ML20114A732
| ML20114A732 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/12/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114A733 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9208200267 | |
| Download: ML20114A732 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION gi E
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NEBRASKA PUBllC POWER DISTRICl D_0CKET NO. 50-298 00PER NVCLEAR STATI0f!
AliENDMENT TO FAClllTY OlTRATUJG llCENSE Amendment No.153 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated June 16, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
ad 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 Cemmission; 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 license 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.
9208200267 920012 PDR ADOCK 05000298-p PDA
D 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-46 is hereby amended to read as follows:
-t 2.
hcnnical Sqq.cificaijmi The-Tachnical Specifications contained in Appendix A, as revised tbmugh Amendment No.153, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specification >.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMalSS10N M
-fs,JohnT.Larkins, Director Project Directorate IV-1 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 12, 1992 L
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V ATTACHMEf4T TO LICEf4SE AMEf4DMEf1T f10.153 i
f_AGR ITY OPERATitJG LICEtJSE t10. DPR-46 DOCKET f40. 50-298 i
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.
i REMOVE PAGES ltJSERT PAGES 64 64 65 65 66 66 79 79 80 80
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COOPEh NUCLEAR STATION TABLE 3.2.E INSTRI' MENTATION THAT MONITORS DRYWELL LEAK DETECTION 4
Minimum Number of Action Required When Instrument Operable Components Component Operability Instrument I.D. No.
Setting Limit Is Not Assured (2)~
l Orywell Floor Drain Sump Flow RW-FT-354 N.A.
I A
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Dryvell Equipment Drain Susp RW-FT-364 U.A.
1 A
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Flow r
Air SamplinP System RMV-RM-4 A.B&C N.A.
1 A
l L
5 I
NOTES FOR TABLE 3.2..E 1.
The two (2) flow transmitters, one for the equipment drain sump and the other for the floor drain sump.
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comprise the basic instrument system.
E The air sampiing system is an alternate sy, tem to this system.
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2.
Action l
A.
Refer to Specification 3.6.C of this Technical Specification.
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. COOPER NUCLEAR STATION TABLE 3.2.F PRIMARY CONTAINMENT SURVEILLANCE INSTRUMENTATION Minimum Number Action Required When Instrument.
of Operable Minimum Condition Instrument I.D. No.
Range Instrument Channels Not Satisfied (1)
Reactor Water Level NBI-LI-85A
-150" to +60" 2
A,B,C NBI-LI-85B
-150" to +60" Reactor Pressure RFC-PI-90A 0 - 1200 psig 2
A.B.C RFC-PI-908 0 - 1200 psig Drywell cressure.
PC-PR-2A
-5 to 70 psig 2
A.B.C PC-PR-2B
-5 to 70 psig PC-PR-lA 0 - 250 psig 2
F PC-PR-1B 0 - 250 psig Drywell Terperature PC-TR-503 50 - 170*F 2
A,B,C PC-TI-505 50 - 350*F 1
Suppression Chamber / Torus PC-TR-21A 0 - 300*F 2
A.M.C Air Temperature PC-TR-23, Det I&2 0 - 400*F y
Suppret,sion Chamber / Torus PC-TR-24. Det la to th 0 - 250*F 1 (2)
Note 2 Water Temperature PC-TR-25 Det 2a to 2h 0 - 250*F Suppression Chamber / Torus j
Water Level PC-LI-10
(-4' to +6')
2 A,B.C PC-LR-il
(-4' to +6')
PC-LI-12
-10" to +10" 2
A.B.C.E y
PC-LI-13
-10" to +10" PC-LR-IA 0 - 30' 2
F 1
g PC-LR-1B 0 - 30' o
5 Suppression Chamber / Torus PC-PR-20 0 - 2 psig 1
B,C Pressure z
Control Rod Position N.A.
Indicating Lights I
A.B C.D y
Neutron Monitoring
'N.A.
S.R.M.,
I.R.M.,
1 A.B.C,0 O
LPRM y
0 - 100% power y
Primary Containment Oxygen PC-AN/CS-II /0 A Various 2 (3)
A,B,C 2 2 w
Concentration PC-AN/CS-II /0 B Va rious.
2 2 l
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NOTES FOR TABLE 3.2.F 1.
The following actions will be taken if the minimum number of operable instrument channels as required are not available.
