ML20154E116
| ML20154E116 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-33-A-154, DPR-52-A-150, DPR-68-A-125) |
| Issue date: | 09/02/1988 |
| From: | Black S NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20154E119 | List: |
| References | |
| TAC-00095, TAC-00096, TAC-00097, TAC-95, TAC-96, TAC-97, NUDOCS 8809160218 | |
| Download: ML20154E116 (27) | |
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UNITED STATES o,
8 NUCLEAR REGULATORY COMMISSION g-t W ASHIM2 TON. D. C. 20665
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TENNESSEE VALLEY AUTHORITY 00CKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 i
APEN0 MENT TO FACILITY _0PERATING LICENSE Amendment No. 154 1
License No. OPR-33 i
f 1.
The Nuclear Regulatory Consission (the Connission) has found that:
)
A.
The application for amendrent by Tennessee Valley Authority (the licensee) dated April 20, 1988, cocplies with the standards and requirerents of the Atemic Energy Act of 1954, as ament.d Dhe Act),
and the Cocuissiot rules and regulations set forth in 10 0/R Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the t
Connission; i
l C.
There is reasonable assurance (1) that the activities authorized by
]
this arendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be j
conducted in compliance with the Consission's regulations; l
0.
The issuance of this arendrent will not be inimical to the couron defense and facurity or to the health and safety of the public; and t
E.
The issuance of this arendrent is in accordance with 10 CFR Part 51 j
of the Coewission's regulations and all applicable requirements have i
been satisfied.
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PDR ADOCK 05000259 P
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, 2.
Accordingly, the license is arrended 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. OPR-33 is hereby anended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amenderent No.154, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technicat Specifications.
3.
This license s mimtnt is effective as of its date of issuance and shall be impleirer.t x
- r. t!".
60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COM415S10N Frh Suzanne Black. Assistant Director for Projects i
TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Cate of issuance: September 2, 1988 I
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.AT..T.ACHMENT TO LICENSE AMENDMENT NO.154 FACI (I,TYOPERATINGLICENSENO.OPR-33 DOCKET NO. 50-259 s
Revise the Appendix A Technical Specifications by removing the pages i
identified below and inserting the enclosed pages. The revised pages i
are identified by the captioned amendment number and contain narginal l
lines indicating the area of change.
REMOVE INSERT 3.4/4.4-1 3.4/4.4-1 3.4/4.4-2 3.4/4.4-2 3.4/4.4-3 3.4/4.4-3 3.4/4.4-4 3.4/4.4-4 r
3.4/4.4-5 3.4/4.4-5 3.4/4.4-6 3.4/4.4-6 3.4/4.4-7 i
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I 3.4/4.4 STANDBY.LIOUIp_QQHIjt0L SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDRY LICUID CONTROL SYSTEM 4.4 STANDBY LIOUID C0FfROL SYSTEM Aeolicability Acclicability t
Applies t*, the operating status Applies to the surveillance of the Standby Liquid Control requirements of the Standby 1
System.
Liquid Control System.
Ob.iectlyt Oblactive To assure the availability of a To verify the operability of the system with the capability to Standby Liquid Control System.
shut down the react 9r and maintain 4
the shutdown condition without the use of control rodi.
12reification grecifiention A.
Normal Svates Availability A.
Eg,tmal System Availability l
1.
Except as specified in The operability of the Standby j
3.4.B.1, the Standby Liquid Liquid Control System aball be control Syeten shall be verified by the performanc'e OPERABLE at all times when of the following tests:
j there is fuel in the reactor vessel and the reactor is not 1.
At least once per month in a shutdevn condition with each pump loop shall be Specification 3.3.A.1 functionally tested.
satisfied 2.
At least once during each 4
operating cycles a.
Check that the setting i
of the system relief
)
valves is 1,425 A 75 l
pais.
1 l
b.
