ML20237C456
| ML20237C456 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/13/1998 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20237C449 | List: |
| References | |
| NUDOCS 9808210186 | |
| Download: ML20237C456 (130) | |
Text
{{#Wiki_filter:,-- l I Docket No. 50-213 J CY-98-003 4 l 1 1 I L 1 l- \ ll j' l Attachment 1 l Haddam Neck Plant l-
- t. Proposed Revision To The Operating License And The Technical Specifications l
1 Marked-Up Pages ; l ' -; ; l .: l I l l . I i> f I l 'r . i }; n 9908210186 9e0013 August 1998 ppR Apocn 05 % j3 W
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I dene 32, 1999 i The licensee may make changes to the fire protection program I without NRC approval if these changes do not reduce the \ effectiveness of fire protection for facilities, systems, and equipnent which could result in a radiological hazard, taking into account the decommissioning plant conditions and l activities. 1 (5) Physical Protection i ii The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical cecurity, guard training and qualification, and safeguards contingency planti including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50. 90 and 10 CFR 50.54 (p) . The plans, which contain Safeguards Information protected under 10 CFR 73.21, are j entitled: "Haddam Neck Plant Physical Security Plan," with { revisions subaitted through January 24, 1989; "Haddam Neck Plant Guard Training and Qualification Plan," with revisions submitted through January 27, 1983; and "Haddam Neck Plant Safeguards Contingency Plan," with revisions submitted through ! Decauber 9, 1983. Changes made in accordance with 10 CFR 73.55 chall be implemented in accordance with the schedule set forth therein. 1
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q (Date :f !+emens: I'd;us f 2 2,, 19 r. G)- ( Fuel Movement ' l The movement of special nuclear matorial used as reactor fuel F'
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p l FOR THE ATOMIC ENERGY COttiISS20N h./gfMO A. Giambusso, Deputy Director for p[a(J bS[ Ronctor Projects
-- ( Df. rectorate of Licensing Original Signed by A. Giambusso
Enclosure:
, Appendices A and B - Technical Specifications Date of Issuance: December 27, 1974
?$0PLIC. DOC L_______________.___________.__
i Insert A This license is effective as of the date ofissuance and authorizes ownership and possession of this facility until the Commission notifies the licensee in writing that the license is terminated. The licensee shall:
- 1. Take actions necessary to decommission and decontaminate this facility and continue to maintain this facility, including, where applicable, the stomge, control and maintenance of the spent fuel, in a safe condition; rnd
- 2. ' Conduct activities in accordance with all other restrictions applicable to this facility in accordance with NRC regulations and the specific provisions of this 10CFR50 facility license.
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T l Q 30, 1998 I INDEX < DEFINITIONS SECTION PAGE 1.0- DEFINITIONS I 1.1 ACTION.................... .................................. 1 1 TEST............................... l (1.2 1.3 1.4 ANALOG CHANNEL OPERATIONAL DELETED CHANNEL CALIBRATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 1 11 l/} 1.5 CHANNEL CHECK................................................. 11 1.6 DELETED l 1.7 DELETED l 1.8 CORE ALTERATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 1.9 DELETED l 1.10 DELETED l 1.11 DELETED l 1.12 FREQUENCY N0TATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 1.13 DELETED l 1.14 DELETED ll 1.15 MEMBER (S) 0F THE PUBLIC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 I*g L1.16 h-17 DELETED OPERABLE J OPERAB I LITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .i fI.18 OPERATI ONAL MODE M0DE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . P3--
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INDEX ADMINISTRATIVE CONTROLS 1 SECTION PAGE i 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS........................... 6 1 6.2.2 FACILITY STAFF............................................. 61 TABLE 6.2 1 MINIMUM SHIFT CREW COMPOSITION............................. 6 3 6.3 FACILITY STAFF QUALIFICATIONS 64 1 i 6.4 TRAINING 6-5 l l 6.5 "I"IEW ^ND JOIT & 6LEGD e r , u.s.. ni n u.r. n, nro.A.r.
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l Jur.; 30. 1000 INDEX l ADMINISTRATIVE CONTROLS SECTION g 6.9 REPORTING REQUIREMENTS ,,,.
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6.9.1 Routine Ronnrte .................................. 6-(DELETED l Annual Reports............................................ 6 13 Annual Radiological Environmental Operating Report........ 6 14 Annual Radioactive Effluent Report. . . . . . . . . . . . . . . . . . . . . . . . 6 15 i DELETED s DELETED L Special Reports........................................... 6-17 { l 6.10 RECORfHtETENfMS. SL57GD 6M l 6.11 RADIATION PROTECTION PROGRAM 6 6.12 HIGH RADIATION AREA 6-[,e 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM).............................. 6 d 6.14 RADI0ACTIVEWASTETREATMENT...............................6P[# 6.15 DELETED 6.16 DELETED I ( l 1 I l l f I HADDAM NECK XII Amendment No.125.155.158.170.181.-1"A l TS-INDEX. DOC l \ 1
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~ ~ ~ ~ ' ' ' ' 1 g~ l L0 DEFINITIONS I l The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications. l i
I , l ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.
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l I i 4 I HADDAM NECK 12 Amendment No.-125,1'0,493 TSSEC1.00C
Juma 30. 1999 LO DEFINITIONS OPERABLE OPERABILITY
) .,1 W. A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
- OPEP^. TION ^1 uggE . uggE 1.10 Ar, 0"E"ATIONAL "00E (i .e. , MODE) Chall c0rrespOnd t0 any One inclu-sive combination of core reacti"ity coaditier, pcuer level, ar.d average 4eacter coolant temperature speified da Table 1.2.
1.10 DELETED 1.20 DELETED-l I 1.21 DELETED l t 1.22 DELETED RADIOACTIVE WASTE TREATMENT SYSTEMS vl I' RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive l material in order to meet the LC0's set forth in the:c speci#ic"4cr- p RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE C ULATIO MANUAL (REMODCH) j.9 O L24 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall be a manual containing the site and environmental sampling and analysis programs for h measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULA-TION MANUAL (0DCM) shall be a manual containing the methodology and param-eters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. Requirements of the REMODCM are provided in Specification 6.13. HADDAM NECK 13 Amendment No.125r193-TSSEC1. DOC I
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June 30, 19 TABLE 1.1
. FREQUENCY NOTATION NOTATION FREQUENCY S At least once r 12 hours.
D At least o e per 24 hours. W At leas once per 7 days. B At ast once per 14 days. M t least once per 31 days. SW At least once per 42 days. Q At least once per 92 days. SA At least once per 184 days. R t least once per 18 months. i l P Pri to each release. N.A. Not ap licable. j i i i I l f e vv19 K Qaye HADDAM NECK 15 Amendment No.42 h 193 i TSSEC1.00C
_ 0 _ 3 o t e _ n u l a _ J u E q R e R r o C n a . E h _ G E t A T R E s F _ s 0 V e4 _ A l 1 R E W O D P S E E T L D A A O R M 2 M R 0
%E 1 L H A T E N O
L B I A T T A R - E P O 1 g_ K r Y o T . I N n V O a I I h 4 T T t 9 C I _ A D s 0 E N s R O e o C l t
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D E T D E T D E T D E T D E T G N I L E E E E E E J P L L L L L E E E E E E D D D D D R 1 2 3 4 5 6 Dq W<O DhgD
SELTTON5 3, 3 Alv b y. g. IIUS T Rv NEN TATIoAj D El4 T E D 1/U Tl+EI( FA7d&Ty I
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SecTICAS 77A/UD%y 7 g Ard T S Y 5 TEetS T)E LPT ED L /U ~ HEIR F/LTJ/wTy L
c 1 SEC T T C)/V 3 3 , 't l T H R C U G /4 3' 9. 6,' S EcTIdo 5 4, 9. / T/ Moo 6 N z/,7g-t J F% UB & 3,9-/, J WS 4/u D 3/4 9-1 T HRo vG H 3/Y 7- 4 3 EL&7 ED 1 l-L
! \ i I i l, i ss_v PEN T P OEL. 60 CL.O 'u [N k - s - m y 27, 1993 _ REICEL = OPERATIGNS 3/4.9.7 CRANE TRAVEL - SPENT FUEL STOPJCE-BUILDING LIN TING CONDITION FOR OPERATION l 3.9.7 Loads in excess of ounds shall e prohibited from travel over j fuel assemblies in the :t r;;c pool. j gho} ( < w l APPLICABILITY: With fuell assemblies in the -ter;;c pool. ACTION: /CMSI - # 5/fM l ! ih- With the requirements of the above specification not satisfied, place the crane load in a safe condition. j l b. The pievisicas of Specificstica 3.0.3 are act applicable. SURVEILLANCE REQUIREMENTS 4.9.7 Administrative controls that prevent the travel of loads in excess of pounds over fuel assemblies shall be in place prior to lifting a load in excess of %59-pounds,
/ 9)# #
I HADDAM NECK 3/4 9 7 Amendment No. 125.lta-TS359. DOC- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ - _ - - - _ _ - _ _ - - _ ~
F i l: l 4 l l SECTT0/V5 K18 TH90vG, H 3. 9, /0j l 5 s cT1civ s 4,9. B T W ti a ucs H 4. 't M) 4kD
%q ws 3/9 9- 8 TiutovGH yy 7-n QPLETf=0 1 4
1 J l l
S f GAIT F U G l- B u r L.0 % N &- April 25. 1000
-nEFUELINC OPERATIONS CN 3/4.9.11 WATER LEVEL STORAGE POOL
^9 5 PENT Fu @
am LIMITING CONDlIl0LEOR.0PERATION 3.9.11 At least 20 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the stcr;;c racks. - APPLICABILITY: Whenever irradiated fuel assemblies l are in the stw pool. ; gyny: b +^* f *
- I ggg} __/We - - )
+ With the requirements of the above specification not satisfied, suspend all movements of fuel assemblies and crane operations with loads in the -fual- steF2 0 areas and restore the water level to within its limit within 4 hours.
- b. The pmvision; cf Specification 3.0.2 are not applicabic.
SURVEILLANCE REQUlREMENIX --. [ 4.9.11 The water level in the stere;c pool hall be determined to be at least its minimum required at least once per 7 days when irradiated fuel assemblies are in th fuel :tcr:ge pool.
/
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l HADDAM NECK 3/4 9-12 Amendment No.409-TS359.00C (
l l i l i l Ssc TIow 5 3,'f, /2 AND (1. 9,O)' \ ANP : Pl% ns 3/t/ '1-13 /)W D 3/9' 9-/V l 1 QELE7hb , 1 i i 1 1 1 1
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?ug=t 15.1994
-AE4WiMMi OPERATIONS
/
l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL f MtilIING CONDIT10tLf0R OPERATION 3.9.13 Prior to movement of a fuel assembly in the spent fuel pool, the boron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of greater than or. equal td 800 ppm. { AEf1ICABILITY: Whenever+ fuel ' assembly is _ moved in the spent fuel pool, gngg: ,_ _ -wa ia$ed i With the boron concentration less than 800 ppm, suspend the movement of all { fuel in the spent fuel pool. SURE1LLANCE_Ef'lUIREt1ENI 4.9.13 Verify that the boron concentration is greater than or equal to 800 ppm within 24 hours prior to any movement'of a fuel assembly in the spent fuel pool and every 72 hours thereafter.
, , ,, , ~ er' d
. $p e ) ,+1 o veMC N b '
_, x.h l. f 1 HADDAM NECK 3/4 9 15 Amendment No.tNr l TS359.DCC
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3/4.9.14 SPENT FUEL P00L lREACIGIILf0N01 TION LIMITING CMD.Ill0fLf0R OPERATION _ L .3.9.14 Thg,,feactiyjty[ondition of the spent fuel pool shall be such that K,y is less/than)or/equaVto 0.95 at all times. ABELICABILITY: Whenever fuel is in the spent fuel pool.
- c. -~~-'
6CIl0N: ) er ad io fed w~v
- 1
- Annediately initiate actions to correct the loading error if the placement of fuel assemblies does not meet the requirements of Figure 3.9 2, Figure 3.9 3. and l
- Figure 3.9-4.
l 1: SURVflu.MCE_ REQUIREMENT _ , _ . _ , _ _ i 4.9.14 Ensure that all fuel assemblies to be placed in the spent fuel pool are M l
" within the enrichment and burn up limits of Figure 3.9 2 (Region 2) and 3 Figure 3.9 3 (Region 3) by checking the assembly's design and burn up '
documentation. Region locations are shown in Figure 3.9 4. l l I' 3/4 9 16 HADDAM NECK Amendment No.4MvhM-- , I TS359. DOC- _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ - l
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[ - - -- guue 33, 1333_ WEift:idF2_0EE8 ail 0HS 3/LRJ6 .Sfiff[JllEL POOL COOLING - DEFUELED nL-J MBlH!f1_C0f01II0lHOR OPERATION 3.9 16 The spent fuel pool coolant temperature shall be maintained at less than or equal to 150 degrees F. APPLICABILITY: Whenever irradiated fuel assemblies are stored in the spent fuel pool. ACIIDS: With the spent fuel pool coolant temperature not within limit:
- a. Immediately initiate action to restore the spent fuel pool coolant temperature to within limit, and
- b. Imediately verify that a spent fuel pool makeup water source is available, and
- c. Within 7 days, restore the spent fuel pool coolant temperature to within the limit.
SURYEILLIKE_REQUl8EBERIS l 4.9.16 At least once per 24 hours, verify that the spent fuel pool j coolant temperature is less than or equal to 150 degrees F. . { l l
)
l 1 1 HADDAM NECK 3/4 9 21 Amendment No.19& > TS359. DOC U
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p 3/4.9 RETUEL'He OPERATIO31 CPGruTPhH-6ditoID) s ; BASES 3/4.9.1 -30"0" C0"CC"T"'TIG K DEL% 673 ()
: li:-i t:ti: .: :n re::tivMy c ndition; durir.g RETU LING ensure thet; QL.
the will remain subcritical during CORE ALTERATIONS, and W'
+ ation is maintained for reacti ity-centF6 Tin the l uniform boron J l water volume having direhgto the re ' c-vessel. These limitations i l
are consistent with the initial c assumed for the boron dilution incident in the accide'it aml'ses. A value o .. r less for X,n is required fo ccident. For a core configuration o - ds in an 3ddit-itma 0.05 K,n penalty is required to account for a heavy loa ; cinshing the core inte : = r: rc: tive configur+t4en. m l 3/4.9.2 IMSTP,LHEMTAT40N- D E L ETC- L)7 ' The OPE"nA"ILITY cf the "curc: ":ng: " utren Flux ". : iter: ensur4s that- . u,unitering ;;p;.bility i: :":il:ble te detect chaar;=s in the reactivity I c,endition of th; : u_re. ____,.a... P, dund:nt -^niteria; c?" ability i' "aa"irad ta
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,,iini ,0,T, requir;=nt fer. reecter subcritic:lity pri r t: =v=:r' Of::' I irra semblies in the reactor vessel ensures that Js ff4c1~6ftlime has elapsed to al o adioactive decay of the shor iv E fission products.
Tne minimum requiremen ctor hold or to movement of irradiated fuel from the reactor vessel to' fuel pool ensures that sufficient decay time has elapsed fo uate spent ol cooling should a failure occur to the cool stem. The resctor hold time unction of cooling water ta re. The required decay time assumes a conser aximum er rate of six assemblies per hour. These decay times are consi nt.
;gjfh tha age _ nant 4 nn e.
n e_ a_d_i n t_ h.e e_ n_ f a t_,u a n. n_ i. ,v e. i. c_ _ 3 /4 . 9 . 4 emM,,, , mo,o.,. o.n m .. ,n... . , , m , m...,,
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The r:riuir;=nt: : : t:f r.=nt bum 4ing per.:tr:t4:n cle:ur: :nd OPEP.^,SH4-TY
-enwre th:t :. rele::: Of r:di :. 44v: =t:ri:1 within :: t:ir;;; nt will be re d,icted fiv le.keye to the environment. Th GPE"ABILIT" end ciesvre
-re+tr-istien er : ffittent te re:teict r: die::tive = teri:1 rele::: frem-a Tuwl el; nt-repture besed oper, the nf 1::k Of : nt:i .=nt pre::ur4att44n-a_ak 2. &L.
