ML20098C098

From kanterella
Revision as of 01:43, 1 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Proposed Tech Specs Re Pressurizer & Main Steam Safety Valves
ML20098C098
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/29/1995
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20098C097 List:
References
NUDOCS 9510060243
Download: ML20098C098 (8)
v • d • e


Text

. .

Docket No. 50-336 i B15371 '

l I

Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications  !

Pressurizar and Main Steam Safety Valves Marked-up Pages September 1995 9510060243 950929 PDR ADOCK 05000336 P PDR

.' February 15,1995 j

REACTOR COOLANT SYSTEM

. l 4

$AFETY VALVES i i i LIMITING COM ITION FOR OPERATION j

3.4.2.1 Ae of one pressurizer code safety valve shall be OPERABLE with
a lift sett g'o 2500 PSIA m o
AP'PLICABILITY
MODE 4 when the temperature of any RCS cold leg is greater than 1 275'F.

i l 8GIlQ!i:

i With no pressurizer code safety valve OPERABLE, immediately suspend all ourations involving positive reactivity changes and place an OPERABLE

.: sautdown cooling loop into operation.

W j 3.4.2.2 All pr surizer code safety valves shall be OPERABLE with a lift setting

of 2500 PSIA 1 gp

! APPLICABILITY: M00 , 2 and 3.

AGIIQlf:

l With one pressurizer code safety valve inoperable, either restore the inoperable j valve to OPERABLE status within 15 minutes or be in H0T SHLJTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l SURVEILLANCE REQUIREMENTS l

4.4.2 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2500 PSIA i 15, in accordance with Specification 4.0.5.

l fc w 1% wt seu pam akll cerescuct2 4o awkne~4 cdkva eMe de i e a+ aman opeura,w m c u m s rt 5 ~ile, b(& &.44-tn' A SkIl be t Yi" $ l % N lu~)IY h W l*5 f Y G Sc4 vA w -leshM Y U f

i MILLSTONE - UNIT 2 3/4 4-2 Amendment No. 77 JJ7185 v el, l

3 February 26, 1991 t ,

l o '

s

3'/4.7 ' PLANT SYSTEMS

} 3.4.7.1 TURBINE CYCLE

),

hAFETYVALVES

\

j LIMITING CONDITION FOR OPERATION

{

1 3.7.1.1 All main steam line code safety valves shall be OPERABLE.

, APPLICABILITY: MODES 1, 2, and 3.

j ACTION:

4

a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves

! )

inoperable, operation in MODES 1, 2, and 3 may proceed provided, l that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, either the inoperable valve is restored to l i

OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the l i

next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in OLD SHUTDOWN within the following 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.  !

SURVEILLANCE REQUIREMENTS H *  !

4 i 4.7.1.1 Each main steam line code safety valve shall be demonstrated l j

,0PERABLE, with lift settingsG : ce fic: :fzibas shown in Table 4.7-2, in accordance with Specification 4.0.5.

3 f

i MILLST0NE - UNIT 2 3/4 7-1 oa6 Amendment No. M. JM,151

-. - - - - ~. _ _

May 12, 1979 .

. TABLE 4.7-l' ts ~, -

DP .

STEAM LINE SAFETY YALVES-b z

,f *

%er OR1FICE SIZE- +

LIFT SETT1 t[jt) l

". VALVE NUMBERS 6 a. 2-MS-246 & 2-MS-247 1000 psia 4.515 in.2

\

b. 2-MS-242 & 2-MS-254 1005 psia 4.515 in.2
c. 2-MS-245 & 2-MS-249 1015 psia: 4.515 in.2
d. 2-MS-241 & 2-MS-252 1025 psia 4:515 in.2 e

C e. 2-MS-244 & 2-MS-251 10:,5 psia 4.515 in.2 1 b .

f. 2-MS-240 & 2-MS-250 1045 psia 4.515 in.2 i

1

g. 2-MS-239, 2-MS-243, 1050 psia, 4.515 in.2 2-MS-248 & 2-MS-253

,G W C sL 6 e"

4 4 t, w s u g pes > w b F '

,j_l c,pc<ckg W " * ,

( .

"+1I *d *..a A h+ccA3'h" .

g A g 6 dt b u b. " 9' l

w hJ .

l l_ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ . _ _____ ___ ____ __ .-- _ _ _ _ _ _ _m_____ . _ _ _ _

< l l

{

. . l Docket No. 50-336 B15371 t

a Attachment 4 i Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications 1 Pressurizer and Main Steam Safety Valves Retyped Pages i

l 4

i e

1 l

l 1

.' September 1995

REACTOR C0OLANT SYSTEM SAFETY VALVES LINITING COMITION FOR OPERATION 3.4.2.1 A minimum of one pressurizer code safety valve shall be OPERABLE with a lift setting

  • of 2500 PSIA i 3%.** l APPLICABILITY: MODE 4 when the temperature of any PCS cold leg is greater than 275'F.

ACTION:

With no pressurizer code safety valve OPERABLE, immediately suspend all o)erations involving positive reactivity changes and place an OPERABLE slutdown cooling loop into operation.

3.4.2.2 All pressurizer code safety valves shall be OPERABLE with a lift setting

  • of 2500 PSIA i 3%.**

APPLICABILITY: MODES I, 2 and 3.

ACTION:

With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIRENENTS 4.4.2 Each pressurizer code safety valve shall be demonstrated OPERABLE with a lift setting of 2500 PSIA i 1%, in accordance with Specification 4.0.5.

i i

  • The lift setting pressure shall correspond to ambient conditions of the

-valve (s) at nominal operating temperature and pressure.

    • The lift setting shall be within i 1% following pressurizer code safety valve testing.

NILLSTONE - UNIT 2 3/44-2 Amendment No. JJ JJ7, JJJ, 0217

3/4.7j PLANT SYSTEMS 3.4.7.1 TURBINE CYCLE 4

i SAFETY VALVES LINITING CONDITION FOR OPERATION 4

3.7.1.1 All main steam line code safety valves shall be OPERABLE.  !

, APPLICABILITY: H0 DES 1, 2, and 3.

ACTION:.

i a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam line code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, I

.that within 4 ' hours, either the inoperable valve is restored to '
OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l SURVEILLANCE REQUIRENENTS P

4.7.1.1 Each main steam line code safety valve shall be demonstrated

. OPERABLE, with lift settings as shown in Table 4.7-1, in accordance with l !

l.

Specification 4.0.5.

a i-4 NILLSTONE - UNIT 2 3/4 7-1 Amendment No. 77, JJ7, JJJ, 0218

er TABLE 4.7-1 STEAN LINE SAFETY VALVES VALVE NUMBERS LIFT SETTING * (t 3%)**

a. 2-MS-246 & 2-MS-247 1000 psia
b. 2-MS-242 & 2-MS-254 1005 psia
c. 2-MS-245 & 2-MS-249 1015 psia
d. 2-MS-241 & 2-MS-252 1025 psia l
e. 2-MS-244 & 2-MS-251 1035 psia i
f. 2-MS-240 & 2-MS-250 1945 psia
g. 2-MS-239, 2-MS-243, 1050 psia 2-MS-248 & 2-MS-253 4
  • The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
    • The lift setting shall be within i 1% following main steam line code safety valve testing.

NILLSTONE - UNIT 2 3/4 7-3 Amendment No.

0218

Retrieved from "https://kanterella.com/w/index.php?title=ML20098C098&oldid=2781254"