ML20195C859

Proposed Tech Specs Incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant

ML20195C859
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/03/1999
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20195C856	List: CY-99-041, Application for Amend to License DPR-61,incorporating Changes Which Reflect Limitations & Requirements Appropriate to Present Configuration of Plant ML20195C859
References
NUDOCS 9906090012
Download: ML20195C859 (250)

Text

,

INDEX

(-

nFFfMTTfAMC

'l SECTION pffg

,2."CERTIF@ fut, HAuPMiR. f b

1.0 M TIONS ~ l c

1.1 ACTION .............................. 1-1  ;

q ANALOG CHANNEL OPERATIONAL TEST . . . . . . . . . . . . . . . . . . 1-l 1.3 ETED l

'1.4 CHAN CALIBRATION . . . . . . . . . . . . . . . . . . . . ... 1-1  % U 1.5 CHANNEL C . . ................... ..... 1-1 f 1.6 DELETED 1.7 DELETED 1.8 CORE ALTERATION . . . . . . .... .............. 1-3 1.9 DELETED 1.10 DELETED 1.11 DELETED ,

1-3 /

1.12 FREQUENCY NOTAT . . . . . . . . . . . . . . . . . . . . . . . . . 1

. 1.13 DELETED' '

{1.14 DELE [

-4 11.15 BER(S) 0F THE PUBLIC . . . . . . . . . . . . . . . . .-. . . . . i

/ .6 DELET,ED _

1-ffl f, ) M OPERABLE - OPERABILITY .......................

MODE - MODE . . D . . . . . . . . . 9

' l 1.20 DELETED 1.21- DELETED' M

g Bh.tiLD - l

/,4f -hs- RADI0 ACTIVE WASTE TREATMENTS SYSTEMS ................ 1-7 l f, f .+:24 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE r

CALCULATION MANUAL (REMODCM)

................... Ik 26 , , - , _ . ..... C........ 1-5

~

1.27 RHR I N* . . . . . , , . . . . . . . . . . . . . , . ..... 1-5  ;

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N _ f l

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9906090012 990603 PDR ADOCK 05000213-PDR ,,

p HADDAM NECK I Amendment No. J U. 193 0413 j

i INDEX DEFINITIONS SECTION ~ gag

1. DELETED-~

i 1,29 S NDARY . . . . . . . . . . . . . . . . . . . . . . . . . . . -6 1-6 f) 1.31. DELETED 1.30 SOURCE C ....................... ...

I 1.32 DELETED 1.33 DELETED  %

-f1.34 DELETED' 1.35 C:LETED 1.36 DELETED 1.37 DELETED TABLE 1.1 F NCY NOTATION ..................... 1-8

.TABL . OPERATIONAL MODES . . . . . . . . . . . . . . . . . . . . . . . -

L_

I l

l HADDAN NECK II Amendment No. J7), J7), Jpp.193 0413

1110E1 SAFETY LIMITS AND LIMITIM SAFETY SYSTEM SETTINGS l SECTION ff3E o .

2.f DELETED l OFASES 2.,/ DELETED l all3ES f SECTI E8EE 2.1 ' TED l 2.2 DELETED l

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't 9b j iko$

a l

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l III Amendment No. #J. ##,193 MDOAM NECK 0413

,i L .~.

r: 1 June 30. 1998 INDEX j LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS --

. a ;.

(;.,) SECTION pg l

... 3/4.0 APPLICABILITY 3.0.1 ....................................................... 3/4 0 1 )

3.0.2 ....................................................... 3/4 0 1  !

3.0.3 DELETED 3.0.4 ....................................................... 3/4 0 1 4.0.1, .............................................. ......... 3/4 0 2 4.0.2 ....................................................... 3/4 0 2 4.0.3 ' ....................................................... 3/4 0 2

....................................................... 3/4 0 2 4.0.4 . -

.0 ED l 3/4.1 DELETED l' 1

l

,u

[.c. ms

-sv l

HADDAM NECK. IV Amendment No.125.1SS.1 % 193 T5.! E.X.00C I-L

m- r. , , ,

APR-29-1999 10:55 tRC46R/DSSA/SPLB I

INDEX

, \

BASES P. AGE SECTION .

APPI TCA8f t ITY

........................................ ..............B3/4 0 2 3/4.0 01 3.0.1 3.0.2 .......................................................B3/4 3.0.3 DELETED 0-3 3.0.4 .......................................................B3/4 0 4 4.0.1 .......................................................B3/4 0 4 4.0.2 .......................................................B3/4 0 4 4.0.3 .......................................................B3/4 0 5 4.0.4 _ .......................................................B3/4 DEL

. /T. . LETED i 4.0.6 D

(Referepees 3/4.1 0FfFTED 3/4.2 0FIFTED 3/4.3 i==N"ATIM Pe & P f .1 DELETED 3/4.S. DELETED 3/4.3.3 NITORING INSTRUMENTATION 3/4.3.3.1 DE 3/4.3.3.2 - DELETED l 3/4.3.3.3 32 HETEOROLOGICAL INSTN.UME...................B3/4 DELETED 3/4.3.3.4 AT ......

3/4.3.3.5 DELETED A 3/4.3.3.6 DELE'ED RADI0ACTIV UID EFFLUENT 3/4.3.3.'/ ......... 83/4 3 3 HONI G INSTRUMENTATION.................

3/4.'3.3.8 0 ACTIVE GASEOUS EFFLUENT B3/4 3 3 MONITORING INSTRUMENTATION...........................

3/4.3 . DELETED 3 . 4 DELETED u

,3/4.4 0FIFTED

? -

3/4 8s _

0FIETED 0FtETED

( 3/4.6 VI Amendment No. W W .194 HADDAM NECK i

13.!N00.00C i'

lune 30, 1998 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS (ps;.,, SECTION pyg 3/4.2 DELETED l

3/4.3 I"SU""CATIOu pELET6 D i g/4. .,

3 D l 3/4. ETED O l l

l 3

l f

)

l

( l j.

3e 9  :

4 l d

4 )

j . . -

HADDAM NECK V Amendment No.125,l'.S.1SS,193 T5-INDEX.00C i

]

June 30, 1998 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 6%

'@ r pg 3/4.3. MONITORING INSTRUMENTATION .l 3/4.3.3. DELETED l 3/4.3.3.2 DELETED' l 3/4.3.3.3 SEISMIC INSTRUMENTATION.............. ............... 3/4 3 27 TABLE 3.3-5 ISMIC MONITORING INSTRUMENTATION .................. 3/4 3 28 TABLE 4.3 4 S MIC MONITORING INSTRUMENTATI SURV LANCE REQUIREMENTS.... ........................ 3/4 3 29

.I 3/4 d.3.4 METEORO ICAL INSTRUMENT ON........................ 3/4 3 30 l TABLC 3.3 6 METEOROL AL MONITORI INSTRUMENTATION 3/4 3 31 TABLE 4.3 5 HETEOROLOGIC MONIT I*3 INSTRUMENTATION SURVEILLANCE RE MENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 3 - 32 3/4.3.3.5 DELETED l 3/4.3.3.6 DELETED l 3/4.3.3.7 ~RADI0ACT LIQUID EFFLUE MONITORING I j INSTRU ATION.............. ....................... 3/4 3 44 j TABLE 3.3 9 RAD TIVE LIQUID EFFLUENT MON ING I TRUMENTATI0N.................... .................. 3/4 3 45 '

I0 ACTIVE LIQUID EFFLUENT MONITORI

.gg TABLE 4.3 7 [ INSTRUMENTATION............ SURVEILLANCE 3/4 3 47 R

'3/4.3.3, RADI0 ACTIVE GASEOUS EFFLUENT MONITORING i(?~?P- INSTRUMENTATION............................... ....... 3/4 3 49 4

A l 3  !

. 1 4

3 h

1 1

i ,

i 1

A 2

-Q  !

(.fy

,- HADDAM NECK VI Amendment No.125.179.193 l

$ Ts.noa.oot i

LE .. ]

l INDEX LIMITING ColeITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION f3CtE

<- ~

-10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING f ENTATI0N.............................. ... 3/4 3-50 .

TABLE 4.3-8 RADIOACTIV 5 EFFLUENT MONI INSTRUMENTATION SURVE REQUIREMENTS.......... 3/4 3-52 3/4.3.3.9 DELETED f

. DELETED

~ _

h 3/4.4 DELETED l

l t

HADOAN NECK VII Amendment No. 177, 177 177, 193 0413

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naer a kau Tu. t. . . . _ _ T.NTEM.T.

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. _ . _ . . s i V. . _ ,

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VIII Amendment No. J2), JJJ, JES, HADOAM NECK J7J, 193 au

INDEX LINITING ColeITIONS FOR OPERATION AND SURVEILLANCE REQUIRENENTS SECTI0tl -

EASE 3/4.5 DELETED 3/4.5 DELETED l

}/.1,7 "L% T'; ';Y';TE;'i3 pfl.8T6D

'L

, . DE(ETED l

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HADOAM NECK IX Amendment No. J17. JJF J77 193 M13

ElDil LINITIM COM ITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGI

^

47.2- DELEIED i

3/4.7. DELETED 3/4.7.4 DE 3/4.7.5 SEALED S CONTAMINATION . . . . . . . . . . .. . . 3/4 7-14 3/4.7.6 DELETED ./

3/4.7.7 DELETED 3/4.7.8 DELETED 3/4.7.9 DELETED f3/4.7.10 DELETED y 3/4.7.11 ED DELETED 3/4.8 DELET(D l

)

b I

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HADDAM NECK X Amendment No. Jg), JJJ. JpF. 177. 177 193 M11

1 b

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION < j%gg .

)

~

SPFMT FUEL BW3 DING 3/4.9 dIEFtfrLIM,10PERATIONS 3/4.9.1 h CONCENTRATION . . . . . . . . ....... 3/4 3/4 9-2 D"# ,L 3/4.9.2 INSTRUMEN ................... .

3/4.9.3]DECAYTIME...... ........ ....... 3/4 9-3 8887 9 f ULL CORE OFFLOAD. . 3/4 9-3a II dIGURE3.9-1 REQUIRED REACTOR HOLD TIM 3/4.9.4 l CONTAINMENT BUILDING TIONS . . . . . . 3/4 9-4 3/4 9-5 8Mf l petaT*

3/4.9.5 COMUNICAT .....................

3/4.9.6' LATOR CRANE . . . . . . . . . . . . . . . . . . . . . 3/4 08% j '

3/4.9.7 CRANE TRAVEL - SPENT FUELSTORAtrBUILDING ........ 3/49-Ki pg 78[

3/4.9.8 EAT REMOVAL AND COOLANT CIRCULATION l lHIGH WATER ............... ... 3/4 9-8 1 LOW WATER LEVEL . . . . . . ... .......... 3/4 9-9 3/4.9.9 CONTAINMENT PURGE SUPPLY EXHA , Q[Ta0 l PURGE EXHAUS. S ISOLATION SYSTEM . . . . . . . . .

3/4 9-10

- REACTOR VESSEL . . . ._._. ....... 3 P6487Y

_3_/49.10LWA_

IC..

3/4.9.11 WATER LEVEL-ST0"".CE--P00b 3/4 9-)f2. j

-@ L 9712 TUEL ST0"".0E S M CI"O Ain m._, SYSTE". . . . . . . . . . -3/ 4 3 47 _ - _ .

[

3/4.9.13 HOVEMENT OF FUEL IN SPENT FUEL POOL . . . . . . . . . . 3/4 9-J5'J l 3/4.9.14 SPENT FUEL 00CL - REACTIVITY CONDITION . . . . . . . . . 3/4 9-J6'Y FIGURE 3.9-2 SPENT FUEL P0OL RACK MINIMUM BURNUP REQUIREMENTS . 3/4 9-)7 f j FOR REGION 2 l FIGURE 3.9-3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIP.EMENTS .

3/4 9-}B'4 FOR REGION 3 l l

FIGURE 3.9-4 SPENT FUEL POOL RACK REGION LOCATIONS . . . . . . . . 3/4 9 .19 7 3 4.9.15 @ 00LIN . .' T . . . . . . . . . [ .3/4 9-2 pet 8f4 1

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/ I 3/19,f6 Sf n T N t fod" MMPG - peyg7 ,; ,7___g w ._- A ,

l MADOAM NECK XI Amendment No. J15,177 JS, J7J.

oats JM,193 f:

f 1

i INDEX LINITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIRENENTS SECTION g 3/4.10 DELETED 3/4.11 IRADI0ACTIVEEFTLUENTS DF1 F*

/

s LIQUID EFFLUENTS ]

-1 3/4.11.1.1 C0 TION . . . . . . . . . . . . . . . . . . . . . .

3/4.11.1.2 DOSE, LIQUI ................. . . 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE . . . . . . . . . . . . . . . . . . . . . 3/4 11-3 3/4.11.2.2 DOSE, NOBLE GASES . ........ . . . . . . . 3/4 11-4 3/4,11.2.3 DOSE, RADIO MATERIAL IN PARTICULATE F RADIONUCLIDES OTHER THAN NOBLE GASES . . . . . . 4 11-5

3/4. . TOTAL DOSE . . . . . . . . . . . . . . . . . . . . . . 3/4 -

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4

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I 1

i HADDAN NECK XII Amendment No. J77,177,177,193 l 0413 I

l

INDEX BASES .

1 SECTION PAGE l  ;

I 3/4.0 APPLICABILITY 3.0. I' ~1

. ..'................. B 3/4 0-1 l 3.0.2 . .................... B 3/4 0-2 l l

3.0.3 DELETED 3.0.4 . .................... B 3/4 0-3 4.0.1 .. ................... B 3/4 0-4 /

4.0.2 . .................... B 3/4 0-4 l 4.0.3 . .................... B 3/4 0-4 4.0.4 . .................... B 3/4 0-5 i

. DELETED l

4.0.6 D l l Refer s DEL J

3/4.1 DELETED 3/4.2 DELETED eA

~

, ~Pl; GTEb 3/4.3 / INSTRUMENTATION ",5

.3.1 /

f DELETED 3/4.3. DELETED 3/4.3.3 ITORING INSTRUMENTATION 3/4.3.3.1 DEL 1

l 3/4.3.3.2 DELETED 3/4.3.3.3 SEISMIC INSTRUME ION ..... ... B 3/4 3-2 3 L

3/4.3.3.4 METEOROLOGICAL INSTRUM TI ...... B 3/4 3-2 3/4.3.3.5 DELETED i 3/4.3.3.6 DELETED 3/4.3.3.7 RADI0 ACTIVE ID EFFLUENT MONITORI NSTRUMENRATION ........ 3/4 3-3

'3/4.3.3.8 RA CTIVE GASEOUS EFFLUENT 41TORING INSTRUMENTION ......... B 3/4 3-3/4.3 . DELETED e .3.4 DELETED y 3/4.4 DELETED XIII Amendment No. JJJ JJP, 193 HADDAM NECK 0413 l

,.- 3

{'

INDEX l BASES PAgg SECTION I 3/4.5 D5LETED, 3/4.6 DELETED f

3/4.7 bTSYSTEMS 96 )

I I

d 7.1 DELETED ]

l l 3/4.7.2 D ED l

l 3/4.7.3 DELETED 3/4.7.4 DELETED l 3/4.7.5 SEALED SOURCE CONTAMI ON...... .................. B 3/4 7-4 3/4.7.6 DELETED 3/4.7.7 DELETED p

3/4.7.8 DELETED o

3/4.7.9 DELETED

! 3/4.7.10 0 ED 3/4.7.1 DELETED

. 12 DELETED 1

1 1 l

l l 1 l o a

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XIV Amendment No. Jjf7.177,177 177.177,193 HADDAM NECK 0413 k_

1 BDIX BASES SECTION pjj;g 3/4.8 DELETED ppjp I y

3/4.9 REFLTLJC OPERATIONS 3/4.9.1 NCENTRATION ....

.....(,...... B 4-T-T P6887"'

B 3/4 9-1 Ps s7eb 3/4.9.2 INSTRUMENTAT .............. . ..

3/4.9.3 DECAY TIME ........ .. . ........ B 3/4 9-1 PAeMP 3/4.9.4 CONTAINMENT BUILDING PE NS .. . . . . . . B 3/4 9-1 (,p p578D 3/4.9.5 COMMUNICATI .................. . B 3/4 9-1 DMM ps2.AW 3/4.9.6 i TOR CRANE .................. B

-J '

3/4.9.7 CRANE TRAVEL - SPENT FUEL-GTORAGE BUILDING ...... B 3/4 9-71 3/4.9.8 IDUAL HEAT REMOVAL AND COOLANT CIRCULATIONA B 3/4 9-2/PEl47s0 3/4.9.9 CONTAI RGE SUPPLY, PURG , AND (DsWT*P

,/

PURGE EXHAUST BY ON SYSTEM ........ B 3/4 9-2 >

3/4.9. R LEVEL - REACTOR VES GE 3/4.9.10 .

I . ... .. . .

..... ... 4 9-1 3/4.9.12 (UEL STORBE:11tfQiING AIR CLEANUP SYSTEM ....... B 3/4 9- '

3/4.9.13 MOVEMENT OF FUEL IN g SPENT FUEL POOL .......

SPENT FUEL POOL - REACTIVITY CONDITION ........

B3/49-[l B3/49-f l f 3/4.9.14 N NT; FE M nk N LIM .......... B 3/4 9-3 PE i 3/4.9.15 -

-, ,n-s 3 4 9 ,48 MTWR. LEVWL - Sf997 FugL c u. N ,

3/4. DE EW ^ *--~ u sr w rFab' yjg'4'g co0Lu h ~0&fM M O Y v

3 . . . . B 3/t 4 3/4.11 NI0ACTIVEEFFLUENTS D6NE J ~

11.1 LIQUID EFFLUENTS

................... 4 11-1

, 3/4.11. . CONCENTRATION DOS , UIDS ............... . . . B 3/4 11-1 f 3/4.11.1.2 3/4.11.2 GASEOUS EFFL 3/4.11.2.1 DOSE RATE ...... . . . . . . . . . . . . . B 3/4 11-2

. . . . . . . . . . B 3/4 11-2

('

3/4.11.2.2 DOSE, NOBLE GASES .......

DOSE, IVE MATERIAL IN PARTICULA RM 3/4.11.2.3 4 i

f DIONUCLIDES OTHER THAN NOBEL CASES ..... . B 3/4 11-3 11-3 3 .3 TOTAL DOSE ......................

XV Amendment No. J77, 177. J)P.

HADDAM NECK mia 177,193

IIEEX DESIGN' FEATURES.

SECTION PAE l 5.0 DESIGN FEATURES J

5.1 SITE , , , , , . . , , . . - * ** * *- * * * **

m /

t

.1 EXCLUSION AREA .......................

5.1. LOW POPULATION ZONE .................. . 5-1 I FIGURE 5.1- EXCLUSION AREA BOUNDARY AND SITE BOUNDARY FOR L D AND GASEOUS EFFLUENTS . . . .. ........ 5-2 4 FIGURE 5.1-2 LOW P0 ION ZONE ,..... ........... 5 ,

l l

5.2 DELETED 5.3 DELETED l I

5.4 0 ED 1/ METEOROLOGICAL TOWER LOCATION . . . . . . . . . . . . . . . . 1 ,

i -

} i

, g. 2. ,5Jr- SPENT FUEL STORAGE i

J,2.1 -6dr:t- CRITICALITY , . . . . . . . . . . . . . . . . . . . . . . . . 5- /

5 . 2 6.2.t 4dr.+ DRAINAGE ..........................

5-/d 2-g,2 } 4.0.3 CAPACITY ..........................

5.7 DELFT i

l li l HADDAM NECK XVI Amendment No. JJJ. 177. JJJ. 193 l .0413 l

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' XVII Amendment No. J75, Jpp 193 i- HADDAN NECK i M13

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INDEX

'ADMINISTr.ATIVE CONTROLS SECTION E8AE 6.0 SADMINIS'TRATIVE CONTROLS 6.1' RESPONSIBILITY , . . . . . . . . . . . . . . . . . . -

kJ 6.2~ -ORGANIZATION 6. enal Org 4 / '*!

6.2.1- ^" SITE" ^. " Occe!TE ^"i'?::Z"T:'":d. . . . . . . . 6-/ 2--

6.2.2 FACILITY STAFF . . . . . . . . . . . . . . . . . . . 6-7 3

. TABLE 6.2-1 MININUM SHIFT CREW COMPOSITION . . . . . . . . . . . 6-J' 4 l

l

'6.3- FACILITY STAFF QUALIFICATIQHE . . . . . . . . . . . 6-f 5-6.4 TRAINING . . . . . . . . . . . . , . . . . . . . . . 6g 6 REVIEW AND AUDIT

'I '

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6.5.1 PLANT OPERATIONS REVIEW COMITTEE (PORC) . . . . . ,, 6-5 Function . . . . . . . . . . . . . . . . . . . . . . 6-5 sition ..................... 6-5 Alt ates . . . . . . . . . . . . . . . . . . . . . 6-6 Meeting equency ................. .

6-6 Quorum . . . ......... ......... 6-6 Responsibilities ..... . . ......... 6-6 Authority ..... . ............. 6-7 Records . . -. . . . . ............. 6-7 6.5.2 NUCLEAR SAFETY SSESSMENT BOARD SAB) . . . . . . . 6-7 Function . . . . . . . . . . . . . . ....... 6-7 Compos on .............. ..... 6-8 Al nates . . . . . . . . . . . . . . . . . ... 6-8

}

eting Frequency ............... . 6-8 Quorum . . . . . . . . . . . . . . . . . . . . . . .

6-8 Review Responsibilities .............. 6-HADDAM NECK XVIII Amendment No. JJ), JJ), III 193 0413

n INDEX i ADMINISTRATIVE CONTROLS TECff0N EMig

_ Audits Program Responsibilities

..... ... 6-9 Records ... .... ........... 6-10 k 6.6 REPORTABLE IVENT ACTION ..... ...... 6-10

. DELETED _

t _-

6 ,6 fritr~ PROCEDURES AND PROGRAMS .............. 6-M 7 66 (g , 7 4+- REPORTING, REQUIREMENTS Ro e rts . ................. 6-1 D/- ) {,-}-

4,7.I h = 1 ";;;rt: '..T W T........ 6-tAs y'

- Annual Radiological Environmental Operating Report . 6-M f,y t g,yg Annual Radioactive Effluen eport . . . . . . . . . 6-%

, DEL ED e ease

< DELETE _ k Spec Rep.

N A

..... 6-17 \

) ~

6.10 RECORD . ........ ....... 6-17 11 TION PROTECTION PROGRAM . . . . . . . . . . . .

6-

f. 8 tf HIGH RADIATION AREA ................ -

6. RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE N LCULATION MANUAL fREM00CM) ..... ..... 6-20 6.14 RADIQACTIVE T ............ 6-20 l

6.15 DELETED >

__,6. - . . -

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A (h

HADOAM NECK 0 6l W' J V XIX Amendment No. J77 177 177 777 ypf,193

Insert A to old onge XIX 6.6. Programs and Manuals 6.6.1 Radiation Protection Prog ram ................................................................. 6-8 6.6.2 Process Control Progra:u (PC P).............................................................. 6-8 6.6.3 Radiological Effluent Monitoring and Offsite Dose Calculation Manual

( R E MO DC M ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6.6.4 Radiological Effluent Controls Program............................................... 6-10 6.6.5 Radioactive Environmental Monitoring Program................................. 6-12 6.6.F Spent Fuel Pool Cooling and Makeup Monitoring Program................ 6-12 6.6.7 Technical Specification (TS) Bases Control Program......................... 6-13

1.0 DEFINITIONS i The defined terms of this section appear in capitalized type and are applicable thr.oughout theso Technical Specifications.

ACTION 1.1 ACTION shall be that part of a Technical Specification which prescribes remedial measures required under designated conditions.

~

..uniog c}^""' M L TEST ]

1.2 ANALOG CHANNEL OPERATIONAL TEST shall be the injection of a simulat signal into the channel as close to the sensor as practicable verify OP BILITY of alarm, interlock and/or trip functions. The the CHANNEL OPE ONAL TEST shall include adjustments, as necessary, I alarm, interloc and/or Trip Setpoints such that the Setpoints a within the required range nd accuracy.

1.3 DELETED l1 GHANNEL CALIBRATION 1.4 A CHANNEL CALIBRATION shall be djustment, as necessary, of the channel such that it responds within equired range and accuracy to known values of input. The CHANN ALIB ON shall encompass the entire

) channel including the sensors alarm, inte ock and/or trip functions,

{andmaybeperformedbyany rios of sequentia , overlapping ted.

or total i channel steps such that t entire channel is cali

\

\

CHANNEL CHECK CHECK shall be the qualitative assessment of annel \

A CHANN f1.5 behavior d ng operation by observation. This determination sh 1 include, where p ible, comparison of the channel indication and/or status th nels othe ndications and/or status derived from independent instrument c uring the same parameter.

l'GRTiflED f1AEL MpM.Elt I' h

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1-1 Amendment No. Up,193 HADDAN NECK 0814

Insert B to old onge 1-1  !

A CERTIFIED FUEL HANDLER is an individual who complies with provisions of the CERTIFIED FUEL HANDLER training program required by Specification 6.4.1.

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1~2 Amendment No, ygg, ygg, ygg,,,,

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DEFINITIONS l

, C N ALTERATION 1.8 C0 ALTERATION shall be the movement or manipulation of any comp nt within the ctor vessel, with the vessel head removed and fuel in vessel. Suspen n of CORE ALTERATION shall not preclude comple n of movement of a comp nt to a safe position.

1.9 DELETED 1.10 DELETED 1.11 DELETED FRE0VENCY NOTATION 1.12 The FREQV NOTATION specified for the performance of veillance Requirement all correspond to the intervals defined in Table 1.

1 DELETED l I

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1 1-3 Amendment No. Jg), JJ7 193 <

HA00AM NECK 0414

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DEFINITIONS

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. DELETED MEMBERfS) O PUBLIC I ~1.15 MEMBER'('S) 0F THE shall include all per who are not occupa-tionally associated with the p . This cate does not include employ-ees of the licensee, its contractors, ors. Also excluded from this category are persons who enter the to vice equipment or to make deliveries. This category do clude persons use portions of the site i for recreational, occup al, or other purposes not ciated with the plant.

1 ELETED OPERABLE - OPERABILITY f,) -htt 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 '

l function (s).

N TIONAL MODE - MODE N s ,

j 1.18 An 0 L MODE (i.e., MODE) shall correspond to an lu-l sive combination o reactivity condition, power el d average 'k i reactor coolant temperature fied in Tabl ..

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1.19 DELETED l

1. ED V -

J HADDAM NECK 14 Amendment No. J M ,193 0414

i DEFINITION!.

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22 D_ELElyn - --

RADI0AGIlyi WAhTE TREATMENT' SYSTEMS Pef ** I

/4 +;tt RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required t maintain control over radioactive material in order to meet the set orth in th:::. ;;;:i'i::ti:::.

p ggyopc.M F 3

RADIOLOGIC AL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) j f,5 +:f4 A RADIOLOGICAL EFFLUENT MONITORING MANUAL (REMM) shall be a manual l containing the . site and environmental sampling and analysis programs for l measuremerits of radiation and radioactive materials in those exposure pathways and for tirose radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An OFFSITE DOSE CALCULA-TION MANUAL (00CM) shall be a manual containing the methodology and param-j eters to Ise used in the calculation of offsite doses due to radioactive i gaseous ard liquid effluents and in the calculation of gaseous and liquid effluent vanitoring instrumentation Alar #Tr Setpoints. Requirements of the REMODLM are provided in Specification 6 5 DELIED REPORTAB W ENT 1.26 A REPORTABLE shall be any of those conditio ecified in l Section 50.73~to 10CFR Pa 0.

i RHR LOOP 1.27 An RHR LOOP consists Residual Heat val (RHR) pump, a dedi-her from the same train rom the opposite tcated RHR heat exchan to receive and  !

train and all oth ecessary piping and components roqu cool react ant.

p d LETED x ) i l

1-5 Amendment No. J M ,193 HADDAM NECK 0414

DEFINITIONS I:

BOUNDARY 1.29 SITE. BOUNDARY shall be that line beyond which the land is neithe owned, nor ased, nor otherwise controlled by the licensee.

SOURCE CHECK be the qualitative assessmen f channel f1.30 A SOURCE response when theCHECK channel sha s or is exposed to a so e of increased radio-activity.

1.31 DELETED Q_

1.32 DELETED 1.33 DELETED 1.34 DELETED 1.35 DELE 1.3 ELETED 1-6 Amendment No. J M ,St 193 HADDAM NECK 0414 l

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l MADDAN NECK 1-7 Amendment No. J7).177 187 193 i 1

0414 I i

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TABLE 1.1 FREQUENCY NOTATION ,

FREQUENCY  :

NOTATION S At ler.st onc per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. t 5 D At leas once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

W At ast once per 7 days.

B t least once per 14 days. I M At least once per 31 days.

SW At ast once per 42 days.

Q At leas ince per 92 days.

I i

SA At least once er 184 days.

R At least once per months.

I P Prior to each release. l A. Not applicable.

HAD0AM NECK 1-8 Amendment No. JU.193 0414 L.

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rw 1- 9 Amendment No. J M , 193 HADOAM NECK 0414

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SECTION 2.

ETY L ITS LIMITING SAF YSTEM SETTINGS i'

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LINITING 5AF YSTEM SETTINGS DELET IN THEIR IRETY l l

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SECTIONS 4.0.5, 4.0.6; ABLES 4.0-1, 4.0-2;  ;

URE 4.0-1; AND ,

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f PAGES 3/4 -3 THROUG /4 0-8 DEL T 9-I' 1

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. .l SECTIONS 3.1 AND 4.1

'REA IVITY CONTROL SYSTEM DELETE IN THEIR ENT ETY l

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TfBLES 3 1 THR00 3.3 5: l R0 4.3 4: AND {

TABLES 4.3 1 PAGES 3/4 3-1 OUGH 3/4 3 29 DELETED l

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i 3/4 3 1 Amendment No.M3,194 DAM NECK T5353.00C

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l SECTIONS 3.3.1 THROUGH 3. 3.2; l 4

S TIONS 4.3.1 THROUGH .3.3.2; {

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4 HADDAM NECK osie

HIWENIAIIDH METEORCLOGICAL INSTRUMQ(IAT10M  !

LINI CONDITION FOR OPERATION 3.3.3.4

\ The eteorologicai monitoring instrumentation channel' shown in Table 3.3-6 sha 1 be OPERABLE.

APPLICABILITY: At ' all times.

1 ACTION: ,'

a. With one or re required rosteorolo c.al monitoring channels inoperable for.. e than 7 days, prepar and submit a Special Report to the Comm ssion pursuant to S ecification 6.9.2 within the next 10 days ou ining the cause f tne malfunction and the plans for restoring t e channel (s) o OPERABLE status.

b. DELETED l SURVEILLANCE REQUIRENENTS

/ 1

) eorological mo itoring instrumentation 4.3.3.4 Each of the above channels shall be demonstrat OPERABLE by the erformance of the CHANNEL CHECK and CHANNEL CAllBRAT at the frequencies shown in Table 4.3-5.

Amendnent No. # 5,1 HADDAN NECK 3/4 3-30 0417

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\ TABLE 3.3-6 NETEOROLOGICAL NONITORING INSTRUNENTATION l

l l-NININUN

! INSTRURCNT/ LOCATION OPERABLE

1. Wind ed l

a. B ine Elev. 33' 1 i

b. Nomin Elev. 200' 1

2. Wind Direction

a. Biseline Elev. 33' 1

b. Nominal Elev.196 1

3. Air Temperature

a. Baseline Elev. 33' 1

4. Delta T*

a. Nominal Elev.120' 1

b. Nominal Elev. 200' 1 i

• Delta T is the air t erature of the n inal elevation minus the air temperature at the 33 baseline elevation.

