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* TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 3. Pressurizer Pressure-I.ow
* INITIATING SIGNAL AND FUNCTION TABLE 3.3-5 (Continued~
: 4. a. Safety Injection (ECCS) b. Reactor Trip (from SI) c. Feedwater Isolation
ENGINEERED SAFETY FEATURES RESPONSE TIMES RESPONSE TIME IN SECONDS
: d. Containment Isolation  
: 3. Pressurizer Pressure-I.ow
-Phase "A" e. f. g. Containment Ventilation Isolation Auxiliary Feedwater Pumps Service Water System Differential Pressure Betwee.n Steam Lines-High
: a. Safety Injection (ECCS)                       s  21.0< 1 >;12.0< 2 >
: a. b. c. d. Safety Inj action (ECCS') Reactor Trip (from SI) Feedwater Isolation Containment Isolation  
: b. Reactor Trip (from SI)                       s  2.0
-Phase e. Containment Ventilation Isolation
: c. Feedwater Isolation                           s  7.0
: f. *Auxiliary Feedwater Pumps g. Service Water System 5. Steam Flow in Two Steam Lines -High Coincident with Tavg --Low-Low a. b. c. d. e. f. g. h. Safety InJection (ECCS) Reactor Trip (from SI) Feedwater Isolation Containment Isolation
: d. Containment Isolation - Phase "A"             s  18.0< 2 >
-Phase "A" Containment Ventilation Isolation Auxiliary Feedwater Pumps Service Water System St.eam Line Isolation s 21.0<1>;12.0<2> s 2.0 s 7.0 s 18.0<2> Not Applicable
: e. Containment Ventilation Isolation             Not Applicable
< 60 49.0<1> ;13.'0&deg;<2> s s 2.0 s 7 .0 s .-0 ( 2.> /2 7 . 0 ( 3) Not Applicable s 60 s 13.0<2>/48.0<3> s 15.75<2>;25,75<3> s 5.75 s 10.75 s 20.15<2>;30.15<3> Not. Applicable s 61.75 . s 15.75<2>;50.15<3>
: f. Auxiliary Feedwater Pumps                     < 60
* s 10.75
: g. Service Water System                         ~  49.0< 1 >;13.'0&deg;< 2 >
* Sl3.75 until restart following refueling outage. SALEM -UNIT 1 3/4 3-28 Amendment No. 112 "t
: 4. Differential Pressure Betwee.n Steam Lines-High
* TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 6. Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure -Low a. b. c. d. e. Safety Injection (ECCS) Reactor Trip (from SI) Feedwater Isolation Containment Isolation-Phase "A" Containment Ventilation Isolation
: a. Safety Inj action (ECCS')                     s ~2.0< 2 >;22.0< 3 >
: f. 0 Auxiliary Feedwater Pumps g. Service System h. * *. Steam Line IsOlatfon
: b. Reactor Trip (from SI)                       s 2.0
: 7. Containment
: c. Feedwater Isolation                           s 7 .0
: a. Containment Spray b.* Containment Isolation-Phase "B". c. Steam Line Isolation
: d. Containment Isolation - Phase   ~A"          s ~17 .-0 ( 2.> /2 7.0 ( 3 )
: d. *C9ntainment Fan Cooler 8. Steam Generator Water Level--High-High
: e. Containment Ventilation Isolation             Not Applicable
: a. b. Turbine Trip Feedwater Isolation
: f.   *Auxiliary Feedwater Pumps                     s  60
: g. Service Water System                         s  13.0< 2 >/48.0< 3 >
: 5. Steam Flow in Two Steam Lines - High Coincident with Tavg -- Low-Low
: a. Safety InJection (ECCS)                       s 15.75< 2 >;25,75< 3 >
: b. Reactor Trip (from SI)                        s 5.75
: c. Feedwater Isolation                          s 10.75
: d. Containment Isolation - Phase "A"            s 20.15< 2 >;30.15< 3 >
: e. Containment Ventilation Isolation            Not. Applicable
: f. Auxiliary Feedwater Pumps                      s 61.75         .
: g. Service Water System                          s 15.75< >;50.15< 3 >
2
: h. St.eam Line Isolation                        s 10.75 *
* Sl3.75 until restart following   t~ta refueling outage.
0 SALEM - UNIT 1                   3/4 3-28           Amendment No. 112
 
