ML20113C256

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Revising TS 3.3.11, Pami, & 5.5.2.13, Diesel Fuel Oil Testing Program
ML20113C256
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/25/1996
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20113C242 List:
References
NUDOCS 9607010080
Download: ML20113C256 (15)
v • d • e


Text

[ l j .,

PAM Instrumentation r

3.3.11 fable 3.3.11-1 (page 1 of 1)

Post Accident Monitoring instrumentation l

-==

CCNOITIONS REFERENCED FROM FUNCTICN REQUIRED REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2 G
2. Reactor Coolant System Hot Leg Temperature 2 per loop G
3. Reactor Coolant System Cold Leg Terrcerature 2 per loop G 4 Reactor Coolant System Pressure (wide range) 2 C
5. Reactor Vessel Water Level 2(d) H
6. Containment Strnp Vater t.evel (wide range) 2 G
7. Containment Pressure (wide range) 2 G 8.

Containment Isolation Valve Position 2perpene{g((Q'nflow path G

9. Containment Area Radiation (high range) 2 H
10. Containment Hydrogen Monitors 2 G
11. Pressuelter Level 2 G
12. Steam Generator Water Level (wide range) 2 per steam generator G
13. Condensate Storage Tank Level 2 G 14 Core Exlt Temperature -Quadrant 1 2CCI C
15. Core Exit Temperature-cuadrant 2 2(*) G
16. Core Exit Temperature -Quadrant 3 ZIU G l 17, Core Exit Tenperature - Quadrant 4 2CCI G
18. Auxiliary Feedwater Flow 1 per steam generator G

! 19. Containment Pressure (narrow range) 2 G

20. Reactor Coolant System Subcooling Margin Monitor 2 0
21. Pressurf ter Safety Valve Position Indication 1 per valve G
22. Containment Tenperature 2 G
23. Containment Water Level (narrow range) 2 C 24 HPSI Flow Cold Leg 1 per cold leg G 2$. HPS! Flow Hot Leg

.1 per het les G

26. Steam Line Pressure 2 per steam generater G
27. Refueling Water Storage Tank Level 2 G (a)

Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated valve secured.automatic valve, closed manual valve, blind flange, or check valve with flow through the

.(b) only one position indication channel is required for penetration flow paths with only cne installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

(d) A channel consists of eight sensors in a probe.  !

sensor in the upper head and three sensors in the lower head are OPERA 8LE.A channel is CPERABLE if four or SAN ON0FRE--UNIT 2 3.3-47 t

Amendment No. 127 9607010080 960625 PDR ADOCK 05000361 p PM

I i -

i Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.12 Ventilation Filter Testing Program (VFTP) (continued)

The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are applicable to the VFTP test frequencies.

5.5.2.13 Di.esel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include. sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:

a. At lease once per 92 days and from new fuel oil prior to '

addition to the storage tanks by verifying that a sample )

obtained in accordance with ASTM-D4057-81 has a water and sediment content of less than or equal to 0.05 volume percent, an API gravity or an absolute specific gravity within limits, and a kinematic viscosity @ 40 C of greater than or equal to 4.1 when tested in accordance with ASTM-D975-81.

b. At.least once every 92 days by obtaining a sample of fuel oil l in accordance with ASTM-D2276-81 and verifying that i

particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

l l

l l

A ONOFRE--UNIT 2

.S.N 5.0-20 Amendment No. 127 l -. -

PAM Instrumentation B 3.3.11 BASES LC0 2, 3. Reactor Coolant System (RCS) Hot and Cold Lea (continued) Temperature i

RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long term surveillance. l Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elements and l associated transmitters in each loop. '

4. Reactor Coolant Si em Pressure (wide rance)

RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity long term surveillance.

The pressure transmitters are located inside the containment. Redundant monitoring capability is provided by two trains of instrumentation.

Operater actions to maintain a controlled cooldown, such as adhsting steam generator pressure or level, would use this indication. Furthermore, RCS pressure is one factor that may be used in decisions to terminate reactor coolant pump operation.

5. Reactor Vessel Water Level Reactor Vessel Water Level is provided for verification and long term surveillance of core cooling.

The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignrant plate. The collapsed level represents the amount of liquid mass that is in the reactor vessel above the core.

