HL-1685, Proposed Tech Specs Re Spent Fuel Pool Water Depth Above Irradiated Fuel & post-LOCA Radiation Monitor Calibr Frequency
| ML20079C026 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/13/1991 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20079C025 | List: |
| References | |
| HL-1685, NUDOCS 9106180301 | |
| Download: ML20079C026 (17) | |
Text
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i ENCLOSUP.E 3 PLANT HATCH UNITS 1 AND 2 NRC DOCKETS 50 321 AND 50 366 REQUEST TO REVISE TECHNICAL SPECIFICATIONS SPENT FUEL POOL WATER DEPTH AB0VE 1RRADIATED FUEL, CORRECTION OF ADMINISTRATIVE ERRORS, AND POST-LOCA RADIATION MONITOR CAllBRATION FRflQEE1 PAGE CHANGE INSTRUCTIONS Unit 1 Removed P_L4G Inserted Panes 3.2-23 3.2-23 3.2-48 3.2-48 3.10 2 3.10 2 3.10 7 3.10 7 Unit 2 3/4 3-13 3/4 3-13 3/4 8 23 3/4 8 23 3/4 9-15 3/4 9-15 B 3/4 9-2 B 3/4 9 2 HL-1685 002358 E3 1 9106180301 910613 h,DR ADOCl: 05000321 PDR
i -
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- t I NOTES FOR TABLE 3.2-11 p ,
-4 r tt :
.I
, s. The column entrtled *Ref. No." se ordy for ca.....-..e so that e one-to-one teleteneshup can be ;
I established batween items in Table 3.2-11 and items in Table 4.2-11. -
i 6
- b. Lsrrating Condit.ons for Operation for the Neutron Morstonng System are insted in Table 3.2-7.
~
I
- c. With one or more of the moratonng chennels enoperrtde, eithe* restore the enoperable channel (s)
' to OPER ABLE status wittun 30 days or be in at least HOT SHUTDOWN wittwn the twat 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t i
1 i Cont.nued operetson is pomussable for seven days from and after the date that one of these parameters is l'
twt irabested in the control room. SurvesRenee of local penois wdl be substztuted for indecetion in the 4 control room during the seven days.
i d. Drywell and Suppreswon Chamber Pressure are each recorded on the same recorders. Each output chonnel hos j its own recorder j 1
i Drywes and Suppreswon Chamber we terversture end s sppreswan chamber water terriperature are en recorded j en the same recorders. Each output channel has its own recorder. Each recorder takes input from several j temperature efements.
1 Hydrogen and Ouygen are andecated on one recorder. The receeder hee two pene, one pen for each parameter.
1 i 7 Each channet of the post LOCA redietion morntonng systwnincJudes two detectors; one located m the !
y drywell end the other ire the suppression chamber. Each detector feeds e segnal to e seperste log count f
rete eneter. The eneter output goes to e two pen recorder. One high redsetson levet eierm as provided per i j channel and annunciation of sierm is prtmded in the control room.
n Weh Range Dryw.3 Pressure e wi Hgn Range Drywet Redserion are recorded on the same recorders. Each j
+
T n
output chennel has its own recorder.
[
s t
}' r+ e. In the event that eG stufoce%=e of Jus parameter is dsabled and such L-hm co wsot be restored in '
$ seu (6) hours, en orderly shutdoorn sheB be erstieved and the reector sheE t e in e Hot Shutdown condeDon t
{ in siv 461 hours0.00534 days <br />0.128 hours <br />7.622354e-4 weeks <br />1.754105e-4 months <br /> and a Cold ShuMown condetson in the foRowing eWeen (18) hours.
j h
- f. If eether the pomery or secondary indecetwyn is enoperable, the torus temperature well be trie stored at
- _ i.est once per stuft to observe any une=pewned temperature increase whech might be andcative of en operi m SRV. Weth both the primary end seconde y moratori,g channels of two or more SRVs inoperable either
) Y restore suff.cient inoperable channels such that no more then one SRV has both pnmery and seco wiery y
channels enoperable wittun 7 days or be in et least hot shutdown witten the nest 12 ' sours.
