 51 l
of the Commission's regulations and all: applicable. requirements have--
been satisfied.
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Accordingly, the licenst is amended by_ changes _ to the Technical Specifi-cations as indicated in the attachment to this license amendment and-L Paragraph 2.C.(2) of facility Operating License No. DPR-46 is:hereby i
amended to read as follows:
2.
Technical Specifications.
The Technical-Specifications contained in Appendix A, as revised through Amendment No.160, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the i
Technical Specifications.
q 3.
The license amendment is effective as of its date of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION f
) & C f Y v 4" George -. Hubbard, Acting Director Project Directorate IV-1 Division of Reactor Projects Ill/IV/V
-i Office of Nuclear Reactor Regulation
Attachment:
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Changes to the j
Technical Specifications Date of Issuance:
March 11, 1993 r
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ATTACHMENT TO LICENSE AMENDMENT NO. 160
'l FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 l
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and j
contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 219
'219 l.!
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220 220 221 221
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r 223 223 l
227 227 l
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6.0 ADMINISTRATIVE CONTROLS "6.1
'QESANIZATION 6.1.l Etsoonsibility The Plant Manager is directly responsible for the safe and efficient operation of the plant by providing direction for operation, radiological, engineering, an'd maintenance support activities. The Plant Manager reports to the Site Manager who has overview and coordination responsibility for ensuring the safe and efficient operation of Cooper Nuclear Station.
During periods of time when
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the Plant Manager is unavailable, his responsibilities automatically shift to the Senior Manager of Operations. During periods of time when the Plant i
Manager and the Senior Manager of Operatione are not available, the responsibilities of the Plant Mansger may be delegated in writing to one of the managers on the Cooper Nuclear Station Site staff qualified.for this position.
6.1.2 offsite and Onsite creanizations 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 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 of documentation. These requirements shall be documented i
in the USAR.
B. The Site Manager shall have overview and coordinate the activities of the following positions:
B.1 The Plant Manager who is responsible for overall safe unit operation and who has control over those onsite activities necessary for safe operation and maintenance of the plant.
B.2 The Senior Manager of Site Support who is directly responsible for supporting the safe and efficient operation of the plant by providing direction for training, outage and modification coordination, station security, and administrative support.
C. The Nuclear Power Group Manager shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, c.aintaining, and providing technical support to the plant to ensure nucienr safety.
D. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressurcs.
6.1.3 Plant Staff - Shift Complement TLe shift complement at the station shall at all times meet the following requirements. Note: Higher grade licensed operators may take the place of j
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.
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B. A licensed reactor operator shall be in the control room at all times when I
there is any fuel in the reactor.
C. Two licensed reactor operators shall be in the control room during all i
startup, shutdown and other periods involving significant planned control rod manipulations. A licensed SRO shall either be in the Control Room or immediately available to the Control Room during such periods.
Am2ndment No. E, S 2, S 3,99,131,1??,150, 160-219-
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6.2 REVIEW AND AUDIT 6.2.1 The organization and duties of committees for the review and audit of station operation shall be as outlined below:
A.
Station Operations Review Committae (SORC) 1.
SORC shall have a minimum of eight voting members comprised of the following:
a.
Chairman: Plant Manager, or alternate l.
b.
Individuals from the fo11owin5 disciplines:
Operations 1
Radiological (Chemistry / Health Physics)
Maintenance Engineering 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-18.1 1971, " Selection and Training of Personnel 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 serte 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 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.
c.
Review propoced changes to Technical Specifications.
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 10CFR50.59(c).
Submit changes to equipment or systems having safety significance' to the NPPD Safety Review and Audit Board for review.
e.
Review station operetion to detect potential nuclear safety hazards.
Amendment No. SO M,85,99,100,122,
-220-T 160
l 6.2 (cent'd) f.
Investigate all violations of Technical Specifications, including 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 10CFR Part 50.
1.
Review drills on emerEency 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 a.
The Station Operations Review Committee shall be advisory.
b.
The Station Operations Review Committee shall recommend to the SORC Chairman approval or disapproval of proposals under items 4, a through e and j above. In case of disagreement between the recom-mendations of the Station Operations Review Committee and the Plant Manager, the course determined by the Plant Manager to be the more conservative will be followed. A written summary of the disagreement will be sent to the Site Manager, Nuclear Power Group Manager, and l
to the NPPD Safety Review and Audit Board.
c.