(continued)

SAN ONOFRE--UNIT 2 B 3.3-162 Amendment No. 127

NPF-10/15-466 ATTACHMENT "B" (Existing Specifications)

Unit 3 I i

i l

1

PAM' Instrumentation >

3.3.11 Table 3.3.11 1 (page 1 of 1)

Post Accident Monitoring Instrunentation

=

CCNOLTICMS REFERENCE 0 FROM FUNCTION REQUIRED

\ REQUIRED CHANNELS ACTICN F.1

1. Excore Neutron Flux 2 G
2. Reactor coolant System Not Leg Tenperature 2 per loop G
3. Reactor Coolant System Cold Leg Temerature 2 per loop G 4

Reactor Coolant System Pressure (wide range) 2 G

5. Reactor vessel Water Level 2Id3 H
6. Containment Sunp Water Level (wide range) 2 G
7. Contairwent Pressure (wide range) I 2 G
8. \

Contairinent Isolation Valve Position 2 per path pene{ g n flow G

( 9. Contairwent Area Radiation (high range) 2 H

10. Contairvnent Hydrogen Monitors 2 G
11. Pressurizer Level 2 G I

12/ Steam Generator Water Level (wide range) 2 per steam generator G

13. Condensate Storage Tank Level 2 G 14 Core Exit Tercerature - Quadrant 1 2(c) a
15. Core Exit Terrperature-Quadrant 2 2CCI C
16. Core Exit Ternperature -Quadrant 3 ZICI C
17. Core Exit Temperature - Quadrant 4 2(c) a f 18. Auxiliary Feedwater Flow 1 per steam generator G
19. Containment Pressure (narrew range) 2 G l
20. Reactor Coolant Systen Sdx:ooling Margin Monitor 2 G t
21. Pressurizer Safety Valve Position Indication 1 per valve G
22. Containment Tenperature 2 G )

1

23. Contairunent Water Level (narrow range) 2 G 24 HPS! Flow Cold Leg 1 per cold leg G
25. HPS! Flow Hot Leg 1 per hot leg G
26. Steam Line Pressure 2 per steam generator G
27. Refueling Water Storage Tank Level 2 C (a)

Not required for isolation valves wnose as.sc.ciated penetration is isolated by at least one closed and de.

valveactivated secured.autcmatic valve, closed rnanual valve, blind flange, or check valve with flow through the

( (b) l only one control position room irdication indication channel is required for penetration flow paths with only one installed channel, I }

(c) A channel cortsists of ti.o or rnore core exit thermocouples.

! SAF ONOFRE--UNIT 3 3.3-47 i Amendment No. 116 L

i l , -

r Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.12 Ventilation Filter Testing ' Program (VFTP) (continued) l l

_The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are applicable to the VFTP test frequencies.

5.5.2.13 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:

a. At lease once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-04057-81 has a water and sediment content of less than or equal to 0.05 volume percent, an API gravity or an absolute specific gravity within limits, and a kinematic viscosity @ 40 C of greater than or equal to 4.1 when tested in accordance with ASTM-Ds75-81.

l b. At least once every 92 days by obtaining a sample of fuel oil in accordance with ASTM-D2276-81 and verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-02276-83, Method A.

i l

i i

! i SAN ON0FRE--UNIT 3 5.0-20 Amendment No. 116 I 1

\

l

PAM Instrum:ntation B 3.3.11

, BASES LC0 2, 3.

Reactor Coolant System (RCS) Hot and Cold leg (continued) Temoerature 1

RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long term surveillance.

Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elements and associated transmitters in each loop.

4. Reactor Coolant System Pressure (wide rance) 1 RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity long term surveillance.

The pressure transmitters are located inside the containment. Redundant monitoring capability is provided by two trains of instrumentation.

Operator actions to maintain a controlled cooldown, l such as adjusting steam generator pressure or level, would use this indication. Furthermore, RCS pressup<

is one factor that may be used in decisions to terminate reactor coolant pump operation.

5. Reactor Vessel Water level Reactor Vessel Water Level is provided for i verification and long term surveillance of core l cooling.

The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignment plate. The collapsed level represents the amount of liquid mass that is in the reactor vessel above the core.

(continued)

SAN ONOFRE--UNIT 3 8 3.3-162 Amendment No. 116

1

  • I l

l NPF-10/15-466 1

1 1

l l

l l

i j

W 1

l l

ATTACHMENT "C" (Proposed Specifications)  ;

Unit 2 <

l l

l l

l

  • 1 I

l l

. _ -. _ - _ _. - -. - = _ _ - - _ . _ _ _ _ - _ __

. I PAM Instrumentation {

3.3.11 . l l

2 Table 3.3.11 1 (page 1 of 1)

Post Accident Monitoring Instrunentation l j

l j CONDITIONS REFERENCED FROM REQUIRED FUNCTION

, REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2 G
2. Reactor Coolant System Hot Leg Teaperature ($fta M# gE/uf44 M
3. Reactor Coolant System Cold Leg Tenperature 2"m.-

(,1 penN" G M .