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l HADOAM NECK 3/4 3-31 Amendment No. M ( 3 0417 i

1 I

TABLE 4.3-5 METEOROLOGICAL NONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l

INSTR ENT/ LOCATION CHANNEL CHECK CHANNEL C BRATION

1. Win Speed

a. B eline Elev. 33' D SA

b. Nomi 1 Elev. 200' D <

2. Wind Directi

a. Baseline v. 33' D SA

b. Nominal Elev. 6' D SA l

3. Air Temperature

a. Baseline Elev. 33' D SA

4. Delta T*

a. Nominal Eley.120' D SA

b. Nominal Elev. 200' SA

• Delta T is the air temper ure of e nominal elevation minus the air temperature at the 33' ba line elevat n.

AmendmentNo./ff,\ 193 MADDAN NECK 3/4 3-32 s 1

0417

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ECTIONS 3.3.3.5, 4.3 .5; l

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TAB S 3.3-7, 3.3- 4.3-6; I,

PAGES 3/4 3 THROUGH 3/4 3-43 j I

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HADDAM. NECK )

0417 {

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INSTRUNENTATION 10 ACTIVE LIQUID EFFLUENT NONITORING INSTRUNENTATION L TING CONDITION FOR OPERATION 3.3.3. The radioactive liquid effluent monitoring instrumentation  !

channel shown in Table 3.3-9 shall be OPERABLE with applicable Ala / Trip .

Setpoints et to ensure that the limits of Specification 3.11.1.1 are t exceeded. he Alarm / Trip Setpoints shall be determined in accordance ith methodology nd parameters described in the f)FFSITE DOSE CALCULAT N MANUAL (ODCH).

APPLICABILITY: t all times *.

ACTION:

a. With a radi ctive liquid effluent monitoring ' strumentation channel Ala Trip Setpoint less conservativ than required by the above specific tion, without delay suspend e release of <

radioactive liq d effluents monitored by he affected channel, or declare the chan 1 inoperable, or chang the Alarm / Trip Setpoint so it is acceptabl conservative. [

lJ

b. With the number of ch nels less th the minimum channels operable {

requirement, take the TION shown n Table 3.3-9. Exert best efforts to restore the operabl monitor to OPERABLE status within 30 days, and, if unsucces #ul, plain in the next Annual Effluent ,

s not corrected in a timely manner.

~

Report why the inoperabili1 Releases need not be termin d after 30 days provided the specified actions are continued.

c. DELETED l SURVEILLANCE REQUIRENENTS 4.3.3.7.1 Each radioactiv liquid effluent monit ing instrumentation channel shall be demonstr ed OPERABLE by performanc of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CA BRATION, and ANALOG CHANNEL PERATIONAL TEST operations at the freq ncies shown in Table 4.3-7.

i

• At al times means that channel shall be ODERABLE and in serv e on a cont uous, uninterrupted basis, except that outages of monito ng channels are l itted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purposse o maintenance pe'd a performance of requwed tests, checks, calibrations or samplin HADDAN NECK 3/4 3 44 Amendment No. JU,179,19 0418

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TABLE 3.3 9 (Continued)

ACTION' STATEMENTS ACTION 6 -

With the number of channels OPERABLE less than requi d by the Minimum Channels OPERABLE requirements, efflu t releases may continue provided that best efforts are made o repair the instrument and that prior to initiating a r ease:

a. At least two independent samples of the tank to be discharged are analyzed in accordanc with Specification 4.11.1.1.1. and;

b. original release rate calcul ions and discharge va ving are independently verif ed by a second indi idual.

ACTION 47 -

DELETED l

ACTION 48 -

With the number. channels ERABLE less than required by the Minimum Chan s OPE LE requirement, effluent releases

,7 3, via this pathway ma co inue provided that best efforts are f"I'l made to repair the in ument and that once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> grab samples of the serv c water effluent are collected and

~

analyzed for gross adio tivity (beta or gamma) at a lower limit of detection f at le t 3 x 10 microcuries/ml.

l ACTION 49 -

With the number of channels OP LE less than required by the Minimum annels OPERABLE r uirement, effluent releases via this pa ay may continue pro ided that best efforts are made to air the instrument a that the flow rate is estimat once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during ctual releases. Pump perfo nce curves generated insitu ma be used to estimate

. Ow.

d dilj HADO ECK 3/4 3 46 Amendment No.4267 3 j .

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TABLE 4.3-7 (Continued 1 TABLE NOTATION

( CHANNEL CHECK need only be performed daily when discharges are made -

from this pathway. The CHANNEL CHECK should be done when the discharge l is in process. '

(2) NEL CALIBRATION ~ shall be performed using a known radioactive liqui or olid source whose strength is determined by a detector which has i bee calibrated to an NBS source. The radioactive source shall be na i known reproducible geometry, i (3) The ANA CHANNEL OPERATIONAL TEST shall also demonstrate th control room ala annunciation occurs if any of the following condi ons exist-

1. Instrume indicates measured levels above the ala trip ')

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'setpoint.

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2. Instrument i icates a downscale failure or ci cuit failure. E

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(3. Instrument cont is not set in operate mod . j l

(4) Pump status should be c cked at least once r 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the l

purpose of determining f w rate.

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• tomatic isolation shall also be demonstrated annually for the t t tank discharge monitor line. l 3/43-48 Amendment No. # 5,1 4 )

. HA u,DDAN NECK w ._ . l

L I l INSTRUNENTATION RADI0 ACTIVE GASE0US EFFLUENT NOMITORING INSTRUNENTATION '

ITING C0lGITION FOR OPERATION i N 3.3. .The radioactive gaseous effluent monitoring instrumentation channe lshown in Table 3.3-10 shall be OPERABLE with applicable Alarm l Setpoin set'to ensu'e r that the limits of Specification 3.11.2.1 are ot exceeded. The.setpoints shall.be determined in accordar.ce with the methodolog and parameters as described.in the 00CN.

j APPLICABILITY. At all times *, l ACTION:-

a. With a ra loactive gaseous effluent monitoring i trumentation l channel Al Setpoint less conservative than r quired by the above l Specificati , without delay suspend.the rele- e of radioactive gaseous efflu ts monitored by the affected aannel, or declare the

channel inoper le, or change the Alarm Se oint'soitisacceptablyl .i' l conservative.

l

b. With the number of hannels less than e minimum channels operable requirement, take th ACTION shown i able 3.3-10. . Exert best efforts to restore th inoperable itor to OPERABLE status within 30 days and, if unsucc sful, exp1 in in the next Annual Effluent Report why the inoperabi ity was ot corrected in a timely manner.

l Releases need not be term ated after 30 days provided the specified actions are cont u .

l c. DELETED l-SURVEILLANCE REQUIREMENT L 4.3.3.8.1 Each radioactive seous effluent nitoring instrumentation l channel shall be demonstrat OPERABLE by perfo ance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALI TION, and ANALOG C EL OPERATIONAL TEST operations.at the frequen es shown . in Table 4.3-8.

'* At all ines means that the channel shall be OPERABLE and service on a conti ous basis, except that outages of monitoring channels are l pe tted for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> each time for the purpose f ma tenance and performance of required tests, checks, calibra ons.

l HADDAM NECK 3/43-49 Amendment No. JU,177,1 om E.

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l TABLE 3.3-10 (Continued)

. ACTION STATEMENTS g ACT ON 50 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, releases via e Waste Gas Holdup System may continue provided that best

., efforts are made to repair the instrument and that pr r to j initiating the release:

(a) For the tank to be discharged, at least two i dependent samples of the tank's contents are analyzed; d, (b) The release rate calculations and discharg valve lineups are independently verified by a s cond individual.

Othe ise, suspend releases from the Wast Gas Holdup System.

Release from. all pathways other tha the Waste Gas Holdup System a continue provided , grab s les are taken at least once per hours and these sampi are analyzed for gross radioactivi within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 51 -

With the numbe of channels 0FE LE less than required by the Minimum Cha els OPERABLE quirement, effluent releases via this pathway ay continu provided that best efforts are made to repair the nstrume and that samples are continuously collec d wi auxiliary sampling equipment for periods of seven (7) d s and analyzed for principal gamma emitters with half liv greater than 8 days within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the end of the ling period. Auxiliary sampling shall be establishe with 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of declaring the channel INOPERABLE.

ACTION 52 - With the number f channels O RABLE less than required by the Minimum Ch nels OPERABLE r uirement, effluent releases via this path ay may continue pr ided that the best efforts are made to repair the instrumen and that the flow rate is estimated ce per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

HADDAM NECK 3/43-51 Amendment No. M I,193 ous

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TABLE 4.3-8 (Continued 1 TABLE NOTATION (1) C NNEL CHECK daily when releases exist via this pathway.

(2) Cal ration shall be performed using a known source whose streng is dete ined by a detector which has been calibrated to an NB source.

These urces shall be in a known, reproducible geometry.

(3) The CHAN L FUNCTIONAL TEST shall also demonstrate that co rol room alarm annu iation occurs if any of the following conditi s exist:

a. Instrime t indicates measured levels above the Al Setpoint. l

b. Instrument ndicates a downstale failure or ci uit failure.

c. Instrument co rols not set in operate mode P

I i .

Amendment No. y J, 93

, HADDAN NECK 3/43-53 one

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I SECTI 3.3.3.9, 3.3.4, 4.3.3.9.1, .3.4; i TABLE 3.3-11; AND PAGES 4 3-54 THROUGH 4 3-57 LETE l

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SECTIONS 3.6 AND 4.6 ONTAINMENT SYSTEMS DELETED THEIR TIRETY ~

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NECK

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A SECTIONS 3.7.1 THROUGH 3.7.4; CTIONS 4.7.1 THROUGH 4.7.4 BLES 3.7-1 THROUGH 3.7-TABL 5 4.7-1 THROUGH 4.7-2* AND PAGE 3/4 7-1 THROUGH 3/4 -13 DELETED J

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i NECK PLANT L-- . .

SYSTEMS 3/ 7.5 SEALED SOURCE CONTAMINATIQM LIMI11 ColWITION FOR 0FERATION s

J 3.7.5 ch' sealed source containing radioactive raaterial eit r in excess of 100 micro uries of beta and/or gama emitting material or 5 crocuries of l alpha emittin material shall be free of greater than or equal o 0.005 i microcurie of movable contamination. {

APPLICABILITY: At 11 times.

ACTION:

a. Each sealed urce with removable contamina on in excess of the  ;

above limits s all be immediately withdraw from use and either: I

1. Decontamina and repair the sealed source, or 4

2. Dispose of th sealed source in cordance with Commission Regulations.

b. DELETED SURVEILLANCE REQUIREMENTS ,

4.7.5.1 Test Requirements - Each se e source shall be tested for leakage and/orcontaminationby:

a. The licensee, or

b. Other persons specifi 11y authorize by the Conmiission or an 1 l

Agreement State.

The test method s 11 have a detection s sitivity of at least 0.005 microcurie er test sample.

4.7.5.2 Test Frequenci s - Each category of sealed urces (excluding) startu) sources and fis ion detectors previously subjec d to core flux j shall >e tested at the frequency described below.

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a. Sources i use - At least once per 6 months for a 1 sealed i

- sources ntaining radioactive materials:

1) th a half-life greater than 30 days excluding Hydrogen 3), and

2) In any form other than gas.

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4 AN NECK 3/47-14 Amendment No. J M. 93

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SECTIONS 7.6.THROUGH .7.12; SECTIONS 4.7. THR 4.7.12; TABLES 3.7-3 TH 3.7-6; AND PAGES3/47-16 HR GH 3/4 7-36 ]

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SYSTEMS 3/4 5 SEAtEn SOURCE CONTAMIN&IJ9H SURVE! E REQUIREMENTS (Continued) l

b. S red sources not in use - Each sealed source and fis ion i

det tor shall be tested prior to use or transfer to nother lice ee unless tested within the previous 6 months Sealed sourc and fission detectors transferred without certificate '

i indicat g the last test date shall be tested pri r to being placed i o use; and I c. Startup sou es and fission detectors - Each ealed startup ;1 l

source and f sion detector shall be tested ollowing repair or maintenance t the source. ll h

4.7.5.3 Reports - A re)o shall be prepared and submitted to the j Commission on an annual aasa if sealed source or fission detector leakage 1 l tests reveal the presence of reater.than or eq 1 to 0.005 microcurie of i removal contamination. 1 I

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l Amendment No. J U. 3 NECK 3/4 7-15

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SEC ONS 3.13 4.8 ELECTRIC POW SYSTEMS DELETED I THE ENTIRETY .

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4.9-REFUELING OPERATIONS 3/ .1 BORON CONCENTRATION itury enunivinu ran nornartnu- _

3.9.1 e boron concentration of all filled unisolated portions of t Reactor Co lant System and the refueling canal shall be maintained un orm and suffici t,to ensure a K, of 0.94 or less.

APPLICABILITY: MODE 6*.

ACTION:-

With the requiremen of the above specification not satisf d, insnediately suspend all operatio involving CORE ALTERATIONS or posit e reactivity changes and initiate a continue boration at greater tha or equal to 30 gpm of a solution conta ing a minimum of 14000 ppm bor or its equivalent until K, is reduced to 1 s than or equal to 0.94, ciavriiiauer nrnisterurutt _

4.9.1.1 The above reactivity ondition shall be etermined prior to:

a. Removing or unbolting the reactor v ssel head, and

b. Withdrawal of any contr rod in xcess of 3 feet from its fully inserted position within er ctor vessel. except when control rod drag testing is being r reed, at which time the reactivity condition shall be determin prior to the first control rod withdrawn in excess of 3 fe t nd every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> thereafter until completion of the testing 4.9.1.2 The boron concentration o the Reac r Coolant- System and the refueling canal shall be determin by chemica analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

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• The reactor shall be ntained in MODE 6 who ver fuel is in the i reactor vessel with t vessel head closure bol s less than fully tensioned or with t head removed.

f Amendment No. I,193 NECK 3/49-1

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f rrUELING OPERATIONS 3 9.2 INSTRUNENTATION upt un enamtvinu rna nornartnu _ i 3.9.2.a As a min!aum, two Source Range Neutron Flux Monitors shall be OPERABLE nd operating, each with continuous visual indication in the control ro and one with audible indication in the containment and c trol room when C E ALTERATIONS or positive reactivity changes are takin place.

When CORE AL RATIONS or positive reactivity changes ara not takin< place, at least one urce Range. Neutron Flux Monitor shall be OPERABLE id operating with- visual indication in the control room and audi e indication in-th containment.

3.9.2.b As a mi imum, two Source Range High Neutron Lev Alarms (Containment Evacuat n) shall be OPERABLE and operating w h a minimum logic to audibly ala in both the control room and cont ment of one (1) of two (2).

APPLICABILITY: MODE 6.

ACTION:

a. With one of the abo e required moni rs inoperable or not operating, immediately suspend 1 operations nvolving CORE ALTERATIONS or positive reactivity c nges.

'b. With both of the require moni rs inoperable or not operating, determine the boron conce ra ion of the Reactor Coolant System at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

movrtiimuer nrnnvarur m , .

4.9.2 Each Source Range Neutron ux Monit shall be demonstrated OPERABLE by performance of:

a. A CHANNEL CHECK at east once per 12 ours,

b. An ANALOG CHANN OPERATIONAL TEST with n 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to the initial start f CORE ALTERATIONS, and

c. An ANALOG C EL OPERATIONAL TEST at leas once per 7 days.

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Amendment No. JJJ. JJ J%$,193 NECK 3/49-2

1 REFUELING OPERATIONS 3 9.3 DECAY TINE LIMI ColWITION FOR OPERATION

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3.9.3.a e}eactor shall be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />. ,

3.9.3.b Ir diated fuel .shall remain in the reactor vessel fo at least the time equired in Figure 3.9-1 prior to movement to t e spent fuel pool.

APPLICABILITY: Du ing movement of irradiated fuel in the re tor vessel.*

l ACTION:

a. With the reactor bcritical for less than 100 ho s, suspend all operations involving movement f irradiated fuel in the re tor vessel.

b. With the combination reactor hold time and ooling water temperature in the unacceptable region of Figure 3.9-1, sus end all operations involving l movement of irradiated f 1 from the react vessel to the spent fuel pool until the combination of actor hold ti and cooling water temperature return to the. acceptable re ion of Figur 3.9-1.

SURVEILLANCE REQUIRENENTS l l

l l  !

The reactor shall be determ e to have been subcritical for at

! 4.9.3.1 l 1 east 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of t da and time of subcriticality prior I to movement of irradiated fuel in t e reac r vessel.

l 4.9.3.2 Verify that the combin ion of reac r hold time and cooling water temperature are in the acceptab region of F1 re 3.9-1 prior to and at least l

once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during tran er of irradiated el from the reactor vessel to the spent fuel pool.

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• Specif cation 3.9.3.b does not apply if less than 53 fuel assemblies are tran ferred to the spent fuel pool, NECK 3/4 9-3 Amendment No. J M , p,193 j

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CCEPTABLE f/ REGION f/

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164 188 212 236 260 264 308 3 356 380 140 REQUIRED IN-CORE DECAY TIME (HOURS)

FI 3.9-1 REqu! RED REACTOR HOLD TIME FOR A FULL CORE OF GAD NECK 3/4 9-3a Amendment No. $d193

FUELING OPERATIDjE 3 .4 CONTAINNENT BUILDING PENETRATIONS ivur enunrrinu ran opreartnu

-3.9.4- e containment building penetrations shall be in the follow g  :

status:

a. Th equipment hatch installed and secured in place,

b. A mi mum of one door in the airlock is closed,_ and

c. Each pe tration providing direct access from the ontainment ,

atmosphe to the outside atmosphere shall be, ther:

1) Closed y an' isolation valve, blind flan , manual valve or ,

special evice, or z

2) Be capable f being closed by an OPE BLE containment purge supply, pur exhaust, or purge exh st bypass isolation valve.

nt of irradiated fuel within APfLICMILIII: During CORE ALT TIONS or mov the containment.

ACTION:

With the requirements of the above sp i ication not satisfied, timediately suspend all operations involving CORE TERATIONS or movement of irradiated fuel in the containment building, oth an placing an irradiated fuel assembly into a safe storage locatio '.

f l SRMEILLANCEJEgillRFuyun .

4.9.4 Each of the above requ ed containment' uilding penetrations shall be determined to be either in ts closed / isolate condition or capable of being closed by an OPERABLE ontainment purge sup y, purge exhaust, or purge exhaust bypass isola on valve or capable of eing closed by an OPERABLE airlock door wit n 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the tart of and at least once per 7 days during C E ALTERATIONS or movement o irradiated fuel in the containment buildi by:

a. Verifying a penetrations referred to in Speci ication 3.9.4c are in their losed/ isolated condition,  ;

b. Testi the containment purge supply, purge exhaust, and purge exha t bypass isolation valves in accordance with S cification '

4.9 , and I V rifying that at least one of the doors in the airlock capable c.

f being closed.

Amendment dp,193 AM NECK 3/494

f KFUELING OPERATIONS l 3/ 19.5 COMMUNICATIONS 11mf7Incenuntrrnsrannornartnu ,

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3.9.5 rect communications shall be maintained between the contr 1 room and person el at the refueling cavity manipulator crane area. ,

APPLICABILIT During CORE ALTERATIONS.

ACTION:

With the requireme s of the above specification not satis ied, immediately suspend all operati s involving CORE ALTERATIONS or mov nt of irradiated fuel in the containee t bui,lding other than placing an radiated fuel assembly into a safe s rage location.

titevrfil aNcr e$allTRFMrNTE , ,

4.9.5 Direct communications tween the contro room and personnel at the '

refueling cavity manipulator c ne area shall demonstrated within I hour ,

, prior to the start of and at lea.t once per 1 ours during CORE 1

, ALTERATIONS. l i

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l HAD NECK 3/4 9-5 Amendment No. 8% 193 use h-

pn ELING OPERATIONS 3/4 .6 MANIPULATOR CRANE itury enuntrunu ran nornatinu _

3.9.6 manipulator crane and auxiliary hoist shall be used for vement of control od-drive shafts

• or fuel assemblies and shall be OPERA E with:

-a. The anipulator crane used for movement of fuel assem ies haviag:

1) minimum capacity of 1650 pounds, and

2) An erload cut off limit less than or equa to 175 pounds abov the indicated weight for wet conditi s for a stainless steel lad fuel assembly with a full len 1 RCCA inserted.

b. The auxiliary oist used for latching and u atching control rod drive shafts ha ing a minimum capacity of 00 pounds.

APPLICABILITY: During mov t of control rod dri shafts or fuel assemblies within the rea or vessel.

ACTION:

With the requirements for crane an or hois OPERABILITY not satisfied, place any fuel' assembly or control r i in ransit into a safe storage location and suspend use of t 4 operable manipulator crane and/or auxiliary hoist from oporations involv' the movement of control rod drive shafts or fuel assemblies within the r a tor vessel.

clinwrrii muer nrniiforururc , .

4.9.6.1 Each manipulator crane sed for mov nt of fuel assemblies within the reactor vessel shall be d strated OPERA E within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations performing a loa test of at least 2063 exceeds 175 pounds above th indicated weight for t conditions for a stainless steel clad fuel ssembly with a full lengt RCCA inserted.

4.9.6.2 Each auxiliar hoist used for movement of con rol rod drive shafts I j

within the reactor ves el shall be demonstrated OPERABLE ithin 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of such operations. If loads greater an the weight of a stainless stes clad fuel assembly with an RCCA insert d are to be lifted l withi- the reactor essel with the auxiliary hoist then a lo test will be  !

performed for 12 of the weiglit of the load to be lifted.

• The RCCA' may be attached to the control rod drive shafts ring some refueli evolutions.

Amendment No. II,193

. NECK 3/4 9-6

=:.aa= -w ..= ~- -

J OPERATI m >

3/4.9.7 CRANE TRAVEL - SPENT Flirt STfleAIE tull. DING f r i TAffffMR PAAElfTinti/Wae ADFRATfatl _

3.9.7 Loads hexcesDof,2L pounds shall be prohibited from travel over

-fuelassembliesinthe{tt::: pool. ^

APPLICABILITY: With fuel assemblies in the -t r:;; pool. A '

ACTION: -

a. With the requirements of the above specification not satisfied, place.the crane load in a safe condition.

b. TS: prri:ier: :( !;::!ffettie: ?.0.? re ::t ;;!!: 910.

enavrfiianser nrntiferurutt 4.9.7 Administrative controls that prevent the travel of loads in ::::=-

pounds __over fuel assemblies shall be in place prior to lifting a load a ::::'-Y @ 1"" pounds.

}l800 N IS8 lU l Amendment No. 4H ,193 HADOAN NECK 3/4 9-

FUELING GPERATIONS l3/ .8 RESIDUAL HEAT REMOVAL Ale C0OLANT CIRCULA110N HIGH TER LEVEL ifurtrun\nuntrinurnenornartnu ,

3.9.8.1 A least one RHR LOOP shall be OPERABLE and in operation.

APPLICABILITY: _ E 6, when the water level is greater than or.e al to 23 et above the top of the reactor vessel flange.

l ACTION:

With no RHR LOOP OPE LE and in operation, suspend all o rations involving an increase in the rea or decay heat load or a reductio in boron l concentration of the Rea tor Coolant System and immedia ly initiate corrective action to retu the required RHR LOOP to ERABLE and operating i status as soon as possible. Close all containment p etrations providing i direct access from the conta ment atmosphere to th outside atmosphere l within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, j tisavrrii aner nrntif erururs . .

4.9.8.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> erify at least one RHR LOOP is in

operation and circulating reactor cool t t a flow rate of greater than or equal to 2000 gps.

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• The RHR LOOP may be remo from operation fo up to I hour per 8-hour l period during the perfo ance of CORE ALTERATI 5 in the vicinity of the reactor vessel h legs.

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u Amendment No. W,193 L NECK 3/49-8 l-1 l

i FUELING OPERATIONS L0 ATER LEVEL itutT\cenuntrinurnanornatinu ,

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3.9.8.2 wo-independent RHR LOOPS shall be OPERABLE, and at least ne RHR .

LOOP shall in operation. l APPLICABILITY: DE 6 when the water level is less than 23 feet bove the i p of the reactor vessel flange. l1 ACTION:

With less t n th.e required RHR LOOPS OPERABLE immediately h a.

initiate cor ctive action to return the requ ed RHR LOOPS to [

OPERABLE statu or establish greater than o equal to 23 feet of water above the eactor vessel flange, as on as possible.

b. With no RHR LOOP i operation, suspend a operations involving a l reduction in boron c ncentration of the eactor Coolant System and  !

immediately initiate rrective actio to return the required RHR l LOOP to operation. C1 e all contai nt penetrations providing .;

direct access from the c tainment tmosphere to the outside ,

atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

umvrtiiaw r erntirnrurutt ,

4.9.8.2.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> e fy at least one RHR LOOP is in operation and circulating reactor coo ant a flow rate of greater than or J equal to 2000 gpm.

4.9.8.2.2 The RHR LOOP not in o eration shall be determined OPERABLE at least once per 7 days by verifyi g correct break alignments and indicated power availability.

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Amendment No. 1 ,193 AN NECK 3/49-9

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FUELING OPERATIONS 3/ .9 CONTAINNENT PURGE SUPPLY. PURGE EXHAUST. AND PURGE EXHAUST BYP S ISOLMION SYSTEM l itufTT enuntTinu ran nornartnu /

3.9.9 Th containment purge supply, purge exhaust, and purge e aust bypass isol ion valves shall be OPERABLE.

APPLICABILITY: uring CORE ALTERATIONS or movement of irradi ed fuel within e containment.

ACTION:

a. With the re irements of the above specifica on not safistied, immediately s spend all operations involvin CORE ALTERATIONS or movement of ir diated fuel in the contai nt building, other than placing an tradiated fuel assembly nto a safe storage ,

location. l

b. The provisions of Sp cification 3.0.3 are not applicable.

clavrtiiaurr nrnattnrururs . ,

4.9.9 The containment purge suppl pur exhaust, and purge exhaust bypass isolation valves shall be vert te OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 d during CORE ALTERATIONS and prior to movement of irradiated fuel within tainment by verifying that containment purge, bypass or exhaust sol tion valves are accessible for manual operation or verifying that e ass iated penetrations are blind fl anged.

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1 Amendment No. ,193 NECK 3/4 9-10

I' t

L UELING OPERATIONS

, 3/4 10 WATER LEVEL - REACTOR YESSEL itutTT enuntrinu ren nornartna ,

I 3.9.10 A least 23 feet of water shall be maintained over the top f the reactor ves 1 flange.

APPLICABILITY: uring movement of fuel assemblies or control ro within the l '

ntainment while in MODE 6.

ACTION:

I i

With the requirements of the above specification not sati ied, place any 1 fuel assembly or contr rod in transit into a safe stor ge location and ,

i suspend all further ope tions involving movement of f 1 assemblies or control rods within the r actor vessel.

siinvrti i auer nrntif nrururt 4.9.10 The water leval shall determined to e at least its minimum l required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> pri to the st t of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movement o fuel ass blies or control rods.  ;

l Amendment No. 5,193 AM NECK 3/49-11 1

SPENT fMSL DU/LDIAIG-F11EEfMG'9PERATIONS -

" A gg u Tn n T u 3.9.11 At leg 4 20 feet of water shall be maintained over the top of jr.r.ad+etstrfu assemblies seated in the s.tneege racks.

?

APPLICABILITY: Whenever W fue assemblies are in the $2eetprpool. j ACTION: gmYfue/ /* 9'AY b*

uspend (

With the requirements of the above specification not satisfied, i all movements of fuel assemblies and crane operations with loads 4-4he  !

'=1 stae::: are s andVrestore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. i S. " : pr=t:ter: Of S;: i'ie:tien 3.0.? r : :t 1;;110 ble.

O trinvr11 i auer nrntif eruruTs 4.9.11 The water level in the pool sha3 be determined to be at least its minimum required at least once per 7 days when irra fuel assemblies are in th .mel ste..se pool.

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Amendment No. If!I,193 HADDAN NECK 3/4 9

i MEFUELING OPERATIONS 3 .9.12 FilEL STORAGE BUILDING AIR CLEANUP SYSTEN LIN NG COMITION FOR OPERATION '

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3.9.12 The Fuel Storage Building Air Cleanup Systeta shall be OPERABLE nd in operat n.

APPLICABILI  :.During operations involving movement of fuel within e storage pool or crane operation with loads over the storage ool.* g i

ACTION: ,

a. With the el Storage Building Air Cleanup System noperable, or not operati , suspend all operations involving vesents of fuel within the s rage pool or crane operation with oads over the storage pool. \

b. The provisions o Specification 3.0.3 are n applicable.

SURVEILLANCE REQUIRENENTS l l

4.9.12 The Fuel Storage Building ir Cleanup -ystem shall be demonstrated

-OPERABLE and in operation:

a. At least once per 18 months ( after any structural maintenance on the HEPA filte charcoal adsorber housings, or (2) following painting, fire, chemical release in any ventilation zone communicati w h the system by:

1) Verifying that the c1 nup sys em satisfies the in-place penetration and byp s leakage sting acceptance criteria of less than 1% and u s the test p cedure guidance in Regulatory Positi s C.5.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revi ion 2, March 1978, and the system flow rate is 4000 cfm i  ;

Verifying, w hin 31 days after remova that a laboratory 2) analysis of a representative carbon samp obtained in accordanc with Regulatory Position C.6.b f Regulatory Guide 1.52, Re sion 2, March 1978, meets the la ratory testing criteri of Regulatory Position C.6.a of Reg latory Guide 1.52, evision 2, March 1978, for a methyl to de penetration of less han 10% at test conditions of 86*F, 95% lative hun ity atmospheric pressure, and 40 feet / min f a velocity in accordance with ASTN D3803; and

3) erifying a system flow rate of 4000 cfm i 10% durin system operation when tested in accordance with ANSI N510-19 .

• The abov specification does not apply during movement of fuel storage ra ved modules into or out of the SFP during the cycle 19 rerack, provided an app safe 1 ading path is established with no loads over stored fuel assemblies.

Amendment No. #5, ,193 NECK 3/4 9-13

REbLINGOPERATIggi cievr\i mer ornmorurm (canHnna,n

b. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verify g, Ithin 31 days after removal, that a laboratory analysis of a r 2resentative carbon sample obtained in accordance with Re latory Position C.6.b of Regulatory Guide 1.52, Revisi 2,

Mar 1978, meets the laboratory testing criteria of Regu tory Post on C.6.a of Regulatory Guide 1.52, Revision 2, Mar 1978, for a thyl iodide penetration of less than 10% at tes conditi s of 86'F, 95% relative humidty, atmospheric ressure, and 40 f t/ min, face velocity in accordance with AS D3803.

c. At least on a per 18 months by:

1) Verifyin that the pressure drop across th combined HEPA filters a charcoal adsorber banks is le than 6 inches Water Gauge while operating the system a a flow rate of 4000 cfm i 10%, a

2) Verifying that he system maintains e spent fuel storage pool area at a n ative pressure of reater than 0 inch Water Gauge differentia relative to the outside atmosphere during system operation.

d. After each complete or par ial rep 1 ement of a HEPA filter bank, by verifying that the clean syst satisfies the in-place penetration and bypass leaka te ing acceptance criteria of less than 1% in accordance with AN 510-1980 for a DOP test aerosol while operating the system at flow rate of 4000 cfm i_10%; and

e. After each complete or parti re acement of a charcoal adsorber bank, by verifying that th cleanup system satisfies the in-place penetration and bypass le age testi acceptance criteria of less than 1% in accordance wi ANSI N510- 80 for a halogenated .

l hydrocarbon refrigerant est gas while perating the system at a flow rate of 4000 cfm i 1 l

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Amendment No. J M , ,193 NECK 3/49-14 t

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i p~ - m SysNT FUSL U H- 91Ulr

,REF M _ PERATIONS p

3/4.9.13 NOVEMENT OF FUEL IN SFENT FUEL POOL LINITING C0lWITION FOR 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 i a boron concentration of greater th:  :;; 1 te 800 ppa.

APPLICABILITY: Whenever a fuel assembly is moved in the spent fuel pool.

EM* >

With the boron concentration '::: 'h:n 800 ppm, suspend the movement of all fuel in the spent fuel pool.