Manually initiate the I
system, ezeept explo.
sive valves. Visual'.y verify r.'.ov by pumping i
boron solution through a
the recirculation path l
and back to the Standby Liquid Contrcl Solution l
Tank. After pumping i
boron solution, the 1
nystem shall be flushed with demineralized veter. Verify minimum i
i BTN 3.4/4.4-1 Amendment No. I N 154 Unit 1 l
e f
3.4/4.4 STANDBY LIOUID CONTROL SYSTIM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.A Normal System Availability (Cont'd) 4.4.A.2.b. (Cont'd) pump flow rate of 39 sps against a system head of 1275 pois by pumping desineralized water from the l.
Standby Liquid Control Test Tank,
- c. Manually initiate one j
)
of the Standby Liquid l
Control Systes loops and pump desineralized wate" into the reactor i
vessa..
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This test checks j
amplosion of the charge associated with the,
[
tested loop, proper
(
aperation of the valvea, l
and pump operability.
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Replacement charges shall l
be selected such that the age of charge in service j
shall not exceed five years from the manufacturer's assembly date.
)
d.
Both systems, including both axplosive valves, i
shall be tested in the course of two operating
(
cycles.
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i BrN 3.4/4.4-2 Amendment No. ZJ6 154
]
Unit 1 i
3.4/4.4 STANDBY LfotfD CONTROL SYSTEM LIMITING CONDITIONS FOR OPERA 7',0N SURVEILLANCE RIQUIREMENTS 3.4.8.
Deeration with fnemerable 4.4.5. Surveillance with Inocerable Gonconents Ggmoenenta 1.
From and after the date 1.
When a component is found that a redundar.t component to be inoperable, its is made or found to be redundant c9aponent shall inoperable, Specification be demonstrated to be 3.4.4.1 shall be considered operable immediately and fulfilled and continued daily thereafter until the operation permitted inoperable component is provided that the repaired.
component is returned to i
an operable condition l
vithin seven days.
3.4.C Sodium Fantaborate Solution 4.4.C Sodium Pentaborate Solution At all times when the Standby The following tests shall be Liquid Centrol Systaa is required performed to verify the to be OPIRABLE, the following availability of the Liquid conditions shall be sett Control Solution:
1.
At least 180 pounds 1.
Volumet Check at least
].
Boron-10 must be stored once per day.
in the Standby Liquid
)
Control Solution tank and 2.
Sodium Pentaborate be available for injection.
Concentration check at least once per month.
i 2.
The sodium pentaborate Also check conctatration solution concentration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime I
must be equal to or lesu water or boren is added than 9.2% by weight.
to the solution.
I 3.
Boron-10 Quantity:
At least once per month, calculate and record the quantity of Boron-10 stored in the Standby Liquid l
Con *,rol Solution Tank.
4 i
4.
Boron-10 Enrichment! At i
least once per 18 months and following each addition of boron to the Standby Liquid Control Solution i
Tankt BrN 3.4/4.4-3 Amendrent No. Z3f 154 Unit 1
3.4/4.4 STANDBY LIOUID CONTROL SYSTIM i
1.IMITING CONDITIONS FOR OPERATION SURVEILI.ANCE REQUIREMENTS a.
Calculate the enrich-sent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 b.
Verify by analysis within 30 days.
3.4.D The Standby Liquid Control Systes conditions must satisfy the following equation.
(
c it 0 if I
i 11 (13 wt.1)(86, spa)(19.8 atom %)
i
- where, C = sodium pentaborate solution concentration (weight percent)
Determined by the most recent perfcreance of the surveillan:n instruction required by Specification 4.4.C.2.
Q = pump flow rate (spa) 4.4.D Verify that che equation given in Specification Determined by the most 3.4.D is satisfied st least recsnt performance of the once per month and within surveillance instruction 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime water or required by Specification boron is added to the 4.4.A.2.b.
solution.
E = Boron-10 enrichment (aton percent Boron-10)
Determined by the most recent performance of the surveillance instruction required by Specification 1
4.4,C.4.
3.4.E If Specification 3.4.A through 4.4.E No additional surveillance 3.4.D cannot be ret, make at required.
least one subsystem operable within 4 hcurs or the reactor shall be placed in a Shutdown Condition with all operable control rods fully inserted within the followins 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
BrN 3.4/4.4-4 Amendment No. I2f 154 Unit 1
3.4 BASES
STANDBY LIOUID CONTROL SYSTEM A.
