ML20129K380

Ack Receipt of Re Proposed Changes to QA Program Description.Rev Continues to Meet Requirements of 10CFR50, App B & Acceptable

ML20129K380
Person / Time
Site:	Duane Arnold
Issue date:	11/14/1996
From:	Kropp W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Leslie Liu IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
References
NUDOCS 9611220147
Download: ML20129K380 (37)

Text

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Ibvember 14, 1996 Mr. Lee Liu Chairman of the Board, President, and Chief Executive Officer IES Utilities incorporated 200 First Street S. E.

P.O. Box 351 Cedar Rapids, IA 52406-0351

Dear Mr. Liu:

Thank you for your 10 CFR 50.54(a) submittal dated November 12,1996, which proposed changes to your Quality Assurance Program description. This submittal supersedes your March 18 and August 14,1996, submittals. Your submittal proposed changes to your supplier evaluation program, lead auditor certification requirements, and your organization.

We have reviewed the changes associated with this submittal. We understand that the organization chart shown in Figure 13.1-1 of your submittal will be modified to show a dashed line between the Manager, Corporate Quality Assurance, and the Vice President, Nuclear, to reflect the reporting relationship between the two positions. This understanding was discussed between Mr. David J. Jantosik of your staff and Mr. Ronald A. Langstaff of this office on November 13,1996. Based on our review of ,

your submittal, we conclude that this revision continues to meet the requirements of  !

10 CFR Part 50, Appendix B, and is acceptable.

We appreciate your timely submittal of information required by 10 CFR 50.54(a). If there are changes to quality assurance commitments existing in docketed correspondence outside of the Quality Assurance Program description, you are obligated to notify this i office. Please contact Mr. Langstaff of my staff at (630) 829-9747 with any questions you may have regarding this matter.

Sincerely, Original cigned by Andrew Dunlop for j Wayne J. Kropp, Chief Engineering Specialists 1 ,

Docket No. 50-331

Enclosure:

IES Utilities ltr NG-96-2432 fm Franz to NRC dtd 11/12/96 See Attached Distribution DOCUMENT NAME: G:\DRS\DU A111_6.D RS To receive a copy of this docurnent, indicate in the box *C" = Copy without attach /enct *E" = Copy with attach /enci *N* = No copy OFFtCE Rlli 6 Rlli _

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l L. Ju cc w/ encl: G. Van Middlesworth, Plant Manager K. E. Peveler, Manager, Licensing and Emergency Planning

! Chairperson, Iowa Utilities Board Distribution:

Docket File w/ encl DRS w/encI A. B. Beach, Rlil w/ encl PUBLIC IE-01 w/ encl Rlli PRR w/ encl Enf. Coordinator, Rlll w/enci OC/LFDCB w/ encl SRI, DAEC w/enct CAA1 w/enci (E-mail)

I DRP w/ encl LPM, NRR w/enct W. L. Axelson, Rlll w/enct R.A. Gramm, NRR '

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IES Utihties Inc.

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200 First Street S.E.

Do. Box 351 Cedar Raords. IA $2C6-0351 Telephone 319 398 8162 Fax 319 398 8192 UTILITIES ,,,,,,,,,, ,,

November 12,1996 Vice President. Nuceear NG-96-2432 l Mr. Frank J. Miraglia, Director

! Office of Naclear Reactor Regulation l

U.S. Nuclear Regulatory Commission Attn: Document Control Desk l i Mail Station P1-37 Washington, DC 20555-0001

Subject:

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

Reference:

1) January 30,1996 letter from Stephen D. Floyd of the Nuclear Energy Institute to Suzanne C. Black of the Nuclear Regulatory l Commission.

2) March 18,1996 letter (NG-96-0096) from John J. Franz of IES Utilities to William Russell of the Nuclear Regulatory Commission.

3) August 14,1996 letter (NG-96-1683) from John F "mnz of IES Utilities to William R. Russell of the Nuclear RequisArv Commission.

4) October 24,1996 letter from Suzanne C. Black of the Nuclear Regulatory Commission to Stephen C. Cloyd of the Nuclear Energy Institute.

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

Dear Mr. Miraglia:

This letter transmits three changes to Revision 16 of the IES Utilities Inc. Quality Assurance Program Description (QAPD) for the Put 1e Amold Energy Center in accordance with the requirements of 10 CFR Sectica 50.54(a)(3). These three changes were previously provided by references 2 and 3 and have now been revised to incorporate the results of reference 4. In addition, respcnsibility for the resolution of conflicts on quality matters have been added in response to

! concems expressed by the reviewer.

l This submittalincludes the following changes:

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! Mr. Frank J. Miraglia l NG-96-2432 Page 2 l

l l . Regulatory Guide 1.144 (ANSI N45.2.12 - 1977) requires suppliers to be evaluated annually. This submittal replaces the annual supplier evaluation with an ongoing supplier evaluation process.

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. ANSI N45.2.23-1978 requires an auditor to participate in a minimum of five l (5) audits prior to certification as a lead auditor. This submittal recognizes l the performance attributes required for an individual to be considered for lead l- auditor certification. This performance based approach to lead auditor certification may require more than, or less than five (5) audits for -

certification.

. The Manager, Corporate Quality Assurance previously reported to the Vice President, Nuclear and now reports to the Manager, Regulatory

Performance.

Attachment 2 to this submittal discusses the identification of changes in the -

QAPD, the reasons for the changes, and states the basis for concluding that the program continues to satisfy the criteria of 10 CFR Part 50, Appendix B.

Attachment 3 to this submittal is a mark-up of UFSAR Chapter 13.1, " Conduct of Operations" which reflects the current organizational structure and incorporates changes since the previous 10 CFR 50.71(e) submittal.

j These three changes will be incorporated into Revision 17 of the IES Utilities Inc.

, QAPD as part of the next UFSAR update in accordance with 10 CFR 50.71(e).

Very truly yours,

,hn F. Franz Vice President, Nuclear

! JJF/KEP/JMG/hjf Attachments: 1) Affected pages from the DAEC UFSAR, Chapter 17.2, 6 Revision 17, date to be determined.

l 2) Discussion of Changes in the Quality Assurance Program Description.

3) Mark-up of UFSAR Section 13.1," Conduct of Operations".

l cc: L Root l K. Peveler At B. Beach, (NRC - Region lil)

G. Kelly (NRC - NRR) i NRC Resident Office

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Attachment 1 Affected pages ficm the DAEC UFSAR Chapter 17.2, Revision 17, date to be determined.

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Attachment 1

- NG-96-2432 The responsibility and authority for the establishment and execution of the Operational Quality i Assurance Program for the operation of the DAEC will be retained by lES Utilities Inc.

!. 17.2.1.2 Manager, Regulatory Performance  !

l The Manager, Regulatory Performance reports to the Vice President - Nuclear and is

responsible for quality essurance, emergency planning and nuclear licensing functions.

j Reporting to the Manager, Regulatory Performance are the Manager, Corporate Quality i Assurance, Manager, Emergency Planning and Supervising Engineer, Licensing.

17.2.1.3 Manager, Corporate Quality Assurance i

The Manger, Corporate Quality Assurance reports to the Manager, Regulatory Performance j and is assigned the primary responsibility for ensuring that quality requirements relative to the l l safe operation of the DAEC are identified and met. The Manager, Corporate Quainy Assurance  :

1 also has the authority and organizational freedom to directly access the Vice President -

1 Nuclear regarding quality matters. The Manager, Corporate Quality Assurance is responsible for elevating conflicts regarding quality matters with the Manager, Regulatory Performance to the Vice President, Nuclear for resolution.

l l Fulfilling the responsibilities of the Corporate Quality Assurance Department requires significant i communication with the DAEC, the Nuclear Licensing Department, the Emergency Planning

Department, the Nuclear Business Unit, the Engireering Department, the Training Department, and the Purchasing Department.