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.s.m e mm. 6= 4, w.1e ywwv unu a i,w. e es unw n u.s we. m , nw av 31.iJtJ.:sfEEGaHfE -
&LFTeD Tk- requ4rm-t fer cc unicatient canbi'ity ensures thet refueling cavity-ernipulater crane are pertenael can a pre-atly 4afem:1 ef significant
-change 4a the fact'ity : tite: er core res:tivity cehditiens during CORE
-AtT-
.fnAT*AM.P.. . .
1 l l I HADDAM NECK B3/4 9-1 Amendment ho. W 188
._ ___-_ a
. REFUEL 1N0 FM[1qEli b BASES f i
% 1 3/4.9.6 "ANIPULATOPs CPANEE D
-The-OPERABR44-Y-requ4*ement+4e e-the-san 4pula tor-c ranes-en sur4--thate.- --{4 ) !
-man 4puht+e -eeanes-w444-te-used4er-travement-of-contr41-rod driye skaf4s-and-fuel-asser.M445, (?) each crane h2: ruff 4c44nt-Joad-capac4ty te lift-a-dr4ve-
+hafbe*4ue.1 :::cmbly, and (2) th: core %termels-and-reactor-vessebar4- j Sretected from avcessive lif tir.g forces 4n4he-event-they-ar4-inadvertently
-er. gaged during 14-ft4ng-epeeat40ns. j 3/4.9.7 CRANE TRAVEL - SPENT FUEL STOPaCE BUILDING 'Dk e b ypnil f /loads in excess of the = inal" weight of a e
@The fuel andrestriction on movement ofand associated handling tool over control rod assembly assemblies in the star-age r pool ensures that in the event this load is 60 l dropped: (1) the activity release will be limited to that contained in 4 single fuel assembly, and (2) any possible distortion of fuel in the stor ge f".]f racks will not result in a critical array. This assumption is consistent w
fj <ith the activity release assumed in the safety analysis. zn 1/4.9.8 m.,m m m.m. ,mov.n_ mm
.-. -2114H9H C1Tp)p i-k
- Itte reqdr4mont sufTte44nt that cooling at-lea:tisene capacity RHR LOOP available to removebe-in-eper:tica decay heat ensures and m intthet[: "
the watehnahe reactor vessel below 140*F as required durin REFUELING MODE, and (2) Dsu 14c[ent coolant circulation is maintai 1 rough the core to minimize the effect4 fa boron dilution incide nd prevent boron stratification. . The requirement to nave two RHR S0 R E when there is less than 23 feet of water above the r,ea or vessel flange es that a single failure of the operating RHL1-00P will not result in a comp oss of residual heat removalJaps5Tlity. With the reactor vessel head re nd 23 feet of water.,ab6ve the reactor vessel flange, a large heat sink is a ble for cpr-e-tooling . Thus, in the event of a failure of the operating RHR L
-adequata time is provided te ini44 ate emergency-procedur4s-to-coobthe-corer 3/4.9.9 E0MTA1N. MENT PURCE SUPPE-Y-PURGE EX"AUST. AND PURGE EXHAUST-BYPASS-
-l@ HAT 40N SYSTEM- N g
-The-OPERAEMTho f-th h-sy s tem-ensu re s-that-t he-c ontainment-ven t-a nd- pu rge-tenetrathns-cen-be4soh t ed-u pon-det ec t4on-of-high-rad 4 at4 cn-le v el s-withi n-
-the-conte 4nment . The-OPERA &R4TY cf th4-system 4s-requ4 red-to-r4str4ct the
-release-of-eadbactive ::ter4abfron4he-cont 44nment-atmosphere to the
-onv4ronment . - - -
mn. fThe restriction also ensures that the effects of
< h any load drop on the spent fuel pool structural
% f o/
) (integrity Holtec Reportis enveloped HI-941225, Rev. O,by the load drop a
" Accident i U/ N gb / h b. b b h N ]h i Analysis Report for CY Spent Fuel Racks," Dr.[
l Yu Wang, item 11, Holtec Project 40264) - performed for Techmoampecificilio~h Amendment my 188. r -- t ~ W] HADDAM NECK 8 3/4 9-2 Amendment No. W . 158 l t
hPEfdT Fv H- Sv L DIi W 9 g. - - - ~ - o ern e' '""
-- TIONS , F *
BASES I
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0/4.0.10 =d 3/4.9.11 WATER LEVEL "r"cc' ^"" """ ^GE P0OL
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is eveilable to remove 00% of the naumed 10% i; dine gap =tivity eektwed-. 3o8h
'frem the ruptcrs of = lrr:di:ted fuel n embly. The r"7mur m.ter dep4h-4s $EE'
- casi: tent with the n:umption of the afety =;1ysi-s. J;;;8@
mao J./4.9.12 TUEL ST0"J,CE SUILDINC A!" CLEANUP SYSTE p&L ETs t) ~h w_a
-The limit &tiens on the Iuel Sterage Odilding Air Cle&nup System ensure-that k h 5:
- 11 radioactive :: tee 4:1 r:1 = d 'rc= = irr duted f=1 n embly will be- oo2
-filtered thresh the HEPa, filter: =d cherce:1 :d:er4w-pr4+r to dinharge t $53
-the atac:phere. W -OPEPf.EILITY cf thi: tyster ud the -eculting 4odina_.-. E. 3 $
~n' capacity are :=:,dtmt with the n:umpt4cas of the 3efetj 3%Ijsis. $8 T E 8 ar ANSI N510 1980 wi be u: d n pr-ocedural guide for cur"a'l=ce tutin"a. wa<
1s:1 "F 3 g*- 3/4.9.13MOVEMENTOFFUELINSPENTFUELP00_L esm The limitations of this specification ensure that, in the event of any fuel $$k> 8$g handling accident in the spent fuel pool, Km will remain s 0.95. .- i 3/4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION feel,) { .]g o u[$ m - c. gu a I The limitations described by Figures 3.9-2, 3.9-3, and Figure 3.9-4 nsure , g g R. that the reactivity cf fuel assemblies introduced into the spent fuel racks, {sg! with no credit taken for soluble boron in the col, are conservatively within REE the assumptions of the safety analysis. ,gg7
~
gt.#TED $c. $g o 6 3/4.9.156PENTTUELPOOLCOOLI"Or~-(f,-v -- - -)3 \ imitations on the Spent Fuel Pool Cooling System ensure there is maw -a sufficie acity to remove decay heat produced by the stored e ements sw8g, ja (1019 assemblies maintain the bulk pool temperature t w 150 F with a gEjf i . B3/4.9 1. -@ g maximum heat load as show $o s!ii w Requiring both SFP cooling pur be OPE rovides backup capability in p j. p j the event the operat' - mp fails. In the event or olete loss of forced i!so s a l l cooling, the " to boil, excluding the effect of evaporatio . ~ reater ig , tha curs based on current heatup calculations. Only makeup wou i j l
, equired to maintain pool inventory. Q' c L
U l l f Amendment No. JU. J7f, J# , _ HADDAM NECK B3/4 9-3
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l - S FEN T I= U6 L- () vf L.DZN I-- - Junc 30, ITO RErJELI"G OPERATIONS l BASES 3/4.9.16 SPENT FUEL POOL COOLING DEFUELED The primary basis for 150 degrees F is to limit thermal stresses on the spent j fuel pool concrete structures due to the differential temperature across the f j j internal and exterior surfaces of the walls and floor. The basis is further ( ) l discussed in License Amendment No. 188. As of May 1998, the spent fuel heat load was calculated to be less than 2.3E+06 BTU /hr. Each heat exchanger has the capability of removing this heat load. One spent fuel pool heat exchanger and one spent fuel pool cooling pump, that can be operated intermittently, is sufficient to remove the decay heat load. l ' Assuming no forced or evaporative cooling, the calculated-May 1998 heatup rate { l is approximately 1.2 degrees F/hr. Thus, in the event of a complete loss of j forced cooling and assuming an initial spent fuel pool temperature of 150 degrees F, the time to boil, assuming no evaporative cooling, is greater l than 50 hours. Therefore, sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory. I l l ! B3/4 9 5 HADDAM NECK Amendment No.493-l TSB359.00C l j
1 l l l I 3ASES 3j/ d, // k%10ACTIL'& E = FluEtuiS Tl W I R % Tz k T'T sy 9 ,g T & D S iv l l
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5.0 DESIGN FEATURES f
!L1 MTE e - COELETCO EXCLUSION APIA 5.1.1 The Exclusion Area shall be as shown in Figure 5.11. The minimum .
distance to the boundary of the exclusion area as defined in 10CFR100.3 shall be 1740 feet. 7 LOW POPULATION ZONE Q_ The Low Population Zone shall be as shown in Figure 5.12. 5.2 DELETED 4 5.3 DELETED E4 DELETED f 5.5 "ETEOR0 LOGICAL T0ER LOCATION A ( 6TE
. meteorological tower shall be located as shown in Figure 5.1-i l
l HADDAM NECK 51 Amendaent No. ME-193-TSSEC5. DOC [
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b ( es94 l f 5-3 Amendment No. 125 HADDAM NECK 1
June 30, 1998 DESIGN FEATURES 5.6 SPENT FUEL STORAGE l CRITICALITY l 5.6.1 The spent fuel storage racks are made up of 3 regions which are designed l and shall be maintained with:
- a. For Region 1 a nominal 10.98 inch (East / West) and a nominal 10.142 inch (North / South) center to center distance including neutron absorber surrounding each assembly to ensure a Kerr less than or equal to .95 when flooded with unborated water. Fuel with a maximum nominal enrichment of 5 weight percent U 235, without regard for fuel burnup, may be stored in this region. The location of Region 1 within the Spent Fuel Pool is shown in Figure 3.9 4.
- b. For Region 2, a nominal 9.00 inch center to center distance including neutron absorber surrounding each assembly to ensure a Kerr less than or equal to .95 when flooded with unborated water.
Storage of fuel in Region 2 must be in accordance with the requirements of Specification 3.9.14. The location of Region 2 within the Spent Fuel Pool is shown in Figure 3.9 4.
- c. For Region 3, a nominal 10.75 inch center-to center distance to ensure a K,rr less than or equal to .95 when flooded with unborated water. No credit is taken for the neutron absorber contained within the racks of this region. Storage of fuel in Region 3 must be in accordance with the requirements of Specification 3.9.14.
The location of Region 3 within the Spent Fuel Pool is shown in Figure 3.9 4. DRAINAGE l 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 27.0 feet MSL. i CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 224 storage locations in Region 1, 560 storage locations in Region 2, and 696 storage locations in Region 3 for a total of 1480 storage locations. HADDAM NECK 54 k Amendment No. 4&l93 TSSEC5. DOC
June 0, 1998
)
I i l SECTI 5.7; TABL 5.7 1; FIGURES 5.6 and 5.6 2: D PAGES 5 THROUGH 5 8 j DELETED i I l l l e dp*pf HADDAM NECK 5 11 Amendment No. 193 TSSEC5.00C
- - - _ = _ - _ _ _ - - _ - _ - - _ - _ _ _ _ - . . - _
u-.6 9nno NJ 'e A .< m 6.0 ADMINISTRATIVE CONTROLS (., 6.4 TRAINING A retraining and replacement training program for the Certified Fuel Handlers shall be maintained under the direction of the Unit Director. A retraining and replacement training program for the facility staff shall be maintained under the direction of the Unit Director,, cr.d ch:11 =cct er exceed the ___.2____m_ m _, r__m._ r r _, ame, m,n , , , , , ,
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v - - (;~m,3 HADDAM NECK 65 Amendment No. 126, 4 M , 4 % , 468, 179. 490. 494. 492 L__- - - - - _ - - - - - _ _ _ - - - - - - - - - - - _ - - - - )
May 2. 1998 6M ADMINISTRATIVE CONTROLS l i
, ALTE TES
( 6.5.1.3 All alternate members shall be appointed in writing by the RC Chairperso to serve on a temporary basis: however, no more tha two alternates all participate as voting members in PORC activities at ny one time. MEETING FRE00 ENC 6.5.1.4 The POR shall meet at least once per calenda month and as convened by the PORC C. irperson or his/her designated alter te. OUORUM 6.5.1.5 The quorum of the ORC shall consist of th Chairperson or his/her designated alternate and four m bers including alte ates. , RESPONSIBILITIES 6.5.1.6 The PORC shall be respons1 le for:
- a. Review of: (1) all procedur equired by Specification 6.8 and i changes thereto, and 2) any o er proposed procedures or changes I ll thereto as determined by t nit Director to affect nuclear safety:
- b. Review of all proposed t sts and e eriments that affect nuclear l safety;
- c. Review of all propos changes to the Te nical Specifications:
- d. Review of all pro sed changes or modific ions to plant systems or equipment tha affect nuclear safety;
- e. Investigation f all violations of the Techni 1 Specifications, including th preparation and forwarding of eports covering evaluation nd recommendations to prevent rec rence, to the VP Opera ons and Decommissioning and to the clear Safety l Assessme Board:
- f. Review f all REPORTABLE EVENTS:
! g. Rev w of facility operations to detect potential safety h ards:
- h. P rformance of special reviews, investigations or analyses and eports thereon as requested by the Nuclear Safety Assess nt l Board or the Unit Director.
l HADDAM NECK 66 Amendment No. 426, M 6, 468, 181., 191, 192
> 1 6.0 ADMINISTRATIVE CONTROLS
- i. Not used.
Not used. I
- k. Review of the Fire Protection Program and Implementing Pro dures.
AUTHORITY 6.5.1.7 The C shall:
- a. Report t and be advisory to the Unit Director n those areas of responsib ity specified in Section 6.5.1.6(a) rough (k):
- b. Render deter nations in writing to the Uni Director if any item '
considered un r Specification 6.5.1.6a. hrough d. , above, as ) appropriate a as provided by 10 R50.59 or 10CFR50.92 i constitutes an unreviewed safety estion or requires a ! significant hazar consideration dete ination. l
- c. Provide written noti ' cation, meeti minutes may be used for this purpose, to the VP Operatio and Decommissioning and the t {
Chairperson of the Nucle Safet Assessment Board of disagreement between the PORC and eU t Director; however, the VP - Operations and Decommiss1 n g shall have res onsibility for i resolution of such disagree ts pursuant to Speci ication 6.1.1. !)
- RECORDS 6.5.1.8 The PORC shall mainta written min tes of each meeting that, at a minimum, document the results f all PORC ac vities performed under the responsibility and authority rovisions of thes. Technical Specifications.
