ML19254D471
| ML19254D471 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/11/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19254D472 | List: |
| References | |
| NUDOCS 7910260021 | |
| Download: ML19254D471 (52) | |
Text
.
p "%q),,
f UNITED STATES y
g NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20655
%*...*/
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-33 1.
The Nuclear Regulatory Commission r
lission) has found that:
s A.
The application for amendaent by haessee Valley Authority (the licensee) dated July 20, 1979, 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 confomity with the application, the provisions of the Act, and the rules and regulations of the Connission; 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 witF the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense an't 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 opplicable requirements have been satisfied.
2.
Accordingly, the 1icense is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendnent and paragraph 2.C(2) of Facility License No. DPR-33 is hereby anended to read as follows:
(2) Technical Specifications 8
320 The Technical Specifications contained in Appendices A and B, as revised throJgh Amendment No. 53, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
7910260 0 1 /
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
v Thomas ppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 11, 1979 bl 32l O
ATTACHMENT TO LICENSE AMENDMENT NO. 53 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:
304/305 338/339 306/3D7
- 340/T4T 310/311 342/343 312/313
- 343/345 2.
The underlined pages are those beirg changed; marginal lines on these pages indicate the revised area. The overleaf pages are provided for convenience.
- There are no marginal lines on pages 306 and 312.
The change on page 306 is to move, verbatim, paragraph 3.10.B.2 from the bottom of page 305 to the top of page 306.
The change on page 312 is to move the first paragraph of 3.10.C " Spent Fuel Pool Water" verbatim from the bottom of page 311 to the top of page 312.
1^8 322
l, LIMITlHC CO8til1TinM; rom nPERATION SURVg1LIMCE RFf}UIRD4f.NTS 3.10.A Refueling Interlocks 4.10.A Refuelint interlocks O
refuelina interlocks shall be operable.
v b.
A sufficient number of control rodo shall be operable so that the core. can be made sub-critical with the otrongest operable con-trol rod fully with-drawn and all other
! j "h operable control rods
}
fully inserted, or al1 iW directional control valves for remaining control rods snell be disar,med electrically and sufficient margin to criticality shall be demonstrated.
c.
If maintenance is to be performed on two control rod drives they must be separated by more than two control cells in any direction.
y J.
An appropriate number of SRM's are available as defined in specif1-cation 3.10.B.
i 6.
Any en.ber of cont rol rod' 3.
With the riode selection swit:k e6a y be wit helrewn or removed in from the reactor core pro-the refuel or Shutdcun tode, r.:
viding the following condi-Control rod may be with: ras.n **"*I two licensed Operators have cerficer+f tions are entistled:
.that either all fuel has been re-e.t.i s.
The reactor mode switch from ar0Und that rod or that all is locaed in the "re.
Control rods in immediately a:*40ETI fuel" position. The Cells have been fully insertpg gn:
refueling interlock electrically disarmed.
which prevents sore than one control rod from 8
323
'^#
304 D
b Amendment No. 53
tiestter. c4rentflises ret otra,aftou svavetLLAsci troutatwtwT5 3.10.A tafvetten Inteeleche 4.10.4 'Biefooltat teteeleche betag withdrawn may be bypassed en a withdraws U
coa t t el re.d a f t.ar t he fuel sasem611ee la the ce ll a se t eis ta a (e so-trolled by) that ese-t rol v ed have been re-1 no ved f r om the reestae q
]
b e.re.
411.tm., re.
fealles interle.hs ll A
ena11 be operable.
3.
Core Mentroring 3.
Core Mentterfar 1.
During core alterations. e.xcept Frier to makins any siteratlane as in 3.10.5.2. two SPJt's shall to the core the 51M's shall be fosstionally tasted and checked be operable. in or adjacent '. J any for naist ren r e s po n s e.
Ther.-
quadrant where fowl or control "I"* 'hII" '
- I'*d 6' Tods are being moveJ.
For a n SRf1
- '**I'*
- 'III **
to be considered operable, the
&&d daily for response following shall be satisfied:
except as specified in 3.10.B.1.b.2.
a.
The SPJI shall be inserted to the normal operating level.
(Us e of special meveable.
dunking rype detectors during initial fuel l'oading and maj or core alt e>
. sons in place
,n, q
g of normal detect;rs is per-O v
eissible as long ar. the detector is connected to th-notsal SRM eircuit.)
b.1 The SRM shall have a minimum of 3 cps with all rods fully inserted in the core, if one or acre fuel assemblies are in the core, or, b.2 During a full core reload where both irradiated and fresh fuel is being loaded, SRM's (FLC's) may have a count rate of <3 cps provided that the SRM's are response checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a neutron source until >3 cps can be maintained, and provided also that the core is loaded in a spiral sequence only.
305 v
Amendment No. 53
E LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2.
During a complete core removal, the SEN's shall have an initial minimum count rate of 3 cos prior to fuel removal, with all rods fully inserted and rendered electries11y inoparable. The count rate will diminish during fuel r emov a l. Individual control rods outside the periphery of
- 7. pg the then esisting hoci ma t r ia pjl
. E)
, I 3
may be electrically armed and gU j{
j moved for maintenance af ter all fuel in the cell containing f ront roll ed by l t h.i t control rod have been removed I' rom the reactor core.
