ML18031B129
| ML18031B129 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/12/1987 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML18031B130 | List: |
| References | |
| NUDOCS 8701150373 | |
| Download: ML18031B129 (90) | |
Text
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A~etio 1]
Remarks Instrument Channel-Reactor ~ Mater Level f63 (LIS-3-2n3 A-D) 2 538" aoove ves"el zero A or
{B and t)
Belov trip setting does the follovinq:
Initiate Reactor Buildzng Isolat ion b
Inxtiat Pramary Cont xrment Isolation c.
Iniczates MTS Instrument Channel
-'eactor Biqh Pressure 100
+
15 psig l.
Above trzp setting isolates the shutdovn coolin; "uction valves of the RHR system, l'ABLE 3 2 A PRINARY COHTAIl]Hl.PT A]CD RLACTOR BUII.UNC ISOIATION IHSTRU]CESTATlOA I f3)
Instrument Channel Reactor Lcw Mater Level (LIS-3-56 A-D)
Instrument Channel Biqh Dryvell Pressure f6)
(PIS-64-56 A D)
Instrument Channel-Bigh Radiation Hain Steam Line Tunnel f6)
Instrument Channel-Lcw Pressure Hain Steam (PIS-1-72, 76, 82, Instrument Channel-Sigh tlcnc Hain Steam Line (PctI S-1-13A-D, 25A-D; t 378" above vessel zero A
S I.S pllr h or tB and B) 3 times normal rated full power background a
SI$ psig tat 36A-D, 50A-D) 86)
S 140% of rated steam fine B
1 ~
Belo]c trip setting initiates Hain Steam Line Isc lation 1.
Above trip settinq does the follcwingI a.
Initiates Reactor Building Isolation b.
Initiate" Primary Containmen Isolation c
Initiates SCTS 1 ~
Above trip setting initiates Rain Steam l.ine Isolation
'1 Below'rip setting initiates Hain Steam Line Isolation Above trip setting initiates Hain steam Line Isolation
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BASES
-3.5M. Re ortin Re uirements The LCOs associated with monitoring the fuel rod operating conditions are required to be met at all times, i.e., there is no allowable time in which the plant can knowingly exceed the limiting values for MAPLHGR, LHGR, and MCPR. It is a requirement, as stated in Specifications 3.5.I, J, and K, that if at any time during steady state power operation it is determined that the limiting values for MAPLHGR, LHGR or MCPR are exceeded, action is then initiated to restore operation to within the prescribed limits.
This action is initiated as soon as normal surveillance indicates that an operating limit has been reached.
Each event involving steady state operation beyond a
specified limit shall be reported within 30 days.
It must be recognized that there is always an action which would return any of the parameters (MM?LHGR, LHGR, or MCPR) to within prescribed limits, namely power reduction.
Under most circumstances, this will not be the only alternative.
3.5.N. References
- 1. Loss-of-Coolant Accident Analysis for Browns Ferry Nuclear Plant Unit 2, NEDO 24088-1 and Addenda.
2.
"BUR Transient Analysis Model Utilizing the RETRAN Program,"
TVA-TR81-01-A.
- 3. Generic Reload Fuel Application, Licensing Topical Report, NEDE 24011-P-A and Addenda.
169A
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December 12, 1986 UOE6ISE AUTHORITY RkE OOI*k 0ockets IIos. 50-259~60 96
~ Aanager, Office of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Sir:
SUBJECT:
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, and 3
DO lRIOT REMOy.
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.Re:
Error in Amendments Nos.
- 129, 124,, and 100 By letter dated August 19, 1986, we transmitted amendments Nos.
129, 124, and 100 respectively for the Browns Ferry Nuclear Plant, Units 1, 2, and 3.
The Safety Evaluation enclosed referred to section 4.6.4.2 being removed from the Technical Specifications.
Section 4.6.4.2 was not requested to be removed, nor was it removed.
The Safety Evaluation has been corrected and the corrected version is enclosed.
In addition, Amemdments 129, 124, and 100 inadvertently removed information from pages
- 185, 185, and 198 for Units 1, 2, and 3 respectively.
Item 6.H in amendment 129, p. 185, item 4.6.H in amendment 124, p.
185 and item 4.6.H in amendment 100, p.
196 refers to BF SI 4.6.H.
These pages should each read "BF SI 4.6.H-l and -2" as was approved by Amendments
- 128, 123, and 99 issued on March 31, 1986.
Corrected pages are enclosed.
Sincerely, Marshall Grotenhuis, Project. Manager BWR Project Directorate ¹2 Division of BWR Licensing
Enclosure:
As stated cc w/enclosure:
See next page DISTRIBUTION
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Manager of Nuclear Power Tennessee, Valley Authority CC:
General Counsel Tennessee Valley Authority 400 Commerce Avenue E 118 330 Knoxville, Tennessee 37902 R.
M. Cantrell Acting, Director, Nuclear Engineering Tennessee Valley Authority 400 West Summit Hill Dirve, M12 A12 Knoxville, Tennessee 37902 R. L. Gridley Tennessee Valley Authority 5N 157B Lookout Place Chattanooga, Tennessee 37402-2801 M. J.
May Tennessee Valley Authority Browns Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602 H. P.
Pomrehn Tennessee Valley Authority Browns Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602
- Chairman, Limestone County Commission Post Office Box 188
- Athens, Alabama 35611 Ira L. Meyers, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 Browns Ferry Nuclear Plant Units 1, 2, and 3
Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311 Athens,.Alabama 35611
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SA ETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTIN iAMENDMENT NO. 129 TO FACILITY OPERATING LICENSE NO DPR-33 AMENDMENT NO. 124 TO FACILITY OPERATING LICENSE NO..
R-52 AYIENDMENT NO. 100 TO FACILITY OPERATING LICENSE DPR 68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNITS I 2 AND 3 DOCKET N S.
