ML20198E371
| ML20198E371 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  (DPR-49-A-190) |
| Issue date: | 11/23/1992 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198E377 | List: |
| References | |
| NUDOCS 9212070067 | |
| Download: ML20198E371 (9) | |
Text
. __-.
- - ~ ~ -
na Mag
~
,y o
UNITED STATES 3
i NUCLEAR REGULATORY COMMISSION
[
WASHINoToN, D.C. 20666 9....*f 4
IOWA ELECTRIC LIGHT AND POWER COMPANY a
CENTRAL 10WA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.190 license No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al., dated December 13, 1990, 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 l
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, Facility Operating License No. DPR-49 is amended b3 changing paragraphs 2.C.(2) and 2.C.(3) to read as.follows and by changing the Technical Specifications as indicated in the attachment to this license amendment.
9212070067 921123 DR ADOCK 0500 1
4 l.
2-f (2) Technical Soecifications l
The Technical Specifications contained in Appendix A, as rev i
j through Amendment No.190, are hereby incorporated in the lic-The licensee shall operate the facility in accordance with the
. Technical Specifications.
j (3)
Fire Protection Iowa Light and Power Company shall implement and maintain in effect all provisions of the approved fire protection program as described l
in the Final Safety Analysis Report for the Duane Arnold Energy Center and as approved in the SER dated June 1, 1978 and Supplement l
dated February 10, 1981 subject to the following provision:
T The licensee may make changes to the approved fire protection program without prior approval of the commission only. if those changes would not adversely affect the ability to achieve and maintain safe shutdown i
in the event of a fire.-
i 3.
The license amendment is effective as of the date of issuance and shall be implemented within 60 days of the date of issuance.
l-
-FOR THE NUCLEAR REGULATORY COMMISSION v =r John N. Hannon, Project Director Project Directorate III-3 Division'of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation-l
Attachment:
i Changes to_the Technical Specifications-Date of issuance: November 23, 1992 0
Y W
l 1
9
- y.
-n, 8-,,-
--,-,..,.-.,,,.-,..,y,-
.,.,,,.._.,.,-n,_,,,,,_
,--,,,,,,,.m.-ww,-,,--..-
-,,m,,--,,,.,,w,
_ _ _ = _
ATTACHMENT TO LICENSE AMENDMENT N0j90 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-33[
Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
LIST OF AFFECTED PAGES REMOVE INSERT iiia ilia vi vi 3.13-1 through 3.13-12 3.13-1 6.2-2 6.2-2 6.5-3 6.5-3 6.11-5 6.11-5 l
l
i e
i 3.
DAEC-1 i
i, N
r l
i SURVEILt.ANCE LIMITING CQ1lDITIONS FOR OPERATION REOUIREMENTS PAGE NO.
i l
l 3.13 Deleted l
3.14 Radioactive Effluonts 4.14 3.14-1 j
A.
Liquid Holdup Tanks A
3.14-1 i
r j
B.
Liquid Holdup Tank Instrumentation B
3.14,
l l
1 a
i 4
i 1
t t
4 3
i i
r Y
Amendment No.190 -
iiia g
. ~ -. _. -
. ~.... -
4 4
DAEC-1 TECHNICAL SPECIFICATIONS LIST OF TABLES (Continued)
Table ligrt t er Title Dag 4.7-1 Summary Table of New Activated carbon Physical Properties 3.7-50 4.10-1 s'ummary Table of New Activatc.3 Carbon Physical Properties 3.20-7 l 3.13-1 Deleted l 3.13-2 Deleted i
l l
6.2-1 Minimum Shift Crew Personnel and License Requirements 6.2-3 6.11-1 Reporting Summary - Routine Reports 6.11-6 i
1 l Amendment No.190 vi
~n-e
-n
- g. - - -. -
.,e-r-.
r.r,-s s
,.m
-...yvsve w.
sey-.