3.10.C Spent Fuel Fool Water 4.10.C Spent Puel Pool Water s
1.
Whenever irradiated fuel is 1.
Whenever irradiated fuel is stored in the spent fuel stored in the spent fuel pool, pool, the pool water level the water level and temperature shall be maintained at a shall be recorded daily depth of B 1/2 feat or greater above the top of the spent fuel. A minimum of 6-1/2 feet of water shall be maintained over single irradiated fuel assemblies during transfer and handling cperations.
2.
Whenever irradiated fuel is 2.
A sample of fuel pool water in the fuel pool, the pool shall be analyzed in accordance water temperature shall be with the following specifications:
~< 150*F.
a.
At least daily for conductivity 3.
Fuel pool water shall be and chloride ion cor. tent.
maintained within the f ollowing 11=1r.s :
b.
At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for conductivity and chloride conductivity 3,10 umhos/cm content when the fuel pool
@25'c cleanup system is inoperable.
chlorides 1 0.5 ppm I"'O b2 306
/Vnendment No. 53
SURVEILLANCE REQUIREMINTS 1,tMITING Cn.4n1TIONS FnR OPERATION 4.10.D Reactor Buildfat Crane 3.10.D Resetor Bofiding C r sne_
1.
The following operational 1.
The reactor building crans checks and inspections shall
(
shall be operable:
be performed on the reactor building crane prior to a.
When a spent fuel cask handling of a spent fuel cask is handled.
and new or spent fuel, (These need not be performed b.
Whenever new or spent more frequently than fuel is handled with quarterly.):
the 5-ton hoist.
a.
The cab and pendant con-trole shall be demon-strated to be operable en both the 125-ton hoist and the 5-ton hoist.
b.
A visual inspection shall be made to insure structural it.tegrity of I) h
{'}
(\\ [U l 5-ten hoist and cask yoke the 125-ton hoist, the I
safety vire ropes.
The overtravel limit c.
svitch int erleck s, move-e.ent speed control and braking operations for the bridge, trolley and hoists, the pendant inter-locks, the esin-auxiliary hoist operation interlock, and the remote er.ergency stop shall be functionally tested.
E.
Spent Tuel Cask E.
Spent Fuel C.isk 1.
Prior to attachment and 1.
Upon receipt. an empty lifting of an empty spent fuel ensk shall not be fuel cask from the shipping Itfted until a visual trailer, a visual inspection inspection is made of the shall be conducted on the cask-lifting trunnions and lifting trunnions and the f as tening connec tion has fasteners used to connect the been conducted.
trunnion to the cask.
307 1
8 326
3.10 EA'.I.5 rods and the r e f ue ling plat f orm pr ovide r e d u n.la n t methods of preventinf.
inadvertent criticality even after procedural violations. The interlocks on hoists provide yet another method of avoiding inadvertent criticality.
Tuel handling is normally conducted with the fuel grapple hoist. The total load on this hoist when the interlock is required consists of the weir.ht of the fuel grapple and the fuel assembly. This total is approxi-mate.y 1,500 lbs, in cemparison to the load-trip setting of 1,000 lbs.
Frovisions have also been made to allow fuel hardling with either of the three auxiliary hoists and still mair tain the refueling interlocks. The 400-lb load-trip setting on these hoists is adequate to trip the interlock when one of the more than 600-lb fuel bundles is being handled.
During certain periods, it is desirable to perform maintenance on two control rods and/or control red drives at the sare time.
The maintenance is performed with the mode switch in the " refuel" osition to provide the refuelint interlocka normally available during re'ueling operations.
In order to withdraw a second control red after wit drawal of the first rod, it to necessary to bypass the refueling interlock on the first control rod which prevents more than one control rod from being withdravm at the sane time.
The requirerent that an adequate shutdown Pargin be demonstrated
~
or that all ter.aininE control rods have their directienal control valves elec t rically dica rmed ensures that inaevertent criticality cannot occur during this maintenance. The adequacy of the shutdown targin is verified by de*eastrating that the core is shut down by a carr,in cf 0.35 percent er that at Lk with.the strengest eperable centrol rod fully withdrawn, least 0.38: ak shutdown margin is available if the rer.aining centrol rods have had their directional control valves disarmed.
Disarming the direc-tional control valves does not inhibit control rod scram capability.
Specification 3.10.A.6 allevs unloading of a significant portion of the reactor core. This operation is perforced with the mode svitch in the
" refuel" position to provide the refueling interlocka normally available during refueling operations.
In crder to withdraw mo.e than one cer.trel rod, it is necessary te bypass the refueling interlock on each ithdraen control rod which prevents more than one control rod from being withdrawn at n time.
The requirement that the fuel assemblies in the cell controlled by the control rod be removed froo the reactor core before the interlock can be bypasscJ ensures that withdrawal of another control red does not result in inadvertent criticality. Each control rod provides prie.ary reactivity control for the fuel assemblies in the cell associated with chat control rod.
Thus, removal of an entire cell (fuel assemblics plus contrel red) results in a lower reactivity potential of the core. The requirements for SRM operability during these core alterations ascure sufficient core menitoring.
31G
1,10 SASES REFERENCES 1.
Ref ueling inter f ocks (BFNP FSAR Subsection 7.6) 5.