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, h Check and Celebreben IWLiemum Freesency for instrumerwesen w,.ch wes Sur.o.r_ inform.en C
I Z e
] Ref. Instrumerw Instrument Check Instrumert Caldwetsen ido. Mewensm Frequency IWirrumum Frewmey
~
(et M (d 1 Reector Vessel Water Level Each shft Once.W cycle m i
2 Shroud Water Level Each shft oncewee g cycle m j 3 Reactor Pressure E :h st=ft 0 we/opare >rg eyese m i
f 4 Drywell Pressure Each shtt Every 6 months S Dryweil Temperature Each shft Every 6 monthe i
f 6 Suppression Chamber Aer Each stoft E.ery6t h Temperature 7 7 Suppresseon Chamber Water Each stwft Ewry 6 months g T - .ture
- 8 Suppression Chamber Water Each st=ft Every 6 moethe Level
- 7..
l T 9 Suppressson Chamber Each st=ft Every 6 moaths V, Pressues c+
l $
7 10 Rod Position Informaten Each stutt N!A f System (RPts)
] t
$ 11 W and Oxygen Monttdy Every 3 monthe C Analyter 7
Y ru 12 Post LOCA P.edsetson Each shtt Every la morttwo o=
m V
s o
- 13 % Sefety/Rehef Vefve Poetson Pre- Montidy Every 18 months 5 mery Ind.cator y bl Safety /Rebet Velve Poort on Monttdy Every 18 months
- Secondary Indecator tu Jt>
1211hfLWid11Ws iM OPLM11M __ .CWrit@OWWL ~ ~ .
l 3.10.C. (ore h>nitorina Nrirri (g_rg < atM f ,@.,y ? f drt(g3 )
811tfallpn1 MatWL t
- 1. riuring nomal core alterations, two t.a ' v.9 rmal alterattms MNs shall te 0;erable; one in the to tie core tie 9it shall te ,
core quadrant where fuel or contrvi ftartionally tested ard dockd for '
rtds are teing noved ard one in an routnri regonse. Themafter, adjacent Quadrant, except as specified tile nmind to te gerable, tie in 2 and 3 telow. 9h will te dubd daily for regonse.
For an SIN to te considered operable, it shall te inserted to the nomal LA.e 01 gocial trovable, d<ralen operatirig level and shall have a tyle detectors djrtrg inittet fuel minian of 3 cps with all rods capable lonfirg ard mjor core alteratims of nomal insertion fully inserted. in plate of rmul detectors is pemtssible as lcag as tre detKtor
- 2. Prior to spiral unloading the SINS is ctrrecttd to tre rmal SN shall te proven operable as stated cirwit. ;
atove, however, during spiral unloading the count rete may drop Prior to spiral miondirq or telow 3 cps. reloading tie 9Hs shall te fmctionally testai. Prior to
- 3. Prior to spiral reload, up to four (4) spiral mloadirg tte 98 struld fuel assatiles will te loaded into also te dockn1 for trutrm core positions next to respanse, each of the 4 SFNs to obtain the required 3 cps. These assemblies may te any which have been shown to meet the criteria for storage in the spent fuel pool. Until these assortlies have teen loaded, the 3 cps requirm ent is not necessary.
D. Scent Fuel Fool Wattr level D. &nt Fml fiel Water level At least 21 feet of water shall te main- Tte water level in tie gmt fuel tained over the top of irradiated roul shall te &temined to te at i fuel assertlies seated in the spent least its minimo rtwind doth fuel storage racks, at least.orre per 7 days.
[. Control Rod Drive Maintennt [. (mtml Rcd Drive H11ntmarre
- 1. Recuirmvints for Withdrawal _ l. @mjnnnts for Withdragl of 1 or 2 Contrt>l Fkds of I or 2 Cmtml Fkds A maximin of two control rods separated by at least two control i calls in all directions may te withdrawn or reoved frta the core for tie purpose of perfoming control rod i drive maintenance provided that:
- a. Tte Rde Switch is lockd in tie a. This surveillance nminsmt is IEFul rositim. Ite refuelirg tre sare as given in 4.10.A.
interlock Midi prevents core than tre control rtd frin teirg wittdrac tr.y te bypassed for are of the caomi rtds cn sich neintmance is trirg MTCH - UNIT 1 3.10-2 K:\wp\techsp\h\3-10Ul. pro \l61151
I I
Ba$ls FOR LIM 111NG (pgl110Ns IOR 011pe[Q4 l l
3.10.A.2. Fuel Ort..ple H.pist toad Sg.itina Interlo dt !