A Copy shall be provided to e Nuclear Safety Asses nt Board. 1 i 6.5.2 NUCLEAR SAF ASSESSMENT BOARD (NSAB) l FUNCTION 6.5.2.1 The imum qualifications of NSAB members are as llows:
- a. -
Chairperson and NSAB members shall have:
- 1. An academic degree in an engineering or physical cience field, or hold a senior management position, and
- 2. A minimum of five years technical experience in th , r respective field of expertise.
hO HADDAM NECK 67 Amendment No. 425 M S, 38, 479, 481, 489, 4 M , 192 i ._ _____________ _ __ -
May 2, 1998 6.0 ADMINISTRATlyE CONTROLS
^
- b. The NSAB shall have experience in and shall function to provid independent oversight review and audit of designated activities the areas of:
Plant Operations, Decommissioning, Engineering, Radiological Safety, hemistry/ Radiochemistry, lity Assurance, and En ronmental Protection. The NSAB serves to advi the VP Operations and Deco issioning on matters related to nuclear safety nd notify the VP Operati s and Decommissioning within 24 hours of a safe significant issue and r a safety significant disagreement between the NSAB d the organization r function being reviewed. COMPOSITION 6.5.2.2 The VP Operations and D ommi ioning shall appoint, in writing, a minimum of five members to the S and shall designate from this . , - membership, in writing, a chairperson a a Vice Chairperson. The membership 1 shall function to provide independent evi and audit in the areas listed in Specification 6.5.2.1. ALTERNATES 6.5.2.3 All alternate mem rs shall be appointe in writing, by the VP - Operations and Decommission ng; however, no more t n two alternates shall participate as members in SAB activities at any one ti, . MEETING FREQUENCY 6.5.2.4 The NS shall meet at least once per calendar qua er. i 000 RUM 6.5.2.5 e quorum of the NSAB shall consist of a majority of NS members including he Chairperson or Vice Chairperson. No more than a minority f the quorum all have line responsibility for operation of the same Haddam eck ! Plant No more than two alternates shall be appointed as members at y meet'ng in fulfillment of the quorum requirements. ( HADDAM NECK 68 Amendment No. M . M6, 468, W , m , 192 \ !
j May 2, 1998 6.0 ADMINISTRATIVE CONTROLS hVIEWRESPONSIBILITIES ( . 6.5. 6 The NSAB shall be responsible for the review of: The safety evaluations for changes to procedures, equipme , or systems, and tests or experiments completed under the pro isions of 10 CFR 50.59, to verify that such actions did not cons tute an nreviewed safety question as defined in 10 CFR 50.59:
- b. Pr osed changes to procedures, ecuipment, or systems hat involve an reviewed safety question as cefined in 10 CFR 5 .59:
- c. Propos tests or experiments that involve an reviewed safety questic as defined in 10 CFR 50.59:
- d. Proposed c nges to Technical Specification and the Operating License:
- e. Violations of pplicable codes, regu tions, orders, license re uirements, o internal procedure having nuclear safety si nificance;
- f. All Licensee Event Re orts require y 10 CFR 50.73:
- g. Indications of signif1 ant un ticipated deficiencies in any aspect of design or era on of structures, systems, or clear safety; (y"
components that could affe
- h. Significant accidental, tifp1 ned, or uncontrolled radioactive releases, including corr ;ive tions to prevent recurrence;
- i. Significant operating normaliti or deviations from normal and ex cted performanc of equipmen that could affect nuclear ,
sa ety:
- j. The performance the corrective actio rogram: and i
- k. Audits and th Annual Audit Plan. l Reports or recor s of these reviews shall be fo arded to the VP -
Operations and Deco issioning within 30 days following ompletion of the review. AUDIT PROGRAM RE ONSIBILITIES 6.5.2.7 T NSAB audit program shall be the responsibility of e Nuclear Oversight o ganization. NSAB audits shall be performed at least on per 24 months i accordance with appropriate administrative procedures an shall l encompa : '
- a. The conformance of unit operation to provisions contained with' (j the Technical Specifications and applicable license conditions:
HADDAM NECK 69 Amendment No. 426, 45, 181, 194, 192
]
l E________________
May 2. 1998 6.0 ADMINISTRATIVE CONTROLS c . The training and qualifications of the unit staff: i
- c. e implementation of programs required by Specification .: ,
i
- d. The Fi Protection Program and implementing proc res:
- e. The fire prot ion equipment and program lamentation utilizing either a qualifie offsite license fi protection engineer or an outside independent e protectio onsultant.
- f. Actions taken to correct ficiencies occurring in equipment, l structures, systems, ponen or method of operation that l affect nuclear saf : and i
- g. Other activ' es and documents as requeste y the VP - Operations and Dec issioning.
RECORDS I i 6.5. . Written records of reviews and audits shall be maintained. sa imum, these records shall include results of the activities conducted un the provisions of Section 6.5.2. _ EP TAOLE EVENT ACTION 6.6.A Tiie iviluwois a usvus asiali Le i.aken Tui REFORTABLE EVENTS. I
- c. The Ccristicr th211 be "Otd f4ad "A " "^P^"* '"hmittod purenant to the rcquircnnt; cf Section 50.73 to 10 CP o:rt 50. and
- b. Each REPORTABLE E"EhT : hall be reviewed by the o0RC nd the result: cf thi; revicw holl bc ;ubmitted to the NSAS and the VI - .
Operatics or,d Occc=izicning. t 6.7 DELETED l g4trye To Pi%e 64 l
- p. fM"'#e W HADDAM NECK 6-10 Amendment No. -126, ES, M1, j -1 M . 192 k _ _ _ _ _ _ . . _
l Junc 20. 1003 LO ADMINISTRATIVE _ CONTROLS l (L8 PROCE00RES ANO PROCMMS .d - {LWM 6.8.1 Written proceaures ana/or administrative policies shall be l established, implemented, and maintained covering the activities referenced i below:
- a. The applicable procedures recommended in Appendix A of Regulatory I Guide 1.33, Revision 2, February 1978;
- b. The requirements and recommendations of Sections 5.1 and 5.3 of 1 ANSI N 18.7 1976.
I
- c. Fire Protection Program implementation.
1
- d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1. June 1974.
I I
- e. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION '
MANUAL (REMODCM) implementation except for Section I.E. Radiological Environmental Monitoring.
- f. Process Control Program implementation.
- g. Spent Fuel Pool Cooling and Makeup Monitoring Program implementation. This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool l l water makeup capability be monitored and maintained. This Program !
shall provide reasonable assurance that the equipment, components, systems and water sources used for spent fuel pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected against freezing, w ho lY g i jf0 VC l l l l l l MADDAM NECK 6 11 Amendment No. 125, 155, 181,
- 191, 192d93-i TLSEC6.00C l l
___________-_______0
1 6.0kADMINISTRATIVECONTROLS
/ I 6.8.2 Each procedure of Specification 6.8.1, and changes there , shall be revie d by the PORC and shall be approved by the Unit Direct prior to l
implementa 'on and reviewed periodically as set forth in each d ument or in I administrate e procedures. 6.8.3 Tem orary changes to procedures of Specification 6.8.1 may be made I provided: I
- a. The int t of the original procedure is no altered: I
- b. The change s approved by a member of the plant management staff j and a Certif d Fuel Handler; and I
- c. The change is do mented, reviewe by the PORC and approved by the Unit Director wit 'n 14 days of implementation.
6.8.4 Written procedures hall be established, implemented and maintained covering Section I.E., a 1ological Environmental Monitoring, of the REMODCM. 6.8.5 All procedures and p cedure anges required for the Radiological Environmental Monitoring Pro am of Spe ification 6.8.4 above chall be reviewed by an individual other than th author) from the Radiological Assessment Branch or the P oduction Operation ervices Laboratory (POSL) and approved by appropriate e pervision. Temporary changes ma e made provided the intent of he original procedure is not altered and the change is documented and reviewed an individual (other than the author) rom the Radiological Assessment Branc or the POSL, within 14 days of impi .entation. ye . -t HADDAM NECK 6-12 Amendment No. 425 A W -1 & 191, 1 % 193 l l TSSEC6 DOC l l [
l May 2. 1998 Q ,. ADMINISTRATIVE CON EDLS P 6.9 REPORTING REQUIREMENTS - lttMTINE REPORTS 6.9. n addition to the applicable reporting requirements of T Code of Feder Regulations, the following reports shall be subm' d to the U. S. Nuclear Reg ory Commission, Document Control Desk. - ington, D.C. 20555, one copy to th propriate Regional Office of t RC, and one copy ; to the appropriate NRC Rcsldeot Inspector, unless oth 1se noted, f 6.9.1.1 DELETED k N
' 11 6.9.1.2 DELETED i
( 6.9.1.3 DELETED 1 1 , ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the faci Q as t dese d below for the previous calendar year shall be submitted prion r ( l
,JafIh1ofeachyear.
(
; u
% Rtvisca m sha n ..
pmes 6-A swd 4-8 j i i, t l J f T.h HADDAM NECK ' 4 43, Amendment No, IM, MG,192 1 ' I
May 2, 1998 p,0 ADMINISTRATIVE _CQ1I20Ls _ mm _., v v v-~v-v v ( 6. 1.5 Reports required on an annual basis shall include: A tabulation on an annual basis of the number of station, u ity, 5 and ocher personne1' (including contractors) receiving osures f reater than 100 crem/yr and their associated man r exposure a ording to work and job functions * (e.g., reactor o ations and , sur illance, inservice inspection, routine maint ance, special { maint ance (describe maintenance), waste rocessing and { refuelin . The dose assignments to various d y functions may ba ) estimated sed on pocket dosimeter, therm uminescent dosimeter I (TLD), or fi badge measurements. Small xposures totalling less I than 20% of th individual total dose .ed not be accounted for.
) In the aggregate, at least 80% of the total whole body dose f received from exter 1 sources shal be assigned to specific major work functions; l a
- b. DELETED j l c DELETED
) )
N ! ANNUAL RADIOLOGICAL ENVIRONMENT OPERATING REP '
^
/
- ( 6.9.1.6 Routine Annu Radiological Environm tal Operating Reports covering the operation the facili?.y during the previ s calendar year shall be submitted prior t ay 1 of each year. ,
The Annual Rad ogical Environmental Operating Report sha include that ! information d neated in the REMODCH. l . k
\* This tabulation supplements the requirements of Section 10 CFR Part 20.
20.2206 f l l
. ~K_ '% -
/
4 $4YISC 43 5l1htw P W / "W pes (r-j u d 4-B.
- l. ('
HADDAM NECK 6 14 Amendment No.126, 4rA,192 i
May 2, 1998
. 6.0 AQEgg;5[BALNLS _
r'"-O ~~ m ...- m - m --- , [ b L RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1 outine Annual Radioactive Effluent Report coveri - he operation of the ity during the previous calendar year of a 1on shall be submitted by May 1 o eacj1 year. The report shall include that inform N s i i a deli ed in the REM 00CM. Any changes to the REM 00CM sh 3 1.V6e submitte 'n the Annual Radioactive [' Effluent Release Report. , ' N k 6.9.1.8 D N
. .9 DELETED w _,
1 ~ l 6 {kevjSe)(}s .r boy'4 tw t A'S t*t' N lAf la -/) s4<l V0 l hy M i l ($$ HADDAM NECK 6 lo- Amendment No. MS, -148, gg, M6, M8. We,192
i fWW-l l') b
,- -% ~ ..-~ \
ADMINISTRA W L CONIROLS _ _ _ ) l 6.9 REPORTISE RE0111REJfjlIS ! ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following reports shall be submitted to the U. S. Nuclcar Regulatory Commission. Document Control Desk, Washington, DC 20555, with one copy to the appropriate NRC Regional Office and one copy to l the appropriate NRC Resident Inspector. { tdNUAL OCCW ATIONAL RADIATION EXPOSURE REPORI 6.9.1.1 Routine Annual Occupational Radiation Exposure Reports covering l 1 the activities of the facility during the previous calendar year shall be ! submitted prior to March 1 of.each year. The Report shall ir!clude a l tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure accerding to work and job I functions * (e.g., decontamination and decommissioning, surveillance, routine ! maintenance, special maintenance (describe maintenance), waste processing 'and j spent fuel movenent). The dose assignments to various duty functions may be ! estimated based on' pocket dosimeter, thennoluminescent dosimeter (TLD), or I film badge measurements. Small exposures totalling less than 20% of the j individual total dose need not be accounted for. In the aggregate, at least i 80% of the total whole body dose received from external sources shall be ! assigned to specific major work functions. I ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERAJJB.GlEEDRI i 6.9.1.2 Routine Annual Radiological Environmental Operating Reports covering the cctivities of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The Report shall include that information delinated in the REMODCM. l f
- This tabulation supplements the requirements of Section 20.2206 of l 10 CFR Part 20.
64J o :
,.- - .m m- ,g m (TpjS ER T&b ?AM ps b te - - . s s ._..__._ u --
ADMINISTPE 1VE CONIBOLS. , ANjuAL RADIOACTIVE EFFLUENT RELEASE REEORI 6.9.1.3 Routine Annual Radioactive Effluent Release Reports covering the activities of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The Report shall include that information delinated in the REM 0DCM. Any changes to the REHODCM shall be submitted in the Report. 6.10 DELETED 6.11 RADIATJ0fLP80_TECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared l 1 consistent with the requirement of 10 CFR Part 20 and shall be approved, {' maintained, and adhered to for all operations involving personnel radiation exposure. I 1 l i 1 I l 6W ____.______.____m_.___.__
May 2, 1998 (.~.(' t.
'L
*T'117 t* f4 &hf* TLM&ETTMaf A t I is na na >
#I#6W i rygsk 4 IV 4 LIT g AVimb l ULfyin 1g i
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'HADDAM NECK 6 16 Amendment No. 424, 448, 453, ;
466, 468. 485, 192 l i-( l r
May 2, 1998
. 6.0 ADMTNISTRATfVE CONTROLS
.r:
a
,.% e fir * /* T A i n r* n An*I"C" at tuiriu viti uni ,
j .t C.O.C 5pccici repcrt: chall bc cubmitted tc the U.S. Nuclear Regulatcry Cea,ission Occumcat Control Oc;k, ";;hington 0.C. 20555, with onc copy to-the approprieta Regional Offic; cf the NRC. and onc copy to the approprista NRC Rcsident Inspector, within the time pcried spccificd for cach rcport.
/.-n mm, 6.10 n""^unu u ^^^ ^~"m",1m"f(,D E L f TWgu 41ME To FME V b nm
^
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-G.10.1 In eddition to th; applic;bic rcccrd retention requirement: cf Titic 10 Codc of Icdcral Rcgulation;. thc follcwing rccords shcil be retained iv. et leest the minimum pcried indic:ted.
[ 10.2 The following records shall be retained for at least 5 years: Records and logs of facility operation:
- b. ords and logs of principal maintenance activitie , inspections, repa' , and replacement of principal items of e pment related to nuclear fety:
I
- c. All REPORTABL
,(. ~ )f l
. VENTS:
L d. Records of surveilla activit s, inspections, and calibrations I required by these Techn1 1 ecifications
- e. Records of tests and erimen -
l b f. Records of nges made to th procedures required by 9 Specificati 6.8.1: i
- g. Recor of radioactive shipments:
! k
)
I h. ecords of sealed source and fission detector lea tests and l results: I
- 1. Records of annual physical inventory of all sealed source mater '
of record; and l 7 A-l l
,f/#V8
( .; HADDAM NECK 6 17 Amendment No. 426, 148, 163, 166, 192 I t __ _ _ __ _ _ -_ _
I 6.0 ADMINISTRATIVE CONTROLS 7 ' (* 6.1 I RECORDRETEUTiON(Cont) 6.1 3 The following records shall be retained for the duration of he facill Operating License:
- a. ecord and drawing changes reflecting facili design deifications made to systems and equipment describe in the FSAR:
- b. Reco of new and irradiated fuel inventory, f transfers, and l assemb burnup histories; i t j c. Records of cility radiation and contamin on surveys
- , J t ,
individuals entering
- d. Records of ra ation exposure for 11 l l radiation control reas:
l e. Records of gaseous an liquid ra active material released to the l l environs;
- f. Records of transient or op tional cycles of the reactor vessel: l
- g. Records of training an qualif1 tion for current members of the facility staff:
- h. Records of in vice inspections erformed under previous amendments to ese Technical Specificat ns; t.