"t
* TABLE 3.3-5 (Continue~
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION                           RESPONSE TIME IN SECONDS
: 6. Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure - Low
: a.     Safety Injection (ECCS)                         s 12.0< 2 );22.0< 3 )
: b.      Reactor Trip (from SI)                           s 2.0
: c.      Feedwater Isolation                             s 7.0
: d.      Containment Isolation-Phase "A"                 s 17.0< 2 );21.0< 3 )
: e.      Containment Ventilation Isolation               Not Applicable
: f. 0 Auxiliary Feedwater Pumps                       s 60 .*
: g.       Service ~at~r System                           s 14.~~ 2 )/48.0( 3 )
: h. * *. Steam Line IsOlatfon                             s 8.0*
: 7. Containment     Pressur~--High-High
: a.       Containment Spray                               s ~5.0 b.*     Containment Isolation-Phase "B".                 Not Applicable
: c.       Steam Line Isolation                             s 7.0 *
: d.     *C9ntainment Fan Cooler                           s 40.0.
: 8. Steam Generator Water Level--High-High
: a.       Turbine Trip                                    s 2.5
: b.       Feedwater Isolation                             s 11.0*
: 9. Steam Generator Water Level--Low-Low
: 9. Steam Generator Water Level--Low-Low
: a. Motor-Driven Auxiliary_
: a.       Motor-Driven Auxiliary_ *:Feed~ater Pumps(4)                                         s 60.0
Pumps(4) b. Turbine-Driven Auxiliary Feedwater Pumps(5) s 12.0<2);22.0<3) s 2.0 s 7.0 s 17.0<2);21.0<3) Not Applicable s 60 .* s
: b.       Turbine-Driven Auxiliary Feedwater Pumps(5)                                         s 60.0 lte&#xa3;+h I SlO.O seconds until restart following the       ~*refueling      outage.
* s 8.0 s Not Applicable
  *                                                                                    .  '
* s 7.0 s 40.0. s 2.5 s 11.0* s 60.0 s 60.0
                                                                                          "
* lte&#xa3;+h I SlO.O seconds until restart following the outage. SALEM -UNIT 1 3/4 3-29 Amendment No. 112 . ' " 
SALEM - UNIT 1                       3/4 3-29             Amendment No. 112
. . . 0 PLANT SYSTEMS *
 
* MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION . 3.7.1.S Each main steam line isolation valve shall be OPERABLE.
...
APPLICABILITY:
PLANT SYSTEMS
MODES 1, 2 and 3. ACTION; MODES 1 -With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours; otherwise, be in HOT SHUTDOWN within the next 12 hours .. ' MODES 2 -With one main steam line isolation inoperable, and 3 operation in MODES 1, 2 or 3 may proceeA:provided; . . . . . . a. The isolation valve h maintained closed. b. The. provisions of Specification 3.0.4 applicable.
* MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION
Otherwise, be in HOT SHUTDOWN within. the next 12 hours. SURVEILLANCE REQUIREMENTS 4.7.l\S Each main steam line isolation v1lve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to o Specification 4.0.5. ** 8 seconds until restart following refueling outage. SALEM -UNIT 1 3/4 7-10 Amendment No. 112}}
* 3.7.1.S
                                                            .
Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION; MODES 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours; otherwise, be in HOT SHUTDOWN within the next 12 hours ..
                                                                      '
MODES 2 - With one main steam line isolation ~alve inoperable, and 3     sub~equent operation in MODES 1, 2 or 3 may proceeA:provided;
                    .         .     .       .                         .
            . a. The isolation valve h maintained closed.
: b. The. provisions of Specification 3.0.4 ar~n6t applicable.
Otherwise, be in HOT SHUTDOWN within. the next 12 hours.
SURVEILLANCE REQUIREMENTS 4.7.l\S   Each main steam line isolation v1lve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to o Specification 4.0.5.
      **     8 seconds until restart following t!e!a!s~  refueling outage.
0 SALEM - UNIT 1                 3/4 7-10             Amendment No. 112}}

Revision as of 10:46, 21 October 2019

Proposed Tech Spec 4.7.1.5 & Table 2.2-5 Allowing Continued Use of 8 MSIV Stroke Time During 10th Fuel Cycle
ML18095A733
Person / Time
Site: Salem PSEG icon.png
Issue date: 02/01/1991
From:
Public Service Enterprise Group
To:
Shared Package
ML18095A732 List:
References
NUDOCS 9102080144
Download: ML18095A733 (3)
v • d • e


Text

' .