Fuel haniling is normally conducted with the fuel grapp'e hoist. The total load on '
this hols' when the interlock is required consists of the weight of the fuel grapple and the fuel assembly. This total is approximnely 1500 lbs. in comparison ,
to the load setting of 485 1 30 lbs.
l
- 3. Auxiliarv Hoi.ts load Settina Interlock Provisions ha.e also been made to allow fuel handling with either of the three auxiliary holsts and still maintain the refueling interlocks. The 485 1 30 lb load ,
setting of these hoists is adequate to trip the interlock when a fuel bundle is !
being handled. j B. Fuel loadina To minimize the possibility of leading fuel into a cell containing no control md.
It is required that all control rods ars (Lily inserted when fuel is being loaded into the reactor core. This requirement assures that during refueling the refueitng interlocks, at designed, will prevent inadvertent criticality. ;
C. Core Monttgrina Durino Core Alterations i i
The SRMs are provided to monitor the core during periods of Unit shutdown and to I guide the operator during refueling operations and Unit startup. Requiring two !
operable SRMs in or adjacent to any cote quadrant where fuel or control rods are ;
being moved assures adequate monitoring of that quadrant during suCh alterations. i L The requirements of 3 counts per second provides assurance that neutron flux is ;
being monitored. I During spirci unloading, it is not necessary to maintain 3 cps because core alterations will involve only react"vity removal and will not result in criticality.
The loading of up to four fuel bundles around the SRMs before attaining the 3 cps :
is permissible because these bundles form a subcritical configuration. ,
D. Seent Fuel Pool 4ter level i
The minimum water level in the spent fuel pool shall be maintained at least 21 feet above the top of the upper tio plates of the irradiated fuel assemblies seated in the spent fuel pool racks. This minimum level ensures removal of at Isast 98.6%
of the assumed 10% todtne gap activity released from the rupture of an irradiated fuel assembly. This water depth is consistent with the atsumptions for the fuel handling accident analysis outlined in Regulatory Guide 1.25 and the requirements ;
in Standard Review Plan 15.7,4 for radiological releases resulting from that accident, s E. Control Rod Drive Maintenancg During certain periods, it is desirable to perform maintenance on two control rod ;
drives at the same time. !
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j HATCH - UNIT 1 3.10 7 K:\wp\techsp\h\3-10VI. pro \l61-l$1 p, ---r+-*--,=,~,r-mvwyww,-wv y v m '%-w w,-- y -- w,+n+++---r- '
f 4
-4 TABLE 3.3 2-1 (Cenem-11 m
- - ISOLATION ACTUAT ON INSTRUS.qNTATION l
8 E * ' - VALVE GRO r ASNW!UM NUMBER APPLICABLE
! Q OPERATED BY OPER ABLE CNANNELS OPERATIONAL TRP FUNCTKW SIGNAL lst PE8% TRtP SYSTEV'Nid CONDITION ACTION
! 4. PtGH PRESSURE cot.Pt. ANT TNJECT*0N SYSTEM iSOLAT10N i
j e. HPO Steam Lane Flow - Mgh 3 1 1. 2. 3 26
! (2E41-N657 A.8) i
- b. HPCI Steam Supply Pressure -
l Low (2E41-N658 A.B.C.D1 3. a 2 1. 2. 3 26 1
{ d. HPCI Pepe Per:ettation Room (JD Temperature - Mgh (2E41-N671 A. B) 3 1 1.2.3 26 j w e. Suppresson Pool Area Ambeert
' s Temperature - Mgh (2E51-N666 C. DI 3 1 1.2.3 26 w
f l f. Suppresson Pool Aree l W Temp - Mgh (2E51-N665 C. D: 3 1 1.2.3 23
{ IO 2E51-N663 C. D; j 2E51-N664 C. D1
, x
! $ g. Suppresson Poot Area Temperature y Timer Reteys (2E51-M603 A. ED 3 1 1.2.3 2S
- h. Emergency Aree Cooler Temperature-4 y'* Mgh (2E41-N670 A. El 3 1 1.2.3 26 1
g" i. Drywe9 Pressurmgh
'b (2E11-N634 C. D) a
- 1 1.2.3 26 o
'o j. Logic Power Moretor (2E41-K1) N A** 1 1.2.3 27 I /
