Text

Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7
	ML20151W680
Person / Time
Site:	San Onofre
Issue date:	09/10/1998
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20151W656	List: ML20151W652; ML20151W675; ML20151W680;
References
	NUDOCS 9809160069
	Download: ML20151W680 (36)
	v • d • e

.

1 i

l i

1 ATTACHMENT A i

)

1 EXISTING UNIT 2 PLANT LICENSE AND TECIINICAL SPECIFICATIONS WITII RESPECT TO TIIE IlYDROGEN CONTROL SYSTEM i

9909160069 900910 PDR ADOCK 05000361 P

PDR

Low Power

! h.

Reactor Coolant System Vents (II.B.1). SSER #1. SSER #4)

By May 1,1982, SCE shall provide procedures or procedure guidelines for reactor coolant gas vent system operation and testing.

i.

Post-Accident Samolina System (NUREG-0737 Item II.B.3)

The PASS shall be operable and the post-accident sampling program shall be implemented as described in the SCE letter of April 14,1983, and revised by SCE letter of October 2, 1992.

j.

Safety Valve Test Reauirements (II.D.1. SSER #1)

SCE shall conform to the results of the EPRI test program.

By April 1, 1982, SCE shall provide confirmation of the adequacy of the San Onofre 2 RCS safety valves based on a preliminary review of generic test program results.

By July 1, 1982, SCE shall provide evidence supported by test of safety valve functionality for expected operating and accident (non-ATWS) conditions. The testing shall demonstrate that the valves will open and reclose under the expected flow conditions.

By July 1, 1982, SCE shall provide an evaluation of the adequacy of the associated piping and supports at San Onofre 2.

k.-

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

Prior to exceeding five (5) )ercent power, the safety valve position indication system s1all be environmentally and seismically qualified consistent with the component or system to which it is attached, and documentation of this shall be j

provided.

i 1.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #1)

Prior to exceeding five (5) percent power, SCE shall conduct a 48-hour endurance test of all auxiliary feedwater pumps.

)

l 1

l AMENDMENT No. 103

L PAM Instrumentation 3.3.11 CONDITION REQ'JIRED ACTION COMPLETION TIME i

p C.-

NOTE---------

C.1 Restore one channel 7 days Not applicable to to OPERABLE status.

hydrogen monitor channels.

One or more Functions

~

with two required channels inoperable.

l T

D.

Two hydrogen monitor D.1 Restore one hydrogen 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channels inoperable.

monitor channel to OPERABLE status.

u I

E.

Required channel of E.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE or 25 inoperable, status.

F.-

Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C, D Table 3.3.11-I for or E not met..

the channel.

G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AND Table 3.3.11-1.

G2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months H.

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to'the and referenced in NRC in accordance Table 3;3.11-1.

with Specification 5.7.2.

SAN ON0FRE--UNIT 2 3.3-45 Amendment No. 127 l

I

.-__.._.m

PAM Instrumentation 3.3.11 Table 3.3.11 1 (page 1 of 1) post Accident Monitoring Instrumentation CONDITIONS REFERENCEE5 FROM l

REQUIRED FUNCTION.

REQUIRED CHANNELS

?r.T!0N F.1

'f 1.. Excore Neutron FluxL 2

f

2.. Reactor Cociant System Hot Leg Temperature 2 (1 per steam G

generator)

~ 3.

Reactor Coolant System Cold Leg Temperature 2 (1 per steam G

generator)

R

' 4.

ReactorCoolantSystemPressure'(widerange) 2 G

{

5.

Reactor Vessel Water Level 2(d)

H

[

6. ; Containment Sump Water level (wide range).

2 G

~7 Containment Pressure (wide range) 2

'G i

8. - Containment Isolation Valve Position,

G 2 per pene g n flow path I

i 9.

Containment Area Radiation (high range) 2 H

i

10. Containment Hydrogen Monitors 2

G j

f

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 Temperature - Quadrant 1

-2IC)

G l

15. Core Exit-Temperature - Quadrant 2 2(C)

G-16? Core Exit Temperature - Quadrant 3 2(C)

G

17.. Core Exit Temperature - Quadrant 4 2IC)

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

- 21. Pressurizer. Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2

G

-23.

