ML20128Q889
ML20128Q889 | |
Person / Time | |
---|---|
Site: | Zion File:ZionSolutions icon.png |
Issue date: | 10/14/1996 |
From: | COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20128Q873 | List: |
References | |
NUDOCS 9610210210 | |
Download: ML20128Q889 (13) | |
Text
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ATI'ACHMENT B ZION NUCLEAR GENERATING STATION ANNOTATED AND CLEAN COPIES OF 'IllE CTS FOR SUPPLEMENTAL PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSES DPR-39 AND DPR-48 SUPPLEMENT TO LICENSE AMENDMENT REQUEST 96-02 9610210210 961014 PDR ADOCK 05000295 P PDR
LIMITItiG C0tIDIT10tl FOR OPERAT10tl SURVEILLAtiCE REQUIREMEtiT 3.3.2.G. Low Temperature Overpressure Protection (Continued) 4.3.2.G. Low Temperature Overpressure Protection (Continued)
- 4. Verifying each PORV's isolation valve is open at least once per
.* shift when this method is being used for low temperature overpressure protection.
- 5. Testing pursuant to Specification
- b. The Reactor Coolant System (RCS) 4.0.5.
pressure shall be less than 100 b.
psig, and the pressurizer level The RCS pressure shall be verified to less than 25%, or be less than 100 psig, and pressurizer level shall be verified to be less than 25% at least once per shift, when this method is being used for low
- c. The RCS is depressurized and one temperature overpressure protection.
PORV and its isolation valve are open. c. Verifying one PORV and its isolation valve are open at least once per shift, when this method is being used for low
- 2. A maximum of one* charging pumppe-- temperature overpressure protection.
safety injectica p=p, aligned for 2. At least tbee clqt.3 injection into the RCS, and no of the f Me pumps (chargie9-.
,- Tibmu s and sa^ety iiiieet4empumps), and all accumulatorskshallbeOPERABLE. ( accumulators, shall be verified to be owcl no sq % tie h, f*f S - incapable of injecting into the RCS prior to entering a condition in which they are required to be inoperable, and at least For short durations of time during pump once per shift thereafter while they are s'witchover, two charging pumps may be OPERABLE required to be inoperable.
for the purpose of maintaining seal injection M "N A)i'3 c
N b tow 5, flow to the reactor coolant pumps.
~
83 Amendment Nos. 151 and 139
._ . . ~. . . . _. _ __ ._ . . . _ .- . _ _ _ . _ . . . _ . . _ _ _ _ . . . _ . _ _ _ _ _ _
LlHITING CONDITION FOR OPERATION '
SURVEILLANCE REQUIREMENT .
3.3.2.G Low Temperature Overpressure Protection 4.3.2.G Low Temperature Overpressure Prot'ection (Continued) -
(Continued) ;
Y
- 3. when'
%rstarting no re a reactor coolant coolant pumps are pu ng, the pt4ppHeable. ,
t temperature e sec steam generator y side of the '
loop in which the L W b s M i a reai b u la*tf' f*7 Wbh ,
""""'?' 4
~
reactor c pump is arted shall "o R" E "'t " d f
- f5 I
- be I han 50*F hither than the erature. -teqedet. '" a,,;s ife 5o lq Q j.
ye3 7"c*3 K loop c(a g be*
APPt.ICABILITY: Mode 4 when the temperature of any' RCS h55 h SO*FMk-A % MS leg is less than or equal to fe -pe m k " - '
, MODE 5 and MODE 6 with-the N '
., reactor vessel head on. 4 f rop ,g/.] ,
j L
ACTION: a. With one PORV Inoperable in MODE 4 restore the Inoperable PORY to OPERABLE I D"'(*"#
I" ' I 3/ * '
status within 7 days, or within the k 1
next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either; ;
- 1. Depresstirize the RCS to less than 100 pstg and lower pressurtzer level to less than 251, or
[ '
- 2. Depressurize the RCS and open at ~ .
least one PORY and its block valve.
- b. With one PORV inoperable in MODES 5 or 6 restore the inoperable PORV to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or '
within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either; -
- 1. Depressurize the RCS to less than ,
100 psig and lower pressurizer !
. level to less than 251, or -
t .
83a Amendment Nos. 151 and 139
. ---___ _ _ _ _ - - - - . - _ _ _ _ _ ___ _ ----_-___.___--______-J
LIMITING CONDITION FOR OPERATION SURVElLLANCE REQUIREMENT ,
3.3.2.G. Low Temperature Overpressure Protection 4.3.2.G. Low Temperature Overpressure Protection (Continued) (Continued)
- 4. Verifying each PORV's isolation valve is open at least once per shift when this method is being used for low temperature overpressure protection.
