ML19340D499
| ML19340D499 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/10/1980 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340D500 | List: |
| References | |
| NUDOCS 8012300716 | |
| Download: ML19340D499 (16) | |
Text
/
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
2 WASHINGTON D. C. 2J565 r
...../
TENNESSEE VALLEY AUT"0RITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. DPR-33 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dates September 17, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci-l fications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:
230n j
2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, 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 the dr+-
its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
t Thoma
. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1980 l
ATTACHMENT TO LICENSE AMENDMENT NO. 64 FACILITY OPERATING LICENSE NO. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove tht. ?ollowing pages and replace with identically numbered pages:
151/152 15 TET 164 2.
The underlined pages are the pages being changed; marginal lines on these pages indicate the revised area.
The overleaf pages are provided for convenience.
i l
l l
l l
l
t,IMITING C0'10tTICNS FOR CPEpAT:CN SURVEILLANCE RICUIRE D TS 3.5.C RN R Service Water and Energency 4.5.C RHR Service Water and Etervency Fquir-ent Cooline Wate r Svs teas Equipment Coolin; Water Systees IE; :WS)
(Continuel)
(ETCVS) (Continued) 2, nuring powe r ope ra tion.
2 a.
If no more than tso K)(RSW p u.mp s mu s t be RHRSV p unp s a re inup-operable and assigned ersble. increased to service as indicated surveillance is not below for the specified required.
tice li-its.
b.
When three RH ?.SW p co s are incpe rable. the remaining pumps, asse-RIME MINIMUM ciated essential con-t.IMIT SER'/ ICE ASSIGNMINT trol velves, and asse-(OAYS)
RHRSV EECWa*
cisted diesel genera-tors shall be operated Indefinite 7*
3*
veekly.
30 7* or 6***
2* or 3***
c.
When four RHRSV pu:ps are inoperable. the 7
6*
2*
remaining pumps. asse-ciated essential con-trol valves, and asso-
tors shall be operated
- o ly autenatically starting pumps may be n
assigned to EECW heade service.
Nine pu.9ps mus t be op.e 6 'ble.
Either configuration is accept.-le: 7 and 2 or 6 and 3.
3.
During power oper-3.
Routine surveillance for ation both RHRSV pumps D1 these purps is specified and D2 nor= ally or alter-in 4.5.C.1.
nately assigned to the RHR heat exchanger header supplying the standby coolanc supply connection
= sat be operable ex:ept as spec.'fied in 3.5.0.4 and 3.5.C.5 beln.
152 Amendment No. 64
1,IMITINC CONDITIONS FOR OPT. RATION SURVEILI.ANCE REQUTREMENTS r
- 3. 5. C JHR Service Water and Emergency 4.3.C RHR Service Water and Erergency Equipment Cooling Water Systema Equipment Cooling Water Systems (EECWS)
(EECVS) 1.
Prior to reactor. startup from a 1.
a.
Each of the RHRSW pumps cold condition, 9 RRRSV putps must normally assigned to be operable, with 7 pumps (includ-attomatic service on ing pump D1 or D2) assigned the EECW headers will to RHRSW service and 2 auto-be tested automatically
['
matically starting pumps each time the diesel assigned to EECW service.
E*"*'*C ***
j b.
Annually each RRRSV l
pu=p shall be flow-i rate tested. To be l
considered operable, each puop shall pump at least 4500 gym through its normally assigned flow path.
151 Amendment No. 64
t.IMITINC CONDITIONS FOR OPERATICN SURVEILLANCE RICUIRDTITS 3.5.C (Continued) 4.5.C (Continued) 4.
When it is deter,ined that 4
One of the D1 or D2 one o f the MS'.i pu:-as sup-RiiRSW pumps assigned to plying standbv coolant is the RHR heat exchanger to perable at a etz wnen supplying the standby operability is required. the coolant supply connecticn E*#*
E" E
- may be inoperable for a same header and its asso-cisted diesel generator and period not to exceed the RRR heat exchanger 30 days provided the header and associated essen-operable pump is tial control valves shall aligned to supply the be demonstrated to be RHR heat exchanger CPerable i= mediately and header and the every 15 days thereafter.
associated diesel generator and essential control I
valves are operable.