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LAft E 3.8.LEl (Cont inutdl P R I M A R LC 0t{IMlitdUfLEUillR!LT_10!L(OfiDM(10 B OK!GMf4T PR01[CT11LJ1YlLLS DEVICE NUMBER SYSTEM / COMP 0f1ENT At4D l qc M 1pjf* POWfRID 13, 600 VAC, MCB, M0 DRYWELL RETURt1 AIR FAf1 2R24-50ll, fR 18C 2T47-C001A
- 14. 600 VAC, MCB, M0 DRYWELL C00Llt4G Utili 2R24-5013, FR 3B 2T47-B010A
- 15. 600 VAC, MCB, M0 DRYWEll COOLING Utill 2R24-5014, IR 8A 2147-B010B
- g. Type 7:
- 2. 208 VAC, MCB, M0 DRYWELL RETURN AIR FAN 2R24-S012, FR 23C 2T47-C002B
- 3. 208 VAC, MCB, M0 DRYWELL RElVRN AIR FAtt 2R24-50ll, FR 22C 2T47-C002A
- MCB - molded case circuit breaker MO - magnetic only TM - thermal magnetic HATCH - UNIT 2 3/4 8-23 K:\wp\techsp\h\3_4-802. pro \l61-109
REFUEllf4G OPERATIONS 3/4.9.10 WATER LEVEL - SPENT FUEL ST@ age 01 LIMITill(Li@DITION FOR OPERATION 3.9.10 At least 21 feet of water shall be maintained over the top of l f irradiated fuel assemblies seated in the spent fuel storage pool racks.
APPLICABillTY: Whenever irradiated fuel assemblies are in the spent fuel storage pool. l ACTION:
With the requirements of the above specification not satisfied, suspend l all movement of fuel assemblies and crane operations with loads in the i spent fuel storage pool area after placing the load in a safe condition. t The provisions of Specification 3.0.3 are not applicable, SURVElllANCE RE0VIREMENTS ,
4.9.10 The water level in the spent fuel storage pool shall be determined to be at least its minimum required depth at least once per 7 day i r
2 HATCH - UNIT 2 3/4 9-15 K:\wp\techsp\h\3_4-9V2. pro \l61-0 1
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BLLy(LIM OrfRA110N5 '
EAllS I
3/4.9.6 Mt(LCA110NS 5 The requirement for communications capability ensures that refueling i station personnel can be promptly informed of significant changes in the '
f acility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
314.9.7 (RANI AND HDIST OP M L1H 1he OptRABill1Y requirements of the cranes and hoists used for movement of fuel assemblies ensures that: (1) tach has sufficient load capacity to
- lift a fue) element and (2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
314.9.1._ DANE TRAv[L-Sp[f(T f t[L STORACE POOL The restriction on movement of loads in excess of the nominal weight of a fuel element over irradiated fuel assemblies ensures that no enore than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity ,
release assumed in the accident analyses. All fuel leaded into the (dwin 1. t Hatch Nuclear Plant spent fuel pool shall have an uncontrolled lattice b less than or equal to the limit for high density fuel racks described in the
- General Electric Standard Application for Reactor Fuel" (GISTAR 11), '
Nt0E-240ll P A-8. Alternatively, fuel not described in GESTAR !! shall have !
been analyred with another NRC approved methodology to ensure conformity to the FSAR design basis for fuel in the spent fuel racks. L 3/4.9.9 WAT[R tt/[L ptAC10R Vfl 1[L i
The restrictions on minimum water level ensure that sufficient water ,
depth is available to remove 99% of the assumed 10% todine gap activity !
released from the rupture of an irradiated fuel assembly, this ethtmum water depth is consistent with the assumptions of the accident analysis. 1 3/4.9.10 WATER LEVfL-SPINT FUfL STORACE POOL The minimum water level in the spent fuel pool shall be maintained at least 21 feet above the top of the upper tie plates of the trradiated fuel h assemblies seated in the spent fuel pool racks. This minimum level ensures removal of at least 98.6% of the assumed 10% iodine gap activity released from :
the rupture of an irradiated fuel assembly. This water depth is consistent i with the assurptions for the fuel handling accident analysis outlined in Regulatory Guide 1.25 and the requirements in Standard Review Plan 15.7.4 for ,
,,, radiological releases resulting from that accident. !
