ML20070E041

Proposed Tech Specs,Clarifying Requirements for Audit of Conformance to Tss,Deleting Requirement for Safety Committee Oversight of Audits & Allowing Designation of Signature Authority

ML20070E041
Person / Time
Site:	Duane Arnold
Issue date:	06/30/1994
From:	IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20070E039	List: ML20070E041 NG-94-1595, Application for Amend to License DPR-49,clarifying Requirement for Audit of Conformance to Tss,Deleting Requirement for Safety Committee Oversight of Audits & Allowing Designation of Signature Authority
References
NUDOCS 9407140028
Download: ML20070E041 (4)

Text

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l RTS-268 Attachment 2 to NG-94-1595 Page 1 of 1 PROPOSED CHANGE RTS-268 TO THE DUANE ARNOLD ENERGY CENTER

_ JECHNICAL SPECIFICATIONS The holders of license DPR-49 for the Duane Arnold Energy Center propose to amend Appendix A (Technical Specifications) to said license by revising the attached pages as indicated below.

LIST OF AFFECTED PAGES 6.5-8 6.8-2

SUMMARY

OF CHANGES:

The following list of proposed changes is in the order that the changes appear in the Technical Specifications.

• Page Description of Changes 6.5-8 Revise 6.5.2.8.a, b, c and d to clarify the requirements and to make them consistent with Regulatory Guide 1.33.

Delete the requirement for Safety Committee involvement in the audits of the Emergency Plan and Security Plan consistent with Generic Letter 93-07.

6.8-2 Capitalize the defined term OPERATING CYCLE in 6.8.1.11.

Add provision to allow the Plant Superintendent- I Nuclear to designate signatory authority for <

procedure approval in Sections 6.8.2 and 6.8.3.

1 These changes are consistent with the BWR/4 Draft Improved Technical ,

Specifications, NUREG-1433. j 1

1 9407140028 940630 PDR ADOCK 05000331 p PDR

DAEC-1 1

Recor:s and meeting minutes of the Operations Comittee.

6.5.2.8 Audits Audits of facility activities shall be' performed under the cognizance of the Safety Comittee. These audits shall encomoass:

a. TheconformanceoffacilityoperationtM isions contained within the Technicaj_5pecifications and applicable license conditions

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at least once perg, \1.1 months.

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

c.

The results ofhactions taken to correct deficiencies occuring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months. '

d.

The performance o -en etivities required by the Quality Assurance Program to meet the criteria of Appendix "S",10CFR50, at least once per 24 months.

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e. The Em:rg: :y "!= v.d ir.,,1;r.;n:ing pr;;; dure: :: 10;:tance p:r 12--

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he 5:=H ty a!= =d 1 ;;l;;an:ing pr;; dar;; :t 1::tt : :: p:r 12 -

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RTS-EG6 olo /94 6.5-8 Amendment No. 95

DAEC-1

8. Procedures required by the plant Security Plan.

9. Operation of radioactive waste systems.

10. Fire Protection Program implementation. 1 1

11. A preventive maintenance and periodic visual examination program

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to reduce lea'k age 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 er.formance-4 odic systems leak tests of each,.

OPERATING C system once per peratipg-cycle. '

12. Program to ensure the capability to accurately determine the  !

airborne iodine concentration in vital areas under accident i 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. a 6.8.2 Procedures described in 6.8.1 above, and changes thereto, shall be h

-reviewed by the Operations Committee as indicated in Specification 6.5.1.6 and approved by the Plant Superintendent-Nucle 3 ior to implementation, except as provided in 6.8.3 below. or h573"**

.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 revi , _ Operations Committee and by, j the Plant Superintendent-Nuclenrg ent incorporation, if necessary, as a permanent chang , shall'belin accord with 6.8.2 above.

AMENDMENT NO.JD),J26,J28,JA3,JU,199 6.8-2 RTS-%8-g 94

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RT'S-268 Attachment 3 to NG-94-1595 Page 1 of 1 Safety Assessment Introduction By letter dated June 30, 1994, IES Utilities Inc. (IES) submitted a request for revision of the Technical Specifications (TS) for the Duane Arnold Energy Center (DAEC). The proposed changes will improve the effectiveness of the organization supporting DAEC by eliminating unnecessary administrative burden. The specific changes are to clarify the Safety Committee Audit requirements in Section 6.5.2.8.a, b, c, and d; delete the requirement for Safety Committee involvement in audits of the Emergency and Security Plans in Section 6.5.2.8.e and f; and to add provision for the Plant Superintendent-Nuclear designation of signature authority for approval of plant procedures in Sections 6.8.2 and 6.8.3. These changes are consistent with the draft Improved Technical Specifications for BWR/4 plants, NUREG-1433 and the guidance contained in Generic Letter 93-07.

Assessment The proposed changes to DAEC TS will simplify administrative requirements. The changes to the audit requirements will allow more focused reviews by the safety Committee, thereby increasing effectiveness. The allowance for designation of authority for procedural approval will relieve the Plant Superintendent-Nuclear of the burden of approving all plant procedure changes.

These changes will not result in any degradation of administrative controls. They will result in simplifications of existing processes which will ultimately allow more focused audits and procedure reviews at a more appropriate level.

Based on the above information, we have concluded that the proposed changes to the DAEC TS are acceptable.

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'TS-26B Attachment 4 to I NG-94-1595 l Page 1 of 1 j l

3 ENVIRONMENTAL CONSIDERATION  !

10 CFR 51.22(c)(9) identifies certain licensing and regulatory actions l which are eligible for categorical exclusion from the requirement to  !

perform an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents  !

that may be released offsite; and (3) result in an increase in individual or cumulative occupational radiation exposure. IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:

F Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:

<. As demonstrated in Attachment 1 to this letter, the proposed Amendment does not involve a significant hazards consideration.

2. The proposed Amendment includes changes to the Administrative Controls section. No changes in plant design or operational strategies will be made as a result of these changes; thus, there will be no increase in either the types or amounts of effluents that may be released offsite.

3. The proposed Amendment includes changes to the Administrative Controls section requirements for audits and procedure reviews. No changes in either plant design or operational strategies will be made as a result of these changes; thus, there will be no significant increase in either individual or cumulative occupational exposure.

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