50-259 50-260 50-296
1.0 INTRODUCTION
t operation 2.0 EVALUATION The proposed amendments cl rify the requirements for seismic restraints,
- supports, an snubbers by adopt,ing the requirements of the Standard Technical Spec'cations.
This wob<ld permit the plant, during all modes. of operation to replace or restore inoperable seismic restraints,
- supports, and snubbers within a 7
hour period of time after they were discovered It also requi.res an engi eering analysis to show that the supported omponent(s) has not been dam ged by the inoperable snubber(s).
Sine this is a provision in the Stahdard Technical Specifications, tie addition of this requirement i acceptable.
The licensee a
so proposed to remove the following r uirements from the present Tech cal Specifications:
4.6.4 Visual Ins ection,
- Schedule, and Lot Size By letter dated February 12,
$ 86 (TV FNP TS-217),
the Tennessee Valley Authority (the licensee or TVA+requ ted amendments to Facility Operating License Nos.
DPR-33, DPR-and DPR-68 for the Browns Ferry Nuclear Plant, Units I, 2 and 3.
he proposed amendments would change the Technical Specifications to aIify the limiting conditions for regarding seismic res raih s, supports and snubbers.
The first inservice visual inspection of snubbers no previously it) luded in these technical specifications and whose
'sual hspection has not been performed and documented previo sly, shall e performed within six months for accessible snubbers a
d before resuming power after the first outage.
e purpose of this requirement was to assure that any safety-rela ed snubbers inadvertently missed during the first inservice visual inspection be visually inspected within a certain time frame.
Since these plants have been operated several fuel cycles, the deletion of this requirement, which applies only to the first visual inspection of
- snubbers, is therefore acceptable.
I
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~.o As noted above, the revised Technical Specifications would per it a unit to startup with an inoperable seismic restraint, support or s bber (SRSS),
which is consistent with the BWR Standard Technical S
ci.flcations (NUREG-0123).
At a glance, this might seem to be at variance ith the Ion standin corn liance-based oli ENVIRONMENTAL CONSIDERATIONS The amendments change a requirement with respect to installation or use of a facility component 1ocated within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of 'any efiluents that may be released offsite, and that there should be no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding.
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(9).
Pursuant to 10 CFR 551.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
9 9
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cy that any plant repairs should be completed before a plant starts up, even though some period of time might be allowed to fix the item it it becomes non-functional during operation.
(.For SRSSs, this period of time is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
If a SRSS is inoperable, it technically renders the system it is protecting inoperable.
The Browns Ferry Technical Specifications (TS) contain specific restrictions on what systems must be operable prior to startup.
For example, Section 3.5.A. 1 of the TS on.the core spray system (CSS) states:
"The CSS shall be operable prior to startup from a cold condition." If a SRSS on the CSS were inoperable, the unit could not startup until the SRSS was repaired.
As TVA stated in the justification for the proposed change to the TS in the submittal of February 12, 1986, "instances of starting the reactor prior to completing a
SRSS repair would rarely occur" because of the present restrictions in the TS on what systems (vs specific components of these systems) must be operable prior to startup.
The proposed revisions to the TS is not inconsistent with having plants ready for sustained operation before startup from a-shutdown condition and is acceptable.
4.0 CONCLUSION
We have concluded, based on the considerations discussed above, that: (I) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
t Principal Contributor:
H. Shaw, R. Clark Dated:
August 19, 1986
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Seismic Res r I gs S,o and Snubbers ing all modes of operationi all selsa<c restraint",
ann>ters, and upports shall be operable excep as noted in 3.6.H.1.
All safety<< elated snubbers are listed in Surveys'glance Instruction aF Sl 0.6.8 1.
11ith one o
more seismic restraint,
- support, or snubber inopcrablc on q system that is required to be operablc in the current plant condition, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re@ace or restor e the inoperab e
seismic restr aint (s),
uppor t s),
or snubber (s) to oper a le status and perform an engineering evaluation on the attached component or declare the attache system inoperable and follow the appropria e
Limiting Condition tatement for that syste The surveii pence rerut of percy" ph 4.G.C cre thu only r uircmenss that F ch sc: ""-.elated sn"bbe perfnrmsnte o! th<: fo -
. ~r-Soec'.'ti n
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BF SI I.
In"neer~<>n Crn<:o l Tl>".
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gorieud into tvo:.;".jor snubb.rs era accessible or inacccs<<iblc durin,", re ctor operation.
Thu e mayor Erouos
<'~y b<< furtner subd ivi< cd illto f, Qup e ba"ed on dc itn, a>le!t-ons:an, or other fc-tur;s vh.'eh ;ny ba exoectud to af!uct thc oparabilitv o:
the
'nubbc.s vxthln the pro<.p Each,"soup msv b.:
accrtd'loca vith 4eu.H.2 thrr<<'h 4.6.H.9.
2.
Vise.ll Irsnt!ation Sche "vie.
and !.,lt Si=c Thc "rst inservice visual inspe sion of nubbers not prcvin sly included in these tachnica~l specificatiors and vhosc vis/el inspect>on has not bah oerformad and documented p cviously, shell bc performed ithl.n six mon.hs for occ
'sible snub-ber.
and bciorc esuninf ponce airer the fx ".
rafuelinS outspc 185
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and 6 Iub c>>s During all modes of operation, all seismic restraints,
noted in 3.6.H.1
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. All safety-re ted snubbcrs are listed in Surveill nce Znstruction nF SI I).6.H.
only require)))cn ta any suspo
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Pith one o
more seismic restraint, s
por t, or snubbe inoperable on system that i
is required to e operable in "the cur. ent pl nt cond tion, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> re ace r
restore the inopera e
seismic restraint(s),
upport(s),i or snubber(s) to ope a
e status and perform n
engineering evalu tion on the attached corn nent or declare the a tachcd system inopera e and follow the ap ropriate Limiting Con ition statement for that sy tern.
