ML20069Q332
| ML20069Q332 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/09/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069Q336 | List: |
| References | |
| NUDOCS 9101150272 | |
| Download: ML20069Q332 (23) | |
Text
- -
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![g. cso 1\\,
w UNITED STATES' g
NUCLE AR REGUL'ATORY COMMISSION 5
'f WASHINGTON, D. C. 20555
\\...../
1 i
TENNESSEE VALLEY AUTHORITY i
DOCKET NO. 50-260 i
BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING _ LICENSE i
Amendment No.186 License No. DPR-52 1
l 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated July 13, 1990, complies with'the standards and requirementsoftheAtomicEnergyActof1954,asamended(theAct),
and the Commission's rules and regulations set forth in 10 -CFR Chapter I; B.
The facility will operate in conformity with the epplicction, the provisions of the Act, and the rules _and regu htions of the Comission; C.
There is reasonable assurance (1) ;, hat t % activities authorized by this amendment can be conducted. Hhout endangering the health and safety of the public, and (ii) that such activities will be ccnducted in' compliance with the Comission's regulations;-
D.
The issuance of this amendment will not-be inimical to the comm n defense and security or to the health and safety of the public; and-E.
.The issuance of this amendment is in accordance with 10'CSR Part 51 of the Comission's regulations and all applicable requirements have-
'been satisfied.
l 9101150272 910109 PDR ADOCK 05000259 P
PDR I
s
'e 2
1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.0.(2) of Facility Operating License No. DPR-52 is hereby amended to read as follou:
(2) Technical Specifications The Technical Specifications contained in Appendices A. and.B as revised through Amendment No.- 186, 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 n
(rM Frederick J. Hebdon, Director
^
Project-Directorate II-4.
Division of Reactor Projects - I/II-Office of Nuclear Reactor-Regulation l
Attachment:
i Changes to the Technical Specifications Date of Issuance: January 9, 1991 I
L l
AiiACRMENT TO LICENSE AMENDMENT NO.186 FACILITY OPERATING LICENSE NO. DPR-52
' DOCKET NO 50-260 Revise the Appendii A Technical Specifications by removing the pages-identified below and. inserting the enclosed pages.
The revised pages areLidentified by the captioned amendment-number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT iii
'111 iv
_ j y*
3.9/4.9-15 3,g/4,g.15 4
3.9/4.9-15a-
~~
3.9/4.9-19 3.9/4.9-19*
3.9/4.9-20 3.9/4.9-20 3.9/4.9-21 3.9/4.9-21' 3.9/4.9-22
.3.9/4.9-22*
l
-e w
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n
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. +
w.,
- r r or
+
er w.e
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n._,
n S e c t i on--.
Pane No.
E.
_ Jet Pumps.-..--.
..1.;.-._.
3.6/4.6-11 F.
Recirculation Pump _ Operation..n.
.--c.L...:
.3.6/4.6-12 G.
Structural Integrity.-.
..,......:.-... -. =..
3.6/4.6-13:
H.-
Snubbers _........
-3.6/4.6 -l 3.7/4.7 Containment Systems.
3.7/4.7-l' A. -.
3.7/4.7-l' B.
Standby Gas. Treatment-System..
- 3. 7 /4 '. 7.. -. -. -.. -.-..
' 1 O.
l 3. 7/4. 7-16 --
....... = -. -. - - -. -.
q 3
D.
Primary Containment Isolation Valves-..
-3.7/4.7-17 1
1 E..
Control Room Emergency Ventilation '..-.
3.7/4.7-19 l
F.
Primary Containment Purge System.
3.7/4.7-21!
G.
Containment Atmosphere Dilution System'(CAD).
3.7/4.7-22L l
11.
Containment Atmosphere Monitoring (CAM)-
System:ll2 Analyzer...:..,..;.....
327/4.7-24' 3
3.8/4.8 Radioactive Materials.
l 13.8/4.8.... _.... -... _..-.. _ _
A.
Liquid Effluents-.
,3.8/4.8-1
..,,.n.-.
B.
Airborne. Effluents.:-..-.-.
3.8/4.8-3 C.
-Radiosctive Effluents - Dose
.c.1
-3.8/4.8-6 D.
Mechanica1' Vacuum Pump.
-3.8/4.8-6 E.