The Station Operations Review Committee shall report to the Chairman of the NFPD Safety Review and Audit Board on all reviews and inves-tigations conducted under items 4.f. 4.g. 4.h, and 4.i.
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d.
The Station Operations Review Committee shall make determinations regarding whether or not proposals considered by the Committee involve unreviewed safety questions. This determination shell be subject to review by the NPPD Safety Review and Audit Board.
6.
Records:
Minutes shall be kept for all meetings of the Station Operations Review Committee and shall include identification of all documentary material reviewed. Copies of the minutes shell be forwarded to the Chairman of the NPPD Safety Review and Audit Board and the Nuclear Power Group Manager vitbin one month.
7.
Procedures:
Written administrative procedures for Committee operation shall be prepared and maintained describing the nothod for submission and content of presentations to the committee, provisions for use of subcommittees, review and approval by members of written Committee evaluations and recommendations, dissemination of minutes, and such other matters as may be appropriate.
Amendment No. 80, S2 SS, SS,100,102,122,
-221-160
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Proposed. tests or experiments which involve an unreviewed c.
safety question as defined in Section' 50.59, 10 CFR.
d.
Proposed changes to Appendix A Technical Specifications or the j
CNS Operating License.
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e.
Violations of applicable codes, regulations, orders. Technical Specifications, license requirements, or of internal _ procedures-
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or instructions having nuclear safety-significance.
.l3 f.
Significant operating abnormalities or deviations from normal.
and expected performance of plant equipment that affect nuclear safety.
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g.
All reportable events specified in Section 50.'73 to 10CFR Part l
50.
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h..
Any indication of an unanticipated deficiency in some aspect of':
design or operation of safety related structures, systems, or -
'l components.
i.
Minutes of meetings of the Station Operations Review Committee.
-f.
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Disagreement between the recommendations of the Station Opera '
tions Review Committee and the SORC Chairman.
k.
Review of events covered under e,f,g, and h above. ' include.
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.reportin5 to appropriate members of management on the results j
of investigations and recommendations to prevent or reduce the probability of recurrence.
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S.
Authority: The NPPD Safety Review and Audit Board shall report to and be
'l advisory to the Nuclear Power Group Manager on those areas of responsi-j bility specified in Specifications 6.2.1.B.4 and 6.2.1.B.7..
.i 6.
Records:
j Minutes shall be recorded for all meetin5s of the NPPD Safety Review and
- i Audit Board and shall identify'all documentary material reviewed. Copies-of the minutes shall be forwarded to,the Nuclear _ Power Group Manager,;
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4 Site Manager, and the Plant Manager,_and such others as the Chairman may s
designate within one month of the meeting.
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7.
Audits:
Audits of selected aspects of plant operation shall be performed under.
the co5nizance of SRAS with a frequency commensurate _vith their safety significance. Audits' performed by the Quality Assurance Department'which.
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meet this specification shall be' considered to meet the SRAB audit-1 requirements if the audit results'are; reviewed by SRAB. A representative
'I portion of procedures and records of the activities performed during the4 audit period shall be audited and, in~ addition,. observations of.perfor--
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mance of operating and maintenance activities shall be included. - These
.J audits shall encompass q
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.1 Amendment No. SO '6'd, SS,102,124 7
-223--
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6.3 (cant'd) 6.3.5 Temporary Chances
' Temporary changes to procedures which do not change the intent of the original procedure may be made, provided such changes are approved by two members of the operating staff holding.SR0 licenses. Such changes shall be l
documented and subsequently reviewed by the Plant Manager within one month.
l 6.3.6 Exercise of Procedures Drills of the Emergency Plan procedures shall be conducted annually, including a check of communications with offsite support groups. Drills on
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the procedures specified in 6.3.2.A, B, and C above shall be conducted as part of the retraining program.
6.3.7 fragtags The following programs shall be established:
A.
Systems Intecrity Monitorine Procram A program shall be established to reduce leakage to as low as' practical levels from systems outside the primary containment during a serious; accident that would or could contain highly radioactive fluids. This program shall include provisions establishing preventive maintenance and periodic visual inspection requirements, and leak testing require-i ments for each system at a frequency not to exceed refueling cycle intervals.
B.
Iodine Monitorint Prorram A program shall be established to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include training of personnel, procedures for monitoring and provisions for maintenance of sampling and analysis equipment.
C.
Fost-Accident Samuline System (PASS)
A program shall be established to ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions. This program shall include training of personnel, proce-dures for sampling and analysis and provisions for operability of -
sampling and analysis equipment.
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