3/4.9.11 C(1NTROL ROD R[MOVAL This specif tention ensures that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous i removal of more than one control red are more stringent since the $HUTDOWN !
MARGIN specification provides for the core to remain subcritical with only i one control rod fully withdrawn, HATCH - UNIT 2 B 3/4 9-2 K \wp\techspth\ Bas 3,4A.pr0\l61-66 i
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~ m .eao w a v arooo w r m . o m - -- . _ _ .
3.10.C. Lgft_s nitorino Durina fore 4.10.C. Core Monitorina 0urina Con 1
.. Alterations hiterations During normal core alterations, two l toPrior to making acrN) alterations l
- 1. )
5RMs shall be operable; one in the the core the SRMs shall be core quadrant where fuel or control f unctionally tested and thethed f or rods are being moved and one in an neutron response. Thereafter, adjacent quadrant, encept as specified while reovired to be operable, the in 2 and 3 below. 5tMs will be checked daily f or response. '
For an $RM to be considered operable. ; g it sha11 be inserted to the norw.41 Use of special movable, dunkiesg F operating leve? .nd th411 have a type detectors during initial fuel minimum of 3 cp. with all rods capable loading and major core alterations of normal insertion f ully inserted. in place of normal detectors is pernissible as long as the detector
- 2. Prior to spiral unloading the 5RMs l 15 tonnected to the norw41 $RM ,
shall be proven operable as stated circuit. )
above, however, during spiral unloading the count rate Ny drop Prior to spiral unloading or below 3 cps. reloading the $RMs shall be l functionally tested. Prior to
- 3. Prior to spiral reload, up to f our (4) spiral unloading the SRMs should l fuel assemblies will be loaded into also be checked for neutron core positions next to response, each of the 4 5tMs to obtain the required 3 cps. These assemblies may be any which have been shown to meet the criteria for storage in the spent fuel pool. Until these /- ~^ %
assemblies have been loaded, the 3 cps TNfERT $
requirement is not necessary.
D. Seent Fuel Pool Water tevel 0. Seent Fuel Pool Water Level yg gg,py Whineva (irradiated fuel is store d n ver_ irradiated fuel i_Sator'e'd the spent TutQool. Jt e.4061 water in the speht4sti pogir-the water level shall be,r.Aetigd and recorded'
> level shall be uhtnined at or above f e'thetop'6Mhtgtive daily /
[. Control Rod Drive Maintenance [. Control Rod Drive Maintenance
- 1. Pecuirements for Withdrawal 1. k avirements for Withdreq.1 o J ) or 2 Control Gods pd 1 or ? Control Rods A maimum of two control rods separated by at least two control 3 tells in all directions may be withdrawn or removed f rom the core f or the purpose of perforning control rod drive maintenance provided that:
- 4. The Mode Switch is locked in the This surveillance requirement REFUEL position. The refueling a. y interlock which prevents more than the same as given in 4.10. A.
one control red f rom being withdrawn
' Ny be bypassed f or one of the -
control rods on which maintenance is being HAICH - UNIT 1 3.10-2 Amen 0 ment No. 66. 102. 151 i
l
-*~
B ATT5 5 0R L1lTlwG CohDIT10N5 F OR 081e A110N 3.10,A.2. Fuel Gracole Heist lead Settino Interlocks f uel handling is normally conducted with the f uel grapple hoist. The total load on this hoist when the interlock is required consists of the Weight of the fuel
( grapple and the fuel assembly. This total is approximately 1600 lbs. in comparison to the load setting of 486 1 30 lbs.
. 3. Auxiliary Heists lead Settino Interlock Provisions have also been made to allow fuel handling with eithe of the three
('
auniliary hoists and still maintain the refueling interlocks. The 405130 lb load setting of these hoists is adequate to trip the interlock when a fuel bundle is being handled.
- 8. Fuel loading
/ 10 minimite the possibility of loading fuel into a cell containing no control rod,
( it is required that a1) control rods are fully inserted when fuel is being loaced into the reactor core. This recuirement assures that during refueling the refueling interlocks. 45 designed, will prevent inadvertent criticality.