, 1. Records of uality assurance activities re ired by the Quality Assuranc anual not listed in Specification 6. 0.2: J. Reco s of reviews performed for changes made t rocedures or ! eq pment or reviews of tests and experiments pursu t to 10 CFR P rt 50.59: l l k. Records of meetings of the PORC and the NSAB; l . Records for Environmental Qualification: . l i
- m. Records of reviews performed for changes made to the RADIOLOGICAL l EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REH0DCM s and the Process Control Program. s 1 RADIATION PROTECTION PROGRAM l 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirement of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation (exposure, p i p v e N O j' T b~ N f L-4 HADDAM NECK 6 18 Amendment No. 426, 448, 4% ,
181, 192
v l
.k y 2. 1998 6.0 ADMINISTRATIVE CONTROLS l
l 1 6.12 HIGH RADIATION AREA
^
_ 6.12.1 Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the ,
" control device" or " alarm signal" required by paragraph 20.1601, each high radiation area, as defined in 10 CFR Part 20 in which the intensity of f radiation is greater than 100 mR/h but equal to or less than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the l RWP issuance requirement during the performance of their assigned duties in
, high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of l individuals permitted to enter such areas shall be provided with or l accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made
,,- knowledgeable of them; or 1)
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is res)onsible for providing positive control over the activities within :he area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Manager in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface which the radia-tion penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of I the shift supervisor on duty and/or health physics supervision. Doors shall l' remain locked except during periods of access by aersonnel under an approved RWP which shall specify the dose rate levels in t1e immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure . control over the activities being performed within the area. For individual high radiation areas accessible to personnel with radiation - levels of greater than 1000 mR/h that are located within large areas, such , as PWR containment, where no enclosure exists for purposes of locking, and l i where no enclosure can be reasonably constructed around the individual area,
- . that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device or continually i(/ -
guarded. HADDAH NECK 649- Amendment No. 436, M 5,-192-
T tiey 2,1998 -- 6.0 ADMINISTr4 TIE _C0HIROLS l,- fLl3_ RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE I' CALCULATION MANUAL (REMODCM) l Section I, RADIOLOGICAL EFFLUENTS MONITORING MANUAL (REMM), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released l, as a result of facility operation. It shall also specify operating l guidelines for RADI0 ACTIVE WASTE TREATMENT SYSTEMS and report content. Section II, the OFFSITE DOSE CALCULATION MANUAL (ODCM), shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setaoints. consistant wito the applicabic LCO*: contained irm these Trcinical Spccificctient. Changes to the REMODCM:
- a. Shall be docurranted and records of reviews performed shall be retained as required by Specificaticr Sg37 is g e g i,on ,,_s,ha]'l_
contain. A g g g g g gj --
- 1) Sufficient information support e change together with the appropriate analyses or evaluations justifying the change (s), and l
- 2) A determination that the change will maintain the level of 1
'I radioactive effluent control required by 10 CFR 20.106, 40 CFR ! Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not 'j adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after nev4ew ,@'9Megajp by o0RC and the approval of the Unit Director,
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as appropriate, as a part of or concurrent with the Annual Radioactive Effluent Report for the period of the resort in which any change was made. Each change shall be identifiec by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
l 6.14 RADI0 ACTIVE WASTE TRJATMENT Procedures for liquid and gaseous radioactive effluent discharges from the - facility shall be prepared, approved. maintained and adhered to for all I operations involving offsite releases of radioactive effluents. These l procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT l SYSTEMS utilizing the guidance provided in the REMODCM. The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance with the Precess Control Program to process wet radioactive wastes to meet [ ( shipping and burial ground requirements. vl HADDAM NECK 4-Eg- Amendment No. IM, IM, 448,
'r70. 1M ,-192-l l
May 2, 1998
. 6.0 ADMINISTRATIVE CONTROLS -
., S.15 DrLHE0 5.15 TLrre i
l l L j i E.!). l: HADOAM NECK # Amendment No. 426, 3 6. M8, I 192 (;: 1. l L______________
l DQGket No. 50-213 CY-98-003 Attachment 2 Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Retyped Pages i l' i l , August 1998 l \ l
The licensee may make changes to the fire protection program without NRC approval if these changes do not reduce the effectiveness of fire protection for facilities, systems, and equipment which could result in a radiological hazard, taking into account the decommissioning plant conditions and - activities. (5) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50. 90 and 10 CFR 50.54 (p) . The plans, which contain i Safeguards Information protected under 10 CFR 73.21, are entitled: "Haddam Neck Plant Physical Security Plan," with revisions submitted through January 24, 1989; "Haddam Neck Plant Guard Training and Qualification Plan," with revisions submitted through January 27, 1983; and "Haddam Neck Plant Safeguards Contingency Plan," with revisions submitted through December 9, 1983. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein. (6) Fuel Movement i The movement of special nuclear material used as reactor fuel into the containment is prohibited. D. This license is effectivs as of the date of issuance and authorizes ownership and possession of this facility until the Ca== mission notifies the licensee in writing that the license is terminated. The licensee shall:
- 1. Take actions necessary to decommission and decontaminate this facility and continue to maintain this facility, including, where applicable, the storage, control and maintenance of.the spent fuel, in a safe condition; and
- 2. Conduct activities in accordance wi'ch all other restrictions applicable to this facility in accordance with NRC regulations and
,. the. specific provisions of this 10CFR50 facility license.
- j. FOR THE ATOMIC ENERGY COM(ISSION l A. Giambusso, Deputy Director for '
Reactor Projecto Directorate of Licensing - I Original Signed by A. Giambusso
Enclosure:
Appendices A and B - Technical Specifications Date of Issuance: December 27, 1974 TSOPLIC. DOC
INDEX DEFINITIONS SECTION EAGE 1.0 DEFINITIONS 1.1 ACTI0N..................................................... 1-1 l 1.2 OPERABLE - OPERABILITY..................................... 1-1 l 1.3 RADI0 ACTIVE WASTE TREATMENT SYSTEMS........................ 1-1 l l 1.4 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)............................... 1 1 l l SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION EAGE 2.1 DELETED 2.2 DELETED t BASES SECTION EAGE 2.1 DELETED 2.2 DELETED i l ! l : f HADDAM NECK I Amendment No.125.168.178.188.193 TS-INDEX. DOC
INDEX 1 , LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTIDN EAGE 3/4.0 APPLICABILITY l L 3.0.1 ....................................................... 3/4 0 1- ; 3.0.2 ....................................................... 3/4 0 1 3.0.3 DELETED l 3.0.4 ....................................................... 3/4 0-1 l 4.0.1 ....................................................... 3/4 0-2 4.0.2 ....................................................... 3/4 0 2 4.0.3 ....................................................... 3/4 0 2 4.0.4 ....................................................... 3/4 0 2 4.0.5 DELETED 4.0.6 DELETED 3/4.1 DELETED 3/4.2 DELETED 3/4.3 DELETED l 3/4.4 DELETED i 3/4.5 DELETED i 3/4.6 DELETED 3/4.7 DELETED l l 3/4.8 DELETED ; HADDAM NECK II Amendment No.125.148,168.179.180.
-193 TS-INDEX. DOC
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION pyg, 3/4.9 SPENT FUEL BUILDING OPERATIONS l 3/4.9.1 DELETED l 3/4.9.2 DELETED l 3/4.9.3 DELETED l 3/4.9.4 DELETED l 3/4.9.5 DELETED l 3/4.9.6 DELETED l 3/4.9.7 CRANE TRAVEL - SPENT FUEL BUILDING .................... 3/4 9 7 l 3/4.9.8 DELETED l 3/4.9.9 DELETED l 3/4 9.10 DELETED l 3/4.9.11 WATER LEVEL SPENT FUEL P00L.......................... 3/4 9 12 l 3/4.9.12 DELETED l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L................... 3/4 9 15 3/4.9.14 SPENT FUEL P00L REACTIVITY CONDITION................ 3/4 9 16
' FIGURE 3.9 2 SPENT FUEL P0OL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2.......................................... 3/4 9 17 FIGURE 3.9 3 SPENT FUEL P0OL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3.......................................... 3/4 9 18 FIGURE 3.9 4 SPENT FUEL P00L RACK REGION LOCATIONS................. 3/4 9 19 3/4.9.15 DELETED l 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED. . . . . . . . . . . . . . . . . . . . 3/4 9 21 3/4.10 DELETED 3/4.11 DELETED l l
l HADDAM NECK III Amendment No.125.127.158.175.188 M3 TS-INDEX. DOC
INDEX l BASES l l l SECTION fgCE, ! 3/4.0 APPLICABILITY l l 3.0.1 ......................................................B 3/4 0-1 3.0.2 ......................................................B 3/4 0 2 3.0.3 DELETED ! 3.0.4 ......................................................B 3/4 0 3 l 4.0.1 ......................................................B 3/4 0 4 4.0.2 ......................................................B 3/4 0 4 i 4.0.3 ......................................................B 3/4 0 4 ! 4.0.4 ......................................................B 3/4 0 5 l 4.0.5 DELETED 4.0.6 DELETED 3/4.1 DELETED 3/4.2 DELETED 3/4.3 DELETED l 3/4.4 DELETED 3/4.5 DELETED 3/4.6 DELETED 3/4.7 DELETED l 3/4.8 DELETED l HADDAM NECK IV Amendment No.125.158,171,179.193 TS-INDEX. DOC
INDEX BASES
- SECTION EA(iE l
- l. 3/4.9 SPENT FUEL BUILDING OPERATIONS l 1
3/4.9.1 DELETED l 3/4.9.2 DELETED l 3/4.9.3 DELETED l 3/4.9.4 DELETED l 3/4.9 5 DELETED l 3/4.9.6- DELETED l 3/4.9.7 CRANE TRAVEL - SPENT FUEL BUILDING....................B 3/4 9 2 l 3/4.9.8 DELETED l 3/4.9.9 DELETED l 3/4.9.10 DELETED l 3/4.9.11 WATER LEVEL - SPENT FUEL P00L.........................B 3/4 9 3 l 3/4.9.12 DELETED l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L. . . . . . . . . . . . . . . . . . .B 3/4 9-3 l 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION................B 3/4 9 3 3/4.9.15 DELETED l 3/4.9.16 SPENT FUEL P0OL COOLING - DEFUELED....................B 3/4 9 5 3/4.10 DELETED 3/4.11 DELETED l HADDAM NECK V Amendment No. 125,127,158,171 4 97 493 TS-INDEX DOC
INDEX
~ DESIGN FEATURES SECTION PAGE 5.0 DESIGN FEATURES 5.1 DELETED l 5.2 DELETED 5.3 DELETED 5.4 DELETED 5.5 DELETED l 5.6 SPENT FUEL STORAGE 5.6.1 CR I TI CAL I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 5.6.2 DRA I NAGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 5.6.3 CAPACITY................................................... 52 5.7 DELETED l
HADDAM NECK VI Amendment No.425,175.188.193. 75-INDEX. DOC: a _. _
INDEX
-ADMINISTRATIVE CONTROLS SECTION PKE 6.0 ADMINISTRATIVE CONTROLS 6.1' RESPONSIBILITY 61 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS........................... 6 1 6.2.2 FAC I L ITY STAFF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1 TABLE 6.2 1 MINIMUM SHIFT CREW COMPOSITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3 6.3 FACILITY STAFF 00ALIFICATIONS 64 6.4 TRAINING 65 6.5 DELETED l 6.6 DELETED l
? 6.7 DELETED 6.8 DELETED l 6.9- REPORTING REQUIREMENTS 6.9.1 Routine Reports............................................ 6 5 l 6.10 DELETED l 6.11 RADIATION PROTECTION PROGRAM 66 6.12 HIGH RADIATION AREA 66 l l i 6.13' RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE '{ l-CALCULATION MANUAL (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 7 6.14 RADI0 ACTIVE WASTE TREATMENT................................ 68 ) HADDAM NECK VII Amendment No.125,155.158.170.181
-193 TS INDEX.00C . . _ _ _ _ _ __- _ ____=__-___ --___.
i 1.0 DEFINITIONS
- .The defined terms of this section appear in capitalized type and are l applicable throughout these Technical Specifications.
ACTION l 1.1 ACTION shall be that part of a Technical Specification which l prescribes remedial measures required under designated conditions. ' OPERABLE OPERABILITY 1.2 A system, subsystem, train, component, or device shall be OPERABLE or l l have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s). RADI0 ACTIVE WASTE TREATMENT SYSTEMS 1.3 RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and I solid waste systems which are required to maintain control over radioactive material in order to meet the LC0's set forth in the REMODCM. I i RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) 1.4 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall be a manual l containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead. to the highest potential radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULA-TION MANUAL (ODCH) shall be a manual containing the methodology and param-eters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. Requirements of the REMODCH are provided in Specification 6.13. I HADDAM NECK 11 Amendment No.125,140,138,158,175r 188r193 TSSEC1. DOC {
SECTIONS 3.3 AND 4.3 INSTRUMENTATION DELETED IN THEIR ENTIRETY HADDAM NECK 3/4 3-1 Amendment No. 493 ( Tsas: oot i u
i l i i i 1 I l I SECTIONS 3.7 AND 4.7 PLANT SYSTEMS l i j DELETED IN THEIR ENTIRETY ; l
)
i l l l ( l HADDAM NECK 3/4 7 1 Amendment No. 193 ! Tsas7.coc
l SECTIONS 3.9.1 THROUGH 3.9.6: l 1 SECTIONS 4.9.1 THROUGH 4.9.6: l i i FIGURE 3.9 1: AND PAGES 3/4 9 1 THROUGH 3/4 9 6 DELETED i I l I. l l [. HADDAM NECK 3/4 9 1 Amendment No. TS3S9.00C-
j SPENT FUEL BUILDING OPERATIONS l 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING l LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 1800 pounds shall be prohibited from travel l over fuel assemblies in the spent fuel pool. APPLICABILITY: With irradiated fuel assemblies in the spent fuel pool. l l ! ACTION: With the requirements of the above specification not satisfied, place the l crane load in a safe condition. I SURVEILLANCE REQUIREMENTS l 4.9.7 Administrative controls that prevent the travel of loads in excess of 1800 pounds over fuel assemblies shall be in place prior to lifting a lcad in excess of 1800 pounds. 1 i i l l l l l l HACDAM NECK 3/4 9-7 Amendment No. 125,158 l TS359.00C m_ _ _ _ _ _ _ _ _ _ _ _ _ . - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1
SECTIONS 3.9.8 THROUGH 3.9.10: SECTIONS 4.9.8 THROUGH 4.9.10: AND PAGES 3/4 9 8 THROUGH 3/4 9-11 DELETED i i L .HADDAM NECK 3/4 9 8 Amendment No. TS359.00C
t SPENT FUEL BUILDING OPERATIONS l 3/4.9.11 WATER LEVEL SPENT FUEL POOL l LIMITING CONDIIION FOR OPERATION 3.9.11 At least 20 feet of water shall be maintained over the top of l' irradiated fuel assemblies seated in the spent fuel pool racks. APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel l pool. ACTION: With the requirements of the above specification not satisfied, suspend all l movements of fuel assemblies and crane operations with loads in the spent fuel l pool areas and restore the water level to within its limit within 4 hours. l SURVEILLANCE REQUIREMENTS j l 4.9.11- The water level in the spent fuel pool shall be determined to be I at least its minimum required level at least once per 7 days when irradiated fuel assemblies are in the spent fuel pool. I l ( I i HADDAM NECK 3/4 9 12 Amendment No.-136 TS359.00C
SECTIONS 3.9.12 AND 4.9.12: AND PAGES 3/4 9-13 THROUGH 3/4 9 14 DELETED l I i 1 I 4 I HADD;Ji NECK 3/4 9 13 Amendment No. l TS359.00C o i
SPENT FUEL BUILDINidEBeIIONS l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL LIMITINGCONDIT10EE0ROPERATION _ 3.9.13 Prior to movement of a fuel assembly in the spent fuel pool, the boron concentration of the pool shall be maintained uniform and sufficient to maintain a boron concentration of greater than or equal to 800 ppm. APPLICABILITY: Whenever an irradiated fuel assembly is moved in the spent l fuel pool. ACTION: With the boron concentration less than 800 ppm, suspend the movement of all fuel in the spent fuel pool. SURVEILLANCE REQUIREMENT 4.9.13 Verify that the boron concentration is greater than or equal l to 800 ppm within 24 hours prior to any movement of a fuel assembly in the spent fue'l pool and every 72 hours thereafter during fuel j movement. l l l l I i HADDAM NECK 3/4 9 15 Amendment No.-176 T5359. DOC
l SPENT FUEL BUILDING OPERATIONS l l i 3/4.9.14 SPE.NT FilEL POOL REACTIVITY CONDITION l i LIMITING CONDITI0fLEOR_0PERATION _ , 3.9.14 The reactivity condition of the spent fuel pool shall be such that K,y is less than or equal to 0.95 at all times. APPLICABILITY: Whenever irradiated fuel is in the spent fuel pool. l ACTION: Inunediately initiate actions to correct the loading error if the placement of fuel assemblies does not meet the requirements of Figure 3.9-2, Figure 3.9 3. and Figure 3.9 4. SURVEILLANCE REQUIREMENT 4.9.14 Ensure that all fuel assemblies to be placed in the spent fuel pool are within the enrichment and burn up limits of Figure 3.9-2 (Region 2) ard Figure 3.9 3 (Region 3) by checking the assembly's design and burn up documentation. Region locations are shown in Figure 3.9 4. 1 HADDAM NECK 3/4 9 16 Amendment No.U 5d 88 TS359. DOC _w
1 l THIS PAGE INTENTIONALLY LEFT BLANK l
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1 I 1 I l l l l l. HADDAM NECK 3/4 9 20 Amendment No. I l Tsas9. Doc
SPENT FUEL BUILDING OPERATIONS l 3/4.9.16 SPENT FUEL POOL COOLING DEFUELED l LIMITING CONDLTION FOR OPERATION j 3.9.16 The spent fuel pool coolant temperature shall be maintained at ! less than or equal to 150 degrees F. i l j; APPLICABILITY: Whenever irradiated fuel assemblies are stored in the spent fuel pool. l ACTION: ! l With the spent fuel pool coolant temperature not within limit:
- a. Immediately initiate action to restore the spent fuel pool coolant l temperature to within limit, and
- b. Immediately verify that a spent fuel pool makeup water source is l available, and
! c. Within 7 days, restore the spent fuel pool coolant temperature to within the limit.
