ML20067D799
| ML20067D799 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/06/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20067D801 | List: |
| References | |
| NUDOCS 9102130251 | |
| Download: ML20067D799 (15) | |
Text
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[fg UNITED STATES t
NUCLE AR REGULATORY COMMISSION 3e aI s
w Asm NO T ON, 0. C. 70666
%..../
LENNESSEEVALLEYAUTHORITY DOCKET NO. 50-260 EPOWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDHENT TO FACILfTY OPERATING LICENSE Amendment No.189 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Cossnission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee)datedJune4,1990,complieswiththestandardsand requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Connission'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 Cossnissien; C.
There is reasonable assurance (1) 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.
Tne issuance of this amendment will not be inimical to the cosenon 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.
9102130251 910206 DR ADOCK 050 0
' l 4
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this lictrse amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-52 is hereby atended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Art.cndment No.189, are hertby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendmcnt is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NilCLEAR REGULATORY COMMISSION
%4 bhb 6
4 rederick J. Hebdon, Director r
( Division of Reactor Projects - 1/11 Project Directorate 11-4, NRR Office of Nuclear Reactor Regulation Attachrent:
Changes to the Technical Specific:tions Date of issuance: February 6, 1001
s ATTACHMENT TO LICENSE AMENDHENT NO.189 FACILITY CPERATING LICENSE NO. OPR-52 00CKET NO. 50-260 Revise the Apptndix A Technical Specifications by removing the pages idt-ntified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf
- and spillover pages**
art 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 3.2/4.2-11 3.2/4.2-11*
3.2/4.2-11a 3.2/4.2-12 3.2/4.2-12*
3.2/4.2-13 3.2/4.2-13 3.2/4.2-42 3.2/4.2-42*
3.2/4.2-43 3.2/4.2-43 3.2/4.2 67 3.2/4.2-67 3.2/4.2-68 3.2/4.2-68*
3.7/4.7-30 3.7/4.7-30 3.7/4.7-31 3.7/4.7-31**
o i
TABLE 3.2.A PRIfMRY CONTAINMENT AND REACTOR BUILDING IS0t.ATION INSTELPENTATION 1
E$
Minimum No.
O%
Instrument i
Channels Operable N
Per Trio Sys(1)(11)
Function Trio Level Setting Action (11 Remarks 2
Instrument Channel -
1 538" above vessel rero A or 1.
Below trip setting does l
Reactor tow Water Level (6)
(8 and E) the following:
(LIS-3-203 A-D) a.
Initiates Reacter Building Isolation b.
Initiates Primary Containment Isolation j
c.
Initiates SGTS 1
Instrument Channel -
100 2 15 psig D
1.
Above trip setting isolates Reactor High Pressure the shutoown cooling suction (PS-68-93 and -94) valves of the RNR System.
2 Instrument Channel -
139B" above vessel stro A
1.
Below trip setting l
Reactor low Water initiates Main $ team u
Level (LIS-3-564-D)
Line Isolation tJ s
2 Instrument Channel -
1 2.5 psig A or 1.
Above trip setting does the High Drywell Pressure (6)
(8 and E) following:
to (PIS-64-56A-0) a.
Initiates Reacter L
Building Isolation b.
Initiates Primary 1
Containment Isolation c.
Initiates SGTS 3CEW
=9 N
CZ2 4
.I
i TABLE 3.2.A (Cw tinued)
PRIftMY CD4TAIM*.ENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION e,
1 n
- s OZ Minimum No.
i Instrument
'3 Channels Operable
[
Per Trio Sys(1)(11)
Function Trio level Settim Action (1)
Recarts 2
Instrument Channel -
1 3 times r.ormal rated B
1 Atove trip setting i
t F
High Radiation Nin Steam full power L -dground Line Tunnel (6) initiates Main Steam Line Isolation
[
2 Instrument Channel -
1 825 psig (4)
B 1.
