ML19209B025
| ML19209B025 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/18/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209B022 | List: |
| References | |
| NUDOCS 7910090015 | |
| Download: ML19209B025 (2) | |
Text
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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE N0. OPR 46 DOCKET NO. 50-298 Replace page 219 and 219a of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Ameninent number an'd contain vertical lines indicating the area of change.
1119 264 O
19100P
g 6.0 ADMINISTRATIVE CONTROLS 6.1 Orzani:ation 6.1.1 The S ta: ion Superintendent shall have the over-all full:1=e ensite responsibility for the safe operation of the Cooper Nuclear Station.
During periods when the Station Superintendent is unavailable, he
- &y delegate his responsibili
- y to the Assistant to S:ation Superintendent or, in his absence, to one of the Depart =ent Supervisors.
6.1.2 The portion of the Nebraska Public Power Distric: =anage=ent which relates to the opera: ion of this station is shown in Figure 6.1.1.
6.1.3 The organization for conduct of opera: ion of :he sta:1on is shown in Fig. 6.1.2.
The shift co=ple=ent at the station shall at all ti=es
=eet the follewing require =en:s.
Note: Eigher grade licensed operators
=ay 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 :i=es when there is any fuel in the reac:or.
3.
A licensed reac:or operator shall be in the control roo= at all ti=es when there is any fuel in the reactor.
C.
Two licensed reactor operators shall be in the control roo=
during all startup, shutdown and other periods involving signif-icant planned control red =anipulations. A licensed SRO shall either be in the Contro: Roo= or i=nediately available to the Con:rol Roo= during such periods.
D.
A licensed senior reactor opera:or (SRO) w1:h no c:her concur-duties shall be directly in charge of any refueling opera-rent
- 1on, or alteration of :he reac:or core.
A 11:ansed reac:or operator (RO) w1:h no other concurrent duties shall be directly in charge of operations involving the handling of irradiated fuel othe: chan refueling or reac:or core alteration operations.
E.
An individual who has been trained and qualified in health physics techniques snall be on site at all ti=es tha: fuel is on site.
F.
Mini =u= crew si:e during reactor operation t ha11 consist of three licensed reactor operators (one of who= shall be licensed SRO) and ro unlicensed opera: ors.
Eini=u= crew si:e during reac:or _ _.d shu:down conditions shall consist of two licensed reactor opera: ors (one of who= shall be licensed SRO) and one unlicensed operator.
In the even: :ha: any =e=ber of a =ini=u= shif: crew is absent or incapaci:ated due :o illness or injury a qualified replace-nen: shall be designa:ed :o report on-si:e vichin rwo hours.
-219-1119 265
s G.
A Fire Brigade of at least 5 members shall be maintained at all times. This excludes the 3 members of the minimum 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 members may be from other departments inclusive of Security personnel.
i 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 acconnodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.
6.1. 4 The minimum qualifications, training, replacement training, and retraining of plant personnel at the time of fuel leading or appointment to the active position shall meet the requirements as described in the American National Standards Institute N18.1-1971,
" Selection and Training of Personnel for Nuclear Power Plants".
The Assistant to Station Superintendent qualificatior.s shall comply with Section 4.2 of ANSI-N18.1-1971. The Chenistry and Health Physics Supervisor shall meet or exceed the cualifications 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 re' training program shall be every two years. The training program shall be under the direction of a designated member of the plant staff.
A.
A training program for the fire brigade will be maintained under the direction of the plant training coordinator and shall meet or exceed the requirements of Section 27 of the NFPA Code 1976, except for Fire Brigade training sessions which shall be held at least quarterly.
The training program requirements will be provided by a quali-fled fire protection engineer, thru the Risk Manager.
1119 266
-219a-
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7590-01 UNITED STATES NUCLEAR' REGULATORY C0tNISSION DOCKET NO. 50-298 NEBRASKA PUBLIC PDWER C? STRICT NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regu)atory Commission (the Commission) has issued Amendment No. 59 to Facility Operating License No. DPR 46, issued to Nebraska Public Power District, which revised the Technical Specifications for operation of the Cocper Nuclear Station, located in Nemaha County, Nebraska.
The amendment is effective as of the date of issuance.
The amendment modifies the Technical Specifications t require a five ran fire brigade.
The Safety Evaluation related to this change was issued on May 23,1979 along with Amendment No. 56 to License tie. DPR-46.
The application for the amendment complies with the st4ndards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Prior public notice of this amendment was not required since the amendment does not involve a significant ha ards consideration.
The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR Section 51.5(d)(4), an environmental impact statement or negative declaration and-environmental impact appraisal need not be prepared in connection with issuance of this amendment.
Ii19 267
7590-01 For further details with respect to this action,- see (1) the formal application for amendment dated July 17,1979,(2) Amendment No. 59 to License No. OPR-46, and (3) the Commission's letter to the licensee dated September 18, 1979. All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N. W., Washington, D. C. and at the Auburn Public Library,118 - 15th Street, Auburn, Nebraska 68305. A copy of items (2) and (3) may be obtained upon recuest addressed to the U. S. Nuclear Regulatory Commission, Washington, D. C.
- 20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland, this 18 day of September 1979.
FOR THE NUCLEAR REGULATORY COMMISSION
, Chief Operating Reactors Branch #3 Division of Operating Reactors 1119 268
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