Containment Water Level (narrow range) 2 G

24.' HPSI Flow Cold Leg 1 per' cold leg G

25. - HPSI Flow Hot leg -

1 per hot leg G

26. 1 Steam Line Pressure

- 2 per steam generator G

27. = Refueling Water Storage Tank Level 2

G (a) Not required for isolation valves whose assoctated penetration 15 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.

I (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.

l 5

SAN 0NOFRE--UNIT 2 3.3-47 Amendment No. tet 130

Hydrogen Recombiners 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Hydrogen Recombiners LC0 3.6.7 Two hydrogen recombiners shall'be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One hydrogen A.1

NOTE---------

recombiner inoperable.

LC0 3.0.4 is not applicable.

Restore hydrogen 30 days recombiner to OPERABLE status.

B.

Two hydrogen B.1 Verify by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recombiners administrative means inoperable.

that the hydrogen control function is maintained.

AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

SAN ON0FRE--UNIT 2 3.6-23 Amendment No. 127

Hydrogen Recombiners

{

3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

SR 3.6.7.1 Perform a system functional test for each 24 months hydrogen recombiner.

SR 3.6.7.2 Visually examine each hydrogen recombiner 24 months enclosure and verify there is no evidence of abnormal conditions.

SR 3.6.7.3 Perform a resistance to ground test for 24 months each heater phase.

i I

i SAN ON0FRE--UNIT 2 3.6-24 Amendment No. 127

=

j' l

I t

i i

ATTACllMENT B EXISTING UNIT 3 PLANT LICENSE AND TECIINICAL SPECIFICATIONS WITII RESPECT TO TIIE HYDROGEN CONTROL SYSTEM I

l l

l

._=

Low Poter (17)

NUREG-0737 Conditions (Section 22)

Each of the following conditions shall be completed to the satisfaction of the NRC.

Each item references the related subpart of Section 22 of the SER and/or its supplements.

a.

Procedures for Transients and Accidents (I.C.I. SSER #1.

SSER #2. SSER #5)

Emergency procedures based on guidelines approved by the NRC shall be implemented prior to startup following the first refueling outage that occurs six months or more after NRC approval of the guidelines.

b.

Erocedures for Verifyina Correct Performance of Ooeratina Activities (I.C.6. SSER #1)

Prior to fuel loading, SCE shall implement a system for verifying the correct performance of operating activities, and shall keep the System in effect thereafter.

c.

Control Room Desian Review (I.D.1. SSER #1)

The control room modifications identified as required in Section 22, Item I.D.1 of Supplement No. I to the SER shall be installed and made operational on the schedules identified for each modification in Supplement No. I to the SER.

d.

Post Accident Samolina System (NUREG-0737 Item II.B.3)

The PASS shall be operable and the post-accident sampling program shall be implemented as described in the SCE letter of April 14,1983, and revised by SCE letter of October 2,1992.

I e.

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

The safety valve position indication system shall be environmentally and seismically qualified consistent with the component or system to which it is attached, and documentation of this shall be maintained.

f.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #11)

Prior to exceeding five (5) percent power, SCE shall conduct a i-48-hour endurance test of all auxiliary feedwater pumps. The l

results of the test shall be submitted to the NRC staff.

l l

Amendment No. 92 l

l

PAM Instrumentation 3.3.11 CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE---------

C.1 Restore one channel 7 days

'Not applicable to to OPERABLE status.

hydrogen monitor channels.

One or more Functions with two required channels inoperable.

D.

Two hydrogen monitor D.1 Resto,e one hydrogen 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channels inoperable.

monitor channel to OPERABLE status.

E.

Required channel of E.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status.

F.

Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C, D Table 3.3.11-1 for or E not met.

the channel.

G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AND Table 3.3.11-1.

G.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months H.

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to the I

and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

SAN ON0FRE--UNIT 3 3.3-45 Amendment No. 116 l

PAM Instrumentation 3.3.11 i

i Table 3.3.11 1 (page 1 of 1)

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

Excore Neutron Flux 2

0 2.

Reactor Coolant System Hot leg Temperature 2 (1 per steam G

generator) 3.

Reactor Coolant System Cold Leg Temperature 2 (1 per steam G

generator) 4.

Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor Vessel Water Level 2IdI H

6.

Containment Sump Water Level (wide range) 2 G

1.

Containment Pressure (wide range) 2 G

8. ' Containment Isolation Valve Position 2perpeneggnflow G

path 9.

Containment 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 Temperature - Quadrant 1 2(C)

G

15. Core Exit Temperature - Quadrant 2 2IC)

G

16. Core Exit Temperature - Quadrant 3 2(C)

G

17. Core Exit Temperature - Quadrant 4 2IC)

G

18. Auxiliary Feedwater Flow I per steam generator G

19. Containment Pressure (narrow range) 2 G

20. Reactor Coolent System Subcooling Margin Monitor 2

G

21. Pressuriger Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2

G

23. Containment Water Level (narrow range) 2 G

24. HPSI Flow Cold Leg 1 per cold leg G

i

25. HPSI Flow Hot Leg 1 per hot leg 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.

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

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

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

l l

SAN ON0FRE--UNIT 3 3.3-47 Amendment No. tt6,119 I'

Hydrcgen Recombiners 3.6.7 j

i 3.6 CONTAINMENT SYSTEMS 3.6.7 Hydrogen Recombiners LC0 3.6.7 Two hydrogen recombiners shall be OPERABLE.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i

A.

One hydrogen A.1

NOTE---------

recombiner inoperable.

LC0 3.0.4 is not applicable.

Restore hydrogen 30 days recombiner to OPERABLE status.

1 B.

Two hydrogen B.1 Verify by 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months recombiners administrative means inoperable.

that the hydrogen control function is maintained.

AND B.2 Restore one hydrogen 7 days recombiner to i

OPERABLE status.

)

C.

Required Action and C.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met.

l SAN ON0FRE--UNIT 3 3.6-23 Amendment No. 116

Hydrogen Recombiners 3.6.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Perform a system functional test for each 24 months hydrogen recombiner.

SR 3.6.7.2 Visually examine each hydrogen recombiner 24 months enclosure and verify there is no evidence s

of abnormal conditions.

SR 3.6.7.3 Perform a resistance to ground test for 24 months each heater phase.

1 4

i SAN ON0FRE--UNIT 3 3.6-24 Amendment No. 116

r 1

t i

l 1

l l

ATTACIIMENT C

~ PROPOSED U~ NIT 2 PLANT LICENSE AND TECHNICAL SPECIFICATIONS WITH RESPECT TO THE HYDROGEN CONTROL SYSTEM (redline and strikeout) i-l.

j.-

l Loa Power

! i l

h.

Reactor Coolant System Vents (II.B.1). SSER #1. SSER #4)

By May 1,1982, SCE shall provide procedures or procedure 1

guidelines for reactor coolant gas vent system operation and testing.

1.

Post-Accident Samolina System (NUREG-0737 Item II.B.3)

The PASS shall be operable and the post-accident sampling 3

program shall be implemented as described in the SCE letter of i

April 14,1983, and revised by SCE letter of October 2,1992-,

except for the containment atmosphere hydrogen analyzer, which i

shall not be required.

1 j.

Safetv Valve Test Reauirements (II.D.1. SSER #1)

I SCE shall conform to the results of the EPRI test 3rogram.

By April 1,1982, SCE shall provide confirmation of tie adequacy of the San Onofre 2 RCS safety valves based on a preliminary review of generic test program results. By July 1, 1982, SCE shall provide evidence supported by test of safety (valve i

functionality for expected operating and accident non-ATWS) i conditions. The testing shall demonstrate that the valves will open and reclose under the expected flow conditions.

By July 1,1982, SCE shall provide an evaluation of the adequacy of the associated piping and supports at San Onofre 2.

k.

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

Prior to exceeding five (5) )ercent power, the safety valve position Indication system siall be environmentally and seismically qualified consistent with the component or system l

to which it is attached, and documentation of this shall be provided.

~,.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #1)

Prior to exceeding five (5) percent power, SCE shall conduct a l

48-hour endurance test of all auxiliary feedwater pumps.

l 1

l I

l AMENDMENT No. 103 l

l l

J PAM Instrumentation 3.3.11 i

CONDITION REQUIRED ACTION COMPLETION TIME i

C.

