ML20209B731
| ML20209B731 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 04/20/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20209B734 | List: |
| References | |
| NUDOCS 8704280504 | |
| Download: ML20209B731 (8) | |
Text
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UNITED STATES f
g NUCLEAR REGULATORY COMMISSION g
a WASHINGTON, D. C. 20655 g.....,/
i NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
M A.
The a lication for amendment by Nebraska Public Power District (the censee) dated July 2,1986, as modified by letter dated December 29 1986, complies with the standards and requirements 4
of the Atomic Energy Act of 1954, as amended the Act), and the
%j, Commission's rules and regulations set forth n 10 CFR Chapter I; L
B.
The facility will operate in conformity with the application, the
{
provisions of the Act, and the rules and regulations of the Commission; f.
i 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; 5
0.
The issuance of this amendment will not be inimical to the common f..
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 license 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:
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o (2) Technical Specification The Technical Specifications contained in Appendix A, as revised through Amendment No.108, 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 COP 9 FISSION di. dM
- w:r 4
Jose A. Calyo, Director Pro iect Directorate - IV
- y..
,p Div;1sion of Reactor Pro;'ects - III,
- y IV, V and Special Pro;'ects k
Attachment:
Changes to the Technical Specifications Date of Issuance: April 20, 1987
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1 ATTACHMENT TO LICENSE AMENDMENT NO. 108 FACILITY OPERATING LICENSE NO. 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 28 31 61
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COOPER NUCLEAR STATION l
TABLE 3.1.1 REACTOR PROTECTION STSTEM INSTRUMENTATION REQUIREMENTS Minimum Number Action Required l
Applicability Conditions of Operable When Equipment Reactor Protection Mode Switch Position Trip Level Channels Per Operability is System Trip function Shutdown Startup Refuel Run Setting Trip Systems (1)
Not Assured (1)
Mode Switch in Shutdown I(7)
I I
I 1
A l
l Manual Scram I(7)
I I
I I
A 1
i High Flux
-< 120/125 of in-3 A
IRN (17)
I(7)
I I
(5) dicated scale' l
Inoperative I
I (5) 3 A
APRM (17)
I < (0.66W+54%-0.66aW)
FRP 2
C High Flux (Flow biased)
(14)(19)(20)
MFLPD l
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l Migh Flux Z(7)
Z(9)
I(9)
(16) i 15% Rated Power 2
A l
Inoperative I(9)
Z(9)
I (13) 2 A
Downscale (12)
(12)
(12)
I(11) > 2.5%
2 A
l l
High Reactor Pressure I(9)
X(10)
I
< 1045 psig 2
A NBI-PS-55 A.B.C. & D l
f High Dryidik Messre I(9)(8) Z(8)
I
< 2 psig 2
A or D
-. ~..
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g PC-PS-12 A.S $6 &D ReactorISwWaterLevel I
I I
-> + 12.5 in. indi-2 A or D f
NBI-LIS-101 A.B.C. & D cated lesel I Scram Discharge Instrument Volume I
Z(2)
I
-< 92 inches 3 (18)
A High Water Level o
CRD-LS-231 A & B CRD-LS-234 A & B CRD-LT-231 C & D CRD-LT-234 C & D
c.
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11.' The'APRM down:1310 trip fcnction to only C2tiv3 when the reactor 1sode' switch is in RUN. When in RUN this function is. automatically bypagee.d.
when the companion IRM instrumentation is operable and not upscalm.
- 12. The APRM downscale trip is automatically bypassed when the mode switch is not in RUN.
- 13. An APRM will be considered inoperable if there are less than 2 LPRM inputs per level or there is less than 11 operable LPRH detectors to an APRM.
- 14. W is the two-loop recirculation flow in percent of rated flow.
- 15. This note deleted.
- 17. The APRM and IRM instrument channels function in both the Reactor Protection System and Reactor Manual Control System (Control Rod Withdraw Block, section 3.2.C.).
A failure of one chpanel will affect both of these systems.
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- 18. The minimum number operable associated with the Scram Discharge Instrument Volume are three instruments per Scram Discharge Instrument Volume and y
thraa level devices per RPS channel.
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- 19. AW is the difference between two-loop and single-loop effective drive flow and is used for single recirculation loop operation. AW-0 for two recirculation loop operation.
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- 20. The ratio of PRP (fraction of rated thermal power) to MFLPD (maximum fraction of limiting power density) shall be set equal to 1.0 unless g
the actual operating value is less than the design value of 1.0 in
..F which case the actual operating value will be used.