! The Manager, Corporate Quality Assurance.is responsible for preparing, approving and

maintaining the Operational Quality Assurance Program and the Quality Assurance Department

- implementing procedures.

l The Manager, Corporate Quality Assurance is also responsible for evaluating the effectiveness 3

of the Operational Quality Assurance Program and issuing periodic reports to the appropriate

levels of management. Effectiveness of the Operational Quality Assurance Program at the  !

_ DAEC is determined through intemal audits and surveillances and through analysis and

trending of reported conditions adverse to quality. The Manager, Corporate Quality Assurance also provides support for the procurement of materials and equipment through audits, j surveillances, and evaluations of suppliers and contractors for quality capabilities and

performance and maintains the list of approved suppliers for nuclear procurements.

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' Training responsibilities include the training of Quality Assurance Department personnel and Nuclear Generation Division personnel relative to the Operational Quality Assurance Program.

l The Manager, Corporate Quality Assurance provides direct support to the nuclear Safety

Committee and assures that Quality Assurance Department personnel are designated to i support the Operations Committee.

17.2 0

/ Revision 17 Date to be determmed i

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t j 18.2 Section 1.1, " Scope", and Section 1.2, " Applicability", of ANSI N45.2.12-1977 3

reference ANSI N45.2. IES Utilities Inc. is committed to ANSI N18.7-1976 for the f operational phase, consistent with its commitment to Regulatory Guide 1.33.

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! 18.3 Regulatory Position C.3.b(1) states that extemal audits, after the award of a contract, are not necessary for procurement actions where acceptance of the product is in accordance with Section 10.3.2," Acceptance by Reviewing Inspection", of ANSI

N45.2.13-1976. The suppliers of products that meet this requirement are included on the IES Utilities Inc. extemal audit schedule and are audited on a triennial basis.

18.4 ANSI N45.2.12, Section 4.3.1 " Pre-Audit Conference" t

For internal audits, a " pre-audit planning meeting" may be substituted for the " pre-

, audit conference." The pre-audit planning meeting should accomplish the following:

L 1) The Lead Auditor to present the proposed audit plan and an opportunity for the audited organizations to provide input to the proposed audit plan, j 2) Introduce the Lead Auditor and identify proposed audit team members. Those

! audit team members available will be introduced. Note: Non-utility team

members are usually not available at these meetings.

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3) Counterparts are invited to these audit planning meetings as part of the planning l' process.

4) The audit schedule is presented, including a tentative exit date. The final exit i date is announced separately during the audit period.

5) The channels of communication are opened at the audit planning meeting through participation in the audit planning process.

l 6) Following the audit planning meeting, the Lead Auditor will finalize the audit plan.

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18.5 in lieu of an annual supplier evaluation specified by Regulatory Position C.3.b(2), a i documerned ongoing evaluation of the supplier should be performed. Where

! applicable, this evaluation should take into account (1) review of supplier-fumished

i. documents such as certificates of conformance, non-conformance notices, and

corrective actions, (2) results of previous source verifications, audits, and receiving j inspections, (3) operating experience of identical or similar products furnished by the j same supplier, and (4) results of audits from other sources, e.g., customer, ASME, or i NRC audits. The results of the evaluations should be reviewed and appropriate

corrective action should be taken. Adverse findings resulting from these evaluations i should be periodically reviewed in order to determine if, as a whole, they result in a j significant condition adverse to quality and to provide input to support supplier audit activities conducted by lES Utilities or a third party auditing entity.

17.2 A-13 i Revision 17 T6 be determined

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l 19,0 REGULATORY GUIDE 1.146. " Qualification of Quality Assurance Proaram Audit i Personnel for Nuclear Power Plants"

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l 4 COMMENTS AND CLARIFICATIONS:  ;

i lES Utilities Inc. complies with the Regulatory Position of this Regulatory Guide with j the following clarifications: i l: 19.1 ' The IES Uti!ities Inc. commitment is to Regulatory Guide 1.146, August 1980, and to .

ANSI N45.2.23-1978 which it endorses.

19.2 ANSI N45.2.23 Section 1.2 references ANSI N45.2. For IES Utilities Inc., the entities 4

subject to audit are defined in 10 CFR 50 Appendix B and ANSI N18.7-1976. This is

, consistent with IES Utilities Inc.'s commitment to Regulatory Guide 1.33 which l j endorses ANSI N18.7-1976, in lieu of ANSI N45.2.

i 19.3 in lieu of ANSI N45.2.23 Section 2.3.4, prospective lead auditors shall demonstrate j their ability to effectively implement the audit process and effectively lead an audit team. This demonstration process shall be described in written procedures or

instructions. The demonstration shall be evaluated and the results documented.

I Regardless of the methods used for the demonstration, the prospective lead auditor

shall have particip 2ted in at least one nuclear quality assurance audit within the year i preceding the individual's effective date of qualification. Upon successful i demonstration of the ability to effectively implement the audit process and effectively

lead audits, and having met the other provisions of Section 2.3 of ANSI N45.2.23 -

1978, the individual may be certified as being qualified to lead audits.

i 20.0 REGULATORY GUIDE 1.155. " Station Blackout"

! COMMENTS AND CLARIFICATIONS:

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! IES Utilities Inc. complies with Appendix A," Quality Assurance Guideline for Non-l Safety Systems and Equipment," to Regulatory Guide 1.155, Revision 1, August 1988.

'21.0 REGULATORY GUIDE 4.15. " Quality Assurance for Radiological Monitorina Proarams j (Normal Ooerations) - Effluent Streams and the Environment" i COMMENTS AND CLARIFICATIONS l IES Utilities Inc. complies with the Regulatory Position in Regulatory Guide 4.15, i

Revision 1, February 1979.

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i i 17.2 A-14 i- Revision 17 To be determined 4

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22.0 ASME B&PV Code.Section XI.1980 Edition with Addenda through Winter 1981 4

COMMENTS AND CLARIFICATIONS:

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The IES Utilities Inc. commitments relative to the Ten-Year inspection Program and the Pump and Valve Test Program are established separately in formal correspondence with the Nuclear Regulatory Commission and incorporated into

, appropriate IES Utilities Inc. documents.

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17.2 A-15 Revision 17 To be determined

Attachment 2 Discussion of Changes in the Quality Assurance Program Description 4

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1 i Attachment 2

, NG-96-2432 i

Discussion of Changes in the Quality Assurance Program Description 1

, Identification of Change: l i

! The DAEC current commitment to Regulatory Guide 1.144 Revision 1 1980 (c.3.b.2) is

! m follows:

l i A documented evaluation of the supplier should be performed annually. Where l applicable, this evaluation should take into account (1) review of supplier-i fumished documents such as certificates of conformances, nonconformance notices, and corrective actions, (2) results of previous source verifications, audits, and receiving inspections, (3) operating experience of identical or similar products fumished by the same supplier, and (4) results of audits from other sources (e.g., customer, ASME, or NRC audits).

i The DAEC revised commitment is stated in the revised 17.2 A-13 paragraph 18.5 (of

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this submittal).

i Reason for Change:

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l DAEC has developed more effective and efficient practices for conducting the reviews l recommended in Regulatory Guide 1.144 Revision 1,1980. The DAEC's operating experience and the operating experience of other licensee's is included in supplier evaluations (as applicable). As a Nuclear Procurement issues Committee (NUPIC) j member the DAEC receives significant information as a result of audits performed by

other members. The significant information is included in the supplier evaluation process on a real time basis. An additional annual review is an unnecessary resource i burden because the function and purpose of the review has already been accomplished.

l Reliance for effective control over supplier quality is better placed on real time j evaluations than by deferring reviews to one selected time frame, i

i These activities may result in some supplier evaluations being performed more j frequently than annually to address the operating experience, etc. (categories of l information identified above), and for some suppliers the evaluation period may be

j. extended, commensurate with actual procurement activity.