5.
The standby coolant supply capability may be inoperable for a period not to exceed ten days.
l 6.
If specifications 3.5.C.2 through l
3.5.C.5 are not met, an orderly shutdown shall be initiated-and the unit placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
7.
There shall be at least 2 RHRSW pumps, associated with the selected RHR pumps, l
aligned for RHR heat exchatter service for er.ch re. actor vessel contain ug irradiated fuel.
153 omendment No. 64
LRMITINC Cat'07TIONS FOR OPERATION SURVEILLANCZ EEOUIREMINTS 3.5.3 Equipment Aree Coolero 4.5.b,1guipment Arec Cnolers 1.
The equipnent arec cooler 1.
Each equipnent ares coolcra asacciateo with each RRR is operated in conjunctica pv=p and the equipment area with the equipment served by cooler associated with ecch that particular coolcr; set of core spray pumps (1 therefore, the equip:ent area and C or B and D) nust be coolers are tested at the operable at all times when same frequency as the pu:ps the pump or pu:po served by which they serve.
that specific ecoler is considered to be operable.
2.
Vhen an equipcent area cooler is not operable, the pu:p(s) served by
- hat cooler cust be considered inoperable for Technical Specification pur-poses.
E.
Figh Pressure Coelant Injection E.
High Prcosure Coolant In$cetien System ( r.PC I S )
System (HPCIS) 1.
The HPCI sygten shall be 1.
HFCI subsysten testing shall operable:
be perforced as follows:
(1) prior to startup from a a.
Simulated Once/
Cold Condition; or Auto =atic operating Actu6 tion cycle (2) whenever there is irra-Test diated fuel in the reac-tor vesse l and the reactor b.
Purp Opera-Onces' vessei pressure is greater bility conth than 122 psig, except no specifici in specificc-c.
Motor Operated Ca e/
tion 3.3.E.2.
Valve Opers-
=enth bility d.
Flov Tate at Cr.ce/3 nor=al reactor months vessel opers-ting precoure e.
Flow Rate at Once/
150 peig op e ra t ir.g cycle The HPCI pc=p shall deli ser at least 5000 gps durins each flow rete test.
154 Amendment No. 64
3.,m ne suppression chamber a be drained wt m the reactor vessel pressure is atmospheric, irradia
.1 fuel is in tha setor vessel, and work is the potential to drain the vessel. By re ;uiring not in progress whiet a
k the fuel pool gate to e open with the vessel head removed, the combined water inventory in the fuel pool, the reactor cavity, and the separater/
dryer pool, between the fuel pool low level slarm and the reactor vessel (k 2,000 gallons ). This vill provide flange, is about 65,800 cubic feet 9
adequate low-pressure cooling in lieu of CSS and PER (LPCI anc contain-ment cooling mode) as currently required in specificatione 3.5.A.h and 3.5.B.9 The additional requirements for providing standby coolant supply available vill ensure a redundant supply of coolant supply.
Control rod drive r.aintenance may continue during this period provided no nere than ene drive is removed at a time thiless blind flanges are installed during the period of time CRD's are t. t in place.
I 163 Amendment No. 64 l
I S';
- 3. 5 BASSS Should the capability for providing flow throu6h tha cross-connect lines be lost, a ten day repair time is allowed before shutdown is required.
This repair time is justified based on the very small probability for ever needing PJi? pus.pu ind heat exchanger., to supply an adjacent unit.
FU1HE.;CES 1.
