ML20141C937
| ML20141C937 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/15/1997 |
| From: | Kugler A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20141C940 | List: |
| References | |
| NUDOCS 9705190278 | |
| Download: ML20141C937 (8) | |
Text
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. t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 4
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DETROIT EDIS0N COMPANY DOCKET NO. 50-341 FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 112 License No. NPF-43 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated December 2, 1996, complies with the standards 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 Comission; 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 Comission's regulations;
)
D.
The issuance of this amendment will not be inimical to the comon 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.
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i 9705190278 970515 PDR ADOCK 05000341 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating' License No. NPF-43 is hereby amended to read as follows:
13chnical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.112, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
i DECO shall operate the facility in accordance with the Technical l
Specifications and the Environmental Frotection Plan.
3.
This license amendment is effective as of the date of its issuance with full implementation within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION B L //
Andrew J. Kug er, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
l Specifications Date of Issuance: May 15, 1997 i
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i ATTACHMENT TO LICENSE AMENDMENT NO. 112 FACILITY OPERATING LICENSE NO. NPF-43 1
DOCKET NO. 50-341 i
1 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
1 REMOVE INSERT 3/4 1-18 3/4 1-18 3/4 3-43 3/4 3-43 3/4 3-44*
3/4 3-44*
3/4 3-45*
3/4 3-45*
3/4 3-46 3/4 3-46 i
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- Overleaf page provided to maintain document completeness.
No changes on these pages.
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REACTIVITY CONTROL SYSTEMS ROD BLOCK MONITOR LIMITING CONDITION FOR OPERATION 3.1.4.3 Both rod block monitor (RBM) channels shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 30% of RATED THERMAL POWER.
ACTION:
a.
With one RBM channel inoperable:
1.
Verify that the reactor is not operating on a LIMITING CONTROL R0D PATTERN, and 2.
Restore the inoperable RBM channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Otherwise, place the inoperable rod block monitor channel in the tripped condition within the next hour.
b.
With both RBM channels inoperable, place at least one inoperable rod block monitor channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
SURVEILLANCE RE0UIREMENTS 4.1.4.3 Each of the above required RBM channels shall be demonstrated OPERABLE by performance of a:
CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION at the frequencies a.
and for the OPERATIONAL CONDITIONS specified in Table 4.3.6-1.
b.
CHANNEL FUNCTIONAL TEST prior to control rod withdrawal when the reactor is operating on a LIMITING CONTROL R0D PATTERN.
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I FERMI - UNIT 2 3/4 1-18 Amendment No. %), 112
_ _.. _ ~
TABLE 3.3.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION ACTION STATEMENTS ACTION 60 - Declare the R8N inoperable and take the ACTION required by Specification 3.1.4.3.
ACTION 61 - With the number of OPERABLE Channels:
a.
One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
b.
Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within I hour.
i ACTION 62 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 63 - With the numbr.r of OPERABLE channels less than required by the j
Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.
1.
TABLE NOTATIONS With THERMAL POWER greater than or equal to 30% of RATED THERMAL POWER.
l With more than one control rod withdrawn. Not applicable to control j
rods removed per Specification 3.9.10.1 or 3.9.10.2.
{
(a)
The RBM shall be automatically bypassed when a peripheral control rod is selected or the reference APRM channel indicates less than 30% of RATED THERMAL POWER.
i.
(b)
This function shall be automatically bypassed if detector count rate is
> 100 cps or the IRM channels are on range 3 or higher.
(c)
This function shall be automatically bypassed when the associated IRM c
channels are on range 8 or higher.
(d)
This function shall be automatically bypassed when the IRM channels are on range 3 or higher.
(8)
This function shall be automatically bypassed when the IRM channels are on range 1.
(f)
These two Source Range Monitors shall be OPERABLE as required by Specification 3.9.2.
FERMI - UNIT 2 3/4 3-43 Amendment No. #p, 112
l TABLE 4.3.6-2 CONTROL ROD BLOCK INSTRUNENTATION SETPOINTS j
TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE 1.