A k j t

b SURVEILLANCE REQUIREMENT ,

4.9.13 Verify that the boron concentration is gr::t:r th:I..Or:;t: 1 t: 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to any vesent of a fuel assembly in the spent fuel pool and every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafte . i gg fael Mvemeb

+

HADDAN NECK 3/49-g AmendmentNo.f7I.193 L - __ _

^

Sf&U NN V'Y

/t 3/4.9.14 SPDfT FUEL P0OL , TIVITY CONDITION LINITING CONDITION FOR OPERATION 3.9.14 The activity ndition of the spent fuel pool shall be such that K., is Gess-tn3 equal-ty 0.95 at all times.

APPLICABILITY: Whenever fuel is in the spent fuel pool.

ACTION: .6 Immediately 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 REQUIRENENT 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) and  !

Figure 3.9-3 (Region 3) by checking the assersbly's design and burn-up documentation. Region locations are shown in Figure 3.9-4. -

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Amendment No. J7J. M193

? HADDAM NECK 3/4 9-[

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3.0 3.5 4.0 4.5 5.0 AVERAGE ASSEMBLY INITIAL NOWINAL ENRICHWENT ',WT I - U235)

FIGURE 3.9-2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2 S

Amendment No. 177, 19f,193 HADDAM NECK 3/49-)T

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AVERAGE ASSEMBLY INITIAL NOWINAL ENRICHWENT (WT I - U235) f j FIGURE 3.9-3 SPENT FUEL P00L RACK MINIMUM BURNUP REQUIREMENTS,FOR REGION 3

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HADOAM NECK 3/4 9- Amendment No. M . M 193

REGION 1 .

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- REGION 3 1 4-- N I

FIGURE 3.9-4 SPENT FUEL POOL RACK REGION LOCATIONS h

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!! Amendment No. M 193 HADOAN NECK 3/4 9

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\RUELING OPERATIONS 3/4 15 SPENT FUEL POOL C0OLING J LIMITI CONDITION FOR OPERATION 3.9.15 Th spent fuel pool cooling system shall be OPERABLE wit .

l

a. oth spent fuel pool cooling pumps OPERABLE an at least one i ent fuel pool cooling pump and the plate he t exchanger in I op ration, and l

b. Spen fuel pool temperature less than 150 d rees F.

APPLICABILITY: MODE 6, uring transfer and storage of ir adiated fuel from the  !

reactor essel to the spent fuel ol for a full core l offl oad.*

ACTION: With less than the equired equipment OPE LE and in operation or with i spent fuel pool temperature g eater than 150 degr s F, suspend all operations )

involving the addition of irra iated fuel to th spent fuel pool and initiate corrective action to restore t spent fuel p ol cooling system to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.9.15.1 Prior to movement of irradia fuel to the spent fue! pool, verify that both spent fuel pool cooling pumps lined up to provide flow to the piate heat exchanger.

4.9.15.2 At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> , verify hat at least one spent fuel pool cooling pump is running.

4.9.15.3 At least once per 12 urs, verify that e spent fuel pool temperature is less than 150 degrees F. ,

I

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• Speci cation 3.9.15 does not apply if less than 53 fuel assemblies are tra ferred to the spent fuel pool.

Amendment No. 1 93 AN NECK 3/49-20

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"~ wDv 3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED LIMITINQ_GDNDITIONS FOR OPERATION I

3.9.16 The spent fuel pool coolant temperature shall be maintained at

-1n' e to150digrees3 6 v l j

APPLICABILITY:

1 Whenever ip fuel assemblies are stored in the spent fuel pool. .

ACTION:

1 With the spent fuel pool coolant temperature not within limit:

a. Immediately initiate action to restore the spent fuel pool coolant g temperature to within limit, and (.

b. Immediately verify that a spent fuel pool makeup water source is

~

available, and j Within 7 days, restore the spent fuel pool coolant temperature to  !

c.  !

within the limit.

i SURVEILLANCE REQUIREMENTS 4.9.16 At least once per 24_ hours verify that the s nt fuel pool coolant temperature isQess t)wtfr eqp 150 F.

x *F 3/4 9 Amendment No.193 HADDAM NECK

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SECTIONS 3.10 AND 4.10 S CIAL TEST EXCEPTIONS D$LETE IN THEIR ENTI TY l

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1 AN NECK PLANT

l3 .11 RADI0 ACTIVE EFFLUENTS

'3/4 1.1 LIQUID EFFLUENTS CONC TION LIMITING iTION FOR OPERATION l

3.11.1.1 The oncentration of radioactive material released rom the site

-(see Figure 5.1 ) shall not exceed the concentrations speci ied in 10 CFR Part 20, endix B. Table II, Column 2 for radionu ides other than i dissolved or entra ed noble gases. For dissolved or en ained noble gases, the concentr ion shall not exceed 2 x 10 microc /ml total activity.

APPLICABILITY: At all t s.  :

l i

ACTION:

With the concentration of ra onctive material . leased from the site exceeding the above limits, re tore the conce ration to within the above limits within 15 minutes.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid waste hall be sampled and analyzed in accordance with the sampling and an ysi program specified in Section I of the REMODCM.

4.11.1.1.2 The results of the adioactive alysis shall be used in accordance with the methods of action II of e REM 00CM to assure that the concentration of the point of .elease are main ined within the limits of Specification 3.11.1.1.

IECK 3/4 11-1 Amendment No. ,193 was

10 ACTIVE EFFLUENTS DOS LIQUIDS l

LIMITI ColWITION FOR OPERATION 3.11.1.2 e dose or dose commitment to any MEMBER OF THE PUB C from radioactive terials in liquid effluents released from the si e (see Figure 5.1-1) shall limited:-

a. Durin any calendar quarter to less than or equ to 1.5 mrem to the tot 1 body and to less than or equal to 5 rem to any organ, and ,

b. During any alendar year to less than or e al to 3 mrem to the total body a to less than or equal to 1 mrem to any organ.

I APPLICABILITY: At all ti .

i

)

ACTION:

a. With the calculated se from the elease of radioactive materials in liquid effluents e eeding an of the above limits, prepare and submit to the Commissio within 0 days, pursuant to Specification 6.9.2, a Special Report ich dentifies the cause(s) for exceeding the limit (s) an d ines the corrective actions to be taken to reduce the release of radioactive materials in liquid effluents during the remai r of the current calendar quarter and during the remainder of t e c endar year so that the cumulative dose or dose commitment o any EMBER OF THE PUBLIC from such release during the cal dar year is within 3 mrem to the total body and 10 aren to a y organ.

b. DELETED l

$URVEILLANCE REQUIREMENTS \

I 4.11.1.2.1 Cumulativ dose contributions from liqui effluents shall be determined in accord ce with Section II of the REMODCM.

4.11.1.2.2 Relat e accuracy or conservatisms of the cal ulations nitoring shall be confirmed by perf nce of the Radiological Environmental Program as detai ed in the REM 00CM.

}

I Amendment No. J 193

! KCK 3/4 11-2

c l'

10 ACTIVE L !LUENTS I

3/4 1.2 GASE0US EFFLUENTS DOSE E l LIMITING OND1 TION FOR OPERATION

[ i

[

I 3.11.2.1 Th dose rate, at any timo, offsite (see Figure 5.1 ) due to radioactive mat rials released in gaseous effluents from the ite shall be limitad to the f lowing values: j

a. The dose rate li.mit for noble gases shall be 1 ss than or equal to l 500 mres/ to the total boiy and less than o equal to 3000 {

mrerg/yr to he skin, and  !

b. The dose rate limit due to inhalation for tritium and for all l radioactive ma rials in particulate fo with half-lives greater than 8 days sha. be less than or equa to 1500 mrem /yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate (s) exceeding the bov limits, decrease the release rate within 15 minutes to comply with the ii it(s) given in Specification 3.11.2.1.

SURVEILLANCE REQUIREMENTS

/ 1 4.11.2.1.1 The release rat , at any time, of oble gases in gaseous effluents shall be contro11 by the of fsite dos rate as established above in Specification 3.11.2.1. The corresponding rel se rate shall be determined in accordance ith the methodology of S tion II of the REMODCM.

4.11.2.1.2 The noble as effluent monitors of Spect ication 3.3.3.8 shall be used to control re ease rates to limit offsite dose within the values established in Spec ication 3.11.2.1.

4.11.2.1.3 The elease rate of radioactive materials in seous effluents shall be deterni ed by obtaining representative samples and erforming analyses in ac rdance with the sampling and analysis program specified in Section I of e REMODCM (Table 0-1). The corresponding dose te shall be determined ing the methodology and parameters given in the 0 (Section II of the DCM).

Amendment No. J,193 HECK 3/4 11-3

j 10 ACTIVE EFFLUQ[Il DOS NOBLE GASES l LIMITI CONDITION FOR OPERATION 3.11.2.2 e air dose offsite (see Figure 5.1-1) due to noble gas released in g seous effluents shall be limited to the following:

a. Durin any calendar quarter, to less than or equal t 5 mrad for gama adiation and less than or equal to 10 mrad f r beta radiati , and

b. During any calendar year to less than or equal o 10 mrad for  :

gama radia on and less than-or equal to 20 ad for beta radiation.

i APPLICABILITY: At all time i ACTION:

a. With the calculated a r dose from ra (cactive noble gases in  ;

gaseous effluents exce ing any of e above limits, prepare and i

submit to the Comissio within 30 days, pursuant to Specification 6.9.2, a Special Report ich id tifies the cause(s) for i exceeding the limit (s) an eft s the corrective actions to be taken to reduce the release o radioactive noble gases in gaseous l effluents during the remaind of the current calendar quarter and l during the remainder of the a ndar year so that the cumulative dose during the calendar y ar in within 10 mrad for gama radiation and 20 mrad for beta ra iation.

b. DELETED l SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Cumulative d se contributions for the cur ent calendar quarter and current calendar year for noble gases shall be dete ined in accordance with Section II of the EM00CM once every 31 days.

4.11.2.2.2 Relativ accuracy or conservatism of the calcu tions shall be confirmed by perfo nce of the Radiological Environmental M itoring Program as ditail d in Section I of the REM 00CM.

5 b.

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l MECK 3/4 11-4 Amendment No. 77 (93

m RAD ACTIVE-EFFLUENTS DOSE 10 ACTIVE NATERIAL IN PARTICULATE l FORN AR RADInamXLIDES OTHER THAN NOBLE GA$Li LIMITING ITION FOR OPERATION ~ f 3'.11.2.3 .The ose to any MEMBER OF THE PUBLIC tritium and r ioactive l materials in pa iculate form with half lives greater than 8 ays in gaseous effluents releas offsite (see Figure 5.1-1) shall be limi d to the following: -

a. Durirg an calendar quarter to less than or ual to 7.5 arem to any organ;

b. During'any ca ndar year to less than or qual to 15 area to any organ.

I APPLICABILITY: At all times. j ACTION:

a. With the calculated do from th release of radionuclides, i radioactive materials i partic ate form, or radionuclides other than noble gases in gase s of uents exceeding any of the above limits, prepare and submit to he Commiission within 30 days, .

I pursuant to Specification 6 .2, a Special Report which identifies the cause(s) for exceeding limit and defines the corrective actions to be taken to r ce he releases.during the remainder of the current calendar qua er a during the remainder of the calendar year so that. e cumula ive dose or dose commitment to any MEMBER OF THE PUB C from suc releases during the calendar year is within 15 nr to any orsa

b. DELETED l o

. SURVEILLANCE REQUIREMENTS .

'4.11.2.3.1 Cumulativ dose contributions for the curr t calendar quarter and current calendar ear shall be determined in accorda e with Section II of the REM 00CM once very 31 days.

4.11.2.3.2 Re1 ive accuracy or conservatism of the calcul ions shall be confirmed by per ormance of the Radiological Environmental Mo toring Program as det led in the REM 00CM.

3/4 11-5 Amanhent No. 5 193 NECK

o l

0 ACTIVE EFFLUENTS 3/4 .3 TOTAL D0SE LIMITI ColGITION FOR OPERATION

)

3.11.3 The ose or dose commitment from the site to a MEMBER THE PUBLIC l 1s limited to ess than or equal to 25 mrem to the total body any organ l (except the th oid, which is limited to less than or equal 75 mrem) over t a period of 12 e secutive months. l APPLICABILITY: At 1 times.

ACTION:

a. With the calc lated dose from the release of radioactive materials in liquid or g eous effluents exceedin twice the limits of I I

Specification 3. 1.1.2, 3.11.2.2, or 3 1.2.3, prepare and submit a Special Report o Commission pursua to Specification 6.9.2 and f limit the subseque t releases such t at the dose or dose i commitment from the ite to any ME ER OF THE PUBLIC is limited to less than or equal t 25 mrem to e total body or any organ (except thyroid, which is limite to less than or equal to 75  ;

ares) over 12 consecuti month . This Special Report shall include an analysis whic de strates that radiation exposures i from the site to any MEMB THE PUBLIC (including all effluent pathways and direct radiati ) are less than the 40 CFR Part 190 Standard. If the estimate ses exceed the above limits, the l special report shall inc1 de a request for a variance in accordance with the pro sions 40 CFR Part 190. Submittal of '

the report is consider a timel request, and a variance is granted until staff a tion on the equest is complete.

b. DELETED l SURVEILLANCE REQUIREMENTS 4.11.3 . Cumulative do e contributions from liquid and aseous effluents and direct radiation shal be detenmined in Specifications 11.1.2.1, 4.11.2.2.1 and 4.11 .3.1 and in accordance with Section I of the REM 00CM once per 31 days.

/

IECK 3/4 11-6 Amendment No. J .193

c I

SES 4.0.5, 4.0.6; REFER CES 1, 2, 3; D PAGES B3/4 6 THROU B3/4 0-7 DE T l

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a DELETED I THEI ENTIRETY i.

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DELETED .THEIR NTIRETY l

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NECK

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l IN UMENTATIOM

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! BASES \

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~3 /4 ; 3 '. 3 ' HONITORING INSTRUMENTATION 9 3/4.3.3.1 :0 ETED-l

? 3/4.3. 3. 2 DELE D l

1 3/4.3.3.3- DELETED

/

4 3 /4 . 3 . 3 . 4 - METEOR 0LO" L' INSTRUMENTATION 1

The OPERABILITY of the met rological instrumentatio ensures that suffi-

$ cient meteorological data is vailable for estimat . g potential radiation

q doses to the public as a resu of routine or ac dental release of radio-  ;

j active materials to the atmosph e. This capab' ity is required to evaluate

);

the need for initiating protectiv measures.t protect the health and safety. ,

of the public and is consistent wi the re smmendations of Regulatory Guide t

1.23. "Onsite Meteorological Program ." F ruary 1972. l

.3/4. 3. 3. 5 DELETED 81

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3/4.3.3.6 DELETED l3. -

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4 13 -

B3/4 3 2 Amendment No.128,179,19. 194

.I HADDAM NECK'

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4' TSB353.00C

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BASE 3/4.3.3.5 AND 3/4.3.

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_ . _ - . ~ . . _ . . . , . .,

IBlalDf1 RATION sAs II 3/4.3.3\ RADIQACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION

~The-radica ive liquid effluent instrumentation is provided to monit r and control,.as p11 cable, the releases of radioactive materials in 1 uid effluents dur actual or potential releases of liquid effluents The Alars/ Trip Set iints for these instruments shall be calculated a d adjusted in accordance w' h the methodology and parameters in the 00CM ensure that the alareVtrip w 1 occur prior to exceeding the limits of 10 FR Part 20.

The OPERA 8ILITY a use of this instrumentation is consisten with the requirements of Gen al Design Criteria 60, 63, and 64 of pendix A to 10 CFR Part 50.

3 /4 . 3'. 3 . 8' RADI0 ACTIVE SE005 EFFLUENT MONITORING INS UMENTATION The radioactive gaseous e luent instrumentation is vided to monitor and control,- as applicable, the eleases of radioactive materials in gaseous effluents during actual or p ential releases of seous effluents. The AlarsVTrip Setpoints for thes instrurents shall e calculated and adjusted in accordance with the methodo1 ty and paramete in the REM 00CM to ensure that the alars/ trip will occur o*4or to exceed g the limits of 10 CFR Part 20. The OPERABILITY dvd use:of is instrumentation is consis-tent with the requirements of Gene 1 Desig Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

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Amendment No. J$p, Jpp, J , 193 NECK B3/43-3

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BASES 4.3.3'.9 AND 3/4.3.4; O l GE B 3/4 3-4 ,

i ELETED i

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BASES 3/4.4 TOR C0OLANT 5 EN DELETE IN THEI ENTIRETY I

f 0

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BASES 3/4.5 ENERG Y CORE C0OLING S TEMS DELETED N THEIR TIRETY l

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9 HADDAM NECK

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i i BASES 3/4.6 j AINNENT SYST J

.1 j DELETED IN THEIR NTIRETY

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BASES 3 .7.1 THROUGH 3/4.7.4; AND

j. PAGES B 3 7-1 THROUGH 3/4 7-3a ELETE I

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L SYSTEMS j

S 3/4. SEALED SOURCE CONTAMINATION The limit tions on removable contamination for sources requiring leak testing, i :luding alpha emitters, is based on 10 CFR 70.39(a)(3) 1 its for plutonium. is limitation will ensure that leakage from Byproduct, urce, and Special Nucle r Material sources will not exceed allowable intake values.

Sealed sources a classified into three groups according to heir use, with Surveillance Requi nts commensurate with the probability of amage to a source in that group. Tho sources which are frequently handled e required to be tested re often than those which are not. ealed sources which are continuously enc 1 ed within a shielded mechanism .e., sealed sources within radiation monito ng or boron measuring devices) re considered to be stored a d need not be tested unless t ey are removed from the shielded mechanism.

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l NECK B3/4 7-4 Amendment No. JU. #7, ,193 l o4 1

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BASE /4.7.6 THROUGH 3/4.7.1 ; AND PAGES 3/4 7-5 THROUGH B ./4 7-7 1

DELETED  !

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BASES 3/4.8 ELE ICAL POWER STEMS DELETED THE ENTIRETY

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NECK

I 3/4. REFUELING 9MB&T10til BASES 3/4.9.1 OROM CONCENTRATI.Qfi

\

The limitati s on reactivity conditions during REFUELING ensure e at: (1) the reactor w 1 remain subcritical during CORE ALTERATIONS, and ;2) a uniform baron ncentration is maintained for reactivity contro in the water volume having direct access to the reactor vessel. The limitations are consistent wi the initial conditions assumed for the b on dilution incident in the ac dent analyses. A value of 0.94 or less or K, is required for this ac ident. For a core configuration of rods in an additional 0.05 K.,, p alty is required to account for a eavy load crushing the core into more reactive configuration.

3/4.9.2 INSIBQMENTATION The OPERABILITY of the Sour Range Neutron Flux itors ensures that monitoring capability is ava able to detect chan< es in the reactivity condition of the core. Redun t monitcring cap sility is required to 3

detect changes in the reactivit condition of e core during fuel movement.

- 3/4.9.3 DECAY TIME 5

The minimum requirement for reactor bcr icality prior to movement of l irradiated assemblies in the reactor s 1 ensures that sufficient time has

elapsed to allow the radioactive decay the short-lived fission products.

- The minimum requirement for reactor ho d time prior to movement of irradiated fuel from the reactor vessel to the ent uel pool ensures that sufficient

! decay time has elapsed for adequate pent el pool cooling should a failure I occur to the cooling system. The eactor ho d time is a function of cooling water temperature. The required ecay time a umes a conservative maximum transfer rate of six assemblies er hour. The decay times are consistent 0 with the assumptions used in t safety analysis 3/4.9.4 CONTAINMENT BUTLDIN PENETRATIONS The requirements on conta ment building penetration losure and OPERABILITY ensure that a release of radioactive material within ntainment will be restricted from leakag to the environment. The OPERA LITY and closure restrictions are suff ient to restrict radioactive mate ial release from a

- fuel element rupture ased upon the lack of containment p ssurization

, potential while in e REFUELING MODE.

d 3/4.9.5 CDEMUNIC IONS

- The requireme for communications capability ensures that refue ing cavity l- manipuiator ane area personnel can be promptly informed of sign icant changes in e facility status or core reactivity conditions durin CORE ALTERATION .

l

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DAM NECK B3/4 9-1 Amendment No. M . J 193 I

E L- S u tL P)AIG-TFJL Hit 0P.ERATIONS BASES Ih MANIPULATOR CRANE The OPERABI nts the man or cranes ensure that: (1) L-R__

manipulator cranes will be used nt of control rod drive shafts and fuel assemblies, (2) eac as sufficie capacity to lift a drive

, and (3) the core internals an r vessel are shaft or fuel asJ ntly protect Aea excessive lifting forces in the event they are n l epgagtFd during lifting operations. l 3/4.9.7 CRANE TRAVEL - SPENT FUEL SMBUILDING The restriction on movement of loads in excess of the n weight of a l y

u fuel and control assembly and associated handling tool over other fuel p gl l assemblies in the pool ensures that in the event this load is dropped: (1) the activity release will be limited to that contained in

/*'d l' g

single fuel assembly, and (2) any possible distortion of fuel in the -A.ge racks will not result in a critical array. This eaan.; tier, is consistent with the activity release assumed in the safety analysis.

3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATIQH

'The re rement that at least one RHR LOOP be in operation ensures  : (1)I sufficien oling capacity is available to remove decay heat a aintain the water in reactor vessel below 140*F as required duri Le REFUELING MODE, and (2) su ient coolant circulation is maintai through the core to minimize the effec f a boron dilution incident prevent boron ,

stratification.

D gh The requirement to have two RHR PS OPE ange E when there is less than 23 ensures that a single failure g )I w o feet of water above the reactor ves of the operating RHR LOOP will not r a in a complete loss of residual heat removal capability. With t reacto essel head removed and 23 feet ti d flange, a e heat sink is available for .

9 of water above the reactor ves core cooling. Thus, in the vent of a failure o the operating RHR LOOP, adequate time is provide o initiate emergency pro dures to cool the core.

i URGE SUPPLY. PURGE EXHAUST. AND PUR EXHAUST BYPASS 3/4.9.9 CONTAINMEN ISOLATION SYSTEM /

The OPERAB TY of this system ensures that the containment vent d purge penetra ons can be isolated upon detection of high radiation levels ithin the tainment. The OPERABILITY of this system is required to restric the rel ase of radioactive material from the containment atmosphere to the m

vironment. . .

HADDAN NECK B 3/4 9-2 Amendment No. W . M 193

Insert C to old oace B 3/4 9 2 l

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 l 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.

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a AEf9Et4NS ERATIONS f* E N M- O' BASES hiedT F6l- '

3/i ". "_0 ..d 3/4.9.11 WATER LEVEL - AEACT"," t'ESSEL A"O ST0"."C POOL Tfie restrictions on water le re that sufficient water dept is available to remove 9 ssumed 10% iodine gap activity released Y(T from the ruptur rradiated u ably. The minimum water depth i wd consisjon the assumptions of the safe w 1ys k gefp 3/4.9.12FUELSTORAGEYILDINGAIRCLEANUPSYSIBI The limitations on the Fuel age ding Air Cleanup System ensure that all radioactive material releas on an irradiated fuel assembly will be filtered through the HEPA fil sa harcoal adsorber prior to discharge to the atmosphere. The OPE ITY of this stem and the resulting iodine removal capacity are' sistent with the as tions of the safety analysis. I l

used as a procedural gu for surveillance testing

@ SIN 510-1980wi 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL The limitations of this specification ensure that, in the event of any fuel  ;

handling accident in the spent fuel pool, K, will remain s 0.95.

3/4.9.14 SPENT FUEL P00L - REACTIVITY CONDITION Fo!

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 fue racks, with no credit taken for soluble baron in the pool, v ively within the assumptions of the safety analysis, p p t ,( g

" ~ ^

M 9.15 SPENT FUEL POOL COOLING

)

l The limita ns on the Spent Fuel Pool Cooling System ensure there is sufficient cap ty to remove decay heat produced by the stored spe fuel

} elements with a fu om offload and maintain the bulk pool te rature below

150*F with a maximum h load of 22.4x10' BTU /hr. The maxi design heat l

load is based on an emergen ull core offload scenari onservatively evaluated after the final opera cycle.

Requiring both spent fuel pool cooling sP OPERABLE provides backup capability in the event the operating pump 1s. In the event of a complete loss of forced cooling during a full co offlo the time to boil is greater t-

! than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> in the most severe dis rge scanario. This allows sufficient l time to provide an alternate pow source to the SFP p s for an electrical l 1 failure or alternate SFP inve ry makeup capability for chanical failure. )

In the event of a loss of site power and the A train diese is out-of-service, there is suff ent time to repower the SFP cooling sys from an alternate diesel ge ator. Therefore, operability of the spent f pool cooling system s not require the A train diesel generator to be av lable. )

y ng f  !

3 Should fa re to restore operation of the cooling system occur before boi

t

kes ce, cooling of the spent fuel pool can be accomplished by allowing i the P to boil and adding makeup water at a rate equal to or greater than the \

-off rate. d HADOAM NECK B3/4 9-3 Amendment No. J77,17J JSF,193

I l

Insert D to old oaae B 3/4 9-3 l  !

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 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (as of December 1997), based on an initial spent fuel pool temperature of 150 *F. and no evaporative cooling.

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1 3/4.9 ,

_ g PERATIONS &

BASES _

3/4.9.16 SPENT FUEL POOL COOLING DEFUELED #[

The primary basis for 150 r'ees is to limit thermal stresses on the spent fuel pool concrete structures ue 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 load. One spent fuel pool heat exchanger and one spent fuel pool cooling pump, that can be operated intermittentl is sufficient to remove the decay heat load. ,g/jp Assuming no forced or rativ ooling, the calculated May 1998 heatup rate  ;.

is approximately 1.2 s . Thus, in the event of a complete loss of )

forced cooling and assuming an initial spent fuel pool temperature of 1 reesJ2, the time to boil, assuming no evaporative cooling, is greater than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Therefore, sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory.

'F  ;

i HADDAM NECK B 3/4 9 5 Amendment No.193

g f

BASES 3/4.10 SPEC TEST EX PTIONS DELETED IN T IR ENTIRETY m

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/4.11 RADI0 ACTIVE EFFLUENTS'

. b 3/4.1 LIQUID EFFLUENTS 3/4.11.1 CONCENTRATION y This specif ation is provided to ensure that the concentration f l radioactive terials released in liquid waste effluents from e site will be less.than t concentration levels specified in 10 CFR Par 20, Appendix B, Table II, Co an 2.- This lir.itation provides additional ssurance that the levels of rac onctive materials in bodies of water out de the site will result in exposure within: (1) the Section II.A design jectives of  ;

Appendix I, 10 CFR rt 50, to a MEMBER OF THE PUBLIC, a (2) the limits of i

- 10 CFR 20.106(e) to t a population. The concentration imit for dissolved or entrained noble gas is based upon the assumption e.t Xe-135 is the controlling radioisotop and its MPC in air (submers n) was converted to an equivalent concentration water using the methods escribed in International Commission o Radiological Protectio (ICRP) Publication 2.

3/4.11.1.2 DOSE. LIQUIDS This specification is provided t implement t e requirements of Sections II.A, III.A, and IV.A of Appendix , 10 CFR art 50. The Limiting Condition for Operation implements the' guide set fo h in Section II.A of Appendix I.

The ACTION statements provide the re uir operating flexibility and at the same time implement the guides set fo h in Section IV.A of Appendix I to assure that the releases of radioactiv material in liquid effluents will be kept "as low as is reasonably achieva e. The dose calculation methodology and parameters in the REM 00CM imp 1 tt requirements in Section III.A of Appendix I that conformance with t guide of Appendix I is to be shown by calculational procedures based on als an ata, such that the actual exposure of a MEMBER OF THE PUBL through ap opriate pathways is unlikely to be substantially underestina . The equat ns specified in the REM 00CM for calculating the doses due o the actual role e rates of radioactive materials in liquid effluent are consistent with he methodology provided in Regulatory Guide 1.109, alculation of Annual ,ses to Man from Routine Releases of Reactor Efflue ts for the Purpose of Eva ating Compliance with 10 CFR Part 50, Appendix ." Revision 1, October 1977, and Regulatory Guide j 1.113, " Estimating Aqua c Dispersion of Effluents fr Accidental and Routine Reactor Releas s for the Purpose of Implementing ppendix I," April l j

1977.

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10 ACTIVE EFFLUENTS BAk ,

3/4.1 GASEOUS EFFLUENTS 3/4.11.2 DOSE RATE-This specif ation is'provided to ensure that the dose rate at an ime from gaseous eff1 ts from all units on the site will b6 within the nnual dose limits of 10 C Part 20 for all areas offsite. The annual do limits are l the doses assoc ted with the concentrations of 10 CFR Part 2 , Appendix B, Table II. These imits provide reasonable assurance that ra oactive material discharge in gaseous effluents will not result in he exposure of an' individual offsi to annual average concentrations ex edihg the limits I i

specified in Appendi B, Table II of 10 CFR Part 20 (10 R20.106(b)). For individuals who may at times be within the site boundar' , the occupancy of l that individual will be ufficiently low to compensate 'or any increase in the atmospheric diffusio factor above that for the s te boundary. The specified release rate li ts restrict, at all time the corresponding gamma and beta dose rates a ve background to an i ividual at or beyond the site boundary to less than o equal to 500 arem/y r to the total body or to less than or equal to 3000 mr year to the skin These release rate limits also restrict, at all times, th corresponding yroid or other organ dose rate above background to a child o less than r equal to 1500 mrem / year from inhalation.

I 3/4.11.2.2 DOSE. NOBLE GASES l

This specification is provided to imp 1 nt the requirements of Sections l II.B., III.A and IV.A of Appendix I, 1 R Part 50. The Limiting Condition for Operation implements the guides s f th in Section II.B of *ppendix I.

The ACTION statements provide the re uired a9 rating flexibility and at the same time implement the guides set orth in ction IV.A of Appendix I assure that the releases of radio tive mater 1 in gaseous effluents will be kept "as low as is reasonably chievable." he Surveillance Requirements implement the requirements in 5 ction III.A of pendix I that conform with the guides of Appendix I be sh wn by calculationa proceduras based on models and data such that th actual exposure of a individ2a1 through the appropriate pathways is un1 ely to be substantia 11 underestimated. The dose calculations establis d in the ODCM for calcul ing the doses due to the actual release rates f radioactive noble gases in gaseous effluents will be consistent with a Ethodology provided in Reg' latory Guide 1.109,

" Calculational of Annu Doses to Man from Routine Relea s of Reactor  ;

Effluents for the Pur se of Evaluating Compliance with I CFR Part 50, Appendix I," Revisio 1, October 1977 and Regulatory Guide .111, " Methods for Estimating Atmo pheric Transport and Dispersion of Gaseo Effluents in Routine Releases f Light-Water-cooled Reactors," Revision July 1977.

The ODCM equati s provided for determining the air doses at the ite boundary are b red upon utilizing successively more realistic dos calculational methodologies. More realistic dose calculational met ds are used whenev simplified calculations indicate a dose approaching a substantia portion of the regulatory limits. The methods used, in o er are, prev usly determined air dose per released activity ratio, histo cal meteoro1 ical data and actual radionuclide mix released, or real time meteoro ogy and actual radionuclides released.

AM NECK 83/4 11-2 Amendment No. J7J 193 04

10 ACTIVE EFFLUENTS f BA 3/4.11 .3 DOSE. RADIOACTIVE MATERIAL IN PARTICULATE l FORM ANd\ RADIONUCLIDES OTHER THAN NOBLE GASES This speci cation is provided to implement the requirements of Sect ns II.C. III.A nd IV.A of Appendix I, 10 CFR Part 50. The Limiting C ditions for Operation are the guides set forth in Section II.C of Appendi I. The - l' ACTION stateme s provide the required operating flexibility and t the same time implement e guides set forth in Section IV.A of Appendix to assure that the releases of radioactive materials in gaseous effluent will be kept "as low as is reas ably achievable." The ODCM calculationa methods k specified in the su eillance requirements imple:::ent the re trements in l Section III.A of Appe dix I that conformance with the gui s for Appendix I be shown by calculatio al procedures based on models and ata such that the actual exposure of an i tvidual through appropriate pa ways is unlikely to  !

j be substantially underes mated. The ODCM calculation methods for calculating the doses due o the actual release rate of the subject f materials will to be consis nt with the methodolog provided in Regulatory  !

