ML20093D541

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Amend 87 to License DPR-46,revising Tech Specs to Incorporate Requirement to Document Challenges to Relief Valves or Safety Valves
ML20093D541
Person / Time
Site: Cooper Entergy icon.png
Issue date: 09/19/1984
From: Vassallo D
Office of Nuclear Reactor Regulation
To:
Nebraska Public Power District (NPPD)
Shared Package
ML20093D543 List:
References
DPR-46-A-087, TAC 51674 NUDOCS 8410110278
Download: ML20093D541 (5)


Text

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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMEN 0 MENT TO FMILITY OPERATING LICENSE Amendment No. 87 License No. DPR-46 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Nebraska Public Power District dated April 27, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter,1; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of tht:

Comission; C.

There is reasonable assurance (1) 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 conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicabic requirements have been tatisfied.

2.

Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachr"ent 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 Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorpordted in the license.

The licensee shall operate the facility in accordance with the Technical Specificatior,s.

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This license amendment is effective as of its'date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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fc t-Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the, Technical Specifications Date of Issuance: September 19, 1984 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Revise the Appendix A Technical Specifications as follows. The revised areas are indicated by marginal lines.

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FEACTOR WATER LEVEL IfolCATION CORRELATION I

Amendment NO. 87 n.

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'A tabulation on an annuai wis of the nurber of station, utility and other personnel (including contractors) re-ceiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, 1/ e.g., reactor operations and surveillance, 1-inservice inspection, routine maintenance, special cain-tenance (describe maintenance), vaste processing, and refteling.. The dose ~ assignment to;various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totaling less than 20%

of the individual total dose need not be accounted for.

In the aggregate, at least 80% of the total whcle body dose received from external sources shall be assigned to specific major work functions.

2.

A summary description of facility changes, tests or experi-ments in accordance with the requirements of 10CFR50.59(b).

3.

Pursuant to 3.8.A.

a report of ' radioactive source leak testing.

This report is required only if the. tests reveal the presence of 0.005 microcuries or more of removable contamination.

4.

Docu=entation of all challenges to relief valves or safety valves.

D.

Monthly Operatine Report-Koutine reports of operating statistics, shutdowr. experience, and a narrative suc=ary of operating experience relating to safe operation of the facility, shall be submitted on a monthly basis to the individual designated in the current revision of Reg.

Guide 10.1 no later than the tenth of each month following the calendar month covered by the report.

6.5.2 Reeortable Events A Reportable Event shall be any of those conditions specified in Secticn 50.73 to 10CFR Part 50.

The NRC shall be notified and a report submitted pursuant to the requirements of Section 50.73.

Each Reportable Event chall be reviewed by SORC and the results of this review shall be submitted to SRAB and the Assistant General Manager - Nuclear.

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This tabulation supplements the requirements of $20.407 of 10CFR Part 20.

Amendment No. 87

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