Core Monitoring The SRM's are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and Requiring two operable SRM's in or adjacent to any station startup.
core quadrant where fuel or control rods are being moved assures ade-quate monitoring of that quadrant during such alterations. The require-ment of 3 counts per second provides assurance that neutron flux is being monitored and ensures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
During a full core reload SRM/FLC (Fuel Loading Chamber) operability will be verified using a portable external source at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until sufficient fuel has been loaded to maintain 3 eps. A large number of fuel assemblies will not be required to maintain 3 eps.
This increased surveillance rate assures proper detector operability until that tLee.
Under the special condition of removing the full core with all is permissible control rods inserted and electrically disarmed, itAll fuel moves to allow SRM count rate to decrease below 3 cys.It is expected that during core unloading vill reduce reactivity.
the SRM's will drop below 3 eps before all of the fuel is unloaded.
Since there vill be no reactivity additions during this period, the When all of the low number of counts will not present a hazard. fuel storage pool, SRM's will no fuel has been removed to the spentRequiring the SRM's to be functionally tested longer be required.
the SKM's will be operable at the prior to fuel removal assures thatThe daily response check of the SRM's ensures start of fuel removal.
their continued operability until the count rate diminishes due to Control rods in cells from which all fuel has been fuel removal.
'he periphery of the then existing fuel removed and which are outside matrix may be armed electrically and moved for maintenance purposes during full core removal, provided all rods that control fuel are fully inserted and electrically disarmed.
REFEREN CES_
Neutron Manitoring System (BFNP FSAR Subsection 7.5) 1.
Morgan, W. R.,"In-Core Neutron Monitoring System f or General Electric Boiling Water Reactors," Ceneral Electric Co=pany, Atomic Power 2.
Equipment Department, November 1968, revised April 1969 (APED-570F1 b
320 311 Amendment No.
53
a 3.10 EASES C.
Spent Fuel Pool Water The design of the spent fuel storage pool provides a storage locat?on for approximately 140 percent of the full core load of fuel assemblies in the reactor building which ensures adequate shielding, cooling, and reactivity control of irradiated fuel. An analysis has been performed which shows that a water level at or in excess of eight and one-half feet over the top of the stored assemblies will provide shielding such that the maximum calculated radiological doses do not exceed the limits of 10 CFR 20.
The normal water level provides 14-1/2 feet of additional water shielding.
The capacity of the skimmer surge tanks is available to maintain the water level at its normal height for three days in the absence of additional water input from the condensate storage tanks. All penetrations of the fuel pool have been installed at such a height that their presence does not provide a possible drainage route that could lower the normal water level acre than one-half foot.
The fuel pool cooling system is designed to maintain the pool water temperature less than 125'F during normal keat loads. If the reactor core is completely unloaded when the pool contains two previous discharge batches, toe temperature ma,'
increase to greater than 125'F.
The RHR system supplemental fuel pool cooling mode will be used under these conditions to maintain the pool temperature to less than 125'F.
3.10.D/4.10.D B AS ES Reactor Building Crane The reactor building crane and 125-ton hoist are required to be operable for handling of the spent fuel in the reactor bui? 'ing.
The controls for the 125-ton hoist are located in the crane cab. The 5-ton has both cab and pendant controls.
A visual inspection of the load-bearing hoist wire rope assures detec-tion of signs of distress or wear so that corrections can be promptly made if needed.
The testing of the various limits and interlocks assurcs their proper operation when the crane is used.
3.10.E/C.10.E Spent Fuel Cask The spent fuel cask design incorporates removable lifting trunnions.
The visual inspection of the trunnions and f asteners prier to attach-ment to the cask assures that no visual damage has oc,urred during prior handling. The trunnions must be properly attached to the cask for lif ting of the cask and the visual inspection assures correct installation.
O 329
~
312 Amendment No.
53
3.10.?
f c c: *.. ' ' n r V *
.. i s.._ - Yv f A k i::" i. e.'>r A*.....r.:.-lt Taiits 1,. t teet j n. : i:: L,c c n pr..-i f.e ? 1: tl.e de r.5,.r: c."
t..e 125-ten hoist d r t::- shaft, vire ronet., h >M ted lover blo:1. ecserisay c the reecte r t ildir,; crane, the lir.iting of lift heit;ht of a sper.t
(.
f.e: cask contrels the amount of energy available in a dropped cask 5.
- ' ient whe.- t he ce sk is e ecr the re'uclin.- fj o'
- k. crr.'.ysis bac been P...le which : h'..r t hat t he fJ oor L id support r.cr.Ler s it the area cf ets}. tr.try it.tc thc de: entre.instier fr.cility can s h *. i t -
re:te-;1:. suste.in a drcp ed cask frer a heicht of 3 feet.
Tr.e y:he s re ty links pr vide sinc,le fr.ilure protectie-for the hoek e : ' : r er b'+ck. usber.11y rind If r.it en:k rote. tion.
Ctrk rotstici,ir t.er er r ar;; fer ce rci.it.inat ier er.d t he.sa fety lin!.: r.rc r e,o v e d d..ri n -
d e:ent r.-i n sti on.
P00R 0111NAL s
330 313
6.0 ADMINISTRATIVE COffrROL5 300R OR E L
- 6. 3 Procedures A.