NGTE---------

C.1 Restore one channel 7 days i

nV i. OppiiLGuiC LU to OPERABLE status.

IlJ u l USCll 411Ull i L U T ~

LliGilliC i 3.

One or more Functions with two required channels inoperable.

t i

i b.

INU hly i Uycli illvill LUT h.k kC3 byl C UllC hlJ I USCII

[2 IUui 3 LiiGillic I D lilVpCI GUI C.

Ilivil i L U I bilGlillC 4 LU orcRAai.c s i.G t.us.

l E.

Required channel of E.1 Restore required 7 days functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status.

F.

Required Action and F.1 Enter the Condition Immediately i

associated Completion referenced in Time of Condition C, D Table 3.3.11-1 for i

or E not met, the channel.

l 9

f G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AND l

Table 3.3.11-1.

G.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months l

i H..

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to the i

and referenced in NRC in accordance i

Table 3.3.11-1.

with Specification 1

5.7.2.

i r

SAN ONOFRE--UNIT 2 3.3-45 Amendment No. 127

)

PAM Instrumentation l

3.3.11 i

i Table 3.3.11 1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM 1

REQUIRED I

FUNCTION REQUIRED CHANNELS ACTION F.1 j

1 1.

Excore h tron Flux 2

G 2.

Reactor Coolant System Het Leg Temperature 2 (1 per steam G

generator) 3.

Reactor Coolant System Cold Leg Temperature 2 (1 per steam G

generar:r) 4 Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor Vessel Water Level 2Id)

H 6.

Containment Sump Water Level (wide range) 2 G

{

7.

Containment Pressure (wide range) 2 G

8.

Containment Isolation Valve Pcsition 2 per penegn flow G

path 9.

Containment Area Radiation (high range) 2 H

I 10.

C m oium m % vgu Lu iivi a f

6

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 Temperature - Quadrant 1 2(CI G

15. Core Exit Temperatore - Quadrant 2 2ICI G

ICI

16. Core Exit Temperature - Quadrant 3 2

G

17. Core Exit Temperature - Quadrant 4 2ICI 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. Pressurizer Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2

G

23. Containment 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

G (a) Not required for 1 solation valves whose associated penetration is 1solated 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, 127,130

~

2.

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

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s l'if u l US CII nCLUllIU l eici 3

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l'IV U LJ 1 Gilu c.

ML i A VI1J CGiiDIIiGii RE^UIRED nCiiGii CGM ^LETIGii IIME m

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Unt eiy ui U3Cii n.4

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CLUinbinCi suUpCiGbiC.

LCO,3. G.,' i s nV i.

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bC) k UI C IJul USCil bh bGJ3 i CLUiliu lilCI LU m

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i ATTACIIMENT D PROPOSED UNIT 3 PLANT LICENSE AND TECHNICAL SPECIFICATIONS WITH RESPECT TO THE HYDROGEN CONTROL SYSTEM (redline and strikeout) 1 v

4 4

Low Power !

(17) liUREG-0737 Conditions (Section 22) l Each of the following conditions shall be completed to the satisfaction of the NRC.

Each item references the related subpart of Section 22 of r

the SER and/or its supplements.

a.

Procedures for Transients and Accidents (I.C.1. SSER #1.

SSER #2. SSER #5) l l

Emergency procedures based on guidelines ap) roved by the NRC shall he implemented prior to startup following tie first refueling outage that occurs six months or more after NRC approval of the guidelines.

b.

Procedures for Verifyina Correct Performance of ODeratina r

Activities (I.C.6. SSER #1) i Prior to fuel loading, SCE shall implement a system for verifying the correct performance of operating activities, and shall keep the System in effect thereafter.

c.

Control Room Desian Review (I.D.1. SSER,_f1).

The control room modifications identified as required in Section 22, Item I.D.1 of Supplement No. I to the SER shall be installed and made operational on the schedules identified for each modification in Supplement No. I to the SER.

d.

Post Accident Samolina System (NUREG-0737 Item II.B.3) l The PASS shall be operable and the post-accident sampling program shall be implemented as described in the SCE letter of April 14, 1983, and revised by SCE letter of October 2, 1992:,

exce)t for the containment atmosphere hydrogen analyzer, which shall not )e required.

e.