If no more thsn one OPERABLE control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control System is not required. Thus, the basic reactivity requirement for the core is the primary determinant of when the liquid control system is required.
The purpose of the standby liquid control system is to provide the capability of bringing the reactor from "ull pova.r to a cold, xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. To meet this objective, the liquid control system is designed to inject a quantity of boron that produces a concentration greater than 660 ppa of natural borer. In the reactor core. This amount of Boron-10 is required to bring the reactor from full power to a suberitical condition, considering the l
hot te cold reactivity difference, zenon poisoning, etc. The quantity of stored boron includes an additional.argin (25 percent) beyond the amount nesded to shut down the reactor to allow for possible imperfect mixing of the chemical solution in the reactor
[
water.
The minimum limitation on the relief valve setting is intended to prevent the loss of liquid control solution via the lifting of a relief valve at too lov a pressure. The upper limit on the relief valve settings provides system protection ? rom iverpressure.
B.
Only one of the two standby liquid control pumping loeps is needed for operating the system. One INOPERABLE pumping circuit does not immediately threaten shutdown capability, and reactor opetation can continue while the circuit is being repaired. Assurance that the i
remaining system will perform its intended function and that the I
long-term average availability of the system is not reduced is obtained from a one-out-of-two system by an allevable equipment i
out-of-service time of one-third of the normal surveillance l
frequency. This method determines an equipment out-of-service time of 10 days. Additional conservatism is introduced by reducing the allevable out-of-service time to seven days, and by increased testing l
of the OPERABLE redundant component.
i 4
C.
Level indication and alarm indicate whether the solution volume has i
ch,anged, which might indicate a possible solution concentration change. The test interval has been established in consideration of these factors. Temperature and liquid level alarms for the system are annunciated in the control room.
The sodium pentaborate solution concentration is limited to less than 9.2 weight percent. This concentration limits the saturation temperature to 40' F vhich yields a 10' T margin below the minimum ambient te9perature of 50' F.
a i
j D.
To meet 10 CFR 50.62, the Standby Liquid Control System must have a i
minimum flow capacity and boren content equivalent in control capacity to 86 pgm of 13 veight percent natural sodium pentaborate solution.
BFN 3.4/4.4-5 Amendment No. 226 154 Unit 1
i I
3.4 BASES (Cont'd)
This equivalency requirement is met when the equation given in 3.4.D is satisfied. Each parameter in the equation is tested consistent with its potential to vary. The enriched sodium pentaborate solution is made by combining stoichiometric quantities of borox and boric acid in desineralized water. Since the chemicals used have known Boron-10 enrichments, the Boron-10 enrichment of the sodium pentaborate formed can be calcu'ated.
Followins initial solution formation or chemical addition, the result of this calculation will be used to determine compliance with 3.4.D pending subsequent verification by analysis.
1
4.4 BASES
STANDBY LIOUID CONTROL SY M Experience with pump operability indicates that the month?.y test, in combination with the tests during each operating cycle, is sufficient to maintain pump performance. Various components of the system are individually tested periodically, thus making unnecessary more frequent I
testing of the entire system.
r The solution volume, concentration and B-10 enrichment are checked at a l
frequency to assure a high reliability of operation of the system should it ever be required.
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NUCLEAR REGULATORY COMMISSION j
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TENNESSEE VALLEY AUTHORITY p0CLETNO.50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-52 1.
The Nuclear Regulatory Comissior. (the Comission) has found that:
A.
The application for amendrent by Tennessee Valley Authority (the licensee) dated April 20, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as aMnded (the Act),
and the Comissico's rules and regulations set forth in 10 CFR Chapter 11 B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; l
C.
There is reasonable assurance (1) that the activities authertred by
)
this arendment 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; i
D.
The issuance of this amendrent 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 arendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1 l
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'g 2-2.
