ML20215E420
| ML20215E420 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/08/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Central Iowa Power Cooperative, Corn Belt Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20215E423 | List: |
| References | |
| DPR-49-A-138 NUDOCS 8610150289 | |
| Download: ML20215E420 (5) | |
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UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION D
ej WASHINGTON. D. C. 20555
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE
. DOCKET N0. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.138 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al, dated December 6,1985 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 Comission; C.
There is reasonable assurance (1) 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations 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:
8610150289 061000 ~~
PDR ADOCK 0D000331 P
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
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Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 8, 1986
ATTACHMENT TO LICENSE AMENDMENT N0.138 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 areas are indicated by marginal lines.
Pages 3.7-23 3.7-26
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DAEC-1 TABLE 3,.7-2 (Continued)
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CONTAllMENT ISOLATION VALVES SU8 JECT TO TYPE C TEST REQUIREMENTS PENETRATION #
SYSTEM BOUNDARY VALVES 320 Containment Compressor Suction CV-4378A, CV-43788 32E Rectre Pump "A" Seal Purge V-17-96, CV-18048 32F Recirc Pianp "B" Seal Purge V-17-83, CV-1804A 35A,8,C,0 T.I.P Orives T.I.P Ball Valves and Check Valve on X-35A 361 CR0 Return V-17-53, V-17-52, V-17-54 39A Containment Spray / CAD Supply SV-4332A, SV-4332B 398 Containment Spray / CAD Supply SV-4331A, SV-43318 40C,0 Post-Accident Sampling / Jet Pump Sample SV-4594A, SV-45948, SV-4595A, SV-45958 41 Recire Loop Sample CV-46394, CV-4640 42 Standby Liquid Control V-26-8, V-26-9 46E O Analyzer SV-81058, SV-81068 z
48 Drywell Equipment Orain Discharge CV-3728, CV-3729 508 O Analyzer SV-8101A, SV-8102A, g
50E 0 Analyzer SV-8103A, SV-8104A, 2
500 O An alyzer SV-8105A, SV-8106A g
543 Reactor Building Closed Cooling Water Return M0-4841A 553 teactor Building Closed Cooling Water Supply M0-48418 56C 0 Analyzer SV-81018, SV-81028, 3
560 0 Analyzer SV-81038, SV-81048 2
205 Toret Furge Outlet CV-43004, CV-4301, C7-4309 211A Torus Spray / CAD Supply SV-4333A, SV-43338 2118 To us Spray / CAD Supply SV-4334A, SV-43348 2121 RCIC Turbine Exhaust V-24-84, V-24-23 V-24-46, V-24-47 2141 HPCI T irbine Exhaust V-22-16, V-22-174 V-22-63, V-22-64 3.7-23 Amendnent No. 106. 1/3. 131
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, TABLE 3.7-3 (Continued)
PRIMARY CONTAIPMENT POWER OPERATED ISOLATION VALVES Ntaber of Maximum Isolation Power Operating Action on Group Operated Time Normal Initiating (Note 1)
Valve Identification Valves (Seconds)
Position Signal 5
RWCU Supply 2
20 0
GC 5
RWCU Return 1
10 0
GC 6
Steau to HPCI Turbine 2
13 0'
GC 6***
HPCI Discharge to 1
20 C
GC Feedwater 6
Stem to RCIC Turbine 2
20 0
GC 6***
RCIC Discharge to 1
15 C-GC Feedwater 8
Condensate fram HPCI 2
NA 0
GC 8**
Condensate from RCIC 2
NA 0
GC 3
- Containment Compressor 3
NA 0
GC Discharge 7
- Reactor Building 2
20 0
GC Closed Cooling Water Supply / Return 7
- Well Cooling Water 4
NA 0
GC Supply / Return 9
HPCI/RCIC Exhaust 2
10 0
GC Vacuun Breaker 3
Post-Accident Supling 2
NA C
SC Liquid Sample Return i
l 3
Post-Accident Sapling 4
NA C
SC Jet Pump 5mpie
- 0ue to plant operational limitations, these valves will be subject to the requirenents of 4.7.0.1.a only.
- Low-Low Water Level Only
- These valves close only upon sensing closure of their respective turbine steam supply or turbine stop valve closure.
3.7-26 Amendment No. f2), 138
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