Detailed written procedures, including applicable check-off lists covering items listed bel;w shall be prepared, approved and adhered to.
1.
Normal startup, operation and shutdown of the reactor and of all systems and components involving nuclear safety of the facility.
2.
Refueling operations.
3.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.
4 I:mergency conditions involsing potential or actual release of Radioactivity.
5.
Preventive or corrective maintenance operations which could have an effect on the safety of the reactor.
6.
Surveillance and testing requirements.
7.
Radiation coatrol procedures.
8.
Radiological Dnergency Plan implementing procedures.
9.
Plant security program implementing procedures.
10.
Fire protection and prevention procedures.
B.
Written procedures pertaining to those items listed above shall be reviewed by PORC and approved by the plant superintendent prior to implementation.
Temporary changes to a procedures which do not change the intent of the approved procedure may be made by a member of the plant staff knowledgeable in the area affected by the procedure except that temporary changes to those items listed above except item 5 require the additional approval of a member of the plant staff who holds a Senior Reactor operator license on the unit affected.
Such changes shall be documented and suosecuently reviewed by PORC and approved by the plant superint end ent.
m
'^'8 331
6.0 ADMINIS'TRATIVE CONTROLS C.
Drills on actions to be taken under emergency conditions involving release of radioactivity are spe cified in the radiological energency plan and shall be conducted annually.
Annual drills shall also be conducted on the actions to be taken following failures of aafety related systems or components.
D.
Fadiation control Procedures Radiation Control Procedures shall be maintained and made available to all station personnel.
These procedures shall show permissible radiation expoeure and shall be consistent with the requirementre of 10 CTR 20.
This radiation protection program shall he organized to meet the requirements of 10 CTR 20 except in lieu of the or " alarm signal" required by paragraph "centrol device a 20.203 (c) (2) of 10 crn 20:
1.
Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1,000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area, and entrance thereto shall be coitrolled by issuance of a special work permit.
Any individual or group of individuale permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose while ln l
the area.
2.
Each Righ Radiation Area in which the intensity of radiation is greater than 1,000 mrem /hr shall be subject to the pr9visigns of (a) above; and, in addition, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under administrative control of the shif t engineer on duty.
O J D"' L3
'n*
n
~1 339 Amendment No.
53
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'^'S 333 Amendnent No. 53 340
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'^8 334 Amendment No.
53 341
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335
'~#
Amendment No.
53 342
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'3 336 Amendment No.
53 343
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'"'8 337 A
Amendment No.
53 344
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^^8 338 Amendment No.
53 345
go nigg, f
UNITED STATES
'g NUCLEAR REGULATORY COMMISSION y
E WASHINGTON, D. C. 20555
\\
/
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The opplication for amendment by Tennessee Valley Authority (the licensee) dated July 20, 1979, 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 Conmission; 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 Spec-ifications 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. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
1'" 8 339
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas ppo'ito, ief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 11, 1979
'"'8 340
ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE N0. DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages:
303/304 305/306*
311/312*
339/340 341/342 343/344 345/346 2.
The underlined pages are those being changed; marginal lines on these pages indicate the revised area. The overleaf pages are provided for convenience.
- There are no marginal lines on pages 306 and 312.
The change on page 306 is to move, verbatim, paragraph 3.10.B.2 from the bottom of page 305 to the top of page 306.
The change on age 312 is to move the first paragraph of 3.10.C " Spent Fuel Pool Wat>., verbatim from the bottom of page 311 to the top of page 312.
1^8 341
SURvr ?!.LaNCT. RErt1TREMINTS FCR OPFWATION
.l.tMITINC CONutTION' 4.10.A Refueling Interlocks J.10.A Refueling Interloeis control rods are fully inserted and have had their directional con-trol valves electrically disarmed, it is suffi-cient to demonstrate that the core is sub-critical with a margin of at least 0.38 ok at any time during the maintenance. A control rod on which enintenance is being performed shall be considered inoperable.
).
The fuel grapple hoist load switch shall be set a t _< 1,000 lb s.
4.
I f the f rame-mount ed auxi-lgj I
11ary hoist, the r-onora11-mount ed auxilia ry hoist. or g
[
the s e rvice 'pla t f o rm hois t is to be used for handling fuel with the head off the reactor vessel, the le a'd limit switch on the hoist to be used shall be est at
<400 lbs.
5.
A nsx t r.u, o f two non-adjacent control rode may
- g }
be withdrsvn from the core for the purpose of perf or-ming control rod and/or cont rol rod d rive mainten-ance. provided the follow-ing conditions are satis-fled:
The reactor mode switch a.
shall be locked in the
" refuel" position. The refueling interlock which prevents more than one contrel red f rom being withdrawn may be bypassed for one of the cont rol rods on.which maintenanct is being pe r f orme d. All other 303
a 3.s m a r iut, reiwn t T i nn t.
row nPt it.ATloN sutvEtt.LJLNCE REQUIR DWNTS 3.10.A Refueling Interincha 4.10.A Refuelinr Interlocks O
refueltna interlocks shall be operable.
U b.
A oufficient number of control rode shall be operable so that the
)
core can be made sub-critical with the
,d j"(
etrongest operable con-trol rod fully with-drawn and all other operable control rods fully inserted, or al-1 directional control valves for remaining control rode anall be disarmed electrically and sufficient margin to criticality shall be demonstrated.
c.