Accordingly, the license is arended by changes to the Technical Specifications as indicated in the attachrent to this license amendrent and paragraph 2.C.(2) of Facility Operating License No. OPR-52 is hereby amended to read as follows_:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendfrent No.150, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technicat Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 dc/s from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Cate of Issuance: September 2,1988 i
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ATTACHMENT TO L!rENSE AMEN 0 MENT NO.150 FACILITYOPERATINGLICENSENO.OPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified 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.
REMOVE INSERT 3.4/4.4-J 3.4/4.4-1 3.4/4.4 2 3.4/4.4-2 3.4/4.4-3 3.4/4.4-3 3.4/4,4-4 3.4/4.4-4 3.4/4.4-5 3.4/4.4-5 l
l 3.4/4.4-6 3.4/4.4-6 i
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A 3.4/4.4 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 STANDRY LIOUID CONTROL SYSTEM Aeolicability Aeolicability Applies to the operating status Applies to the surveillance of the Standby Liquid Control requirements of the Standby
- System, Liquid Control System.
Obiective Obiective To assure the availability of a To verify the operability of the system with the capability to Standby Liquid Control System.
shut down the reactor and maintain the shutdown condition without the use of control rods.
Egecification Seecification A.
Normal Svaten Availability A.
Normal Svaten Availability 1.
Except as specified in The operability of the Standby
.l 3.4.B.1, the Standby Liquid Liquid Control Systaa.shall be Control Systes shall be verified by the perforsahce OPERABLE at all times when of the following testst there is fuel in the reactor vessel and the reactor is not 1.
At least once per month in a shutdown condition with each pump loop shall be Specification 3.3.A.1 functionally tested.
satisfied.
2.
At least once during each operating cyclet
]
a.
Check that the setting of the system relief
)
valves is 1.425 1 75 L
peig.
b.
Manually initiate the 4
system, except explo-l sive valves. Visually I
verify flow by pumping boron solution through
]
the recirculation path I
and back to the Standby Liquid Control Solution !
i Tank. After pumping j
boron solution, the system shall be flushed with desineralized j
water. Verify minimum i
i BFN 3.4/4.4-1 knendment No. 232 150 Unit 2 i
i
d 3.4/4.4 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.4.A Normal System Availability (Cont'd) 4.4.A.2.b. (Cont'd) pump flow rate of 39 spe against a system head of 1275 pois by pumping domineralized water from the l
Standby Liquid Control Test Tank.
I
- c. Manually initiate one of the Standby Liquid l
Control Systen loops and pump desineralized water into the reactor vessel.
This test checks explosion of the chstge sesociated with the tested loop, proper l
operation of the valves, knd pump operability.
Repiscseent charges shall
]
be selected such that the age of charge in service l
shall not exceed five l
J years from the 1
sanufacturer's assembly date.
d.
Both systems (neluding I
both explosive valves, l
shall be tested in the course of two operating cycles.
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3.4/4.4-2 Amendment No. IJ2150 BrN Unit 2 l
A l
3.4/4.4 STANDBY LIOUID COPrTROL SYSTEM LIMITING CONDITIONS F0R OPERATION SURVEILLANCE REQUIRIMENTS 3.4.B.
Oneration with Inocerable 4.4.B. Surveillance with Inonerable Connonents Comeonents 1.
From and after the date 1.
When a component is found that a redundant component to be inoperable, its is made or found to be redundant component shall inoperable, Specification be demonstrated to be 3.4.A.1 shall be considered operable issediately and l
fulfilled and continued daily thereafter until the i
operation permitted inoperable component is provided that the repaired.
component is returned to an operable condition within seven days, t
3.4.C Sodium Pentaborate Solution 4.4.C Soditae Pentaborate Solution At all times when the Standby The following tests aball be Liquid Control System is required performed to verify the to be OPERABLE, the following availability of the Liquid conditions shall be met:
Control Solution:
1.
At least 180 pounds 1.
Volumet Check at least.
Boron-10 must be stored once per day, in the Standby Liquid j
Control Solution tank and 2.
Sodium Pentaborate I
be available for injection.
Concentration check at least once per month.
2.