Miscellaneous Radioactive Materials Sources.c.: l3.8/4.8-7 F.
Solid Radwaste.......-......_....J..1.-
-3.8/4.8 3.9/4.9-Auxiliary Electrical: System.-...:.
.a... - ; --
3.9/4.9-1 A.
. Auxiliary Electrical Equipmentf..-..-
3.9/4.9 B.
Operation-vith Inoperable _ Equipment.<..
3.9/4.9-8 C.
. Operation-in Cold Shutdown.--.......'...
-3.9/4.9-15 D.
Unit-3 Diesel Generators-Required for -Unit 2 Operation -.
3.9/4.9-15a
.u.
BFN,
-111 Amendment 186 Unit 2
3 i
i Section Pame'No.
3.10/4.10 Core Alterations..
3.10/4.10-1
^
A.
Refueling Interlocks 3.10/4.10-1 B.
Core Monitoring.
3.10/4.10-4 C.
Spent Fuel Pool Water.:.
3.10/4.10-7 D.
Reactor Building Crane 3.10/4.10-8 E.
Spent Fuel Cask.........-.........
3.10/4.10-9 F.
spent-Fuel Cask Handling-Refueling Floor 3.10/4.10-10 3.11/4.11 Fire Protection Systems 3.11/4.11:1 A.
Fire Detection Instrumentation 3.11/4.11 ~
B.
Fire Pumps and Water Distribution Mains.
3.11/4.11-2 C.
Spray and/or Sprinkler Systems 3.11/4.11-7 D.
-C02 Systems.
3.11/4.11...................
E.
Fire Hose Stations 3.11/4.11-9'
_)
.A F.
Yard Fire Hydrants and Hose flouses 3.11/4.11-11 G.
Fire-Rated Assemblies.
3.11/4.11 12 i
H.
Open Flames, Welding and Burning in the Cable l
Spreading Room 3.11/4.'11-13
. =...............
l l
5.0 Major Design Features
. 5.0-1 l
5.1. Site Features....
5.0-1 5.2 Reactor....-.....
...........- 5.0-1 5.3 Reactor Vessel
...- 5.0-1 l
5.4 Containment...
5.0-1 i
5.5 Fuel Storage.
............... -... - - '5.0-1 4
5.6 Seismic Design.. -.....-..........-.
5.0-2 T
BFN iv Unit 2
.m.
_~
h
' ji9/4.9 AUX?LIARY PLECTRICAL SYSTEM-LIMITING CONDITIONS FOR OPERATION -
SURVEILLANCE-REQUIREMENTS 3.9.C.
Qggration in Cold Shutdovn 4.9.C Operation in-Cold Shutdown Whenever the reactor'la in 1.
No additional-COLD SIIUTDOWN CONDITION with surveillance-is irradiated fuel in the required.
reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.
1.
At least two Units 1 and 2 diesel generators and their associated-4-kV shutdown boards shall be OPERABLE.
2.
An additional source of power. energized and capable of supplying power to the Units 1 and 2 shutdovn boards consisting of at least one of the followings a.
One of the offsite. power sources specified in 3.9.A.1.c.
- b. ' A third OPERABLE ~ diesel generator.
3.
At least one 480-V-shutdown board for each unit must'be-OPERABLE.
4.
One 480-V RMOV board mg set is required for each.RMOV board (20 or 2E) required to i
support operation of the RHR system in accordance with 3.5.B.9.
l L
l 1
BFN 3.9/4.9-15 Amendment 186 Unit 2
3.0/4.9 LUXILIARY ELECTRICAL SYSTEM i
LIMITING CONDITION 9 FOR OPERATION ~
SURVEILLANCE REQUIREKENTS 3.9.D Unit 3 Diesel Generaters 4.9.D Unit 3 Diesel Generatora Eeoutred_for Unit 2 opgration geautred for Unit 2 onsration 1.
Whenever any of the 1.a Diesel Centrators following equipment is required to be OPERABLE in Surveillance requirements accordance with the are as specified in corresponding section of T.S. 4.9.A.1.a. 4.9.A.1.c, these technical specifi-4.9.A.1.d and 4.9.A.1.e.
cations, the Unit 3 diesel generator aligned to supply 1.b DC Power System emergency power to that equipment shall be OPERABLE.