R00 BLOCK MONITOR e
a.
Upscale As specified in the As specified in the CORE OPERATING CORE OPERATING e5 LIMITS REPORT LIMITS REPORT w
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b.
Inoperative NA NA.
c.
Downscale a 94% of Reference level a 92.3% of Reference Level 2.
$_PRH a.
Flow Blased Neutron Flux - High
- 1) During two recirculation with a maximum of with a maximum of
-l s 0.63 W + 55.6%*
s 0.63 W + 58.5%*
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loop operatic.-
108%
110E
- 2) During single recirculation s 0.63 W + 50.5%
- s 0.63 W + 53.4%
- l
[
8 8
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loop operation b.
Inoperative NA NA c.
Downscale a 5% of RATED THERMAL POWER a 3% of RATED THERMAL POWER L
d.
Neutron Flux - Upscale, Setdown s 12% of RATED THERMAL l'0WER s 14% of RATED THERMAL POWER
)
i 3.
SOURCE RANGE MONITORS t
a.
Detector not full in NA NA 3
b.
Upscale s 1.0 x 105 cps s-1.6.x 105 cps l
,5 a.
c.
Inoperative NA NA i
j d.
Downscale a 3 cps **
a 2 cps **
l r+
- The APitM rod block function is verted as a function of rectreulethn loop drive flow (W).
- Ney be reshced to 1 S.F cpe provided the signal-to-noise retto g 29.
[
8ering single rueltculotten loop operetten, rather then adjusting the APet Flou Blased Setpoints to comply with the single leap values. the gain of l i Ok 8
the APIMs may be adjusted fee a period not to enceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> such that the final APWI readings are at leest s.ls of rated pouer greater then 2001 times FRTP. provided that the adjusted AMIN readings do not onceed 1001 of RATED THEllMAL POWER and a notice of adjustment is posted on the reactor l
go.
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control panel.
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TABLE 4.3.6-1 CONTROL ROD BLOCK INSTRUNENTATION SURVEILLANCE REOUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION 1.
R00 BLOCK MONITOR
_ CHECK TEST CALIBRATLOMja)
SURVEILLANCE REQUIRED a.
Upscale M
S/U
,Q Q
1*
b.
Inoperative NA S/U
,Q M
1*
c.
Downscale NA S/U
,Q Q
1*
2.
AEM a.
Flow Blased Neutron Flux -
,' 0 h
I b.
rative NA l.
,5 c.
Downscale S
S/U
,' Q d.
Neutron Flux - Upscale, Setdown S
S/U q
SA 2, 5 3.
SOURCE RANGE MONITORS
{
a.
Detector not full in M
S/g
,y M
2***,
5 b.
Upscale S
S/U
,W SA 2***, 5 c.
Increrative M
Sfg
,y M
2***,
5 d.
Dcwnscale S
S/U
,W SA 2***,
5 4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in M
S/U
,W NA 2, 5 b.
Upsr. ale S
S/U
,W SA 2, 5 c.
Inoperative M
S/U
,W M
2, 5 d.
Downscale S
S/U
,W SA 2, 5 5.
Water Level - High NA Q
R 1, 2, 5**
5 b.
Scram Trip Bypass M
R NA 2, 5**
=$
6.
REACTOR.C00UUff $YSTEM RECIRCULATION FLOW I
9 g=
a.
Upscale NA
$/U
,Q Q
l a
b.
Inoperative M
S/U
,Q M
1
=**
c.
Comparator NA S/U
,Q Q
l 7.
REACTOR _ MODE SWITCH SHUIDOWN POSITION NA R
M 3, 4 i
TABLE 4.3.6-1 (Continued) j CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE RE0VIREMENTS TABLE NOTATIONS (a)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(b)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
With THERMAL POWER greater than or equal to 30% of RATED THERMAL POWER.
l With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
With IRMs on Range 2 or less.
s
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FERMI - UNIT 2 3/4 3-46 Amendment No. f), 112