Below trip setting low Pressure Mair' Steam line initiates Main Steam Line Isolation (PIS-1-72, 76, 82, 26) 2(3)
Instrument Channel -
1 140% of rated steam flow B
1.
Above trip setting i
i High Flow Main Steam Line initiates Main Steam (PdIS-1-13A-D. 254-D, Line Isolation 36A-D, SOA-D) 2(12)
Inst w.t Channel -
1 200*F B
1.
Above trip setting Main Steam Line Tunnel y
initiates Main Steam 1
ea High Teeperature Line Isolation.
t l
2 1
Instrument Channel -
1 100 mr/hr or dr -scale G
1.
1 upscale or 2 downscale will Reactor Building g
a.
Initiate SGTS.
Ventilation High b.
Isolate reactor rene and O'
Radiation - Reactor Zone j
refueling floor.
}
c.
Close atmosphere control system.
I B
CL E3 O
3 i
to i
r t
t E
C t
O
v TABLE 3.2.A (Continued)
FRIt%RY CONTAINMENT AND REACTOR BUILDING ISCLATION IN**'1JMENTATIOPe c es 5E a
Minimum No.
Instrument
,a Chennels Operable Per Trio Sys(1)(11)
Function Trio Level Settino Action (1)
Remark s 1
Reactor Building Isolation N/A H or F (refueling floor) Logic 1
Reactor Building Isolation N/A H or G (reactor zone) Logic or A 1(7) (8)
SGTS Train A Logic N/A L or (A and F) 1(7) (8)
SGTS Train B Logic N/A L or (A and F) 1(7) (8)
SGTS Train C Logic N/A L or (A and F) y Refer to Table 3.2.8 for RCIC and HPCI functions including Groups 4. 5. and 7 valves.
U r
G l
TABLE 3.2.A (Continued)
PRIt'ARY CONTAINMDiT AND REACTOR BUILD' NG ISOLATION INi~2UPsENTATION Minimum No.
e,
- s ~
Instrument l7 7-Channels Operable Per 1rio Sys{1)(11)
Fuw tion Trio Level Settino Action (1)
Re*ta rk s sa 2
Instrumt Channel i 201.0*F
.C Above Trip Setting Peacter Water Cleanup initiates Isolation of l
System Main Steam Reactor water Cleanup l
Valve Vault Lines to and from the (T15-069-834A-D)
Reactor 2
Instrument Channel i 135.O*F C
Above Trip Setting Reactor Water Cleanup initiates Isolation of System Pipe Trench Reactor Water Cleanup
( TIS-069-835A-D)
Lines to and from the Reactor 2
Instrument Channel i 152.0*F C
Above Trip Setting Peactor Water Cleanup initiates Isolation cf System Pump Room 2A Reactor Water Cleanup
( TIS-069-436A-0) tines to and fress the u
Reactor S
2 Instrument Channel i 152.0*F C
Above Trip Setting L
Reactor Water Cleanup initiates Isolation of System Pump Room 2B Reactor Water Cleanup C
(TIS-069-837A-0)
Lines to and frw the Reactor o
2 Instrument Channel i 143.0*F C
AW Trip Setting Reactor Water Cleanup initiates Isolation of System Heat Enchanger Reacter Water Cleamsp y-Room (TIS-469-833A-D)
Lines to and f rom the Reactor i
a
~
2 a
2
-,. - ~. -..
. ~. - _. - -
4 L
I
--ROTES FOR TABLE 3.2.P 4
1 1.
Whenever the respective functions are required to be OPERABLE there shall i
be two OPERABLE or tripped trip systems for each function.
If the first i
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 l
systems, the appropriate action listed below shall be taken.
j A.
Initiate an orderly shutdown t.nd 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 />.
I B.
Initiate an orderly load reduction and have Main Steam Lines isolated i
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 declare the affected system
,4 inoperable.
E.
Initiate primary containment isolation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
T.