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

The safety valve position indication system shall be environmentally and seismically qualified consistent with the com)onent or system to which it is attached, and documentation of this s1all be maintained.

f.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #11)

Prior to exceeding five (5) percent power, SCE shall conduct a 48-hour endurance test of all auxiliary feedwater pumps. The results of the test shall be submitted to the NRC staff.

Amendment No. 92 I

.. =

. ~.

l PAM Instrumentation 3.3.11 i

l CONDITION REQUIRED ACTION COMPLETION TIME C.

WGTE---------

C.1' Restore one channel 7 days NUL Oppi i t.G ui C LU to OPERABLE status.

iiJ U I US CII lilUll i LUI' LiiGilllC 4 3.

One or more. Functions

~

with two required channels inoperable.

e o.

I FVU liJdi USCil HlUlli LUI o.1 aC3 LUi C UllC hifdl USCII

((. IlUU 3 3 LIIGillic 6 3 4 liUFCI GU 4 C.

Bilulli LUI L,IIG ililt i LU VFLnMDLL 3LOLU3.

i E.

Required channel of E.1 Restore required 7 days Fonctions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status, i

F.

Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C, B Table 3.3.11-1 for or E not met.

the channel.

G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AND

. Table 3.3.11-1.

G.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1

H.

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to the and referenced in NRC in accordance l

Table 3.3.11-1.

with Specification j

l 5.7.2.

i i

1 I

SAN ON0FRE--UNIT 3 3.3-45 Amendment No. 116

PAM Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

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

Excore Neutron Flux 2

G 2.

Reactor Coolant System Hot Leg Temperature 2 (1 per steam G

generator)

3. ' Reactor Coolant System Cold leg Temperature 2 (1 per steam G

generator)

'4.

ReactorCoolantSystemPressure(widerange) 2 G

5.

Reactor Vessel Water' Level 2Id)

H 6, _ Containment Sump Water Level (wide range) 2 G

~

7.

Containment Pressure (wide range)-

2 G-8.

Containment Isolation Valve Position 2 per penegn flow G

path 9.

Containment Area Radiation (high range) 2 H

G.

Gm i.uom nM yn en i m.

t e

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 Estt Temperature - Quadrant 1 2IC)

G

15. Core Exit Temperature - Quadrant 2 2ICI G

ICI

16. Core Exit Temperature - Quadrant 3' 2

G IC) 17 Core Extt Temperature - Quadrant 4 2

G

18. Auxillary Feedwater Flow I per steam generator G

19. ContainmentPressure(narrowrange) 2 G-

20. Reactor Coolant System Subcooling Margin Monitor 2

G

21. Pressur12er Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2

G

23. Containment Water Level (narrow range)'

2 G

24.'

HPSI Flow Cold Leg 1 per cold leg C

25. HPSI Flow Hot Leg 1 per hot leg 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 penetratton 15 1solated 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.

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

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

l i

SAN'ONOFRE--UNIT 3 3.3-47

' Amendment No. M6,119 j

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ATTACIIMENT E PROPOSED UNIT 2 PLANT LICENSE AND TECliNICAL SPECIFICATIONS WITII RESPECT TO TIIE IIYDROGEN CONTROL SYSTEM 4

i l

l l

- ~ _ ~ _... -

t Low Power l h.

Reactor Coolant System Vents (II.B.1). SSER #1. SSER #4) i By May 1, 1982, SCE shall provide procedures or procedure guidelines for reactor coolant gas vent system operation and testing.

l 1.

Post-Accident'Samolina System (NUREG-0737 Item II.B.3)

The PASS shall be operable and the post-accident sampling program shall be implemented as described in the SCE letter of April 14, 1983, and revised by SCE letter of October 2,1992, except for the containment atmosphere hydrogen analyzer, which shall not be required.

J.

Safety Valve Test Reauirements (II.D.l. SSER #1)

SCE shall conform to the results of the EPRI test program.

By April 1,1982, SCE shall provide confirmation of the adequacy of the San Onofre 2 RCS safety valves based on a preliminary review of generic test program results.

By July 1, 1982, SCE shall provide evidence supported by test of safety valve functionality for expected operating and accident (non-ATWS) conditions. The testing shall demonstrate that the valves will open and reclose under the expected flow conditions.

