ML20041F555

Amend 72 to License DPR-49,modifying Tech Specs to Incorporate Organizational Changes to Plant Staff & Safety Committee

ML20041F555
Person / Time
Site:	Duane Arnold
Issue date:	03/05/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Iowa Electric Light & Power Co, Central Iowa Power Cooperative, Corn Belt Power Cooperative
Shared Package
ML20041F556	List: ML20041F555 ML20041F559
References
DPR-49-A-072 NUDOCS 8203170146
Download: ML20041F555 (7)

Text

-

Sanc f

UNITED STATES y

g, NUCLEAR REGULATORY COMMISSION.

'E WASHINGTON, D. C. 20555

-:E s'

%..~...f IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-49 l'.

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

A.

The application for amendment by Iowa Electric Light & Power Company, et al, dated December 23, 1981 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 will 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 Spec-ifications 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:

(2) Technical Soecifications

-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in'the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

8203170146 820305 PDR ADOCK 05000331 P

PDR

=- - - _ _ _ - -

1 p

2 l

a p

3-This license amendment is -effective as of the date of its issuance.

i i

FOR THE NUCLEAR REGULATORY COMMISSION r

Domenic B. Vassallo, Chief

[

Operating Reactors Branch #2 l

Division of Licensing l

1 Attachment-Changes to the Technical

(

Specifications l

I.

I Date of Issuance: March 5,1982 i

i l

j l

t i

I t

t r

e e

I h

t e

e

.+-w w

-rd---

v-h-.

r e

7-m--

e r w

+-

m+

we

ATTACHMENT TO LICENSE AMENDMENT N0.72 FACILITY 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 pages are identified by Amendment 3

number and contain vertical lines indicating the area of change.

Remove Insert 6.2-4 6.2-4 6.5-5 6.5-5 6.5-6 6.5-6 6.5-9 6.5-9 e

I i

t I

i i

l l

i

m 3

CL g

O 3

rP Quellty Control Supervlser C)

Chiel Engineer se Quality Control N

Personnel fu Assistent Chlol Engl&eer Assistant Chief Enginewr Assistent Chlet Engineer Hediation Protectica and Ischnical Support Operations 5ecurity I

I I

I I

I I

I I

I I

I I

Me,hanical Electrical Malatemence Radletion Security technical Training Support Reactor and Operations c

Supervisor Malatenance Maintenance Engin.or Protection Supervisor Engineer Coordlestor Services Plant SLO Supervisor Supervisor Engineer Supervisor Perlermance Engineer.

I l

l l

Operating I

I m

Shitt Mechanical Electrical Malatenance Mediation Security lechalcal lastructors support Plant s

Supervislag Malatenance Malatenance l'n g i n ear l ag Protection Personnel Engineering Services Performance 1

Engineer Personnel Personnel Personnel Personnel Personnel Personnel Engineering

~

Personnel SLO I

Haector Nuclear Engineering Station Personnel and Assistant Operallag Engineers LO SLO - Senior Llconsed Operator Duane Arnold Energy Center Second toma Electric Light and Power Company Assletant 60 - Licensed Operator Technical Specillcations Operatlag Engineer

- Chie f or Assistant Chief to Meet DAEC Neclear Plant Statling and Al351 N.lS.5-8978 License Requirements figure 6.2-1 Aunlitary Engineer g

DAEC-1

c.

• Chemistry and radiochemistry.

d.

Metallurgy.

e.

Instrumentation and control.

f.

Radiological safety.

g.

Mechanical and electrical engineering.

h.

Quality assurance practices.

6.5.2.2 Composition The Safety Committee shall be composed of persons who have been appointed in writing by the Executive Vice President to serve on a permanent basis and who collectively have or have access to applicable technical and experimental expertise in the following are'as:

~

a.

Nuclear power plant operations.

b.

Nuclear engineering.

l c.

Chemistry and radiochemistry.

i l

1 d.

Instrumentation and control.

e.

Radiation protection.

6.5-5 Amendment No. 7, % 72

1 i

I I

DAEC-1 f.

Mechanical and electrical engineering.

g.

Nuclear safety.

6.5.2.3 Alternates All alternate members shall be appointed in writing by the Executive Vice President to serve on a permanent basis.

6.5.2.4 Consultants Consultants shall be utilized as determined by the Safety Committee Chairman to provide expert advice to the Safety Committee.

'6.5.2.5 Meeting Frequency The Safety Committee shall meet at least once per calendar ' quarter quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

1 6.5.2.6 Quorum A quorum of the Safety Committee shall c,onsist of the Chairman or Vice Chairman and at least four members including alternates.

No more than a minority of the quorum shall have line rdsponsibility for operation of the facility.

m Amendment No. % g, 72 6.5-6

- c.

DAEC-1 t -

\\

g. Any other area of facility operation considered appropriate by the Safety Comittee c} the. Executive Vice President.

h. Design change request s,4fety evaluations.

i

i. The DAEC Fire Protection Program and implementing procedures at N-least once per 24 months.

s z

6.5.2.9 Authority The Safety Comittee shall report to and advise the Executive Vice

]~

President on thos'e areas of res'ponsibility specified in Specifications 6.5.2.7 and 6.5.2.8.

1.

6.5.10 Records i

s s

Records of Safety Comittee activities shall be p{epared,

approved and distributed as indicated below:

r

a. Minutes ci each Safety Comittee meeting shall be prepared, approved and forwarded to the Executive Vice President within 14 days following each meeting.

s

b. Reports of reviews encompassed by Specification 6.5.2.7 above, s

shall be prepared, approved and forwarded to the Executive Vice President within 14 days following completion of the review.

c. Audit reports encompassed by Specification 6.5.2.8 above, shall be forwarded to the Executive Vice President and to the l

management positions responsible for the areas audited within 30 days after completion of the audit.

Amendment No. pf, 72 6.5-9