ML20195G973

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Amend 227 to License DPR-46,revising DAEC TS by Adding New TS 3.7.9, Control Building/Standby Gas Treatment Sys (Cb/Sbgt) Instrument Air Sys
ML20195G973
Person / Time
Site: Duane Arnold, 050331O  NextEra Energy icon.png
Issue date: 06/09/1999
From: Craig C
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20195G964 List:
References
NUDOCS 9906160237
Download: ML20195G973 (7)
v • d • e


Text

n jp k UNITED STATES g .- NUCLEAR REGULATORY COMMISSION

  1. - WAstilNOToN, D.C. seteHOM

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- lES UTILITIES INC.

CENTRAL-IOWA POWER COOPERATIVE

, ' CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 227 License No. DPR49

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by IES Utilities Inc., et al., dated October 15, 1998, as supplemented December 21,1998,'~ 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 end. 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 .

Ei 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 Specifcations as

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indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR49 is hereby amended to read as follows:

9906160237 990609 PDR ADOCK 05000331 P PDR

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..(2) Technical Soecifications

! . The Technical Specifications contained in Appendix A, as revised through Amendment No..227, are hereby incorporated in ti)e license. The licensee shall i operate the facility in accordance with the Technical Specifications. ]

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3. - The license amendtsent is effective as of the date of issuance and shall be implemented

. within 30 days of the date of issuance. j FOR THE NUCLEAR REGULATORY COMMISSION l g

Claudia M. Craig, Chief, Section 1 ,

Project Directorate lli  !

Division of Licensing Project Management Office of Nuclear Reactor Regulation ,

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Attachment:

Changes to the_ Technical Specifications Date of lasuance: June 9, 1999  :

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f ATTACHMENT TO LICENSE AMENDMENT NO.227 l FACILITY OPERATING LICENSE NO. DPR-49 )

DOCKET NO. 50-331 j 1

Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised aras are identified by amendment number and contain marginal lines indicating the areas of changs.

Remove Insert l lll lii l 3.6-11 3.6-11 l 3.7-19 3.7-20 l

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F 1 L. i TABLE OF CONTENTS y

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-3.7 PLANT SYSTEMS (continued) 3.7.6 Main Co.1 denser Offgas................................. 3.7-14 3.7.7 Mai n Turbi ne Bypass System . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.7-16 3.7.8 Spent Fuel Stcrage Pool Water Level . . . . . . . . . . . . . . . . . . . 3.7-18 3.7.9 Control Building / Standby Gas Treatment

. I n s t rument Ai r Sy s tem . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 7 - 19 ),

1 3.8 E LECTRI CAL POWER SY ST EMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 . 8 - 1 i 3.8.1 AC Sources - Operating................................ 3.8-1 3.8.2 ,

AC Sources - Shu tdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 8- 11 3.8.3 Diesel Fuel 01 . Lube Oil , and Starting Ai r . . . . . . . . . . . 3.8-14 3.8.4 DC Sources .- Oper c ti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8-17 3.8.5 DC Sources - Shutdown................................. 3.8-21 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.8-23 3.8.7 Di stri buti on Systems - Operating . . . . . . . . . . . . . . . . . . . . . . 3.8-27 3.8.8 Di stri bution Systems - Shutdown . . . . . . . . . . . . . . . . . . . . . . . 3.8-30 3.9 REFUELING 0PERATIONS...................................... 3.9-1 3.9.1 Refueling Equipment Interlocks . . . . . . . . . . . . . . . . . . . . . . . 3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock . . . . . . . . . . . . . . . . 3.9-3 3.9.3 Control Rod Posi ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3. 9- 5 3.9.4 Control Rod Posi tion Indication . . . . . . . . . . . . . . . . . . . . . . 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling . . . . . . . . . . . . . . . . . . 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level . . . . . . . . . . . 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level . . . . . . . 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level . . . . . . . . 3.9-13

'3.10 SPECIAL 0PERATIONS........................................ 3.10-1 3.10.1 System Leakage and Hydrostatic Testing Operation...... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing . . . . . . . . . . . . . . . . 3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown . . . . . . . . . 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown . . . . . . . . 3.10-9 3.10.5 Single Control Rod Drive (CRD)'

Removal - Refuel i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.10-13

.3.10.6 Multiple Control Rod Withdrawal - Refueling . . . . . . . . . . 3.10-16 3.10.7 Control Rod Testing - Operating . . . . . . . . . . . . . . . . . . . . . . 3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling . . . . . . . . . . . . . . . 3.10-20 4.0 DESIGN FEATURES .............................................. 4.0-1 4.1 Si te Locati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 . 0- 1 4.2 Re a c to r Co re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 . 0 - 1 4.3 Fuel Sto ra ge . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 0- 2 5.0 ADMI N I ST RAT I V E CONT R0 LS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 . 0 -

5.1 Responsibility........................................... 5.0-1 5.2 O rg a ni z a ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5. 0 - 2 5.3 Unit Staff Quali fications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.0 5 5.4 Procedures............................................... 5.0-6 l Prog rams and Manual s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.0- 7 t

5.5 Reporting Requi rements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5. 0-19 5.6 Hi gh Radi ati on Area . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5. 0- 22

, 5.7 l

iii Amendment No. 22 DAEC

-PCIVs 3.6.1.3 ACTIONS (continued)

. CONDITION. REQUIRED ACTION COMPLETION TIME

' D. .One or more D.1 Restore leakage to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> penetration flow paths within limits.

with one or more MSIVs not within leakage limits. ,

E. One or more E.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow paths- penetration flow path with one or more by use of at least containment purge one closed and

-valves not within de-activated )

purge valve leakage automatic valve,  ;

limits. closed manual valve, or blind flange.

E E.2 --------NOTE---------

Only required to be performed if a purge valve with resilient seal is used to satisfy Required Action E.1.

Restore leakage to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> within limits.

8 E.3 --------NOTE---------

Isolation devices in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path for isolation  !

is isolated. device outside j containment (continued) 3.6-11 Amendment No. 227 l DAEC l

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i CB/SBGT Instrument Air System

3.7.9 i L

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s 3.7: PLANT _ SYSTEMS 3.7.9' Control Building / Standby Gas Treatment (CB/SBGT) Instrument Air System .

1 LLCO 3.7.9 _Two' CB/SBGT In'strument. Air. subsystems shall be OPERABLE.

APPLICABILITY:: . MODES 1', 2, and 3.

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" ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A...OneCB/SBGT A.1- Declare required .

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> from Instrument Air- feature (s), supported discovery of .

6 subsystem by the inoperable Condition A inoperable. CB/SBGT. Instrument Air concurrent with inoperability of subsystem, inoperable  ;

when the' redundant redundant required required feature (s) feature (s) are inoperable.

MD A.2.- Restore the CB/SBGT 7 days Instrument Air  ;

subsystem to OPERABLE i

-status.

I B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

. Associated Completion Time of - MD

. Condition A not .

met.- B.2. Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> DB Both CB/SBG'T

. Instrument Air subsystems?

inoperable,

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DAEC- 3.7-19 Amendment No. 227

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. . *l CB/SBGT Instrument Air System

- 3.7.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FRE0VENCY SR 3.7.9.1 Operate each C8/SBGT Instrument Air 31 days compressor for 2 20 minutes.

SR 3.7.9.2 Verify each CB/SBGT Instrument Air 92 W vs

. subsystem actuates on an actual or .

simulated initiation signal and maintains air pressure 2 75 psig in the receiver.

I DAEC 3.7-20 Amendment No. 227

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