ML19225B406
| ML19225B406 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/15/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225B407 | List: |
| References | |
| NUDOCS 7907250117 | |
| Download: ML19225B406 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMisslON
{,
j WASHINGTON, D. C. 20555 IOWA ELECTRIC LIGHT AND POWER COMPANY ~
CENTRAL 10WA POWER COOPERATIVE CORN BELT POWER COOPERATIVE j
DOCKET f;0_. 50-331 I
DUANE ARNOLD ENERGY CENTER I
AMENDMENT TO FACILITY OPERATING LICENSE I
c e io. DPR-49 l
l l
1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, Central Iowa Power Cooperative, and Corn Belt Power Cooperative (the licensees) dated December 27, 1977, complies with the standards and
[
requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations i
set forth in 10 CFR Chapter I; i
B.
The facility will operate in ccaformity with the application, the provisions of the Act, and the rules and regulations of th' Comission; 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.
417 271 7907250117 D [$ 8 0 D 17
! t 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amende.d to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through knendment No. 51, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Y
S l
Thomas A. I polito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: June 15, 1979 417 272
ATTACHMENT TO LICENSE AMENDMENT NO. 51 FACILITY OPERAT'NG 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 number and contain vertical lines indicating the area of change.
Where there is an overleaf page, the overleaf page is provided for convenience; in these cases, the page that is being changed is underlined below.
Remove Replace 3.2-17/3.2-18 3.2-17/3.2-18 3.6-44 3.6-44 6.10-3 6.10-3 417 273
DAEC-1 NOTES FOR TABLE 3. 2-C 1.
For the startup and run positions of the Reactor Mode Selector Switch, there shall be two operable or tripped trip systems for each function.
The SRM and IRM blocks need not be operable in "Run ' mode, and the APRM xcept for APRM Upscale (Not in Run Mode [and RBM rod blocks need not be operable in "Startup" mode.
If the. first column cannot be met for one of the two trip systems, this andition may exist for up to seven days provided that during-that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the systen shall be tripped.
If the first column cannot be met for both trip systems, the systems shall be tripped.
2.
W is the recirculation loop flow in percent of design.'
Trip level setting is in percent of rated power (159 3 MWt).
Refer to Limiting Safety System Settings for variation with peaking factors.
Peaking factor is applicable only when it exceeds 2.61 (7 x 7 array) or 2.43 (8 x 8 array).
3.
IRM downscale is bypassed when it is on its lowest range.
This function is bypassed when the count rate is >100 cps.
4.
3.2-17
DAEC-1 5.
One of the four SRM inputs may be bypassed.
6.
This SRM function is bypassed when the IRM range switches are on range 8 or above.
7.
The trip is bypassed when the reactor power is 6 30%.
8.
Th'is function is bypassed when the mode switch is placed in Run.
07
,b 5 7
3.2-18
DAEC-1 TABLE 4.6-4 (cont.)
Identification No.
System Location Vendor Dwg. No.
GBC-9-SS-43 Main Stm. Relief Valve Drywell 6043 Discharge GBC-10-SS-24 Drywell 6024 GBC-10-SS-25 Drywell 6025 GBC-10-SS-39 Drywell 6030 GBC-10-SS-40 (2 ea.)
Drywell 6040 GBC-ll-SS-26 Drywell 6026 GBC-ll-SS-27 Drywell 6027 GBC-11-SS-32 Drywell 6032 GBC-ll-SS-33 Drywell 6033 SSB-1-MS Main Steam Drywell GE-BP 405 Rev 2 SSB-2-MS Main Steam Drywell GE-BP 406 Rev 3 SSC-1-MS Main Steam Dryweil GE-BP 407 Rev 2 SSC-2-MS Main Steam Drywell GE-BP 408 Rev 2 SSA-1-MS Main Steam Drywell GE-BP 401 Rev 1 SSA-2-MS Main Steam Drywell GE-BP 402 Rev 1 SSD-i-MS Main Steam Drywell GE-BP 403 Rev 1 SSD-2-MS Main Steam DryweT1 GE-BF 404 Rev 1 SSA-1 Recirc Drywell GE-BP 201 Rev 2 SSB-1 Recirc Orywell GE-BP 202 Rev 2 SSA-2 Recirc Drywell GE-BP 203 Rev 1 SSB-2 Recirc Drywell GE-BP 204 Rev 1 SSA-3 Recirc Drywell GE-BP 205 Rev 1 SSB-3 Recirc Drywell GE-BP 206 Rev 1 SSA-4 Recirc Drywell GE-BP 207 Rev 1 SSB-4 Recirc Drywell GE-BP 203 Rev 1 SSA-5 Recirc Drywell GE-BP 209 Rev i SSB-5 Recirc Drywell GE-BP 210 Rev i SSA-6 Recirc Drywell GE-BP 211 Rev 1 SSB-6 Recirc Drywell GE-BP 212 Rev 1 SSA-7 Recire Drywell GE-BP 213 Rev 1 SSB-7 Recirc Drywell GE-BP 214 Rev 1 SSA-8 Recire Drywell GE-BP 2'.5 Rev 1 SSB-8 Recirc Drywell GE-BP 216 Rev i SSA-9 Recirc Drywell GE-BP 217 Rev 1 SSB-9 Recirc Drywell GE-BP 218 Rev 1
' SSA-10 (2 ea.)
Recirc Drywell GE-BD 219 Rev 1 SSB-10 (2 ea.)
Recirc Drywell GE-BP 220 Rev 1 SSA-ll Recirc Drywell GE-BP 221 Rev 1 SSB-ll Recirc Drywell GE-BP 222 Rev 1 (2 ea.) - Indicates there are 2 snubbers with that nu=ber.
Modifications to this Table due to changes in high radiation areas should be submitted o the NRC as part of the next license amendment.
3.6-44
DAEC-1 7.
Records of training and qualification for current members of the. slant staff.
8.
Records of in-service inspections performed pursuant to these Technical _ Specifications.
9.
Records of Quality Assurance activities raquired by the OA Manual.
f 10 Records of reviews perfotrad for changes made to procedures or equip-ment or reviews of tests and experiments pursuant to 10 CFR 50.59.
11.
Records of meetings of the Operations Committee and the Safety Cemitt ee.
07 777 6.10-3
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