Residual Heat Pemoval Systen (BFMP FSAR subsecticn N.8)
'. C.co Ct.andby Coaling Syr.t e.r (PMip F"AP rection 6) 7.>.C RHi t.~vice U$ter SyLLam and !Dercency 1:viment Cec.uc atei
'y M em IU"
)
There are two EECW headers (north and south) with four automatic starting RHRSW pumps on each header. All components requiring emergency cooling water are fed from both headers thus assuring continuity of operation if either header is operable. Each header alone can handle the flows to all components. Two RHRSW pu=ps can supply the full flow requirements of all essential EECW loads for any abnormal or postaccident situation.
There are four RHR heat exchanger headers (A, B, C, & D) with one RRR heat exchanger from each unit on each header. There are two RHRSW pumps on each header; one normally assigned to each header (A2, B2, C2, or D2) and one on alternate assignment (Al, B1, Cl, or D1).
One RHR heat exchanger header can adequately deliver the flow supplied by both RHRSW pumps to any two of the three RHRSU heat exchangers on the header. One RHRSW pump can supply the full flow requirement of one RHR heat exchanger. Two RHR heat exchangers can more than adequately handle the cooling requirenents of one unit in any abnormal or postaccident situation.
The RHR Service Water Systems was designed as a shared system for three units. The specification, is written, is conservative when consideration is given to particular pumps being out of service and to possible valving arrangements. If un2sual operating conditions arise such that more pumps are out of service cl an allowed by this specification, a special case request may be made to the NRC to allow continued operation if the actual system cooling requirements can be assured.
Snould one of the two ERRSW pumps nornally cr alternately assigned to the RHR heat crchanSer header supplying the standby coolant supply connection beccee inopersble, an equal capsbility for long-term fluid makeup to the unit reactor en) for cooling of the unit containnent remains operable. Because of the availability of an equal makeup and cooling capab!11ty which is denonstrated to be operable immediately and with specified subsequent surveillance, a 30-day repr: r period is justi fied. Should the capability to provide standby coolant 10-day repair time is justified based on the low probability supply be lost, a for ever needing the standby coolant supply.
16h Amendment No. 64
6 c,
e oreg 0
UNITED STATES l'
7i NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C,20$55 t,
a
%, +~^..../
TENNESSEE VALLEY AUTHORIlf, DOCKET NO. 50-260 B_F')WNS FERRY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority _(the i
licensee) dated September 17, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Conunission'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 l
51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 60, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l
a
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d 6,2'
.. lim 7
Thomas A Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 60 FACILITY OPERATING LICENSE N0. DPR-52 DOCKET N0. 50-260 Review Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
151/152 153/T5T T6T/164 2.
The underlined pages are the pages being changed; marginal lines on these pages indicate the area being revised. The overleaf pages are provided for convenience.
l
a LIMITINC CONDITIONS FOR CPERATION SURVEILLANCE RF.QUIREMENTS i
3.5.C RRR Service Water and Emergency 4.5.C RHR Service Vater and E=ergency Equipment Cooling b'ater Systems Equipment Cooling Water Systems (EECWS)
(EECWS) 1.
Prior to reactor sta'rtup from a 1.
a.
Each of the RHKSW pumps cold condition, 9 RRRSW pumps must normally assigned to be operable, with 7 pumps automatic service on (including one of pumps D1, D2, the EECW headers will B2, or B1) assigned to RHRSW be tested automatically service and 2 automatically each time the diesel starting pumps assigned to generators are tested.
Each of the RHRSW pumps EECW service.
and all associated essential control valves for the EECV headers and RER heat exchanger headers shall be demon-strated to be operable once every three months.
b.
Annually each RHRSW pump shall be flow-rate tested. To be considered operable, each pump shall pump at least 4500 rpm through its normally assigned flow path.
151 Amendment No. 60
o I
1 1
1 i
t.1= tTINC rcNDITIONS FOR CPF.RATICN SURVET1.LA.NCE ECUI7f'E57S 3.5.C RN R Ser stee Water and Emertenev 4.5.C RNR Service Water and E err.ney FCut??ent Coolin4 Water Systems Ecutement Coolinz '4a t e r S is tees
( E EC* 'S i (Continued 1
( ETC'4S )
(Continued) 2.