Guide 1.109, " Calculating of nnual Dose to Man fr Routine Releases of }

Reactor Effluents for the Purp se of Evaluating C mpliance with )

j 10 CFR Part 50, Appendix I," Re ision I, October 1977 and Regulatory Guide 1.111, " Methods for Estimating A spheric Tra port and Otspersion of i Gaseous Effluents in Routine Rele es from Li t-Water-Cooled Reactors,"

Revision I, July 1977. The release rate sp ifications for radioactive l material in particulate form and rad nuc1 es other than noble gases are 1 dependent on the existing radionuclid pa ways to man. The pathways which are examined in the development of the calculations are:

1) individual inhalation of airborne r onuclides, 2) deposition of radionuclides onto green leafy vegeta on ith subsequent consumption by man, 3) deposition onto grassy areas here ilk animals and meat producing animals graze with consumption of e milk a d meat by man, and 4) deposition on the ground with sub quent expo re of man.

3/4.11.3 TOTAL DOSE This specification is provid d to meet the reporti requirements of 40 CFR Part 190. For the purposes f the Special Report, i may be assumed that the dose commitment to any ME ER OF THE PUBLIC from othe fuel cycle sources is negligible, with the exc tion that dose contributions from other nuclear i fuel cycle facilities the same site or within a radi of 5 miles must be considered.

Amendment No. J # ,493 AM NECK B3/4 11-3 27

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5.0 DESIM FEATURES

1. N _

l 5.1 SITE 11TeVf E I LIS N AREA- - Ny l 5.1.1 Exclusion Area shall be 'as shown in Figure 5.1-1. The minim ,

distance to boundary of the exclusion area as defined in 10CFR100.3 shall be 1740 l I ,

LOW POPULATION ZONE

~

5.1.2 The Low Population Zone 11 be as show Figure 5.1-2.

l 5.2 DELETED d

5.3 DELETED l

l 5.4 DELETED 5.5 METEORO CAL TOWER LOCATION

.5.1 The meteorological tower shall be located as shown in Figure 5. .

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l 5-1 Amendment No. J7),193 HADDM NECK 0420

i Insert E to old naae 5-1 i

The plant site, consisting of approximately 525 acres, is located'in the '

Town of Haddam, Middlesex County, Connecticut, on the east bank of the Connecticut River.

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s sw s FIGURE 5.1-2 LOW POPULATION ZONE NECK 5-3 Amendment No. A ',193

E L

DESIGN FEATURES 2

l 5[SPENTFUELSTORAGE I

CRITICALITY

~

2.

5.l.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 .4 , j (North / South) center-to-center distance including neuJfon absorbe surrounding each assembly to ensure a K.,, qtss snan-cr eaual .95 when flooded with unborated water. Fuel with a maxis,lm nominal enrichment of 5 weight percent U-235, without regard for fuel burnup, may be stored in i this' region. The location of Region I 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 e, neutron absorber surrounding each assembly to ensure a K.,, .... ...... , .

p:1 te .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. Q

c. For Region 3 *a nominal 10.75 inch center-to-center distance to ensure a K ,, GMs th rTaii'at-to .9S when flooded with unborated nter. No credit is taken for the neutron absorber contained within the racks of this region. Storage of fuel in Region 3 must be in accorcance 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 I I DRAINAGE 5.f.2 The spent fuel storage pool is designed and shall be nintained to prevent inadvertent draining of the pool below elevation 21.0 feet MSL.

CAPACITY ,

5 The spent fuel storage pool is designed and shall be maintained with a sdor.3 age 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.

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i HADOAN NECK 5/

/

Amendment No. J#, NJ, 77), 2W193 a

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SECTION 5.7; TABLE 5.7-1; i FIGU S 5.6-1 AND 5;6-2 AND PA S 5-5 THROUGH 8 DELETED 1

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deel Ahleabl h/mof-gnat F

, 6.0 ADMINISTRATIVE CONTROLS l

se heff0ni' l' 6.1 -ESMaiER{JV

6.1.1 The VP Operations and Decommissioning shall be responsible for [-

overall facility operation and shall delegate, in writing, the succession to ,

g this responsibility during his abs ca.

6.2 t=uZ;u iGN OrfJdaba /faf, dray O .

frrnj(a$eb hen l 6.2.1 ^" SITE '."O OFFSITE 0""'"I'ATI^" - 7%ese l 02:i.e :.r.d ;ff;it: organizations shall be established for it operation and corporate management, respectively. Th . es. site c.r4 ;ff;it organizations shall include the positions for activities affecting the ::fet, of 'h;

' reel- peer phet.

g

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization d .

positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional ,[ l descriptions of departmental responsibilities and relationships, ?M-and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in 1 j the Connecticut Yankee Quality Assyt n Program (CYQAP). g fhave

b. c The Unit and operation Director shallcontro shall have 5: c:;l.sistli over those oyerall f uni onsite activities

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-ef p un+.-~ nece g .4parv  % y forgg f7 g;ygjer. ;gg-- j9+4p[ 3 g f, g d if,,g

c. The VP Operat ons an c ss onin s all ave corporate l l j l

responsibility for overall plant nuclear safety and shall take any '

measures needed to ensure acceptable performance of the staff in

, D

-fi operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

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$ d. The individuals who train theG;ifid. 7 :1 " r'1.r: andh Equipment Operators # and those who carry out health physics and j

pq quality assurance functions cay report to the appropriate onsite Q manager; however, they shall have sufficient organizational freedom to ensure their ir':;: i~= f= - seatM =cessupos 6.2.2 't 1:~ ;~~. 7 - ceT*1FIED FUEL N OLEN w

a. Each on-duty shift shall be composed of at least the minimum shift I crew composition shown in Table 6.2-1; I

b. At least one person qualified to stand watch in the control room

(a ' " ' '-1 ":r.dkr or an Equipment Operator) shall be present in the# control room when irradiated fuel is in the spent f # fuel pool; g_ e, '

9hild;$do prfor* d5RTf@ rust. H A90i& R their 2siched f6dioMA 6-1 Amendment No. JJJ, JJJ. JJJ. JJJ,192 HADDAM NECK osa i

-Insert F to old nace 6-1 l

' '6.1.2 The Unit Director or his designee, in accordance with approved administrative procedures shall approve each proposed test fuel m u--^n* le:d -~10 c't. or experiment prior to implementation and ,

shall approve modification to structures, ystems, or equipment i that affect the safe storage of irradiated fuel.

6.1.3 The Shift Manager (SM) shall be responsible for the operational  !

command function.

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c. An individual qualified in radiation protection procedures

• shall be on site during fuel handling operations; l )

d. All fuel handling operationsgsiIEIl be observed and directly j supervised by a C:rt T;, J Fowl ii...J1;7 who has no other concurrent l responsibilities during' this operation; 1

[ DELETED K .

6/

• Administrative procedures shall be developed and implemented to limit'the working hours of facility staff who perform functions Q important to the safe storage and handling of irradiated fuel. l jl There pr:: h r:: :heeld fell;w th: ;:::r:1 ;ethr.:: Of the N L 1

.;1 icy St:t;.;r.t er,.;;rki..g

"  ;.v... (G ..e.ic Letter Ne. 32-12). -

f N

• The individual qualified in radiation protection procedures may be less h

than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate i action is taken to fill the required position.

W" f, & $& }%najeu fsll be a deWD W WAL f

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HADDAN NECK 6-2 Amendment No. JJJ, Jp). 177, 192 0432

[ Sjl(( Mahayev ( *]' I TABLE 6.2-1

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. A MINIMUM SHIFT CREW COMPOSITION

< L POSITION NUMBER OF INDIVIDUALS REOUIRED TO Fill POSITION

% ,;.ified fuel llar.dier- 1*

Equipment Operator 1 d

1 The shift crews' composition may be one less than the minimum requirements of Table 6.2-1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to  ;

accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift omposition to within the minimum requirements of Table 6.2-1. This provision does not permit any {

shift crew position to be unmanned upon shift change due to an oncoming 1 '

shift crewman being late or absent.

cWW5 1 i

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• Does not include the C r'ifi:d Tal ::er.dl= supervising fuel handling operations. i CcB1\FISD R" M# j i

i HADDAM NECK 6-3 Amendment No. Jg), JJJ,192 0432

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ADMINISTRATIVE CONTROLS 1

6.3 "" ILITV ST" OL'*1ITICAiiM".r J

6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications,of ANSI N18.1-1971 for comparable positions.

6.3.1.1 The position of Health Physics Manager shall meet the following minimum qualifications:

a. Academic degree in an engineering or science field or equivalent as per Section 6.3.1.1.c.

b. Minimum of five years professional technical experience in the area of radiological safety, three years of which shall be in applied radiation work in a nuclear facility dealing with problems similar to those encountered in a nuclear power reactor.

c. Technical experience in the area of radiological safety beyond the five year minimum may be substituted on a one-for-one basis towards the academic degree requirement (four years of technical experience being equivalent to a four year academic degree),

d. Academic and technical experience must total a minimum of nine years.

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6.3.1.2 DELETED l

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6-4 Amendment No. JJJ, JJJ,192 HADDAM MECK use

. ADNINISTRATIVE CONTROLS

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6.4 T"'INING e- r; Hem fog / retraining and replacement training program for the E tified Tuwi n ndlers [

shall be maintained under the direction of the Unit Director.J A retraining and replacemen trainin program for the factitt start sh be maintained under the direc no he Unit Director and shall et o exceed the -

R requirements and ndations of Section 5.5 of 18.1-1971. The Unit \

Director has the e 11 responsibility for the imp men tionoftheTrain]ing

m. EW AND AUDIT

6. PLANT OPERATIONS REVIEW COMMITTEE (PORC) '

\ f FUNCTION j I

6.5.1.1 The P shall function to advise the Unit Director all matters related to nuclear fety. ,

i COMPOSITION 6.5.1.2 The PORC shall be co osed of at least ven members. Members shall l collectively have experience an pertise in e following areas:

Plant Operations, f Decommissioning,*

Engineering, Maintenance, Health Physics, Chemistry /Radioche try, Quality Assuranc , and Security.*

The minimum qualif ations of PORC members shall be that all m ' ers have an academic degree an engineering or physical science field, or h a management po tion, and have a minimum of five years technical expe ence in their resp ive field of expertise. The members of PORC shall be appo' ted in writi by the Unit Director, who is the PORC Chairperson. The altern Chair sons of the PORC shall be drawn from the PORC members and be appoint in iting by the Unit Director.

_ \ -

• These areas are exempt f the 5-year experience requirement.

HADDAM NECK 6-5 Amendment No. 177,177 177,177, ons 179, 199 191 192 j

., INISTRATIVE CONTROLS

/

AL NATES 6.5.1. All alternate members shall be Spointed in writing by the Chairpe on to serve on a, temporary basis; however, no more than two alternat shall participate as voting members in PORC activities at ny one time.

MEETING FREO NCY 6.5.1.4 The C shall meet at least once per calendar mont and as convened by the RC Chairperson or his/her designated alter ate.

SQQfM1 6.5.~.5 The quorum o the PORC shall consist of the airperson or his/her designated alternate an four members including alter ates.

RESPONSIBILITIES 6.5.1.6 The PORC shall be r ponsible for:

a. Review of: (1) all pro dures requi ed by Specification 6.8 and changesthereto,and2) ny other reposed procedures or changes thereto as determined by e Uni Director to affect nuclear safety; l

b. Review of all proposed tests d experiments that affect nuclear safety;

c. Review of all proposed ch ges t the Technical Specifications;

d. Review of all proposed hanges or ifications to plant systems or equipment that aff t nuclear saf y;

e. Investigation of a violations of the echnical Specifications, including the pre tration and forwarding f reports envaring evaluation and commendations to prevent ecurrence, to the VP Operation and Decommissioning and to e Nuclear Safety l Assessment rd;

f. Review of 1 REPORTABLE EVENTS;

g. Review f facility operations to detect potential faty hazards;

h. Perf nce of special reviews, investigations or ana ses and rap rts thereon as requested by the Nuclear Safety Ass sment Board I or the Unit Director.

l ,

6-6 Amendment No. JJJ JJJ,177. JP 171,192 ;l NECK as I

/

NISTRATIVE CONTROLS i Not used.

J. Not used. I

k. eview.of the Fire Protection Program and Implementing rocedures.

AUTHORITY 6.5.1.7 The RC shall:

a. Report and be advisory to the Unit Directo on those areas of responsi lity specified in Section 6.5.1.6(a through (k);

b. Render dete inations in writing to the U t Director if any item considered u er Specification 6.5.1.6a through d., above, as appropriate an as provided by 10CFR50.5 or 10CFR50.92 constitutes an unreviewed fety question or req res a significant hazards consideration de reination.

)

c. Provide written not ication, meet g minutes may be used for this purpose, to the V Operetion and Decommissioning and the Chairperson of the Nuc ear Safe Assessment Board of disagreement between the PORC and the it Director; however, the VP -

Operations and Decommis io ng shall have responsibility for resolution of such disagre nts pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The PORC shall maintain ritten inutes of each meeting that, at a minimum, document the results all POR activities performed under the responsibility and authority p ovisions of hese Technical Specifications.

A Copy sha.11 be provided to th Nuclear Safety ssessment Board. l 6.5.2 NUCLEAR SAFETY ASSE MENT BOARD (NSAB)

FUNCTION 6.5.2.1 The mini qualifications of NSAB members re as follows:

a. The Cha person and NSAB members shall have:

1. An academic degree in an engineering o physical science field, or hold a senior management positio and A minimum of five years technical experi ce in their respective field of expertise.

j 6-7 Amendment No. JEF, JJJ, 177, 17 l HADDAM NECK one 191, 199, 191', 192 r

~. . , .

t N . ISTRATIVE CONTROLS

b. The NSAB shall have experience in and shall function to p vide independent oversight review and audit of designated activi ies in the areas of:

P1 ant Operations, Decommissioning, Engineering, Radiological Safety, ,

hemistry/ Radiochemistry t ality Assurance, and E ironmental Protection.

The NSA8 serves to adv e the VP Operations and Dec issioning on matters related to nuclear safet and notify the VP Operat' ns and Decommissioning within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of a sa ty significant issue and r a safety significant disagreement between the NS and the organization function being reviewed.  ;

I COMPOSITION {

6.5.2.2 The VP Operations an Decommissioni g shall appoint, in writing, a minimum of five members to the NSA and shall signate from this membership, in j writing, a Chairperson and a Vice Ch irperson The membership shall function to provide independent review an aud in the areas listed in  ;

Specification 6.5.2.1.

ALTERNATES 6.5.2.3 All alternate members shall be a cinted, in writing, by the VP -

Operations and Decommissioning; ho ver, n more than two alternates shall participate as members in NSAB act'vities at one time.

MEETING FREQUENCY 6.5.2.4 The NSA8 shall see at least once per ca endar quarter.

QUORUM 6.5.2.5 The quorum o the NSAB shall consist of a crity of NSAB members including the Chairper on or Vice Chairperson. No more an a minority of the quorum shall have 11 e responsibility for operation of a same Haddam Neck Plant. No more tha wo alternates shall be appointed as rs at any meeting in fulfillment of a quorum requirements.

NECK 6-8 AmendmentNo.J7F,JPJ,177,17 177 192

]

~; , INISTRATIVE CONTROLS f

[

REVI RESPONSIBILITIES 6.5.2.6 The NSAB shall be responsible for the review of:

a. The safety evaluations for changes to procedures, equi it, or y' stems, and tests er experiments completed under the pr isions of CFR 50.59, to verify that such actions did not c stitute an u eviewed safety question as defined in 10 CFR 50.59

b. Prop ed changes to procedures, equipment, or syst s that involve 1 an un viewed safety question as defined in 10 CF' 50.59;

c. Proposed tests or experiments that involve unreviewed safety question defined in 10 CFR 50.59;

d. Proposed ch ges to Technical Specifica ons and the Operating License;

e. Violations of plicable codes, re lations, orders, license

]j requirements, or internal procedu es having nuclear safety significance;

f. All Licensee Event Re rts requir by 10 CFR 50.73;

g. Indications of significa unan cipated deficiencies in any aspect of design or operation o str ctures, systems, or components that could Effect nuclear safet l i

h. Significant accidental, np nned, or uncoritrolled radioactive releases, including corr tive etions to prevent recurrence;

i. Significant operating bnormalit s or deviations from normal and expected performance f equipment t at could affect nuclear safety;

j. The performance o the corrective act on program; and

k. Audits and'the nnual Audit Plan. l l Reports or record of these reviews shall be orwarded to the VP -

Operations and Decomm' sioning within 30 days follow g completion of the review; AUDIT PROGRAM RE NSIBILITIES 6.5.2.7 The SAB audit program shall be the responsibility 3

the Nuclear Oversight o nization. NSAB audits shall be performed at leas'. once per 24 l months in cr.ordance with appropriate administrative procedure and shall l encompass:  ;

a The conformance of unit operation to provisions contained wi in the Technical- Specifications and applicable license conditions; 6-9 Amendment No. J7), JJJ, J71. JJ 192 DAN NECK-

-c ADMIMSTRATIVE CONTROLS 1

b. he training and qualifications of the unit staff;

c. Th implementation of programs required by Specific tion 6.8;

d. The re Protection Program and implementing procedu si

e. The fir protection equipment and program impleme ation utilizing either a qualified offsite license fire protecti n engineer or an outside i ependent fire protection consultant.

f. Actions tak .to correct deficiencies occ rring in . equipment, structures, s tems, components, or method o operation that affect nuclear safety, and 9 Other activities nd documents as reque ed by the VP Operations and Dacommissicain.

RECORDS l l

l 6.5.2.8 Written records of revie s and au ts shall be maintained. As a minimum, these records shall include esults f the activities conducted under the provisions of Section 6.5.2.

l 6.6 REPORTABLE EVENT ACTION 6.6.1 The fc11owing actions shall taken or REPORTABLE EVENTS:  ;

a. The Commission shall b notified an a report submitted pursuant to

{

th> requirements of etion 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE ENT shall be revi ed by the PORC and the results of this view shall be submitte to the NSAB and the VP -

Operations and ecommissioning.

6.7 DELETED i

9 AN NECK 6-10 Amendment No. JJJ. JJJ, JJJ, JJJ,192

79vMesJ 6.0- ADMINJSTRATIVE CONTROL _S_

S." FRGCEDURES ,"O ""0C"E f,,y,I . A 8-1 Written procedures -aM!cr ati&tr:the pcl.cic . - shall be established, implemented, and maintained covering the activities referenced

,Jelow:

Rho *'N

~

fa. The applicable procedure rec ed in Appendix A of Regulatory) gg- G Guide.l.33, Revision 2. Fe uar 1978:

b The requirements and rec

k. ANSI N 18.7-1976. tions of Sections 5.1 and 5.3 >of

c. Fire Protection Program implementation.

d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1. June 1974.

hf ue l Wg -

e. RADIOLOGICALhLUENT MONITORING AND OFF DOSE CALCULATION 733cv;. b MANUAL (REMODCm implementation exc for Section I.E.

Radiological Envir ntal Monitoring.

(

f. Process Control Progra implement on.

g. Spent Fuel Pool Cooli and Makeup Monitoring Program implementation. This Pr am equires that the primary method for spent fuel pool cooli and the rimary method for spent fuel pool i water makeup capabi ty be monito and maintained. This Program ,

- shall provide re onable assurance at the equipment, components.

systems and w er sources used for s t fuel pool cooling and for spent fuel pool water level re capable of fulfilling maintaini their ended functions and are protect gainst freezing.

i a I 1

7 HADDAM NECK Amendment No. 426, 155, 4 M ,

6-)I 4M , 492,193 i

I Insert G to old oaae 6-11

a. The p_rocedures applicable to the safe storage of spent fuel l

, recommended in Regulatory Guide 1.33, Appendix A. (Revision 2, February 1978):

l

b. All programs specified in Specification 6.6. '

i Insert H to old oaae 6-11

e. The use or operation of RADWASTE TREATMENT SYSTEMS utilizing the- ,

_ guidance provided in the REM 0DCM.  !

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4<*f@cth j Yel$esve Ib a ccdv Dhte YIS 2 lh f #

', fro eduits 2k) ^ - Y 6.0 _ ADMINISTRATIV O R OLS S I S

6/.2 Each procedure of Specification 6.g.1, and changes thereto, shall be .evhtd by the DPC :nd 0h:11 be approved by the Unit Director prior to l implementation and reviewed periodically as set forth in each document or in i administrative procedures. l 6.8.3 Temporary changes to procedures of Specification 6. 1 may be made provided: i ebuim, 9

a. The intent of the criginal-procedure is not altered: {

b. The change is approved by a member of the lan manana =nt staf_

cErnFsAD FudL HA#btEA and a C;.tified iji ll;adicr: ands

{ c. The change is documented, reviewed by the PORC and approved by the or des [gAce _

Unit Directo ithin 14 days of implementation.

shall be established, I 4 Written procedures implemented i

maint ~ covering Section I.E., Radiological Environmental Moni ' g, of the REMODCM.

} 6.8.5 All procedures rocedure changes r ed for the Radiological l

Environmental Monitoring Progr f Specif ion 6.8.4 above shall be

reviewed by an individual (other th author) from the Radiological j Assessment Branch or the Productio ratio rvices Laboratory (POSL) and

approved by appropriate super on.

Temporary changes made provided the intent of the origin rocedure is not altered the change is documented and reviewed by an individu other than uthor) from the Radiological Assessment Branch or the POSL, wi j ays of implementation. k(

i h itI?

6 eyo 7

9 HADDAM NECK 6 12 Amendment No. 426. 45, 468.

491. M2, 193

[ ~ .

psen z -

ry+ c 6.0 ADMINISTRATIVE CONTROLS l 6.6 Programs and Manuals 6.6.1 Radiation Protection Procram A program for personnel radiation protection shall be prepared consistent with the requirement of 10 CFR 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.

6.6.2 Process Control Proaram (PCP)

The PCP shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes will be accomplished to ensure compliance with 10 CFR Parts 20, 61, and 71: state regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.

Changes to the PCP:

a. Shall be documented and records of reviews shall be retained.

This documentation shall contain:

1. sufficient information to support each change, together with the appropriate analyses or evaluations to justify the l change; and i

2. a determination that each change maintains the overall I conformance of the solidified waste product to existing requirements of Federal, State, or other applicable I regulations; and  !

b. Shall become effective after the change is independently reviewed in accordance with administrative procedures and approved by the Unit Director or designee.

i i

HADDAM NECK 68 Amendment No. 125.155.158.191.

i

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)

hsa+ I - py a D \

)

6.6 Programs and Manuals (continued) 6.6.3 Radioloaical Effluent Monitorina and Offsite Dose Calculation Manual (REM 0DCM) l J

The REM 0DCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioa:tive gaseous and i liquid effluents, in the calculation of gaseous and liquid effluent {

monitoring alarm and trip setpoints, and in the conduct of the l Radiological Environmental Monitoring Program.

The REM 0DCM shall also contain the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by Specifications 6.6.4 and 6.6.5, respectively, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required under Specifications 6.7.2 and 6.7.3.

Changes to the REMODCH:

a. Shall be documented and records of review shall be retained. This documentation shall contain:

1. sufficient information to support each change together with the appropriate analyses or evaluations to justify the change:.and

2. a determination that each change maintains the levels of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and 10 CFR 50 Appendix I, )

and that the change will not adversely impact the accuracy J or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after the change is independently reviewed in accordance with administrative procedures and approved by the l Unit Director or designee: and

c. Shall be submitted to the NRC in the form of a complete legible l copy of the entire REMODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change was made to the REM 0DCM.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the I change was implemented.

HADDAM NECK 69 Amendment No. 125.155.158.170

]

1 5hsev Y > {*f' 3 A $

i 6.6 Programs and Manuals (continued)

{

6.6.4 Radioactive Effluent Controls Proaram This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCH, shall be implemented by procedures, and shall include remedial actions ~ to be taken whenever the program limits are exceeded. The program shall include the following elements: i

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests and setpoint determinations, in accordance with the methodology described in the REMODCH:

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 Ln=P

_(4ff E tn$concentrationvaluesin10CFRPart20, Appendix , Tabley Column 2; d b 20 8L

c. Monitoring, sampling, and ana ysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20. and wi the methodology and parameters described in the REMODCH: ;og

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from the facility to unrestricted areas, conforming to 10 CFR Part 50, Appendix I:

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters i described in the REMDDCH (performed at least every 92 days);

f. -Limitations on the functional capability and use of the liquid and J gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose I commitment, conforming to 10 CFR Part 50, Appendix I:

1 HADDAM NECK 6 10 Amendment No.

- J

c QeyY ] ~ fDy Y of C 6.6 Programs and Manuals (continued) 6.6.4 Radioactive Effluent Controls Proaram (continued) l

)

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be as follows-

1. for noble gases: s a dose rate of 500 mrem /yr to the total body and s a dose of 3000 mrem /yr to the skin; and

2. for tritium and all radionuclides in particulate form with  ;

half lives > 8 days: s to a dose rate of 1500 mrem /yr to 1 any organ;

h. Limitations on the annual and quarterly air doses from noble gases released in gaseous effluents from the unit to areas beyond the site boundary, conforming to 10 CFR Part 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from tritium and all radionuclides in particulate form with ,

- half lives > 8 days in gaseous effluents released from each '

facility to areas beyond the site boundary, conforming to 10 CFR Part 50, Appendix I; and J. Limitations on the annual dose or dose commitment to any' member of the public at points beyond the site boundary due to releases of '

radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190. '

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HADDAM NECK 6 11 Amendment No.

i

c Is,wtT-pp fa&

6.6 Programs and Manuals (continued) 6.6.5 Radiolooical Environmental Monitorina Proaram This program monitors the radiation and radionuclides in the environs of the facility. The program shall provide representative measurements of-radioactive materials in the highest potential exposure pathways, verification,of the accuracy of the effluent monitoring program, and  ;

modeling of environmental exposure pathways. The program shall be contained in the REM 00CM and shall include the following:

a. Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters described in the REMODCH: and

b. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

I 6.6.6 Soent Fuel Pool Coolina and Makeun Monitorina Proaram This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool water makeup capability be monitored and maintained. This program shall provide reasonable assurance that the equipment, components, systems and water sources, including spent fuel pool water chemistry, used for spent fuel l pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected against freezing.

l HADDAM NECK 6 12 Amendment No. 193 i

1 A '

[hJctI('] -faye $ D*

6.6 Programs and Manuals (continued) f 6.6.7 Technical Snecifications (TS) Bases control Proaram This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Changes may be made to Bases without prior NRC approval, provided the changes do not involve either of the following:

1. a change in the TS incorporated in the license: or

2. a change to the updated FSAR or Basos that involves an unreviewed safety question as defined in 10 CFR 50.59.

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained in a manner that is consistent with the  :

FSAR.

, d. Proposed changes that do not meet the criteria of Specification 6.6.7.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency that is consistent with 10 CFR 50.71(e).  ;

HADDAM NECK 6 13 Amendment No.

3

. . . I

- 6.7 feyo< tag fectuiremeh

~

ADNINISTRATIVE CONTROLS / ._

~

$TINEREPORTS c 6.9.1 addition to the applicable reporting requirements of Title 10 Code of Fe al Regulations, the following reports shall be submitt a the U. S. Nuclear gulatory Consnission, Document Control Desk, Was ton, D.C. $

205S5, one copy the appropriate Regional Office of the , and one ccpy i to the appropriate Resident Inspector, unless oth se noted. {

6.9.1.1 DELETED 6.9.1.2 DELETED 6.9.1.3 DELETED ANNUAL REPORIJS I 6.9.1.4 nual reports covering the activities of the fa ity as I desc d below for the previous calendar year shall be submit rior to ch 1 of each year.

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.4 6-13 Amendment No. JJ5, JJ), 192 HADDAN NECK om ,

r,. '

. .; 67.l. Ocup%>I faSn mosan"Rys#

ADNINISTRATIVE CONTROLS

- .:. : .s - Ryoru r yoi, m; m, ... ......

t 1 asa 3:,m ne! /--

re e

, A tabulation on an annual basis of the n er of station, utility, and other personnel (including contrac rs) eceiving exposures

$4"4 $ ~

rester then 100 mrenV'yr and their Ja ociat -rem exposure according to work and job functione(e.g., weetcc spr

tien: :"

y zurvei'1:nce,- in: rvie: h3gdier. routine maintenance, special maintenance (describe maintenance), waste processing and reft: ;hy The dose assignments to various duty functions may be estimated based on pocket dosimeter, tnermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling 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 assi ned to specific major work functions; .g

, kP I*'e p(

b .' DELE g ,v DELETEQ) _

.' I kNhUAL RADIOLOGICAL $%VIRONMENTAL OPERA M REPORT 6.9.1.6 Routine Annu adiolo al Environmental Operating Reports covering the operation of a cility during the previous calendar year shall be submitted prior y 1 of each year.

The Annual Radiolo al Environ ntal Operating Reports shall include thatj i information del) dated in the RE M.

1. 0 cfA 6his tabulatian supplements the requirements of -See44on 20.2206,ef-- l I j y ,. r . -m g ,

Mtna$cm ah twnOY"" )

hg Pvelka4ce

,ffes9 fue[ MdeM*"f W

HADDAM NECK 6-14 Amendment No. Jg), JJJ,192 one

Insert J to old naae 6-14 An Occupational Radiation Exposure Report covering the activities of the

' facility during the previous calendar year shall be submitteJ.by May 1 of each year

Insert K to old oaae 6-14 6.7.2 Annual Radioloaical Environmental Ooeratina Reoort The Annual Radiological Environmental Operating Report 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 summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM).

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in the REM 0DCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not available for inclusion with the report, the submitted report shall note and explain the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

The Annual Radiological Environmental Operating Report shall include licensee-initiated changes to the REM 0DCM during the period of the report as described in Specification 6.6.3, or these changes shall be submitted concurrently.

6.7.3 Annual Radioactive Effluent Release Reoort The Radioactive Effluent Release Report covering the operdion of the facility shall be submitted in accordance with 10 CFR 50.36a. The Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The material provided shall be consistent with the objectives outlined in the REM 0DCM and Process Control Program.

The Radioactive Effluent Release Report covering the activities during the previous calendar year shall be submitted by May 1 of each year.

ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 A outine Annual Radioactive Effluent Repor overing the operation of the facili during the previous calendar year operation shall be submitted by May of each year.

22 T'he report shall inc e that informati delineated in the REMODCM.

fAnychangestotheREMODC hal e submitted in the Annual Radioactive Effluent Release Report.

l 6.9.1.8 DELETE 6.9.1.9. LETED

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HADDAM NECK 6-15 Amendment No. JJJ. Jf7 177 ous JJJ. JJ7 179 192 l

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6-16 Amendment No. JU. 1 5 , # 1,  !

HADDAM NECK r

osse -

1H,1H, IM,192 l

~

INISTRATIVECdTROLS /

SPECI REPORTS 6.9.2 ecial reports shall be submitted to the U.S. Nuclear Regulat y Com-mission,i cument Control Desk, Washington, D.C. 20555, with one cop to the appropriate egional Office of the NRC, and one copy to the appropri ;e NRC Resident Ins ctor, within the time period specified for each repor .

6.10 RECORD R TENTION 6.10.1 In additi to the applicable record retention requi nts of Title 10,' Code of F eral Regulations, the following recorus shall be retained for at least the min period indicated.