- 5. Testing pursuant to Specification 4.0.5.
- b. The Reactor Coolant System (RCS) pressure shall be less than 100 b. The RCS pressure shall be verified to psig, and the pressurizer level be less than 100 psig, and 3ressurizer less than 25% or level shall be verified to >e less than 25% at least once per shift, when this method is being used for low temperature overpressure protection.
- c. The RCS is depressurized and one PORV and its isolation valve are open. c. Verifying one PORV and its isolation valve are open at least once per shift, when this method is being used for low temperature overpressure protection.
- 2. A maximum of one* charging pump aligned for injection into the RCS, and no 2. At least two of the three charging pumps
- accumulators and no safety injection pumps, and all accumulators and all safety shall be OPERABLE. injection pumps, shall be verified to be incapable of injectir.g into the RCS prior to entering a condition in which they are required to be inoperable, and at least once per shift thereafter while they are o For short durations of time during ) ump required to be inoperable.
switchover, two charging pumps may 3e OPERABLE for the purpose of maintaining seal injection flow to the reactor coolant pumps.
83 Amendment Nos.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT ,.
3.3.2.G. Low Temperature Overpressure Protection 4.3.2.G. Low Temperature Overpressure Protection (Continued) (Continued)
- 3. When starting a reactor coolant pump. 3. Not applicable.
when no reactor coolant pumps are running, the temperature in the steam generator secondary side in any unisolated RCS loop shall be less than 50 F higher than the RCS temperature.
APPLICABILITY: Mode 4 when the temperature of any RCS cold leg is less than or equal to the LTOP enable temperature specified in the PTLR, MODE 5 and MODE 6 with the reactor vessel head on.
i ACTION: a. With one PORV inoperable in MODE 4, restore the inoperable PORV to OPERABLE status within 7 days, or <
within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either:
- 1. Depressurize the RCS to less than 100 psig and lower pressurizer .
level to less than 25%, or l
- b. With one PORV inoperable in MODES 5 or 6, restore the inoperable PORV to operable status-within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or . -
within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either:
- 1. Depressurize the RCS to less than '
100 psig and lower pressurizer !
level to less than 25%, or
- 2. Depressurize the RCS and open at '
least one PORV and its block valve.
83a Amendment Nos.
_._.._..____._..__.._.____i.._.___.________.__.___.__-._____ _ _ _ _ _ _ _ _ _ -_ _ _ _ _ _ _
i ATTACHMENT C l l
ZION NUCLEAR GENERATING STATION EVALUATION OF SIGNIFICANT I HAZARD CONSIDERATIONS FOR PROPOSED CHANGES TO l APPENDIX A TECHNICAL SPECIFICATIONS i FACILITY OPERATING LICENSES -l' l DPR 39 AND DPR-48 SUPPLEMENT TO LICENSE AMENDMENT REQUEST 96-02 )
)
Commonwealth Edison has evaluated the previously proposed amendment and I determined that it involves no significant hazards considerations. This was documented in the original License Amendment Request (Ref.1). This supplement to the LAR changes two Technical Specifications to ensure the bounding analysis assumptions of the PTLR are maintained, and graphically illustrates information that had previously been identified in a text. Since these changes are either more restrictive, or are editorial in nature, the changes are bounded by the previous evaluation of significant hazards considerations.
Therefore, the changes contained in this supplement do not alter Comed's previous conclusion that the proposed amendment does not involve a significant increase in the probability or consequences of a previously evaluated accident, does not create the possibility of a new or different kind of accident from any previously evaluated accident, and does not involve a significant reduction in a margin of safety.
A'ITACHMENT D ZION NUCLEAR GENERATING STATION ENVIRONMENTAL ASSESSMENT STATEMENT FOR PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSES DPR-39 AND DPR-48 SUPPLEMENT TO LICENSE AMENDMENT REQUEST 96-02 The proposed changes to the previous license amendment request were evaluated against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. It was determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10 CFR 51.22(c)(9). This was documented in the original License Amendment Request (Ref.1). These changes do not change any of the original evaluations and determinations. Therefore the conclusions of the original environmental assessment remain valid.