By July 1,1982, SCE shall provide an evaluation of the adequacy of the associated piping and supports at San Onofre 2.

k.

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

Prior to exceeding five (5) percent power, the safety valve position indication system shall be environmentally and seismically qua11fied consistent with the component or system to which it is attached, and documentation of this shall be provided.

1.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #1)

Prior to exceeding five (5) percent power, SCE shall conduct a 48-hour endurance test of all auxiliary feedwater pumps.

l i

AMENDMENT No.

i 2

-u

-+

"U PAM Instrumentation 3.3.11 i

CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more Functions C.1 Restore one channel 7 days l

with two required to OPERABLE status, channels inoperable.

D.

deleted l

E.

Required channel of E.1 Restore required 7 days functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status, i

F.

Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.11-1 for l

or E not met.

the channel..

G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AMD Tabl e 3.3.11-1.

G.2 Be in MODE 4.

12 haurs H.

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to the and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

i SAN ON0FRE--UNIT 2 3.3-45 Amendment No.

i

L~ <

PAM Instrumentation.

3.3.11 Table 3.3.11 1 (page 1 of 1)

Post Accident Monitoring Instrumentation l

. CONDITIONS REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS

' ACTION F.1

]

l I

1.

Excore Neutron Flux 2

g l

2.

Reactor Coolant System Hot leg Temperature 2 (1 per steam G

generator) l 3.' Reactor' Coolant System Cold Leg Temperature 2(1persteam G

generator).

I 4.

' Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor Vessel Water Level 2(d).

H

6. ' Containment Sump Water' Level (wide range) 2 G

C 7.

Containment Pressure (wide range) 2 G

'8.

Containment Isolation Valve Position 2 per pene g n flow G

path t

,9.

Containment Area Radiation (high r'ange) 2 H

l 10.

deleted

11. Pressurizer Level 2

G i

L

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

j

13. Condensate Storage Tank Level 2

G.'

14. ' Co're Exit Temperature - Quadrant 1 dC) i G 15.-

Core Exit Temperature - Quadrant 2 2(c) g

16. Core Exit Temperature - Quadrant 3 2(C)

G i

17. Core Exit Temperature - Quadrant 4 2IC)

G

'5 l

18. Auxiliary Feedwater Flow 1 per steam generator G-f

19. ContanmentPressure(narrowrange) 2 G

j

- 20. Reactor Coolant System Subcooling Margin Monitor 2

G j

21. Pressurizer Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2

G

.23.

Containment Water. Level (narrow range) 2 G

24 HPS! Flow Cold Leg 1 per cold leg G

25.. HPSI Flow Hot Leg 1 per hot leg G

26. Steam Line Pressure 2 per steam generator G

27. Refueling Water Storage Tank Level 2

G l

(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 l

valve secured.

i.'

l-

' (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.

j (d) A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sensors, one senser in j

'the upper head and three sensors in the lower head are OPERABLE.

j i.

l.

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

1 1

l 1

I I

l l

l I

I I

This page intentionally blank l

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1 I

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l l

1 I

SAN ON0FRE--UNIT 2 3.6-23 Amendment No.

l I

l l

I I

I This page intentionally blank I

I

)

l J

i SAN ON0FRE--UNIT 2 3.6-24 Amendment No.

ATTACIIMENT F PROPOSED UNIT 3 PLANT LICENSE AND TECIINICAL SPECIFICATIONS WITIl RESPECT TO TIIE IIYDROGEN CONTROL SYSTEM l

l l

Low Power (17) NUREG-0737 Conditions (Section 22)

Each of the following conditions shall be completed to the satisfaction of the NRC.

Each item references the related subpart of Section 22 of the SER and/or its supplements.

a.

Procedures for Transients and Accidents (I.C.1. SSER #1.

SSER #2. SSER #5)

Emergency procedures based on guidelines approved by the NRC shall be implemented prior to startup following the first refueling outage that occurs six months or more after NRC approval of the guidelines.

b.

Procedures for Verifyina Correct Performance of Operatina Activities (I.C.6. SSER #1)

Prior to fuel loading, SCE shall implement a system for verifying the correct performance of operating activities, and shall keep the System in effect thereafter.

c.