The handling of spent fuel will be prohibited and all operations over spent fuels and open reactor wells shall be prohibited.
G.
Isolate the reactor building and start th'e standby gas treatment system.
l H.
Immediately perform a logic system functional test on the logic in the other trip systems and daily thereafter not to exceed 7 days.
1 1.
Deleted J.
Withdraw TIP.
k K.
Manually isolate the affected lines. Refer to Section 4.2.E for the requirements of an inoperable system.
4 L.-
If one SGTS train is inoperable take actions H or A and F.
If two I:
SGTS trains are-inoperable take actions A and F.
2.
When it is determined that a channel'is failed in the unsafe condition, tne other channels that monitor the sar.e eariable shall be functionally tested immediataly before the trip system or-logic for that function is-tripped.
The trip system or the logic for that function may remain untcipped 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 least one sensor per-i trip system must be OPERABLE.
i AMEDMai NO.18 2 BrN 3.2/4.2-12 Unit 2
NOTES ron TAmtr 3.2.A (Cent'd) 4 Only required in RUN MODE (interlocked with Mode Switch).
t 5.
Not recuir ed in RUN MODE (bypassed by Mode Switch).
a 6.
Channtl sl.ared by RPS and Primary Containment & Reactor Vessel Isolation i
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 falAure of more than one will require actions A and T.
9.
Deleted I
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 survelliance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system g
is monitoring that parameter.
Power operations permit'.ed for up to ?,0 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 1
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 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.
I L
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BrN 3.2/4.2-13 Amendment 189 Unit 2
t' TABLE 4.2.A (Cont'd)
SURVEILLANCE REQUIREMENTS FOR PRIPERY CONTAINMENT AND REACTOR BUILDING IWLATIUpt 145TRUP*ENTAT10N cM pZ Function F_unctional Test' (aliLration Freomtcy Instrtment Cheik f
l Group 1 (Initiating) Logic Checked during channel N/A N/A i
l ea l
fisnctional test. No further test rep; ired.(11).
[
Group 1 ( Actuation) Logic Once/ operating cycle (21)
N/A N/A Group 2 (Initiating) togic Checked during channel N/A N/A i
functional test. No forther test required.
Group 2 (RHR Isolation-Actuation)
Once/ operating cycle 121)
N/A N/A I
Logic Group 8 (Tip-Actuation) Logic Once/ operating cycle (21)
N/A N/A t
Group 2 (Drywe11 Sump Drains-Once/ operating cycle (21)
N/A N/A t
Actuation) Logic F
Group 2 (Reactor Niloing an4 Once/ operating cycle (21)
N/A N/A Refueling floor, sod Drywell 3
r>)
Vent and Purge-Actuction) Legic
'f Group 3 (Initiating) Logic Checked during channel N/A N/A functional test. No further test required.
Group 3 (Actuation) Logic Once/ operating cycle (21)
N/A N/A 4
i 4
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TABLE 4.2.A (Cont'd) e a, SURVEILLANCE REQUIREMENTS FOR PRIMILRY CONTAINMENT AND REACTOR BUILDING IS0tATION INSTRUPENTATION Functior.
Functional Test Calibration Frees e instwt Chesi a
i Group 6 Logic Once/ operating cycle N/A N/A (15) l Group 8 (Initiating) Logic Checked during channel N/A N/A
(
functional test. Ne l
further test required.