I
I A'ITACHMENT E 4
ZION NUCLEAR GENERATING STATION REVISED PTLR PRESSURE / TEMPERATURE CURVES SUHMITTED IN SUPPORT OF PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECIFICATIONS FACILITY OPERATING LICENSES DPR-39 AND DPR-48 i SUPPLEMENT TO LICENSE AMENDMENT REQUEST 96-02 d
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14 MATERIAL PROPERTY BASIS j LIMITING MATERIAL: CIRCUMFERENTIAL WELD SA 1769 i
LIMITING ART VALUES AT 32/25.63 EFPY: 1/4T, 233.0'F 3/4T,183.3*F 1
s J
t 2500 , , , , ,,,,,,,,,,,, , , , ,,, ,, , ,
l i
p......o............. ,1 (
2250 L l LEAE TEST LIMIT i l l' I
'
- l } I} } f 2000 l/l, /, !
t i , .
- ' f!' Ii _! .'
l l i i ! '. . . i s Aii J l it i i li , i i
,- i t , ii 6 , ' i i e /! i e i
, ei i i /i6 /'i 750
" g , i 4 7- i i unacesrrants i ' i ! i i I i i OPERAr!ON ' ' fi / !
- . i l' /
. f m I ! !
! I i
a 1500
'/r l
r
/
1 1.
- / Vi
- o 1250 / ,' Accrerant 6 / i OPERATION _
- 5
/
, 1000 , ,
m , f i O 8
/
EEATUP RATE #
6
! 7$Q UP To 3. F/Er. '
[
v i
, /
! . / '
500 _L '
l
/ i a
250 ,
M !.sa!!cs'sYes!.Ta'
/
j
!!!!!!!'!!!1!'i.'I.f!'!.! 5:!.!!'. ,7 ;
O l '; ;' ; i 0 50 100 150 200 250 300 350 400 450 500 Temperature (Deg.F)
MIN. SOLT-UP TEMP: 60 F 4
FIGURE 1 Zion Units 1 and 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to
, 20*F/hr) Applicable to at least 32 EFPY for Zion Unit 1 and Applicable to 25.63 EFPY for Zion Unit 2 (Without Margins for instrumentation Errors) 2 Zion Units 1 & 2 Heatup and Cooldown Limit Curves June 1996
ia 4
4 MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD SA-1769 LIMITING ART VALUES AT 32/25.63 EFPY: 1/4T, 233.0'F 3/4T,183.3*F 2500 ,,,,,,,,,,,,,,,,,, i ,,
p . .... ,.............l l , ,
j 6 1 I I
~
2250 w '; / /
LEAE TEST LIMIT / / / I i i i i i t I ! ! 8 ! t I / ' f f 2000 1
l
l l
l';,'
6 l l/
e il
,/
!/
, , i t i i !I f
, ,i i Iei t i e i e 'A l !
m ' . 6/l i / '
1750 , UNACCEPTABI,E I ! V! t / I 4 OPERATION i ii ;
. i ! /i i /
ii i a
i t ! t i i !
- t i /i ! 1 g
'i ' ' ' ' ' ' ' ' ' #
a 1500 ,i 6 . , i ' !/ '
i t/ !
v I ' I ' '
i i l' /i
[ i[
i
/i e 1250 l' i
,/'
'/
ACCEPTAstE OPERATION
- (
6 _
U ) t i
- 1000 l i f
m >
c
-~
i /
6 -----
NEATUP RATE f s 750 -- or To ** r/ar. N ,
, , v o p f f I^
500
,f L/
, , i l l I II i I i I ,/ i I 250 i ::::tii':,titi .it!'s.:" l
- :i' ::,1:':.'l J::.: '.,,, !
/ '
0 l l l l-0 50 100 150 200 250 300 350 400 450 500
,,m m ,.o, Temperature ,
(Deg.F)
TEMP! 60 F FIGURE 2 Zion Units 1 and 2 Reactor Coolant System Hea.up Limitations (Heatup Rates up to 40*F/hr) Applicable to at least 32 EFPY for Zion Unit 1 and Applicable to 25.63 EFPY for Zion Unit 2 (Without Margins for instrumentation Errors)
Zion Units 1 & 2 Heatup and Cooldown Umit Curves June 1996 ,
iv
^
MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD SA-1769 LIMITING ART VALUES AT 32/25.63 EFPY: 1/4T, 233.0*F 3/4T,183.3*F 2500 ,,,,,,,,,,,,,,,,,, , , , , ,,, , ,
..., .. ,.............; il! j j i i l i
' I 2250 y / r i LEAK TEST LIMIT / / I J i 'i /! /
,i .