  • INITIATING SIGNAL AND FUNCTION TABLE 3.3-5 (Continued~

ENGINEERED SAFETY FEATURES RESPONSE TIMES RESPONSE TIME IN SECONDS

3. Pressurizer Pressure-I.ow
a. Safety Injection (ECCS) s 21.0< 1 >;12.0< 2 >
b. Reactor Trip (from SI) s 2.0
c. Feedwater Isolation s 7.0
d. Containment Isolation - Phase "A" s 18.0< 2 >
e. Containment Ventilation Isolation Not Applicable
f. Auxiliary Feedwater Pumps < 60
g. Service Water System ~ 49.0< 1 >;13.'0°< 2 >
4. Differential Pressure Betwee.n Steam Lines-High
a. Safety Inj action (ECCS') s ~2.0< 2 >;22.0< 3 >
b. Reactor Trip (from SI) s 2.0
c. Feedwater Isolation s 7 .0
d. Containment Isolation - Phase ~A" s ~17 .-0 ( 2.> /2 7.0 ( 3 )
e. Containment Ventilation Isolation Not Applicable
f. *Auxiliary Feedwater Pumps s 60
g. Service Water System s 13.0< 2 >/48.0< 3 >
5. Steam Flow in Two Steam Lines - High Coincident with Tavg -- Low-Low
a. Safety InJection (ECCS) s 15.75< 2 >;25,75< 3 >
b. Reactor Trip (from SI) s 5.75
c. Feedwater Isolation s 10.75
d. Containment Isolation - Phase "A" s 20.15< 2 >;30.15< 3 >
e. Containment Ventilation Isolation Not. Applicable
f. Auxiliary Feedwater Pumps s 61.75 .
g. Service Water System s 15.75< >;50.15< 3 >

2

h. St.eam Line Isolation s 10.75 *
  • Sl3.75 until restart following t~ta refueling outage.

0 SALEM - UNIT 1 3/4 3-28 Amendment No. 112

"t

  • TABLE 3.3-5 (Continue~

ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

6. Steam Flow in Two Steam Lines-High Coincident with Steam Line Pressure - Low
a. Safety Injection (ECCS) s 12.0< 2 );22.0< 3 )
b. Reactor Trip (from SI) s 2.0
c. Feedwater Isolation s 7.0
d. Containment Isolation-Phase "A" s 17.0< 2 );21.0< 3 )
e. Containment Ventilation Isolation Not Applicable
f. 0 Auxiliary Feedwater Pumps s 60 .*
g. Service ~at~r System s 14.~~ 2 )/48.0( 3 )
h. * *. Steam Line IsOlatfon s 8.0*
7. Containment Pressur~--High-High
a. Containment Spray s ~5.0 b.* Containment Isolation-Phase "B". Not Applicable
c. Steam Line Isolation s 7.0 *
d. *C9ntainment Fan Cooler s 40.0.
8. Steam Generator Water Level--High-High
a. Turbine Trip s 2.5
b. Feedwater Isolation s 11.0*
9. Steam Generator Water Level--Low-Low
a. Motor-Driven Auxiliary_ *:Feed~ater Pumps(4) s 60.0
b. Turbine-Driven Auxiliary Feedwater Pumps(5) s 60.0 lte£+h I SlO.O seconds until restart following the ~*refueling outage.
  • . '

"

SALEM - UNIT 1 3/4 3-29 Amendment No. 112

...

PLANT SYSTEMS

  • 3.7.1.S

.

Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION; MODES 1 - With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ..

'

MODES 2 - With one main steam line isolation ~alve inoperable, and 3 sub~equent operation in MODES 1, 2 or 3 may proceeA:provided;

. . . . .

. a. The isolation valve h maintained closed.

b. The. provisions of Specification 3.0.4 ar~n6t applicable.

Otherwise, be in HOT SHUTDOWN within. the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.l\S Each main steam line isolation v1lve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to o Specification 4.0.5.

    • 8 seconds until restart following t!e!a!s~ refueling outage.

0 SALEM - UNIT 1 3/4 7-10 Amendment No. 112

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