!IF SI...u, !.
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In
)!)u r))))bh>>I'o ))ny I)c cate acr>> C'l'to tuo Groups cased on uhcthc
)c snu"bors arc acres ib'c or inatcc"sible durin" reactor ope 'l>> one Tlsusc sale arouos:tay bc iurtncr sub) vidcd into Il o) p based on dcs
))n, env one:unt, or other:c turus uh'ch riy bc c::occtu'o aifcc thc opcrnbi'itv o:
the snubber u t!lxs the gro).p.
Each group mav b).
ins-ected indene )'c; 'v acccrdancc uith 4.6.!!.2 thr::))~'!) t. 6. H. 9.
2.
isual. Insncction Schcd lc.
an
!.Ot Si=c Thc
. rs-in ervitc vi=ual in pec ion of nubbcrs not prcviou.
y included
'.".. these tcchnita speciiicationa and uhosc vis l inspection has not bec oeriorscd and docuscnrcd p eviouslv, shn')l bc ocriora)ad
'ithxn six a)onths for acc ssiblc snub-ber and before rc unin'oMcr a:tcr thc ir t refuel in)', outage 185 Amendment No. g.124
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SURVEZLLANCE RFQUZ RENEIJTS B.5 c'.T~vgY (~~cop y~!renpY 5 i"mi R>>stzeints.
5>>o> orts,
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and% nubbers During all modes of operation, all seismf,c restraints,
,except as ro ed in 3.6.H.1.
All safety-relate snubbers are listed in Surveillanc Znstruction BF SZ !J.6.H.
>Jith one or mo <e seismic restraint,
- support, or snubber inoperable on a k stem that is required to be perable in the current plan condition, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> repl ce or restore the inoperabl seismic restrairt(s),
uppor t or snubber(s) to operab status and perform an engineering evaluation on the attached component or declare the attache system inoperable and follow the appropria e
Limiting Condition tatement for that system.
PRI!V,RY SYS>."-..'. <<C.!aaii 1!
Sci s~i and Snubbcrs Svo"urt b
demon tzatud OPK;~KBa.E BY au!;um 'n: >>>I inso tv'o ]n BF Si 4.6.!!.
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In
. >>e ion Gro>>os T!1>>
I~,>>>hho r~ my hc cate-gorized i.nro tvo major groups based on vhcthcz snubbers are accessible or inaccessible durin reactor operation.
Th>>sc major grouos
>y b>> fvrthcr subdivided into provps based or. desi!;n, envir-
- onment, or o hcz features, vhich may bc c:<no<ted to affect thc opcrabi'ity o'h>>
- nubb>>rs vithxn the pro>.p.
Each group mac bc ins;ected indcprndcntlv acccrdanre vith 4.6.8.2 thzr>>h '.6.H.9.
The sur>>e illan nqutzemcn of para>",zaph
~ G.C cre th>>
only rcq:>i" ments that ape'y su'ppo c he rh n snubbe s
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Visual Insncction Schedule.
and
!.,>t si=c c f'rst inservicc ritual i
pection of nvbbers not prc iously included in these tech ical spec'fications anc vhosc visual inspection ha" no been pcrfor>sed and docvmcn d previously, shall bc pcrfn
. d vithxn six month.. for accessible "nub-bcrs and bc orc re unin.
pov>>r aft>>r c first rcfuclins out,e Amendment Nos. g,$ $ ~1oo 198
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IflcEPIsE AUTHoRITY FILE coPi DO NOT REMOYE
'I Docl<ets Nos.
50-25~260 296 Manager..of Nuclear Power Tennessee Valley Authori.ty 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37401
Dear Sir:
December 4, 1986 PC>KR c AfKU=
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The Commission has issued the enclosed Amendments Nos. 131, 127, and 1o2 to Facility Operating Licenses Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2 and 3.
These amendments are in response to your application dated February 24, 1986 (TVA BFNP TS 218).
The amendments change the.Technical Specifications to expand the structural integrity specification to include the balance of ASME Code Class 1,
2 and 3
equivalent systems.
A copy of the Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Comnission s Bi-Weekly Federal
~Re ister Notice.
Sincerely, Origlaal~
leaf Marshall Grotenhuis, Project Manager BWR Project Directorate 82 Division of BWR Licensing
Enclosures:
l.
Amendment No. 131 to License No. DPR-33 2.
Amendment No. 127 to License No.
DPR-52 3.
Amendment No. 102 to License No.
DPR-68 4.
Safety Evaluation cc w/enclosures:
See next page FCantrell,RII GGears DBL:PDO MGrotenhuis
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Manager of Nuclear Power Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3
CC:
General Counsel Tennessee Valley Authority 400 Commerce Avenue E llB 330 Knoxville, Tennessee 37902 r
R.
W. Cantrell Acting Director, Nuclear Engineering Tennessee Valley Authority 400 West Summit Hill Dirve, W12 A12 Knoxville, Tennessee 37902 R. L. Gridley Tennessee Valley Authority 5N 157B Lookout Place Chattanooga, Tennessee
" 37402-2801 M. J.
May Tennessee Valley Authority Browns Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602 H. P.
Pomrehn
. Tennessee Valley Authority Browns Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602
- Chairman, Limestone County Commission Post Office Box 188
- Athens, Alabama 35611 Ira L. Meyers, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311
- Athens, Alabama 35611
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UNITEDSTATES
.NUCLEAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 13l License No. DPR-33 0
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the
- licensee) dated February 24, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rul,es 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.
D.
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 (ii) that such activities will be
..'onducted in compliance with the Commission's regulations; a
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 Commission's regulations and al-.l 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 2.C.(2), of Facility Operating License No. DPR-33,,is hereby amended to read as follows:
.ii 0
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(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 131, 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 date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate 02 Division of BWR Licensing Date of Issuance:
December 4, 1986
I~l I
ATTACHMENT TO LICENSE AMENDMENT NO. 131 FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
~Pa es 183
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3.6.G Structural Inteprit 1.