The sodium pentaborate Also check concentration i
solution concentration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime l
aust be equal to or less water or boron is added l
than 9.2% by weight.
to the solution.
l 3
3.
Boron-10 Quantity:
I At least once per month, calculate and record the 3
quantity of Boron-10 stored in the Standby Liquid l
Control Solution Tank.
I 4
Boron-10 Enrichment At least once per 18 months and following each addition I
of boron to the Standby l
Liquid Control Solution j
Tanks l
BTN 3.4/4.4-3 Amendment No. Z32/ 150 Unit 2 1
f l
A 3.4/4.4 STANDBY LIOUID CORIRQL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVE!!1ANCE REQUIREMENTS a.
Calculate the enrich-ment within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Verify by analysis within 30 days.
3.4.D The Standby Liquid Control System conditions aust satisfy the following equation.
(
c
)( o
)(
r_
) 11 (13 vt.1)(g6 spa)(19.3 Aton1)
- where, 1
C = sodium pentaborata solution concentration (weight percent)
Determined by the most recent performance of the i
surveillance instruction required by Specification i
4.4.C.2.
Q = pump flow rate (spe) 4.4.D Verify that the equation given in Specification Determined by the most 3.4.D is satisfied at least recent performance of the once per month and within surveillance instruction 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime water or required by Specification boron is added to the l
4.4.A.2.b.
solution.
i E = Boron-10 enrichment (atoa percent Boron-10)
)
Determined by the most l
recent parformance of the surveillance instruction l
required by Specification l
4.4.C.4 I
3.4.E If Specification 3.4.A through 4.4.E No additional surveillance 3.4.D cannot be met, make at required.
least one subsystem operable within a hours or the reactor shall be placed in a Shutdown i
Condition with all operable l
control rods fully inserted I
within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 BTN 3.4/4.4 4 Ar.end ent No IJ2 150 1
Unit 2 l
4 i
3.4 BASES
STANDBY LIOU1D C0!ffROL SYSTEM l
A.
If no more than one OPERABLE control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control System is not required. Thus, the basic reactivity requirement for the core is the primary determinant of when the liquid control system is required.
l t
The purpose of the standby liquid control system is to provide the capability of bringing the reactor from full power to a cold, l
xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. To meet this objective, the liquid control system is designed to inject a quantity of boron that produces a concentration greater than 660 ppa of natural boren in the reactor core. This amount of Boron-10 is required to bring the reactor from full power to a suberitical condition, considering the hot to cold rgactivity difference, menon poisoning, etc. The i
quantity of stored boron includes an additional margin (25 percent) j beyond the amount needed to shut down the reactor to allow for possible imperfect mixing of the chemical solution in the reactor l
l vater.
The minimus limitation on the relief valve setting is intended to I
prevent the loss of liquid control solution via the lifting of a j
relief valve at too lov a pressure. The upper limit on the relief valve settings provides system protection from overpressure.
B.
Only one of the two standby liquid control pumping loops is needed for operating the system. One INOPERABLE pumping circuit does not insediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired. Assurance that the remaining systen vill perfom its intended function and that the i
long-ters average availability of the system is not reduced is obtainer es a one-out-of-two system by an allevable equipment out-of service time of one-third of the normal surveillance frequency. This method determines an equipment out-of-service time 1
i of 10 days. Additional conservatism is introduced by reducing the 1
allevable out-of-service time to seven days, and by increased testing of the OPERABLE redundant component.
l C.
Level indication and alara indicate whether the solution volume has chgnsed, which might indicate a possible solution concentration l
4 change. The test interval has been established in consideration of these factors. Temperature and liquid level alarus for the systes are annunciated in the control room.
The u dium pentaborate solution concentration is limited to less thar.
9.2 weight percent. This concentration limits the saturation l
tempetature to 40* T which yields a 10' F margin below the minimum ambient temperature of 50' T.
l D.
To meet 10 CTR 50.62, the Standby Liquid Control System must have a sinimum flow capacity and boron content equivalent in control capacity to 86 pgm of 13 veight percent natural sodium pentaborate l
I solution.