If maintenance le to be performed on two control rod drives they must be separated by more than two control celle in any direction.
g, d.
An,approprinte number of P.ut's arc availabic as defined in specifi-cation 3.10.B.
6.
Any nu.hcr nf control rode 3.
With the mode selection s.< itch in may be withdram or removed the re fuel or ShutdC in C0de, r from the reactor core pro-riding the following condi-Control rod may be.vithara..n u til tW IWW moh h wHg tiene are satt fted.
tMtd h difM m W n-W a.
The reactor mode evitch from around that rod or that all is locked in the "re.
Control rods in immediately a;ji:E*:
fuel" Po,1ston.
The Cells have been fully inserted 3T.C refueling interlock electrically disar:ted, which prevente sore than one control rod fros
'^'8 343 r
V Amendment No.
48
t
~
_Limittser. connittimes res orgaAT!ce SU1rft11 t.MfCI tt0UlttWENTS 3.10.a Refwellet laterteche 4.10.& amfeel.~1 Interleche being withdrawn any be bypassed en a withdrews U
control red after the fuel easemblies in the eell asetelsLas (een-trolled by) that een-trol ved have been to.
esved from the roastar eers. All other rs=
fueltog interlocka shall be eterable.
B.
Core Mrnitoring 3.
Care Mont to ring 1.
During core alterations, except Frier to makins any etterattane as i n 3.10. B. 2, tvn SR.'t 's s ha ll to the core the SIM's shall be fasetionally tested and checked he operable. in or adjacent to any I*' "***'*"
P*****
D*
quadrant shere fuel or control siter, while required to be rods are being moved.
For an SM
- 'III I' te be considered operable, the
&&d daily for response except following shall be sa t i s t led :
as specified in 3.10.5.1.b.2.
a.
The SP'! s ha ll be ins er t ed to the normal operatins; level.
("se of special moveable, dunking, type det ec tors during ini tial f uel loadar.g and major core altera:lons in place missible as long as the detector 1
1
' il v
of normal detectors is per-(
is c annected to the riortaal SRM o
i i
circuit.)
b.1 The SRM shall have a minimum of 3 cps with all rods fully inserted in the core, if one or more fuel assemblies are in the core, or, b.2 During a full core reload where both irradiated and fresh fuel is being loaded, SRM's (FLC's) may have a count rate of <3 cps provided that the SRM's are
,-4 3
344 response checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a neutron source until >3 cps can be maintained, and provided also that the core is loaded in a spiral sequence only.
305 Amendment No.
48
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 2.
During a complete core r em ova l,
the SRM's shall have an initial minimum count rate of 3 cps prior to f uel removal, with all rods fully inserted and rendered electrically inoperable. The
(
I l
ecunt rate will diminash during fuel removal. Initividual cont rol rods outside the periphery of the then existing fbcl matrix may be electrically armed and moved for maintenance af ter n'll fuel in the cell containing (cont rolled byl that control rod have been removed from the reactor core.
3.10.C Spent Fuel Fool Water 4.10.C Spent Puel Fool Water 1.
Whenever irradiated fuel is 1.
Whenever irradiated fuel is stored in the spent fuel stored in the spent fuel pool, pool, the pool water level the water level and temperature shall be maintained at a shall be recorded daily depth of 6 1/2 feet or greater above the top of the spent fuel. A minimum of 6-1/2 feet of water shall be maintained over single irradiated fuel assemblies during transfer and handling operations.
2.
Whenever irradiated fuel is 2.
A sample of fuel pool water in the fue.1 pool, the pool shall be analyzed ir. accordance water temparature shall bc with the following specifications:
~< 150*?.
a.
At least daily for conductivit:
3.
Fuel pool water shall be and chloride ion cor. tent.
maintained within the following limits:
b.
'At least once per E hours f or conductivity ar.d chloride conductivity <,10 umhos/cm centent when the fuel pool 625'c cleanup system is inoperable.
chlorides < 0.5 ppm T.
> n a 8
343 e
306
t 1.10 srSES y
REFERENCES 1.
Refueling interlocks (BFNP FSAR Subsection 7.6) f B.
Core Monitoring The SRM's' are provided to monitor the core during periods of station shutdown and to guide the operator during refueling operations and station startup.' Requiring two operable SRM's in or adjacent t, any core quadrant where fuel or control rods are being moved assures ade-quate monitoring of that quadrant during such alterations. The require-ment of 3 counts per second provides assurance that neutron flux is being monitored and ensures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident.
During a full core reload SRM/FLC (Fuel Loading Chamber) operability will be verified using a portable external source at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> until sufficient fuel has been loaded to maintain 3 cps. A large number of fuel assemblies will not be required to maintain 3 cps.
This increased surveillance rate assures proper detector operability until that time.
Under the special condition of removing the full core with all control rods inserted and electrically disarmed, it is perctissible to allow SRM count rate to decrease below 3 cps. All fuel moves during core unloading vill reduce reactivity. It is expected that the SRM's will drop belov 3 cps before all of the fuel is unloade d.