Surveillance requirements are as specified in T.S.
a.
Standby gas treatment 4.9.A.2.
train C in accordance with T.S. 3.7.B (diesel generator 1.c Loalc Systgma 3D).
Both divisions of the b.
Control room emergency common accident signal ventilation train B in logic system shall be accordance with T.S. 3.7.E tested every 6 months to (diesel generator 3B or 30),
demonstrate that it will function on actuation of-2.
When the diesel generator the core spray system of aligned to supply emergency the reactor to provide power to the equipment in nn automatic scart signal 3.9.D.1.a or b is. inoperable, to each diesel generator.
the equipment may be considered OPERABLE for the purpose of 1.d Undervoltane Reinvs satisfying the corresponding technical specification during Surveillance requirements the succeeding 30 days provfded are as specified in that the redundant train (s)
T.S. 4.9.A.4.-
of equipment and their normal j
and emergency power supplies 2.
No surveillance required, are OPERABLE.-
3.
No surveillance required.
3.
If Specification 3.9.D.2 cannot be met, the affected equipment shall be declared inoperable.
l l
I BFN 3.9/4.9-15a Amendment 186' Unit 2 l.
- 3. 9 ' $ASES The objective of this specification is to1 assure an adequate source of electri' cal power to operate-facilities to cool the plant during shutdown and to operate the engineered safeguards following an accident. There are three sources of alternating current electrical energy available, namely, the 161-kV transmission system, the 500-kV transmission system,.
and'the diesel generators.
The unit station-service transformer B for unit 1 or the unit-station-service transformer B for unit 2: provide noninterruptible sources of offsite power from the 500-kV transmission system te the units 1 and 2 shutdown boards. Auxiliary power can-also be supplied from the 161-kV-transmission system through the common station-service transformers or through the cooling tower transformers by way of the-busLtie board.
The-4-KV bus tie board may remain out of service indefinitely provided one of-the required offsite power sources is not supplied-from the'161-kV system through the bus tie board.
The minimum fuel oil requirement of 103,300 gallons is sufficient for seven days of full load operation of three diesels and is conservatively based on availability of a replenishment supply.
The degraded voltage sensing relays provide:a state signal to the diesel
~
generators in the event that a deteriorated voltage condition exists on;a 4-kV shutdown board. This starting signal is independent of the starting-signal generated by the complete loss of voltage relays and will continue to function and start the diesel generators on complete loss aof voltage, should the loss of voltage releys become -inoperable.
The 15-day-inoperable time limit specified when one of the three-phase-to-phase degraded voltage relays-is inoperable is justified based on-the two-out-of-three permissive logic scheme provided with these relays.
A 4-kV shutdown board is allowed to be out of operation for-a brief-period to-allow for maintenance'and testing, providedLall. remaining 4-kV-shutdown boards and associated diesel generators, CS,'RHR, (LPCI and containment cooling) systems supplied by.the rema'ining 4-kV' shutdown boards, and all emergency ABO-V power. boards-are operable.
There are eight 250-V de battery systems, each of which consists of a battery, battery charger, and distribution equipment.
Three of these systems provide power for unit! control functions, operative power for unit motor loads, and alternative drive power.for a 115-V ac unit-preferred mg set.
One 250-V de~ system provides power for common plant and-transmission system control. functions, drive power for a 115-V ac plant-preferred mg set, and emergency drive power for certain unit large motor loads. The-four remaining systems deliver control power to the 4,160-V shutdown boards.-
i l
l BFN 3.9/4.9-19 AMENDMENT NO.14 g Unit 2
3.9 BASES (Cont'd)
Each 250-V de shutdown board control power supply can receive, power from its own battery, battery charger, or from a spare charger. The chargers are powered from normal plant auxiliary power or from the standby diesel-driven generator system. Zero resistance short circuits between the control power supply and the shutdown board are cleared by fuses located in the respective control power supply. Each power supply is located in the reactor building near the shutdown board it supplies.
Each battery is located-in its own-independently ventilated battery room.
The 250-V de system is so arranged, and the batteries sized so that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all three units in the event of the loss of offsite power and a design basis accident in any one unit. Loss of control power to any engineered safeguard control circuits is annunciated in the main control room of the unit affected. The loss of one 250-V shutdown board battery affects normal control power for the 480-V and 4,160-V shutdown boards which it supplies. The station battery supplies loads that are not essential for safe shutdown and cooldown of the nuclear system.