C. Core Monitorine Durino Core Alterations The $RMS are provided to monitor the core during periods of Unit shutdown and to l guide the operator during ref ueling operations and Unit startup. Requiring two operable SRMs in or adjacent to any core cuadrant where fuel or control rocs are l being moved assures adequate monitoring of that quadrant during such alteratior.s.
1he requiren.ents of 3 counts per second provides assurance that neutron flux is '
bein; monitored.
During spiral unloading, it is not necessary to maintain 3 col because core alterations will involve only reactivity removal and will not result in criticality.
The loading of up to four fuel bundles around the SRMs before attaining the 3 cps is permissible because these bundles foria a subtritical configuration.
D. Seent Fuel Pool Water Level
'th Q esign of the spent fuel storage pool provides a storage location for 3181 ffT assembitas in the reacter building which ensures adequate shielding, cool , and i the reactDrity_ control of irradiated fuel. An analysis has been perover ed which the top of shows that a watettlevel at or in excess of eight and one-half the active fuel will )r# vide shielding such that the maximpa alculated i
W E PJT- C, radiological doses do noharqeed the limits of 10 CFR 9. The normal water level l
f provides 14-1/2 feet of addit 1 1 water shieldi . All penetrations of the fuel pool have been installed at such a ight t)At heir presence does not provide a possible drainage route that could low Sttie water level to less than 10 feet above 1 the top of the active fuel. Line endi , Qow this level are equipped with two check valves in series to p Jr inadve'ient pooltainage. All fuel loaded into the [dwin 1. Hatch Nuclear' Plant spent f uel pool shall' ige a, n uncontrolled lattice described in the K less
' General than ElejrYStandard e
NF0E-240)1 4 A-8.
or egyWto Application forthe Alternatively, limit Reactor fuel not described Fuel'for(6tSThigh-density fue in GE51 AR !! sha
' analyaen with another NRC-approved methodology to ensure confornity to the fLAR
,6e5Tgn basis for fuel in the spent fuel racks. N
[. Control Rod Drive Maintenance Ouring certain periods, it is desirable to perform maintenance on two control rod drives at the same time.
l 3.10-1 Amendment 'No. 7 6 706 yn , 151 HATCH - UNIT 1 4
1 l- .. -- - -- ,,- - - --,._- ,-- - _ - - - , - . ~ - - - ---_ . . _ - _ _ . -- -.-- --_ _
i 1 d
Instt 3.3.2-1 iCantimmed) 150LAU9pt ACTM11tNI IttSTWlPEHIAI.1DN S VALVE GROUPS tel418ept 91UpWett APPtICA3tf
' OPERAftD Bf OrtRA8tt Clwestt5 OPERATIONAL Ptn TRIP SI11LMhlir,1 .igeg111gst gligg
_ 51rAALial-g IRIP flMCIJON M 4 ti1Gi Perttaalt C00UutT 19tJECTIGIt 5Y$((M 150LA110M 3 1 1. 2. 3 26
- a. MPCI Steam Llae Fle= - High (2E41 seb57 A.8)
MPCI Steam Supply Pressere -
6.
3, 8 2 1. 2. 3 26 Low (2t41-8e658 A.B.C.0)
MPCI Turbine Enhaust Diaphrop c.
Pressere - Migh (2E4I-seb55 A.B.C.D) 3 2 1. 2. 3 26 MPCI Pipe Penetration Room d.
Temperature - High (2E41-8e671 A. 8) 3 I I. 2. 3 26 R e. Suppression Peel Area Ambient 3. 2. 3 26 iceperatwee-Migh (2151-seb66 C. D) 3 I a _
Y C f. 5 PPression Peel Area w Temp.-High (ZE51-88665 C. D; 3 1 1. 2. 3 26 2E51-se663 C. 0; 2t58-88664 C. D)
Suppression Peel Area Temperature g.
Timer selays (2151-84603 A. 8) -
YI 3 I. 2. 3 26 Emergency Area Cooler Temperature-h.
High (ZE41-8eb70 A. 8) h I f. 2. 3 26 i i. or,.en P,es,.,e-ni s 1 1. 2. 3 26 g (2til-ab94 C. D)
- t. ,ic Po e eseoiter (2c4i-u n isA~ i s. 2. 3 2r g 3 r
e e
. TABLE 3.8.2.6-1 (Continued) .