The structural integrity of ASIDE Code Class 1, 2, and 3 equivalent components shall be maintained in accordance with Specification 4.6.G hroughout the life of the plant.
a.
Mith the structural integrity of any AS~K code Class l equivalent component, which is part of the primary system, not conforming to the above requirements, restore the
'tructural integrity of the affected component, to within its limit or maintain the reactor coolant system in either a cold shutdown condi-tion or less than 50 F above 0
the minimum temperature re-quired by NDT considerations, until each indication of a defect has been investigated and evaluated.
b.
Kith the structural integrity of any AS!K Code Class 2 or 3 equivalent component not con-forming to the, above require<<
ments, restore the structural in egrity of the affected component to within its limit or isolate the affected component from all operable systems.
20 Code Cl"ss 1,.Clos" 2, and per=or=cd i-accord-nce:.'.th Sect on ZX o the ~" 5o'~cr wd Prcssur Vessel Code "nd aoolicaole Addenda as requi ad by 10 Ci" SO, Scc "on 50.55a(".),
a@capt where speci"ic -.c'itzcn re~" ez has been S utcd by h.;C pursu"nt to 10 KR 50, Section SO.SSa(g) (6) (i).
Fcodvatcr Cri -9, ZFU-31, k~r 39, X ---3a,
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. l27 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the
. licensee) dated February 24, 1986, 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 conformity with the application, the provisions of the Act, and the rules pnd 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 (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 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 Commission'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 2.C.(2) of Facility Operating License No..DPR-52 is.hereby amended to read as follows:
0 C
II 0
l (2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
127, 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 date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
1 k
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate 82 Division of BWR Licensing
)0 Date of Issuance:
December 4, 1986
II+I 0
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ATTACHMENT TO LICENSE AMENDMENT NO. 127 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
~Pa ee 183
Oi Cl Cl
'i T;IQ C"ND T:"NS FOH OP:-::AT ON SQ. V,. =L
~ ~;C-.
c-..00",~)c)c-.i;T 3.o.G Structural Xnteprit 4o6oC Sc-.Oct))ccl 1".tc""'y
'0 1.
The structural integrity of ASHE Code Class 1, 2, and 3 equivalent components shall be maintained in accordance vith Specification 4.6.G throughout the life of the plant.
a.
Hith tlie " ")ictural irtegrity of any AS:!E code Class 1
equiv"lent componert, which is part of the primary system, not conforming to the above rcqui "e-..."rts, res tore the
'truc"ural integrit'f the affected compon"nt to within its 3 imit or...aintain the reactor cool;..it sy::tem in eithe" a col ) uhutdo.:n condi-tion t)r less than 50 I'bove the mini um tern erature re-quired oy !DDT considerations, unt'l eacii indicatio:i or a def ct has been investigated and e"'3 ua ted
~
2~it'.> t'.ie s ructi:"ai
- r. egrity o
an" AS C de Cl"ss " or 3
equivalent componer.t not con-forming to the above require-
- ments, restore the structural
'ntegrity o" tlie a fected component to -rithin its limit or isolate the affecteci component from all operable svs"ems.
4<<'sQ Jg.ce>>~~oe c
'~mr Cene Class 1
Clat s Cl s
3 components shall be per or ed in accordance and
-essu=e Vessel Code "d
applicable Adderda as requi cd by 10 C~. 50, Sec-"cn 50.55a("-~
eMQQt vncrn SQnc~"='"==ittan re&~L h s been granted b 4 'AC pu=sua:i= to 10 CR 50, Sec=="r.
50.55a(") (6) (i).
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9g> 98, 127
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. UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROMNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING.LICENSE Amendment No. lO2 License No. DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
.0 A.
B.
C.
- The application for amendment by Tennessee Valley Authority (the licensee) dated February 24, 1986, 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; A
~
'he facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 (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 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 Commission'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 2.C.(2) of Facility Operating License No. DPR-68 is hereby amended'o read as follows:
il~
i1
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
lo2, 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 date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Daniel R. Muller, Director BWR Project Directorate 82 Division of BWR Licensing Date of Issuance:
December 4, l986
4i 0
4
ATTACHMENT TO LICENSE AMENDMENT NO. 1O2 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
~Pa es 196
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izHI.Z:1G ca::Dz=z-.ls pon opzp~.-".o:1 t g~~r<>1~ h1g~gyq
~PA
~rhea Jah ~e!0 F:" t..-'.O.s'RY ill o PRXykRY SY T.=~1 E'Oi".:"!A1LY 3.6.0 Structural En ezritv J
i ~
j;.
h JJ L1 ~
Kith the structural.integrity oz cny.K.=" cod" Cla " 1 cuivalent co;.!adorant, 111hich is part oz ti e pri.~rv system!,
not conforming to the above r quire.;.ants, restore the tru" ural integrity oi the a= ected co~on nt to within i"s limkt -or m!aintain the reactor ccolant system in either a cold shutdolm condi-tion or less than 50 F "bove the wni"iud teaperatu c re-qu'red by ZD'Z considerations, until each indication of a dezect has b"en investigated and ev'!luated.
The structural integrity of ASlsr.
"ode Class 1, 2, and 3 equivalent co-.ponents shall oe ~intained in accordance lilith Specification 'l.6.G throughout the lire of th plant.