Since there vill be no reactivity additions during this period, the low number of counts will not present a hazard. When all of the y
fuel has been removed to the spent fuel storage pool, SRM's vill no longer be required. Requiring the SRM's to be functionally tested prior to fuel removal assures that the SRM's will be operable at the start of fuel removal. The daily response check of the SRM's ensures their continued operability until the count rate diminishes due to fuel removal. Control rods in cells from which all fuel has been removcd and which are outside the periphery of the then existiag fuel matrix may be armed electrically and moved for maintenance purposes during full core removal, provided all rods that control fuel are fully inserted and electrically disarmed.
REFERENCZS 1.
Neutron Manitoring System (BFSP FSAR Subsection 7.5) 2.
Horgan, W. R.,"In-Core Neutron Monitoring Systen for General Electric Boiling Water Re. actors," General Electric Company, Atomic Power Equipment Department, Nove nber 1968, revised April 1969 ( ADLD4706)
'^'8 346 1
311 Amendment No.
48
P00R ORGINAl.
^-
C.
Spent Fuel Pool Water The design of the spent fuel storage poel'provides a storage location for approximately 140 percent of the full core load of fuel assemblies in the reactor building which ensures adequate shielding, cooling, and teactivity control of irradiated fuel. An analysis has been performed which shows that a water lqvel at or in exccas of eight and one-half feet over the top of the stored assemblies will provide shielding such that the maximum calculated radiological doses do not exceed the limits of 10 CFR 20.
The normal water level provides 14-1/2 feet of additional water shielding.
The capacity of the skimmer surge tanks is available to maintain the water level at its normal height for three days in the absence of additional water input from the condensate storage tanks. All penetrations of the fuel pool have been installed at such a height that their presence does not provide a possible drainage route that coul lower the normal water level more than one-half foot.
The fuel pool cooling system is designed to maintain the pool water temperature less than 125'F during normal heat loads. If the reactor core is completely unloaded when the pool contains two previous discaarge batches, the temperature may increase to greater than 125'F.
The RHR system supplemental fuel pool cooling mode vill be used under these conditions to maintain the pool temperature to less than 125'F.
3.10.D/4.10.D B AS ES Reactor Buirding Crane
~s The reactor building crane and 125-ton hoist are required to be operabic for handling of the spent fuel in the reactor building. The controls for the 125-ton hoist are located in the crane cab. The 5-ton has be:n
~
cab and pendant controls.
A visual inspection of the load-bearing hoist wire rope assures de:ec-tion of signs of distress or wear so that corrections can be promptly made if needed.
The testing of the various limits and interlocks assures their proper operation when the crane is used.
3.10.E/4.10.E Spent Fuel Cask The spent fuc1 cask design incorporates removable lif ting trunnion 3.
The visual inspection of the trunnions and fasteners prior to at tach-ment to the cask assures that no visual damage has occurred during prior handling. The trunnions must be properly attached to the casi.
for lif ting of the cask and the visual inspection assures correc:
installation.
'^'8 347 312
6.0 ADMINISTRATIVE CONTROLS C.
Drille on actions to be taken under emergency conditione involving release of r idioactivity are epecified in the radiological emergenc e plan and sha)1 be conducted annually.
Annual drillo shall also be conducted c,n t!e actions to be taken following failures or safety related systems or Somponents.
D.
Radiation Control Procedures Radiation Control Procedures shall be maintained as.d made available to all neation personnel.
T hie s.r procedureo shall show pe rmi s si ble radia tion exporuze and shall be consistent with the requi re men t re of 10 CFP 20.
This radiation protection program shall ha organized to meet the requi rements of 10 CFR 20 except in lieu of th e
" con trol device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
1.
Each High Radiation Area in which the intensity of radiation is greater than 100 mrem /hr but less than 1,000 mrem /hr shall be barricaded and conspicuouuly pooted as a High Radiation Area, and entrance thereto shall be controlled by issuance of a special work permit.
Any individual or group of individuale permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose while in l
the area.
2.
Each High Radiation Area in which the intensity of radi a tion is greater than 1,0 00 nre m/hr sh all be s ub j ect to the provisions of (a) a bov e ; and, An addition, locked doors shall be provided to prevent unauthorized entry into euch areas, and the key i shall be maintained under administrative control of the shif t engineer on duty.
i^'8 348 339 Amendment No.
48 s
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48 340
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'^'8 350 Amendment No. 48 341
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y) s n
,n a
I Amendment No. 48 342
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'^'8 352 Amendment No. 48
~
343
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'8 353 Amendment No. 48 344
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^^8 354 Amendment No. 48 345
6.0 AD*.It3ISTRATIVE cot:iRCLS 9
s UUH UH U Hl L
6.4 Actions to be Taken in the Event of a_P ecort able occurrence
(
in Plant Cueration (Ref. Section 6.7)
A.
Any reportable occurrence shall be promptly reported to the Chief, Nuclea r Generation Iranch and shall be promptly reviewed by PORC.
This cermittee shall prepare
~~
a separate report for eacn repcrtatie cecurrence.
This report shall include an evaluation of the cause of the occurr ence and recommenda tions f or appropriate action to prevent or reduce the probability of a repetition of the Occurrence.
B.
Copies of all such reports shall be sutnitted to the Chief, Nuclear Generaticn Branch, the Manager of Power, the Civision of Power Resource Planning, and the Chairman of the NSRB for their review.
C.
