ML20214P272

Amend 101 to License DPR-40,revising Section 5 of Tech Specs to Incorporate Recent Organizational & Job Title Changes

ML20214P272
Person / Time
Site:	Fort Calhoun
Issue date:	11/24/1986
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20214P259	List: ML20214P256 ML20214P272 ML20214P293
References
TAC-62967, NUDOCS 8612040138
Download: ML20214P272 (8)

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uq'o UNITED STATES 8" NUCLEAR REGULATORY COMMISSION

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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 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 September 26, 1986, 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 ar.d regulations of the Commission; C.

There is reasonable assurance (i) that th4 activities authorized by this amendment can be conducted,without endangering the health and safety of the public, and (ii) f. hat such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this 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 of the Commission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, Facility Operating License No. OPR-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 4

ihe Technical Specifications contained in Appendix A, as revised through Amendment No.101, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This' license. amendment is effective as of the date of its issua'nce.

FOR THE NUCLEAR REGULATORY COMMISSION

// (hk<%0W Asho C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B'

Attachment:

Changes to the Technical ,

Specifications '

s Date of Issuance: November 24, 1986 d

5

ATTACHMENT TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE NO. DPR 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.

Remove Pages Insert Pages 5 5-1 5-5 5-5 5-8 5-8 Figure 5-1 Figure 5-1 Figure 5-2 Figure 5-2 s

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5.0 . ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The flanager - 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 1

Offsite 5.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 5-1. I 5.2.2 Plant Staff The plant staff organization shall be as shown in Figure 522 and j function as follows:

a. The minimum number and type of licensed and unlicensed operating i personnel required onsite for each shift shall be as shown in Table 5.2-1.

b. An Operator or Technician qualified in Radiation Protection r procedures shall be onsite when fuel is in 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. .

d. Fire protection program responsibilities are assigned to those positions and/or groups designated by asterisks in Figures 5-1 and 5-2 according to the procedures specified in Section 5.8 of the Technical Specifications.

e. A fire brigade consisting of 5 members shall be maintained onsite at all times.' The fire brigade shall not include the minimum .

shift crew necessary for safe shutdown of the unit (2 members).

1. 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 immediate action is taken to restore the Fire Brigade to within the minimum requirements.

5-1 Amendment No. 9,J9,79,38,E3,76,7B,101

5.0 ADMINISTRATIVE CONTROLS 5.5.1.7 b. Render determinations in writing with regard to whether or not each item considered under 5.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide immediate written notification to the Division. Manager -

Nuclear Production and the Safety Audit and Review Cominittee of 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

, Production and Chairman of the Safety Audit and Review Comittee.

5.5.2 Safety Audit and Review Committee (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 and control '

f. radiological safety ,

g.

- mechanical and electrical engineerinql -

h. quality assurance Composition 5.5.2.2 The Safety Audit and Review Comittee shall be composed of:

Chairman: Division Manager - Quality Assurance and ileg"latory Affairs Member: Senior Vice President - Nuclear Production, Production l Operations, Fuels, and QA&RA Member: Vice President - Engineering and General Services Member: Division Manager - Engineering Member: Division Manager - Nuclear Production Member: OPPD Operations, Engineering, and Technical Support staff Member: Qualified Non-District Affiliated Consultants as Required and as Determined by SARC Chairman 5-5 Amendment No. 9,J9,EO,7E.SE,93,99,101

5.0 ADMINISTRATIVE CONTROLS 5.5.2.8 e. The Fort Calhoun Station Emergency Plan and implementing procedures-at least once every twelve months.

f. Tne Site Security Plan and implementing procedures at least once every twelve months.

9 The Safeguards Contingency Plan and implementing procedures at least once every twelve months.

h. The Radiological Effluent Program including the Radiological Environ-mental Monitoring Program and the results thereof, the Offsite Dose Calculation Manual and implementing procedures, and the Process Control Program for the solidification of radioactive wastes at least once per 2 years.

1. Any other a ea of facility operation considered appropriate by the-Safety Audit and Review Committee or the Senior ViceJeesident - I Nuclear Production, Production Operations, Fuels, and Quality Assurance & Regulatory Affairs.

Authorig 5.5.2.9 Tne Safety Audit and Review Committee shall report to and advise the Senior Vice President - Nuclear Production, Production Operations, Fuels, l and Quality Assurance & Regulatory Affairs on those areas of responsi-bility specified in Sections 5.5.2.7 and 5.5.2.8.

Records '.

5.5.2.10 Records of Safety Audit and Review Commititee activities shall be prepared, approved and distributed as indicated below:

a. Minutes of each Safety Audit and Review Committee meeting shall be prepared, approved and fontarded to the Senior Vice President - I Nuclear Production, Production Operations, fuels, and Quality Assurance & Regulatory 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 l President - Nuclear Production, Production Operations, Fuels, and Quality Assurance & Regulatory Affairs within 14 days following completion of the review.

c. Audit reports encompassed by Section 5.5.2.8 above shall be forwarded to the Senior Vice President - Nuclear Production, Production Opera- i tions, Fuels, and Quality Assurance & Regulatory Affairs and to the responsible management positions designated by the Safety Audit and Review Conmittee within 30 days after completion of the audit.

5-8 Amendment No. 9,J9,3E,60,76,SA,SE,93, 101

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