6.10.2 The following cords shall be retained for at east 5 years:

a. Records and logs f facility operation; l

b. Records and logs o rincipal maintenanc activities, inspections, repair, and replace t of principal it s of equipment related to nuclear safety;

c. All REPORTABLE EVENTS;

d. Records of surveillance act vitie , inspections, ard calibrations required by these_ Technical e fications;

e. Records of tests and experine t

• l

f. Records of changes made to he pro edures required by Specifica-tion 6.8.1;

g. Records of radioactive hipments;

h. Records of sealed s rce and fission det tor leak tests and results;

i. Records of annu physical inventory of all aled source material of record; an AM NECK 6-17 Amendment No. Jg), Jpp, Jp7, J$$,192

• • 1

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AD NISTRATIVE CONTROLS 6.10 CORD RETENTION (Cont) 6.10.3 he*following records shall be retained for the duration o the '

ility Operating License:

a. Reco d and drawing changes reflecting facility design difications made systems and equipment described in the FSAR;

b. Records f new and irradiated fuel inventory, fuel ransfers, and i assembly rnup histories; {

c. Records of cility radiation and contaminatio surveys;

d. Records of rad tion exposure for all indivi uals entering radiation l control areas;

e. Records of gaseous nd liquid radioactiv material released to the environs; 1

f. Records of transient or operational cles of the reactor vessel; l

g. Records of training and q lificat on for current members of the facility staff;

h. Records of inservice inspecti sperformedunderpreviousamendmentsl to these Technical Specifica o ;

i. Records of quality assuran e acti ties required by the Quality Assurance Manual not lis d in Spec ication 6.10.2;

j. Records of reviews per ormed for chan s made to procedures or equipment or reviews f tests and exper nts pursuant to 10 CFR Part 50.59;

k. Records of meeti s of the PORC and the NSA ;

1. Records for En ronmental Qualification.

m. Records of r views performed for changes made to he RADIOLOGICAL EFFLUENT ITORING AND OFFSITE DOSE CALCULATION NUAL (REM 00CM) and the P ocess Control Program.

6.11 RADIATION OTECTION PROGRAM 6.11.1 Proce ures for personnel radiation protection shall be pr ared consistent w h the requirement of 10 CFR Part 20 and shall be appro ed, maintained, nd adhered to for all operations involving personnel radhtion exposure.

N NECK 6-18 Amendment No. JJJ, JJJ, JJJ, JJJ.192

\

x ADMIN STRATIVE CONTROLS f[  %, .

[

u,,o nanturnu d . m [

6. .1 Pursuant to 2 .1601 10 C ieu of the

" control device" or "abra signal requ a- "d:P 20M, in each high F".

radiation area, as defined in 1 CFR Pa ~20, in whicf tie .1601Jy as it of

) radiation 1sT2t?-

em 12 in.

~ rad from t'te 100 the h but source or;es! ate1000 radiation from any surface whicher less the i (ation p)enetrates shall be barricaded and conspicuously posted as a high h attpic 30 em 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 es:orted b(y such individuals may be exempt from thej, RWP issuance requirement during the performance of their assigned duties in -

high radiation areas with exposure rates r;rd t: er lets ths31000 miD'h.

provided they are otherwise following plant radiation protection proce3ures 7

_ for entry into such h!ch r:Sth areas.fXHy individual or group of .

<:::b Individuals permitted to enter such areas shall be provided with or ll accompanied by one or more of the following:

'^

a.

fd A radiation monitoring device Mr.eh continuously indicates the radiation dose rate in the areat w + M

+&

b. A radiation monitoring device,wh4eh 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 l area have been established and personnel have been made knowledgeable of theng[D- @ 3

c. An individual qualified in radiation rotection procedures with a radiation dose rate monitoring devicy who is responsible for providingpositivecontrolovertheactivitieswithintheareaa[nd shall perform >eriodic radiation surveillance at' the frequency specified by t se Health Physics Manager in the RWP. >

6 .2 In addition to the requirements of Specification 6. .1, areas accessible to personnel with radiation levels greate- O.. h at 30.___ *.

cm (12 in.) from the radiation source or from any surface which 1000t s@'te radia-tion penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of h -Mft = :rd:r on duty and/or health physics supervision. Doors shall re ain lockeIf except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in "'+ --"- In_ lieu of the stay time specification of the RWP direct or remote circuit TV cameras) continuous surveillance may be made by(sucri as closed ~

personnel qualified in radiation protection procedures to provide positive exposure _n

~ control over the activi les being performed with n the area, ma for initividual high radiation eas ace ible to personnel with radiai.i2 (levels of greater than 1000 mR/that e located within large areas, such as PWR containment, where no enc e e exists for purposes of locking and s ^

where no enclosure can be reason constructed around the individual area, that individual area shall be rrica d, conspicuously posted, and a flashing light shall be acti ted as a ning device or continually guarded. .

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6-19 Amendment No. Jg), JJJ,192 HADDAM NECK j 042e

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' Insert l. to old naae 6-19' }n  !

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6.8.3 Areas with radiation levels of > 1000 that are accessible to )

personnel, that are located within large areas, such as reactor j containment (i.e., where no enclosure exists' or can reasonably be - -l constructed for, purposes of. locking), or that cannot be continuously {

guarded shall be barricaded and conspicuously posted. A flashing light shall be activated as ,a warning device, i

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6.M RADI N GICA_ E MLUENT MONITORING AND OFFSITE DOSE '

CALCDLATIDI 1ANJA-( EMODCm Sectio RADIOLOGICAL EFFLUENTS MONITORING MANUAL (REM), shall outli l the samp ng and analysis programs to determine the concentration of radioactiv materials released offsite as well as dose commitments to 2 individuals n those exposure pathways and for these radionuclides r eased as a result o It shall also specify operatin f guidelines for facilitkIV!eration.

10AC WASTE TREATMENT SYSTEMS and report con nt.

'Section II, the FSITE DOSE CALCULATION MANUAL (00cM), shall c scribe the l methodology and pa ters to be used in the calculation of o# site doses due to radioactive seous and liquid effluents and in the c .culations of gaseous and liquid e luent monitoring instrumentation Ala Trip Setpoints consistent with the ap icable LCO's contained in these T hnical Specifications.

Changes to the REM 00CM: i

a. Shall be documented and teords of reviews per reed shall be retained as required by Specificatt n 6.10.3.m. This ocumentation shall contain:

. 1) Sufficient information to support th change together with the appropriate analyses or av uation justifying the change (s), and

2) A determination that the cha 11 maintain the level of radioactive affluent control r ired by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and p dix I to 10CFR Part 50 and not adversely impact the accurac or liability of effluent, dose, or setpoint calculations.

b. Shall become effective after view and ac ptance by PORC and the approval of the Unit Directo . ,

c. Shall be submitted to the onnission in the fo of a complete, legible i copy of the entire REM ODCM, as appropriate, as a part of or i concurrent with the Anr al Radioactive Effluent ort for the seriod i of the report in whic any change was made. Each ange shall >e l identified by markin in the margin of the affect ages clearly  !

indicating the are of the hall indicate .

the date (e.g., th/ year)page that was changed, ardthe change was implemI 6.14 RADIQACTIVE W E TREATMENT I

Procedures for ~i id and gaseous radioactive affluent discharges from the facility shall prepared, approved, maintained and adhered to fo all operations inv ving offsite releases of radioactive effluents. The a ENT procedures sh 1 specify the use of appropriate RADI0 ACTIVE WASTE TRE SYSTEMS util ing the guidance provided in the REM 00CM.

10 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accorda e The Solid with the rocess Control Program to process wet radioactive wastes to meet l shippin and burial ground requirements.

MECK 6-20 Amendment No. 117. J5), 177, 179, 191, 192 i

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i INISTRATIVE CONTROLS  ;

l 6.15 LETED 6.16 DELE D.

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AM NECK 6-21 AmendmentNo.JJ),JJJ, 7,192 _ l

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Docket No. 50-213 CY-99-041 Attachment 2 Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Retyped Pages June 1999 p l

i.

l-

-4.

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 l provisions of the Commission-approved physical security, guard i 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 l 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 The movement of special nuclear material used as reactor fuel into the containment is prohibited.

D. This license is effective as of the date of issuance 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 storage, control and maintenance of the spent fuel, in a safe condition; and

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.

FOR THE ATOMIC ENERGY COMMISSION A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing j Original Signed by A. Giambusso Eaclosure:

Appendices A and B - Technical l _ Specifications Date of Issuance: December 27, 1974 i

l l

1

INDEX DEFINITIONS SECTION pgg La DEFINITIONS 1.1 ACTI0N..................................................... 11

.1.2 . CERTIFIED FUEL HANDLER..................................... 1.1 1.3 MEMBER (S) 0F THE PUBLIC . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1- 1 1.4 OPERABLE - OPERABILITY..................................... 1-1 1.5 RADI0 ACTIVE WASTE TREATMENT SYSTEMS........................ 1-2 1.6 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REM 0DCM)............................... 1-2 1.7 SITE B0VNDARY.............................................. 1-2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS LH DELETED 2.0 BASES DELETED LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY 3.0.1 ....................................................... 3/4 0 1 3.0.2 ....................................................... 3/4 0 1 3.0.3 DELETED 3.0.4 ....................................................... 3/4 0-1 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 HADDAM NECK I Amendment No.12S.1E ,178.12.193,

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS (continued)

SECTION PAGE 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 3/4.9 SPENT FUEL BUILDING OPERATIONS 3/4.9.1 DELETED 3/4.9.2 DELETED 3/4.9.3 DELETED 3/4.9.4 DELETED 3/4.9.5 DELETED 3/4.9.6 DELETED 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING .................... 3/4 9 1  !

3/4.9.8 DELETED 3/4.9.9 DELETED 3/4 9.10 DELETED 3/4.9.11 WATER LEVEL SPENT FUEL P00L........................... 3/4 9 2 3/4.9.12 DELETED 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L. . . . . . . . . . . . . . . . . . . . 3/4 9 3 4 3/4.9.14 SPENT FUEL POOL REACTIVITY CONDITION................. 3/4 9 4 FIGURE 3.9 2 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS 1 FOR REGION 2........................................... 3/4 9 5 FIGURE 3.9 3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3........................................... 3/4 9 6 FIGURE 3.9 4 SPENT FUEL POOL RACK REGION LOCATIONS.................. 3/4 9 7 3/4.9.15 DELETED 3/4.9.16 SPENT FUEL POOL COOLING DEFUELED..................... 3/4 9 8 3/4.10 DELETED

-3/4 11 DELETED HADDAM NECK II Amendment No.125.liS.158.179.180 193.

7 L

l INDEX l

)

, )

BASES SECTION pgig 3/4.0 APPLICABILITY 3.0.1 ......................................................B 3/4 0-1 3.0.2 ......................................................B 3/4 0 2 3.0.3 ' DELETED i 3.0.4 ......................................................B 3/4 0 3 1 4.0.1 ......................................................B 3/4 0 4 4.0.2 .......................................................B 3/4 0 4 4.0.3 ......................................................B 3/4 0 4 4.0.4 ......................................................B 3/4 0-5 3/4.1 DELETED 3/4.2 DELETED  ;

3/4.3 DELETED .] l 3/4.4 DELETED l 3/4.5 DELETED 3/4 5 DELETED  ;

3/4.7 DELETED l 3/4.8 DELETED 3/4.9 SPENT FUEL BUILDING OPERATIONS 3/4.9.1 DELETED 3/4.9.2 DELETED 3/4.9.3 DELETED 3/4.9.4 DELETED 3/4.9.5 DELETED ,

3/4.9.6' DELETED 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING....................B 3/4 9 1 3/4.9.8 DELETED 3/4.9.9 DELETED 3/4.9.10 DELETED 3/4.9.11 WATER LEVEL SPENT FUEL P00L.........................B 3/4 9 1  !

3/4.9.12 DELETED 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P00L...................B 3/4 9 1 3/4.9.14 SPENT FUEL POOL - REACTIVITY CONDITION................B 3/4 9 1 3/4.9.15 DELETED

3/4.9.16 SPENT FUEL P00L COOLING DEFUELED....................B 3/4 9 2 3/4.10 DELETED 3/4 11 DELETED HADDAM NECK III Amendment No.125.127.158.175.1SS.

493,

1 l

INDEX DESIGN FEATURES SECTI0lj EME M SLTE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1 M SPENT FUEL STORAGE 5.2.1 C R ITI CAL I TY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 1 5.2.2 DRAINAGE................................................... 52 l 5.2.3 CAPACITY................................................... 52 i ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY............................................. 61 6.2 ORGANIZATION 6.2.1 General Organizational Requirements........................ 6 2 6.2.2 Facility Staff............................................. 6 3 TABLE 6.2 1 MINIMUM SHIFT CREW COMPOSITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4 6.3 FACILITY STAFF QUALIFICATIONS.............................. 6 5 i 6.4 TRAINING................................,................... 66  !

6.5 PROCEDURES AND PROGRAMS 67 l 6.6 PROGRAMS AND MANUALS l )

6.6.1 Radiation Protection Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 1 6.6.2 Process Control Program (PCP).............................. 6 8 6.6.3 Radiological Effluent Monitoring and Offsite Dose Cal cul ation Manual (REM 0DCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 6.6.4 Radiological Effluent Control s Program. . . . . . . . . . . . . . . . . . . . 6 10

-6.6.5 Radioactive Environmental Monitoring Program. . . . . . . . . . . . . . 6 12 ,

6.6.6 Spent Fuel Pool Cooling and Makeup Monitoring Prog"am..... 6 12 1 6.6.7 Technical Specification (TS) Bases Control Prograin. ..... . . 613 6.7 REPORTING REQUIREMENTS 6.7.1 Occupational Radiation Exposure Report.................... 6 14 1 6.7.2 Annual Radiological Environmental Operating Report. . . . . . . . .ti 14 l 6.7.3 Annual Radiological Effluent Release Report. . . . . . . . . . . . . . . 6 15 6.8 HIGH RADIATION AREA....................................... 6 16 l HADDAM NECK IV Amendment No.125.155.158.170.181.

493,

I INDEX QESIGlUEATURES SECTION 11GE L1 SHE.......................................................51 L2 SPENT FUEL STORAGE 5.2.1 CRIT NALITY................................................ 51 5.2.2 DR/u taGE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 2 5.2.3 CAPACITY................................................... 52 i

ADMINISTRATIVE CONTROLS j 6.1 RESPONSIBILITY............................................. 61 6.2 ORGANIZATION 6.2.1 General Organizational Requirements. . . . . . . . . . . . . . . . . . . . . . . . 6 2

'6.2.2 Facility Staff............................................. 6-3 TABLE 6.2 1 HINIMUM SHIFT CREW COMPOSITION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4 6.3 FACILITY STAFF QUALIFICATIONS................ ............. 6 5 6.4 TRAINING................................................... 66 6.5 PROCEDURES AND PROGRAMS 67 l 6.6 PROGRAMS AND MANUALS l 1 6.6.1 Radi ation Protection Program. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 6.6.2 Process Control Program (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 i 6.6.3 Radiological Effluent Monitoring and Offsite Dose Cal cul ation Manual (REMODCM) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 9 i 6.6.4 Radiological Ef fluent Control s Program. . . . . . . . . . . . . . . . . . . . 6-10  !

6.6.5 Radioactive Environmental Monitoring Program. . . . . . . . . . . . . . 6 12 6.6.6 Spent Fuel Pool Cooling and Hakeup Monitoring Program..... 612 6.6.7 Technical Specification (TS) Bases Control Program........ 613 6.7 REPORTING REQUIREMENTS 6.7.1 Occupational Radiation Exposure Report.................... 6 14 6.7.2 Annual Radiological Envirc imental Operating Report........ 614 l 6.7.3 Annual Radiological Efflue, t Release Report. . . . . . . . . . . . . . . 6-15 6.8 HIGH RADIATION AREA....... ............................... 6 16 l HADDAM NECK IV Amendment No.125.155,158.170.181 493 1

1.0 DEFINITIONS i

NOTE -- - - - -- - - -- -

The defined terms of this section appear in capitalized type and.are applicable throughout these Technical Specifications.

ACTION 1,1 ACTION shall be that part of a Technical Specification which prescribes l remedial measures required under designated conditions.

CERTIFIED FUEL HANDLER 1.2 A CERTIFIED FUEL HANDLER is an individual who complies with provisions of the CERTIFIED FUEL HANDLER training program required by Specification 6.4.1.

i MEMBER (S) 0F THE PUBLIC 1.3 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l l occupationally associated with the plant. This category does not l include employees of the licensee, its contractors, or vendors. Also 1 excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.

OPERABLE OPERABILITY 1.4- A system, subsystem, train, component, or device shall be OPERABLE or 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).

HADDAM NECK 11 Amendment No.125,192,

E i l

1.0 DEFINITIONS (continued) l RADI0 ACTIVE WASTE TREATMENT SYSTEMS 1.5 RADI0 ACTIVE WASTE TREATMENT SYSTEMS are those liquid, gaseous and solid waste systems which are required to maintain control over radioactive material in order to meet the requirements set forth in the REM 0DCM.

l RADIOLOGICAL EFFLUENT MONITORING and 0FFSITE DOSE CALCULATION MANUAL (REMODCH) 1.6 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 l pathways and for those radionuclides which lead to the highest potential radiation exposures to individuals from station operation. An 0FFSITE DOSE CALCULATION MANUAL (00CM) shall be a manual containing the methodology and parameters 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 6.6.3.

l l

SITF_ BOUNDARY l

1.7 The SITE BOUNDARY shall be that line beyond which the land is neither l owned, nor leased, nor otherwise controlled by the licensee.

1 i

HADDAM NECK 12 Amendment No.125.193,

l SPENT FUEL BUILDING OPERATIONS l 3/4.9.7 CRANE TRAVEL SPENT FUEL BUILDING l

. LIMITING CONDITION FOR OPERATION 3.9.7 Loads > 1800 pounds shall be prohibited from travel over fuel l

assemblies in the spent fuel pool. )

i

(

l APPLICABILITY: With fuel assemblies in the spent fuel pool. 1 l

ACTION:

With the requirements of the above specification not satisfied, l

place the crane load in a safe condition.

I i

SURVEILLANCE REQUIREMENTS 4.9.7 Administrative controls that prevent the travel of loads > 1800 pounds over fuel assemblies shall be in place prior to lifting a load > 1800 pounds.  !

l l

I HADDAM NECK 3/4 9 1 Amendment No. 125,158, l

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o SPENT FUEL BUILDING OPERATIONS l 314.9.11 WATER LEVEL SPENT FUEL POOL l LIMITING CONDITION FOR OPERATION 3.9.11. > 20. feet of water shall be maintained over the top of fuel l assemblies seated in the spent fuel pool racks.

APPLICABILITY: Whenever fuel assemblies are in the spent fuel pool. l

)

I ACTION:

With the requirements of the above specification not satisfied, i

a. -suspend all movements of fuel assemblies and crane operations with loads over storage racks containing fuel, and

b. restore the water level to within its limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 1 l

SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the spent fuel pool shall be determined to be at least its minimum required level at least once per 7 days when fuel assemblies are in the spent fuel pool.

i i

HADDAM NECK 3/4 9 2 Amendment No.435. l

SPENT FUEL BUILDING OPERATIONS l 3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL LIMITING CONDITION FOR OPERATION i

3.9.13: Psior 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 2 800 ppm.

l 6PfLICABILITY: 'Whenever a fuel' assembly is moved in the spent fuel pool. l ACTION:

With the boron concentration < 800 ppm, suspend the movement of -l all fuel .in the spent fuel pool.

SURVEILLANCE REQUIREMENT  !

4.9.13- Verify that the boron concentration is t 800 ppm within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l prior to~any movement of a fuel assembly in the spent fuel pool and j every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter during fuel movement. l 5

4 I

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l HADDAM NECK 3/4 9 3 Amendment No.W6, l

1 SPENT FUEL BUILDING OPERATIONS l 3/4.9.14 SPENT FUEL P00L RFACTIVITY CONDITION l l LIMITING CONDITION FOR OPERATION 3.9.14' The reactivity condiition of the spent fuel pool shall be such that K.r,is s 0.95 at all times. l APPLICABILITY: Whenever fuel is in the spent fuel pool.- l ACTION:

1 Immediately 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. '

l i

SURVEILLANCE REQUIREMENT  ;

i 4.9.14 Ensure that all fuel assemblies to be placed in the spent fuel pool I are within the enrichment and burn up limits of Figure 3.9 2 (Region 2) and 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 1

4 HADDAM NECK 3/4 9 4 Amendment No.4E488, l

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FIGURE 3.9 4 SPENT FUEL POOL RACK REGION LOCATIONS HADDAM NECK 3/4 9 7 Amendment No.175.1BS, l )

SPENT FUEL BUILDING'0PERATIONS l 3/4.9.16 SPENT FUEL P0OL COOLING DEFUELED LIMITING CONDITION FOR OPERATION 3.9.16 The spent fuel pool coolant temperature shall be maintained at 5 150 *F. l APPLICABILITY: Whenever fuel assemblies are stored in the spent fuel pool.

ACTION:

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. Immediately verify that a spent fuel cool makeup water source is available, and

c. Within 7 days, restore the spent fuel pool coolant temperature to within the limit.

SURVEILLANCE REQUIREMENTS 4.9.16- At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, verify that the spent fuel pool coolant' temperature is 5 150 *F . l 1

HADDAM NECK i 3/4 9 8 Amendment No.M3, I

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l 3/4.9 SPENT FUEL BUILDING OPERATI0ftS l BASES 3/4.9.7 CRANE TRAVEL - SPENT FUEL BUILDING l

The. restriction on movement 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 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 is consistent with the activity release l 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 1 Report HI-941225, Rev. O, " Accident Analysis Report for CY Spent Fuel Racks," j Dr. Yu Wang, Item 11, Holtec Pruject 40264) performed for License Amendment '

188.

3/4.9.11 WATER LEVEL - SPENT FUEL P0OL 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 > 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (as of December 1997), based on an initial spent ]

fuel pool temperature of 150 *F and no evaporative cooling.

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL P0OL l

The limitations of this specification ensure that, in the event of any fuel I handling accident in the spent fuel pool, K,rr will remain s 0.95. l l 3/4.9.14 SPENT FUEL POOL -

RFACTIVITY 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.

HADDAM NECK B3/4 9 1 Amendment No.125,158,175,188,193,

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SPENT FUEL BUILDING OPERATIONS-

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' BASES-l

.3/4.9.16' ' PENT S FUEL P00L COOLING DEFUELED~ -

1 The primary basis _for 150 . F is to limit thermal stresses on the spent fuel j pool concrete; structures'due to the differential ~ temperature across the

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. internal and exterior surfaces of the walls and floor. The basis is further discussed in License ~ Amendment No. 188.

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I As of May 1998, the spent fuel heat load was calculated to be-

< 2.3E+06 BTU /hr. Each heet exchanger has the capability of removing this

. heat load. 0ne. 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 1s approximately 1.2. F/hr. - Thus in the event of a complete loss of forced

. cooling'and assuming an initial spent fuel pool temperature of 150 'F, the time to boil, assuming no evaporative cooling, is > 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />. Therefore.

sufficient time exists to either reestablish forced cooling or to provide makeup to maintain the spent fuel pool inventory, i

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l HADDAM NECK B3/4 9 2 Amendment No. 125,175,18 ,193, 1

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n-l 5.0 DESIGN FEATURES 4 l 5.1 Site The plant site, consisting of approximately 525 acres, is located in the Town of Haddam, Middlesex County, Connecticut, on the east bank of the Connecticut River.

l 5.2 Spent Fuel Storage 5.2.1 Criticality l

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 I

neutron absorber surrounding each assembly to ensure a K,rr s .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. j

b. For Region 2, a nominal 9.00 inch center-to center distance including neutron absorber surrounding each assembly to ensure a K,rr 5 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 Ke rr 5.95 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.

HADDAM NECK 51 Amendment No. 125,142,175.188, 493,

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5.2 -Spent Fuel Storage (continued) 5.2.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 27.0 feet j MSL.  !

5.2.3 Capacity 'l l

l 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 i in Region 3 for a total of 1480 storage locations. I i

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HADDAM NECK 52 Amendment No. 125.142.175.188.

493, l

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5.0 ADMINISTRATIVE CONTROLS 6.1 Responsibility l

6.1.1 The VP Operations and Decommissioning shall be responsible for overall facility operation and shall delegate, in writing, the  ;

succession to this responsibility during his absence.

i 6.1.2 The Unit Director or his designee, in accordance with approved administrative procedures, shall approve each proposed test or experiment, and each set of fuel movements or load movements over the ' spent fuel pool, prior to implementation and shall approve i modification to systems, structures, or components that affect the safe storage of irr6diated fuel.

6.1.3 The Shift Manager (SM) shall be responsible for the operational command function.

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HADDAM NECK 6-1 Amendment No. 125.155.158.191, M3, u -

'6.0 ADMINISTRATIVE CONTROLS

.6.2 Organization 6.2.1 General Oraanizational Reauirements Unit organizations shall be established for unit operation and corporate management, respectively. These organizations shall include positions.

for activities affecting the safe storage of irradiated fuel.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including al1 operating organization .

J positions. ~ These relationships shall be~ documented and updated, as appropriate, in the form of organization charts, functional

. descriptions of departmental-responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Connecticut Yankee _ Quality Assurance Program (CYQAP).

b. The Unit Director shall have overall responsibility for the unit, and shall have control over those onsite activities necessary for

. maintenance and storage of irradiced fuel in a safe condition.

c. The VP - Op? rations and Decommissioning shall have corporate responsibility for overall plant nuclear safety and shall take any i measures needed to ensure acceptable performance of the staff in j operating, maintaining, and providing technical support to the  ;

plant to ensura nuclear safety, j

d. The individuals who train the CERTIFIED FUEL HANDLERS and Equipment Operators, and those who carry out health physics and quality assurance functions, may r mort to'the appropriate onsite l manager; however, they shall.have sufficient organizational '

freedom to ensure their ability to perform their assigned functions.

i HADDAM NECK 62 Amendment No. 125,155,191. '

493.

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i' h 6.2 Organization -(continued)

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-6.2.2 Facility Staff.

a. Each on duty shift shall be composed of at least the minimum shift l crew composition shown in Table 6.21. j i

l b. At.least one person qualified to stand watch in the control room 3 l (a CERTIFIED FUEL HANDLER or an Equipment Operator) shall be  !

l present in the control room when irradiated fuel is in the spent j fuel-pool. l l

c. A individual qualified in radiation protection procedures

• shall be on site during fuel handling operations or movement of loads

over storage racks containing fuel.

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d. All- fuel handling operations shall be observed.and directly supervised by a CERTIFIED FUEL HANDLER who has no other concurrent i responsibilities during this operation. 1 l l

e. Administrative procedures shall be developed and implemented to  ;

l limit the working hours of facility staff who perform functions l l important to the safe storage and handling of irradiated fuel.

f. The Shift Manager shall be a CERTIFIED FUEL HANDLER. 1

• The individual qualified in radiation protection procedures may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the~ required position, j

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l HADDAM NECK 63 Amendment No. 125.179.192.

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l TABLE 6.2 1 (page 1 of 1) l' MINIMUM SHIFT CREW COMPOSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Shift Manager 1* l Equipment Operator 1 The shift crew's composition may be one less than the minimum requirements of l Table 6.21 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew's composition to within l the minimum requirements of Table 6.2-1. This. provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

• Does not include the CERTIFIED FUEL HANDLER supervising fuel handling operations.

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l HADDAM NECK 64 Amendment No. 125.192, l

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'6.0 ADMINISTRATIVE CONTROLS 6.3 Facility Staff Qualifications 1.

6.3.1 Each member of the facility staff shall ' meet or exceed the minimum qualifications of ANSI N18.11971 for comparable positions.

6.3.1.1 The position of Health Physics Manager shall meet the following l minimum qualifications:

a. Academic degree in an engineering or science field or equivalent as per Section 6.3.1.1.c.

b. Minimum of five years professional technical experience in the area of radiological safety three years of which shall be in applied radiation work in a nuclear facility dealing with problems-similar to those encountered in a nuclear power reactor.

l c. Technical experience in the area of radiological safety beyond the i five year minimum may be substituted on a one for one basis towards the academic degree requirement (four years of technical  !

experience being equivalent to'a four year academic degree).

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d. Academic and technical experience must total a miniinum of nine  !

years.

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l l-i HADDAM NECK 65 Amendment No. 125,155.192.

6.0' ADMINISTRATIVE CONTROLS 6.4 Training 6.4.1 An NRC approved retraining and replacement training program for l the CERTIFIED FUEL HANDLERS shall be maintained under the direction of the Unit Director.

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l HADDAM NECK 66 Amendment No. 125.125.155,192, j

6.0 ADMINISTRATIVE CONTROLS 6.5- -Procedures and Programs 6.5.1 Written procedures shall be ' established, implemented, and maintained covering the activities referenced below:

a. The procedures applicable to the safe storage of spent fuel l l . recommended in Regulatory Guide 1.33, Appendix A (Revision 2, i i

February 1978).

b. All prop 3ms specified in Specification 6.6.  !

c. Fire Protection Program implementation.

l d. Quality controls for effluent monitoring, using the guidance in Regulatory Guide 1.21 Rev.1 June 1974.

! e. The use or operation of RADWASTE TREATMENT SYSTEMS utilizing the ,

! guidance provided in the REM 0DCH.

6.5.2 Each procedure of Specification 6.5.1 and program of Specification 6.6, and changes thereto, shall be independently reviewed-in accordance with administrative procedures and approved by the Unit Director or designee prior to implementation.

6.5:3 Temporary changes to procedures ~of Specification 6.5.1 may be made provided: l

a. The intent of the existing procedure is not altered: l

b. The change is approved by a member-of the plant management staff and a CERTIFIED FUEL HANDLER: and

c. The change is documented, reviewed and approved by the Unit l Director or designee within 14 days of implementation.

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l HADDAM NECK 67 Amendment No. 125,155,153.181.

191.192,192, 1

6.0 ADMINISTRATIVE CONTROLS 6.6 Programs and Manuals 6.6.1 Radiation Protection Proaram A program for personnel radiation protection shall be prepared consistent with the requirement of 10 CFR 20 and shall be approved,.

maintained, and adhered to for all operations involving personnel radiation exposure.

6.6.2 Process Control Prooram (PCP)'

The PCP shall contain the current formulas, sampling, analyses.- tests.

and determinations to be made.to ensure that processing and packaging of solid radioactive wastes will be accomplished to ensure. compliance with 10 CFR Parts 20, 61, and 71; state regulations; burial ground requirements; and other requirements governing the disposal' of solid radioactive waste.

Changes to the PCP:

a.. Shall be documented and records of reviews shall be retained.

This documentation shall contain. l

1. sufficient information to support each change, together with the appropriate analyses or evaluations to justify the j change; and '

2. a determination that each change maintains the overall j conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations; and  !

b.. Shall become effective after the change is independently reviewed in accordance with administrative procedures and approved by the  !

Unit Director or designee.

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l HADDAM NECK 68 Amendment No. 125,155,158,191, j

6.6 Programs and Manuals (continued) 6.6.3 Radiolooical Effluent Monitorino and Offsite Dose Calculation flanual (REM 0DCM)

The REM 0DCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program.

The REM 0DCM shall also contain the Radioactive Effluent Controls and Radiological Environmental Monitoring Program required by Specifications 6.6.4 and 6.6.5, respectively, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required under Specifications 6.7.2 and 6.7.3.

Changes to the REMODCH:

a. Shall be documented and records of review shall be retained. This documentation shall contain:

l 1. sufficient information to support each change together with the appropriate analyses or evaluations to justify the change; and l 2. a determination that each change maintains the levels of I

radioactive effluent control required by 10 CFR 20.106, l

40 CFR Part 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and that the change will not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after the change is independently reviewed in accordance with administrative procedures and approved by the l l

Unit Director or designee: and

c. Shall be submitted to the NRC in the form of a complete legible copy of the entire REM 0DCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change was made to the REM 0DCM, Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the I change was implemented.

