ML20149H512
| ML20149H512 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/11/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149H515 | List: |
| References | |
| NUDOCS 8802190301 | |
| Download: ML20149H512 (7) | |
Text
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o UNITED STATES
~,j NUCLEAR REGULATORY COMMISSION ap we.sHING TON, D. C. 20666
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HEBRASK4 PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. OPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated December 1, 1987, complies withthe stanaards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 l
Commission; C.
There is reasonable assurance (i) that the activities. authorized by this amendment can be conducted without endangering the health i
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 comon defense and security or te the health and safety of the l
public; and E.
The issuance of this amandment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable i
requirements have been satisfied.
8802190301 080211 DR ADOCK 05000290 l'DR 4
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ATTACHMENT TO LICENSE AMENOMENT NO.ll5 i
FACILITY OPERATING LICENSE NO. OPR-46 l
DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
t Pages 1
52 62
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67a 67b 4
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-E-t 2.
Accordingly 'the license is amenoec 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 reaa as follows:
(2) Technical Specificatio.!
lhe Technical Specifications contained in Appendix A. as revised through Amendcent No.,
, are hereby incorporated in the licer.se. T The licensee shall operate the facility in accordance with the
1 Technical Specifications.
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3.
The changes related to SRM/IRM powt.r supply bectue effctive 12 months 1
from this date.
The remaining changes are effective imediately.
1 1
FOR THE NUCLUR W;LATORY CCW!SSION i
I p' C. CMu a
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1 Jose A. Calvo. Director Project Directorate - IV Divition of Reactor Projects - 111.
IV. V and Special Projects Office of Nuclear Eeactor Etculation
Attachment:
Changes to the Technical Specifications j
Cate of Issuance: February 11, 1988 I
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4 NOTES FOR TABLE 3.2.A l.
Whenever Primary Containment integrity is required there shall be twc 1,
operaole or tripped trip systems for each function.
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2.
If the minimum number of operable instrument channels per trip system requirement cannot be met by a trip system, that trip system shall be tripped.
If the requirements cannot be met by both trip systems, the appropriate action listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in a cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
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B.
Initiate an orderly load reduction and have the Sain Steam Isolation Valves shut within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
C.
Isolate the Reactor Water Cleanup System.
D.
Isolate the Shutdown Cooling' System.
.].
Tvo, required for each steam line.
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_ 4.-
These signals also start the Standby Gas Treatment System and initiate
-Secondary Containment isolation.
5.
Not required in the refuel, shutdown, and startup/ hot' standby modes (interlocked with the mode switch).
6.
Requires one channel from each physical location for each trip system.
7.
Lov vacuu: isolation is bypassed when che turbine stop is not full open, manual bypass switches are in bypass and mode switch is not in RUN.
8.
The instruments on this table produce primary containment and system isolations.
The following listing groups the system signals and the system isolated.
Group 1 Isolation Signals:
1.
Reactor Low Low Low Water Level (>-145.5 in.)
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2.
Main Steam Line High Radiation (3 times full power background) 3.
Main Steam Line Low Pressure (3 25 psig in the RUN mode) 8 4.
Main Steam Line Leak Detection (<200'F) 5.
Condenser Low Vacuum (37" Hg vacuum) 6.
Main Steam Line High Flow (<150% of rated flow)
Isolations:
1.
MSIV's 2.
Main Steam Line Dcains Amendment No. 55,83,88.
115, _
W NOTES FOR TABLE 3.2.C 1.
For the startup and run positions of the Reactor Mode Selector Switch, the Control Rod Withdrawal Block Instrueentation trip system shall be operable for each function.
The SRM and IRM blocks need not be operable in "Run"
The Control Rod Withdrawal Block Instrumentation trip system is a one out of "n" trip system, and as such requires that only one instrument channel specified in the function column must exceed the Trip Level Setting to cause a rod block.