\\
i BTN 3.4/4.4-5 A,mendment No. I2? 150 l
Unit 2 l
I l
3.4 BASES (Cont'd)
This equivalency requirement is met when the equation given in 3.4.D is satisfied. Each parameter in the equation is tested consistent with its potential to vary. The enriched sodium pentaborate solution is made by combining stoichiometric quantities of borox and boric acid in deatneralized water. Since the chealcals used have known Boron-10 enrichments, the Baron-10 enrichment of the sodium pentaborate formed can be calculated.
Following initial solution formation or chemical addition, the result of this calculation vill be used to determine compliance with 3.4.D pending subsequent verification by analysis.
4.4 BASES
STARDBY LIQUID CONTROL SYSTEM Experience with pump operability indicates that the monthly test, in combination with the tests durina each operating cycle, is sufficient to maintain pump performance. Various components of the system are individually tested periodically, thus making unnecessary more frequent testing of the entire system.
The solution volume, concentration and B-10 enrichment are checked at a j
frequency to assure a high reliability of operation of the systes should it ever be required.
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BTN 3.4/4.4-6 Amendment No. Z32 150 Unit 2 l
i
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UNITED STATES n"
NUCLEAR REGULATORY COMMISSION 3
W ASMG TON, D. C. 20608 o..*
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TENNESSEE VALLEY AUTHORITY DOCKET N0. 50 296 E
BROWNS FERR M UCLEAR PLAN,T d lT_3
.A.MENOWNT T.O F.A.C.IL.I.T.Y..O.P.E..R.ATING LICENSE No bPR.68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the i
licensee)datedApril 20, 1988, corplies with the standards and requirements of the Atceic 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 l
provisions of the Act, and the rules and regulations of the J
Comission; l
C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby this arMndment can be conducted without endangering the health and J
safety of the public, and (11) that such activities will be j
conducted in compliance with the Comission's regulations; I
0.
The issuance of this arendrent will nct te inimical to the corron defense and security or to the health and safety of the public; and E.
The issuance of this asendrent is in eccordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements tave been satisfied.
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2.
Accordingly, the license is atended by changes to the Technical Specifications as indicated in the attachment to this license acendeent and paragraph 2.C.(2) of Facility Operating License No. OPR-68 is hereby arended to read as follcws:
(2) Technical Specifications l
The Technical Specifications contained in Appendices A and B. as revised through Amendrent No.125. are hereby incorporated in the l
licer.se. Tht, licensee shall operate the facility in accordance with l
the Technical Specifications.
3.
This license.amendnent is effective as of its date of issuance and shall be implerented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY CCM41SS10N sa h
Suzanne plack. Assistant Director i
for Projects TVA Projects Division i
Office of Special Projects Attachrent:
Changes to the Technical Specifications Cate of Issuance: September 2,1988 l
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ATTACHMENT TO LICENSE AMEN 0 MENT NO.125 1
FActLITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-?96 l
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal t
lines indicating the area of change, i
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REM 0'/E INSERT 3.4/4.4-1 3.4/4.4-1 1
3.4/4.4 2 3.4/4.4-2 t
3.4/4.4-3 3.4/4.4-3 I'
3.4/4.4-3 3.4/4.4-3 i
3.4/4.4-4 3.4/4.4-4 r
l 3.4/4.4-5 3.4/4.4-5 1
3.4/4.4-6 3.4/4.4 6 3.4/4.4-7
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o 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRDENTS 3.4 STANDRY LIQUID CONTROL SYSTEM 4.4 STANDBY LIQUID CONTROL SYSTEM i
Aeolicability Aeolicability Applies to the operating status Applies to the surveillance i
1 of the Standby Liquid Control requirements of the Standby i
System.
Liquid Control System.
Obiective Obiective J
I To assure the availability of a To verify the operability of the system with the c9pability to 3tandby Liquid Control System.
shut down the reactor and maintain the shutdown condition without
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the use of control rods.
i Scacification Snacification i
j A.
Normal System Availability A.
Normal Svaten Availability i
1.