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3g Amendment No. 39. 46. 86. St.
$$, M,108
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,p COOPER NUCLEAR STATION TABLE 3.2.C CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION Minimus Number Of Function Trip Level Setting Operable Instrument,
Channels / Trip Systee(5)
AFEN,Upecale (Floer Bias) 1 (0.66W + 42% - 0.66 AW) 'FRP (2)(13)(14) 2(1)
AFRN Upscale (Startup) 1 12%
MFLPD 2(1) 2(1)
AFEN Downscale (9) 1 2.5%
APEN Isoperative (10b) 2(1)
REN Upecale (Flow Bias)
$ 0.66W + (N - 66) (2) 1 REM Downscale (9) 1 2.5%
1 REM Isoperative (10c)
I IRN Upecale (8) i 108/125_
,3(1) of Full Scale g
Y IEN Downscale (3)(8) 1 2.5/125 of Full Scale '
3(1) l IEN Detecter Not Fall In (8) 3(1)
IEN Isoperative (8)
(10e) 3(1)
{ SEN Upecale (8) 1 1 x 10 Counts /Second 1(1)(6)
SWE Detector Not Full In (4)(8)
(1 100 cys) 1(1)(6) o SENIsoperative,[(8)
(los) 1(1)(6) o Flow Bias Comparator 3 101 Bifference la Recire. Flows I
.h L *, Flow Blas Specale/Isop.
1 1101 Recire. Flow I
E'M SEM Doumecale (8)(7) 13 Counta/Second (11) 1(1)(6) u
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SDV Water Level Righ
< 46 inches 1(12)
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CRD-231E, 234E
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INNRS F0it TABLE 3.2.C 1.
For the startup'and run positions of the Reactor Mode Selector Switch, the Control Rod Withdrawal Block Instrumentation trip system shall be operable for each function. The SRM and IRM blocks need not be operable in "Run" mode, and the APRM (flow biased) and REN rod blocks need not be operable in "Startup" mode. 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 escoed.the Trip Level Setting to cause a rod block.
By utilising the RFS 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 (2381 MWt). N is the REM setpoint selected (in percent) and is calculated in accordance with the methodology of the latest NRC approved version of NEDE-24011-F-A.
3.
IRM downscale is bypassed when it is on its lowest range.
4.
This function is bypassed when the count is 3,.100 cys and IRN above range 2.
^
5.
By design one instrument chancel; 1.e., one AFRM or IRM per RFS trip system may be bypassed.
For the APRM's and IRM's,.the minimum number of channels t-specified is that minimum number required in each RFS channel and does not refer to a minimum number required by the control rod block instrumentation trip function. By design only one of two REN's or one of four SRM's may be bypassed.
For the SRM's, the minimum number Of channels specified is the minimum number required in each of the[two circuit loops of the Control Rod Block Instrumentation Trip System. For the REM's, the minimum number of channels specified is the minimum member required by the Control Rod Block Instrumentation Trip System as a wholet(encept when a limiting control rod r,
pattern exists and the requirements of Specification 3.3.5.5 apply).
l g'e 6.
IRM channels A.E.C.G all in range 8 or' higher bypasses SRM channels A&C functions.
21 IRM channels B.F.D,H all in range 8 or higher bypasses SEM channels B&D functions.
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7.
This function is bypassed when IBM is above range 2.
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8.
This function is bypassed when the mode switch is placed in Run.
f 9.
This function is only active when the mode switch is in Run.
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- 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 f
(3) Circuit boards not in circuit 4,
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' Amendment No. M, N, M 108
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NOTES @R TASLE 3.2.C (Continued)
(1) Mode switch not in operate (2) Less than 11 LPRM inputs (3) Circuit boards not in circuit c.
RBM (1) Mode switch not in operate (2) Circuit boards not in circuit (3) RBM fails to null (4) Less than required number of LFRM inputs for rod selected
- 11. During spiral unloading / reloading, the SRM count rate will be below 3 cps for some period of time. See specification J.10.3.
- 12. With the number of OPERABLE channels less than required by the Minimum Number of Operable Instrument Channels / Trip System requirements, place the inoperable channel in the tripped condition within one hour.
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- 13. &Wisthedifferencebetweentwo-loopand'singie-loopeffectivedrive
- )
flow and is used for single recirculation loop operation. AW=0 for two recirculation loop operation.
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- 14. The ratio of FRF (fraction of rated thermal power) to NFLpD (aazimum fraction of limiting power density) shall be set equal to 1.0 unless the actual value is lees than the design value of 1.0, in which case che a6toal operating value will be used.
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Amendment No. $J, 77, $$.108