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! Basis for Concluding the Change Continues to Comply with 10 CFR 50

Appendix B and Previous Commitments:

I 10 CFR 50 Appendix B, Criterion Vil, " Control of Purchased Material, Equipment and Services", requires:

$ "The effectiveness of the control of quality by contractors and subcontractors shall be j assessed by the applicant or designee at intervals consistent with the importance, l complexity, and quantity of the product or services.'

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Attachment 2

' NG-96-2432 l

i Discussion of Changes in the Quality Assurance Program Description I

This requirement continues to be met through the performance of an on-going evaluation system versus a delayed process of an annual evaluation. Existing DAEC practices are

performing the function described in Regulatory Guide 1.144 Revision 1,1980 more j effectively and efficiently through an on-going evaluation process.

! I Other considerations supporting the basis for the change are:

1. Nuclear Energy Institute (NEI) Prepared Improvements to Quality Assurance l l Program (NEI letter dated January 30,1996 to Suzanne C. Black of the Nuclear l Regulatory Commission).

2. Letter dated October 24,1996, from Suzanne C. Black of the NRC to Stephen Floyd j (NEI). 'l This change is a reduction in commitment. The evaluation function is being performed in a more efficient, effective and productive manner that enhances safety through a more expedient assessment of potential deficiencies.

2.0 Page A-13; Position 19.3 on Regulatory Guide 1.146 t

Background:

i The process of becoming a Lead Auditor is defined by ANSI N45.2.23-1978,

! " Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants"

] as endorsed by NRC Regulatory Guide 1.146 of August 1980. This standard also j incorporates the requirements of ANSI N45.2.12 which defines the process by which audits are performed.

As defined by ANSI N45.2.23, the process of becoming Lead Auditor certified is essentially composed of three parts:

-*- Candidate's prior education and experience, professional accomplishments, and some

, discretion by management in regards to the candidates maturity, etc., to achieve 10 or i more points within the system defined by section 2.3.1.

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Attachment 2 NG-96-2432 Discussion of Changes in the Quality Assurance Program Description l i

I e Candidate receives, or is evaluated and found to already have, knowledge of quality

, assurance program requirements as defined by section 2.3.3. This section addresses

! knowledge and understanding of ANSI N45.2 standards, and other applicable i standards, general understanding of 10 CFR 50 Appendix B, auditing techniques, and 1 j audit planning. Then as stated by section 2.3.3.5, on-the-job training is required to demonstrate an understanding of the audit process. The lead auditor candidate is also required to take an examination to evaluate the candidate's knowledge of these j requirements.

i e The candidate is required to demonstrate their capabilities by participation in the

performance of audits as defined by section 2.3.4.

From the above chronology, the process oflead auditor qualification is composed of prior knowledge and experience, knowledge obtained in the quality assurance processes, and I

demonstrated performance. This approach to lead auditor qualification is a systematic approach and ensures an individual has demonstrated their ability to lead audits prior to being lead auditor certified. Section 2.3.4, " Audit Participation" currently states: "The Prospective Lead Auditor shall have participated in a minimum of five (5) quality

assurance audits within a period of time not to exceed three (3) years prior to the date of

qualification, one audit of which shall be a nuclear quality assurance audit within the year

! prior to his qualification." In addition, there are other approaches that address the same j objective, based on the candidate being able to demonstrate competency as a lead auditor. l l Identification of Change: l l Section 2.3.4 is replaced with:

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" Prospective Lead Auditors shall demonstrate their ability to effectively implement the g audit process and effectively lead an audit team. Upon successful demonstration of the ,

j ability to effectively implement the audit process and effectively lead audits and having 4 met the other provisions of Section 23 of ANSI N45.2.23-1978, licensee management j may certify the individual as a Lead Auditor." This prospective Lead Auditor shall have j participated in at least one nuclear quality assurance audit within the year preceding the

individuals effective date of qualification.

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Attachment 2  !

NG-96-2432 Discussion of Changes in the Quality Assurance Program Description l l

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Reason for Change: l Currently, section 2.3.4, ANSI N45.2.23 for Audit Participation does not ensure a lead auditor has the necessary skills prior to certification. The standard requires

" participation" in five audits and does not require a prospective lead auditor to demonstrate their skills as a lead auditor during the five audits in which they

" participate". An individual may have related experience and be capable of demonstrating their skills to lead an audit in less than five audits, but the standard does ,

not permit a licensee to certify such an individual until the individual had " participated"  !

in at least five audits. The objective of this section of the standard is for the prospective )

lead auditor to demonstrate the ability to lead audits. The prospective lead auditor may )

, need less than, or more than, five audits to demonstrate adequate on-the-job performance for certification depending on the abilities of the individual.

As the nuclear industry moves into the performance based regime for audits, many utilities have established rotation programs, or similar programs to broaden personnel experience by working in different areas, e.g., auditing. These individuals are generally l capable of demonstrating their ability to effectively lead audits in less than five audits, but because of the restrictive nature of section 2.3.4 of ANSI N45.2.23, they must continue to be supervised to comply with these provisions. This is unnecessary and is not an effective utilization oflicensee resources.

Licensee management should be permined to assess the performance of the prospective lead auditor against the knowledge and performance criteria described in the ANSI standards; knowledge of the audit process, knowledge of the licensee's quality assurance program, knowledge of the requirements of 10 CFR 50 Appendix B, knowledge of applicable and pertinent sections ofindustry standards, the candidates demonstrated performance in implementing the audit process (including leading), demonstrated oral and written communication skills, and demonstrated interpersonal skills interacting with other departments within the Company or supplier organizations.

Basis for Concluding the Change Continues to Comply With 10 CFR 50 Appendix B and Previous Quality Assurance Program Commitments:

The proposed change continues to require demonstrated performance by the individual prior to certification as a lead auditor but provides management the flexibility to certify the individual, once the skills have been demonstrated. This is consistent with 10 CFR 50 Appendix B, criterion II, Quality Assurance Program, which requires a program be defined for the indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintained. This 4-

Attachment 2 NG-96-2432 Discussion of Changes in the Quality Assurance Program Description l

is also consistent with 10 CFR 50 Appendix B, criterion XVIII, Audits, which requires  ;

audits to be performed by appropriately trained personnel.

Other considerations supporting the basis for change are:

1 Nuclear Energy Institute (NEI) Proposed Improvements to Quality Assurance Program (NEI letter dated January 30,1996 to Suzanne C. Black of the Nuclear Regulatory Commission).

2. Letter dated October 24,1996 from Suzanne C. Black of the NRC to Stephen Floyd (NEI).

This change is a reduction in commitment.

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Attachment 3 Mark-up of USFAR 3ection 13.1,

" Conduct of Operations" r

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l'FS AR/DAEC-1 i

Chapter 13 CONDUCT OF OPERATIONS l 13.1 ORGANIZATIONAL STRUCTURE OF IES UTILITIES. INC.

l IES Utiliti s. Inc. (formerly Iowa Electric Light and Power Company) is responsible for all station operations from the start of preoperational testing and is responsible for using properly licensed personnel to operate the plant. Technical assistance and direction during the preoperational testing, initial core loading. startup, and precommercial testing was provided by i Bechtel Corporati~on (Bechtel) and the General Electric Company (GE). Technical assistance is made available as required during plant operation.

l l The DAEC Plant Manager is responsible for the safe, reliable, and efficient operation of the facility. He has a staff of trained and properly licensed personnel to accomplish all of the various plant functions and disciplines. All phases of plant operation are performed in accordance with written and approved operation, maintenance, radiation protection. and emergency procedures. These procedures factor in all available experience encountered in the startup and operation of earlier boiling-water reactor (BWR) plants. Significant operations. tests, and pertinent information are recorded and a file of these records is maintained.