- -... -. -. -... - _ -... ~. -
1
- I i
l j
4*
DAEC-1 1
LIMITIf10 CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMEl{IS 4
i 3.13 FIRE PROTECTION SYSTEMS 4.13 FIRE PROTECTION SYSTEMS 1
1 SECTION 3.13 - Pages 3.13-1 SECTION 4.13 - Pages 3.13-1 through l
through 3.13-12 have been deleted 3.13-12 have been deleted 1
+
I 4
4 1
1 i-
?
1 i
1 e
b I
l
.i 1
i i
i i
i i
L 1.
I Amendment No.
190 3.13 1
{
l 1
. - ~ -,..,
,,..nw._v~,.
,-,.cy._m~c
,.,,,y._....,m,...,..,.-,.,.
,..._w..
,.,w...
,.. ~
i
].
DAEC-1 5
6.2.2 PLANT STAFF ORGANIZATION j
The following manning requirements shall be mett 1.
All CORE ALTERATIONS shall be directly supervised by either a Senior
)
Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who j
has no other concurrent responsibilities during this operation.
l 2.
At all times when there is fuel in the reactors 1
l a.
A senior reactor operator shall be on the plant site.
b.
A reactor operator shall be in the control room.
1 Two reactor operators shall be in the control room during startup, c.
i scheduled shutdown, and during recovery from trips caused by transients or emergencies.
d.
Minimum operating shift crew compositions shall conform to those shown in Table 6.2-1.
i e.
At least one member of each operating shift crew shall be qualified to implement radiation protection procedures.
j l-i I
l
?
l i
1
' Amendment No.190 -
6.2 l
. -- a - -. -, -.. -,
~. -.. _..
-... -. ~ -
. -. -. _ - _ -. -. _. - _ _ ~. -. _..
a t
1
- l*
1 DAEC-1 l
i r
I i
e.
Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager-Huclear 4
Division and to the Chairman of the Safety Committee.
f.
Review of all Reportable Events.
1 a
l g.
Review of facility operctions to detect potential safety hazards.
J h.
Performance of special reviews, investigations or analyses-and reports thereon as requested by the chairman of the Safety Committee.
4 1.
Review of the Plant Security Plan and' implementing procedures.
i j.
Review of the Emergency Plan and implementing procedures.
I k.
Review of every unplanned release of radioactivity to the environs for l
which a report to the NRC is required.
L 4
1.
Review of changes to the Offsite Dose Assessment Manual and changes to the Process Control Program.
l m.
Review of the Fire Protection Program and implementing procedures.
1 6.5.1.7 Authority 2
^
i The Operations Committee shall j
a.
Recommend to the Plant Superintendent-Nuclear written approval or i
disapproval of items consid-ed under Specification 6.5.1.6 (a) through i
(d) above.
8 I
l 1
t i,
i 4
i 1
5 t
i I
I Amendment No.190 '
c.5-3 I
I 2
. ~.
DAEC-1 i
e.
deleted s
l f.
deleted g.
deleted h.
Radioactive Liquid or Gaseous Effluent - calculated dose exceeding specified limit (ODAM Sections 6.1.3, 6.2.3 and 6.2.4).
1.
Off-Gas System inoperalile (ODAM Section 6.2.5).
4 j.
Meaoured levels of radioactisity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 wheen averaged ever any calendar quarter rampling period.(ODAM Section 7.3.2.2) i k.
Annual ( n-a MEM3ER OF THE PUBLIC determined to exceed 40 CFR PL/-
.50 dose limit (ODAM Section 6.3.1.1).
)
1.
Radioactive liquid waste released without treatment when activity concentration exceeds 0.01 yci/ml (O"AM Section 6.1.4.1),
Explosive Gas Monitoring Instrumentation Inoperable m.
(Specification 3.2 I.1).
l n.
Liquid Holdup Tank Instrumentation Inoperable (Specification 3.14.3.1).
k J
d 1
4 1
Amendment No. 190 6.11-5
_