By utilizing the RPS bypass logic (see note 5 below and note 1 of Table 3.1.1) for the Control Rod Withdrawal Block Instrumentation, a sufficient number of instrument channels will always be operable to provide redundant rod withdrawal block protection.
2.
W is the two-loop recirculation flow rate in percent of rated. Trip level setting is in percent of rated power (23F1 MWt).
S is the RBM setpoint selected (in percent) and is calculated in accordance with the methodology of the latest NRC approved version of SEDE-240!!-P-A.
3.
IRM downscale is bypassed when it is on its lowest range.
4.
This function is bypassed when the count is > 100 cps and IRM above range 2.
5.
By design one instrument channel; i.e., one APRM or IRP per RPS trip syste,=
may be bypassed.
For the APRM's and IRM's, the minimum number of channels' specified is that minimum nu=ber required in each RPS channel and does not refer to a minimu= number required by.the control rod block instrueentation trip function.
By design only one of two RBM's or one of four STM's may be bypassed.
For the SRM's, the minimum nu=btr of channels specified is the mini =um nu=ber required in each of the two circuit loops of the Control Rod Block Instrumentation Trip Syste=.
For the RBM's, the minimum number of channels specified is the mini =ue number required by the Control Red Block Instru=entation Trip Syste: as a whole (except when a limiting control rod pattern exists and the require =ents of Specification 3.3.B.5 apply).
6.
IRM channels A,E,C,G all in range 8 or higher bypasses SRM channels A6C functions.
IRM channels B,F,D,H all in range 8 or higher bypasses SRM channels B&D functiens.
7.
This function is bypassed when IRM is above range 2.
8.
This function is bypassed when the mode switch is placed in Run.
9.
This function is only active when the mode switch is in Run.
10.
The inoperative trips are produced by the following functions:
a.
SRM and IRM (1) Mode switch not in operate (2)
Power supply voltage low (3)
Circuit boards not in circuit lI (4)
Loss of negative Supply voltage Amc'dment No. 77, 93, 94. 108, 115, i
COOPER NUCLEAR STATION TAlil.E 't.2.H POST-ACCIDENT HONITORING INSTRUMENTATION REQUIREMENTS
- Minimum Number of Action Required When i
Instrument Operable Isistrument Componcut Operability Instrument 10 Number Range Channels Is Not Assured Elevated Release Point (ERP) kHP-RM-3B 1.00E-2 to I (Note 1)
A I'
Honitor (High Range Noble 1.00E+5 pc/cc Cas)
(Xc-131 Equivalent) 1 Turbine Hulldiny Ventilation RMV-MM-20B 1.00E-2 to I (Note I)
A Exhaust Monitor 1.00E+5 pc/cc (Iligh Range Noble Cas)
(Xe-133 Eqt.Iva l en t )
Nadwaste/ Augmented Radwaste RHV-HM-30B 1.00E-2 to I (Note 1)
A Exhaust Honitor 1.00E+5 pc/cc b
(Iligh Range Noble Cas)
{
Equivalent)
Primary Containment Cross HMA-HH-40A 1.0-l.0E+7 R/Hr.
? (Note !)
A Radiation Hon' tor RMA-MM-408 1.0-1.0E+ 7 N /llr.
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- Note: Other Post-Accident Monitoring Instrumentation is located in Table 3.2.F-g Drywell Pressure, PC-PN-IA and IH, Suppression. Chamber / Torus Water I.evel PC-l.N-IA and IM M=
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- OTES FOR TABLE 3.2.H Action:
ith the nu,T.ber of operable components less than required by the minimum A.
component operable requirements, iniciate the preplanned alternate method of monitoring the appropriate parameter (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
1) either restore the inoperable cor,orent(s) to operable status within 7 days of the event. or 2) prepare and submit a Special Report to the Commission within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
1.
These instruments are required to be opersble at all times except when the reactor is in cold shutdown or in the REFUEL mode during a refueling outage, i
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l Amendment No. N,'ll5
<67b.
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