Reactor Building Isolation Once/6 months (18)
(6)
N/A (refueling floor) Logic Reactor Bo4Tding Isolation Once/6 months (18)
(6)
N/A i
(reactor zone) Logic SGTS Train A Logic Once/6 months (19)
N/A N/A SGTS Train B Logic Once/6 months (19)
N/A N/A i
i SGTS Trein C Logic Once/6 months (19)
N/A N/A i
Instrument Channel -
(T)(27) 4 months N/A Reactor Water Ciesnop System Main Steam valve i
f Vault L
1 w
(TIS-069-834A-0)
Instrument Channel -
(1)(27) 4 months N/A 7
Reactor Water Cleanup System Pipe Trench
(
e" (TIS-069-835A-0) p Instrument Channel -
(1)(27) 4 months N/A i
y System Pump Room 2A g
( TI S-069-83t>A-D) 5 Instrument Cha:anel (1)(27) 4 months N/A Reactre Water Cleanup a
System Pump Room 28 (TIS-069-837A-D) t Instrument Channel (1)(27) 4 months N/A Reactor Vater Cleanup System Heat Enchanger Room (TIS-069-83SA-0) i l
i
^
t L
w
3.2 BASES (C:nt'd) flow instrumentation is a backup to the temperature instrumentation.
In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200'T.
The triperature increases can cause an unnecessary main steam line isolation and reactor scram. Permisalon is provided to bypass the temperature trip for four hours to avoid an unnecessary plant transient and allow performance of the secondary containment leak rate test or Eske repairs necessary to regain normal ventilation.
High radiation monitors in the main steam line tunnel have been provided to detect gross fuel failure at in the control rod drop accident. With the established nominal setting ci three times normal background and main steam line isolation valve clocore, fission product release is limited so that 10 CPR 100 guidelines are not exceeded for this accident.
Reference Section 14.6.2 PSAR. An alarm with e. nominal setpoint of 1.5 x normal full-power background is provided also, Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 825 psig.
The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping. Tripping of this instrumentation results in cetuation of HPCI isolation valves. Tripping logic for the high flow is a 1-out at-2 logic, and all sensors are required to be OPERABLE.
High temperature in the vicinity of the HPCI equipment is sensed by four sets of four bimetallic temperature switches. The 16 temperature switcher sre arranged in two trip systems with eight temperature switches in each trip system.
Each trip system centists of two elements. Each channel contains osa temperature evitch located in the pump room and three temperature switches located in the torus area. The RCIC high flow and high area temperature sensing instrument channels are arranged in the same manner as the HPCI system.
The HPCI high steam flow trip setting of 90 ps_. and the RCIC high steam flow trip setting of 450" H O have been selected such that the trip 2
setting is high enough to prevent spurious tripping during pump startup but low enough to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
The HPCI and RCIC steam line space temperature switch trip settings at:
high enou6h to prevent spurious isolation due to normal temperature excursions in the vicinity of the steam supply piping. Additionally, these trip settings ensure' that the prinary containment isolation steam supply valves isclate a break within an acceptable time period to prevent core uncovery and maintain fission product releases within 10 CFR 100 limits.
High temperature it the Reactor Water Cleanup (RWCU) System in the main steam valve vault, RhCU pump room 2A, RWCU pump room 2B, RWCU heat tychanger room or in the space near the pipe trench containing RWCU piping could indicate e break in the cleanup system.
When high temperature occurs, the cleenup system is isolated.
BFN 3.2/4.2-67 Amendment 189 Unit 2-
4 3.2 BAEEE (Ccnt'd)
The instrument >; ion which initiates CSCS action to arranged in a dual bus-system. As:for other vital instrumentation arranged in this fashion, the specification preserves'the effectiveness of the system even during periods when maintenance or testing is being performed. An exception to this is when logic functional testing is being performed.
The control rod block functions are provided to prcrent excessive control rod withdrawal so that MCPR does not decrease to 1.07.
The trip logic for this function is 1-out-of-n e.g., Sny. trip on one of sir APRMs, eight IRMs, or_four SRMs will respit in a rod block.
The minimum instrument chcanel requirements assure sufficient in=trumentation to assure the single failure criteria is met. The minimem instrument channel requirements for the RBM may be reduced by one for mairtenance, testing, or calibration. This does not significant)y.
increase the risk of an inadvertent control rod withdrawal, as the other channel is available, and the RBM is a backup system to the written sequence for-withdrawal of control rods.