During power operation.
2.
4.
If no more than two RHRSW pu=ps must be RHRF'J pu=ps are inep-operable and assigned etable, increased to service as indicated surveillance is not below for the specified required.
ti=e limits.
' hen three RHRS*J pu=ps b.
are inoperable, the remaining pumps, as so-CIME MINIMUM ciated essential cen-f.!MIT SERVICE ASSIC:iMIN*
trol velves, and asso-1 (CAYS)
RERSV EECWa*
ciated diesel genera-tors shall be operated Indefinite 7*
3*
weekly.
30 7* ar 6**"
2* or 3***
c.
' When fou r RH R5W p ump s are inoperable. the 7
6*
2*
remaining pu=ps, asso-cisted essential con-
- trol valves, and asso-
- At least ene operable pe=p must be ciated diesel ge: era-
.sssigned to each header.
tors shall be operated daily.
- n ly automatically starting pumps may be n
assigned to EEC'4 header ser*tice.
- Nine pumps must be operable. Either configuration is acceptable 7 and 2 or 6 and 3.
3.
Routine surveillance for these pumps is specified in 4.5.C.l.
1 3.
Curing unit 2 power oper-ation any two RPR5*J pu=ps (DI. 02. P.I. and 52) nor-mally or alternately as-siened to the RHR heat ex-changer header supplying the standby coolant supply connection nust be operable except as specified in l
- 3. 5. C. t. and 3.5.c.5 below.
152 l
l Amendment No. 60 i
l
e t1
$URVEILLA24CE 91CUIRDENTS t.!MIT!?tC CO?IDT.TICNS FCR OPERATICN 4.5.C (Continued) 3.3.C (Continued) 6 When it is determined that
/, three of the 01. D2 St. 82 plying standby coolant is RHP.St? pumps assigned t
!=ccerable at 4 tioc vnen the PJiR heat exchanger operability is requt:ed, the supp lyint; the standby operable RF.RSW pump on the coolant supply connection same header and its asso-ciated diesel generator and may be inoperable for a the RER heat exchanger period not to exceed h'*d*' **d *** ****** ****"~
30 days provided the ciel control valves shall operable pump is be demonstrated to be aligned to supply the operable is: mediately and RHR heat exchanger every 13 v'ays thereaf ter.
I header and the associated diesel generator and essential control valves are operable.
5.
The standby coolant J
supply capability may be inope able for a period not ta exceed ten days.
l 6.
If specifications 3.5.C.2 through l
3.3.C.5 are not met, an orderly shutdown shall be initiated and the unit placed i
in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
7.
There shall be at least 2 RHRSW pumps, l
associated with the sulected RHR pumps, aligned for RHR heat exchanger service for each reactor vessel contctining trradiated fuel.
l 153 t
t Amendment No. 60 i
LIMITI!;C Cat 0TTIONS POR OPERATION SURVEILLANCE REQUIREMENTS i
3.5.D E gip =ent Area Coolers 4.5.D Equipment Arca Coolers 3
1.
The equipnent aree cooler 1.
Each equipment ares coolers associated with each RRR is operated in conjunctica pump and the equipment area with the equipment served by cooler associated with ecch that particular coolcr; set of core spray pumps Q.
therefore, the equipeent area and C or B and D) must be coolers are tested at the operable at all times when same frequency as the pumps the pump cr pumpo served by which they serve.
that specific cooler is considered to be operable.
2.
When an equipcent area cooler is not operable, the pu=p(s) served by tMst cooler cust be considered inoperable for Technical Specification pur-poses.
E.
Mieh Pressure Coolant Injection E.
High Prcosure Coolent Injection System (n?CIS)
System (HPCIS) 1.
The HPCI sygten shall be 1.
HPCI Subsystem testing shall operable:
be performed as follows:
(1) prior 'to startup from a a.
Simulated once/
Cold Condition; or Automatic operating Actustion cycle (2) whenever there is irra-Test diated fuel in the reac-tor veeael and the reactor b.