. A training program to qualify the staff to satisfy the then existing Atomic Energy Commission (AEC) license requirements for the initihl fuel loading, preliminary testing, and commercial operation was carried out. Training, retraining, and licensing has continued after

startup to ensure an adequate number oflicensed operators and properly trained replacement

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personnel for all disciplines.

a.4 A Safety Committee has been established to advise the President 3 Chief Operating-en+

Chief ri.. .c.dr.1 Officeron the status of nuclear safety and make recommendations regarding major procedure, facility, and license modifications, and to conduct periodic safety reviews on the site. An Operations Committee consisting of plant supervisory personnel makes l recommendations to the DAEC Plant Manag:r, reviews plant operations in detail, and approves procedure changes involving nuclear safety. Records of the proceedings of both committees are 4

maintained.

13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION l

j l 13.1-1 Revision 12.- 10/95

LTSAR/DAEC-1 13.1.1.1 Design and Ooerating Resoonsibilities

l 13.1.1.1.1 Design and Operating Responsibilities - Project Phase The Design and Operating responsibilities for the DAEC during the project phase were described in Section 1.1.2.1 of the original FSAR.

13.1.1.1.2 Technical Support for Operations Management and technical responsibility for the operation of the DAEC resides in the

. Nuclear Generation Division. This Division is responsible for the integration oflicensing.

engineering and technical support, and operation of the DAEC. The Engineering Department within the Nuclear Generation Division is responsible for providing engineering and technical l support for the DAEC.

l DAEC depends on consultant assistance from specialized consulting companies. Work i activities are authorized by the Vice President, Nuclear, or his designated alternate. Work may 1

. be authorized by purchase order or letter. l Offsite senior management resources are readily available by virtue of the proximity of l the DAEC to the IES Utilities, Inc. corporate offices.

13.1.1.2 Organizational Arrangement __

. 13.1.1.2.1 Corporate Organization k l IES Utilities, Inc., which is a subsidiary ofIES Industries, In , is organized into divisions, departments, groups, and committees, which are uniqu ntities that have been assigned specific responsibilities. The corporate organizational gement is shown in Figure 13.1-1. The Vice President, Nuclear and4he-We P;c:1&nt, Tdaial Seccice: d their -

-respec:voorgamzations.and the Safety Committee, report to the Presidenta hie Operating-and.

Chief rinc.mia Officer and have responsibilities that are germane to the safe operation of the DAEC.

2 Chairman of the Board and Chief ExMutive Officer --w h MWhA The Chairman of the Board and Chief Executive Officer.ofIES Industries, Inc. as ~ ~I l

general supervision of the Company's business affairs and perfor by the Board of Directors and the Executive Committee.

l 13.1-2 Revision 12 - 10/95 l

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UFSAR/DAEC-1 J -

l Presideng Chief Onerating -d Chief"n=dd Officer gyggg 4 J a l The President,, Chief Operating =d Chief T:s.cis! Officer off.ES Utilities. Inc. directs i

the Company's affairs. subject to policies and directives formulated by the Board of Directors 4

and Executive Committee.

M l The President a Chief Operating rd Chief Fr=:!:! Officer assigns to other corporate officers the authority to conduct the Company's operations. He is responsible for all of the  ;

operating. maintenance, and facility expansion activities in the Company. l 1

% responsibilities JMW WO include, btrt are ot limit

&fm to: the management of engm.eering.

l design. construction and contractual execution of all expansion or revisions of physical plant

facilities; the management of all electrical generation facilities, including fuel supply to support these functions; and the management of all gas department activities, including the wholesale i purchases of same. l

$JMis responsible l&& for all me etmg afid -

O&^ Og4, comptercial activities and for the inter-Company i relations, including wholesale sales and purchases, other utility and REA relations, and Regional j and/or business and professional organizational participation. l

' *sd-l The Presidentghief Operating ; .d Chkf T: mm.:o! Officer endorses the Operational

• Quality Assurance Proged % Se esp :!S!!!:y =d sic-i:j f:: d:::v!:r =d :p;rer2!

vf a Operad'5hai yuaihy n;;e;..:- P c;;= E!: f.=::!:n i: : - -- :=:n ::vi: V :: :!:--

Cunetion. f*,

j l 13.1.1.2.2. Nuclear Generation Division Organintion 4

l Vice President. Nuclear The Vice President. Nuclear reports to the President, Chief Operating "' ' ""

! Officer. The Nuclear Generation Division Organization is shown in Figure 13.1-1.

The primary responsibility of the Vice President. Nuclear is the safe operation of the i

DAEC. Other responsibilities include, but are not limited to, the following:

i 1 1. Managing the Nuclear Generation Division, which is responsible for:

I l a. Operation and maintenance of the DAEC

b. Regalatory agency interfaces and relations.

l 13.1-3 Revision 12 - 10/95 i

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9-a 1

UFSAR/DAEC-1 l

) c. Licensing activities.

j d. Emergency planning activities.

e. Nuclear fuel management activities.

i

f. Nuclear facility engineering activities including consultive or special engineering requirements and the special consultant support that may be necessary to ensure the most effective operation.

g. Training of nuclear personnel.

l h. Outage planning and scheduling.

2

2. Maintaining relationships and integration with the co-owners of the nuclear facilities.

]

j / ~ Assistant Vice President. Nuclear 4

(

d The Assistant Vice President, Nuclear reports to the Vice President, Nuclear an l ;ierforms certain activities delegated by the Vice President. The Assistant Vice President acts in l behalf of the Vice President in his absence: - -

! 13.1.1.2.2.1 Duane Amold Energy Center I

To achieve the objective of safe operation of the DAEC, the Nuclear Generation Division 4

has been given specific assignments for operation, engineering, licensing, and emergency planning, and the procurement of nuclear fuel. These responsibilities are distributed among the i organizations within the division. These include the Engineering Department. Nuclear Licensing l Department, Emergency Planning Department Nuclear Training Department. Outage and l( Support Group, Business Unit and the Duane Arnold Energy Center (see Figure 13.1-1).

Fngineering Denartment g g g [ f. -

l The Mana of Engineering is assigned the primary re nsibility for the design changes and engineeri elative to the safe operation of the DAEC. reports to the Vice President, Nucle responsibilities i~'"A ,5 : n r.et " :;d te,ge owing:

! 1. Planning, designing and construction of all facility changes at the DAEC.

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. Supervising project engineering activities assigned to the Nuclear Generation Division.

This includes the implementation of appropriate project financial and schedular control.

3. Assisting in negotiations involving Nuclear Generation Division projects in achieving compliance with legal and regulatory requirements.

l 4. Coordination of those activities associated with maintaining those engineering documents, drawings, specifications, manuals, and computer software and databases necessary to suppon the day-to-day activities within the Nuclear Generation Divisicn.

5. Providing specialized engineering support to the organization in such areas as Systems.

Procurement, Analysis, ASME, ISI, IST, Environmental Qualification (EQ),

Maintenance, etc.

l 6. Preparing and maintaining lists that denote the specific safety-related stmetures. systems.

and components.

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A description of organizational responsibilities are contained within the Nuclear Generation Division Procedures.

Nuclear Licensine Orw /N==h # 2 The Manager. L.!!ng, carreports L6en:&N aL l to the Vice=President.

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1. Managing nuclear licensing activities regarding the DAEC to ensure compliance with regulatory requirements.

2. Maintaining the Updated Final Safety Analysis Report and preparing the periodic t submittal of revisions in accordance with 10 CFR 50.71(e) requirements.