Code Cl"ss ',
C a pcrzozhh!ed 4w
~ca owe ~
~ ~ a 4
e:(capt 1 hc e sv e a
a en 1
~
pv "lant "o 10 ~ ~0 Sc
$0-5:-a(~) (6) (") ~
~
ith.the Rt uctur 1 illtuqrity o
ahly.!S.Z C de C
Jhass 2 or 3 equivalent component not con-zor-'ng.to the above require-
- ments, restore the structur 1
inte rity of tile affected co-ponent to cithin its lit!it or isolate the affected co.pcrcnt fro-all operable SvS te~s
~
Amendment No-gS. N. N, 102 ec 20 addi tior.a 1
~ ~acpactions "hali. Se perforned o.". certain circumlforontial pip z: lda as 1'"
d "-o p-olde ad@'i~<oaaL protect on "gainst pipe uhiy ~
zuhhzlxc y
c Q
ccntro-'Std:Pi&
e
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NFM-3 C, Gh h'-2> ~
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. l3l TO FACILITY.OPERATING LICENSE NO.
DPR-33 AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO. DPR-52 AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO. DPR-68 TENNESSEE VALLEY AUTHORITY.
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 DOCKETS NOS. 50-259, 50-260 AND 50-296
1.0 INTRODUCTION
By letter=dated 'February 24, 1986, (TVA 'BFNP TS 218), the Tennessee Valley Authority (the licensee or TVA) requested amendments to Facility Operating Licenses Nos.
DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear. Plant (BFN).
The applications. by TVA were in response to a request by the NRC staff on April 30, 1984, to revise the Technical Specifications (TS) of Browns Ferry Nuclear Plant Units 1, 2, and 3 to include not only the, primary system but, also the balance of ASME Code Class 1,
2 and 3 equivalent systems in the requiremen't to maintain
- structural integrity through inservice inspection..'-
'he amendments would replace the Limiting Condition for Operation (LCO) 3.6.G of BFN Units 1, 2 and 3 technical specifications, to expand applicability to include not only the primary coolant boundary but, also the balance of ASME Code Class 1, 2 and 3 equivalent systems.
2.0 EVALUATION The regulations for inservice inspection
were changed on February 27, 1976, to require that facility inservice inspection (ISI) programs be periodically updated to later editions of the ASME, Boiler
.and 'Pressure Vessel Code,Section XI.
'In order to eliminate conflicts between ISI requirements in the TS and those specified by regulations, 10 CFR 50.55a(g)(5)(ii) requires that TS be changed to reference 10 CFR 50.55a rather than contain details of specific ISI program.
The surveillance requirement for ISI has already been revised to include this reference by BFN amendment numbers 98, 92, and 65.
Revising the LCO as described here will provide additional clarification and broaden the requirements of 'LCO 3.6.G to be similar to Standard Technical Specifications (STS).
'L 4l i
0 3.0
SUMMARY
The staff has reviewed the licensee's submittal dated February 24, 1986.
Based on our review we find that the proposed amendments are in accordance with the guidance provided by the staff in its April 30, 1984
- letter, as well as the Section 3.4.8 of the Standard Technical Specifications for BWRs (NUREG-0123, Rev. 3, Dec.
1980).
Therefore, we find the proposed proposed changes acceptable.
- 4. 0 ENVIRONMENTAL CONSIDERATIONS The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there should be no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding.
Accordingly, the amendments meet the eligibilitycriteria for categorical exclusion set forth in 10 CFR 551.22(c)(9).
Pursuant to 10 CFR 551.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regula-
- tions, and the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
H. F. Conrad Dated.
December 4, l986
0 ii 0
i 41
~I.ICENSE AUTHORITY RkE OOPY November 17, 1986 Dockets
-Nos.
50-259 260'6 Ql" Manager of Nuclear Power Tennessee Valley Authority 6N'8A Lookout Place 1101 Market Street Chattanooga, Tennessee 37401
Dear Sir,
DO.NOT" REMOYE Po~
/Qb
~ &PE->
The Commission has issued the enclosed Amendments Nos.
130, 126, and101 to Facility Operating Licenses Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2 and 3.
These amendments are in response to your application dated April 8, 1986 (TVA BFNP TS 219).
The amendments"'change the Technical Specifications to delete references to charcoal filter heaters in the Standby Gas Treatment Systems.
A copy of the Safety Evaluation is also enclosed.
Notice of Issuance will be included in the Commission's Bi-Meekly Federal
~Re ister Notice.
Sincerely, O; I-i~.-: e';;,n~d by t,'j, C."O".. IIs'.iiS Marshall Grotenhuis, Project Manager BWR Project Directorate A'2 Division of BWR Licensing LSpessard, DI SRConnelly,OIA BJYoungblood OFFICIAL RECORD COPY FCantrell,RII GGears
Enclosures:
1.
Amendment No. 130 to License No.
DPR-33 2.
Amendment No. 126to License No.
DPR-52 3.
Amendment No. 10lto License No. 'DPR-68 4.
Safety Evaluation cc w/enclosures:
See next page DISTRIBUTION:
~li NRC PDR Local PDR JPartlow LHarmon BGrimes WJones OPA Plant File NThompson HThompson SRichardson,IE
-. JTaylor,IE BHayes,OI NGrace,RII SWeise,RII GZech,RII RBenerno SNorris OGC - Bethesda ACRS (10)
EJordan
'TBarnhart.(12)
DVassallo LFMB EButcher
'HDenton JHolonich CStahle TKenyon WLong TAlexion RWessman MGrotenhuis
11/5/86 si 6
Dst:Fodk'lI MGrotenhuis/cd Jj/j /86 AC - 'Bethesda DBQ: Pffft q> /,/86 gi /~/86
II +
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Manager, Office of Nuclear Power Tennessee Val.ley Authority Browns Ferry Nuclear Plant Units 1, 2,. and 3
0 CC:
General Counsel Tennessee Valley Authority 400 Commerce Avenue E 11B 330 Knoxville, Tennessee 37902 Director, Nuclear Engineering Tennessee Valley Authority 400 Hest Summit Hil.l Dirve, W12 A12 Knoxville, Tennessee 37902 R. L. Gridley Tennessee Valley Authority 5N 1578 Lookout Place Chattanooga, Tennessee 37402-2801 M. J.
