ML20078D698

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Amend 202 to License DPR-49,revising TS to Clarify Requirement for Audit Conformance to Ts,Deletes Requirement for Safety Committee Oversight of Audits of Emergency Plan & Security Plan & Allows Designation of Signature Authority
ML20078D698
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 11/02/1994
From: Hsia A
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20078D701 List:
References
NUDOCS 9411070341
Download: ML20078D698 (5)


Text

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UNITED STATES

.g NUCLEAR REGULATORY COMMISSION

't WASHINGTON, D.C. 20666 0001-4, s/

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IES UTILITIES INC.

CENTRAL IOWA POWER COOPERATIVE

[0RN BELT POWER COOPERATIVE DOCKET NO. 50-331 DVANE ARN0LD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-49 i

1.

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

A.

The application for amendment by IES Utilities Inc., et al., dated June 30, 1994, 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 wil'l operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 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.

2.

Accordingly, the license is amended 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-49 is hereby amended to read as follows:

9411070341 941102 PDR ADOCK 05000331 P

PDR L

(2)

Technical Soecifications

(

The Technical Specifications contained in Appendix A, as revised through Amendment No. 202, 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 the date of issuance and shall be implemented within 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Anthony H.

sia, Project Manager Project D ectorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: November 2, 1994

ATTACHMENT TO LICENSE AMENDMENT NO. 202 FACli.ITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised areas are indicated by marginal lines, j

i Remove Insert 6.5-8 6.5-8 6.8-2 6.8-2 4

DAEC-1 8.

Procedures required by the plant Security Plan.

9.

Operation of radioactive waste systems.

10.

Fire Protection Program implementation.

11.

A preventive maintenance and periodic visual examination program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient to as low as practical levels.

This program shall also include provisions for performance of periodic systems leak tests of each system once per OPERATING CYCLE.

12.

Program to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions, including training of personnel, procedures for monitoring and provisions for maintenance of sampling and analysis equipment.

13.

Administrative procedures for shift overtime for Operations personnel to be consistent with the Commission's June 15, 1982 policy statement.

14.

OFFSITE DOSE ASSESSMENT MANUAL.

15.

PROCESS CONTROL PROGRAM.

16.

Quality Control Program for effluents.

6.8.2 Procedures described in 6.8.1 above, and changes thereto, shall be reviewed by the Operations Committee as indicated in Specification 6.5.1.6 and approved by the Plant Superintendent-Nuclear or designee prior to implementation, except as provided in 6.8.3 below.

6.8.3 Temporary minor changes to procedures described in 6.8.1 above which do not change the intent of the original procedure may be made with the concurrence of two members of the plant management staff, at least one of whom shall hold a senior operator license.

Such changes shall be documented and promptly reviewed by the Operations Committee and by the Plant Superintendent-Nuclear or designee.

Subsequent incorporation, if necessary, as a permanent change, shall be in accord with 6.8.2 above.

6.8 ?

Amendment No. 109,J26,128,JA3,JEJ,

)??.202

V~

DAEC-1 1.

Reports and meeting minutes of the Operations Committee.

6.5.2.8 Audits Audits of facility activities shall be performed under the cognizance of the Safety Committee. These audits shall encompass:

a.

The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b.

The performance, training and qualifications of the facility staff at least once per 24 months.

c.

The results of actions taken to correct deficiencies occuring in l

facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.

d.

The performance of activities required by the Quality Assurance l

Program to meet the criteria of Appendix "B", 10CFR50, at least once per 24 months.

e.

Deleted f.

Deleted Amendment No. B5,202 6.5-8

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