j .i ! a i ! i i J i /i /
2000 ll l , l
! ll l,!/' /
'i i i ! il /
1 i/ /
. I i 1
/l /
^g 1750 !
unace:PTABLE ! /' / '
I OPERATION i f' '
.-- i / /
g I t ! I /i /
2 1500 f
l
/ '
/
l l t / /i o 1250 6 /
/ AccurTAsts OPERATION
> i i 1 1000 j l
)
U /
6 a 750 m:4Ter a4T:
UP 70 Se F/Er. ,
j
/ j i
lk/ i f s' r 500 ,l
/,
, n l
+
iii i!! il I / i! I 250 ' ' ' N' i i l
2 fi!!!!!il'irii!!!af t!'I. I !
/ '
- !;f!!'!!!I&i';.'! J::.!!'.,,1 l 0 ;' '; ; ; ;
0 50 100 150 200 250 300 350 400 450 500 Temperature (Deg.F)
TEMP: 60 F FIGURE 3 Zion Units 1 and 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 60*F/hr) Applicable to at least 32 EFPY for Zion Unit 1 and Applicable to 25.63 EFPY for Zion Unit 2 (Without Margins for Instrumentation Enors)
Zion Units 1 & 2 Heatup and Cooldown Limit Curves June 1996
MATERIAL PROPERTY BASIS i
LIMITING MATERIAL: CIRCUMFERENTIAL WELD SA-1769 LIMITING ART VALUES AT 32/25.63 EFPY: 1/4T, 233.0*F 3/4T,183.3*F 2500 ,,,,,,,,,,,,,,,,,, ,, i j
'1 y.,,,..o........... , , , l r-2250 LEAK TEST LIMIT /
) / /
)
/
)
l 2000 , ,'
.i f
/ f
/ )
n , I \
^
1750 ' - ' ' ' ' l ha i UWACCEPTABLE / i / i i OPERATION J J
=~ I I ,
m i , i / /
l C:1 1500 -- --
, / _ .-
l l o 1250
% i
/ i
)
/l U / / ACCEPTABLE J r OPERATION m
1000 /
/
i O ;
L g 750 , / ,
EEATOP NATE ! .
UP TO 100 F/Er. x / )
V 500 i y ' "
l , l
'i' '
250 ' -
l' i
l a !!!!!itil'iri!!!!a't!'!. I f !!!?!li'!!!1:*i.'}.5::.!!'. ret l 0 '.
l '; ; ; ;i 0 50 100 150 200 250 300 350 400 450 500 Temperature (Deg.F)
HIN, SOLT-UP TEMP: 60 F FIGURE 4 Zion Units 1 and 2 Reactor Coolant System Heatup Limitations (Heatup Rates up to 100*F/hr) Applicable to at Least 32 EFPY for Zion Unit 1 and Applicable to 25.63 EFPY for Zion Unit 2 (Without Margins for instrumentation Errors)
Zion Units 1 & 2 Heatup and Cooldown Limit Curves June 1996 3
18 P
MATERIAL PROPERTY BASIS LIMITING MATERIAL: CIRCUMFERENTIAL WELD SA-1769 LIMrrlNG ART VALUES AT 32/25.63 EFPY: 1/4T, 233.0*F 3/4T,183.3*F 2500 ,,,,,,,,,,,,,,,,,, , ,
p ...... ,.............; j i
2250 l
/
\ l 2000 #
r 1
I I
^g 1750 i i UNACCEPTABLE /
0PERATION I
, ; i , 12 a 1500 '/
, I i i
e L__
6 c) 1250
/ ACCEPTABLE OPERATION
[
a /
1000 , / ,
a G .1 FAV g;n; ova r/xt. , jfff L;
[ff
~
m "s "/ # /
500 _
mw
_ a .ex
. w' ' r, y \
250-.2 '!! I " ' ' '
4 ,
0 100 150 200 250 300 350 400 450 500 o / 50
. . .om.o, Temperature (Deg.F)
TEMP: 60 F FIGURE 5 Zon Units 1 and 2 Reactor Coolant System Cooldown Limitations (Cooldown Rates up to 100*F/hr) Applicable to at least 32 EFPY for Zion Unit 1 and Applicable to 2S.63 EFPY for Zon Unit 2 (Without Margins fo* Instrumentation Errors)
Zion Units 1 & 2 Heatup and Cooldown Limit Curves June 1996 9