ML20066C681
| ML20066C681 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-33-A-177, DPR-52-A-182, DPR-68-A-148) |
| Issue date: | 12/31/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066C683 | List: |
| References | |
| NUDOCS 9101100427 | |
| Download: ML20066C681 (7) | |
Text
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jo UNITED STATES g
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i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
-Amendment No. 177-License No. DPR-33 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 6 1990, 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 au'thorized 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.
9101100427 901231 PDR ADOCK 05000259 P
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--2 2.
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. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.177, 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-and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Lc &
.h Frederick J. Heb on. Director Project Directorate 11 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:. December 31, 1990 i
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ATTACHMENT TO LICENSE AMENOMENT NO.177 FACILITY OPERATING LICENSE NO. DPR-33 00,CKET NO. 50-259 L
Revise the Appendix A Technical Spacifications by removing the pages identified below and inserting 'he enclosed pages. The revisea.pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.2/4.2-7 3.2/4.2-7 3.2/4.2-8 3.2/4.2-8*
3.2/4.2-12 3.2/4.2-12 3.2/4.2-13 3.2/4.2-13*
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L TABLE 3.2.A i
PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION c to
- s n M.inte.um No.
pZ Instrument Channels Operable g
Per Trio Svs(1)(11)
Function Trio tevel Settino Action (1)
Remarks j
i
-2
' Instrument Channel '-.
> 538" above vessel zero A or 1.
Below trip setting does i
Reactor Low Water Level (6)
(8 and E) the following:
i a.
Initiates Reactor i
Building Isolation' b.
Initiates Primary Centainment e
Isolation (Groups F
2, 3, and 6) 1 c.
Initiates SGTS.-
f 1
Instrument Channel -
100 2 15 psig D
1.
Above trip setting isolates i
t Eeactor High Pressure l
(PS-68-93 and 94) the shutdown cooling suction t
valves cf the RHR system.
2 Instrument Channel -
> 378" above vessel zera A
1.
Below trip setting initiates Reactor Low Water Level Main Steam Line Isolation u
- (LIS-3-56A-D, SW #1)
R 2
Instrument Channel -.
I 2.5 psig A or 1.
Above trip setting'does the c-High Drywell ' Pressure (6)
(B and E) following:.
-(PS-64-56A-D)'
g a.
. Initiates Reactor i.
u Building Isolation 5.' Initiates Primary-Containment Isolation i
- c. ' Initiates SGTS -
<o 3
CL B
(D D"
u N
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i TABLE 3.2.A (Continued)
PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION.
i C: D3 m
"2 Minimum No.
Instrument Channels Operable
'~
Per Trio Sys(1)(11)
Function Trio level Setting Action (1)
Remarks e
2 Instrument Channel -
3 times normal rated B
1.
Above trip setting s
High Radiation Main Steam full power background (13) initiates Main Steam Line
. [
i Line Tunnel (6)
Isolation 2
Instrument Channel -
1 825 psig (4)
B 1.
Below trip setting Low Pressure Main Stemn initiates Main Steam Line Line Isolation t
2(3)
Instrument Channel -
1 140% of' rated steam flow B
1.
Above trip setting.
4
_ High Flow Main Steam Line
' initiates Main Steam
' i Line Isolation 2(12)
Instrument Channel -
1 200*F B
1.
Above trip setting Main Steam Line Tunnel' initiates Main Steam High Temperature ta Line Isolation.
Ei 2(14)
Instrument Channel -
160 - 180*F C
1.
Above. trip setting 4
~;
i
~ * > -
Reactor Water Cleanup initiates Isolation
'a System Floor Drain of Reactor Water j,
High Temperature Cleanup Line from
'-l' Reactor and Reactor Water Return Line.
.i 2
Instrument Channel -
160 - 180*F C
1.
Same as above
' i Reactor Water Cleanup i
System' Space High Temperature..
t 1
Instrument Channel -
1100 mr/hr or downscale
-G 1.
I upscale or 2 downscale will s
Reactor. Building a.
Initiate SCTS Ventilation High b.
Isolate reactor zone and.
Radiation - Reactor Zone refueling floor.
c.
Close atmosphere i
control system.
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$QIES'FOR ABLE 3.2.A 1.
Whenever the respective functions are required to be OPERABLE ~there shall be two OPERABLE or tripped trip systems -for each function.
If the first-column cannot be met for one of the trip systems, that trip system or logic for that function shall be tripped (or the appropriate action listed below shall be taken).
If the column cannot be met for all trip systems, the appropriate action listed below shall be taken.
A.
Initiate an orderly shutdown and have the reactor in Cold Shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Water Cleanup System.
D.
Administrative 1y control the affected system isolation valves in the closed position within one hour and then dealare the affected system inoperable.
E.
Initiate primary containment isolation within 24 aours.
F.
The handling of spent fuel will be prohibited and all operations over spent fuels and open reactor wells shall be prohibit ed.
G.
Isolate the reactor building and start the standby gas treatment system.
H.
Immediately perform a logic system functional test on the logic in the other trip systems and daily thereafter not to exceed 7 days.
I.
Deleted J.
Withdraw TIP; K.
Manually isolate the affected lines. Refer-to Section 4.2.E for the requirements of an inoperable system.
L.
If one SGTS train is inoperable take actions H or A and F.
If two SGTS trains are inoperable take actions A and F.-
2.
When it is determined that a channel is failed in the unsafe condition,-
the other channels that monitor the same variable shall be functionally tested immediately before the trip system or logic for that function is tripped. The trip system or the logic for that function may remain untripped for short periods of time to allow functional testing of the other trip system or logic for that function.
3.
There are four sensors per steam line of which at lease one sensor per trip system must be OPERABLE.-
BFN 3.2/4.2-12 Amendment 177 Unit 1
@JES FOR IABLE 3.2.A-(Cont'd) t 4.
On required in RUN MODE (interlocked with Mode Switch).
5.
Not required in RUM MODE (bypassed by Mode Switch).
6.
Channel shared by RPS and Primary Containment & Reactor Vessel Isolation Control System. A channel failure may be a channel failure in each system.
7.
A train is considered a trip system.
8.
Two out of three SGTS trains required. A failure of more than one will require actions A-and F.
9.
Deleted 10.
Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups and their initiating signals.
11.
A channel may be placed in an inoperable status for up to four hours for
)
required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
12. - A channel contains four sensors, all of which must be OPERABLE for the channel to be OPERABLE.
Power operations permitted for up to 30 days with 15 of the 16 temperature switches OPERABLE.
In the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.
During periods when normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control room indicators of the affected space temperatures shall be monitored for indications of small steam leaks. In the event of rapid increases in temperature (indicative of steam line break), the operator shall promptly close the main steam line isolation valves.
13.
The nominal setpoints for alarm and reactor trip (1.5 and 3.0 times l
background, respectively) are established based on the normal background at full power. The allowable setpoints for alarm and reactor trip are 1.2-1.8 and 2.4-3.6 times background, respectively.
14.
Requires two independent channels from each physical location; there are two locations.
l BFN 3.2/4.2-13 Unit 1
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