Preparation and submittal of any necessary changes to the DAEC Operating License l3.

and/or Technical Specifications in accordance with 10 CFR 50.90, {50.91 and {50.92.

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l l4. Assigning the responsibility for the evaluation ofInspection and Enforcement Bulletins. l Generic Letters and Regulatory Guides. Such evaluations will determine applicability to l the DAEC and the necessity for establishing a DAEC position.

5. Investigating plant incidents to determine root cause and recommend corrective actions to plant management, assist in the determination of the reportability of such events pursuant to 10 CFR 50.72 and 50.73 requirements and prepare Licensee Event Reports (LER) in accordance with 10 CFR 50.73 requirements.

g O Performing Post Scram reviews and making recommendations to the Operations Committee for plant re-start in accordance with NRC Generic Letter 83-28. Item 1.1 requirements.

7. Coordinating the dissemination and review ofIndustry Operating Experience on site.

l C3AAL, A description of organizational responsibilitie.sjs' contained in the Nuclear Generation Division Procedures.

Emergency Planninc

/fcu The Manager, Emergency Planning, repons to the Vice . anma, Nucka and is ft=.-=.n assigned the primary responsibility for Emergency Planning activities for the Nuclear Generation l f Division. both onsite and offsitD The purpose of the DAEC onsite and offsite plans is to ensure that the public is adequately protected in the event of a radiological emergency at the DAEC.

The Manager, Emergency Plannmg,is designated as the primary contact with the NRC. State of Iowa and the Federal Emergency Management Agency (FEMA) in matters affecting the emergency plans and implementing procedures.

Duane Arnold Enerev Center __

' TACC. /$B2=S l The dutie d responsi slities of the DAEC Plan't Manager, can be found in Section 13.1.2.2.1.)W epons to the Vice President, Nuclear.

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l Training The Training Depanment is headed by the Manager. Nuclear Trair: ig, who repons to the Vice President. Nuclear and includes the instructors. the DAEC Simulator and other training facilities

needed for carrying out the DAEC training programs for licensed personnel, unlicensed personnel, and general employee training discussed in Section 13.2.2.

Outage and Suncort The Manager, Outage and Suppon reports to the Vice President. Nuclear and is 4:

responsible for managing all activities required to prepare for and conduct refueling and other

planned outages. These responsibilities include but are not limited to budget and co~st monitoring, planning and scheduling, resource procurement, scope control, and work execution.

During the conduct of refueling outages the Manager, Outage and Support will be responsible i

for management and coordination of all activities associated with the outage.

. -He P!st Prcccdurcs Orcup, ddch is asyvasibk for amin:cd.-dag ic pis; precedur=-

forw>peratione-and tumuisumius, acporu to the iviatsger, Gumss -,d Support.

t The Fire Protection Engineering Supervisor heads the Fire Protection Group and reports to the Manager, Outage and Support. The Fire Protection group is responsible for maintaining the DAEC Fire Plan and for coordination of those activities necessary to ensure compliance with i

the Plan, applicable Fire codes and Federal Regulations. Such activities include control of l

! combustibles materials on site, coordination and scheduling of fire drills, ensuring routine l

maintenance of the fire protection equipment is properly performed, ensuring that the DAEC fire l brigade is properly trained and staffed and providing fire protection engineering suppon. The

DAEC Fire Marshall reports to the Fire Protection Engineering Supervisor.

The Securi:y Superintendent is responsible for conducting the security program under the direction of the Manager, Outage and Support. The primary responsibility of the security organization is to regulate access to the plant and protect against radiological sabotage. In addition, they issue and collect radiation monitoring devices. ney also are responsible for implementing the DAEC Fitness-for-Duty Program. See Section 13.6.

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UFSAR/DAEC-1 Dusiness Unit The Manager. Business Unit reports to the Vice President. Nuclear. The Business Unit is responsible for the Nuclear Genaation Division accounting. budgeting and contract administration. The Unit is also responsible for long-term planning. monitoring of the financial viability and decommissioning of the DAEC. The Manager. Business Unit coordinates communications with the DAEC co-owners, i.e. CIPCO and Combelt.

The Nuclear Fuels function within the Business Unit is responsible for the design and economics of each fuel reload, the procurement of nuclear fuel. long-term fuel management for the DAEC, providing for thc long term disposition of spent fuel and for providing operational support to the DAEC. .

[ed<M 13.1.1.2.2.2 Cornorate Ounlity Assurane Denanment g ge No ffA 4 The Manager, Corporate Quality Assurance, is assigned the primary responsibility for ensuring that quality requirements relative to the safe operation of the DAEC are identified and l met. He repo V!:- P: :Mr; %.;' . (See Figure 13.1-1).

'she current description of organizational responsibilities are contained within the l Corporate Quality Assurance Department Procedures.

The Manager, Corporate Qdity Assurance,is responsible for preparing and maintaining the DAEC Operational Quality Assurance Program. (See Chapter 17.2).

I The Manager, Corporate Quality Assurance, is responsible for evaluating the effectiveness of the DAEC Operational Quality Assurance Program and issuing periodic reports to the annronriate levels of management. -

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of the DAEC.

ad equipment Er . 0/.00 ;..d i.; p: r_ n-is responsible for establi .hing procedures for the control of associated procurement ectivities.

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UFSAR/DAEC-1 l 13.1.! '.2.4 Records and Microfilm Administrator The Records and Microfilm Administrator reports to the Manager. Corporate Services and is responsible for storing. protecting, and retrieving records relating to the operation of the DAEC. The organizations responsible for initially controlling records are res~ponsible for the formal turnover of records to the Records and Microfilm Administrator who provides microfilming and record reproduction services.

l 13.1.1.2.3 Safety Committee The Safety Committee functions to provide independent reviews and audits of designated activities. The functions and composition of the Safety Committee are specified in the Technical Specifications and the Safety Committee Charter. See Section 13.4.2.1. -

13.1.1.3 Ouali6 cations . = ~ ~ = "

l The principal se ' r members of the IES Utilities, Inc. corporate staff responsible for providing technical s rt for opgerati ns of the DAEC include the Chauman of the Board and Chief Executive O cer; PresidenkChief Operating M CSf Fi = rid Officer; the Vice President, Nuct @~ ^ ~"-* Vice P=it Muiu, the Manager. Engineering; the Memp r, Mais I.kenig; the Manager, Emergency Planning; the Manager. Outage and 1 Support; the Manger, Business Unit; the Manager, Nuclear Traming and the Manager, Corporate Quality Assurance.

The Regional Administrator, Region III, U.S. Nuclear Regulatory Comnussion. will be kept informed of the individuals filling these positions. Information regarding their individual l educational b 2ckground and related experience will be made available at IES Utilities. Inc. for NRC review upon request.

13.1.2 OPERATING ORGANIZATION 13.1.2.1 Plant Oronnintion pr '

The Vice President. N e as direct line responsibility for the operation of the DAEC. l The DAEC Plant Manager s re nsible for the safe, reliable, and efficient management of the

~

plant. The following capt in e DAEC Plant Manager's behalf during his absence from the plant: Operations-S-t: ; anager, Outage and Support; Manager, Engineering; and the Maintenance CNL. e basic orgar ization of the DAEC consists of departments headed by the Operations Sug.- vir, NuJ= A .dpir Sup--t^ , Maintenance Su;niiMF and the Radiation Protection Manager. The Operations Committee also reports to the DAEC j Plant Manager. ' Die plant orgi.r.nzation is shown in Figure 13.1-2. This basic group is backed up l 13.1-9 Revision 12- 10/95

LTSAR/DAEC-1 by technical personnel as required. and it is enlarged during periods of refueling and maior l equipment maintenance.

l IES Utilities. Inc. has been responsible for all station operations from the start ol' preoperational tests. General Electric and Bechtel provided technical direction and assistance during the period of preoperational testing, core loading, startup. and pre-com_mercia ooerat_ ions.