- j. SURVEILLANCE REQUIREMENTS
! 4.9.16 At least once per 24 hours, verify that the spent fuel pool coolant temperature is less than or equal to 150 degrees F. l l HADDAM NECK 3/4 9 21 Amendment No.-193 TS359. DOC
I i
- 1. l i
i l I l l l L l 1 ,, 1 l' I ? l SECTIONS 3.11 AND 4.11 i i ! RADI0 ACTIVE EFFLUENTS i L DELETED IN THEIR ENTIRETY i i 1 1 ' L HADOAM NECK 3/4 11 1 Amendment No. 493 , T53511.00C' I l t- - - .- - .-- - _ ___ _ _ -- __ _ _ _ _ _ _ u
[ i l I i i BASES 3/4.3 INSTRUMENTATION DELETED IN THEIR ENTIRETY I l I i l J HADDAM NECK B3/4 3-1 Amendment No. 193 TSB353.00C
7-. I 1 i l BASES 3/4.7 PLANT SYSTEMS DELETED IN THEIR ENTIRETY HADDAM NECK 83/4 7 1 Amendment No. 493 TSB357.00C
3/4.9 SPENT FUEL BUILDING OPERATIONS l fBSEs 3/4.9.1 DELETED l 3/4.9.2 DELETED l 3/4.9.3 DELETED l 3/4.9.4 DELETED l 3/4.9.5 DELETED l 3/4.9.6 DELETED l 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING l The restriction on ,ovement of loads in excess of the weight of a fuel and l control rod assembly and associated handling tool over other fuel assemblies in the spent fuel pool ensures that in the event this load is dropped: (1) the l activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the spent fuel pool racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analysis. The restriction also ensures that the effects of any load drop on the spent fuel pool structural integrity is enveloped by the load drop analysis (Holtec Report HI 941225 Rev. 0, " Accident Analysis Report for CY Spent Fuel Racks," I Dr. Yu Wang, Item 11. Holtec Project 40264) performed for License Amendment i f 188.
]
3/4.9.8 DELETED l 3/4.9.9 DELETED l l 3/4.9.10 DELETED l ! 3/4.9.11 WATER LEVEL SPE U FUEL POOL l The restrictions on minimum water level ensure that sufficient water inventory is available, so that in the event of a complete loss of forced cooling, the time to boil is greater than 50 hours (as of December 1997), based on an initial spent fuel pool temperature of 150 degrees F and no evaporative cooling. HADDAM NECK B3/4 9 1 Amendment No.125,158,175,188.193 TSB359. DOC
SPENT FUEL BUILDING OPERATIONS l BASES 3/4.9.12 DELETED l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P0OL The limitations of this specification ensure that, in the event of any fuel handling accident in the spent fuel pool, K rr will remain s 0.95. 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION The limitations described by Figures 3.9 2, 3.9 3, and Figure 3.9 4 ensure that the reactivity of fuel assemblies introduced into the spent fuel pool racks, with no credit taken for soluble boron in the spent fuel pool, are conservatively within the assumptions of the safety analysis. 3/4.9.15 DELETED l 3/4.9.16 SPENT FUEL POOL COOLING DEFUELED The primary basis for 150 degrees F is to limit thermal stresses on the spent fuel pool concrete structures due to the differential temperature across the { internal and exterior surfaces of the walls and floor. The basis is further discussed in License Amendment No. 188. As of May 1998, the spent fuel heat load was calculated to be less than 2.3E+06 BTU /hr. Each heat exchanger has the capability of removing this heat i load. One spent fuel pool heat exchanger and one spent fuel pool cooling pump, that can be operated intermittently, is sufficient to remove the decay heat load. Assuming no. forced or evaporative cooling, the calculated May 1998 heatup rate is approximately 1.2 degrees F/hr. Thus, in the event of a complete loss of forced cooling and assuming an initial spent fuel pool temperature of 150 degrees F, the time to boil, assuming no evaporative cooling, is greater than 50 hours. Therefore, sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory. 1 HADDAM NECK B3/4 9 2 Amendment No. 125.175.188,193 l TSB3S9.00C l _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ J
BASES 3/4.11 RADI0 ACTIVE EFFLUENTS DELETED IN THEIR ENTIRETY l l l l l l HADDAM NECK B3/4 11 1 Amendment No. 493 l l . rssasu.mc L.___._
F 1 1
\
SA__ DESIGN FEATURES j 1 \ l 5.1 DELETED l L2 DELETED l 5.3 DEL ETED l l 5.4 DELETED l 5.5 DELETED l I l l HADDAM NECK 51 Anendment No. 42h493 TSSEC5.00C , l 1
DESIGN FEATURES S.6 SPENT FUEL STORAGE CRITICALITY I 5.6.1 The spent fuel storage racks are made up of 3 regions which are - designed and shall be maintained with: !
- a. For Region 1, a nominal 10.98 inch (East / West) and a nominal 10.142 inch (North / South) center-to center distance including neutron absorber surrounding each assembly to ensure a K,rr less than or equal to .95 when flooded with unborated water. Fuel with a maximum nominal enrichment of 5 weight percent U 235, without regard for fuel burnup, may be stored in this region. The location of Region 1 within the Spent Fuel Pool is shown in Figure 3.9 4.
- b. For Region 2, a nominal 9.00 inch center to center distance including neutron absorber surrounding each assembly to ensure a K,rr less than or equal to .95 when flooded with unborated water.
Storage of fuel in Region 2 must be in accordance with the requirements of Specification 3.9.14. The location of Region 2 within the Spent Fuel Pool is shown in Figure 3.9 4.
- c. For Region 3, a nominal 10.75 inch center-to center distance to ensure a Kerr less than or equal to .95 when flooded with unborated water. No credit is taken for the neutron absorber contained within the racks of this region. Storage of fuel in Region 3 must be in accordance with the requirements of Specification 3.9.14.
The location of Region 3 within the Spent Fuel Pool is shown in Figure 3.9 4. I L DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 27.0 feet MSL. l j j CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 224 storage locations in Region 1, 560 storage locations in Region 2, and 696 storage locations in Region 3 for a total of 1480 storage locations. HADDAM NECK 52 Amendment No. 425 442,175,188,193 l TSSEC5,00C
-__ _-________________________- ____ a
fLO ADMINISTRATIVE CONTROLS 6.4 TRAINING A retraining and replacement training program for the Certified Fuel Handlers shall be maintained under the direction of the Unit Director. A retraining and replacement training program for the facility staff shall be maintained under the direction of the Unit Director. The Unit Director has the overall l responsibility for the implementation of the Training Program. 6.5 DELETED l 6.6 DELETED l 6.7 DELETED l 6.8 DELETED l 6.9 REPORTING REQUIREMENTS ROUTINE REPORTS , 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U. S. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, with one copy to the appropriate NRC Regional Office, and one copy to the appropriate NRC Resident Inspector. ANNUAL OCCUPATIONAL RADIATION EXPOSURE REPORT 6.9.1.1 Routine Annual Occupational Radiation Exposure Reports covering I the activities of the facility during the previous calendar year shall be submitted prior to March 1 of each year. The Report shall include a tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions * (e.g., decontamination and decommissioning, surveillance, routine maintenance, special maintenance (describe maintenance), waste processing and spent fuel l movement). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge i measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
- This tabulation supplements the requirements of Section 20.2206 of l 10 CFR Part 20.
1 HADDAM NECK 65 Amendment No.125,135,155,158,1 % I TSSEC6.00C l
I 6.0 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.2 Routine Annual Radiological Environmental Operating Reports covering the activities of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The Report shall include that information delineated in the REH0DCM. ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.3 Routine Annual Radioactive Effluent Release Reports covering the activities of the facility during the previous calendar year shall be submitted prior to May 1 of each year. The Report shall include that information delineated in the REH0DCM. Any changes to the REH0DCM shall be submitted in the Report. 6.10 DELETED l 6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirement of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 Pursuant to paragraph 20.1601(c) of 10 CFR Part 20, in lieu of the
" control device" or " alarm signal" required by paragraph 20.1601, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is greater than 100 mR/h but equal to or less than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or l
personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in l high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following plant radiation protection procedures ) for entry into such high radiation areas. Any individual or group of i individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: l l HADDAM NECK 66 Amendment No.-125,l'S,153.155.181. ! l N ! TSSEC6.00C
6.0 ADMINISTRATIVE CONTROLS
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is res)onsible for providing positive control over the activities within ;he area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Manager in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radia': ion levels greater than 1000 mR/h at 30 cm (12 in.) from the radiation source or from any surface which the radia-tion penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or health physics supervision. Doors shall remain locked except during periods of access by aersonnel under an approved RWP which shall specify the dose rate levels in tie immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation arotection procedures to provide control over the activit es being performed within the area. positive exposure For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device or continually guarded. 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) Section I, RADIOLOGICAL EFFLUENTS MONITORING MANUAL (REMM), shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radf onuclides released as a result of facility operation. It shall also specify operating guidelines for RADIOACTIVE WASTE TREATMENT SYSTEMS and report content. Section II, the OFFSITE DOSE CALCULATION MANUAL (0DCM), shall describe the ! methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints. l l l HADDAM NECK 67 Amendment No. 125,155.158,170,191 TSSEC6. DOC l
6.0 ADMINISTRATIVE CONTROLS , Changes to the REM 0DCM:
- a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program. This documentation shall contain: l
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after approval of the Unit Director.
l
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REMM or ODCM, as anropriate, as a part of or concurrent with the Annual Radioactive E"luent Report for the period of the re) ort in which any change was made. Each change shall be identifiec by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.14 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT SYSTEMS utilizing the guidance provided in the REMODCM. The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance with the Process Control Program to process wet radioactive wastes to meet shipping and burial ground requirements. i l HADDAM NECK 68 Amendment No.4 & l65,158,170, 19h493 TSSEC6. DOC
Docket No. 50-213 CY-98-003 Attachment 3 Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Description Of Changes t 1 l J
3 U. S. Nuclear Regulatory Commission l CY-98-003/ Attachment 3/Page 1
'l General Reason For The Changes I 1
in a letter dated December 5,1996,W the Connecticut Yankee Atomic Power Company (CYAPCO) informed the NRC that the Board of Directors of CYAPCO had decided to permanently cease operations at the Haddam Neck Plant (HNP) and that the fuel had been permanently removed from the reactor. The majority of the changes proposed reflect the limitations and requirements appropriate j to the present defueled configuration of the plant. The primary reason for this change is to ' simplify and to improve clarity by eliminating the remaining non-applicable material in the current Technical Specifications. The objective is a clear and concise document for maintaining the spent fuel in the spent fuel pool for storage. When this is the reason for a I change, the phrase "Defueled Condition" will signify that the above rationale is applicable, in addition, because this proposed amendment is affecting most of the remaining pages in the Technical Specifications, some changes were made to correct typographical errors or grammar; or to provide consistent terminology, consistent format, clarity, or brevity; or to update the Index (Table of Contents) to reflect the proposed changes. When this is the reason for a change, the phrase " Editorial Changes" will signify that this rationale is j applicable. ' i Finally, some of the changes discussed herein are proposed for other reasons. When this ) is the case, the specific reason will be provided. 1 I FACILITY OPERATING LICENSE )
. change
- 1. Delete:
"This license is effective as of the date of issuance and shall expire at midnight, June 29,2007."
Replace with: l "This license is effective as of the date of issuance and authorizes ownership l and possession of this facility until the Commission notifies the licensee in ! writing that the license is terminated. The licensee shall: l (1) CYAPCO Letter B16066 from T. C. Feigenbaum to the U. S. Nuclear Regulatory Commission, " Certifications Of Permanent Cessation Of Power Operation And That Fuel Has Been Permanently Removed From The Reactor," dated December 5,1996. I _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ l
U. S. Nucisar Regulatory' Commission - CY-98-003/ Attachment 3/Page 2 1
- 1. 'Take actions necessary to decommission and decontaminate this 1 facility and continue to maintain this facility, including, where applicable, the storage, control and maintenance of the spent fuel, in a j safe co.idition; and l 6
L 2. Conduc activities in accordance with all other restrictions applicable to I this faci'ity in accordance with NRC regulations and the specific provisions of this 10CFR50 facility license." Beason L 1. Defueled Condition ! Basis I i 1. The revision to the license expiration reflects the requirements of 10CFR50.51(b). i Change i 2. Delete License Condition 2.C(6), Integrated Implementation Schedu!e, and change condition 2.C(7), Fuel Movement, to 2.C(6). Reason l
- 2. The license condition was effective for three years from the date of issuance of Amendment 183, which was February 23,1995. This change was previously requested by CYAPCO letter CY-97-031, dated April 18,1997.
Basit l' ,
- 2. The expiration date for the license condition has passed.
TECHNIC.AL SPECIFICATIONS
- i. . >
! , GENERAL ; ! .Changet
- 1. Where multiple pages in sequence have been deleted, a single page has been used as a replacement. This includes replacing pages that already denote deleted material (this portion of the replacement is editorial). These new single pages denote what section(s), table (s), figure (s) and/or page(s) have been deleted. In addition, minor typographical errors were corrected.
lo-
l U. S. Nucl ar Regulatory Commission
- CY-98-003/ Attachment 3/Page 3 l
l 2. Some materialis being transferred to the Haddam Neck Plant Updated Final Safety Analysis Report (UFSAR), the Connecticut Yankee Quality Assurance Program (CYQAP), the Radioactive Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM) or the Technical Requirements Manual j (TRM). This material will be relocated verbatim with the exception of section, l table and reference numbers. These will be changed to reflect the format of the UFSAR, CYQAP, REMODCM or the TRM.
- Beason Defueled Condition, Editorial Changes, Administrative Letter 95-06, Generic Letter 95-10 and NUREG-1431.
Basis
- 1. For clarity and brevity.
- 2. The movement of the material to the CYQAP or the TRM is in accordance with Administrative Letter 95-06,<2; Generic Letter 95-10,* and is consistent with the Standard Technical Specifications for Westinghouse Plants
, (WOG STS) provided in NUREG-1431.W INDEX Chanaes
- 1. Revise according to the changes described herein.
- 2. Retain numbering sequences.
- 3. The index was repaginated.
Reason Editorial Changes. (2) NRC Administrative Letter 95-06, " Relocation of Technical Specification Administrative Controls Related To Quality Assurance," dated December 12,1995. (3) NRC Generic Letter 95-10, " Relocation of Selected Technical Specifications Requirements Related to Instrumentation," dated December 15,1995. (4) NUREG-1431, " Standard Technical Specifications, Westinghouse Plants, Specifications," Office of Nuclear Reactor Regulation, NRC, Volume 1, Revision 1, dated April 1995. 1
i U. S. Nucitar Regulatory Commission { CY-98-003/ Attachment 3/Page 4 i i ana <
- 1. The Index must be revised to reflect the changes made to the Technical Specification Sections identified below. The following revisions were ;
implemented: 1 ! . Deleted sections are indicated in the Index by " DELETED". i -
. If all the subsections of a Technical Specification are deleted, then only the major section is shown to be deleted. The deleted l 1
subsections are removed from the Index.
. If a Technical Specification table or figure is deleted, then the table or
. figure is removed from the Index.
. Tables and figures that are retained, continue to be listed in the Index.