Except as specified in The operability of the Standby
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3.4.5.1, the Standby Liquid Liquid Control System sh'all be Control Systes shall be verified by the performance OPERABLE at all times when of the following tests:
I there is fuel in the reactor r
I vessel and the reactor is not 1.
At least once per sonth 1
in a shutdown condittoa with each pump loop shall be
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Specification 3.3.A.1 functionally tested.
J satisfied.
1.
2.
At least once during each i
l operating cycles a.
Check that the setting j
of the system relief 4
valves is 1.425 1 75 pais.
a b.
Manually initiate the system, except exple-i sive valves. Visually verify flow by pumping
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boron solutten through
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i the recirculation path and back to the Standby l
1 Liquid control solution l
j Tank. After pumping boron solution, the system shall be flushed with deatneralized l
vater. Verify minimu:n l
I BTN 3.4/4.4-1 Amendment No. 107 125 Unit 3
0 3.4/4.4 STANDBT LIOUID CpN'lROL SYSTIM LIMITING CONDITIONS FOR OPERATION SU1VIILLANCE REQUIREMENr$
4.4.A Normal Svates Availability (Cont'd) 4.4.A.2.b. (Cont'd) pump flow rate of 39 spa against a system head of 1275 pais by pumping desineralized water from the l
Standby Liquid Control Test Tank.
- c. Manually initiate one of the Standby Liquid Control System loops and pump desineralized water into the reactor vessel.
This test checks arplosion of the charge associated with the, tested loop, preper operation of the valves, and pump operability.
Replacement charges shall be selected such that the age of charge in service shall not exceed five years from the manufacturer's assembly date.
d.
Both systems, including both amplosive valves, shall be tested in the course of two operating cycles.
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BrN 3.4/4.4-2 Amendment No. )77125 Unit 3
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e 3.4/4.4 STANDBY LIOUID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVE!LLANCE REQUIREMENTS i
3.4.B.
Oneration with Inonerable 4.4.3. Surveillance with fnocerable Ceanonanta Commenents 1
1.
From and after the date 1.
When a component is found that a redundant component to be inoperable, its is made or found to be redundant component shall inoperable. Specification be demonstrated to be 3.4.A.1 shall be considered operable immediately and fulfilled and continued daily thereafter until the operation permitted inoperable component is provided that the repaired.
component is returned to an operable condition within seven days.
3.4.C Sodium Pentaborate Solution 4,4.C Sodium Pentaborate Solution At all times when the Standby The following tests shall be Liquid Control System is required performed to verify the to be OPERABLE, the following availability of the Liquid I
conditions shall be sett Control Solution l
1.
At least 180 pounds 1.
Volume:
Check at least Boron-10 must be stored once per day.
in the Standby Liquid Control Solution tank and 2.
Sodium Pentaborate be available for injection.
Concentration check at least once per month.
2.
The sodium pentaborate Also check concentration solution concentration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime must be equal to or less water or boren is added than 9.2% by weight.
to the solution.
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3.
Boron-10 Quantity:
At least once per month, calculate and record the quantity of Boron-10 stored in the Standby Liquid Control Solution Tank.
a j
4 Soron-10 Entiennent: At I
least once per 18 months and following each addition of boren to the Standby Liquid Control Solution i
Tank:
l BTN 3.4/4.4-3 Amendment ho. 127 125 Unit 3 1
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.=.
3.4/4.4 STLERY Lf 0UID CONTROL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUltEMENTS a.
Calculate the enrich-ment within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I b.
Verify by analysis withits 10 days.
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'3.4.D The Standby Liquid Control System conditions must satisfy the following equation.
(
C
)( 0
)(
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)i1 (13 vt.1)(86 spa)(19.8 atoms)
- vhere, C = sodium pentaborate solution concentration i
j (weight percent) l P
Determined by the most recent performance of the a
surveillance instruction l
l required by Specification l
4.4.C.2.
l Q = pump flow rate (spa) 4.4.D Verify that the equation
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given in Specification l
Determined by the most 3.4.D is satisfied at least l
J recent performance of the once per month and within surveillance instruction 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anytime water or i) required by Specification boron is added to the 4.4.A.2.b.
solution.