G 2 r ' 7W

! G

4. Reactor Coolant System Pressure (wide range) 2 G
5. Reactor vessel Water Level 2(d) H
6. Containment Stnp Water Level (wide range) 2 G
7. Containment Pressure (wide range) 2 G
8. Containment Isolation Valve Position 2 per g g flow G
9. Contairunent Area Radiation (high range) 2 H
10. Containment Hydrogen Monitors 2 G
11. Pressurizer Level 2 G
12. Steam Generator Water Level (wide range) 2 per steam generator G
13. Condensate Storage Tank Level 2 G 14 Core Exit Tenperature-Quadrant 1 2(c) g
15. Core Exit Temperature -Quadrant 2 2(C) G
16. Core Exit Tenperature-Quadrant 3 2(C) G
17. Core Exit Temperature-Quadrant 4 2(c) g
18. Auxiliary Feedwater Flow 1 per steam generator G
19. Containment Pressure (narrow range) 2 G
20. Reactor Coolant System Subcooling Margin Monitor 2 G  !

1

21. Pressurizer Safety Valve Position Indication 1 per valve G
22. Contairunent Tenperature 2 G
23. Contairunent Water Level (narrow range) 2 G 24 HPSI Flow Cold Leg 1 per cold leg G
25. HPSI Flow Hot Leg 1 per hot les G
26. Steam Line Pressure 2 per steam generator G
27. Refueling Water Storage Tank Level 2 G (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

(d) A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sensors, one sensor in the upper head and three sensors in the lower head are OPERABLE.

SAN ON0FRE--UNIT 2 3.3-47 Amendment No. 127

~

i Prccedures, Prograss, and Manuals 5.5 i

,5.5 Procedures, Programs, and Manuals i

5.5.2.12 Ventilation Filter Testing Program (VFTP) (continued)

The provisions of Technical Specification Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are 4

applicable to the VFTP test frequencies.

5.5.2.13 Diesel Fuel Oil Testing Program This program implements required testing of both new fuel oil and stored fuel oil. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM standards. The purpose of the program is to establish the following:

a. At lease once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample obtained in accordance with ASTM-D4057-81 has a water and i sediment content of less than or equal to 0.05 volume percent,

,,_ an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 9 40 C of greater than or equal to W M-D[T "

' 4.1 when tested in accordance with ASTM-D975-81.

( D405 ~7 -7(

b. At least once every 92 Ways by obtaining a sample of fuel oil 4

in accordance with ASTM 39E275 01 and verifying that particulate contamination is less than 10mg/ liter when checked i

in accordance with ASTM-D2276-83, Method A.

)

i e

d

, SAN ON0FRE--UNIT 2 5.0-20 Amendment No. 127 4

-E N .

1 PAM Instrumentation i B 3.3.11

. BASES 1

l LC0 2, 3. Reactor Coolant System (RCS) Hot and Cold Leo I (continued) Temperature I RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long term surveillance.

Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elementc and associated transmitters # :~r' '^^7 %

4. Reactor Coolant System Pressure (wide rance)

RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity long term surveillance.

The pressure transmitters are located inside the containment. Redundant monitoring capability is provided by two trains of instrumentation.

Operator actions to maintain a controlled cooldown, such as adjusting steam generator pressure or level,  ;

would use this indication. Furthermore, RCS pressure is one factor that may be used in decisions to terminate reactor coolant pump operation.

5. Reactor Vessel Water Level Reactor Vessel Water Level is provided for verification and long term surveillance of core cooling.

The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignment plate. The collapsed level represents the amount of liquid mass that is in the reactor vessel above the core.