This battery was not considered in-the accident load calculations.
There are two 480-V ac RMOV boards that contain mg sets in their feeder lines.
These 480-V ac RMOV boards have an automatic transfer from their normal to alternate power source (480-V ac shutdown boards).
The mg sets act as electrical isolators to prevent a fault from propagating between electrical divisions due to an automatic transfer.
The 480-V ac RMOV boards involved provide motive power to valves associated with the LPCI mode of the RHR system. Having an mg set out of service reduces the assurance that full'RHR (LPCI) capacity will be available when required.
Since sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) operation, a 7-day servicing period is justified. Having two mg sets out of service can considerably reduce equipment availability; therefore,-the affected unit shall be placed in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The offsite power source requirements are based on the capacity of the respective lines. The Trinity line-is limited to supplying two operating units because of the load limitations of CSST's A and B.
The Athens line is limited to supplying one operating unit because of the load limitations of the Athens line. The-limiting conditions are intended to prevent the 161-kV system from supplying more than two units in the event of a single failure in the offsite power system.
Specification 3.9.D provides the operability requirements for the Unit 3 diesel generators when they serve as emergency power supplies to standby gas treatment train C and control room emergency ventilation train B when they are being considered operable for Unit 2 technical specifications. The allowable out of service time of 30 days is commensurate with the importance of the affected systems when Unit-3 is j
in cold shutdown, the low probability of a LOCA/ Loss of offsite power and availability of onsite power to redundant trains.
i I
BFN 3.9/4.9-20 Amendment 186 Unit 2 l
4.9 MHa
)
3 The monthly tests of the_ diesel generators are primarily to check for failur'es-and deterioration.in the' system since last use. The diesels vill be loaded to at least 75 percent of. rated power while ingine and a
generator temperatures are stabilized (about one hour). Cae minimum 75-percent load will prevent soot formaticn in the cylinders and injection nozzles. Operation up to an equilibrium temperature ensures that there is no overheating problem. The tests also provide an engine and generator operating history to be compared with subsequent engine-generator test data to_ identify _and to correct any mechanical or electrical deficiency before it can result 1n a system failure.
~
The test during refueling-outages is more comprehensive, including procedures that-are most effectively conducted at that time. These I
include automatic actuatien and functional capabil'ty tests to verify-that the generators can start and be ready to assume load in 10 seconds. The annual inspection will detect anyfsigns of wear long before failure.
.i Battery maintenance with regard to the floating charge, equalizing charge, and electrolyte level will be based on the manufacturer's instruction and sound _ maintenance practices.
In addition, written records will be maintained of the battery performance. The plant batteries will deteriorate with time but. precipitous failure is unlikely. The type of surveillance called for in this specification is that which has been demonstrated through. experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
The equalizing charge, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery,: and will be applied as recommended.
The testing of the logic systems will' verify the ability of the logic systems to bring the auxiliary electrical-system to running standby readiness with the presence of an accident signal from any reactor or an undervoltage signal on the 4-kV shutdown boards..
The periodic simulation of' accident signals-in conjunction with diesel-generator voltage available signals will confirm the ability of the 480-V load shedding logic system to-sequentially shed and restart 480-V loads if an accident signal were;present and diesel-generator voltage were the only source of electrical power.
- Specification 4.9.D provides surveillance requirements :for1 Unit 3 diesel generators for the purpose of satisfying Specification 3.9.D.
le contains less stringent testing requirements for the' Unit 3 diesel generators when they are only being used to support Unit 2 equipment.
BFN 3.9/4.9-21 Amendment 186 Unit 2 2
u
EEf1RENCES 1.
Normal Auxiliary Power System (BFNP FSAR Subsection 8.4)-
i 9
2.
Standby AC Power Supply and DistrJhution (BFNP FSAR Subacetion.8.5).-
l 3.
250-Volt DC Power Supply and Distribution (BFNP FSAR Subsection 8.6) 4.