- 2. Numbering sequences were retained to preclude the need to renumber cross-references and preclude the need to revice procedure references to the Technical Specifications.
- 3. Reduced the number of pages with no loss of information. l
'l 1.0 DEFINITIONS Changes
- 1. The following definitions have been retained:
1.1 ACTION 1.17 OPERABLE - OPERABILITY l 1.23 RADIOACTIVE WASTE TREATMENT SYSTEMS 1.24 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) l However in the definition for RADIOACTIVE WASTE TREATMENT SYSTEMS, make the following editorial change: Change "those specifications." to "the REMODCM." The definitions will also be renumbered as follows: 1.1 ACTION l 1.2 OPERABLE - OPERABILITY 1.3 RADIOACTIVE WASTE TREATMENT SYSTEMS ( 1.4 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) i i i
U. S. Nucl:ar Regulatory Commission i CY-98-003/ Attachment 3/Page 5 l o j A;l other definition numbers and " DELETED" statements will be eliminated.
- 2. The following definitions have been deleted:
1.2 ANALOG CHANNEL OPERATIONAL TEST ; 1.4 CHANNEL CALIBRATION ' 1.5 ' CHANNEL CHECK 1.8 CORE ALTERATION 1.12 FREQUENCY NOTATION 1.15 MEMBER (S) OF THE PUBLIC 1.18 OPERATIONAL MODE - MODE 1.26 REPORTABLE EVENT , 1.27 RHR LOOP 1.29 SITE BOUNDARY I 1.30 SOURCE CHECK ,
- 3. Delete Tables 1.1 and 1.2
- 4. The section was repaginated. !
He.a10D Defueled Condition, Editorial Changes, Generic Letter 89-01, Generic Letter 95-10 and NUREG-1431. Basis ' l 1. Tlie definitions retained are referenced by the remaining Technical Specifications. S nce there are only four definitions remaining, they have been renumbered. The editorial change to the definition for RADIOACTIVE WASTE TREATMENT SYSTEMS reflects where the LCO's will be located. l 2. The definitions deleted are not referenced by the remaining Technical l_ Specifications. Those definitions needed to support requirements being L transferred to the UFSAR. TRM, CYQAP, and/or the REMODCM, will be l transferred to the UFSAR, TRM, the CYQAP and/or the REMODCM. l
- 3. Table 1.1 (" Frequency Notation"), is not used by the remaining Technical
- Specifications. However, since requirements being transferred to the TRM l- do use this notation, Table 1.1 will be transferred to the TRM. Since there are no longer my MODES associated with the defueled plant, Table 1.2
("O,ncrational Modes") is no longer necessary.
- 4. Reduced the number of pages with little or no information.
I i
- l. U. S. Nucl ar Regulatory Commission L CY-98-003/ Attachment 3/Page 6 3/4.3 INSTRUMENTATION Changes l 1. Delete the entire subsection, including associated tables, figures and bases.
- 2. The following are transferred to the TRM:
L 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUMENTATION TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS B3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The following are transferred to the REMODCM: 3/4.3.3.7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE 3.3-9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION j l TABLE 4.3-7 RADIOACTIVE LIQUID EFFLUENT MONITORING ' INSTRUMENTATION SURVEILLANCE REQUIREMENTS ' 3/4.3.3.8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE 3.3-10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l B3/4.3.3.7 RADIOACTIVE LIQUID EFFLUENT MONITORING , INSTRUMENTATION I [ B3/4.3.3.8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
U. S. Nucisar Regulatory Commission CY-98-003/ Attachment 3/Page 7 Reason Defueled Condition, Editorial Changes, Generic Letters 89-01 and 95-10, and NUREG-1431. Basis
- 1. With the material being transferred to the TRM and REMODCM this Section is no longer needed.
- 2. In accordance with the guidance in Generic Letter 95-10 and for consistency with NUREG-1431, these sections are transferred to the TRM where they will be controlled by CYAPCO procedures. Any changes to the TRM require a review be conducted in accordance with the requirements of 10CFR50.59,
- 3. In accordance with the guidance in Generic Letter 89-01, the radioactive effluent monitoring instrumentation is transferred to the REMODCM, Any changes to the REMODCM require a review conducted in accordance with the requirements of Technical Specification 6.13.a.2), as well as the 10CFR50.59 review required by CYAPCO procedures.
3/4.7 PLANT SYSTEMS Chanaes
- 1. Delete the entire subsection, including associated tables, figures and bases.
- 2. The following are transferred to the TRM:
3/4.7.5 SEALED SOURCE CONTAMINATION B3/4.7.5 SEALED SOURCE CONTAMINATION Reason Defueled Condition, Generic Lettor 95-10 and NUREG-1431. Basis l
- 1. With the material being transferred to the TRM, this Section is no longer needed.
- 2. In accordance with the guidance in Generic Letter 95-10 and for consistency with NUREG-1431, these sections are transferred to the TRM where they will l
i l U. S. Nucl:ar Regulatory Commission CY-98-003/ Attachment 3/Page 8 be controlled by CYAPCO procedures. Any changes to the TRM require a review be conducted in accordance with the requirements of 10CFR50.59. 3/4.9 REFUELING OPERATIONS 1 Changes
- 1. The following are retained with noted changes:
3/4.9 REFUELING OPERATIONS Change the section title to " SPENT FUEL BUILDING OPERATIONS". 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE BUILDING Change the subsection title to " CRANE TRAVEL - SPENT FUEL l BUILDING" Change in 3 places, "1650" to "1800". Change in two places, "the storage pool." to "the spent fuel pool." In APPLICABILITY change " fuel assemblies" to " irradiated fuel assemblies'. Delete ACTION "b." l 3/4.9.11 WATER LEVEL - STORAGE POOL Delete ACTION "b." Change the subsection title to " WATER LEVEL - SPENT FUEL POOL". In Subsection 3.9.11, change "the storage racks." to "the spent fuel pool racks." In APPLICABILITY, change "the storage pool." to "the spent fuel pool." In ACTION "a." change "the fuel storage areas" to "the spent fuel pool area". In Subsection 4.9.11, change "the storage pool" to "the spent fuel pool", change " depth" to
" level" and change "the fuel storage pool." to "the spent fuel pool."
3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL in APPLICABILITY, change "a fuel assembly" to "an irradiated fuel assembly". In Subsection 4.9.13, change "every 72 hours thereafter." to "every 72 hours thereafter during fuel movement." 3/4.9.14 SPENT FUEL POOL-REACTIVITY CONDITION in Subsection 3.9.14 change " Reactivity Condition" to " reactivity condition" and change "less-than-or-equal-to" to "less than or equal to". In APPLICABILITY, change " fuel" to " irradiated fuel". FIGURE 3.9-2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2 l No change. FIGURE 3.9-3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3 No change.
U. S. Nuclser Regulatory Commission CY-98-003/ Attachment 3/Page 9 FIGURE 3.9-4 SPENT FUEL POOL RACK REGION LOCATIONS No change. B3/4.9.7 _ CRANE TRAVEL - SPENT FUEL STORAGE BUILDING Change the subsection title to " CRANE TRAVEL - SPENT FUEL BUILDING". Change " excess of the nominal weight" to " excess of the weight". Change "the storage pool." to "the spent fuel pool." Change "the storage racks" to "the spent fuel pool racks". J Insert a second paragraph stating:
"The restriction also ensures that the effects of any load drop on the spent fuel pool structural integrity is enveloped by the load drop analysis (Holtec Report HI-941225, Rev. O, " Accident Analysis Report for CY Spent Fuel Racks," Dr. Yu Wang, item 11, Holtec Project ,
40264) performed for License Amendment 188." ' B3/4.9.10 and WATER LEVEL - REACTOR VESSEL AND B3/4.9.11 STORAGE POOL i Delete "B3/4.9.10 and". Change the subsection title to " WATER LEVEL - SPENT FUEL POOL". Replace the paragraph with: "The restrictions on minimum water level ensure that sufficient water inventory is available, so that in the event of a complete loss of forced cooling, the time to boil is greater than 50 hours (as of December 1997), based on an initial spent fuel pool temperature of 150 degrees F and no evaporative cooling." B3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL No change. B3/4.9.14 SPENT FUEL POOL-REACTIVITY CONDITION Cnange " spent fuel racks" to " spent fuel pool racks" and change "the pool" to "the spent fuel pool". FIGURE B3/4.9-1 SPENT FUEL POOL DECAY HEAT LOADS Delete Figure.
- 2. The following were deleted, including associated figures, tables and bases:
3/4.9.1 BORON CONCENTRATION 3/4.9.2 INSTRUMENTATION l 3/4.9.3 DECAY TIME
. U. S. Nuclocr R:gulatory Commission CY-98-003/ Attachment 3/Page 10 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4.9.5 COMMUNICATIONS 3/4.9.6 MANIPULATOR CRANE 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3/4.9.9 CONTAINMENT PURGE SUPPLY, PURGE EXHAUST, AND PURGE EXHAUST BYPASS ISOLATION SYSTEM 3/4.9.10 WATER LEVEL - REACTOR VESSEL 3/4.9.12 FUEL STORAGE BUILDING AIR CLEANUP SYSTEM 3/4.9.15 SPENT FUEL POOL COOLING Reasons and Bases
- 1. For these subsections, the changes are discussed below:
3/4.9 Refueling Operations (now titled: Spent Fuel Building Operations) The change is to reflect the fact that the plant will no longer conduct refueling operations since the plant has permanently ceased operations and the reactor has been permanently defueled. 3/4.9.7 Crane Travel- Spent Fuel Storage Building (now titled: Crane Travel - Spent Fuel Building) The analysis for a 2300-pound fuel handling accident was provided to the NRC in CYAPCO's March 21,1995 submittal
- and was accepted by the NRC in a letter dated January 22,1996.* However, this i 2300-pound value was based on possible future consolidation of fuel
! assemblies if the HNP operated past its 40-year life. Since, this j: scenario is no longer possible, the proposed 1800-pound value limits l' (5) CYAPCO Letter B15136 from J. F. Opeka to the U. S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications Spent Fuel Pool Capacity Expansion," dated March 31,1995. (6) NRC letter from A. B. Wang to R. E. Busch, " Issuance of Amendment 188 i (TAC No. M91976),' dated January 22,1996. 1
U. S. Nucl=r Reguintory Commission 1 e CY-98-003/ Attachment 3/Page 11 I the existing spent fuel assembly / control rod assembly / handling tool { weight. The change from 1650-pound limit to the 1800-pound limit { eliminates the confusion over the nominal weight discussed in th:., j Basis and provides some margin for drag forces when lifting an assembly. The proposed change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fuel within I the spent fuel pool. ACTION "b." refers to deleted Specification 3.0.3. The remaining changes are editorial and provide a consistency in ! terminology. 3/4.9.11 Water Level- Storage Pool (now titled: Water Level- Spent Fuel Pool) ; i ACTION "b." refers to deleted Specification 3.0.3. The remaining changes are editorial and provide a consistency in terminology. 3/4.9.13 Movement Of Fuelin Spent Fuel Pool The changes provide further clarification that the verification of boron ; concentration will only take place during the movement of spent fuel. 3/4.9.14 Spent Fuel Pool - Reactivity Condition ' The changes are editorial and provide a consistency in terminology. ; B3/4.9.7 Crane Travel- Spent Fuel Storage Building (now titled: Crane Travel - Spent Fuel Building) i l The deletion of the word " nominal" eliminates the confusion over ! weight limits. The remaining changes are editorial and provide a consistency in terminology. B3/4.9.10 and Water Level- Reactor Vessel And B3/4.9.11 Storage Pool (now numbered: B3/4.9.11) (now titled: Water Level- Spent Fuel Pool) Subsection 3/4.9.10 has been deleted, thus its Bases is no longer needed. The change to the title is editorial and provides a consistency in terminology. The original Bases was concerned with radiolodine removal. This is no longer a concern. The plant was shutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days),1-129 (half-life ~1.6E7 years), and Kr-85 (half-life ~10.8 years), the spent fuel inventory of the , dose-contributing radioactive iodine and noble gas isotopes has
f i i ) U. S. Nucirr Regulatory Commission CY-98-003/ Attachment 3/Page 12 l decayed more than 20 half-lives since shutdown (i.e., less than 0.0001% of the onginal amount remains). In addition, the definition for ;
- " Dose Equivalent 1-131" (" Standard Technical Specifications, j Westinghouse Plants," NUREG-1431) does not include 1-125 and l-129 in the dose assessm-ent due to their negligible spent fuel {
inventory. Except for Kr-85, the other noble gas nuclides that , contribute to a whole body dose have also decayed to a negligible { amount. CYAPCO has performed fuel handling and cask drop accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.1M) which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The revised Bases reflects that the current predominate concern for spent fuel poo' water level is that sui 5cient water inventory be maintained for cooling purposes in the event of a !oss of forced i cooling. f i B3/4.9.14 Spent Fuel Pool--Reactivity Condition The changes are editorial and provide a consistency in terminology.
- 2. These subsections are associated with fuel in the reactor vessel and/or power operation of the facility. Because the plant has permanently ceased operations and the reactor has been permanently defueled, these !
subsections are no longer required. Specifically: l 3/4.9.1 Boron Concentration i The purpose of this specification was to ensure that the reactor i remained subcritical during core alterations and that boron concentration was un'iform during core alterations. The plant has ; permanently ceased operations and the reactor has been permanently l defueled, core alterations will no longer occur because a licente l condition will prohibit movement of fuel back into the containment. l Therefore, this specification is no longer needed. l (7) Calculation XX-XXX-60RA, Rev.1, " Radiological Assessment of a Spent Fuel ' i Shipping Cask Drop in the CY Spent Fuel Pool," provided in Attachment 5 of ; } CYAPCO Letter CY-97-006, from T. C. Feigenbaum, to the U. S. Nuclear l l Regulatory Commission, " Proposed Revision To Operating License And Technical Specifications Defueled Operating License And Technical Specifications," dated l May 30,1997. 1 l i
U. S. Nucirr Regulatory Commission CY-98-003/Attachrnent 3/Page 13 3/4.9.2 Instrumentation The purpose of this specification was to ensure redundant monitoring capability of reactor core reactivity conditions during core alterations. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations will no longer occur because the certification of cessation of operations W prohibits movement of fuel back into the containment. Therefore, this specification is no longer needed. 3/4.9.3 Decay Time The purpose of this specification was to ensure that sufficient time elapsed before core alterations to allow for radioactive decay of short-lived fission products. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations will no longer occur because a license condition will prohibit movement of fuel back into the containment. Therefore, this specification is no longer needed. 3/4.9.4 Containment Building Penetrations The purpose of this specification was to ensure that any radionuclides releases to the environment resulting from fuel damage occurring during core alterations or movement of irradiated fuel will be limited. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations and/or fuel movement inside containment will no longer occur because a license condition will prohibit movement of fuel back into the containment. Therefore, this specification is no longer needed, in addition, containment penetrations are not required to be operable during decommissioning because the limiting accident, a resin liner accident, does not credit confinement or filtration of particulate. This accident bounds a materials handling accident inside containment. 3/4.9.5 Communications The purpose of this specification was to ensure that refueling l personnel are promptly informed of changes to the plant status or reactivity changes during core alterations or movement of irradiated fuelin the containment. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations will ( ' no longer occur because a license condition will prohibit movement of l
U. S. Nucl:ar Regulatory Commission i CY-98-003/ Attachment 3/Page 14 ' fuel back into the containment. Therefore, this specification is no longer needed. l 3/4.9.6 Manipulator Crane The purpose of this specification was to ensure that the manipulator crane is used correctly and that load limits are not exceeded during refueling operations inside containment. The plant has permanently ceased operations and the reactor has been permanently defueled, refueling operations inside containment have permanently ceased because a license condition will prohibit movement of fuel back into the containment. Therefore, this specification is no longer needed. 3/4.9.8 Residual Heat Removal and Coolant Circulation The purpose of this specification was to ensure that there was sufficient cooling capacity to maintain the reactor coolant system below 140 F and that boron stratification was prevented. The plant has permanently ceased operations and the reactor has been permanently defueled, residual heat removal and boron mixing in the reactor vessel is no longer needed. Therefore, this specification is no longer needed. 3/4.9.9 Containment Purge Supply, Purge Exhaust, and Purge Exhaust Bypass isolation System The purpose of this specification was to ensure that the containment purge system can be shut down upon the detection of high radiation levels during core alterations or movement of irradiated fuel in the containment. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations and/or fuel movement inside containment will no longer occur because a license condition will prohibit movement of fuel back into the containment. Therefore, this specification is no longer needed. In addition, the containment purge system is not required to be operable during decommissioning because the limiting accident, a resin liner accident, does not credit confinement or filtration of particulate. This accident bounds a materials handling accident inside containment. f 3/4.9.10 Water Level- Reactor Vessel The purpose of this specification was to ensure that there is sufficient water in the reactor vessel during the movement of fuel assemblies or L -
U. S. Nuciscr Regulatory Commission CY-98-003/ Attachment 3/Page 15 control rods in the containment. The plant has permanently ceased operations and the reactor has been permanently defueled, core alterations and/or fuel movement inside containment will no longer occur because a license condition will prohibit movement of fuel back into the containment. Therefore, this specification is no longer needed. 3/4.9.12 Fuel Storage Building Air Cleanup System This specification was concerned with radiciodine removal to prevent the radiological dose consequences from radioactive iodine. This is no longer a concern. The plant was shutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days),1-129 (half-life ~1.6E7 years), and Kr-85 (half-life ~10.8 years), the spent fuelinventory of the dose-contributing radioactive iodine and noble gas isotopes has decayed more than 20 half-lives since shutdown (i.e., less than 0.0001% of the original amount remains). In addition, the definition for" Dose Equivalent 1-131" (" Standard Technical Specifications, Westinghouse Plants," NUREG-1431) does not include 1-125 and 1-129 in the dose assessment due to their negligible spent fuel inventory. Except for Kr-85, the other noble gas nuclides that contribute to a whole body dose have also decayed to a negligible amount. CYAPCO has performed fuel handling and cask drop accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.1m) which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The requirement to maintain the HEPA filters will be placed in the TRM. These requirements will meet those stated in ANSI /ANS-57.7, 1988. i 3/4.9.15 Spent Fuel Pool Cooling Technical Specification 3/4.9.15 has been deleted and replaced by a new Technical Specification,3/4.9.16, SPENT FUEL POOL COOLING
- DEFUELED,* that is applicable to the defueled condition of the Haddam Neck Plant.