The APRM rod' block function is flow biased and prevents a significant reduction'in MCPR, especially during operation at reduced flow. The APRM provides gross core protection; i.e.,
limits the gross core power increase from withdrawal of control rods in the normal withdrawal seo"ence. The trips are set so that MCPR is maintained greater than 1.07.
The RBM-rod block tanction provides local protection of the core; i.e.,
the prevention of critical power in a local region of the core, for a tingle rod withdrawal error from a limiting control rod pattern.
If the IRM channels are in the-worst condition of allowed bypesa, the sealing arranger.ent is such that for unbypassed IRM channele, a rod block
-signal is generat'; before the detected neutrons flux has increased-by more than a tacto'. of 10.
A downscale indication is an indication the instrument has failed or the instrument to not sensitive.enough. 2n-either case the instrument wil' rot respond f.o changes in control rod motion and thus, control rod L;cion is prevented.
The refueling interlocks-also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
For. effective emergency core cooling for small pipe breaks, the HPCI system must function since-reactor pressure does not decrease-rapid enough to allow eithet : ore spray or LPCI to cperate in time. The automatic pressure relief function is provided as a backup to the HPCI in the event the KPCI does not operate. -The arrangement of the tripping contacts ia auch as to provide this function when necessary and minimize spurious operation. The trip settings given in the specification are AMENDMENT NO.18 7 BFN 3,2/4.2-68 Unit 2
ROTES FOR TABLE 3.7 1 Key: 0 = Open C = Closed SC = Stays Closed GC = Goes Closed No t e r - Isolation groupings are as follows:
Group 1: The valves in Group 1 are actuated by any one of the following conditions:
1.
Reactor Vessel Low Low Low Water Level (1 398")
2.
Main Steamline High Radiation 3,
Main Steamline High Flow 4
Main Steamline Space High Temperature 5.
Main Steamline Low Pressure Group 2:
The valves in Group 2 are actuated by any of the following conditions:
1.
' Reactor Vessel Lcv Water Level (538")
2.
High Drywell Pressure Group 3! The valves in Group 3 are actuated by any of the following conditions:
4 1.; Reactor Low Water Level (538")
2.
Reactor Water Cleanup (RWCU) System High Temperature in the main-steam valve vault, 3.
RWCU System High Temperature in RWCU pump room 2A, 4.
RWCU System High Temperature in the RWCU pump room ?.3, 5.
RWCU-System High Temperature in RWCU heat exchanger room, 6.
RWCU System High Temperature in the space near the pipe trench containing RWCU piping.
Group 4:
The valves in Group 4 are actuated by any of the following conditions:
1.
HPCI Steamline Space High Temperature 2.
HPCI Steamline High Flow 3.
HPCI Steamline Low Pressure 4.
HPCI Turbine Exhaust Diaphragm High Pressure Group-5: The valves in Group 5 are actuated by any of the following conditions:
l '. - RCIC Steamline Space High Temperature 2.
RCIC Steamline High Flow 3.
RCIC Steamline Low Pressure 4.
RCIC Turbine' Exhaust Diaphragm High Pressure L
BFN-3.7/4.7-30 Amendment 189 Unit 2-
[
NOTES POD TABLE 3.7.A (Continued)
~ Group 6: The valves:in Group 6 are actuated by any of the following conditions:
1.
Reactor Vessel Low Water Level ($38")
2.
High Drywell Pressure.
3.
Reactor Building Ventilation High Radiation Group 7: The valves in Group 7 are tutomatically actuated by-only the following condition:
1.
The respective turbine steam supply valve not fully closed.
Group 81 The valves in Group 8 are automatically actuated by only the following conditions:
- 1. = High Dryvell Pressure 2., Reactor Vecsel Low Water Level-(538")
i
- BFN 3.7/4.7-31 Amendment 189 i
Unit 2:
)
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_ - _ _ - _ _ _ - - - _. _ _ _