Memorandum from Gene M. Wilhoite to H. J. Green dated' December 4, 1981 (LOO 811208 664) and memorandum from C. E. Winn to H. J. Green =
dated January 10, 1983 (G02 830112 002) l 1
l l
AMENDMENT NO.14 g BFN 3.9/4.9-22 Unit 2-l-
l.
dk Cf 09 4
0,,
UNITED STATES E
g NUCLEAR REGULATORY COMMISSION
[
WASHINGTON, D. C. 20555
....+p 1
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMEHOMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the -
licensee) datod July 13, 1990, complies with the standards and requirements of the Atomic Erergy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter It 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 activitie: 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-common 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.
. 2.'
Accordingly, the license is amended by-changes to the Technical Specifications as indicated in-the' attachment to this license amendment and paragraph P.C.(2) of Facility Operating License No. DPR-68 is hereby amended to read as follows:
(2) -Technical Specif_ications y
The Technical Specifications contained in Appendices A and B,.as revised through Amendment t'o,150, are hereby incorporated in-the license. The licensee shall o the Technical Specifications. perate the facil_ity in accordance vith.
3.
This license amendment is effective as of its date of issuance and shal' be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
]
Frederick J. Hebdon, Director Project Directorate 11-4 Division of Reactor. Projects
-I/II-Office of Nuclear Reactor Regulation
Attachment:
l Changes to the Technical-Specifications Date of Issuance: January 9,1991 I
.-.,,.,m
d
~'
- t ATTACHMENT TO LICENSE AltE!!DP.ENT !!0.150--
FACILITY OPERATING LICENSE NO. DPR-68_
DOCKET NO. 50-296-i Pevise the Appendix A-Technical Specifications by removing.the-pages -
identified ~ below and: inserting the_ enclosed pages. The revised pages
-are.identif.ied by the captioned amendment number and contain marginal lines indicating the -area of change. Overleaf-pages* are provided. to maintain document completeness.
j-
- REMOVE INSERT-i iii.
.iii:
iv iv*
1 3.9/4.9-13 3.9/4.9-13*
3.9/4.9-14 3.9/4.9-14 3.9/4.9-14a 3.9/4.9-14b 3.9/4.9-18
= 3.9/4.9-18*'
3.0/4.9-19
. 3.9/4.9-19 3.9/4.9-20
- 3. 9/4 ~. 9 3.9/4.9 3.9/4.9-21*-
t t
I
=s-e s,
av s,
a.
, -. - -. -,...w-
.~
,v,.
.. < e o,a~.-
... ~. _.
.1 SE.tiga Paae Ngi F.
Recirculation. Pump Operation... -.:...-
,3.6/4.6-12
)
3.6/4.6-13 G.
Structural Integrity.;.
3.6/4.6-15 II. :
Snubbers-,..
3.7/4.7 Containme.ht Systems....
3.7/4.7-1 A.
3.7/4.7-1 B.
Standby.-Gas Treatment System....-....:..
3.7/4.7-13
-C.
3.7/4.7-16
..-.......=-....
D.
Primary Containment' Isolation Valves._.-_.._,
.3.7/4.7-17 E.
Control-Room Emergency Ventilation......
3.7/4.7-19 F.
Primary Containment Purge System.
'3.7/4.7-21 L
G.
Containment Atmosphere Dilution System (CAD).
3.7/4.7-22 11.
Containment Atmosphere Monitoring lCAM) l System !! Analyzer.........
3.7/4.7-23 2
3.8/4.8 Radioac4 ve Materials.-.;.
3.8/4.8-1 A.
Liquid Effluents.
.3.8/4.8-1 B.
Airborne Effluents.
3.8/4.8-3'
-C.
Radioactive Effluents - Dose.
3.8/4.8-6 i
D.
Mechanical Vacuum Pump.
3.8/4.8-6 E.
-Miscellaneous Radioactive Materials Sources 3.8/4.8-7 T.
Solid Radwaste.
1.
3.8/4.8-9 3.9/4.9-Auxiliary Electrit:t System'.
- 1. -....-
3.9/4'9-1 A.
Auxiliary Electrit.a1 Equipment'.
3.9/4 9-1:
B.
Operation with Inoperable Equipment.
3.9/4.9-8 1
C.
Operation in Cold Shutdown Condition'.......
3.9/4.9 D.
Unit 3 Diesel Generatora Required.for Unit 2 Operation...........:....-
3.9/4.9-14a-BFN 111 Amendment 150 Unit 3
- _,. _. ~ _..