May Tennessee Val.ley Authority Srowns Ferry Nuclear Plant-Post Office Box 2000
- Decatur, Alabama 35602 H.
P.
Pomrehn Tennessee Valley Authority Browns 'Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602
- Chairman, Limestone County Commission Post Office Box 188 Athens,,
Alabama 35611 Ira L. Meyers, M.D.
State Health Officer, State Department of Public Health, State Office Building Montgomery,, Alabama 36130 Regional Administrator, Region. II U..S. Nuclear 'Regulatory Commission 101'arietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training 'Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311
- Athens, Alabama 35611
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IIA0 0 %y*y4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
$ 3p License No.
DPR-33 0
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 8, 1986, 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 conformity 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 (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 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 Commission'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 2.C.(2") of Facility Operating License No.
DPR-33 is hereby amended to read as follows:
i'll 0
0 i~
2 3.
(2)
Technical S ecifications.
The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
130,, are hereby incorporated, in.the license.
The licensee shall operate the facility in accordance with the Technical Specifications'his license amendment is effective as of the date. of issuance and shall be implemented within 90 days from the date of issuance 4
FOR THE NUCLEAR REGULATORY CON ION A'ttachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1986 Danie'1 R. 'Huller, Director BWR Project Directorate 82 Division of BWR Licensing
'I 0
'TTACHMENTTO'ICENSE AMENDMENT NO.
130 FACILITY OPERATING 'LICENSE NO.. DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
Pacaes 56
.86 2.
The marginal lines on these pages denote. the area being changed.
4l 0
li
)tininium );o.
instrument lXt Clnlnnu j s Opc rob j e pr~tTri 5':s(~1) ))
2 (12)
'U Rem) rks A t ion~I]
T~r'lw i
t..ti.g Func't ion 200oF Inotrument Channel-Natn Steam Line Tunre
)
High Teaaperaturc 1.
Above trip set t inn inatiat rs Haan Steam Lare I eclat ia n.
ThnlE 3 2
A PRINARY cotnhi:1H tat I, IG HKAcl~lll Blitt.BIHC IMltATIOH IBSTRVHHHTATlOH 1
Instrument Channel Reactor Mater Clea aup System Ploor Drain High Temperature Instrument Channel Reactor Mater cleanup System Space Biqh Temperature Instrument Channel Reactor Building Venti-lation High Radiation-Reactor Zone Instrument Channel-Reactor Building Venti-lation Blqh Radiation Retueling Zone lbv 100oF la0 -
1804F S
100 mr/br or downscale G
100 mrlbr or downscale F
1 ~
n'uVv ar al ~ "eta a Mt ana a iateo
'.roiitaai ~ )f Reactor Mater L'.von>>p Lai ~
from Reactor
~:a)
."-e~ctur M ter Return Line.
1 e%e ac
.si JVC 1.
1 upscale or 2 downscale vill Inat late SCTS b.
Isolate reactor "one and retuelinq floor.
c.
Clos~
a oosphere control cysts.
1 upscale cr 2 dcvnscale vill a.
Int iate SGTS I o) atv refuelang floor.
c.
Close atmosphere control system 2 (7) t8)
Instrument Channel SGTS Flow - Train A
Heater HAH. Heater.
S 2000 cfm B and
{A or F)
Be)ov 200: cfm. a.rip settinc R.ll.
heater vill shut off.
2(2) f8) 2 I>) i8)
Instrument Channel SGTS Plow - Train B
Heater Instrument Channel SGTS Flow - Train C Hca'ter R.H. Beater S
2000 cfm R.H. Heater S 2000 cfm H and
{A or F)
H an'l ih or F)
."elov 2c00 cfm, trip setting R.H.
heater vill shut off.
~etov 200G cfm, trap settanq R.H.
t,eater
~l ll nut oil.
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1 TABLE ~
1 ~ A sURUEILLAHcE RBQQIRE)lEHTs FQA PA)HART coHTAIHHEHT AHD RTAcToA BU1LOIHC lsoLATIoH IHsTABHEHTATIoH n 'ti Instcuaent Channel Reactor Building ventilation Sigh Radiation - Refueling acne Instruaent Channel SOTS Train A Heater i)) i)4) )11)
)4)
Ca) Ihration r
uen once/3 sonths nstruzent Check once/day
)B)
Instriuzent Channel-SCTS Train B Beater lnstrunent Channel SCTS Train C Beater Reactor'uilding Isolation Tinec ire iue i ing I ioor) i4) ia) i4) once/operating cycle H/A Reactoc Building Isolation Tlnar izeactor zone),-
ia) once/operating cycle
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P O <<Wa*+'NITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
126 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 8, 1986 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 conformity 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 (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 Commission'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 2.C.(2) of Facility Operating License No.
DPR-52 is hereby amended to read as follows:
15 0
0 0
(2)
Techni'cal S ecifications
/
The Technical Specifications contained in Appendices A and B, as revised through Amendment No'. 126
, are hereby incorporated in the l.icense.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as, of the date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMM SION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1986 W777 Daniel'. Huller, Director BWR Project Directorate 82 Divi'sion of.
BWR Licensing
0 0
i Cl
ATTACHMENT TO LICENSE AMENDMENT NO. 126 FACIL'ITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
~Pa es 56 86 2.
The marginal lines on these pages denote the area being changed.
i i
0
Thnte 3.2.h PRlgh)ry COIrThl )II rrr r, >0 R Fpc'B>!r UUII.I>)t>G 1 >LRTIO~
1
)) 1 11 ).1>iurr> 'lio.