1 HADDAM NECK 69 Amendment No. 125.155,158.170

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l' i- 6.6 Programs and Manuals (continued) i 6.6.4 Radioactive Effluent Controls Proaram -

L i This program conforms to 10 CFR 50.36a for the control of radioactive l effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from i radioactive effluents as low as reasonably achievable. The program shall be contained in the REMODCM, shall-be implemented by procedures,

! and shall include remedial actions to be taken whenever the program l limits are exceeded.' The program shall include the following elements: i i

a. Limitations;on the functional capability of radioactive liquid and gaseous monitoring instrumentation, including surveillance tests i

and setpoint determinations, in accordance with the methodology described in the REM 0DCH:

b.- Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to the pre-1994 concentration values in 10 CFR Part 20, Appendix B (to '

20.1 to 20.602). Table II, Column 2:

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c. Monitoring, sampling, and analysis of radioactive liquid and '

l gaseous' effluents in accordance with 10 CFR 20.106 and with the  ;

I methodology'and parameters described in the REM 0DCM:

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d. Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid l effluents released from the facility to unrestricted areas, conforming to 10 CFR Part 50, Appendix I:

e. Determination of cumulative and projected dose contributions from l radioactive effluents for the current calendar quarter and current  !

calendar year in accordance with the methodology and parameters  ;

described in the REM 0DCH (performed at least every 92 days);

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f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate l portions of these systems are used to reduce releases of l radioactivity when the projected doses in a period of 31 days L would exceed 2% of the guidelines for the annual dose or dose

commitment, conforming to 10 CFR Part 50, Appendix I; I

HADDAM NECK 6 10 Amendment No.

n 1 6.6 Programs and Manuals (continued) 6.6.4 Radioactive Effluent Controls Proaram (continued)

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the SITE B0UNDARY shall be as follows:

1. for noble gases: 5 a dose rate of 500 mrem /yr to the total '

body and 5 a dose of 3000 mrem /yr to the skin; and l

2. for tritium and all radionuclides in particulate form with half lives > 8 days: $ to a dose rate of 1500 mrem /yr to  !

any organ;

h. Limitations on the annual and quarterly air doses from noble gases released in gaseous effluents from the unit to areas beyond the SITE BOUNDARY conforming to 10 CFR Part 50, Appendix I;  !

i. Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each  ;

facility to areas beyond the SITE B0UNDARY, conforming to 10 CFR l Part 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any at points )

beyond the SITE BOUNDARY due to releases of radioactivity and to ,

radiation from uranium fuel cycle sources, conforming to 40 CFR Part 190.

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HADDAM NECK 6 11 Amendment No.

6.6 Programs and Manuals (continued) 6.6.5 Radioloaical Environmental Monitorina Proaram This program monitors the radiation and radionuclides in the environs of the facility. The program shall provide representative measurements of radioactive materials in the highest potential exposure pathways, verification of the accuracy of the effluent monitoring program, and modeling of environmental exposure pathways. The program shall be contained in the REMODCM and shall include the following:

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a. Monitoring, sampling, analysis, and reporting of radiation and I radionuclides in the environment in accordance with the methodology and parameters described in the REH0DCH: and

b. Participation in an Interlaboratory Comparison Program to ensure i that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample i matrices are performed as part of the quality assurance program  ;

for environmental monitoring.

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6.6.6 Soent Fuel Pool Coolina and Makeuo Monitorina Proaram This Program requires that the primary method for spent fuel pool cooling and the primary method for spent fuel pool water makeup capability be monitored and maintained. This program shall provide reasonable assurance that the equipment, components, systems and water sources, including spent fuel pool water chemistry, used for spent fuel l pool cooling and for maintaining spent fuel pool water level are capable of fulfilling their intended functions and are protected against freezing.

HADDAM NECK 6 12 Amendment No. 493, 1

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l 6.6 Programs and Manuals (continued) 6.6.7 Technical Soecifications (TS) Bases Control Proaram l

This program provides a means for processing changes to the Bases of these Technical' Specifications.

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a. Changes to-the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Changes may be made to Bases without prior NRC approval, provided the changes do not involve either of the following:

1. a change in the TS incorporated in the license: or i

2. a change to the updated FSAR or Bases that involves an i unreviewed safety question as defined in 10 CFR 50.59. j

c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained in a manner that is consistent with the FSAR.

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d. Proposed changes that do not meet the criteria of Specification 6.6.7.b above shall be reviewed and approved by the NRC prior to {

implementation. Changes to the Bases implemented without prior l NRC approval shall be provided to the NRC on a frequency that is consistent with 10 CFR'50.71(e).

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HADDAM NECK 6 13 Amendment No.

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-6.0 ADMINISTRATIVE CONTROLS l 6.7- Reporting Requirements The'following reports shall be submitted in accordance with 10 CFR 50.4. g

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i 6.7.1' Occupational Radiation Exoosure Reoort 2 An Occupational Radiation Exposure Report covering the activities of the facility during the previous calendar year shall be submitted by May 1 of each year. A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures

>-100 mrem /yr and their associated person 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 movement). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on self-reading dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. femall exposures totaling < 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 should be assigned to specific major work functions. j 6.7.2 Annual Radioloaical Environmental Operatina Report The Annual Radiological Environmental Operating Report 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 summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM).

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to  ;

the locations specified in the tables and figures in the REM 0DCM, as well as summarized and tabulated results of these analyses and measurements. In the event that some individual results are not I

[ available for inclusion with the report, the submitted report shall note and explain the reasons for the missing results. The missing data shall be submitted in a supplementary report.

HADDAM NECK 6 14 Amendment No. 125.155,192,

6.7 Reporting Requirements (continued)  !

6.7.2 Annual Radioloaical Environmental Operatina Report (continued)

The Annual Radiological Environmental Operating Report shall include licensee initiated changes to the REMODCM during the period of the report as described in Specification 6.6.3, or these changes shall be  :

submitted concurrently. l 6.7.3 Annual Radioactive Effluent Release Report  ;

The Radioactive Effluent Release Report covering the operation of the facility shall be submitted in accordance with 10 CFR 50.36a. The i Report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility. The j material provided shall be consistent with the objectives outlined in the REH0DCM and Process Control Program.

The Radioactive Effluent Release Report covering the activities during .

the previous calendar year shall be submitted by May 1 of each year. l l

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I HADDAM NECK 6-15 Amendment No. 125.155.158.170.

493.

6.0 ADMINISTRATIVE CONTROLS 6.8 High Radiation Area 6.8.1 Pursuant to 10 CFR 20.1601(c), in lieu of the " control device" or " alarm signal" required by 10 CFR 20.1601, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is > 100 mrem /h but 5 1000 mrem /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 RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 5 1000 mrem /h provided they are otherwise following l plant radiation protection procedures for entry into such areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that 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.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device and who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Manager in the RWP.

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HADDAM NECK 6 16 Amendment No. 125.155.192,

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6.8 Hiah Radiation Area (continued) 6.8.2 In addition to the requirements of Specification 6.8.1, areas accessible to personnel with radiation levels > 1000 mrem /h at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates i shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or health physics supervision. Doors shall l remain locked except during periods of access by personnel under an approved RWP that specifies the dase rate levels in the innediate work areas and the maximum allowable stay time for individuals in those areas. 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.

6.8.3 Areas with radiation levels of > 1000 mrem /h that are accessible to personnel, that are located within large areas, such as reactor containment (i.e., where no enclosure exists or can reasonably be l constructed for purposes of locking), or that cannot be continuously '

guarded shall be barricaded and conspicuously posted or have a flashing light activated as a warning device.

l HADDAM NECK 6 17 Amendment No. 125.155.158.192,

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Docket No. 50-213 CY-99-041 i

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Attachment 3 Haddam Neck Plant Proposed Revision To The Operating License And The Technical Specifications Descilption Of Changes l

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l June 1999 l

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f U. S. Nuclsar Regulttory Commission

. CY-99-041/ Attachment 3/Page 1 General Reason For The Chances 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 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 change, the phrase "Defueled Condition" will signify that the above rationale is applicable. .

Substantive content changes have also been made to the specifications as described below, i

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 -

applicable.

Unnecessary pages were eliminated from the final product to make it as compact and easy to use as possible. Thus the LCO and Surveillance sections now consist of only those associated with Chapters 3.0 and 3.9. Chapter 3.9 has been reduced to five pages,

- however the numbering of the LCOs in 3.9 has not changed. The contents will be.

reflected by the Index listing the removed material. (When the approved Amendment is implemented, these will also be reflected in the updated List of Effective Pr.ges.)

Some minor format changes are proposed in Chapters 1,5 and 6. TF.is has been done for clarity and to bring the format closer to the standard of draft NUREG-1625. These format changes primarily affect the section headings.

Consistent with draft NUREG-1625, and for increased clarity, symbols have replaced words where appropriate, e.g., "<" has replaced "less than or equal to", and "*" has replaced " degrees". Also the term "mr/h" has been replaced with " mrem /h" to clarify that the r stands for rem rather than rad.

(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 l December 5,1996.

U. S. Nucisar R:gulatory Commission CY-99-041/ Attachment 3/Page 2 Finally, some of the changes discussed herein are proposed for other reasons. When this is the case, the specific reason will be provided. Substantive content changes have also been made to the specifications as described below.

l FACILITY OPERATING LICENSE A. Chaneg

1. Delete:

"This license is effective as of the date of issuance and shall expire at l midnight, June 29,2007."

Replace with:

"This license is effective as of the date of issuance 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 storage, control and maintenance of the spent fuel, in a safe condition; and i 2. Conduct activities in accordance with all other restrictions applicable l to this facility in accordance with NRC regulations and the specific provisions of this 10CFR50 facility license."

Reason

1. Defueled Condition Basis l l

1. The revision to the license expiration reflects the requirements of 10 CFR 50.51(b).

B. Chanae

2. Delete License Condition 2.C(6), integrated Implementation Schedule, and change condition 2.C(7), Fuel Movement, to 2.C(6). ,

l

U. S. Nuchar Regulatory Commission CY-99-041/Attachm:nt 3/Paga 3 Reason

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.

Basis

2. The expiration date for the license condition has passed.

1.

i l TECHNICAL SPECIFICATIONS l GENERAL K. Chances

1. Where multiple pages in sequence have been deleted, they have been removed and subsequent pages repaginated. Where a whole Section has been deleted, its whole tab has been removed. Such wholesale removals are indicated in the Index by showing the section number followed by

" DELETED". In addition, minor typographical errora %9 corrected.

2. Some material is being transferred to the Connecticut Yankee Quality Assurance Program (CYQAP), the Radioactive Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), or to the Technical Requirements Manual (TRM). This material will be relocated verbatim with the exception of section, table and reference numbers. These will be changed to reflect the format of the CYQAP, REMODCM or the TRM.

Reason 1

Defueled Condition, Editorial Changes, Administrative Letter 95-06<2), Generic Letter 95-100), Generic Letter 89-01W , NUREG-14310), and draft NUREG 16258)  !

4 (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

g U. S. NucleIr Regulatory Commission CY-99-041/ Attachment 3/Page 4 Basis 1

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, Generic Letter S5-10, and is consistent with the Standard Technical Specifications for Westinghouse Plants (WOG STS) provided in NUREG-1431. The movement of material to the REMODCM is in accordance with Generic Letter 89-01 and is consistent with NUREG-1431 and NUREG-1625.

C. INDEX Chanaes

1. Revise according to the changes described herein.

l

2. Retain numbering sequences. l

3. The index was repaginated.

Reason Editorial Changes.

l 1

(4) NRC Generic Letter GL 89-01," Implementation Of Programmatic Controls For Radiological Effluent Technical Specifications in The Administrative Controls ,

Section Of The Technical Specifications And The Relocation Of Procedural Details Of RETS To The Offsite Dose Calculation Manual Or To The Process Control Program," dated January 31,1989.

(5) NUREG-1431, " Standard Technical Specifications, Westinghouse Plants, Specifications," Office of Nuclear Reactor Regulation, NRC, Volume 1, Revision 1, dated April 1995.

(6) NUREG-1625, " Proposed Standard Technical Specifications for Permanently Defueled Westinghouse Plants," draft dated March 1998.

U. S. Nucl=r Regulatory Commission CY-99-041/ Attachment 3/Page 5 Basis

1. The Index must be revised to reflect the changes made to the Technical Specification sections identified below. The following revisions were implemented:

. Where a whole section has been deleted, it is indicated in the Index by " DELETED", unless the adjacent sections have been renumbered (e.g., for the Definitions).

. If all the subsections of a Technical Specification are deleted, then only the major section is shown to be deleted. The deleted 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 for LCOs and SRs were retained to preclude the need to renumber cross-references and preclude the need to revise procedure references to the Technical Specifications.

3. Reduced the number of pages with no loss of information.

D. 1.0 DEFINITIONS Rhanaes and Reason

1. The following cefinitions have been retained:

1.1 ACTION 1.15 MEMBER (S) OF THE PUBLIC 1.17 OPERABLE - OPERABILITY 1.23 RADIOACTIVE WASTE TREATMENT SYSTEMS  :

1.24 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) 1.29 SITE BOUNDARY However in the definition for RADIOACTIVE WASTE TREATMENT SYSTEMS, make the following editorial change:

Change "LCOs" to " Requirements" Change "those specifications." to "the REMODCM."

T U. S. Nuclur Regulatory Commission CY-99-041/ Attachment 3/Page 6 I

The definition of CERTIFIED FUEL HANDLER has been added since it is l used in the Administrative Controls section.

The definition of REMODCM includes reference to Specification 6.6.3.

The definitions will also be renumbered as follows:

1.1 ACTION 1.2 MEMBER (S) OF THE PUBLIC 1.3 CERTIFIED FUEL HANDLER 1.4 OPERABLE -OPERABILITY 1.5 RADIOACTIVE WASTE TREATMENT SYSTEMS 1.6 ' RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM) 1.7 SITE BOUNDARY All other definition numbers and " DELETED" statements will be eliminated.

2. The following definitions have been deleted:

1.8 CORE ALTERATION 1.18 OPERATIONAL MODE - MODE 1.26 REPORTABLE EVENT 1.27 ~ RHR LOOP

3. Delete Table 1.2, OPERATIONAL MODES along with definition 1.18.

1

4. The following definitions will be transferred to the REMODCM to support the transfer of the specifications for radioactive effluents and radioactive effluent monitoring instrumentation per Generic Letter 89-01:

1.2 ANALOG CHANNEL OPERATIONAL TEST 1.4 CHANNEL CAllBRATION 1.5 CHANNEL CHECK 1.12 FREQUENCY NOTATION 1.30 SOURCE CHECK Table 1.1 FREQUENCY NOTATION The definitions for CHANNEL CHECK and CHANNEL CALIBRATION will also be transferred to the TRM to support the transfer of the meteorological l monitoring instrumentation requirements to the TRM per Generic Letter i 95-10.

{ l l

1

1 i

U. S. Nucl:nr Regulatory Commission CY-99-041/Attschment 3/Page 7

5. The section was repaginated.

6. These changes reflect the defueled condition of the HNP. Minor editorial changes have been made to improve the format and make the section more closely reflect the draft NUREG-1625. 1 Basis

1. The definitions included are referenced by the remaining Technical l Specifications. The definition for CERTIFIED FUEL HANDLER was added in accordance with NUREG-1625. The replacernent of Licensed Operators with Certified Fuel Handlers was approved by License Amendment 192 (NRC letter dated March 27,1998), however this addition was not made at that time. Since there are only five definitions, they have been renumbered.

The editorial change to the definition for RADIOACTIVE WASTE TREATMENT SYSTEMS reflects where the LCOs will be located. d

2. The definitions deleted are not referenced by the remaining Technical Specifications.

3. Since there are no longer any MODES associated with the defueled plant, Table 1.2 (" Operational Modes") is no longer necessary.

4. Those definitions needed to support requirements being transferred to the TRM and/or the REMODCM, will be transferred to the TRM and/or the REMODCM. Table 1.1 (" Frequency Notation"), is not used by the remaining Technical Specifications. However, since requirements being transferred to '

the TRM and REMODCM do use this notation, Table 1.1 will be transferred to the TRM and REMODCM.

5. Reduced the number of pages with little or no information. i

1 l

U. S. Nuclear Regulttory Commission CY-99-041/Att:chment 3/Page 8 l E. 3/4.3 INSTRUMENTATION Chanaes and Reasort  ;

i

1. Delete the entire subsection, including associated tables, figures and bases to reflect the defueled condition.

2. The following are transferred to the TRM per Generic Letter 95-10: i l

3/4.3.3.4 METEOROLOGICAL INSTRUMF.NTATION )

TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUMENTATION TABLE 4.3-5 METEOROLOGICAL MONITORING f INSTRUMENTATION SURVEILLANCE I REQUIREMENTS B3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION

3. The following are transferred to the REMODCM per Generic Letter 89-01:

3/4.3.3.7 RADIOACTIVE LIQUID EFFl UENT MONITORING INSTRUMENTATION TABLE 3.3-9 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 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 l INSTRUMENTATION  ;

TABLE 4.3-8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS l B3/4.3.3.7 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION i

~. a

r U. S. Nucirr R gulatory Commission CY-99-041/ Attachment 3/Page 9 B3/4.3.3.8 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 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 and draft NUREG-1625, 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 10 CFR 50.59.

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 6.6.3, as well as the 10 CFR 50.59 screening required by CYAPCO procedures.

F. 3/4.7 PLANT SYSTEMS Chanaes and Reason

1. Delete the entire subsection, including associated tables, figures and bases to reflect the defueled condition. l

2. The following are transferred to the TRM:

3/4.7.5 SEALED SOURCE CONTAMINATION l l

83/4.7.5 SEALED SOURCE CONTAMINATION Basis

1. With the material being transferred to the TRM, this section is no longer needed.

2. The limitations on sealed source contamination are intended to ensure that the total body or individual organ irradiation dose does not exceed allowable limits in the event of ingestion or inhalation should the source be damaged.

This is done by imposing a limitation on the removable contamination on each sealed source. This requirement and the associated surveillance requirements bear no relation to the conditions or limitations which are

U. S. Nuclar Regulatory Commission

.CY-99-041/ Attachment 3/Page 10 necessary to ensure safe plant operations, and thus is similar to other requirements that do not affect safe plant operation and which are permitted to be relocated to the "SAR" by GL 95-10 and NUREG-1431. 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 10 CFR 50.59.

This change is similar to changes previously approved for Hatch and Grand Gulf.

G. }/4.9 REFUELING OPERATIONS Chanaes G-1. 1. The following are retained with noted changes:

3/4.9 REFUELING OPERATIONS Change the section title to " SPENT FUEL BUILDING OPERATIONS".

This is an editorial change to reflect the defueled condition.

3/4.9.7 ' CRANE TRAVEL - SPENT FUEL STORAGE BUILDING Change the subsection title to " CRANE TRAVEL - SPENT FUEL BUILDING" Change in 3 places, "1650" to "1800". Change in two places, "the storage pool." to "the spent fuel pool." Delete ACTION "b." relating to LCO 3.0.3. These are editorial changes to reflect the defueled condition and changes to other specifications.

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". Delete ACTION "b" relating to LCO 3.0.3. In subsection 4.9.11, change "the storage pool" i to "the spent fuel pool", change " depth" to " level" and change "the fuel l storage pool." to "the spent fuel pool," These are editorial changes to  !

reflect the defueled condition and changes to other specifications.

3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL In subsection 4.9.13, change "every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter." to "every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> thereafter during fuel movement." This clarifies that the Surveillance is only to be performed during the time when the LCO is applicable.

U. S. Nuciser Reguintory Commission CY-99-041/ Attachment 3/Page 11 3/4.9.14 SPENT FUEL POOL-REACTIVITY ';ONDITION in subsection 3.9.14 change " Reactivity Condition" to " reactivity condition" and change "less-than-or-equal-to" to "5".

FIGURE 3.9 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 2 No change other than repagination. j FIGURE 3.9-3 SPENT FUEL POOL RACK MINIMUM BURNUP REQUIREMENTS FOR REGION 3 No change other than repagination.

FIGURE 3.9-4 SPENT FUEL POOL RACK REGION LOCATIONS No change other than repagination.

3/4.9.16 SPENT FUEL POOL COOLING - DEFUELED Delete " irradiated" from APPLICABILITY, for consistency with APPLICABILITY of other LCOs in this section. ~ Change "less than or equal to" to "5" and change " degrees F" to "*F" in both LCO and Surveillance. These are editorial changes for clarity. l 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 i weight". Change "the storage pool." to "the spent fuel pool." Change  !

"the storage racks" to "the spent fuel pool racks". These changes are editorial to reflect the defueled condition, 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 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 4 cooling, the time to boilis greater than 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> (as of December 1997), based on an initial spent fuel pool temperature of 150 *F and no evaporative cooling." These changes reflect the i

U. S. Nucirr Rcgul: tory Commission CY-99-041/ Attachment 3/Page 12 decommissioned state and clarify the basis for the spent fuel pool

, water level.

B3/4.9.13 MOVEMENT OF FUEL IN SPENT FUEL POOL No change.

B3/4.9.14 SPENT FUEL POOL-REACTIVITY CONDITION Change " 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.

G-2, 2. The following were deleted, including associated figures, tables and bases:

3/4.9.1 BORON CONCENTRAT!ON 1 3/4.9.2 INSTRUMENTATION 3/4.9.3 DECAY TIME 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 G-3. 3. The entire section has been repaginated.

. U. S.' Nucle:r Regul: tory Commission

- CY-99-041/ Attachment 3/Page 13 Basis for Chanaes to Subsection 3/4.9

1. For these subsections, the changes are discussed below:

3/4.9 Refueling Operations (now titled: Spent Fuel Building Operations)

The change is editorial and reflects 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 22,1996.0 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 proposed change maintains the heavy load restriction over the spent fuel pool and continues to allow movement of fuel within the spent fuel pool. ACTION "b.", which refers to the deleted Specification 3.0.3, is also deleted. 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)

ACTION "b.", which refers to the deleted Specification 3.0.3, is also deleted; The remaining changes are editorial and provide a .

consistency in terminology. In Surveillance 4.9.11. " level" has  !

replaced " depth" as fuel pool level is the parameter monitored and controlled. l (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.

U. S. Nucle:r Regulatory Commission CY-99-041/Att:chment 3/Page 14 3/4.9.13 Movement Of FuelIn Spent Fuel Pool The change to SR 4.9.13 provides clarification that the verification of boron concentration needs to be kept current only during the movement of spent fuel, as this is the time during which a fuel handling accident could occur.

3/4.9.14 Spent Fuel Pool - Reactivity Condition The changes are editorial and provide a consistency in terminology.

3/4.9.16 Spent Fuel Pool Cooling - Defueled The changes are editorial and provide a consistency in terminology.

83/4.9.7 Crane Travel - Spent Fuel Storage Building (now titled: Crane Travel - Spent Fuel Building)

The deletion of the word " nominal" eliminates the confusion over weight limits. A reference to the load drop analysis is included. The remaining changes are editorial and provide a consistency in terminology. i

' :3!4.9.10 and Water Level- Reactor Vessel And I B3/4.9.11 Storage Pool j' (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 radiciodine removal. This is no longer a concern. The plant was shutdown on July 22,1996. I 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"in 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 u

U. S. Nuclur Reguhtory Commission CY-99-041/ Attachment 3/Page 15 accident dose calculations (HNP UFSAR Section 15.5.2 and Calculation XX-XXX-60RA, Rev.15) which conclude that doses (i.e.,

whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10 CFR 100 dose limits and less than the EPA PAGs.

The' revised Bases reflects the current predominate concern for spent fuel pool water level; that sufficient water inventory be maintained for cooling purposes in the event of a loss of forced cooling.

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, the reactor has been permanently defueled, and License Condition 2.C.(7) prohibits the movement of spent fuel into containment, these subsections are no longer required. Specifically:

3/4.9.1 Boron Concentration The purpose of this specification was to ensure that the reactor remained subcritical during core alterations and that boron concentration was uniform during core alterations. The plant has ,

permanently ceased operations and the reactor has been  !

permanently defueled, core alterations will no longer occur because a  ;

license condition prohibits movement of fuel back into the I containment. Therefore, this specification is no longer needed.

3/4.9.2 Instrumentation ,

i I

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") prohibits  !

movement of fuel back into the containment. Therefore, this specification is no longer needed.

(8) 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 Regulatory Commission, " Proposed Revision To Operating License And Technical Specifications Defueled Operating License And Technical Specifications," dated May 30,1997.

U. S. Nuclear R:gulatory Commission CY-99-041/Attechment 3/Page 16 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 prohibits 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 radionuclide releases to the environment resulting from fuel damage occurring during core alterations or movement of irradiated fuel inside containment would 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 prohibits 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 event, a resin liner fire, does not credit confinement or filtration of particulates. This event bounds a materials handling event inside containment.

)

3/4.9.5 Communications The purpose of this specification was to ensure that refueling persorinel are promptly informed of changes to the plant status or j 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 prohibits movement of fuel back into the containment. Therefore, this specification is no longer needed.

3/4.9.6 Manipulator Crane The purpose of this specification was to ensure ths.t the manipulator I 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,

U. S. Nucisar Regulatory Commission CY-99-041/ Attachment 3/Page 17 refueling operations inside containment have permanently ceased because a license condition prohibits movement of fuel back into the containment. Therefore, this specification is no longer needed.  ;

l 3/4.9.8 Residual Heat Removal and Coolant Circulation l The purpose of this specification was to ensure that there was  ;

l sufficient cooling capacity to maintain the reactor coolant system l l

below 140 'F and that boron stratification was prevented. The plant i has permanently ceased operations and the reactor has been permanently defueled, residual heat removal and boron mixing in the l reactor vessel is no longer needed. Therefore, this specification is no l longer needed.

3/4.9.9 Containmmt 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 i containment. The plant has permanently ceased operations and the I reactor has been permanently defueled, core alterations and/or fuel movement inside ccentainment will no longer occur because a license condition prohibits movement of fuel back into the containment.

Therefore, this specification is no longer needed. j in addition, the containment purge system is not required to be operable during decommissioning because the limiting event, a resin liner fire, does not credit confinement or filtration of particulates. This event bounds a materials handling event inside containment. ,

I 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 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 prohibits movement of fuel back into the containment. Therefore, this specification is no longer needed.

U. S. Nuclar Regul: tory Commission CY-99-041/ Attachment 3/Page 18 3/4.9.12 Fuel Storage Building Air Cleanup System This specification was concerned with radioiodine 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 fuel inventory of the j dose-contributing radioactive iodine and noble gas isotopes has i 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" in 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 Ca!culation XX-XXX-60RA, Rev.15) which conclude that doses (i.e.,

whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10 CFR 100 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. As there is no longer a concern with noble gases, the charcoal filters will be eliminated.

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,M that is applicable to the defueled condition of the Haddam Neck Plant. This was approved by Amendment 193, i but the obsolete specification 3/4.9.15 was not deleted with that i amendment.

3. Reduced the number of pages with little or no information.

l (9) 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.

U. S. Nucirr Regulatory Commission CY-99-041/ Attachment 3/Page 19 H. 3/4.11 RADIOACTIVE EFFLUENTS Chances

1. Delete the entire subsection, including associated tables, figures and bases.

2. The following are transferred to the REMODCM:

3/4.11.1.1 LlQUID EFFLUENTS - CONCENTRATION 3/4.11.1.2 LIQUID EFFLUENTS - DOSE, LIQUIDS 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 i RADIONUCLIDES OTHER THAN NOBLE GASES l 3/4.11.3 TOTAL DOSE 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 i B3/4.11.2.3 GASEOUS EFFLUENTS - DOSE, RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES j B3/4.11.3 TOTAL DOSE i Reason and Basis

1. The material is being transferred to the REMODCM in accordance with l

- Generic Letter 89-01. With the material being transferred to the REMODCM, this section is no longer needed and reflects the defueled condition.

2, _ In accordance with the guidance in Generic Letter 89-01, and for consistency i with NUREG-1431 and draft NUREG-1625, these sections are transferred to the REMODCM where they will be controlled by CYAPCO procedures. I

U. S. Nuclear Regulatory Commission CY-99-041/ Attachment 3/Page 20 Changes to the REMODCM require a 10 CFR 50.59 applicability review be conducted in accordance with CYAPCO procedures.

l. 5.0 DESIGN FEATURES Chanaes

1. 5.1 SITE Subsection 5.1.1 and 5.1.2 and associated Figures 5.1-1 and 5.1-2 are deleted and replaced with a text description of the site.

2. 5.5 METEOROLOGICAL TOWER LOCATION Section 5.5 and associated Figure 5.1-1 are deleted.

3. 5.6 SPENT FUEL STORAGE Section 5.6 is renumbered as Section 5.2, and editorial changes are proposed for consistency and clarity.

Reason and 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 and replaced with a narrative description of the site. This is consistent with the guidance of NUREG-1431 and draft NUREG-1625, and has been previously approved for other decommissioning plants, such as Maine Yankee.

2. The Meteorological Instrumentation is being relocated to the TRM in  ;

accordance with the guidance of Generic Letter 95-10. 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, j METEOROLOGICAL TOWER LOCATION and its associated figure, can be i deleted from the Technical Specifications.

3. The changes proposed for Section 5.5 (new Section 5.2) are editorial for clarity and consistency with other specifications. They are consistent with draft NUREG-1625.

U. S. Nucle:r Regul tory Commission CY-99-041/ Attachment 3/Page 21 J. 6.0 ADMINISTRATIVE CONTROLS Due to the complexity of the changes and renumbering of Section 6.0, Table 3-1 is included at the end of this section, giving a comparison of the old and new sections of 6.0.

Chanoes

' J-1. Added subsections 6.1.2 and 6.1.3 relating to the approval of changes and the operational command function.

J-2. Subsection 6.2.1 has been retitled from "Onsite and Offsite Organization" to General Organizational Requirements" to reflect a reduction in reliance on offsite support during decommissioning.

Subsection 6.2.1.b has been revised to reflect the storage of fuel rather than the operation of the plant, in subsection 6.2.1.d, CERTIFIED FUEL HANDLER has been capitalized to reflect that this is a defined term. This editorial change has been made wherever appropriate throughout section 6.0. The reference to operating pressures was deleted and replaced with the performance of their assigned functions.

J-3. Subsection 6.2.2.d has been revised to make it applicable during the movement of loads over the spent fuel storage racks containing fuel.

Subsection 6.2.2.e, which was previously deleted, has been removed, and old subsection 6.2.2.f renumbered as new subsection 6.2.2.e. The reference to NRC Generic Letter 82-12 has been deleted.

Added new subsection 6.2.2.f to require the Shift Manager to be a CERTIFIED FUEL HANDLER.

The Shift Manager replaced the CERTIFIED FUEL HANDLER in Table 6.2-1, consistent with subsection 6.2.2.f. Editorial changes are also made to

. Table 6.2-1 for clarity and to correct the form of the word " crew's".

J-4. Editorial corrections have been made to subsection 6.3, including the deletion of the reference to subsection 6.3.1.2, which was previously deleted.

J-5. Subsection 6.4.1, delete the redundant last two sentences re the Unit Director and the training program. Clarify that the training program for CERTIFIED FUEL HANDLERS is NRC approved.

U. S. Nucbar Regulatory Commission CY-99-041/ Attachment 3/Page'22 J-6. Section 6.5, REVIEW AND AUDIT, is deleted and transferred to the CYQAP.

See Appendix F to Revision 2 of the CYQAP transmitted by CYAPCO letter CY-98-142 dated December 22,1998.

J-7. Section 6.8 PROCEDURES AND PROGRAMS is renumbered as new section 6.5.

Old subsection 6.8.1.a is modified to restrict it to the procedures of RG 1.33 that are applicable to the defueled condition.

Old subsection 6.8.1.b regarding the procedures for ANSI N18.7-1976 has been deleted and is incorporated as a commitment in Appendix C to the CYQAP.

New subsection 6.5.1.b is added to incorporate the programs of new section 6.6.

Old subsection 6.8.1.e regarding the REMODCM is deleted, as this is now covered in new subsection 6.6.3.

Old subsection 6.8.1.f regarding the PCP is deleted as this is now covered in new subsection 6.6.2.

Old subsection 6.8.1.g regarding the Spent Fuel Pool Mekeup and Monitoring Program is deleted and transferred to new subsection 6.6.6.

New subsection 6.5.1.e is added regarding procedures for operation of the RADWASTE TREATMENT SYSTEMS.

J-8. Section 6.6, REPORTABLE EVENT ACTION, is deleted entirely.

J-9. New section 6.6, PROGRAMS AND MANUALS, is added to incorporate the applicable programs of NUREG-1625, including:

Subsection 6.6.1, Radiation Protection Program, (relocated from old subsection 6.11.1);

. The initial word " Procedures..." has been changed to "A program..."

to maintain the intent of the specification.