Etction EAv LNo.
3.10/4.10 Core Alterations.
3.10/4.10-1 A,
Refuell.g Interlocka 3.10/4.10-1 B.
Core Monitoring.
- 3. 0/4.10-4 C.
Spent Fuel Pool Water.............
3.10/4.10-7 D.
Reactor Building Crane 3.10/4.10-8 E.
Spent Tuel Cask.
3.10/4.10-9 T.
Spent Fuel Cask llandling-Refueling Floor....
3.10/4.10-9 3.11/4.11 Fire Protection Systems 3.11/4.11-1 A.
Fire Detection Instrumentation 3.11/4.11-1 B.
Fire Pumps anu Water Distribution Mains.
3.11/4.11-2 C.
Spray and/or Sprinkler Systems 3.11/4.11-7 D.
CO2 System 3.11/4.11-8 E.
Fire llose Stations...............
3.11/4.11-9 T.
Yard Fire !!ydrants and llose flouses 3.11/4.11-11 G.
Fire-Ra'.d Assemblies.
3.11/4.11-12 11.
Open Flames, Welding and Burning in the Cable Spreading Room.
3.11/4.11-13 5.0 Major Design Features 5.0-1 5.1 Site Features.
5.0-1 5.2 Reactor.................
5.0-1 5.3 Reactor Vessel 5.0-1 5.4 Containment 5.0-1 5.5 Tuel Storage 5.0-1 5.6 Seismic Design 5.0-2 l
l l
BFN iv Unit 3 l
l
....-~ - - - - - _ -
1 L9/4.9 AUXILIARY ELEGRICAL..SLt[LM 1
__ LIMITING CONDITIONS F0k OPERATION SURVE!LLANCE REQUlkEMENTS 3.9.B OggIA11gn_With InoptIAhls-Eaulkatill i
- 10. When one 480-V shutdown l
board is found to be j
inoperable, the reactor 1
vill be placed in 110T j
STANDBY CONDITION withit' 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD $!!UTDWA CONDITION Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i 11.
If one 480.V RNOV boerd mg set is inoperable, REACTOR i
POWER OPERATION may I
continue for a period not to exceed seven days,
(
j provided the temnining 480-V RMOV board mg sets and their associated loads remain OPEkABLE.
3 i
12.
If any two 480-V RMOV board mg sets become inoperable, the reactor shall be placed in the C01.D SifUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 1
13.
If the requirements for operation in the conditions specified by 3.9.B.1 through 3.9.B.12 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the COLD SilUTDOWN CONDITION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i 4
i
!j' i
j i
i I
BFN 3.9/4.9-13 Unit 3
=
i 3.9/4.9 AUXILIARY ELEgillCAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS j
3.9.C.
Doeration in COLD SHUTDOWN 4.9 C Qperation in COLD SHUTDOWN gQgg111Qg Q0NDITION Whenever the reactor is in the 1.
No additional COLD SKUTDOWN CONDITION with surveillance is irradiated fuel in the required.
reactor, the availability of electric power shall be as specified in Section 3.9.A except as specified herein.
ll 1.
At least two Unit 3 diesel generators and their associated 4-kV shutdown boards shall be OPERABLE.
2.
An additional source of j
power energized and capable of supplying power to the Unit 3 shutdown boards consisting of at least one of the followingt a.
One of the offsite power sources specified in 3.9.A.1.c.
b.
A third OPERABLE diesel generator.
3.
At least one Unit 3 480-V chutdown board must be OPERABLE.
4.
One 480-V RMOV board motor generator (mg) set is required for each RMOV board (3D or 3E) required to support operation of the RHR system in accordance with 3.5.B.9.
1 4
i BTN 3.9/4.9-14 Amendment 150 Unit 3
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4 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCEREQUIREVfpf 3.9.D gait 3 Diesel Generators 4.9.D Unit 3 Di at1 Jr,w tai n g t
Recuired for Unit 2 Ontration Reauired for yt.g,,,L ODeratl 1s 2
1.
Whenever any of the 1.a Digat1_g/mtta.Lgts following equipment la required to be OPERABLE in Survellince requirements accordance with the are as tpecified in corresponding section of T. S. 4 J. A.1. a, 4. 9. A.1. c,
any units technical specifi-4.9 A.3.4 and 4.9.A.I.e.
cations, the Unit 3 diesel generator cligned to supply 1.b' DC_PD!rt lXA.Ltm emergency power to that equipment shall be OPERABLE.
