NG-97-2114, Transmits Change to Rev 9 of Ies Util,Inc QA Program Description for Duane Arnold Energy Center.Changes to Rev 19 of QAPD Submitted

Transmits Change to Rev 9 of Ies Util,Inc QA Program Description for Duane Arnold Energy Center.Changes to Rev 19 of QAPD Submitted

ML20198M903
Person / Time
Site:	Duane Arnold
Issue date:	01/05/1998
From:	Franz J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	Collins S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NG-97-2114, NUDOCS 9801200157
Download: ML20198M903 (7)

Text

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IES Utilities Inc.

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• 200 First Street SE. l V

e P.O. Box 351 Cedar Rapods, IA 52406-0351 i

TelerMne 319 398 8162 Fax 319 398 8192 UTILITIES ,,,,, , ,,, ,.

Mce Pressdent, t+xtear January 5,1998 NO-97-2114 Mr. Samuel Collins, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Document Control Desk i

Mail Station Pl-37 Washington, DC 20555-0001

Subject:

Duane Arnold Energy Center Docket No. 50-331 Operating License DPR-49 Reporting of Changes to the Quality Assurance Program Description, UFSAR 17.2 l

File: A-116, A-365, Q-98

References:

QAPD Submittal of September 25,1997, NG-97-1348 {

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Dear Mr. Collins:

This letter transmits changes to Revision 19 of the IES Utilities Inc. Quality Assurance Program Description (QAPD) for the Duane Arnold Energy Center (DAEC). Revision 19 to the QAPD was submitted on September 25,1997 in accordance with the requirements of 10CFR ,

50.54(a)(3). The chang:s included with this submittal remove unnecessary text from settions relocated from the Technical Specifications to the QAPD.

This submittal includes the following changes to Revision 19 of the QAPD:

• removed unnecessary text (see attached page 17.2A-11, paragraph 6.14.9) regarding ,

the preventive maintenance program to make the QAPD consistent with the wording in the Technical Specification,

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• clarified basis of shift overtime for Operations personnel to be the Technical l

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Specifications (see attached page 17.2A-11, paragraph 6.14.11). This change makes 1 the text consistent with the approved Technical Specification.

• added " Process Control Program" as a procedure requiring the review of the Operations Committee (see attached page 17.2A-11, paragraph 6.14.12). ,

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Attachment 1 to this submittal is the revised page 17,2.A-11 of UFSAR Section 17.2 ,;

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_(QAPD) Appendix A.'

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. Attachment 2 to this submittal is the revised Discussion of Changes for item Number 8 2 ^

T which replaces the previous discussion which was included in our submittal of -

1 September 25,' 1997 as NG-97 1348.- 1; n

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2These' changes will be incorporated into Revision 19 of the IES Utilities Inc. QAPD andi  !

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' included in the next UFS AR update in accordance with' 10 CFR 50.71e.

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. Very truly yours, ,

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ohn P. Franz .

4< Vice President, Nuclear . y 5

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Attachments: Revised page 17.2.A-ll of UFSAR Section 17.2 (QAPD) Appendix A'

' Revision 19, date to be determined D cc: L. Roo

. K. Peveler

' D. Jantosik i A. B. Beach,(NRC Region III)

L G. Kelly (NRC - NRR)

.- S. Black (NRC - QA)

. NRC Resident Office .,

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t Attachment 1 Changes to UFSAR 17.2 Page 17.2A-11 Only

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approved in the NRC Safety Evaluation Report, BWROG EPG, Revision 4, September

.-1988.

6.14 The following procedures and changes thereto, shall be reviewed by tne Operations Committee as indicated in Section 6.4 above and approved by the Plant Manager,  ;

Nuclear or designee prior to implementation, except as provided in Section 6.7 above:

1. Normal startup, operatloa, and shutdown of systems and components of the facility.

2. Refueling operation.

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

4. Emergency and off-normal condition procedures. The emergency operating i procedures required to implem-nt the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stateo ,n Generic Letter 82-33.

5. Preventive and corrective maintenance operations which could have an effect on the nuclear safety of the facility. ,

6. Surveillance and testing requirements of equipment that could have an effect on the nuclear safety of the facility.

7. Operation of radioactive waste systems.

8. Fire Protection Program implementation.

9. A preventive maintensnce and periodic visual examination program to reduce leakage from systems outside containment that would or could contain highly radioactive fMds during a serious transient to as low as practicallevels. This program shall also include provisions for performance of periodic systems leak tests of each system once per operating cycle.

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

11. Administrative procedures for shift overtime for Operations personnel as specified in Technical Specifications.

12. Process Control Program.

17.2 A 11 Revision 19 to be determined

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Attachment 2 i

e Discussion of Changes in the Quality Assurance Program Description

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.,t Attachnwn 2 NG 97 2114

8. UFPAR 17.2, Appendix A, Section 6.14 h

Previous requirements stated in Technical Specification 6.8.2 are incorporated into UFSAR 17.2, Appendix A Section 6.14 to indicate that plant procedures and changes thereto are reviewed and approved prior to implementation:

The following procedures and changes thereto, shall be reviewed by the Operations Committee as indicated in Section 6.4 above and approved by the Plant Manager, Nuclear or designee prior to implementation, except as provided in Section 6.7 above:

1. Normal startup, operation, and shutdown of systems and components of the facility, b 2. Refueling operation.

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.

4. Emergency and off normal condition procedures. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in Generic Letter 82-33.

5. Preventive and corsective maintenance operations which cou'd have an effect

- on the nuclear safety of the facility.

6. Surveillance and testing requirements of equipment that could have an effect on the nuclear safety of the facility.

7. Operation of redioactive waste systems.

8. Fire Protection Program implementation.

9. 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 practicallevels. This program shall also include provisions for performance of periodic systems leak tests of each system once per operating cycle.

10. Program to ensure that capability to accurately determine the airbome lodins concentration in vital areas under accident conditions, including training of personnel, procedures for monitoring and provisions for maintenance of sampiing and analysis equipment.

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A'tachment 2 NO 971114

11. Administrative procedures for shift overtime for Operations personnel as .\

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specified in Technical Specifications.

12. Process Control Program.

Reason for the Chanoo: (Reference ITS Relocate # R9)

In support of implementing Improved Technical Specifications (NUREG-1433), current Technical Specifications requirements regarding the review of procedures prior to implementation (TS 0.8.2) are relocated to UFSAR 17.2, A.ppendix A, Section 16.4.

There is no change in the requirement, only the location where it is stated.

Basis for Concludina that Channe Continues to Satisfy 10 CFR 50 Anoendix B and Pflylous QA Proaram Commitments The commitment for the Operations Committee to review selected procedures prior to implementation remains unchanged. The relocation of the requirement for the Operations Committee to review selected procedures prior to implementation from the Technical Specifications to UFSAR 17.2, Appendix A. Section 6.14 consolidates the description of the administrative functions of the Committee, and provides an additional level of detail in the OAPD. The commitment to ANSI N 18.7, Section 5.2.15 remains unchanged regarding the review and approval of procedures prior to implementation.

Additionally, the commitment to 10 CFR 50, Criterion V remains unchanged regarding the review and approval of procedures.

This change is not a reduction h commitment.

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