(continued)

SAN ON0FRE--UNIT 2 B 3.3-162 Amendment No. 127

NPF-10/15 466 I

I l

l I

ATTACHMENT "D" (Proposed Specifications 1 '

Unit 3 l

l l

k l

l I

l PAM Instrumentation

. 3.3.11 Table 3.3.11-1 (page 1 of 1)

Post Accident Monitoring Instrunentation CONDITIONS REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2 gG
2. Reactor Coolant System Not Leg Temperature 2 -- '. ::; i */ G 2$m Pen- cteam PO)
3. Reactor Coolant System cold Les Tenperature ' r; C gr.) G
4. Reactor Coolant System Pressure (wide range) 2 C
5. Reactor Vessel Water Level 2(d) H
6. Containment Stap Water Level (wide range) 2 C
7. Containment Pressure (wide range) 2 G
8. Contafrument Isolation Valve Position 2 per g g flow G
9. Contairment Area Radiation (high range) 2 H
10. Contairment Hydrogen Monitors 2 G
11. Pressurizer Level 2 G
12. Steam Generator Water Level (wide range) 2 per steam generator G
13. Condensate Storage Tank Level 2 C 14 Core Exit Temperature-ouadrant 1 2(c) g
15. Core Exit Temperature -Quadrant 2 2(C) G
16. Core Extt Temperature -Quadrant 3 2(C) G
17. Core Exit Tenperature-Quadrant 4 2(C) G
18. Auxiliary Feedwater flow 1 per steam generator G
19. Containment Pressure (narrow range) 2 G
20. Reactor Coolant System Sdx:ooling Margin Monitor 2 G 21 Pressurizer Safety Valve Position Indication 1 per valve G
22. Contairment Tenperature 2 G
23. Contairment Water Level (narrow range) 2 G
24. HPSI Flow Cold Leg 1 per cold leg G
25. HPS! Flow Hot Leg 1 per hot leg G
26. Steam Line Pressure 2 per steam generator G
27. Refueling Water Storage Tank Level 2 C (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated auttmatic valve, closed manual valve, blird flange, or check valve with flow through the valve secured.

(b) only one position indication channel is required for penetration flow paths with only one installed control room irdication channel.

(c) A channel consists of two or more core exit thermocouples.

SAN ON0FRE--UNIT 3 3.3-47 Amendment No. 116

t Proce res, Prcgrams, and Manuals l 5.5 b 5.5 Procedures, Programs, and Manuals -

1 5.5.2.12 Ventilation Filter Testing Program (VFTP) .(continued) l The provisions of Technical Specification' Surveillance Requirement 3.0.2 and Technical Specification Surveillance Requirement 3.0.3 are l applicable to the VFTP test frequencies,

, f . ,.... -

5.5.2.13 Diesel Fuel Oil Testing Program >

. & .;n ~ 1 This program implements required testing of both new fuel oil and i stored fuel oil. The program shall include sampling and testing I requirements, and acceptance criteria, all in accordance with applicable ASTM standards. .The purpose of the program is to establish the following
y ~

y~

,: aa  :

l 1

a.

At lease once per 92 days and from new fuel oil prior to addition to the storage tanks by verifying that a sample  !

obtained in accordance with ASTM-D4057-81 has a water and sediment content of less than or equal to 0.05 volume percent, e an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 9 40 C of greater than or equal to u w w h ot. 4.1 when tested in accordance with ASTM-D975-81.

weac ro D4057-7/ ?; o j

, b. At least once every 9 by obtaining 'a ' sample of fuel oil

in accordance with ASTM and verifying that l

i particulate contamination is less than 10mg/ liter when checked l in accordance with ASTM-D2276-83, Method A.

\

1

. 1 l

l SAN ON0FRE--UNIT 3 5.0-20 Amendment No. 116 L_-_____________-_

PA,M Instrumentation B 3.3.11 BASES LCO 2, 3. Reactor Coolant System (RCS) Hot and Cold lea (continued) Temperature RCS Hot and Cold Leg Temperatures are Category I variables provided for verification of core cooling and long term surveillance.

Reactor outlet temperature inputs to the PAMI are provided by two fast response resistance elements and associated transmitters, t ;;;t 1;;;. A

4. Reactor Coolant System Pressure (wide rance)

RCS Pressure (wide range) is a Category I variable, provided for verification of core cooling and RCS integrity long term surveillance.

The pressure transmitters are located inside the containment. Redundant mon:toring capability is provided by two trains of instrumentation.

Operator actions to maintain a controlled cooldown, such as adjusting steam generator pressure or level, would use this indication. Furthermore, RCS pressure is one factor that may be used in decisions to terminate reactor coolant pump operation.

5. Reactor Vessel Water level Reactor Vessel Water Level is provided for verification and long term surveillance of core cooling.

The Reactor Vessel Water Level Monitoring System provides a direct measurement of the collapsed liquid level above the fuel alignment plate. The collapsed level represents the amount of liquid mass that is in the reactor vessel above the core.

(continued)

SAN ON0FRE--UNIT 3 B 3.3-162 Amendment No. 116

Retrieved from "https://kanterella.com/w/index.php?title=ML20113C256&oldid=2811311"