Pump Opers-Once/
vessel pressure is greater bility conth than 122 psig, except no specified in specificc-c.
Motor _ Operated Cnce/
tion 3.3.E.2.
Valve Opera-conth bility d.
Flov Rate at Once/3 normal reactor monthe vessel opera-ting precoure t
e.
Flow Rate at once/
+
150 peig operating cyc1c 1
The HPCI pump shall deliater at least 5000 sps dering each flow rate test, i
154 Amendment No. 60
na an The suppressicn chamber can be drained when the reactor vessel pressure is atutospheric, irradiated fuel is in the reactor vessel, and work is not in progress which has the potential to drain the vessel. By requiring the fuel pool gate to be open with the vessel head removed, the combined water inventory in the fuel pool, the reactor cavity, and the separator /
dryer pool, between the fuel pool lov level alarm and the reactor vessel flange, is about 65,600 cubic feet ( k92.000 gallons ). This vill provide adequate low-pressure cooling in lieu of CSS and BHR (LPCI and contain-ment cooling mode) as currently required in specifications 3.5.A.h and 3.5.B.9 The additional requirements for providing standby coolant supply available vill ensure a redundant supply of coolant supply.
Control rod drive maintenance may continue during this period provided no nasre than one drie is removed at a time unless blind flanges are installed during the period of tf.e CRD's are not in place.
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t l
l 163 Amendment flo. 60 l
t
.D **D D
3' 3.5 BASES Should the capability for providing flow throuch the cross-connect lince be lost, a ten day repair time is allowed before shutdown is required.
This repair time is justified based on the very small probability for ever needing RHR pumps and heat exchangern to supply an adjacent unit.
REr'EHECCES 1.
Residual Heat Femoval System (BFDF FSAR subsecticn i.8) 4
?.
Core Stavlby Cooling Syr.teme (PFNP FSAP Deetion 6)
L 5.C RHH Se-vice Uater Syst n and B,er.rency Equ itv9ent Coc. ! 4e n '..'at e - "vn em (F1)
There are two EECW headers (north and south' with four automatic starting RHRSW pumps on each header.~ All components requiring emergency cooling water are fed from both headers thus assuring continuity of operation if either header is operable. Each header alone can handle the flows to all components. Two RHRSW pumps can supply the full flow requirements of all essential EECW loads for any abnormal or postaccident situation.
There are four RHR heat exchanger headers (A, B C, & D) with one EHR heat exchanger from each unit on each header. There are two RHRSW pumps on each header; one normally assigned to each header (A2, B2, C2, or D2) and one on alternate assignment (A1, B1, C1, or D1). One RHR heat exchanger header can adequately deliver the flow supplied by both RHRSW pumps to any two of the three RHRSW heat exchangers on the header. One RHRSW pump can supply the full flow requirement of one RHR heat exchanger. Two RHR heat exchangers can more than adequately handle the cooling requirements of one unit in any abnormal or postaccident situation.
The RHR Service Water Systems was designed as a shared system for three units. The specification, as written, is -conservative when consideration is given to particular pumps being out of-service and to possible valving arrangements. If unusual operating conditions arise such that more pun;s are out of service than allowed by this specification, a special case request may be made to the NRC to allow continued operation if the actual system cooling requirements can be assured.
Should one of the two FHRSU pumps nonmally cr alternately assigned to the RHR I
heat exchancer header supplying the' standby coolant supply connecticn beceme inoperable, an equal capability for long-term fluid makeup to the unit reactor and for cooling of the unit containment remains operable. Because of the availability of an equal makeup and coolin6 capability which is dencnstrated to be opernble immediately and with specified subsequent surveillance. n 10-day rep 2!r parind is just i fied.
Unit 2 nay be nupplied standby.oolant fran either or nor pumpn -B1. N!. nl. or D2.
Should the capability to provide standby coolant supply be lost, a 10-day repair time is justified based on the low probability for ever needing the standby coolant supply.
164 Amendment No. 60-