PRIMARY CONTAll4HENT PENETRATION CONDUCTOR l OVERCURREN_T PROTECTIVE DEVICIS i I
- l SYSTEM / COMPONENT DEVICE NUMBER l POWERED AND LOCATION'
- 13. 600 VAC, MCB MO ORYWELL RETURN AIR FAN 2R24-50ll, FR 18C 2T47-C001A l
- 14. 600 VAC, MCB, M0 DRYWELL COOLING UNIT 2R24-5013. FR 38 2T47-8010A 15, 600 VAC, MCB, MO ORYWELL COOLING UNIT 2R24-5014, FR 8A 2T47-80108
2A24 ~0 3 FR-00 2i47-00:0A II'
$E2,['3,E!,,)#C$mIU,. k.3.,5N,Eh.h 590'I"O\UNIh sns -v ,in o
- g. Type 7:
- 2. 208 VAC, MCB, M0 ORYWELL RETURN AIR FAN 2R24-5012. FR 23C 2T47-C0028 208 VAC, MCB, MO ORYWELL RETURN AIR FAN
- 3. '
2R24-5011. FR 22C . 2T47-C002A
'MCB - molded case circuit breaker i MO - magnetic only TM - thermal magnetic I
o
{
l 3/4 8-23 Amendment No. #f, 50,109 HATCH - UNIT 2
_ - _ _ . . . _ . . . . . . . ~ . . . _ . . _ _ . _ _ _ _ . _ . _ , _ _ _ _ . . , . _ . . _ _ _ _ . . . _ , . . _ . _ _ , _ . ~ _ _ , _ . _ . , _ _ _ _ - . _ _ . _
i l 1 I
, _, REFUEllNG OPERATION $ .
k-3/4.9.10 WA1ER LEVEL - SPENT FUEL STORACE p00L ..,j.,
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3.9.10 At leastMfeet of water shall be maintained over the top of
' trradiated fuel assemblies seated in the spent fuel storage pool racks.
i APPLICABILITY: Whenever irradiated fuel assemblies are in the spent ;
Tuel storage pool.
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i ACTION: ,
With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the j.
spent fuel storage pool arca after placing the load in a safe condition.
- The provisions of Specification 3.0.3 are not applicable, s
i SURVEILLANCE REQUIREMENT 5
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4.9.10 The water level in the spent fuel storage pool shall be determined 8 to be a least its minimum required depth at least once per 7 days.
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I HATCH - UNIT 2 3/4 9-15 -
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REFUELING OPERATIONS -
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3/4.9.6 COMMUNICATIONS
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The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.
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3/4.9.7 CRANE AND H0!$T OPERABILITY The OPERABILITY requirements of the cranes and hoists used for movement of fuel assemblies ensures that (1) each has sufficient load capacity to lift a fuel element, and (2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE p00L The restriction on movement of loads in excess of the nominal weight of a fuel element over irradiated fuel assemblies ensures that no more I than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity release assumed in the accident analyses. All fuel loaded into the Edwin I.
Hatch Nuclear Plant spent fuel pool shall have an uncontrolled lattice K-less than or equal to the limit for high density fuel racks described in the
" General Electric Standard Application for Reactor Fuel" (GESTAR !!),
NEDE-24011-P-A-8. Alternatively, fuel not described in GESTAR !! shall have been analyzed with another NRC-approved methodology to ensure conformity to the FSAR design basis for fuel in the spent fuel racks.
3/4.9.9 ud4/4-9-ie WATER LEVEL-REACTOR VESSEL AND-WATEbtEVEE-SrPENT-FUEL RO M E POOL-The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. This minimum water depth is g g g j g thej ssumptions of the accident analysis.
Wy. s.w W w w. /- spas n. / s n ., A, / 9 3/4.9.11 CONTROL ROD REMOVAL fu r This specification ensures that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTOOWN )
MARGIN specification provides for the core to remain suberitical with only
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one control rod fully withdrawn.
HATCH - UNIT 2 B 3/4 9-2 . Amendment No. 66 l
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1 INSERT A At least 21 feet of water shall be maintained over the top of irradiated fuel assemblias seated in the spent fuel storage racks.
INSERT B The water level in the spent fuel pool shall be determined to be at least its minimum required depth at least once per 7 days.