Ooerations Denartment a.a .

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l jf& ar The Operations Department is headed by th O erations.Supemsonnd the .^.zim Operations Supervisors. Each is a Senior Reactor Operator p g OgJg j 5 *,'#~0 l

Most of the personnel who make up this group are q ified by academic instrucuon and l experience at operating reactor and simulator facilities. The Operations Shift Supervisors. the l Nuclear Station Operating Engineers, and the Assistant Nuclear Station Operating Engineers j hold appropriate NRC licenses. Thesegepons monit r and operae the plant nuclear.

mechanical, and electrical equipment:

i Eel-handling activities. M, conduct radit. tion surveys as required e/Cne ~CA, g ?W Op% f~,**;

The personnel for these positions were initially assigned their duties by selection from those undergoing training. Their experience and performance during training were evaluated before they were assigned to a position. Most of the initial individuals were chosen from a group 7

of Company personnel who successfully completed a Company-cord :cted nuclear power l

orientation course. These individuals were supplemented by persor.H who had previous nuclear experience in the Naval Nuclear Power Program.

Since the DAEC has become operational, positions on the staff that become vacant are filled. where possible, by employees who progress through the different positions. They. of course, have to meet all the requirements of the appropriate NRC licenses. Individuals are initially assigned to these positions after a careful evaluation of their qualifications, their progress j in the training progran, and the proficiency level reached in their last position.

The duties and responsibilities of personnel from the Operations Group on an operating shift are described in Section 13'1.2.3.

l e Reactor Engineering Group, headed by the Reactor Engineering Group Leader.

~~ to the Operations Supervisor.- The group has responsibility for monitoring the performance of the reactor core to ensure safe and economical use of the nuclear fuel and for maintaining all the necessary records for the special nuclear material on site. Reactqr Engineering also assists Nuclear Fuels. ,

13.1-10 Revision 12 - 10/95 l

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_o The Majntenanc epartment is hea ed y t e Maintenance Sh$Yd5 and is M" divided inito.1href gr ps: the Mechanical Group. headed by the Mechanical Maintenance I Supervisor: the ctrical Group. headed by the Electrical Maintenance SuperviCorpadahe l Instrumentati and Controls Group, headed by the Instrumentation and Controls Maintenance l Supervisor l'The Mechanical Maintenance Group is composed of the Supervisor. nuclear mechanics / nuclear mechanic machinists, nuclear mechanic welders, and apprentices as required.

Their duties consist of day-to-day repairs and adjustments, equipment condition inspections.

equipment overhauls. and equipment modifications. The Electrical Maintenance Group is composed of the Su pervisor, nuclear station and substation electricians, and apprentices as I required. Their duties consist of the maintenance, and modification of plant electrical equipment l and equipment condition inspections. The Instrumentation and Controls Group is composed of the Supervisor, nuclear station control system technicians and apprentices as required. Their l duties consist of the maintenance. modification and calibration ofinstruments and controls. l The maintenance staffis augmented with qualified personnel from outside sources during refueling and major maintenance periods. The maintenance staff closely coordinates its work l with the Operations Department and assisted during the initial _c _ ,,

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' l The Radiation Protection Department is headed-by the-Rrdiation Protection Manager.

This Department is composed of the Health Physics, Chemistry and Radioactive Waste Groups.

l The Radiation Protection Department is responsible for plant radiation safety and l performs contamination and radiatinn surveys and radiological decontamination activities  !

necessary to ensure plant safety. The Radiation Protection Department is on call at all times.

l The department is also responsible for those plant activities associated with maintaining the plant water chemistry as well as collection, packaging and transport of all adioactive waste materials.

The department is responsible for satisfying the Technical Specifications and manpower requirements for sidit coverage in radwaste, chemistry, and health physics.

Health Physics Technicians are assigned shift work as required to meet plant operating needs. All members of the plant operating staff receive sufficient health physics training to be able to perform self-monitoring activities.

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l 13.1.2.2 Plant Personnel Resoonsibilities and Authorities The job description. requirements. and responsibilities of key plant personnel are included in this section. The responsibilities described are not meant to apply to only one specific position. Supervisors who meet the necessary qualifications may assume the responsibilities of positions other than their own on a temporary basis.

l l 13.1.2.2.1 DAEC Plant Manager l

l The DAEC Plant Manager is assigned the primary responsibility for the safe operation of the DAEC. The DAEC Plant Manager has supervisory control over those onsite activities necessary for safe operation and maintenance of the DAEC. The organizational arrangement is

! presented in Figu :e '3.1-2. The current organi7ational arrangement and description of orgamzational re. consibilities are contained within the administrative procedures and the Technical Specifications. The license requirements for each position are specified in the j Technical Specifications. i l*> The various organivations reporting to the DAEC Plant Manager are responsible for those j activities associated with operations, maintenance, r air, refueling, performance-evaluation, testing, radiation protection /ALARA, e environmental survey program,4per p p-^trt =., r_.;, _-2 n x d.: =~c.;,.

l*- The Operations Committee functions to advise the DAEC Plant Manager on all matters related to nuclear safety. The composition, function, and responsibilities of the Operations Committee are specified in the Technical Specifications and are delineated in appropriate DAEC administrative procedures.

l The DAEC Plant Manager reports to the Vice President, Nuclear. Spec'.fic l responsibilities include, but are not limited to, the following: l

1. Managing the day-to-day activities of the DAEC. Tliese activities include power plant i operations, maintenance, radiation protection, security, and technical support.

2. Coordinating interfacing activities with the NRC inspecting personnel and Corporate Quality Assurance personnel.

3. Planning and coordinating all onsite activities.

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l 13.1-12 Revision 12 - 10/95 e

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UFSAROAEC-1 l 13.1.2.2.2 Operations.hpm vuur M m' $ // O$

Y The Operations Sep r .:::is responsible for the operation. safety and security of a 1 plant equipment and the safety and action of all personnel involved in plant operations. is responsible for maintaining station operating records in accordance with the facility license.

N'":f4 l .13.1.2.2.3 Operations Shifg"3---- _ __

M y <i The Operations Shift Sep r _:= cin charge of their respective shifpf and supervise personnel and equipment operation for the safe, efficient. and reliable operation of the plant. $ ee

' Section 13.1.2.3.

NT l 13.1.2.2.4 Maintenance Sg.i ..ad;;;

The Maintenance Mn is responsible for day-to-day maintenance, alteration.

overhaul, and repair of elec rical, mechanical, and auxiliary equipment associated with the plant.

The M:!n xsu En;; ins , Mechanical Maintenance Supervisor, Electrical Maimenance.

Supervisor, gad' Instrumentation and Controls Maintenance Supervisop report to the Maintenance Superintendent. - ... C g y , , 4,

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l 13.1.2.2.5 Mechanical Main enance Supervisor

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The echanical Maintenance Supervisor is responsible for supervising the day-to-day  ;

maintenan e, alteration, overhaul, and repair of meche.ical equipment associated with the facility.<fe participates in personnel training and in the review of operating and maintenance manuals for his area of responsibility.

l 13.1.2.2.6 (fG.Elg:trical DMAMaintenance gy Supervisor m

The Electrical Maintenance Supervisor is responsible for supervising the day-to-day maintenance, alten tion, overhaul, and repair of electrical equipment associated with the facility.

JWparticipates in personnel traming and in the review of operating and maintenance manuals for his area of responsibility.

l 13.1.2.2.7 Instrument & Control (I&C) Maintenance Supervisor gg- - + h l The I&C Maintenance Supervisor is responsible f supervising the day-to-day

maintenance, alteration, overhaul, calibration, repair surveillance ofinstrumentation and j control equipment associated with the facility, articipates in personnel trammg and in the i review of operating and maintenaace manuals for his area of responsibility.