Control Room Desian Review (I.D.1. SSER #1)

The control room modifications identified as required in Section 22, Item I.D.1 of Supplement No. I to the SER shall be installed and made operational on the schedules identified for each modification in Supplement No. I to the SER.

d.

Post Accident Samolina System (NUREG-0737 Item II.B.3)

The PASS shall be operable and the post-accident sampling program shall be implemented as described in the SCE letter of April 14, 1983, and revised by SCE letter of October 2, 1992, except for the containment atmosphere hydrogen analyzer, which shall not be required.

e.

Direct Indication of Safety Valve Position (II.D.3. SSER #1)

The safety valve position indication system shall be environmentally and seismically qualified consistent with the component or system to which it is attached, and documentation of this shall be maintained.

f.

AFW Pumo 48-hour Endurance Test (II.E.1.1. SSER #11)

Prior to exceeding five (5) percent power, SCE shall conduct a 48-hour endurance test of all auxiliary feedwater pumps.

The results of the test shall be submitted to the NRC staff.

Amendment No.

I

i PAM Instrumentation 3.3.11 CONDITION REQUIRED ACTION COMPLETION TIME j

f C.

One or more Functions C.1 Restore one channel 7 days l

with two required to OPERABLE status.

channels inoperable.

D.

deleted l

i I

E.

Required channel of E.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE i

or '25 inoperable.

status.

i I

. F.

Required Action and F.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.11-1 for l

or E not met.

the channel.

I G.

As required by G.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action F.1 and referenced in AHH Tabl e 3.3.11-1. -

G.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months H.

As required by H.1 Prepare and submit a 30 days Required Action F.1 Special Report to the and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

I SAN ONOFRE--UNIT 3 3.3-45 Amendment No.

r PAM Instrumentation l

.3.3.11 f able 3.3.11 1 (page I of 1)

Post Accident Monitoring Instrumentation l

REFERENCED FROM REQUIRED

+

FUNCTION-REQUIRED CHANNELS ACTION F.1 l

i i

1.

Excore Neutron Flux 2

G j

f'

2.. Reactor Coolant System Hot Leg Temperature 2 (1 per steam G

l 3

generator) 3.

Reactor Coolant System Cold Leg Temperature 2 (1 per steam G

generator)

I 4.

ReactorCoolantSystemPressure(widerange) 2 G

j I

5.

Reactor Vessel Water Level 2(d)

H 6.

Containment Sump Water Level (wide range) 2 G

I i

7.

Containment Pressure (wide range) 2 G

r i G

'8.

Containment Isolation Valve Position 2perpene}agbynflow

path,

}

9.

Containment Area Radiation (high range) 2 H

{

10. deleted l

!!. Pressuriger 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 Temperature - Quadrant 1 2(C)

G

' 15. Core Exit Temperature - Quadrant 2 2(*)

G

'f

16. Core Exit Temperature - Quadrant 3

'2(C)

G

17. ' Core Exit Temperature - Quadrant 4 2(C)

G

18. Auxiliary Feedwater Flow I per steam generator G

[

l l.

19. ContainmentPressure(narrowrange) 2 G

j

[

20. Reactor Coolant System Subcooling Margin Monitor 2

G

[

21. - Pressuriger Safety Valte Position Indication 1 per valve G

22. Containment Temperature 2

G

'23.

Containment Water Level (narrow range) 2 G

i 24 HP51 Flow Cold Leg:

1 per cold leg G

?

25. HPSI Flow Hot Leg 1 per hot leg G

l

26. Steam Line Pressure 2 per steam generator-G j

t l

~27.

Refueling Water Storage Tank Level 2

G

{j

= = = -

D). 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, i

T (b) Only'one position indication channel is required for penetration flow paths with only one installed f

control room indication channel.

i

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

t (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.

{

I t-i

\\'

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

t

(

'f

r I-1 I

I l

I I

I_

l l

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I This page intentionally blank l

.I I

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1 t

I i

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I I

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I i

SAN ONOFRE--UNIT 3 3.6-23 Amendment No.

l i

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This page intentionally blank l

1 l

l SAN ONOFRE--UNIT 3 3.6-24 Amendment No.

l

ML20151W680

Text

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