The plant superintendent shall notify the NRC as specified in Specification 6.7 of the circumstances of any reportable occurrence.
6.5 Action to be Taken ir the Event a Sa f et v Lir.it is Txceeded If a safety limit is exceeded, tne reactor chall be shut down and reactor operation shall not be resumed until authorized by the NRC.
A prcmpt report I Sall te mcde to the Chief,
Nuclear Generation Branch and the Chairman of the NSR3 A
complete analysis of the circumstances leading up to and resulting from the situation, together with recommendations
~
to prevent a recurrence, shall be prepared by the PORC.
This report shall te submitted to the Chief, Nuclear Generation Branch, the Manager of Power, the Division of Power Resource Planning, and the NSRS.
Notificaticn of such occurr ences will be made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.6 Station Coeratino Pecords A.
Records and/or 7 ogs shall be kept in a manner convenient for review as indicated below:
1.
All normal plant operstion including such items as power level, fuel exposure, and shutdowns 2.
'rincipal maintenance activities 3.
Reportable Occurrences 346 8
355
p"' "4%g j
y, o,
UNITED STATES y
' 'g NUCLEAR REGULATORY COMMISSION
',- r WASHINGTON, D. C. 20555 t
e*
n s,e*
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLrf,R PLANT, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated July 20, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comnission'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 Conmission; 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 Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-68 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 25, are hereby incorporated in the license. The licensee shall operate the 'acility in accordance with the Technical Specifications.
'^'8 356
_2_
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
Thomas
.Jfppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: Octaber 11, 1979
'^'8 357
ATTACHMENT TO LICENSE AMENDMENT N0. 25 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:
334 370 336 371 337*
372 342 373 343' 374 369 375 Marginal lines indicate revised area.
- There are no marginal lines on pages 337 and 343.
The change on page 337 is to move, verbatim, paragraph 3.10.B.2 from tiie bottom of page 336 to the top of page 337.
The change on page 343 is to move two references, verbatim, from the bottom of page 342 to the tcp of page 343.
'"^8 358
/
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
+
1.10 COR E ALTERATIONS 4.10 CORE ALTERATIONS b.
A suificient number of control rods shall be operable so that the core can be made suberitical with the strongest operable control rod fully withdrawn and all other operable control rods fully inserted, or all directional control valves for remaining control rods shall be disarmed electrically and sufficient margin to criticality shall be demonstrated.
c.
If maintenance is to be performed on two control rod drives they must be separated by more than two control cells in any direction.
d.
An appropriate number of SRM's are available as defined in specification 3.10.B.
33.
'^'8 359 Amendment No. 25
LINfilWP. COMnt TInal% FCs OFREATIon SUWYtlLUJICE RtQUlttMENTS
~
900R DR8MR I.10 CuRI: Al.TI.KATIONS 4.10 CORE ALTERATIONS n.
Core Monitoring 3.
Care Menitoring r
1.
During core alterations, except Frier to making any alteratione to the core the 51J4's shall be au i n 3.181. 8. 2, two Slot'n uhall fusstionally tested and checked he oper.ible, in or adjacent to any for neutron response. Here-sinailrant where fuct or control af tes, while regrad to be rs=ls are heing moved. For an SRM gerable, the m a will be to be runsidered operabic, the a
ed hily for respose except followinr min 11 he matisfied:
as specified in 3.10.B.1.b.2.
a.
The SRf t shall be inserted to t he norm.:1 operaeing level.
(Use of specini movestale, ikinking type detectors during initial fuct loading and m.ilor core alterattons in place of norru t detec tors in per-miswihle nw long as the detector in connrcted to' the normal SRM rircuit.)
b.1 The SR!! shall ha. c a mininian of I cps with all rods fully
- inserted in the core, if one on more fuel assemblics are in t he core, or b.2 During a full core reload where both irradiated and fresh fuel is being loaded, SRM's (FLC's) may have a count rate of <3 cps provided that the SRM's are
,,,8 360 response checked at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with a neutron source uniti >3 cps can be maintained, and provided also that the core is loaded in a spiral sequence only.