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j E = Boron-10 enrichment (aton l
percent Baron-10) 4 Determined by the most recent performance of the surveillance instruction required by Specification 4.4.C.4 r
1 3.4.E If Specification 3.4.A through 4.4.I No additional r.urveillance t
l 3.4.D cannot be met, make at required.
least one subsystem operable I
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be placed in a Shutdown i
l Condition with all operable control rods fully inserted within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i BrN 3.4/4.4-4 l
A9endment No. 207125 Unit 3 4
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3.4 BASES
STANDBY LIOUID CONTROL SYSTEM A.
If no more than one OPERABLE control rod is withdrawn, the basic shutdown reactivity requirement for the core is satisfied and the Standby Liquid Control System is not required. Thus, the basic reactivity requirement for the core is the primary determinant of when the liquid control system is required.
The purpose of the standby liquid control system is to provide the espability of bringing the reactor from full power to a cold, l
xenon-free shutdown condition assuming that none of the withdrawn control rods can be inserted. To meet this objective, the liquid control systen is designed to inject a quantity of boron that
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produces a concentration greater than 660 ppe of natural boren in the l
reactor core. This amount of Boron-10 is required to bring the reactor from full power to a suberitical condition, considering the hot to cold r4 activity difference, menon poisoning, etc. The quantity of stored boron includes an additional margin (25 percent) beyond the amount needed to shut down the reactor to allow for possible imperfect sizing of the chemical solution in the reactor water.
The minimum limitation on the relief valve setting is intended to prevent the loss of liquid control solution via the lifting of a relief valve at too low a pressure. The upper limit on the relief i
valve settings provides system protection from overpressure.
l B.
Only one of the two standby liquid control pumping loops is needed for operating the system. One INOPERABLE pumping circuit does not issnediately threaten shutdown capability, and reactor operation can continue while the circuit is being repaired. Assurance that the remaining system will perform its intended function and that the t
long-turn average availability of the system is not reduced is obtained from a one-out-of-two system by an allowable equipment out-of-service time of one-third of the normal surveillance l
frequency. This method determines an equipment out-of-service time i
of 10 days. Additional conservatisa is introduced by reducing the
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allowable out-of-service time to seven deys, and by increased testing i
of the OPERABLE redundant component.
C.
Level indication and alaru indicate whether the solution volume has cheged, which might indicate a possible solution concentration change. The test interval has been established in consideration of these factors. Temperature and liquid level alarms for the systen are annunciated in the control room.
The sodium pentaborate solution concentration is limited to less than j
9.2 weight percent. This concentration limits the saturation temperature to 40* T which yields a 10' r margin below the sintaua ambient temperature of 50' r.
D.
To meet 10 CTR 50.62, the Standby Liquid Control System must have a l
l ainimum flow capacity and boron content equivalent in control capacity to 46 pga of 13 weight percent natural sodium pentaborate solution.
BTN 3.4/4.4-5 teend-ent No. N7125 Unit 3
3.4 BASES (Cont'd)
This equivalency requirement is set when the equation given in 3.4.D is satisfied. Each parameter in the equation is tested consistent with its potential to vary. The enriched sodium pentaborate solution is made by combining stoichiometric quantities of borox and boric acid in desineralised water.
Since the cheatcals used have known Boron-10 enrichments, the loron-10 enrichment of the sodium pentaborate formed can be calculated.
Followins initial solution formation or cheatcal addition, the result of this calculation vill be used to determine compliance with 3.4.D pending subsequent verification by analysis.
4.4 AA111
STARDaY LIQUID. CONTROL SYSTDI Experience with pump operability indicates that the monthly test, in combination with the testa durina each operating cycle, is sufficient to maintain pump performance. Various components of the system are individually tested periodically, thus making unnecessary more frequent j
testing of the entire system.
i The solution volume, concentration and 8-10 enrichment are checked at a l
1 frequency to assure a high reliability of operation of the system should l
l it ever be required.
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BTN 3.4/4.4-6 Amendment No. Z07 125
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Unit 3 l
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