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fo l 13.1.2.2/ Radiation Protection Manager (ffp) N N' The Radiation Protection Man =~ '

e r t radiation safety and plant chemistry. hupervises plant chemical iological ^L ctivitie

'n charge of the laboratory, plant chemical equipm , d radiological sis. In addition e aintains a j documented r: cord of ra evels within plant areas as ecified by the Plant Manager. and maintains a d.y : ed exposure history on all plant perso el and visitors who are subject to

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exposure. 6t rm des technical advice to plant personnel. 's responsible for establishing.

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i and has the authority to enforce, the radiation safety control policies by which the plant operates i and with which all plant personnel and visitors must comply.

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l 13.1.2.2[ Environmental Supervisor The Environmental Supervisor is responsible for developing and maintaining programs  ;

i for onsite compliance with environmental regulations. This includes compliance with RCRA

hazardous waste regulations, spill regulations, regulations on liquid (non-radiological) discharges, water use regulations, and air emission regulations.

/k l 1,3.1.2.2.J<I Chemistry Supervisor f C&{

The plant Chemistry Supervisor is sponst le for performing the chemical and b

5 radio-chemical ana or the power plant. is responsible for maintammg the Plant Water l Chemistry $k p~.-Ak. =gl fm the radiological environmental monitoring program.

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l 13.1.2.2. Radwaste Supervisor I l

The Radwaste Supervisor is responsible for the collection, treatment, packaging. storage j

l and shipment of all radioactive waste generated at the DAEC. The Radwaste Operators report to the Radwaste Supervisor.

13.1.2.2 Decontamination Supervisor The Decontamination Supervisor is responsible for coordinating all radiological decontammation activities performed on site and for the lease, purchase, storage and issue of all radiological protective clothing.

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l 13.1.2.2.1J Health Physics Supervisor f]d /d$f .dy-= ,

The Health Physics Supervis r is responsible for performing the radiation and 1 contamination surveys of the plant. osting of radiological conditions. issuance of Radiation i Work Permits and establishing th ecessary radiological controls for work performed in radioactive areas of the plant. is also responsible for evaluati n g radiological conditions in the l plan andmaking recommendations on work practices and design changes to ensure doses are l AL @: ..;@e.-itic for the issuance and analysis of personnel dosemitry, maintenance of records of personnel exposurg and the off-site environmental monitoring program. The Health Physics technicians report to the Heahh Physics Supervisor.

b 13.1.2.2.}/ ALARA Supervisor g,u/4 The ALARA Supervisorimpi ents the site program to maintain personnel radiation exposure As Low As Reasonably ^ Anbk (ALARA).The ALARA Supervisor is responsible for the measurement and docurr.entation of personel radiation exposure.

fl 3.1.2.2.15 Quality Control and Quality Assurance Assessment Supervisors The Quality Control Supervisor and the Quality Assurance Assessment Supervisor are responsible for verifying that the Operational Quality Assurance Program is being adequately implemented at the DAEC. Quality Control is responsible for providing the inspection and testing necessary to support operation, testir g, maintenance, and modification of the DAEC.

4 Both Supervisors report to the Manager, Corporate Quality Assurance. l w

l 13.1.2.3 Oneratimr Shift Crews My 1

_The ormal operating shift consists of an 'A" Operations Shift Sugn & (SRO) in charge, a, 'B" Operations Shift Supervisor (SRO), a Nuclear Station Operating Engineer (RO). an Assistant Nuclear Station Operating Engineer (RO),: S=:nd A=i~e him 0; :ica-Cp=in;; En-inern 2 Nuclear Statio . "!de Engingand a S_hift Technical Advisor.

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The duties and responsibilities of e personneFonlin operanng shift are as follows:

M Er n y e r

1. " " Operations Shift Su;~ umr- SRO l

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The Operations Shift Sr . -is in charge of the shift. He supervises personnel to l

i ensure safe, efficient, and proper operation of the DAEC. He is responsible for radiation safety and chemistry, as well as tests and results on his shift. He participates in personnel

, traimng and in the review of operating manuals and instructiorts in the startup, operation. -

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! 13.1-15 Revision 12 - 10/95 l

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i UFSAR'DAEC-1 and rhutdown of the facility. He participates in and contributes to the planning and i

scheduling of maintenance and refueling activities.

2. perations Shift Supervisor - SRO

, The Shift Sp:gigns

. . .xa pW Shift t Supervisor has the same duties and responsibil

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iat of bgei e in charge of the shift. He is included in the shift in order to permit the ' Shift Sup:$$ move about the plant as needed during normal i and emergency situations while at the same time fulfilling the NRC requirement that a

Senior Licensed Operator be present at all times in the control room when the unit is being operated. The@perations Shift Supervisor is required for all reactor modes except cold shutdown and refuel mode.

3. Nuclear Station Operating Engineer - RO The Operating Engineer, on instructions from the Operations Shift Supervisor, directs generator loading and electrical switching. He monitors, controls, and directs the operation of the reactor, turbogenerator, auxiliaries, and electrical equipment. He interprets, audits, and reviews instrumentation and chart indications as to the performance, efficiency, radiation, and chemistry of the plant. He assists in the training of personnel in the skills and knowledge required for the safe and efficient operation of i the facility. He performs work in reactor-fuel-handling operations involving the preparation, transfer, loading, and unloading of fuel. He may be assigned to the maintenance crew while the reactor plant is not in operation.

4. Assistant Nuclear Station Operating Engineer - RO y.g;,, f/.Me-Ms-e m . '

1 The First Assistant Operatingngineer works under the intermittent supervision of the)

Operations Shift Supervisor, Operating Engineer,m Rchsi ^y -o. Co.um.. The duties of the First Assistant Operating Engineer are essentially the same as those of the  ;

Operating Engineer; thus, the Operating Engineer and First Assistant Operating Engineer l are equally qualified to operate either the reactor control board or turbine-generator control board. The First Assistant Operating Engineer may be assigned to the maintenance crew while the reactor plant is not in operation.

5. S::0.d .' Me"-tNuclear Station 0;c" ; r-f 7r /4d 6 M*d P* M The

1. ~ <.ka< J%dk SrM 9 :-*--* 0;:

Afd 4g*erl.,

-- E-f - _ ,

sh ops--k the direction oflicensed operators in the 4

plant control room, inspects, services, starts, and stops turbogenerators, mechanical, electrical, related nuclear equipment, and auxiliaries 9sianardy in the reactor building v.SN.

observes charts, gauges, instruments, and controls,jad" records readings as required /3 13.1-16 evision 12 - 10/95 l

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UFSAR/DAEC-1 f< #J/fo assists in the preparation of station loc sheets and reports. Jifis able to conductgiatio #

surveys and possesses a working kno[viedge of water treatment equipment. pf hihhe assigned to the maintenance crew while the reactor plant is not in operation.

r6. Nuclear Station Auxiliaries Engineer The Auxiliaries Engineer has essentially the same duties as the Second Assistant Operating Engineer, except that his duties are routinely performed in the turbine building, pump house, intake strucmre, and cooling towers. The Auxiliaries Engineer may be assigned to the maintenance crew while the reactor plant is not in operation.

7. - Shift Technical Advisor The Shift Technical Advisor (STA) provides engineering support on-shift in accordance with NUREG-0737, Item I.A.1 requirements.