Ins tr i>men t ClrJnnul 5 Opur0b j 0 rur Tr>~s: s(l )I>~lpll~l Tri twvnl Settin pemr res
-'12)
Instrument Channe 1
)rain steam Line Tr>i>nc)
Hiqh Temperature 2006 F h)>ave trip s<.tt)nn in)tint "
Hair> Steam Linc 1 snl itirn.
Instrument Channel Reactor Mater Clea iup System Ploor Drain
)tish Temperature Instrument Channel Reactor Mater Cleanup System Space Hich Temperature Instrument Channel-Rcactor Building venti-lation High Radiataon-Reactor Xone Instrument Channel-Reactor Building venti-lation High Radiation-Retuelinr)
Xoi>c la
- leooF le0 -
1804F 5
100 nrrhr or downscale C
S 100 mr/br or downscale F
) ~
hivvv t t ili "t"t'tinu llrit iastcs
!::ri>>i.>r~
>f Reictor Water C.leo>nip L<<.
flem RC~Ctnr a:il
.-coactor
'!cr I cturn Line.
1..'use as.r.'ovc 1.
1 u).scale or 2 dovnscale vill In it i at c SG'1 S b.
tsolate reactor onc and retuclinq floor.
c.
Clos~ a:nosnhcre control system.
1 Opscale or 2 downscale vill D ~
lnltiato SCTS I ol ate refueling floors c.
Clo=c atmosphere control system 2 (7) 10) tnstrument Channel SCIS Flow - Train h Heater R ~.'I Heater 5 2000 cfm H and th or F) 2e)ov 20'. cfm, t,rip setting R.i).
heater will shut off.
2(T) IO)
Instrument Channel SGTS Plow - Train B
Heater R.H. Heater i 2000 cfm It and (h or below 2t30 cfm, trip sett inr) R.!I.
heater vill s)ut off.
2)T) fO)
Instrument Channel SCTS Flow - Train C
Heater H an~)
R.H. Beati.r 5 2000 cfm (h or r)
~clov 2000 ctm, trip sett in@ R.II.
heater vill shut otter
t Il 4l
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TAOISM
~ s 1 o A SURVE11LAHCA RIc)OIRCHE74TS tOR tAIIIART COHTAINHEHT AHO RCJLCTOA bUILOIHC ISOLATLOH 1HSTADNTHTATfOH Tnetcunent Channel Reactor sulldlnq vehttlattcat Stgh Qadlatlon Retue) lng reve lnatruhent channel-SALTS Tcaln A Seater lnetruneht Channel-SCTS Train B Ueatec fnetrunent Channel SCTS Train C Ueatei Reactor sutldtng leolatton Ttnec tcctuel tng t loor)
~~ass]~est tl) tl~ ) till tel t ~ I tel tel Cal lb ~t ton tre< ueh once/) hohthe once/operattng cycle Ihetruheht Cbegt once/day te)
H/A
'eactor sukldlng leo)ation Ttner tceactoc acne) te) once/operattng cycle
~ H/A
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/y UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT,, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
>o>
License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Coamission)
.has found that:
A.
The application for amendment by Tennessee Valley Authority (the
-licensee) dated April 8, 1986 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 (i) 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 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 Commission'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 2.C.(2) of Facility Operating License Xo. DPR-68 is hereby amended to read as follows:
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(2)
Technical' ecifications The Technical Speci.fications contained in Appendices A and B, as revised through Amendment No. 101,, are hereby incorporated in the license.
The licensee 'shall operate the facility in accordance with the Technical Speci'fications.
3.
This l,icense amendment is effective as of the date of issuance and shall be implemented within 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of. Issuance:
November 17, 1986 Daniel R. Muller, Director BWR Project Directorate ¹2 Divisi'on of BWR Licensing
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'TTACHMENT.TO LICENSE AMENDMENT NO.
101 FACILITY OPERATING LICENSE NO..DPR-68 DOCKET.NO. '50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
~Pa es 58 89 2.
The, marginal lines on, these pages denote the area being changed.
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Instr!!!sent Clll!nnuls OI croblc TAIII.B.I, 1 ~ A PIIIHAIIY CVIIThlqII'lit Ii Ili RIJiC1%)ll I!IIIIDIIIG I ROIATIOti Rll iTIllllIEIITATIllll Pu ction Tt I RA'.vr1 Srt t lni)
Art Inn~I]
Rem,items
(]4)
Instrument Channel Reactor Mater Clea lup System Ploor Drain Iligh Temperature Instrument Channel-Rcactor Mater Cleanup System Space Uiqh Temperature Instrument Channel Reactor Building Venti-lation nigh Radiation-Reactor tone Instrument Channel-Reactor Buildinq venti-lation Uiqh Radiation Rcfuelinq tone I
Ia
- Inoor 1804P I&0 nr/nr or dovnscale G
S 100 mr/hr ot dovnscalc 1 ~
A:vvv tt Rl ~ Sett l Aq Rtil 'RRJ too
~ ioj %t! Or lf Re lctot octet L.< nu!
al.
flos Rcottol a:i)
) csctut I'cr Return Line l.
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1 ug,scale or 2 dovnscale vill In)t late SGTS b.
Isolate reactor one and telucl inq floor.
e.
C Los>> Rtno phcre control sy tee.
1 upscale ot 2 dcvhscalc vill a.
Ini iatc SGTS I o)ate refuclrnq floor ~
C.
LLc.;c atmosphere control system.
2 (7) IB) 2(7) fn) 2(7) Ia)
Insttument Channel SGTS Flov - Train A Hca'ter Inst tument Channel SGTS PLov - Train B
llcater Instrument Channel SGTS Plov Train C Boater RADII lleater S 2000 cfm R.II Ucatct S
1000 cfri R.ll ~ llcatet S 2000 cfn 8 and IA or rl II and
{A or c)
II anl IA or F)
Belov fi);". cf:i, trip setting R.il.