Subsection 6.6.2, Process Control Program (PCP), (relocated from old subsection 6.8.1.f and expanded to include details from NUREG-1625);

Subsection 6.6.3, Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REMODCM), (relocated from old subsection 6.13, and incorporating old subsection 6.8.1.e);

U. S. Nucl=r Rrgulatory Commission CY-99-041/ Attachment 3/Page 23

. In the 2nd paragraph, delete "... consistent with the applicable LCOs contained in these Technical Specifications."

e in Item a, change " required by Specification 6.10.3.m." to " required by the Quality Assurance Program." I e deleted old subsection 6.13.b; ,

New subsection 6.6.4, Radioactive Effluent Controls Program retains the l pre-1994,10 CFR 20 limits.

New subsection 6.6.5, Radiological Environmental Monitoring Program; I Subsection 6.6.6, Spent Fuel Pool Cooling and Makeup Monitoring Program, relocated from old subsection 6.8.1.g, modified to include spent fuel pool chemistry; New subsection 6.6.7, Technical Specification (TS) Bases Control Program.

J-10. Old section 6.7, which was deleted by Amendment 192, has been removed.

J-11. Old section 6.8 has been renumbered as new section 6.5 as described above. Old subsections 6.8.4 and 6.8.5 have been deleted as redundant to-other provisions of the new section 6.5.

J-12. Old section 6.9, REPORTING REQUIREMENTS, has been relocated as new section 6.7, with the following changes:

Old subsection 6.9.1 regarding routine reporting requirements has been deleted. Subsections 6.9.1.1,6.9.1.2, and 6.9.1.3, which were deleted by Amendment 192, have been removed; ,

Old subsection 6.9.1.4, regarding submittal dates has been deleted and incorporated in specific subsections as appropriate; j Old subsection 6.9.1.5 has been renumbered as new subsection 6.7.1, OCCUPATIONAL RADIATION EXPOSURE REPORT, This subsection has been reworded to make it applicable to a decommissioning plant, and the submittal date changed for consistency; e For dosimeters, " pocket" has been changed to "self-reading";

Old subsection 6.9.1.6 has been renumbered as new subsection 6.7.2, expanded to include the details from NUREG-1625, and the submittal date  ;

change for consistency;  ;

1

l U. S. Nucirr Regulatory Commission CY-99-041/ Attachment 3/Page 24 ,

Old subsection 6.9.1.7 has been renumbered as new subsection 6.7.3, expanded to include the details from NUREG-1625, and the submittal date change for consistency; Old subsections 6.9.1.8 and 6.9.1.9, which were deleted by Amendment 192, have been removed; Additionally, changes have been made to Section 6.9 that are editorial, remove deleted portions, improve grammar, and reflect the defueled and shutdown condition of the plant.

J-13. 6.9.2, SPECIAL REPORTS, is deleted entirely. J J-14. 6.10, RECORD RETENTION, deleted and transferred to Appendix F to l Revision 2 of the CYQAP transmitted by CYAPCO letter CY-98-142 dated I December 22,1998.

J-15. 6.11, RADIATION PROTECTION PROGRAM, is renumbered as 6.6.1; see J-9 above.

J-16. 6.12, HIGH RADIATION AREA, is renumbered as 6.8.

J-17 6.13, RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE DOSE CALCULATION MANUAL (REMODCM), is transferred to subsection 6.6.3; see above.

J-18. 6.14, RADIOACTIVE WASTE TREATMENT, is renumbered as 6.5.1.e; see i above.

J-19. The section was repaginated and the page showing deleted Sections 6.15 i and 6.16 was removed. '

Reason and Basis 1 Subsections 6.1.2 and 6.1.3 have been added for consistency with NUREG-1431 and NUREG-1625.

2. The changes to subsection 6.2.1 are editorial, reflecting the defueled condition.

3. The changes to subsection 6.2.2 reflect the defueled condition, are for consistency with NUREG-1625, or are editorial.

4. The changes to subsection 6.3 are editorial format changes.

U. S. Nucle:r Regul: tory Commis: ion CY-99-041/ Attachment 3/Page 25

5. The portion marked for deletion in Section 6.4 references Section 5.5 of ANSI N18.1-1971 (from old Section 6.6). 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. The remaining requirements are consistent with NUREG-1625.

6. In accordance with the guidance in Administrative Letter 95-06,* section 6.5 is transferred to the CYOAP where it will be controlled by CYAPCO procedures. Any changes to the CYQAP require a review be conducted in accordance with the requirements of 10 CFR 50.54(a). See Appendix F to Revision 2 of the CYOAPS .

7. In accordance with the guidance of Administrative Letter 95-06m ANSI N18.7-1976 has been incorporated as a commitment in Appendix C of the CYQAP.* Other changes are editorial and for consistency with NUREG-1625,

8. Section 6.6 has been deleted entirely as subsection 6.6.1.a is a requirement of 10 CFR 50.73 and is thus required by regulation; and subsection 6.6.1.b, for PORC review of REPORTABLE EVENTS, is covered in the CYQAPS, Appendix F. This is consistent with NUREG-1431 and NUREG-1625.

9. Subsection 6.6.1 is unchanged from the old subsection 6.11.1, except:

. The initial word " Procedures..." has been changed to "A program..."

to maintain the intent of the specification. Under old section 6.11.1, the procedures did not require PORC and Unit Director approval.

Otherwise, relocating this specification to Section 6.6 would require all implementing procedures to be PORC and Unit Director approved, which is not the intent of this relocation.

Subsection 6.6.2 is expanded from the old subsection 6.8.1.f for consistency with NUREG-1625.

Subsection 6.6.3 is relocated from old subsection 6.13.b. The portion marked for deletion in old section 6.13.b is part of the PORC responsibilities being transferred to the CYOAPN per the guidance of NRC Administrative l

(9) CYAPCO letter CY-98-142 from R. A. Mellor to.the U. S. Nuclear Regulatory i Commission, " Proposed Revision 2 to the Quality Assurance Program," dated December 22,1998.

U. S. Nucle:r R:gul: tory Commission CY-99-041/Att:chment 3/Prgs 26 Letter 95-06W and can therefore be deleted from the Technical l Specifications.

New subsection 6.6.4 is adapted from NUREG-1431 and draft NUREG-1625 and formalizes the program presently contained in the REMODCM.

Subsection 6.6.4.b retains the reference to pre-199410 CFR 20.106. This is acceptable as the presently licensed 500 mrem per year limit for liquid ,

effluents provides assurance that the 10 CFR 50, Appendix I limits are not exceeded. Subsection 6.6.4.h uses the wording from NUREG-1431, as the i NUREG-1625 wording would duplicate that of subsection 6.6.1,1-131 not '

being considered due to decay of over 20 half-lives since shutdown.1-131 has also been removed from subsection 6.6.4.g.2.

New subsection 6.6.5 is adapted from NUREG-1431 and draft NUREG-1625 and formalizes the program presently contained in the REMODCM. ,

Subsection 6.6.6 is relocated from old subsection 6.8.1.g. A new requirement for spent fuel pool water chemistry has been added in place of the Spent Fuel Pool Water Chemistry Program of NUREG-1625.

New subsection 6.6.7 has been adapted from NUREG-1625, and formalizes the safety evaluation program currently used for Technical Specification bases changes.

10. The deletion of old subsection 6.7 is editorial.

1

11. The relocation of section 6.8 is described above and shown in Table 3-1 at the end of this Attachment. In summary: '

6.8.1 has become new subsection 6.5.1; 6.8.2 and 6.8.3 have been combined as new subsection 6.5.2; 6.8.4 and 6.8.5 have been deleted as their requirements are now covered by new section 6.5. Specifically 6.5 and 6.5.1.b require written procedures for the programs of Specification 6.6, which includes the previously covered programs; and 6.5.2 covers the review of these procedures and temporary changes thereto.

12. The reporting requirements of old section 6.9.1 are covered by the regulations in 10 CFR 50.4.

6.9.1.4 and 6.9.1.5 have been merged into new 6.7.1 and reworded for consistency with draft NUREG-1625.

6.9.1.6 is now covered in the expanded description in 6.7.2 per draft NUREG-1625.

U. S. Nucle:r Regulitory Commission ,

CY-99-041/ Attachment 3/Page 27 j

6.9.1.7 is now included in the expanded description in 6.7.3 per draft NUREG-1625. l The submittal dates for all reports required by new section 6.8 have been q

established as May 1, for consistency.

j

13. The requirements of the old section 6.9.2 are covered in 10 CFR 50.4. Any specifications, or relocated specifications, requiring special reports will refer to 10 CFR 50.4. The requirements for special reports will be transferred with 3 the relocated specifications 3.3.3.4, 3.11.1.2, 3.11.2.2, 3.11.2.3, and 3.11.3; I to the TRM for Specification 3.3.3.4, and to the REMODCM for the others.

14. In accordance with the guidance in Administrative Letter 95-06") section 6.10, Records Retention, is transferred to the CYQAP where it will be controlled by CYAPCO procedures. Any changes to the CYQAP require a '

review be conducted in accordance with the requirements of '

10 CFR 50.54(a). See Appendix F to Revision 2 of the CYQAPS) This is.

consistent with NUREG-1625. The implementation of License Amendment 1920 ) also 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.

15. Editorial and for consistency with draft NUREG-1625.

16. Editorial and for consistency with draft NUREG-1625.

17. Editorial and for consistency with draft NUREG-1625.

18. Editorial and for consistency with draft NUREG-1625.

19. Editorial, i

i

)

A 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. i l

U. S. Nucle r Regulitory Commission -

CY-99-041/ Attachment 3/Page 28 Table 3-1 Comparison of the Old and New Sections of 6.0 Old New Subject / Comment Section Section 6.1.1 6.1.1 Vice President 6.1.2 Unit Director - new

- 8.1.3 Shift Manager - new 6.2.1 6.2.1 General Organizational Requirements (formerly Onsite and Offsite Organization) 6.2.2 6.2.2 Facility Staff 6.2.2.f SM shall be a CFH - new 6.3.1 6.3.1 Facility Staff Qualifications 6.3.1.1 6.3.1.1 HP Manager 6.3.1.2 --

" DELETED" by Amendment 192 6.4 6.4.1 Training -

6.5.1 -

Relocated entire section on PORC to CYQAP 6.5.2 --

Relocated entire section on NSAB to CYQAP 6,6 -

Reportable Event Action - Deleted entire section as covered by 10 CFR 50 6.7 -

" DELETED" by Amendment 192 6.8.1.a 6.5.1.a Procedures and Programs - RG 1.33 6.8.1.b --

ANSI 18.7-1976 is being deleted.

6.8.1.c 6.5.1.c Fire Protection Program implementing procedures 6.8.1.d 6.5.1.d Effluent Monitoring procedures 6.8.1.e 6.5.1.b REMODCM implementing procedures 6.8.1.f 6.5.1.b Process Control Program procedures - See also new section 6.6.2 6.8.1.g 6.6.6 Spent Fuel Pool Cooling and Makeup Monitoring Program 6.5.1.e Radwaste Treatment System implementing procedures - new 6.8.2 6.5.2 - Review and approval of procedures (of 6.5.1) '

6.8.3 6.5.3 Temporary changes to procedures 6.8.4 6.5.1.b Radiological Environmental Monitoring Procedures - 1 REMODCM Section I.E  :

6.8.5 6.5.2 Approval of changes to the REM procedures  !

6.9.1- --

Routine Reporting Requirements - deleted as covered by 10 i CFR 50 6.9.1.4 Submittal date for annual reports - deleted & incorporated in new 6.7.1 6.9.1.5 6.7 1 Occupational Radiation Exposure Report 6.9.1.6 6.7.2 Annual Radiological Environmental Operating Report 6.9.1.7 6.7.3 Annual Radiological Effluent F.elease Report 6.9.1.8 -

" DELETED" by Amendment 192 i

U. S. Nuclerr Regulatory Commission CY-99-041/ Attachment 3/Page 29 Old New Subject / Comment Section Section 6.9.1.9 -

" DELETED" by Amendment 192 6.9.2 -

Special Reports - Deleted as covered by 10 CFR 50 or transferred to TRM 6.10 -

Record Retention - Relocated to CYQAP 6.11.1 6.6.1 Radiation Protection Program 6.6.2 Former section 6.8.1.f expanded

- 6.6.4 Radioactive Effluent Control Program - new 6.6.5 Radiological Environmental Monitoring Program - new 6.12.1. 6.8.1 High Radiation Area 6.12.2 6.8.2 High Radiation Area Controls 6.8.3 6.13 6.6.3 REMODCM 6.14 6.5.1.e Radioactive Waste Treatment 6.15 -

" DELETED" by Amendment 192 6.16 -

" DELETED" by Amendment 192

Docket No. 50-213 CY-99-041 Attachment 4 Haddam Neck Plant l

1 l

June 1999 {

i

t I

U.S. Nuclzr Regul tory Commission CY-99-041/ Attachment 4/Page 1 Haddam Neck Plant

)

Proposed Revision To The Operating License And The Technical Specifications i Safety Assessment And No Significant Hazards Consideration Descriotion of Amendment Requent The proposed amendment would complete the modification of the Operating License and Technical Specifications to support decommissioning of the Haddam Neck Plant (HNP). It would do this by modifying the following:

1 A. Changing the License expiration date to reflect the fact that the plant has I permanently ceased operation and is being decommissioned.

B. Removing obsolete License Condition 3.C.(6), relating to the Integrated Implementation Schedule Program Plan, which has expired. i l

C. Revising the Index to support the proposed changes in this letter. I D. Revising the Definitions to remove Definitions that are no longer used, and adding a new Definition for CERTIFIED FUEL HANDLER.

E. Relocating the remaining instrumentation specifications of Section 3/4.3 and their associated bases by transferring LCO 3.3.3.4, Meteorological Monitoring Instrumentation, to the TRM per GL 95-10, and LCOs 3.3.3.7, Radioactive Liquid I

Effluent Monitoring Instrumentation, and 3.3.3.8. Radioactive Gaseous Effluent Monitoring Instrumentation, to the REMODCM per GL 89-01.

4 F. Relocating the remaining Plant Systems specification of Section 3/4.7 by transferring LCO 3.7.5, Sealed Source Contamination, and its associated basis to the TRM, consistent with NUREG-1431 and draft NUREG-1625.

G-1. Removing the following specifications and their associated bases from Section 3/4.9, which are no longer required for a defueled and decommissioning plant:

. 3.9.1, Boron Concentration

. 3.9.2, Instrumentation

. 3.9.3, Decay Time e 3.9.4, Containment Building Penetrations

. 3.9.5, Communications e 3.9.6, Manipulator Crane

. 3.9.8, Residual Heat Removal And Coolant Circulation

. 3.9.9, Containment Purge Supply, Purge Exhaust, And Purge Exhaust Bypass isolation System

. 3.9.10, Water Level - Reactor Vessel

. 3.9.12, Fuel Storage Building Air Cleanup System

. 3.9.15, Spent Fuel Pool Cooling

r U.S. Nuclxr R::gulitory Commission CY-99-041/ Attachment 4/Page 2 G-2. Making editorial modifications to the remainder of section 3/4.9 to suit them to their decommissioning role, eliminating unnecessary pages, and repaginating. The following LCOs and their associated bases will remain:

. 3.9.7, Crane Travel- Spent Fuel Storage Building

. 3.9.11, Water Level - Storage Pool

. 3.9.13, Movement Of Fuel in Spent Fuel Pool

. 3.9.14, Spent Fuel Pool--Reactivity Condition

. 3.9.16, Spent Fuel Pool Cooling - Defueled l

G-3. Making minor technical changes to LCOs 3.9.7,3.9.11 and 3.9.13 and their )

associated bases to clarify information.

H. Relocating the remaining specifications of section 3/4.11 by transferring the following LCOs and their associated bases to the REMOCDM per GL 89-01:

4

. 3/4.11.1.1, Liquid Effluents - Concentration

. 3/4.11.1.2, Liquid Effluents - Dose, Liquids e 3/4.11.2.1, Gaseous Effluents - Dose Rate

. 3/4.11.2.2, Gaseous Effluents - Dose-Noble Gases e 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

1. Section 5.0, Design Features, is revised by replacing specifications 5.1 and 5.5 with a narrative description of the site, renumbering specification 5.6 to 5.2, and repaginating to eliminate unnecessary material.

J-1. Section 6.1 is revised by adding two new subsections,6.1.2 and 6.1.3. to reflect site-specific responsibilities, consistent with draft NUREG-1625.

J-2. Section 6.2.1 has been revised to reflect the storage of fuel rather than operation of the plant, consistent with draft NUREG-1625.

J-3. Section 6.2.2 has been revised to reflect the present staff requirements, consistent with draft NUREG-1625.

J-4. Section 6.3 has been revised editorially, consistent with draft NUREG-1625.

J 5. Section 6.4.1 has been revised to delete information which is no longer applicable, consistent with draft NUREG-1625.

U.S. Nucber Regul tory Commission CY-99-041/ Attachment 4/Page 3 J-6. Section 6.0, Administrative Controls, is revised to incorporate the recommendations 1 of AL 95-01 by relocating specifications 6.5, Review and Audit, and 6.10, Reporting  ;

Requirements, to the CYOAP. (See also J.14) 1 J-7. Section 6.8, Procedures and Programs, is renumbered as Se :+ ion 6.5 and is revised consistent with draft NUREG-1625 to reflect the defuead and decommissioning condition.

J-8. Section 6.0, Administrative Controls, is revised consistent with NUREG-1431 and draft NUREG-1625 by deleting specifications 6.6, Reportable Event Action, and l 6.9.1 Routine Reporting Requirements, to eliminate requirements covered by i Regulations, i.e.,10 CFR 50.73 and 10 CFR 50.4, respectively. (See also J-12) l J-9. Section 6.6, Programs and Manuals, is added to incorporate the applicable programs of draft NUREG-1625, including:

l

. Subsection 6.6.1, Radiation Protection Program, (relocated from old subsection I 6.11.1);

. Subsection 6.6.2, Process Control Program (PCP), (relocated from old subsection 6.8.1.f and expanded to include details from draft NUREG-1625);

. Subsection 6.6.3, Radiological Effluent Monitoring and Offsite Dose Calculation  !

Manual (REMODCM) retains the reference to pre-199410 CFR 20.106 (relocated from old subsection 6.13, and inccrporating new old subsection 6.8.1.e);

. New subsection 6.6.4, Radioactive Effluent Controls Program provides for liquid effluent using the pre-1994 limits cf 10 CFR 20.106;

. New subsection 6.6.5, Radiological Environmental Monitoring Program;

. Subsection 6.6.6, Spent Fuel Pool Cooling and Makeup Monitoring Program, relocated from old subsection 6.8.1.g, modified to include spent fuel pool chemistry);  ;

. New subsection 6.6.7, Technical Specification (TS) Bases Control Program.

J-10. The removal of reference to a previously deleted subsection 6.7.

J-11. See J-7 above for the relocation of old section 6.8 as new section 6.5.

J-12. Section 6.0, Administrative Controls, is revised consistent with NUREG-1431 and draft NUREG-1625 by deleting specifications 6.6, Reportable Event Action, and 6.9.1 Routine Reporting Requirements, to eliminate requirements covered by Regulations, i.e.,10 CFR 50.73 and 10 CFR 50.4, respectively. (See also J-8)

J-13. Specification 6.9.2, Special Reports, is deleted as the specifications referring to it have all been relocated out of the Technical Specifications or deleted, and its remaining information is covered by 10 CFR 50.4.

g  ;

U.S. Nuclehr Regulttory Commission

CY-99-041/ Attachment 4/Page 4 l

. J-14. Section 6.0, Administiative Controls, is revised to incorporate the recommendations 1 of AL 95-01 by relocating specifications 6.5, Review and Audit, and 6.10, Reporting i Requirements, to the CYQAP. (See also J.6)

J-15. See J-9 above for the relocation of section 6.11, Radiation Protection Program, as new section 6.6.1.

J-16. Section 6.12, High Radiation Area, is renumbered as 6.8, and contains editorial changes for clarity and consistancy with draft NUREG-1625; J-17. See J-9 for the relocation of section 6.13, REMODCM, as new section 6.6.3.

J-18. See J-7 for the relocation of section 6.14, Radioactive Waste treatment as new

. section 6.5.1.

J-19. Section 6.0 was repaginated and deleted sections removed.

K. To reduce the amount of unnecessary material, sections which are no longer i applicable have been eliminated and their tabs removed. This includes the following:

e 2.0, Safety Limits and Limiting Safety System Settings o 3/4.1, Reactivity Control Systems e 3/4.2, Power Distribution Limits e 3/4/3, Instrumentation

. 3/4.4, Reactor Coolant System ,

e 3/4.5, Emergency Core Cooling Sys,tems 1 e 3/4.6, Containment Systems e 3/4.7, Plant Systems i e 3/4.8, Electrical Power Systems u

. 3/4.10, Special Test Exceptions e 3/4.11, Radioactive Effluents Safety Assessment The proposed change to the Haddam Neck Plant Operating License and Technical Specifications has been evaluated against the standards of 10 CFR 50.92 and has been determined not to involve a significant hazards consideration and to be safe. The following discussion demonstrates that the proposed changes are safe considering the changed configuration of the plant.

l The proposed changes are similar to those previously approved by the NRC Staff for l Maine Yankee and Big Rock Point. These have been reviewed and fcund to be safe. )

l I

U.S. Nucirr Regul: tory Commission CY-09-041/ Attachment 4/Page 5 Summarv The plant has permanently ceased operations, the reactor has been permanently defueled, and the spent fuel is stored in the spent fuel pool.

The Operating License and Technical Specification requirements that are proposed to be removed deal with structures, systems, components, programs and/or administrative controls that the NRC has found suitable for relocation to other means of control. In addition, the editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. None of these changes affect plant configuration nor do they affect plant operations. Therefore, the changes do not affect the safety of the plant.

The plant was shutdown on July 22,1996 and more than 1,000 days have passed since the shutdown, thus the heat load on the spent fuel pool cooling system is greatly reduced.

Present cooling performance data as well as calculations demonstrate that either the plate I or the shell and tube heat exchanger has more than adequate heat removal capacity. In the event of a loss of forced coo!ing, calculations indicate that the spent fuel pool time to boil is greater than 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> based on an initial pool temperature of 150 *F. The initial pool temperature of 150 *F is based on Technical Specification 3/4.9.16 which has a pool temperature limit of 150 *F. Even during boi!ing, the fuel is adequately cooled. Once boiling commences, the operators have in excess of 18 days to provide forced cooling and/or makeup before there is inadequate shielding provided by the water ln the pool.

This allows sufficient time to provide alternate forced cooling or makeup to the spent fuel pool for a cooling water system failure. Therefore, operability of spent fuel pool cooling does not require electrical power or makeup water to be immediately available.

1 Should failure to restore operation of the spent fuel pool cooling system occur before boiling takes place, cooling of the spent fuel can be accomplished by allowing the spent fuel pool to boil and adding makeup water at a rate equal to or greater than the boil-off rate.

CYAPCO has in place procedures to estau:sh onsite power in the event of a Loss of Normal Power (LNP) and in the event of a loss of cooling to the Spent Fuel Pool. For a LNP, power can be made available within approximately one hour. If onsite powar cannot be reestablished, due to equipment failure, at approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> into the LNP, limited makeup water could be provided from a tank and portable pump, or an unlimited supply of water could be provided via the diesel fire pump from the Connecticut River (available in approximately 30 minutes). Therefore, within approximately 2 % hours of the event start, cooling and/or makeup would be reestablished to the spent fuel pool. Historically, the longest LNP the HNP has experienced has been less than 30 minutes With the decommissioning of the HNP, the sources of offsite power supply have been reduced.

However, the most probabie initiating event, turbine trip, has been eliminated. Therefore, the probability of an extended loss of offsite power remains low.

I _

=

U.S. Nucle:r R:gult. tory Commission CY-99-041/ Attachment 4/Page 6 The plant was Wutdown on July 22,1996. Except for 1-125 (half-life ~59.5 days), .-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 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 inventory in the spent fuel. 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 diep accident dose calculations which conclude that doses (i.e., whole body and thyroid) at the Exclusion Area Boundary are a small fraction of the 10 CFR 100 dose limits and the EPA PAGs. RG 1.25,

" Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25)," requires only the gas gap activity be considered, and does not predict any particulate releases.

Therefore, the changes to this group of Technical Specifications do not diminish the level

'of protection of the public health and safety.

• Soecific Chanaes A. License Expiration Date The change in wording replacing the license expiration date with the wording from a portion of 10 CFR 50.51(b). This change reflects the regulatory requirements for a facility that has permanently ceased operations. As such, it more accurately reflects the requirements for termination of the license. This change has no effect on the systems, structures or components of the HNP, and is safe.

B. Mcense Condition 3.Cf6)

This license condition expired on February 23,1998, its removalis an editorial change as it is no longer in effect. This change has no effect on the systems, structures or components of the HNP, and is safe.

C. Index The revision of the Index to support the changes to other sections is editorial in nature and contributes to the clarity and usability of the manual. This change has no effect on the systems, structures or components of the HNP, and is safe.

U.S. Nucle:r Regu!ctory Commission CY-99-041/ Attachment 4/Page 7 D. - Definitions

' The removal of definitions that are no longer used in the technical specifications is editorial in nature, and contributes to the clarity and usability of the manual. Evaluation of the '

deletion of the requirements that used the definition adequately address their deletion.

Addition of the definition of CERTIFIED FUEL HANDLER clarifies the intention of License  !

Amendment 192. This change has no effect on the systems, structures or components of the HNP, and is safe.

E. Relocation of Instrumentation Soecifications The relocation of the remaining LCOs and surveillances is being done in accordance with NRC guidance. These are specifications that even during power operation did not meet the criteria of 10 CFR 50.36 for inclusion as a technical specification. After relocation, changes to this material will be controlled under the 10 CFR 50.59 process.

LCO 3.3.3.4, Meteorological Monitoring Instrumentation, which is being relocated to the TRM per GL 95-10, covers instrumentation that is used after an event occurs, to monitor and evaluate the impact of the event. As this instrumentation acts neither to prevent nor mitigate a design basis event, and no events have a significant offsite impact, controlling -

this instrumentation via the TRM is safe.

LCOs 3.3.3.7, Radioactive Liquid Effluent Monitoring Instrumentation, and 3.3.3.8.

Radioactive Gaseous Effluent Monitoring Instrumentation, which is being relocated to the REMODCM per GL 89-01, monitor normal releases to the environs. As these instruments act neither to prevent nor mitigate a design basis event this change is safe. i F. Relocation of Sealed Source Contamination Specification LCO 3.7.5, Sealed Source Contamination is being relocated to the TRM consistent with NUREG-1431 and draft NUREG-1625. This specification does not meet the criteria cf 10 CFR 50.36 for inclusion as a technical specification, and bears no relation to the l conditions and limitations which are necessary to ensure the safe storage of spent fuel.

After relocation, changes to this material will be controlled under the 10 CFR 50.59 process.

G-1. Specifications Removed from Section 3/4.9 These are specifications which are related to operations within containment while fuel was still in the reactor vessel, or that are related to the storage of spent fuel recently removed from the reactor vessel. As all fuel has been placed in the spent fuel pool, and has decayed for a significant period of time, these specifications are no longer applicable.

Thus these changes are safe.

U.S. Nucle:r Regul: tory Commission CY-99-041/ Attachment 4/Page 8 Previously, the fuel storage building air cleanup system of LCO 3.9.12 was uti!ized to rernove iodine via the charcoal filters, thus mitigating the consequences of a fuel handling accident. As the spent fuel has decayed to the extent that there is no longer any appreciable iodine activity to be released should a fuel handling event occur, there is no longer any need for filtration to mitigate such an event. The only remaining use of this system is normal ventilation of the spent fuel building, which is not a safety-related function. Therefore the removal of this specification is safe.

LCO 3.9.15 was replaced by LCO 3.9.16 in Amendment 193 but inadvertently was included in our' submittal of May 30,1998, and thus was reissued in the package issued as Amendment 193. Its deletion was approved in the Staff's Safety Evaluation of March 27, 1998 for Amendment 193.

G-2. Editorial Chanaes for Section 3/4.9 The editorial changes associated with repaginating the remaining specifications of Section 3/4.9, changes words to symbols, and changing nomenclature are being proposed for 4 clarity and ease of use of these specifications, as well as for consistency of nomenclature.

These changes have no effect on the systems, structures or components of the HNP, and are safe.

G-3. Technical Chanaes to Specifications in Section 3/4.9 Specification 3/4.9.7 is revised to increase the maximum load to be transported over the fuel pool due to the movement of a fuel bundle. This is less than the analyzed load for the drop of a bundle which has been previously submitted and approved. Thus this change is I safe. The bases has been revised to reference the calculation for the fuel handling accident.

Specification 3/4.9.11 is revised to more accurately reflect the manner in which the amount of water covering the spent fuel stored in the spent fuel pool is surveilled. it is sufficient for the operator to confirm that the water level is maintained, rather than to confirm that a particular depth of water is maintained. This reflects that the depth of water i is maintained procedurally by maintaining the appropriate level of the spent fuel pool.

Specification 3/4.9.13 is clarified to specify that the surveillance is only applicable when the LCO is applicable, lu, during fuel movement. l H. Relocation of Specifications in Section 3/4.11 j

The specifications for Radioactive Liquid Effluent Monitoring and Radioactive Gaseous Effluent Monitoring, which are being relocated to the REMODCM per GL 89-01, control normal releases to the environs. As these neither prevent nor mitigate a design basis event this change is safe. After relocation, changes to this material will be controlled under the 10 CFR 50.59 process. l

U.S. Nucle r Regulatory Commission CY-99-041/ Attachment 4/Page 9

1. Desian Features 1 The replacement of the site drawings in Section 5.1 with a narrative description of the site conforms with NUREG-1431 and draft NUREG-1625. As the figures are maintained in the UFSAR, the change eliminates the duplication of material which does not affect the safe ,

storage of nuclear fuel. The replacement of a pictorial representation by a narrative '

description of the site has no effect on the materials of construction or geometrical arrangement of the site which, if altered or modified, would have a significant effect on safety, and thus is safe.

Section 5.5 and Figure 5.1-1 describes the location of the meteorological tower. With the relocation of the meteorologicalinstrumentation of Specification 3.3.3.8, to the TRM per GL 95-10, this is no longer needed in the technical specifications. As this instrumerdstion acts neither to prevent nor mitigate a design tiasis event, and no events have a significant offsite impact, maintaining the location of the meteorological tower in the UFSAR is safe.

The renumbering of Section 5.6 as Section 5.2 is an editorial change which promotes clarity and reduces the volume of pages with no meaningful material, and thus is safe.

J-1. Responsibility - Specification 6.1 The addition of two new subsections to Specification 6.1 is consistent with NUREG-1431 and draft NUREG-1625. This change adds requirements formalizing the existing functions of the Unit Director and Shift Manager. The Unit Director and Shift Manager are the positions in the direct line of command responsible for the safe storage of the spent fuel.

As this formalization of existing functions does not change the operation of the unit, the change is safe.

J-2. Oraanization - Specification 6.2.1 The changes to Specification 6.2.1 are editorial reflecting the fact that CYAPCO has separated from Northeast Utilities, who was the holding company of the HNP when it was generating power. Editorial changes consistent with the draft NUREG-1625 also reflect the change from an operating unit to the safe storage of the spent fuel. As these changes reflect the current status of the unit, which has been previously approved, they are safe.

J-3. Facility Staff - Specification 6.2.2 ,

1 Specification 6.2.2.d formalizes existing practice by an additional restriction relating to the movement of loads over spent fuel, consistent with draft NUREG-1625. Renumbered  ;

Specification 6.2.2.e has deleted the reference to the NRC Policy Statement on working  :

hours (GL 82-12), consistent with the draft NUREG-1625. This is acceptable as the l guidance of GL 82-12 applies to plant staff working hours during operations, and HNP is no longer an operating plant. Staff working hours are still covered by procedure, requiring a management approval to exceed normal working hours. The requirement for the Shift I

)

U.S. Nuclear R:gulatory Commission CY-99-041/ Attachment 4/Page 10 Manager to be a CERTIFIED FUEL HANDLER has been formalized as the new Specification 6.2.2.f, consistent with the draft NUREG-1625. Editorial changes for clarity and to correct English have been made to this Specification and the accompanying Table 6.2-1. These changes have been evaluated and found to be safe.