The requirements and responsibilities of the STA include the following:

a.. The Shift Technical Advisor will be stationed onsite and will be pr;sent in the control room within 10 minutes of being summoned during plant power operation.

in other than cold shutdown or refuel mode.

b. The Shift Technical Advisor serves as an advisor to the Operations Shift c :ni= during off-normal reactor plant conditions.

c. The Shift Technical Advisor will provide operating experience assessment functions as related to DAEC design, procedures, and practice, and in support of their transient / accident assessment functions.

i

d. In the performance of these duties, the Shift Technical Advisor will be free of  !

duties associated with the commercial operation of the plant and will report l l directly to the Operations',+.-.i;e,;: c l

Thy 1 13.1.3 QUALIFICATION OF NUCLEAR PLANT PERSONNEL 13.1.3.1 Onnlifications Reanirements t

The qualifications ofindividual members of the plant staff meet or exceed the minimum l qualification requirements referenced in ANSI /ANS 3.1-1978 for comparable positions.

i i l i l 13.1-17 Revision 12.- 10/95 l

c UFSAR/DAEC-1 The Radiation Protection Manager meets or exceeds the qualification requirements of Regulatory Guide 1.8. September 1975.

Table 13.1-1 provides the cross-reference for the various positions within the DAEC organization to those comparable position descriptions and training and experience requirements within ANSI /ANS 3.1-1978, where applicable.

'13.1.3.2 Oualifications of Plant Personnel Personnel qualifications are set forth in the Technical Specifications. It is the intent of l IES Utilities, Inc. to adhere to these qualifications when obtaining replacements for vacant positions, whether they be curre .t DAEC employees advancin; to positions of greater responsibility or newly hired personnel.

The personnel qualifications of key plant managerial and supervisory personnel at the time of DAEC initial fuel loading were included in the original FSAR.

Information regarding qualifications of personnel currently occupying positions in the operating l organization of the DAEC n file and available at the site for NRC inspection.

13.1 18 Revision 12.-10/95 l

. . . . . . -- .. .- .. . . - _ _= . .. ._

UFSAPJDAEC-1 Cnairman ci tne Boaro anc Ched Executrve OMcer i on t a ,..u__ e___

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7".E'l'.""'. Nuclear Outage and Manager, Manager, Traimng Support Business Unit Encineenne v c e, s.r

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UPDATED FINAL SAFETY ANALYSIS REPORT IES Utilities, Corporate Organization Figure 13.1-1 Revision 12 -

10/9

UFSAR/DAEC-1 From Firoure 13.1 1 Vce Prescent.

Nuclear Plant Manager (a) operations Commrtee

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( ,,, Radiacon Protecton ff operations IAlt'wa Mantenance Manager

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Enoineerino Supervisor Maintenance fuge I 4r**? , ) ,

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Operating and Supervisor Maintenance Seg ,

Nuclear Station l Aseistant I operating Raowaste Engswers (c) Suoervisor ,

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f/on V Tsas f Wnb Ope.sa /pj e . Piant Meneger er one el his oesagneted symcicle enemates meet AN$f 11 1979 Lcense Reguremente D = Serwor SeeClar Operelor C = Reactor Opereser DUANE ARNOLD ENERGY CENTER IES UTILITIES, INC.

UPDATED FINAL SAFETY ANALYSIS REPORT Duane Arnold Energy Center Organization Figure 13.1-2 Revision 12 - 10/95

] l l

2

! UFSAR/DAEC-1

Table 13.1-1

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, i DAEC Plant Staff Position Standard of QualiScatka (Note !) Description of Duties UFSAR Section (Note 4) j ANSI /ANS 3.1-1978 Tech Spec NUREG 0737 Reg Guide j Section (Note 2) Section Plant Manager 4.2.1 6.3.4 13.1.2.2.1 l Operations E:;a ...or No-.a . v 4.2.2 6.3.5 13.1.2.1.I3.1.1 2.2 i Operatio Shift E,.

Opm 4J fWr'hs.h5W

..-r/f&ra7- 4.3.1 13.1.2.1.13.1.2.2.3.

} I 3.1.2.3 j brating Engineers 4.5.1 (Nbte 3) 13.1.2.3 4 ShiftTechnical Advisors 4.5.1 6.3.3 Item 1.A.1 13.1.2.3 l Maintenance L. .- " Afaww4.2.3 13.1.2.1.13.1.2.2.4 j Mechanical Maintenance Supervisor' 4.3.2 13.1.2.1.13.1.2.2.5 j Electncal Maintenance Suoervisor 4.3.2 13.1.2.1.13.1.2.2.6 J

l & C Superviser 4.4.2 13.1.2.1.13.1.2.2.7 j Reactor Engmeets ,

4.4.1 13.1.2.1 Fire Protection Engineering Supervisor 4.3.2 13.1.1.2.2.1 j Radiation Protection Manager 4.4.4 6.3.2 1.8 1975 13.1.2.1.13.1.2.2.8 a

Chemistry Supervisor 4.4.3 13.1.2.2.10 Radwaste Supervisor 4.3.2 13.1.2.2.11

} Health Physics Supervisor 4.3.2 13.1.2.2.13 Decon Supervisor 4.3.2 13.1.2.2.12 ALARA Supervisor 4.3.2 13.1.2.2.14 Manager. Outage and Support 4.3.2 13.1.1.2.2.1 l

i Supervisor. Procedures Department 4.3.2 i Testing and Surveillance Supervisor 4.2.4 13.1.1.2.2.1 l Security Supenntendent 4.3.2 e Manager. Corporate Quality Assurance 4.2.4 13.1.1.2.2.2

]

g. -- _ _ _.c.7-=.~ 4.4.5 J 1. ' - O ' "..- ... .. 5 ;- .... 4.4.5 13.1.2.2.15

^" !-_; rir , 4.4.5 13.1.2.2.15 9

Manager. P- '--- ' ' - -- - - C 44/ 4.2.4 13.1.1.2.2.1 3 Supervisor. Nuclear Licensias f 4.3.2

! c "

c.. g .~ o7 _. . u . _ -.. 4.3.2 j Manager. Engineering 4.2.4 13.1.1.2.2.1 4

Project Engineenne Supervisor 4.3.2 l

Plant Engineenne Supervisor 4.3.2 Program Engineering Supervisor 4.3.2 Materials Management Supervisor 4.3.2 i Manseer. Nuclear Training- 4.2.4 13.1.1.2.2.1  !

! Trairung Supervisor-Simulator 4.3.2 l

! Training Supervisor-Techrucal Programs ' 4.3.2 1 Training Supervisor-Operations 4.3.2 Training Supervisor Administrative 4.3.2 i

• . - - ; S ;- Er '- -

r. ' Std- 4.3.2

'1....-... __ 4.*.2 Note: 1 - In some cases, plant design femmres or unusual operating condmons may indicate that additional or more 5= ale =i expertise beyond qualifications presented in this Standard is needed. 'this determiannon will be made on a case-by-case basis.

Note: 2 - See DAEC Technical Specifications Section 6.3.1 for comnnument to ANSI /ANS 3.1 1978.

Note: 3 Applicants for senior operator licenses shall have 4 years of tr5=nahle power plant experience. Respoenbie power plant experiences should be that obtained as a control room operator (fossil or seclear) or as a power plant staff engineer involved in the day-tcwlay ac ivities of the facility, commencing with the final year of constnaenon. A ===== of 2 years power plant expenance may be fulfilled by am demic or related techmcal training, on a one-for-one time basis. Two years shall be nuclear power plant exponence. At least 6 months of the nuclear power plant experience shall be at the plant for which he seeks a license.

Applicants for senior operator licenses shall have held an operators license for 1 year Note: 4 - If no UFS AR Section is listed. staff position is not discussed in Chapter 13.1.

f.*DJ F*~ ha h f 3, 2 -

/194 W A c " f fyfNyV tfi2 T13.1-1 Revision 12.- 10/95

- .