A.
From and after the date that one of these parameters i educed to one indication, continued operation is permissible duo as the succeeding thirty days unless such instrumentation is sooner made operable.
B.
From and af ter the date that one of these parameters is not indicated in the control room, continued operation is permissible during the succeeding seven days unless such instrumentation is sooner made operable.
C.
If the requirements of A and B above cannot be met, an orderly shutdown shall be initiated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
These surveillance instruments are considered to be redundant to each other.
E.
In the event that both channels are inoperable and indication cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in Hot Shutdown in six (6) hours and in a Cold Shutdown condition in the following eighteen (18) hours.
F.
From and after the date that one of these parameters is reduced to one indication, either restore the inoperable component (s) to operable status within 30 days of the event, or prepare and submit a Special Report to the Commission outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
In the event that both channels are inoperable.and indication cannot be restored in fourteen (14) days, an orderly shutdown shall be initiated.
2.
Each channel contains eight detectors.
A channel is considered inoperable if rwo adjacent detectors are unmonitored by the channel in question.
A.
From and after the date that one channel becomes inoperable, continued operation is permissible during the succeeding seven days l-unless sooner made operable.
i S.
From and after the data that the second channel becomes inoperable.
L an orderly shutdown shall be initiated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> unless sooner made operable, t
3.
During periods when both channels are inoperable, grab samples may be taken to verify primary containment oxygen concentration.
-66 Amendment No. 50,90,9Z,ZZ2, 153 L
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COOPER NilCLEAR STATION
. TABLE 4.2.E MINIMtH TEST AND CAI.IBRATION FREQUENCY FOR DRYWELL LEAK DETECTION Instrument Item Item I.D. No.
Function Test Freq.
Calibration Freq.
Check Instruwent Channel 1.
Equiparent Drain Sump Flow RW-FT-(364)
Once/ Month (1)
Once/3 Months Once/ Day 2.
Floor Drain Sump Flow RW-FT-(354)
Once/ Month (1)
Once/3 Months Once/ Day 3.
Air Sampling System EMV-RM-4A, B. & C Once/ Month (1)
Once/3 Months once/ Day l
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COOPER NUCLEAR STATION TABLE 4.2.F PRIMARY CONTAINMENT SURVEILLANCE INSTRUMENTATION TEST AND CALIBRATION FREQUENCIES I
Instrument Ins t rtunent I.D. No.
Calibration Frequency Instrument Check Reactor Water Level NBI-LI-85A Unce/6 Months Each Shitt NBI-LI-858 Once/6 Months Each Shift Reactor Pressure RFC-PI-90A Once/6 Mocths Each Shift i
RFC-PI-90B Once/6 Months Each Shift l
Drywell Pressure PC-PR-2A Once/6 Months Each Shift PC-PR-2B once/6 Months Each Shift PC-PR-IA Once/6 Months Each Shift 3
PC-P".-1B Once/6 Months Each Shift Drywell Temperature PC-TR-503 Once/6 Months Each Shift PC-TI-505 Once/6 Months Each Shift i
f, Suppression Chamber / Torus PC-TR-21A Once/6 Months Each Shift y Air Temperature PC-TR-23, Det !&2 Once/6 Months Each Shift
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Suppression Chamber / Torus PC-TR-24, Det la to lh once/6 Months Each Shift Water Temperature PC-TR-25, Det 2a to 2h Once/6 Months Each Shift
, y y Suppression Chamber / Torus PC-LI-10 Once/6 Months Each Shift
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@ Water Level PC-LR-11 Once/6 Months Each Shift PC-LI-12 Once/6 Months Each Shitt i
g PC-LI-13 Once/6 Months Each Shift PC-LR-IA Once/6 Months Each Shift l
g PC-LR-1B Once/6 Months Each Shifs Suppression Chamber / Torus PC-PR-20 Once/6 Months Each Shift 82 Pressure w
e Control Rod Position N.A.
N.A.
Each Shift I
4
- Neutron Monitoring (APRM)
N.A.
Once/ Week Each Shift
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hPrimaryContainmentOxygen
-PC-AN/CS-H /0 A Once/3 Months Once/ Day 2 2 j
y Concentration PC-AN/CS-H /0 B Once/3 Months Once/ Day y 2 i
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