J-4. Editorial changes made to Section 6.3 are for clarity and consistency. These changes have been evaluated and found to be safe.

J-5. The changes to Section 6.4 are for consistency with draft NUREG-1625. As the provisions being deleted are covered by the commitment to Regulatory Guide 1.8,

" Personnel Selection and Training," which endorses ANOI N-18-1-1971, which is contained in Appendix C to the CYQAP. Thus the commitment to standards for training are now contained in the CYQAP. Commitments contained in the CYQAP cannot be reduced without an NRC approved safety evaluation report (SER), although other changes are only required to be submitted on an annual basis in accordance with 10 CFR 50.54(a).

Therefore, this change is safe.

J-6. The old Section 6.5, " Review and Audit," has been transferred to Appendix F of the CYQAP consistent with the guidance of AL 95-06, and draft NUREG-1625. Thus the requirements for review and audit are now contained in the CYQAP. Commitments contained in the CYQAP cannot be reduced without an NRC approved safety evaluation report (SER), although other changes are only required to be submitted on an annual basis in accordance with 10 CFR 50.54(a). Therefore, this change is safe.

J-7. The new Section 6.5 has been modified to restrict the procedures included to those applicable to the safe storage of the spent fuel. This is appropriate as the plant is permanently shutdown with fuel removed from the reactor and stored in the spent fuel pool. The elimination of the reference to ANSI N18.7- 1976, " Administrative Controls and Quality Assurance Requirements for the Operational Phase of Nuclear Power Plants,"is appropriate as this standard is applicable to the operational phase activities of a plant.

Consistent with the relocation of PORC and NSAB to the CYQAP, the requirement for PORC review of procedure changes has been replaced by a requirement for independent review of procedure changes. This independent review may be by either PORC or an individual independent reviewer, and is controlled by Section 5.2.1 of the CYQAP. The substitution of an independent reviewer for review by the PORC maintains a high level of assurance that procedure revisions will be done safely and will not adversely affect plant operations. This change allows the PORC to concentrate on those aspects of operation that are more important to safety, that is, on the safe storage of spent fuel.

The provision to allow the Unit Director to designate an alternate for approval of procedures is consistent with draft NUREG-1625 and industry practice, and provides flexibility in the performance of this administrative activity. The allowance in Specifications 6.5.2 and 6.5.3 of a designee to approve procedures in lieu of the Unit Director ensures

U.S. Nucle r Regul: tory Commission CY-99 041/ Attachment 4/Page 11 that procedure changes have an additionallevel of review above that of the independent reviewer, and provides for those occasions when the Unit Director may not be available.

Inclusion of all the programs of Section 6.6, ensures that implementing procedures for programs important to the safe storage of the fuel are covered by the mandated reviews.

Thus these proposed changes have been reviewed and found to be safe.

J-8. The deletion of old Section 6.6 is safe because the requirements for reportable events are covered by the regulations of 10 CFR 50.72 and 10 CFR 50.73.

J-9. The new Section 6.6 consolidates programs from several old sections and adds new program requirements for a Radiological Environmental Monitoring Program and a Technical Specification Bases Control Program. Also spent fuel chemistry requirements are formalized as part of the Spent Fuel Pool Cooling and Makeup Monitoring Program.

The new programs are a formalization of requirements which are presently administratively controlled at HNP. As these changes constitute a formalization of existing programs, this change is safe.

J-10. The change to remove reference to previously deleted Section 6.7 is an editorial change for consistency and clarity. Its removal makes the resultant package of specifications more user friendly, and it has been reviewed and found to be safe.

J-11. The renumbering of old Section 6.8 as new Section 6.5 is discussed under J-5 above. The replacement of old subsections 6.8.4 and 6.8.5 by new subsection 6.6.5 is an editorial change for consistency with draft NUREG-1625. These changes have been reviewed and found to be safe. ,

J-12. The changes to new Section 6.9, Reporting Requirements, removes requirements i which are covered by the regulations in 10 CFR 50.4; changes the functions to be covered from operating to decommissioning ones; establishes a consistent submission date of May j 1 for annual reports; and makes editorial changes for clarity and ease of use. These j changes are consistent with draft NUREG-1625. As the three reports required by this section have not changed, these administrative changes have been reviewed and found to be safe.

J-13. Old Section 6.9.2, Special Reports, has been deleted. As all Specifications requiring special reports are being removed by this proposed license amendment, this change is safe.

J-14. Old Section 6.10, Record Retention, has been deleted consistent with draft NUREG-1625. As this requirement is now contained in Appendix F to the CYOAP this change is safe.

J-15. The renumbering of old Section 6.11, Radiation Protection Program, as new Section 6.6.1 is a purely editorial change for clarity and ease of use, and is safe.

q l

U.S. Nucle:r Regul: tory Commission CY-99-041/ Attachment 4/Page 12 l

J-16. The renumbering of old Section 6.12, High Radiation Area, as new Section 6.8 is a purely editorial change for clarity and ease of use. Other editorial changes have been made for clarity, ease of use, and consistency with draft NUREG-1625. The terminology

" shift supervisor" has been corrected to " Shift Manager". These changes have been reviewed and found to be safe.

i J-17. The relocation of old section 6.13, REMODCM, to new Section 6.6.3 is covered 4 under item J-9 above, and is safe.  ;

J-18. The relocation of old section 6.14, Radioactive Waste Treatment, to new Section 6.5.1.e is an editorial change for consistency with draft NUREG-1625, and is safe. I J-19. The repagination and removal of reference to deleted sections is editorial for clarity and ease of use, and is sah.

l i

Sianificant Hazards Consideratiort CYAPCO has reviewed the proposed changes to the Operating License and the Technical Specifications in accordance with 10 CFR 50.92 and concluded that the changes do not involve a significant hazards consideration (SHC). The basis for this conclusion is that the three criteria of 10 CFR 50.92(c) are not compromised. An evaluation against these standards is provided below as first a summary against the overall change, and also against each of the specific proposed changes.

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. \

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. The following events are presently considered as bounding of all other events:

. Fuel handling and cask drop accidents in the spent fuel building,

. Criticality in the spent fuel pool,

. Loss of spent fuel cooling,

. Resin fire (gaseous release), and

. Rupture of a tank containing radioactive liquid.

There is no significant increase in the probability of a fuel handling accident since refueling operations have ceased, with a corresponding decrease in the frequency of fuel movement. The radiological consequences of a fuel handling accident,

1 I

U.S. Nucir:r R:gul: tory Commission CY-99-041/ Attachment 4/Page 13 i

should one occur, decrease the longer the spent fuelis allowed to decay. As I discussed previously. the spent fuelinventory of radioactive iodine and noble gases {

have decayed more than 20 blf-lives since shutdown and are no longer a release l concern. With this reduced source the results of the fuel handling accident show j that the filters of Specification 3.9.12 are no longer necessary. The allowed weight over the spent fuel peol is still less than that previously approved. Therefore, there has been no increase in the probability or consequences of a fuel handling or cask j drop accident. )

Criticality controls are imposed by specifications 3/4.9.13 and 3/4.9.14. There has  :

been no technical changes to these specifications. Therefore, there has been no l increase in the probability or cc,nsequences of a criticality event.

Spent fuel cooling is maintained by keeping the pool temperature below 150 *F.

Should normal cooling be lost, the availability of an abundant supply of water ensures that sufficient time is available prior to boiling to restore cooling. This is controlled by specifications 3/4.9.11 and 3/4.9.16. There has been no technical changes to these specifications. Therefore, there has been no increase in the probability or consequences of a loss of cooling event. The elimination of I specification 3/4.9.15 was previously approved in Amendment 193, which replaced I it with specification 3/4.9.16, and it's removal is being implemented with this change.

The probability of a gaseous or liquid radioactive release is not changed by the proposed revisions. As the plant undergoes decommissioning, the previous limiting events are no longer applicable, and previous non-limiting events now become limiting. These new events have not changed from how they might have occurred in the past. 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 processing of resin from the reactor coolant system ,

decontamination. The rupture of a tank containing radioactive liquid was assessed and found to be bounded by these events. 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 changes to conform to Section 6.0 to draft NUREG-1625 are of an administrative nature, and have been reviewed and found to be safe.

A. This is an administrative change to the operating license to reflect the fact that the Haddam Neck Plant has permanently ceased operation, that fuel has permanently been removed from the reactor, and that the plant is undergoing decommissioning. This change removes the possibility of those reactor-related events which were applicable while the plant was operating.

I U.S. NucleIr Regulatory Commission CY-99-041/ Attachment 4/Page 14 It is a purely administrative change which does not authorize any new activities at the plant site, but rather restricts the activities which may occur there to a subset of those activities previously considered. Thus the change does not increase the probability of an event previous!y considered, nor does it increase the consequences of such an event should it occur.

Changes B, C, G-2, J 4, J-10, J-11, J-13, J-15, J-16, J-17, J-18, J-19, and K The editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. None of these changes affect plant configuration nor do they affect plant operations. Therefore, these I editorial changes have no effect on the probability or consequences of an accident previously evaluated.

D. This is an administrative change to the Definitions that has no effect on the i physical plant, and does not change the way the plant is operated.

Evaluation of the deletion of the requirements that used the definition adequately address their deletion. Therefore, the revisions to the definitions cannot increase the probability or consequences of any accident previously evaluated. 1 l

E. The meteorological monitoring and radioactive effluent monitoring )

instrumentation are used for information gathering and monitoring the course ,

of an event should one occur. This instrumentation does not interect with any other plant equipment such that it could cause an event should it fail. l This instrumentation does not actuate any equipment in response to an event, and is not used to terminate or mitigate an event should one occur.

Therefore, the relocation of the requirements for this instrumentation from the technical specifications to the TRM and REMODCM cannot increase the probability or consequences of any accident previously evaluated.

F. The surveillance for sealed source contamination ensure that the sources used for calibration of radiation monitoring equipment remain intact.

Sources, and the equipment they are used to calibrate, do not have any interaction with any other plant equipment such that they could cause an event. The sources and this instrumentation do not actuate any equipment in response to an event, and are not used to terminate or mitigate an event should one occur. Therefore, the relocation of the requirements for the surveillance for sealed source contamination from the technical specifications to the TRM cannot increase the probability or consequences of any accident previously evaluated.

G-1. There is no change in how the spent fuel is stored or moved in the spent fuel pool. The specifications which were related to operations with fuel in the reactor vessel no longer have any applicability as all fuel has been removec

U.S. Nucber Regul:. tory Commission CY-99-041/ Attachment 4/Pags 15 from containment, and fuel is prohibited from beir,g returned inside containment. Of the specifications proposed to be deleted from Section 3/

4.9, only LCOs 3.9.12 and 3.9.15 relate to operations in the spent fuel building.

Previously, the fuel storage building air cleanup system of LCO 3.9.12 was utilized to remove iodine via the charcoal filters, thus mitigating the consequences of a fuel handling accident. As the spent fuel has decayed to the extent that there is no longer any appreciable activity to be released should a fuel handling event occur, there is no longer any need for filtration to mitigate such an event.

The deletion of LCO 3.9.15 is an editorial change to implement what was previously approved in Amendment 193. The reactor was permanently shutdown on July 22,1996 and more than 1,000 days have passed since the shutdown, resulting in a greatly reduced heat load. Thus maintaining the spent fuel pool temperature below 150 F, as is done by LCO 3.9.16, is sufficient to provide time for compensatory actions should a loss of normal cooling occur.

Therefore, the deletion of these specifications cannot increase the probability or consequences of any accident previously evaluated.

G-3. For LCO 3.9.7, the increase in the allowable load permitted to be moved over the spent fuel assemblies, from 1650 pounds to 1800 pounds maintains the load less than that previously evaluated.

For LCO 3.9.11, the change in the description of the parameter surveilled does not change the way the plant is operated, nor does it affect the way the fuelis stored or moved.

For LCO 3.9.13, the clarification of the frequency of the surveillance does not change the way the plant is operated, nor does it affect the way the fuel is  !

stored or moved. '

Therefore, the changes to these specifications cannot increase the probability or consequences of any accident previously evaluated.

H. The radioactive effluent monitoring specifications impose limits on releases l during the normal operation of the plant. These specifications are primarily l for reporting purposes and do not actuate any equipment in response to an '

event, nor are they used to terminate or mitigate an event should one occur.

Therefore, the relocation of these requirements from the technical i specifications to the REMODCM cannot increase the probability or consequences of any accident previous!y evaluated.

o

U.S. NucleIr Regulatory Commission CY-99-041/Att:chment 4/Prge 16

1. In the Design Features, the replacement of a pictorial representation by a narrative description of the site has no effect on the materials of construction or geometrical arrangement of the site. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

J-1. . The formalization of the functions of the Unit Director and Shift Manager in

. Specification 6.1 does not change the operation of the unit. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

J-2. The changes to the organization in Specification 6.2.1 reflect the change from power production to the safe storage of spent fuel. As power production is no longer applicable to the HNP, this change cannot increase the probability or consequences of any accident previously evaluated.

J-3. The changes to the facility staff in Specification 6.2.2 formalizes existing administrative requirements for control of movement of loads over spent fuel, and requires that the Shift Manager must be a CERTIFIED FUEL HANDLER.

It also removes the formalization of the restriction on working hours which was a post-TMl requirement applicable to operating nuclear plants. As these changes do not affect the operation of the plant, this change cannot increase the probability or consequences of any accident previously evaluated.

J-5. The transfer of training requirements for the plant staff from Specification 6.4 does not affect plant operations as these requirements are maintained in the CYQAP. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

J-6. The transfer of requirements for review and audit from old Specification 6.5 does not affect plant operations as these requirements are maintained in the CYQAP. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

J-7. The changes to the controls for procedures and programs in new Specification 6.5 reflect the change from power production to the safe storage of spent fuel. As power production is no longer applicable to the HNP, this change cannot increase the probability or consequences of any accident previously evaluated.

J-8. The deletion of the reporting requirements of old Specification 6.6 does not affect plant operation because the requirements are still in effect under the regulations of 10 CFR 50. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

1 U.S. Nucinr R:gul*. tory Commission CY-99-041/ Attachment 4/Page 17 J-9. The formalization of presently existing programs in Specification 6.6, and reorganization of this section from other old sections does not change plant operation. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

J-12. The changes to the reporting requirements of Specification 6.9 remove requirements that are covered by the requirements of the regulations in 10 CFR 50, formalize presently existing requirements, and make administrative changes to submittal dates. As these changes do not affect the operation of the plant, they cannot increase the probability or consequences of any accident previously evaluated.

J-14. The relocation of Reporting Requirements of old Specification 6.10 to the CYQAP does not affect plant operation. Therefore, this change cannot increase the probability or consequences of any accident previously evaluated.

I

2. Create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes are generally of an administrative nature and do not have an effect on the physical plant. The events considered bound other potential events and are considered the limiting cases for potential gaseous or liquid releases to the environment.

With the plant undergoing decommissioning, the types of accidents one might be  !

concerned with involve criticality of the spent fuel, or draining of the spent fuel pool.

None of the proposed changes affect the possibility of such an event. Also, none of the proposed changes could lead to a radiological release of a greater magnitude  !

than for the events considered, such as might occur with-the accumulation of a j greater quantity of radioactive material in one location, or with damage to a greater j number of fuel assemblies than considered in the fuel handling accident.  ;

i The proposed changes restrict the operations that can be conducted at the plant, and do not permit any new type of activity from what had previously been authorized. The effect on systems, structures and components affected by the proposed changes have no adverse impact on the storage of fuel nor on the processing of radioactive wastes presently at the site. The present set of limiting events are a subset of events previously considered. Therefore these changes do not create the possibility of a new or different kind of accident from any accident previously considered.

U.S. Nucle:r Regulatory Commi sion CY-99-041/ Attachment 4/Page 18 A. This is an administrative change to the operating license to reflect the fact that the Haddam Neck Plant has permanently ceased operation, that fuel has permanently been removed from the reactor, and that the plant is

-undergoing decommissioning. This change removes the possibility of those reactor-related events which were applicable while the plant was operating, it is a purely administrative change which does not authorize any new

~ activities at the plant site, but rather restricts the activities which may occur there to a subset of those activities previously considered. Thus the change does not create the possibility of a new or different kind of accident from any accident previously considered.

Changes B, C, G-2, J-4, J-10, J-11, J-13, J-15, J-16, J-17, J-18, J-19, and K The editorial changes included in this proposed revision provide correct spelling, brevity, clarity and/or consistency. None of these changes affect plant configuration nor do they affect plant operations. Therefore these editorial changes cannot create the possibility of a new or different kind of accident from an accident previously evaluated.

D. This is an administrative change to the Definitions that has no effect on the physical plant, and does not change the way the plant is operated, i Therefore it cannot create the possibility of a new or different kind of l accident from any accident previously considered.

E. The meteorological monitoring and radioactive effluent monitoring instrumentation are used for information gathering and monitoring the course of an event should one occur. This instrumentation does not interact with any other plant equipment such that it could cause an event should it fail.

This instrumentation does not actuate any equipment in response to an event, and is not used to terminate or mitigate an event should one occur.

Therefore, the relocation of the requirements for this instrumentation from the technical specifications to the TRM and REMODCM cannot create the possibility of a new or different kind of accident from any accident previously considered.

F. The surveillance for sealed source contamination ensures that the sources used for calibration of radiation monitoring equipment remain intact.

Sources, and the equipment they are used to calibrate, do not have any 4 interaction with any other plant equipment such that they could cause an event. The sources and this instrumentation do not actuate any equipment  !

in response to an event, and are not used to terminate or mitigate an event I should one occur. Therefore, the relocation of the requirements for the surveillance for sealed source contamination from the technical specifications to the TRM cannot create the possibility of a new or different kind of accident from any accident previously considered.

U.S. Nuclear Regul; tory Commission CY-99-041/ Attachment 4/Page 19

)

G-1. There is no change in how the spent fuel is stored or moved in the spent fuel pool. The specifications which were related to operations with fuelin the reactor vessel no longer have any applicability as all fuel has been removed from containment, and fuel is prohibited from being returned inside containment. Of the specifications proposed to be deleted from Section 3/4.9, only LCOs 3.9.12 and 3.9.15 relate to operations in the spent fuel building.

Previously, the fuel storage building air cleanup system of LCO 3.9.12 was utilized to remove iodine via the charcoal filters, thus mitigating the consequences of a fuel handling accident. As the spent fuel has decayed to the extent that there is no longer any appreciable activity to be released should a fuel handiing event occur, there is no longer any need for filtration to mitigate such an event.

The deletion of LCO 3.9.15 is an editorial change to implement what was previously approved in Amendment 193. The reactor was permanently shutdown on July 22,1996 and more than 1,000 days have passed since the shutdown, resulting in a greatly reduced heat load. Thus maintaining the spent fuel pool temperature below 150 *F, as is done by LCO 3.9.16, is sufficient to provide time for compensatory actions should a loss of normal cooling occur. i Therefore, the deletion of these specifications cannot create the possibility of a new or different kind of accident from any accident previously considered.

G-3. For LCO 3.9.7, the increase in the allowable load permitted to be moved i over the spent fuel assemblies, from 1650 pounds to 1800 pounds maintains I the load less than that previously evaluated.

For LCO 3.9.11, the change in the description of the parameter surveilled does not change the way the plant is operated, nor does it affect the way the fuel is stored or moved.

For LCO 3.9.13, the clarification of the frequency of the surveillance does not change the way the plant is operated, nor does it affect the way the fuel is stored or moved.

Therefore, the changes to these specifications cannot create the possibility of a new or different kind of accident from any accident previously ,

considered.

H. The radioactive effluent monitoring specifications impose limits on releases ,

during the normal operation of the plant. These specifications are primarily '

U.S. Nucirr R:gul: tory Commission CY-99-041/ Attachment 4/Page 20 for reporting purposes and the parameters monitored do not actuate any equipment in response to an event, nor are they used to terminate or mitigate an event should one occur. Therefore, the relocation of these requirements from the technical specifications to the REMODCM cannot create the possibility of a new or different kind of accident from any accident previously considered.

1. In the Design Features, the replacement of a pictorial representation by a narrative description of the site has no effect on the materials of construction or geometrical arrangement of the site. Therefore, this change cannot create the possibility of a new or different kind of accident from any accident previously considered. 3 l

J-1. The formalization of the functions of the Unit Director and Shift Manager in Specification 6.1 does not change the operation of the unit. Therefore, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-2. The changes to the organization in Specification 6.2.1 reflect the change from power production to the safe storage of spent fuel. As power production is no longer applicable to the HNP, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-3. The changes to the facility staff in Specification 6.2.2 formalizes existing administrative requirements for control of movement of loads over spent fuel, and requires that the Shift Manager must be a CERTIFIED FUEL HANDLER.

It also removes the formalization of the restriction on working hours which was a post-TMI requirement applicable to operating nuclear plants. As these changes do not affect the operation of the plant, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-5. The transfer of training requirements for the plant staff from Specification 6.4 does not affect plant operations as these requirements are maintained in the CYQAP. Therefore, this change caraot create the possibility of a new or i different kind of accident from any accident previously considered.

~J-6. The transfer of requirements for review and audit from old Specification 6.5 does not affect plant operations as these requirements are maintained in the i CYQAP. Therefore, this change cannot create the possibility of a new or  :

different kind of accident from any accident previously considered.

J-7. The changes to the controls for procedures and programs in new j Specification 6.5 reflect the change from power production to the safe i

o U.S. Nuclear R:gulatory Commission CY-9g-041/Att chm::nt 4/Page 21 storage of spent fuel. As power production is no longer applicable to the HNP, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-8. . The deletion of the reporting requirements of old Specification 6.6 does not affect plant operation because the requirements are still in effect under the regulations of 10 CFR 50. Therefore, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-9. The formalization of presently existing programs in Specification 6.6, and reorganization of this section from other old sections does not change plant operation ' Therefore, this change cannot create the possibility of a new or ,

different kind of accident from any accident previously considered.

1 J-12. The changes to the reporting requirements of Soecification 6.9 remove requirements that are covered by the requirements of the regulations in ,

10 CFR 50, formalize presently existing requirements, and make l administrative changes to submittal dates. As these changes do not affect -

the operation of the plant, they cannot create the possibility of a new or different kind of accident from any accident previously considered.

J-14. The relocation of Reporting Requirements of old Specification 6.10 to the CYQAP does not affect plant operation. Therefore, this change cannot create the possibility of a new or different kind of accident from any accident previously considered.

3. Involve a significant reduction in a margin of safety, 1

The proposed changes have no impact on the analyses of postulated design basis  ;

events remaining applicable to the Haddam Neck Plant. Analysis of the limiting events show that their consequences to the public are within the limits of 10 CFR 20 and the EPA PAGs. The consequences to members of the operating staff are within the limits of 10 CFR 50, Appendix A, General Design Criterion 19,

" Control Room Habitability". Therefore there is no reduction in a margin of safety.

A. This is an administrative change to the operating license to reflect the fact that the Haddam Neck Plant has permanently ceased operation, that fuel has permanently been removed from the reactor, and that the plant is undergoing decommissioning. This change removes the possibility of those reactor-related events which were applicable while the plant was operating.

It is a purely administrative change which does not authorize any new activities at the plant site, but rather restricts the activities which may occur there to a subset of those activities previously considered. As this change

U.S. Nuciter Rtgulatory Commission CY-99-041/ Attachment 4/Page 22 does not affect the likelihood, course or outcome of any licensing basis event, the change does not involve a significant reduction in a margin of safety.

Changes B, C, G-2, J 4, J-10, J-11, J-13, J-15, J-16, J-17, J-18, J-19, and K The editorial changes included in this proposed revision movide correct spelling, brevity, clarity and/or consistency. None of these changes affect plant configuration nor do they affect plant operations. As this change does not affect the likelihood, course or outcome of any licensing basis event, these editorial changes have no effect on the margin of safety. '

D. This is an administrative change to the Definitions that has no effect on the physical plant, and does not change the way the plant is operated. As this change does not affect the likelihood, course or outcome of any licensing basis event, the change does not involve a significant reduction in a margin of safety.

E. The meteorological monitoring and radioactive effluent monitoring instrumentation are used for information gathering and monitoring the course of an event should one occur. This instrumentation does not interact with any other plant equipment such that it could cause an event should it fail.

j This instrumentation does not actuate any equipment in response to an '

event, and is not used to terminate or mitigate an event should one occur.

As this change does not affect the likelihood, course or outcome of any licensing basis event, the relocation of the requirements for this instrumentation from the technical specifications to the TRM and REMODCM does not involve a significant reduction in a margin of safety.

F. The surveillance for sealed source contamination ensure that the sources used for calibration of radiation monitoring equipment remain intact.

Sources, and the equipment they are used to calibrate, do not have any interaction with any other plant equipment such that they could cause an 4 event. The sources and this instrumentation do not actuate any equipment l in response to an event, and are not used to terminate or mitigate an event  !

should one occur. As this change does not affect the likelihood, course or i outcome of any licensing basis event, the relocation of the requirements for j the surveillance for sealed source contamination from the technical specifications to the TRM does not involve a significant reduction in a margin of safety.

G-1. There is no change in how the spent fuel is stored or moved in the spent fuel pool. The specifications which were related to operations with fuel in the reactor vessel no longer have any applicability as all fuel has been removed from containment, and fuel is prohibited from being returned inside j

r 1 U.S. Nucl=r Regulatory Commission CY-99-041/Attachm:nt 4/Page 23 containment. Of the specifications proposed to be deleted from Section 3/4.9, only LCOs 3.9.12 and 3.9.15 relate to operations in the spent fuel building.

Previously, the fuel storage building air cleanup system of LCO 3.9.12 was utilized to remove iodine via the charcoal filters, thus mitigating the consequences of a fuel handling accident. As the spent fuel has decayed to the extent that there is no longer any appreciable activity to be released l should a fuel handling event occ.ur, there is no longer any need for filtration to mitigate such an event. The only remaining use of this system is normal ventilation of the spent fuel building, which is not a safety-related function.

The deletion of LCO 3.9.15 is an editorial change to implernent what was previously approved in Amendment 193. The reactor was permanently l shutdown on July 22,1996 and more than 1,000 days have passed since the shutdown, resulting in a greatly reduced heat load. Thus maintaining the spent fuel pool temperature below 150 *F, as is done by LCO 3.9.16, is '

sufficient to provide time for compensatory actions should a loss of normal cooling occur.

As this change does not affect the likelihood, course or outcome of any licensing basis event, the deletion of these specifications does not involve a significant reduction in a margin of safety. l G-3. For LCO 3.9.7, the increase in the allowable load permitted to be moved over the spent fuel assemblies, from 1650 pounds to 1800 pounds maintains the load less than that previously evaluated.

For LCO 3.9.11, the change in the description of the parameter surveilled does not change the way the plant is operated, nor does it affect the way the fuel is stored or moved.

For LCO 3.9.13, the clarification of the frequency of the surveillance does not change the way the plant is operated, nor does it affect the way the fuel is stored or moved.

Therefore, the changes to these specifications do not involve a significant reduction in a margin of safety.

H. The radioactive effluent monitoring specifications impose limits on releases j during the normal operation of the plant. These specifications are primarily  !

for reporting purposes and do not actuate any equipment in response to an l event, nor are they used to terminate or mitigate an event should one occur. l Therefore, the relocation of these requirements from the technical  !

U.S. Nucl=r Rrgulatory Commission CY-99-041/ Attachment 4/Page 24

]

specifications to the REMODCM does not involve a significant reduction in a margin of safety. i I

1. In the Design Features, the replacement of a pictorial representation by a j narrative description of the site has no effect on the materials of construction {

or geometrical arrangement of the site. Therefore, this change does not {

involve a significant reduction in a margin of safety. l l

J-1. The formalization of the functions of the Unit Director and Shift Manager in l Specification 6.1 does not change the operation of the unit. Therefore, this change does not involve a significant reduction in a margin of safety.  !

)

J-2. The changes to the organization in Specification 6.2.1 reflect the change l from power production to the safe storage of spent fuel. As power l' production is no longer applicable to the HNP, this change does not involve a significant reduction in a margin of safety.

J-3. The changes to the faci lity staff in Specification 6.2.2 formalizes existing administrative requirements for control of movement of loads over spent fuel, l and requires that the Shift Manager must be a CERTIFIED FUEL HANDLER.

It also removes the formalization of the restriction on working hours which was a post-TMI requirement applicable to operating nuclear plants. As these changes do not affect the operation of the plant, this change does not involve a significant reduction in a margin of safety. l J-5. The transfer of training requirements for the plant staff from Specification 6.4 does not affect plant operations as these requirements are maintained in the CYQAP. Therefore, this change does not involve a significant reduction in a

)'

margin of safety.

J-6. The transfer of requirements for review and audit from old Specification 6.5 does not affect plant operations as these requirements are maintained in the CYQAP. Therefore, this change does not involve a significant reduction in a margin of safety.

J-7. The changes to the controls for procedures and programs in new Specification 6.5 reflect the change from power production to the safe storage of spent fuel. As power production is no longer applicable to the HNP, this change does not involve a significant reduction in a margin of safety, i J-8. The deletion of the reporting requirements of old Specification 6.6 does not affect plant operation because the requirements are still in effect under the regulations of 10 CFR 50. Therefore, this change does not involve a significant reduction in a margin of safety.

F l

U.S. Nuclear Rsgulatory Commission CY-99-041/Attachm:nt 4/Page 25 l

J-9. The formalization of presently existing programs in Specification 6.6, and '

reorganization of this section from other old sections does not change plant operation. Therefore, this change does not involve a significant reduction in l a margin of safety.

J-12. The changes to the reporting requirements of Specification 6.9 remove I requirements that are covered by the requirements of the regulations in l

10 CFR 50, formalize presently existing requirements, and make I administrative changes to submittal dates. As these changes do not affect the operation of the plant, they do not involve a significant reduction in a margin of safety.

l J-14. The relocation of Reporting requirements of old Specification 6.10 to the

' CYOAP does not affect plant operation. Therefore, this change does not involve a significant reduction in the margin of safety.

Based on the above, the proposed cnanges to the operating license and technical specifications do not involve a reduction in the margin of safety due to the reduced decay I heat load, the decay of radionuclides since shutdown and by maintaining the heavy load restriction.

Conclusion The Commission has provided guidance concerning the application of standards for determining whether a significant hazards consideration exists by providing certain examples (51 FR 7751) of amendments that are considered not likely to involve significant hazards. Example (i) relates to a purely administrative change to technical specifications; for example a change to achieve consistency throughout the technical specifications, correction of an Error, or a change in nomenclature. Example (ii) relates to a change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications, e.g., a more stringent surveillance requirement. Example (iv) relates to a relief granted upon demonstration of acceptable operation from an operating restriction that was imposed because acceptable operation was not yet demonstrated.

This assumes that the operating restriction and the criteria applied to a request for relief l have been established in a prior review and that it is justified in a satisfactory way that the I

criteria have been met.

In this case, the proposed change described above is simi'ar to Example (i), Example (ii),

and Example (iv).

• Proposed changes B, C, D, G-2, G-3, J-2, J-4, J-10, J-11, J-13, J-15, J-16, J-17, J-18, J-19, and K are similar to Example (i) in that they are editorial, purely administrative, or modify the format of the specifications to make them clearer and more user friendly, l.

r..

U.S. Nuciaar Regulatory Commission CY-99-041/Attachmsnt 4/Page 26 Proposed changes A, J-1, and J-9 are similar to Example (ii) in that they impose additional restrictions on the plant.

Proposed changes G-1, I, J-3, J-5, and J-7 are similar to Example (iv) in that the deletion of specifications applicable to operation with fuel in the reactor were restrictions of imposed prior to the removal of fuel from the vessel and prior to operation the spent fuelisland.

The proposed relocation of material per AL 95-06, GL 89-01, GL 95-10, and of Specifications 3.7.5,6.6, and 6.9.1 by proposed changes E, F, H, J-6, J-8, J-12, and J-14 do not clearly fall under any of the examples given. However, the material does not meet the criteria of 10 CFR 50.36 for inclusion as a technical specification and it has been demonstrated above that these changes do not negatively impact the public health and safety.

Therefore, based on the above considerations, CYAPCO has determined that these changes do not constitute a significant hazards consideration.

_ _ _ _