(8) NRC Letter from T. L. Fredrichs, to R. A. Mellor, " Issuance Of Amendment No.193 Facility Operating License No. DPR Connecticut Yankee Atomic Power Station (TAC No. M98997)," dated June 30,1998. l L_ __ - - _ - - _ - - - - - - - - - - . . . - - - - - - - - - - -
U. S. Nucis r Regulatory Commission CY-98-003/ Attachment 3/Page 16 j 3/4.11 RADIOACTIVE EFF1 UEMIS Changes
- 1. Delete the entire subsection, including associated tables, figures and bases.
- 2. The following are transferred to the REMODCM:
3/4.11.1.1 LIQUID EFFLUENTS - CONCENTRATION 3/4.11.1.2 LIQUID EFFLUENTS - DOSE, LIQUIDS 1 3/4.11.2.1 GASEOUS EFFLUENTS - DOSE RATE 3/4.11.2.2 GASEOUS EFFLUENTS - DOSE-NOBLE GASES 3/4.11.2.3 GASEOUS EFFLUENTS - DOSE, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES 3/4.11.3 TOTAL DOSE i B3/4.11.1.1 LIQUID EFFLUENTS - CONCENTRATION B3/4.11.1.2 LIQUID EFFLUENTS - DOSE, LIQUIDS B3/4.11.2.1 GASEOUS EFFLUENTS - DOSE RATE ) B3/4.11.2.2 GASEOUS EFFLUENTS - DOSE, NOBLE GASES B3/4.11.2.3 GASEOUS EFFLUENTS - DOSE, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES B3/4.11.3 TOTAL DOSE Reason Defueled Condition, Generic Letter 89-01 and NUREG-1431. Basis
- 1. With the material being transferred to the REMODCM, this Section is no longer needed.
i l __-____________________A
U. S. Nuclser R:gulatory Commission l CY-98-003/ Attachment 3/Page 17
- 2. In accordance with the guidance in Generic Letter 89-01 and for consistency with NUREG-1431, these sections are transferred to the REMODCM where they will be controlled by CYAPCO procedures. Any changes to the REMODCM require a 10CFR50.59 applicability review be conducted in accordance with CYAPCO procedures.
5.0 DESIGN FEATURES Changes
- 1. The following subsections and associated figures are deleted.
5.1 SITE 5.5 METEOROLOGICAL TOWER LOCATION Reason Duplication of information appearing in the UFSAR. Basis
- 1. Subsection 5.1.1, EXCLUSION AREA, is shown on UFSAR Figure 2.1-3 and described in UFSAR Section 2.1.2.1. Subsection 5.1.2, LOW POPULATION ZONE, is defined in UFSAR Section 2.1.3.4. Therefore these subsections can be deleted from the Technical Specifications.
Since the Meteorological Instrumentation is being relocated to the TRM and the tower's location is shown on UFSAR Figure 2.1-5, Subsection 5.5, METEOROLOGICAL TOWER LOCATION, can be deleted from the Technical Specifications. l
l U. S. Nucl=r Regulatory Commission CY-98-003/ Attachment 3/Page 18 i 6.0 ADMINISTRATIVE CONTROLS Changes
- 1. Delete ".. and shall meet or exceed the requirements and recommendations {
of Section 5.5 of ANSI N18.1-1971." from Section 6.4, TRAINING.
- 2. Delete "... review and acceptance by PORC and the ..." from subsection !
6.13.b. f
- 3. Delete the following from the Technical Specifications: i 6.6 REPORTABLE EVENT ACTION 6.9.2 SPECIAL REPORTS
- 4. The following are deleted from the Technical Specifications and transferred to the CYQAP:
6.5 REVIEW AND AUDIT 6.8 PROCEDURES AND PROGRAMS 6.10 RECORD RETENTION
- 5. 6.9 REPORTING REQUIREMENTS Section 6.9.1 is changed as shown on the inserted pages 6-A and 6-B in Attachment 1. (Sections 6.10 and 6.11 are shown on inserted page 6-7 for completeness.)
- 6. 6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM)
In the 2nd paragraph, delete "... consistent with the applicable LCO's contained in these Technical Specifications." In item a, change " required by Specification 6.10.3.m." to " required by the Quality Assurance Program." ! 7. The section was repaginated and the page showing deleted Sections 6. :5 and 6.16 was removed. I L l
U. S. Nuclerr Regulatory Commission CY-98-003/ Attachment 3/Page 19 Reason
' Defueled Cond! tion, Editorial Changes, Administrative Letter 95-06, Generic Letter 89-01, and NUREG-1431.
Basis
- 1. The portion marked for deletion in Section 6.4 references Section 5.5 of ANSI N18.1-1971. Since the issuance of License Amendment 192, reference to this ANSI standard is no longer applicable. Licensed Operators have been replaced with Certified Fuel Handlers and Equipment Operators at the HNP.
Training of the Certified Fuel Handlers and Equipment Operators is governed by the training program approved by License Amendment 192. Therefore ( this statement can be deleted from the Technical Specifications.
- 2. The portion marked for deletion in Section 6.13.b is part of the PORC i responsibilities being transferred to the CYQAP and can therefore be deleted from the Technical Specifications.
- 3. With respect to the deletion of Section 6.6, the actions required in Subsection i 6.6.1.a is a requirement of 10CFR50.73. Referencing 10CFR50.73 within the Technical Specifications is therefore redundant and can be deleted from the Technical Specifications. The actions of Subsection 6.6.1.b, PORC review of
. REPORTABLE EVENTS, is covered in Subsection 6.5.1.6.f, which is being transferred to the CYOAP. Therefore, Section 6.6.1.f can also be deleted from the Technical Specifications.
Regarding Section 6.9.2, in accordance with the guidance in Generic Letter 95-10 and for consistency with NUREG-1431, those sections requiring Special Reports are transferred to either the REMODCM or the TRM. Therefore, the reporting requirements for Special Reports are also being transferred to either the REMODCM or the TRM. Each of these documents are controlled by CYAPCO procedures. Any changes to the REMODCM and I the TRM require a review be conducted in accordance with the requirements of 10CFR50.59. With all the Secens requiring Special Reports being transferred to either the REMOOCM of the TRM, this Section is no longer ; needed in the Technical Specifications.
- 4. With the requirements of Sections 6.5,6.8 and 6.10 being transferred to the CYQAP, these Sections are no longer needed in the Technical Specifications. The implementation of License Amendment 192 M also (9) NRC Letter from T. L. Fredrichs to R. Mellor, " Issuance of Amendment No.192 Operating License No. DPR Haddam Neck (TAC Nos. M98997 & M98998),"
dated March 27,1998.
U. S. Nucl:cr R:;gulatory Commission CY-98-003/ Attachment 3/Page 20 requires PORC meeting minutes be provided to the VP - Operations and Decommissioning. The requirements being transferred to the CYQAP include the submittal of PORC meeting minutes to the NSAB and the VP - Operations and Decommissioning. In accordance with the guidance in Administrative Letter 95-06 and for consistency with NUREG-1431, these Sections are transferred to the CYQAP where they will be controlled by CYAPCO procedures. Any changes to the CYQAP require a review be conducted in accordance with the requirements of 10CFR50.54(a).
- 5. The changes to Section 6.9 (in addition to the changes already discussed in the May 30,19970 ) submittal) are editorial; removing deleted portions, improving grammar, and reflecting the defueled and shutdown condition of the plant.
- 6. These are editorial changes, which are being done for consistency, reflect that the radioactive gaseous and liquid effluent monitoring requirements are contained within the ODCM portion of the REMODCM, and that records retention requirements are being transferred to the Quality Assurance Plan.
- 7. Reduced the number of pages with little or no information.
l (10) CYAPCO Letter CY-97-006 from T. C. Feigenbaum to the U. S. Nuclear Regulatory l Commission, " Proposed Revision To Operating License And Technical Specifications Defueled Operating License And Technical Specifications," dated , May 30,1997. u _--- -- - - - _
Docket Nos. 50-213 I CY-98-003 l l l l l Attachment 4 Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Safety Assessment And No Significant Hazards Consideration i i l I
)
i e 's 1 L P L L- August 1998 ] f
) .I d
U. S. Nucl:ar Regulatory Commission j CY-98-003/ Attachment 4/Page 1 j
)
Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Safety Assessment And No Significant Hazards Consideration Safety Assessment l i The plant has permanently ceased operations, the reactor has been permanently defueled, and the spent fuel is stored in the spent fuel pool. The Technical Specification requirements that are proposed to be removed are in one of the following categories: I i e Transferred Material This material is being transferred to the Haddam Neck Plant Updated Final Safety Analysis Report (UFSAR), the Connecticut Yankee Quality , Assurance Program (CYQAP), the Technical Requirements Manual I (TRM), or the Radioactive Effluent Monitoring and Offsite Dose l Calculation Manual (REMODCM). This transfer is in accordance with l Administrative Letter 95-06,W Generic Letter 95-10,W Generic Letter 89-01 W and for consistency with the Standard Technical Specifications for Westinghouse Plants (WOG STS) provided in NUREG-1431.W The removed material included in this category are portions of the material removed from Sections 1.0 and 6.13, and all the material removed from l Sections 3/4.3.3,3/4.3.4, 3/4.3.7,3/4.7.5,3/4.11.1, 3/4.11.2,3/4.11.3,5.1, 5.5, 6.5, 6.6, 6.8, 6.9.2, and 6.10. 1 (1) NRC Administrative Letter 95-06," Relocation of Technical Specification Administrative Controls Related To Quality Assurance," dated December 12,1995. (2) NRC Generic Letter 95-10," Relocation of Selected Technical Specifications Requirements Related to Instrumentation," dated December 15,1995. (3) NRC Generic Letter 89-01," Implementation Of Programmatic And Procedural Controls for Radiological Effluent Technical Specifications," dated January 31, 1989. (4) NUREG 1431, " Standard Technical Specifications, Westinghouse Plants, Specifications," Office of Nuclear Reactor Regulation, NRC, Volume 1, Revision 1, dated April 1995. ( C
U. S. Nucirr R:gulatory Commission i CY-98-003/ Attachment 4/Page 2 I e Removed Matedal This material deals with structures, systems, components and/or l programs that are only needed when the plant is operating, fuel is in the l reactor and/or fuel is in containment. The .vmoved material included in j this category are portions of the material removed from Section 1.0 and { 6.4, as well as all the material removed from Sections 3/4.9.1 through 3/4.9.6, 3/4.9.8, 3/4.9.9, 3/4.9.10, and 3/4.9.15. Since the issuance of License Amendment 192, reference to ANSI N18.1-1971 in Section 6.4 is no longer applicable. Licensed Operators have been replaced with Certified Fuel Handlers and Equipment Operators at the HNP. Training of the Certified Fuel Handlers and Equipment Operators is governed by the training program approved by License Amendment 192.
- Iodine Mitiaation This materialis used to mitigate the consequences of a radioactive lodine release. Since this is no longer a concern, this material is being removed.
The plant was shutdown on July 22,1996. Except for 1-125 (half-life
~59.5 days), 1-129 (half-life ~1.6E7 years), and Kr-85 (half-life
~10.8 years), the spent fuel inventory of the dose-contributing radioactive iodine and noble gas isotopes has decayed more than 20 half-lives since shutdown (i.e., less than 0.0001% of the original amount remains). In addition, the definition for " Dose Equivalent I-131" (" Standard Technical Specifications, Westinghouse Plants," NUREG-1431) does not include 1-125 and 1-129 in the dose assessment due to their negligible spent fuel inventory. Except for Kr-85, the other noble gas nuclides that contribute to a whole body dose have also decayed to a negligible amount.
CYAPCO has performed fuel handling and cask drop accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.1*) which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The removed material included in this category is Section 3/4.9.12. (5) Calculation XX-XXX-60RA, Rev.1, " Radiological Assessment of a Spent Fuel Shipping Cask Drop in the CY Spent Fuel Pool," provided in Attachment 5 of CYAPCO Letter CY-97-006, from T. C. Feigenbaum, to the U. S. Nuclear I Regulatory Commission, " Proposed Revision To Operating License And Technical Specifications Defueled Operating License And Technical Specifications," dated May 30,1997.
U. S. Nuclear Regulatory Commission CY-98-003/ Attachment 4/Page 3 The change to Section 3/4.9.7 from 1650 pounds to 1800 pounds is permissible since l the analysis for a 2300-pound fuel handling accident was provided to the NRC in I CYAPCO's March 21,1995 submittalW and was accepted by the NRC in a letter dated January 22,1996.A However, this 2300-pound value was based on possible future consolidation of fuel assemblies if the HNP operated past its 40-year life. Since this i scenario is no longer possible, the proposed 1800-pound value limits the existing spent fuel assembly / control rod assembly / handling tool weight. The change from 1650-pound limit to the 1800-pound limit eliminates the confusion over the nominal weight discussed in the Basis and provides some margin for drag forces when lifting an assembly. The change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fue! vithin the spent fuel pool. Since all fuel has been permanently removed from the reactor vessel and placed in the Spent Fuel Pool, Technical Specification 3/4.9.15 is being deleted and replaced by a new Technical Specification,3/4.9.16, SPENT FUEL POOL COOLING - DEFUELED,W that is applicable to the defueled condition of the Haddam Neck Plant. The changes to Sections 5.1 and 5.5 are permissible since the deleted information is provided in the UFSAR. The CYAPCO Defueled Security Plan includes the provision for CYAPCO to request the U. S. Coast Guard to close the Connecticut River to traffic in the vicinity of the HNP. Therefore, while the deleted statement in Section 5.1.1 may have been ambiguous when utilized in conjunction with Figure 5.1-1, the ambiguity has been eliminated. CYAPCO's UFSAR states that the Exclusion Area Boundary minimum distance is 1740 feet. In addition, the editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. In summary, the administrative and editorial changes do not have an effect on the safety of the plant. These changes remove text that is duplicated or is no longer applicable and provides consistency and clarity throughout. (6) CYAPCO Letter B15136 from J. F. Opeka to the U. S. Nuclear Regulatory Commission, " Proposed Revision to Technical Specifications Spent Fuel Pool Capacity Expansion," dated March 31,1995. (7) NRC letter from A. B. Wang to R. E. Busch, " Issuance of Amendment 188 (TAC No. M91976),' dated January 22,1996. (8) NRC Letter from T. L. Fredrichs, to R. A. Mellor, " Issuance Of Amendment No. l 193 Facility Operating License No. DPR Connecticut Yankee Atomic Pov,er i Station (TAC No. M98997)," dated June 30,1998.