Surveillance requirements are-as specified in T.S.
a.
Standby gas treatment 4.9.A.2.
train C in accordance with T.S. 3.7.B (diesel generator 1.c L2&ls_f2Altma 3D).
Both divisions of the b.
Control room emergency common accident signal ventilation train B in logic system shall be accordance with T.S. 3.7.E tested every 6 months to (diesel generator 3B or 3C),
demonstrate that it will function on actuation of 2.
When the diesel generator the core spray system of aligned to supply emergency the Unit 2 reactor to power to the equipment in provide an automatic start 3.9.D.1.a or b is inoperable, signal to each diesel the equipment may be considered generator.
OPERABLE for the purpose of satisfying the corresponding 1.d Und e rvolt Att_PalA1A tecimical specification during the succeeding 30 days provided Surveillance requirements that the redundant train (s) are as specified in of equipment and their normal T.S. 4.9 A 4.
l and emergency power supplies are OPERABLE, 2.
No surveillance required.
3.
If Specification 3.9.D.2 3.
No surveillance required.
cannot be met, the affected equipment shall be declared inoperable, i
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l BFN 3.9/4.9-14a Amendment 150 Unit 3 l
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l BFN 3,9/4,9-14b Amendment 150 Unit 3
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3.9 ELSER
)
ne objective of this specification is to assure an adequate source of electrical power to operate facilities to cool the unit during shutdown i
and to operate the engir. cered safeguards following sa accident. nere are three sources of alternating current electrical energy available, namely, the 161-kV transmission systas, the 500-kV uansmission system, and the diesel generators.
n e unit station-service transformer B for unit 3 provides a noninterruptible source of offsite power from the 500-kV transaiasion system to the unit 3 shutdown boards. Auxiliary power can also be supplied from the 161-kV transmission system through the common station-service transformers or through the coolirs tower transformers J
by way of the bus tie board. The 4-kV bus tie board may remain out of service indefinitely provided one of the required offsite power sources 4
is not supplied from the 161-kV system through the bus tie board.
l n e r.inimum fuel oil requirement of 103,300 gallons is sufficient for l
neven days of full load operation of three diesels and is conservatively based on availability of a replenishment supply.
s ne degraded voltage sensing relays provide a start signal to the diesel i
generators in the event that a deteriorated voltage condition arists on a 4-kV shutdown board. This starting signal is independent of the starting signal generated by the complete-loss of voltage relays and vill continue to function and start the diesel generators on complete loss of voltage should the loss of voltage relays become inoperable.
n e 15-day inoperable time limit specified when one of the three phase-to-phase degraded voltage relays is inoperable is justified based on the two-out-of-three permissive logic schame provided with these relays.
A A-kV shutdown board is allowed to be out of operation for a brief period to allow for maintenance and testing, provided all remaining 4-kV shutdown boards and associated diesel generators, CS, RER, (LPCI and containment cooling) systems supplied by the ramaining 4-kV shutdown boards, and all emergency 480-V power boards are operable.
D e 480-V diesel auxiliary board may be out of service for short periods for tests and maintenance. There are five 250-V de battery systems associated with unit 3, each of which consists of a battery, battery charger, and distribution equipment. Three of these systems provide
, power for unit control functions, operative power for unit motor loads, and alternative drive power for a 115-V ac unit-preferred ma set. One 250-V de systaa provides power for common plant and transmission system control functions, drive power for a 115-V ac plant-preferred mg set, and emergency drive power for certain unit large motor loads. The fifth battery system delivers control power to a 4-kV shutdown board.
BTN 3.9/4.9-18
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Unit 3 Agggy M I2(
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3.9 BASES (Cont'd)
The 25,0-V de systen is so arranged and the batteries sized so that the loss of any one unit battery will not prevent the safe shutdown and cooldown of all three units in the event of the loss of offsite power and a design basis accident in any one unit. Loss of control power to any engineered safeguard control circuits is annunciated in the main control room of the unit affected.
The station battery supplies loads that are not essential for safe shutdovn and cooldown of the nuclear system. This battery was not considered in the accident load calculations.