330 Amendment No. 25
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LIMITINC CONDITIONS FOR OPERATION SURVEILIANCE REQUIREMENTS 2. During a complete core removal, the TEM's shall have an initial minimum count ra t e ef 3 eps prior to fuel removal, with all rods fully inserted and rendered electrically inoperable. The count rate will diminish during fuel removal. In.fiviitua l control D rods outside the periphery of l 'I the then existing Ibel matrix may be electrically anned and moved for maintenance after all fuct in the cell containing (enrtrolled byl that control rod have been removed f rom the reactor core. 3.10.C Spent Fuel Pool Vater 4.10.C Spent Puel Pool Water 1. Whenever irradiated fuel is 1. Whenever irradiated f uel is stored in *he spent fuel stored in the spent fuel pool, pool, the pool water level the water level and temperature shall be maintained at a shall be recorded daily depth of 8 1/2 feet or greater above the top of the spent fuel. A minimu= of 6-1/2 feet of water shall be maintained over single irradiated fuel assemblies during transfer and handling operations. 2. Whenever irradiated ' fuel is 2. A sample of fuel pool water in the fuel pool, the pool shall be ar.alyzed in acecrdance vat,r te=perature shall be v1th the follovir.g specifications : 0 1 150 7. a. At least daily for conductivit. 3. Fuel pool water shall be and chloride ion cer. tent. maintained within the following licits: b. At least or.ce per 3 hcurs for conductivity snJ cnloride conductivity 3,10 u=hos/cm concent when the fuel pool 025'c cleanup systec is ir.cperable. chlorides f,0.5 ppm 19 001 337 Amendment No. 25
o 300R ORGINAL prova.len pr 1 mar y aesetkvity control tua the tin't.sionemblien in e tm cell anuin:ta tnel with that control. rod. Tinen, r.mv,e l o t sn entire cell (f uel assemblies plus control newl) r :iu to n in a lower reactivity potential of the core. The re.tuirements for SRM operability during these core alterations assure sufficient core monitoring. R EF E.R ENC ES 1. Refueling interlocks (BFNP FSAR Subsection 7.6) B. Core Monitoring The SDH's are provided to monitor the core during periods of station shutdown and to guide the operator dur'ing refueling operations and station startup. R equiring two operable SRM's in or adjacent to any core quadrant where fuel or control rodu are being moved assures adequate monitoring of that epiad r an t ductnq such a ltera tions. The requirement of 3 count s per second provides assurance that neutr on flux is beinq monitored and insures that startup is conducted only if the source range flux level is above the minimum assumed in the control rod drop accident. During a full core reload SRM/FLC (Fuel Loading Chamber) operability will be verified using a portable external source at least once every 8 hours until sufficient fuel has been loaded to maintain 3 eps. A large number of fuel assemblies will not be required to maintain 3 cps. This increased surveillance rate assures proper detector operability until that time. l'nder the special condition of removing the full core with all contrul rnds inserted and electrically disarmed, it is permissible to allow SR's ceent rate to decrease below 3 cps. All fuc1 moves durinC core unloadinr, will reduce reactivity. It is expected that the SRf t's will drop below 3 cps before all of the fuel is unloaded. Since there will be no reactivity additions durinr. this pericd. the low number of ccunts will not present a hazard. Uhen all of the fuel has been recoved to the spent fuel stcrage pool. SR'I's will no lonr,cr be required. Requiring the 5".'I's to be functionally tested prior to fuct reneval assures that the 5".'t's vill be operable at the start of fuel renoval. The daily response check of the SR:l's ensures their centinued operability until the count rate dix.inishes due to fuel rcmoval. Contrcl rods in cclls from which all fuel has been imo"ed ma; be art:ed electrically and coted for maintenance purp:ses d o r i n a. full core reroval, provided all rods that control fuel are fully inserted and electrically disarmed. 1^'9 002 342 Amendnent No. 25
. - - P00 O l l I j L, REFER ENgES 1. Neutron Monitoring System (BFNP FSAR Subsection 7. 5) 2.
- Morgan, W.
n., aln-Core Neutron Monitoring System for i;ene r a l Electsac Boiling Water Reactors," General Electric Company, Atomic Power Equipment Department, November 1968, revised April 1969 (APED-5706) C. S pa n t ruel Pool Water The elestqn of the spant fuel storage pool pr ovi les a storage location for approximately 140 percent of the full core load est fuel assembltes in the reactor building which ensures a le.pa -s t. e sh a elet tny, c'Joling, and rt* activity control of t ra adiateel f uel. An analysin taas been perf ormed which that a water level at shows or in excess of eight and one-half f eet uvar tne top of the stored annemblies will provide shielding cuch that the maximum calculated radiological doses do not exceed the limits of 10 CFR 20. The normal watar level providen 14-1/2 feet of additional water shielding. The c.spacity of t he skimmer surge tanks is available to maintain the water level at its normal height for three days an the ~ abnence of ailds t ional wa ter . All penetrations of the fuel pool have been installedinput from tanks. at much a height that ponnibl** drain-eye route thattheir oresence does not provide a level more than one-half foot.could lower the normal water w,a t er t am pe ra t u r e l es s thanThe f uel pool cooling system is designed ool 125'r during normal heat 11 the contains two previous discharge batches, reactor core is completely un
- loads, the temperatures may increase to 9: eater than 125'T.
The RHR system supplemental maintain the pooltuel pool cooling mode will be used under these condition temperature to less than 1258F. s to ^"9 003 343 Amendment No. 25
i G 300R ORGINAL 6.0 ADMINISTRATIVE CONTROLS c. Drills on actions to be taken under emergency conditions involving release of radioactivity are specified in the radiological emergency plan and shall be conducted annu ally. Annual drills shall also be conducted on the actions to be taken following failures of safety related systems or components. D. Radiation Control Procedures Radiation Control Procedures shall be maintained and su.de available to all station pera.onnel. These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CTR 20. This radiation protection program shall be organized to meet the requirements of 10 CFR 20 except in lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CPR 20: 1. Each High Radiation Area in which the intensity cf radiation is greater than 100 mrem /hr but less ti.an 1,000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area, and entrance thereto shall be controlled by issuance of a special work permit. Any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dosc while in l the area. 2. Each High Radiation Area in which the intensity of radiation is greater than 1,000 mren/hr shall be subject to the provisions of (a) above; and, in addition, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under administrative control of the shif t engineer on duty. 1~ 9 004 3" Amendment No. 25
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