U. S. Nucl::r R gulatory Commission CY-98-003/ Attachment 4/Page 4 Thus none of the above changes affect plant configuration nor do they affect plant i operations. Therefore, the changes do not affect the safety of the plant. Significant Hazards Consideration CYAPCO has reviewed the proposed changes to the Operating License and the ! Technical Specifications in accordance with 10CFR50.92 and concluded that the I changes do not involve a significant hazards consideration (SHC). The basis for this conclusion is that the three criteria of 10CFR50.92(c) are not compromised. The proposed changes do not involve an SHC because the changes would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated.
Because in the present plant configuration, the reactor-related accidents previously evaluated (i.e., LOCA, MSLB, etc.) are no longer possible. The accidents previously evaluated that are still applicable to the plant are fuel handling accidents and gaseous and liquid radioactive releases. There is no significant inciease in the probability of a fuel handling accident since refueling operations have ceased. In fact, there is more likely a decrease in probability of a fuel handling accident since the need to move / rearrange fuel assemblies is minimal until they are removed from the spent fuel pool (e.g., for transferring to USDOE possession). The radiological consequences of a gaseous or liquid radioactive release are bounded by the fuel handling accident during defueled operation and a spent resin fire during the reactor coolant system decontamination. With the plant defueled and permanently shutdown, the demands on the radwaste systems are lessened since no new radioisotopes are being generated by irradiation or fission. Therefore, there is no increase in the probability or consequences of a gaseous or liquid radioactive release.
]
The Technical Specification requirements that are proposed to be removed are in one of the following categories: e Transferred Maten'al This material is being transferred to the UFSAR, CYOAP, the TRM, or the REMODCM. This transfer is in accordance with Administrative Letter 95-06, Generic Letter 95-10, Generic Letter 89-01, and for consistency with the Standard Technical Specifications for Westinghouse Plants (WOG STS) provided in l NUREG-1431. The removed material included in this category are portions of the material removed from Sections 1.0 and 6.13, and i
U. S. Nuclear R:gulatory Commission CY-98-003/ Attachment 4/Page 5 l all the material removed from Sections 3/4.3.3, 3/4.3.4, 3/4.3.7, j 3/4.7.5, 3/4.11.1, 3/4.11.2, 3/4.11.3, 5.1, 5.5, 6.5, 6.6, 6.8, 6.9.2, l and 6.10. l l e Removed Material l This material deals with structures, systems, components and/or i programs that are only needed when the plant is operating, fuel is l in the reactor and/or fuel is in containment. The removed material included in this category are portions of the material removed from Section 1.0 and 6,4, as well as all the material removed from Sections 3/4.9.1 through 3/4.9.6, 3/4.9.8, 3/4.9.9, 3/4.9.10, and 3/4.9.15. Since the issuance of License Amendment 192, reference to ANSI N18.1-1971 in Sedon 6.4 is no longer applicable. Licensed Operators have bn replaced with Certified Fuel Handlers and Equipment Operators at the HNP. Training of the Certified Fuel Handlers and Equipment Operators is governed by the training program approved by License Amendment 192. 1 e lodine Mitiaation ' This materialis used to mitigate the consequences of a radioactive iodine release. Since this is no longer a concern, this material is being removed. The plant was shutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days),1-129 (half-life ~1.6E7 years), and Kr-85 (half-life ~10.8 years), the spent fuel inventory of the dose-contributing radioactive iodine and noble gas isotopes has decayed more than 20 half-lives since shutdown (i.e., less than l 0.0001% of the original amount remains). In addition, the definition for " Dose Equivalent 1-131" (" Standard Technical Specifications, Westinghouse Plants," NUREG-1431) does not include I-125 and 1-129 in the dose assessment due to their negligible spent fuel inventory. Except for Kr-85, the other noble gas nuclides that contribute to a whole body dose have also decayed to a negligible amount. CYAPCO has performed fuel handling and cask drop accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.1W) which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The removed material included in this category is Section 3/4.9.12. f
U. S. Nuciser Rcgulatory Commission CY-98-003/ Attachment 4/Page 6 The change to Section 3/4.9.7 from 1650 pounds to 1800 pounds is permissible since the analysis for a 2300-pound fuel handling accident was provided to the NRC in CYAPCO's March 21,1995 submittal
- and was accepted by the NRC in a letter _ dated January 22,1996.R However, this 2300-pound value was based on possible future consolidation of fuel assemblies if the HNP operated past its 40-year life. Since this scenario is no longer possible, the proposed 1800-pound value limits the existing spent fuel assembly / control rod assembly / handling tool weight. The change from 1650-pound limit to the 1800-pound limit eliminates the confusion over the nominal weight discussed in the Basis and provides'some margin for drag forces when lifting an assembly. The change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fuel within the' spent fuel pool.
Since all feel has been permanently removed from the reactor vessel and placed in the Spent Fuel Pool, Technical Specification 3/4.9.15 is being deleted and replaced by a new Technical Specification,3/4.9.16, SPENT FUEL POOL COOLING - DEFUELED,W that is applicable to the defueled condition of the Haddam Neck Plant. The changes to Sections 5.1 and 5.5 are permissible since the deleted information is provided in the UFSAR. The CYAPCO Defueled Security Plan includes the provision for CYAPCO to requeet the U. S. Coast Guard to close the Connecticut River to traffic in the vicinity of the HNP. Therefore, while the deleted statement in Section 5.1.1 may have been ambiguous when utilized in conjunction with Figure 5.1-1, the ambiguity has been eliminated. CYAPCO's UFSAR states that the Exclusion Area Boundary minimum distance is 1740 feet. In addition, the editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. In summary, the administrative and editorial changes do not have an effect on the probability or consequences of an accident previously evaluated..These changes remove text that is duplicated or is no longer applicable and provides consistency and clarity throughout. Based on the above, the proposed changes to the Operating License and the Technical Specifications do not involve a significant increase in the probability or consequences of an accident previously evaluated. l
U. S. Nucl:ar Regulatory Commission CY-98-003/ Attachment 4/Page 7
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated.
There is no change in how spent fuel is stored or moved in the spent fuel pool. l Therefore, the postulated fuel handling accidents are still bounding and are still considered as credible postulated accidents. l The Technical Specification requirements that are proposed to be removed are in one of the following categories: i e Transferred Matedal This material is being transferred to the UFSAR, CYQAP, the TRM, or the REMODCM. This transfer is in accordance with Administrative Letter 95-06, Generic Letter 95-10, Generic Letter - 89-01, and for consistency with the Standard Technical Specifications for Westinghouse Plants (WOG STS) provided in NUREG-1431. The removed materialincluded in this category are portions of the material removed from Sections 1.0 and 6.13, and all the material removed from Sections 3/4.3.3, 3/4.3.4, 3/4.3.7, 3/4.7.5, 3/4.11.1, 3/4.11.2, 3/4.11.3, 5.1, 5.5, 6.5, 6.6, 6.8, 6.9.2, and 6.10.
- Removed Matedal This material deals with structures, systems, components and/or programs that are only needed when the plant is operating, fuel is in the reactor and/or fuel is in containment. The removed material included in this category are portions of the material removed from Section 1.0 and 6.4, as well as all the material removed from Sections 3/4.9.1 through 3/4.9.6, 3/4.9.8, 3/4.9.9, 3/4.9.10, and 3/4.9.15.
Since the issuance of License Amendment 192, reference to ANSI N18.1-1971 in Section 6.4 is no longer applicable. Licensed Operators have been replaced with Certified Fuel Handlers and Equipment Operators at the HNP. Training of the Certified Fuel Handlers and Equipment Operators is governed by the training program approved by License Amendment 192.
- - _ _ _ - - - - - _ - - _ _ - - - - _ _ - - - - - _ - - )
U. S. Nuclear Regulatory Commission CY-98-003/ Attachment 4/Page 8 e lodine Mitigation This material is used to mitigate the consequences of a radioactive iodine release. Since this is no longer a concern, this material is being removed. The plant was shutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days),1-129 (half-life ~1.6E7 years), and Kr-85 (half-life ~10.8 years), the spent fuel inventory of the dose-contributing radioactive iodine and noble gas isotopes has decayed more ~than 20 half-lives since shutdown (i.e., less than 0.0001% of the original amount remains). In addition, the definition l for " Dose Equivalent 1-131" (" Standard Technical Specifications, Westinghouse Plants," NUREG-1431) does'not include 1-125 and 1-129 in the dose assessment due to their negligible spent fuel inventory. Except for Kr-85, the other noble gas nuclides that contribute to a whole body dose have also decayed to a negligible amount. CYAPCO has performed fuel handling and cask drop accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.1*)) which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The removed material included in this category is Section 3/4.9.12. The change to Section 3/4.9.7 from 1650 pounds to 1800 pounds is permissible since the analysis for a 2300-pound fuel handling accident was provided to the NRC in CYAPCO's March 21,1995 submittal
- and was accepted by the NRC in a letter dated January 22,1996.W However, this 2300-pound value was based on possible future consolidation of fuel assemblies if the HNP operated past its 40-year life. Since this scenario is no longer possible, the proposed 1800-pound value limits the existing spent fuel assembly / control rod assembly / handling tool
- weight. The change from 1650-pound limit to the 1800-pound limit eliminates the confusion over the nominal weight discussed in the Basis and provides some margin for drag forces when lifting an assembly. The change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fuel within the spent fuel pool.-
Since all fuel has been permanently removed from the reactor vessel and placed in the Spent Fuel Pool, Technical Specification 3/4.9.15 is being deleted and replaced by a new Technical Specification,3/4.9.16, SPENT FUEL POOL COOLING - DEFUELED,* that is applicable to the defueled condition of the Haddam Neck Plant. l The changes to Sections 5.1 and 5.5 are permissible since the deleted i information is provided in the UFSAR. The CYAPCO Defueled Security Plan includes the provision for CYAPCO to request the U. S. Coast Guard to close the i -- ----__________________z----- - - - - - - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . - - - - - - - - - - - _ _ _ _ - . - - - - - - - - - . _ _ _ _ _ _ _ _ _ - - - _ _ _ _ _ _ _ _ . - - - - - -- -_
i I U. S. Nucirr Regulatory Commission ' CY-98-003/ Attachment 4/Page 9 i Connecticut River to traffic in the vicinity of the HNP. Therefore, while the deleted statement in Section 5.1.1 rnay have been ambiguous when utilized in l conjunction with Figure 5.1-1, the ambiguity has been eliminated. CYAPCO's l UFSAR states that the Exclusion Area Boundary minimum distance is 1740 feet. In addition, the editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. In summary, the administrative and editorial changes do not have an effect on the probability or consequences of an accident previously evaluated. These changes remove text that is duplicated or is no longer applicable and provides consistency and clarity throughout. , i Based on the above, the proposed changes to the Operating License and the Technical Specifications do not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Involve a significant mduction in a margin of safety. l f
The Technical Specification requirements that are proposed to be removed are j in one of the following three categories: e Transferred Matenal This material is being transferred to the UFSAR, CYQAP, the TRM, or the REMODCM. This transfer is in accordance with Administrative Letter 95-06, Generic Letter 95-10, Generic Letter 89-01, and for consistency with the Standard Technical Specifications for Westinghouse Plants (WOG STS) provided in NUREG-1431. The removed materialincluded in this category are portions of the material removed from Sections 1.0 and 6.13, and all the material removed from Sections 3/4.3.3, 3/4.3.4, 3/4.3.7, 3/4.7.5, 3/4.11.1, 3/4.11.2, 3/4.11.3, 5.1, 5.5, 6.5, 6.6, 6.8, 6.9.2, and 6.10.
- Removed Maten'al This material deals with structures, systems, components and/or programs that are only needed when the plant is operating, fuel is in the reactor and/or fuel is in containment. The removed material included in this category are portions of the material removed from Section 1.0 and 6.4, as well as all the material removed from Sections 3/4.9.1 through 3/4.9.6, 3/4.9.8, 3/4.9.9, 3/4.9.10, and 3/4.9.15.
i i U. S. Nucle:r R::gul: tory Commission CY-98-003/ Attachment 4/Page 10 Since the issuance of License Amendment 192, reference to ANSI N18.1-1971 in Section 6.4 is no longer applicable. Licensed Operators have been replaced with Certified Fuel Handlers and Equipment Operators at the HNP. Training of the Certified Fuel Handlers and Equipment Operators is governed by the training l program approved by License Amendment 192. 1 e ' lodine Mitigation l This materialis used to mitigate the consequences of a radioactive iodine release. Since this is no longer a concem, this material is i being removed. The plant was shutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days),1-129 (half-life ~1.6E7 yecrr.), and Kr-85 (half-lifa ~10.8 years), the spent fuel inventory of the dose-contributing radioactive iodine and noble gas isotopes has decayed more than 20 half-lives since shutdown (i.e., less than 1 0.0001% of the original amount remains). In addition, the definition I for " Dose Equivalent 1-131" (" Standard Technical Specifications, Westinghouse Plants," NUREG-1431) does not include I-125 and 1-129 in the dose assessment due to their negligible spent fue! inventory. Except for Kr-85, the other noble gas nuclides that contribute to a whole body dose have also decayed to a negligible amount. CYAPCO has performed fuel handling and cask drop : accident dose calculations (HNP UFSAR Section 15.5.2 and l Calculation XX-XXX-60RA, Rev.1*)) which conclude that doses i (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10CFR100 dose limits and less than the EPA PAGs. The removed material included in this category is Section 3/4.9.12. The change to Section 3/4.9.7 from 1650 pounds to 1800 pounds is permissible l since the analysis for a 2300-pound fuel handling accident was provided to the NRC in CYAPCO's March 21,1995 submittal
- and was accepted by the NRC in a letter dated January 22,1996.m However, this 2300-pound value was based on possible future consolidation of fuel assemblies if the HNP operated past its 40-year life. Since this scenario is no longer possible, the proposed 1800-pound value limits the existing spent fuel assembly / control rod assembly / handling tool weight. The change from 1650-pound limit to the 1800-pound limit eliminates the t confusion over the nominal weight discussed in the Basis and provides some I
margin for drag forces when lifting an assembly. The change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fuel within the spent fuel pool. L
U. S. Nuclear Regulatory Commission CY-98-003/ Attachment 4/Page 11 Since all fuel has been permanently removed from the reactor vessel and placed in the Spent Fuel Pool, Technical Specification 3/4.9.15 is being deleted and replaced by a new Technical Specification,3/4.9.16, SPENT FUEL POOL COOLING - DEFUELED,* that is applicable to the defueled condition of the i Haddam Neck Plant. The changes to Sections 5.1 and 5.5 do not effect the margin of safety since the deleted information is provided in the UFSAR. The Haddam Neck Plant UFSAR i states that the Exclusion Area Boundary minimum distance is 1740 feet. The CYAPCO Defueled Security Plan includes the provision for CYAPCO to request the U. S. Coast Guard to close the Connecticut River to traffic in the vicinity of the HNP. Therefore, while. the deleted statement in Section 5.1.1 may have been ambiguous when utilized in conjunction with Figure 5.1-1, the ambiguity has been eliminated by the proposed change. The administrative and editorial changes included in this proposed revision { provide correct spelling, brevity, clarity and/or consistency; remove text that is - duplicated or is no longer applicable; and provides consistency and clarity throughout. These changes do not reduce the margin of safety. Based on the above, the proposed changes to the Operating License and the Technical Specifications do not involve a reduction in a margin of safety due to the reduced decay heat load, the decay of radionuclides since shutdown and by maintaining the heavy load restriction. 1 l . i 1 _ _ _ _ _ _ _ - - _ _ _ _}}