There are two 480-V ac RMOV boards that contain mg sets in their feeder lines. These 480-V ac RMOV boards have an automatic transfer from their normal to alternate power source (480-V ac shutdown boards). The mg sets act as electrical isolators to prevent a fault from propagating between electrical divisions due to an automatic transfer. The 480-V ac RMOV boards involved provide motive power to Valves associated with the LPCI mode of the RHR systen. Having an mg set-out of service reduces the assurance that full RHR-(LPCI) capacity will be available when required.
Since sufficient equipment is available to maintain the minimum complement required for RHR (LPCI) operation, a 7-day servicing period is justified. Having two mg sets out of service can conciderably reduce enulpment availability; therefore, the affected unit shall be placed in Cold Shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The offsite power source requirements are based on the capacity of the a
respective lines. The Trinity line is limited to supplying two operating units because of the load limitations of CSST's A and B.
The Athens line is limited to supplying one operating unit because of the load limitations of the Athens line.
The limiting' conditions are--
intended to prevent the 161-kV system from supplying more than two units t
in the event of a single failure in the offsite power system.
Specification 3.9.D provides the operability requirements for the Unit 3 diesel generators when they serve as emergency power supplies to standby gas treatment train C and control room emergency ventilation train B when they are being considered operable for Unit 2 technical specifications. The allowable out of service time of 30 days is commensurate with the importance of the affected systems when Unit 3 is in cold shutdown, the low probability of a LOCA/ Loss of offsite power and availability of onsite power to redcadant trains.
BFN 3.9/4.9-19 Amendment 150 Unit 3
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4.9
'RASIS The monthly tests of the diesel generators are primarily to check for.
failures and deterioration in the system since last use; The' diesels vill be loaded to at least 75 percent of rated power while engine and generator temperatures are stabilized (about one hour). The minimum 75-percent load will prevent soot formation in the cylinders and-injection nozzles. Operation up to an equilibrium temperature ensures that there is no overheating problem. The tests also provide an engine and generator operating history to be compared with subsequent 4
engine-generator test data to identify and to correct any mechanical or electrical deficiepey before it can result in a system failure.
The test during refueling outages is more comprehensive, including procedures that are most effectively conducted at that time.
These include automatic actuation and functional capability tests to verify that the generators can start and be ready to assume load in 10 seconds. The annual inspection will detect any signs of wear long before failure.
Battery maintenance with regard to the floating charge, equalizing charge, and electrolyte level will be based on the manufacturer's instruction and sound maintenance practices.
In addition, written records will be maintained of the battery performance. The plant batteries will deteriorate with time but precipitous failurn is unlikely. The type of surveillance called for in this specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
The equalizing chargc, as recommended by the manufacturer, is vital to maintaining the ampere-hour capacity of the battery, and will be applied as recommended.
The testing of the logic system will verify the ability of the logic systems to bring the auxiliary electrical system to running standby readiness with the presence.of an accident signal from any reactor or an undervoltage signal on the start bunes or 4-kV shutdown boards.
l The periodic simulation of accident signals in conjunction with diesel-generator voltage available signals will confirm the ability of I
the 480-V load shedding logic system to sequentially shed and restart 480-V loads if an accident signal were present and diesel-generator l
voltage were the only source of electrical power.
Specification 4.9.D provides surveillance requirements for Unit 3 diesel I
generators for the purpose of satisfying Specification 3.9.D.
It contains less stringent testing requirements for the Unit 3 diesel generators when they are only being used to support Unit 2 equipment.
BFN 3.9/4.9-20 Amendment 150 Unit 3 V
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' 4.9 BASES (Cont'd)
)
e-l Knierencen l
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Normal Auxiliary Poner System (BrNP r$AR Subsection 6.4) 2.
Standby AC Power Supply and Distribution (BFNP FSAR Subsection 8.$)
[
i 3.
250-Volt DC Power Supply and Distribution (BTNP PSAR Subsection 8.6) i l
4.
Memorandum from C. M. W11hoite to H. J. Green dated December 4, p
1981 (LOO 811208 664) and memorandum from C. E. Winn to H. J. Green i
dated January 10, 1983 (G02 830112 002) f i
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1 AMEN 0 MENT NO.12 4 BFN 3,9/4,9-21 Unit 3
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