!water vilL sliut off Rejov 2GQO cfm, trip sett inq R.!I.
hcatrr vill shut uft
~tlov 200G cfm, !11p se'l RAq R.ll.
tiedtct vlll hut 011
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~ t, TAbLb ~ o 2,A StevbILLANcb bboolbtxbbrs rob 1AI)ubf COHTAINlerr AÃo bbACron svILDING leoLArloH ibsrsmleeATIon Inatrueeat Channel-Qeactor building Venti4tfas Bigb bad)ation - Qotuelioy scae lnatrueat Cbannel-SCTS Train A beater.
Znetruncnt Channel-scrs Train b beater Inatroacat Channel-SCTS Train C beater Reactor building Isolatiaa Tbacr (refuel in@ tloor)
$ 1) $ 11) $ 22) le) b aticn t
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once/) aontha ooce/operating cycle Inetrunent check once/day (I)
):eactor building Ieolatioa Timor (roactor aona) once/operatic cycle
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0 UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
130 TO FACILITY OPERATING LICENSE NO.
DPR-33 AMENDMENT NO.
126 TO FACILITY OPERATING LICENSE NO.
DPR-52 AMENDMENT NO.
101 TO FACILITY OPERATING LICENSE NO.
DPR-68 TENNESSEE VALLEY AUTHORITY BRGWNS FERRY NUCLEAR PLANT UNITS 1, 2 AND 3 DOCKETS NOS. 50-259, 50-260 AND 50-296
1.0 INTRODUCTION
r By letter dated April 8, 1986 (TVA BFNP TS-219), the Tennessee Valley Authority (the licensee or TVA),requested amendments to Facility Operating Licenses Nos.
DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 1, 2 and 3.
The proposed amendments would change the Technical Specifications (TS) to delete references to one of the two electrical heaters in each of the three Standby Gas Treatment System (SGTS) trains in Brown Ferry Technical Specification Tables 3.2.A and 4.2.A (pages 56 and 86 for Units 1 and 2; pages 58 and 89 for Unit 3).
Specifically, the licensee proposes to delete the charcoal adsorber heaters while retaining relative humidity control heaters by changing "heaters" in tables from plural to singular for each SGTS train.
The licensee stated'n its submittal that the charcoal filter heaters have been deenergized and are being removed from the SGTS under the provisions of 10 CFR 50.59.
We did not concur with the licensee's interpretations of 10 CFR 50.59.
The staff called the Licensee and informed it that deenergizing the heaters prior to the TS change being approved by the staff would be a violation of the Browns Ferry Technical Specification.
- Further, since the change involves a TS change it cannot be done under 10 CFR 50.59.
.Based on this conversation the licensee will not remove the heaters under 10 CFR 50.59 but, wait for NRC approval of the amendment request.
2.0 EVALUATION The Browns Ferry SGTS serves Units 1, 2, and 3, and consists of three filtrations trains.
Each train contains an electric heater (40 kw) to reduce the relative humidity of the influent air to less than 70 percent.
The heater is energized automatically with startup of the SGTS and remains energized throughout SGTS operation.
Upon receipt of a DBA signal, all three.
SGTS trains should start.
The operator may shutdown manually one of the three trains.
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In addition to the above relative humidity control heaters, each of three SGTS trains is also provided with an electrical charcoal filter heater.
The original purpose of these heaters was to ensure that the charcoal adsorber beds do not experience significant moisture buildup during SGTS standby conditions.
The charcoal bed temperature is thermostatically controlled by the charcoal filter heaters, with high and low temperatures alarmed in the Main Control Room.
These electrical charcoal filter heaters are automatically tripped upon startup of a SGTS train..
1 Subsequently, the licensee has determined that operation of each train, with its associated'elative humidity control heater on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each
- month, as required in the Browns Ferry Technical Specification, is sufficient to control moisture buildup in the charcoal adsorber bed.
This determination is consistent with the staff's guidance in Regulatory Guide 1.52, Section c.4.d, which states that "Each ESF atmosphere cleanup train should be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per month, with heaters on (if so equipped),
in order to reduce the buildup of moisture on the adsorbers and HEPA filters."
The Standard Technical Specification (STS) for GE/BWRs in its Basis Section 3/4.7.2 also states that cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a
31, day period is sufficient to reduce the buildup of. moisture on the adsorbers and HEPA filters.
The staff does not require either a separate heater for the charcoal adsorbers or more than one heater in each train, so long as the.installed heater is capable of reducing the relative humidity of influent air to less than 70 percent.
The staff further accepts that the operation of
'he SGTS with this heater on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> each month is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.
The staff discussed with the 'licensee, the Browns Ferry Technical Specification Section 4.7.b.2.d to assure the inclusion of the relative humidity control heaters in the SGTS surveillance test.
In addition, the
,Browns Ferry Test Procedure SI-4.7,.B, Revision 2, and the schematic wiring diagram 45N771-2 show that the SGTS surveillance tests are performed with the relative humidity control heaters on automatic control mode.
The information assists in resolving the staff's -concerns regarding the inclusion of the heaters in the SGTS surveillance tests.
On the basis of the above evaluation, and the fact that the proposed amendments are consistent with (1) Regulatory Guide 1.52, Rev. 1, "Design, Testing, and Maintenance Criteria for Post Accident Engineered-Saftey-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants" and (2)
GE Standard Technical Specifications, BWR/4 and BWR/5.
The staff finds that the licensee's requested amendments are acceptable.
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- 3. 0 ENVIRONMENTAL CONSIDERATIONS The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part, 20 and in surveillance requirements.
The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any, effluents that may be released offsite, and that there should be no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding.
-Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(9).
Pursuant to 10 CFR 551.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amend-ments.
- 4. 0 CONCLUSION We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and.safety of the public wil,l not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's re-gulations, and the issuance of the amendments will not be inimical,to the common defense and security or to the health and safety of the public.'rincipal Contributor:
J.
Lee Dated:
November 17, 1986
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