INSERT C The minimum water level in the spent fuel pool shall be maintained at least 21 feet above the top of the upper tie plates of the irradiated fuel assemblies seated in the spent fuel pool racks. This minimum level ensures removal of at least 98.6% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. This water depth is consistent with the assumptions for the fuel handling accident analysis outlined in Reg Guide 1.25 and the requirements in Standard Review Plan 15.7.4 for radiological releases resulting from that accident.
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390tt s TOR TAsLI 3.2-18 .
1 D a. The celtssse entitled "Ror. Me." is only for convenience so that a one-te.one reistionship can be y established between Items in Table 3.2-14 sed Itees in Table 4.2-11.
L8eltiner Conditions for operation for t. lie feeutron teonitoring Systes are sisted in Table 3.2-7.
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" ContIsweed operstion is persIssIlele ror seven dsys fruse end artef- the deto thet one of these yerosetors Ismsrwit tence or local po not f ridica ted in t9ee control avow.
contros ecos during the seven days.
Esc 9e output chensees has
- d. DryweII and Dippression Chessber Pressure are escte recorded on the same recorders.
its own recorder.
Drywell and Suppresslose Ctr ..
" sir tesuperature and suppression chenberTsch water temperature recorder are free tateos Enput af f recorded several on the same recorders. E en e output channet has Its own recorder.
tesperetore eieenents.
Yte recorder has two gens, orve pen for each perseoter.
Hydrogen and dh7 Ten are Ind8cated on one recorder.
Each chonnel of the post LOCA radiation suositoringEach system includes detector twoedetectors-raeds signal to eone locatedtoy seperste in coesnt the drywell and the otter in the suppression chssiber.
ra ts sieter. The seter output goes to a two pea recorcer. One higte radiation level alors is provided per channeI and annuncIet8 ass of s:Iaru Is prowIded in tka cocttoi roose.
ifed on the spee recorders. Each l(Igh Range DrywefI 8'ressure and St!gh Range Drywet I Radiation a re ret j output chasenet has Its cwn recorder.
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ro ' O. In the event that al t Indications er this pareester Is disabled and saech f ad8 cation connot be restored in six (6) hoests, en orderf y shutdown shaf t be #nittsted and the reactor shal8 De In s 14ot Shutdowet casedition h, i r,, Ist six (6) hours and e Cold Shutdown conditiese En the followireg o8ghteen (18) hours,
- f. 3 r elthes- the pries ty or seconda ry Indicstlen is t roope rabl e, the terws temperature viIndicative t t be monitored at of en opese least once per shif t to observe any unewyf aiteed tesaperzture Incresse Wich might beInnperable either SRV.
restore With both the primary and schry moseltoriseg channels o' two or more Sevslacpersbte sufriefeat 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
charriels such that no more than one S channels inoperable within 7 days or be in at least hot shutdowre with8n the stemt m
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Owick and Calibration Minleuer Tregenency for Austrumentation E> g Wielch Provides Surveillance Imrorimstlon a y
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e ner. s r.st ruse at Instriment ce" instrtament Ca s tbration Miaf muss Frequency S age, M 3 ni mum F rocNw th) (c) )
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Esch shift Orice/operstIng cycle (r) 1 55eactor Vessel Water Lmvel Esch shift once/sperstfrig cycle (f) f 2 Shroud Water tevet ci Guacefoperat8rsg cycle (f) toch shift g 3 Reactor Pressaare t> Every 6 months as Drywell Pressure Each shift Every 6 seeths !
C, 5 DrywelI Temperstwrw Ja-@ V ? ,
u Every 6 monthe SuppreasIon Cheadmer A8 r iech sh8s.~
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Teenpera ture tech shirt Every 6 ssJetths N 7 Suppresslose Chamber Water y leaupara ture
'~ fach shift Every 6 months w a Suppress 8on Chamber kater 7 - levet et m e tech sh8rt Every 6 suoseths
,' r. 9 Sasppression Chamber
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Rod Positlen Information tsch shift N/A to o,
.,ystee (RPtS) atydrogen and Owysen Bewithly Eve s l S
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Post LOCA Radiation tach shift very f emoths
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a) Safety / nester Vssve Position Pr5- Mosethey Every 13 months t> " <' sary Indicator Every 18 morrths
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' b) Sarety/fietier Valve Position Maesthly o '
Secondary IndIcetor s
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