ML20213F621
| ML20213F621 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/10/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20213F624 | List: |
| References | |
| DPR-46-A-103, TAC 62768 NUDOCS 8611140347 | |
| Download: ML20213F621 (6) | |
Text
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated September 5, 1986, complies with the 5tdndards 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 (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 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 licensee 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-46 is hereby amended to read as follows:
8611140347 861110 PDR ADOCK 05000298 P
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(2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, 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 its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION q
m Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 10, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 103 FACILITY OPERATING LICENSE N0. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indiciated by marginal lines.
Pages 52a 168 173 l'
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l KOTES FOR TABLE 3.2.A (cent'd.)
Group 2 Isolation Signals:
1.
Reactor Low Water Level (+12.5 in.)
2.
High Dry Well Pressure (12 psig)
Isolations:
1.
RHR Shutdown Cooling System 2.
Drywell floor and equipment drain sump discharge lines.
3.
TIP ball valves 4.
Group 6 isolation relays Group 3 Isolation Signals:
1.
Reactor Low Water Level (+12.5 in.)
2.
Reactor Water Cleanup System High Flow (200% of system flow) 3.
Reactor Water Cleanup System High Area Temperature (< 200*F) 4 Reactor Water Cleanup System High System Temperature (1140*F)
Isolations:
1.
Reactor Water Cleanup System Group 4 Isolation Signals:
Provided by instruments on Table 3.2.B (HPCI)
Isolations:
Isolates the HPCI steam line Group 5 Isolation Signals:
Provided by instruments on Table 3.2.B (RCIC)
Isolations:
Isolates the RCIC steam line.
Group 6 Isolation Signals:
1.
Group 2 Isolation Signal 2.
Reactor Building H&V Exhaust Plenum High Radiation (<100 mr/hr)
Amendment No. 103
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COOPER NUCI. EAR STATT.ON TABLE 3.7.1 (Page 1)
,o PRIMARY CONTAINMENT ISOLATION VALVES
.R 3
Number of Power Maximum Action On Operated Valves Operating Normal Initiating Valve & Steam Inboard Outboard Time (Sec) (1)
Position (2)
Signal (3)
Main Steam Isolation Valves MS-AO A,B.C. & D 4
3<T<5 0
GC MS-AO A,B,C, & D 4
3<T<5 0
GC Drywell Floor Drain Iso. Valves 1
1 15 0
GC RW-AO-82, RW-AC-83 l
Drywell Equipment Drain 1
1 15 0
GC Iso. Valves RW-AO-94, RW-AO-95 m
Main Steam Line Drain 1
1 30 C
SC Valves MS-MO-74, MS-MO-77 Reactor Water Sample Valves 1
1 15 0
GC RRV-740AV, RRV-741AV P
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Reactor Water Cleanup System 1
1 60 0
GC Iso. Valves RWCU-MO-15. RWCII-MO-18 RHR Suction Cooling Iso.
I 1
40 C
SC Valve RHR-MO-17. RHR-MO-18 RHR Discharge to Radwaste 1
1 20 C
SC Iso. Valves RHR-MO-57, RHR-MO-67 e
Suppress')n Chamber Purge &
2 15 C
SC Vent P -245AV, PC-230MV Suppression Chamber N Supply 2
15 C
SC y
PC-237AV, PC-233MV i
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TABLE 3.7.4 PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES TEST PEN. NO.
VALVE NUMBERS MEDIA X-7A MS-AO-80A and MS-AO-86A, Main Steam Isolation Valves Air X-7B MS-AO-80B and MS-AO-86B, Main Steam Isolation Valves Air X-7C MS-AO-80C and MS-AO-86C, Main Steam Isolation Valves Air X-7D MS-AO-80D and MS-AO-86D, Main Steam Isolation valves Air X-8 MS-MO-74 and MS-MO-77, Main Steam Line Drain Air X-9A RF-15CV and RF-16CV, Feedwater Check Valves Air X-9A RCIC-AO-22 RCIC-MO-17, and RWCU-15CV, RCIC/RWCU j
Connection to Feedwater Air X-9B RF-13CV and RF-14CV, Feedwater Check Valves Air X-9B HPCI-AO-18 and HPCI-M0-57. HPCI Connection to Feedwater Air X-10 RCIC-MO-15 and RCIC-MO-16 RCIC Steam Line Air X-ll HPCI-MO-15 and HPCI-MO-16. HPCI Steam Line Air X-12 RHR-MO-17 and RHR-MO-18, RHR Suction Cooling Air X-13A RHR-MO-25A and RHR-MO-27A, RHR Supply to RPV Air X-13B RHR-M0-25B and RHR-MO-27B, RHR Supply to RPV Air X-14 RWCU-M0-15 and RWCU-MO-18, Inlet to RWCU System Air X-16A CS-MO-12A and CS-MO-12A, Core Spray to RPV Air X-16B CS-MO-llB and CS-MO-12B, Core Spray to RPV Air X-18 RW-732AV and RW-733AV, Drywell Equipment Sump Discharge Air X-19 RW-765AV and RW-766AV, Drywell Floor Drain Sump Discharge Air X-25 PC-232MV and PC-238AV, Purge and Vent Supply to D.ywell Air X-25 ACAD-1305MV and ACAD-1306MV, Supply to Drywell Air l
X-26 PC-231MV, PC-246AV, and PC-306 MV Purge and Vent l
Exhaust from Drywell Air i
X-26 ACAD-1310MV, Bleed from Drywell Air i
Amendment No. 80, 82, 88, 103
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