Text

Proposed Tech Specs,Reinstating Provisions of Current SONGS TS Revised as Part of NRC Amends 127 & 116
	ML20112D461
Person / Time
Site:	San Onofre
Issue date:	06/03/1996
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20112D441	List: ML20112D436; ML20112D451; ML20112D461;
References
	NUDOCS 9606040330
	Download: ML20112D461 (36)
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_

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

Unit 2 l

i 9606040330 960603 l

PDR ADOCK 05000361 p

PDR j

I 3

.Im Power (18)

Initial Test Program (Section 14. SER)

SCL 'shall conduct the post-fuel loading initial test program (set forth in Section 14 of the San Onofre units 2 and 3 Final Safety Analysis Report. as amended) without making any major modifications to this program unless such modifica-tions have been identified and have received prior WRC approval. Major modifications are defined as:

Elimination of any test identified in Section 14 of a.

the Final Safety Analysis Report. as amended as being essential.

b.

Modification of test objectives. rethocs, or acceptance criteria for any test identified in Section 14 of the Final Safety Analysis Report. as amenoed. as being essential.

j Performance of any test at a power level different f

l c.

inan that described in tne test procedure.

Failure to complete any tests incluoed in the descrioed d.

program (plannec or scheduled for power levels up to l

the authorized power level).

(19) WUREb-0737 Conditions (Section 22)

Each of the following conoitions shall be completec to the satisfaction of the NRC. Each item references the related subpart of Section 22 of the SER and/or its supplements.

Shif t Technical Advisor (I. A.1.1. SSEk 91) a.

i SCE shall provice a fully trained on-shift technical i

advisor to the shift supervisor (watch engineer).

l:

Shif t Manning (1. A.1.3. SSER el. SSER ES)

T.

b.

SCE shall develop and implement administrative procedures to limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an immediate impact on public health ano safety.

Adequate shift coverage shall be maintained without routine l

heavy use of overtime. However, in the event snet unforeseen I

problems require substantial amounts of overtime to i

be usec. the following guidelines shall be followed-4 FEB J 7 382 9

F

l

,104 Fm er f

.s.

l 1.

An individual shall not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shif t turnover time).

2.

An individual shall not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period (all excluding shift turnover time).

3.

A break of at least eight hours shall be allowed between work periods (including shif t turnover time).

4.

The use of overtime shall be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the station manager, his deputy, the operations manager, or higher levels of management, in accordance With established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the station man'ager or his designet to assure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

Indeoendent safety Encineerino Gruuo (1.B.1.2. SSER 81) c.

SCE shall have an on-site independent safety engineering group.

Procedures for Transients and Accidents (I.C.1 SSER *1, d.

55in 72. 55LA e3)

By May 1,1982, SCE shall provide emergency procedure guidelines.

Emergency procedures based on guidelines approved by the NRC sM1 be implemented prior to startup follodng the first eling outape, i

,:edures for Verifying Correct Performance of Operating e.

Activities (l.C.b. 55ER $ 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.

f.

Control Room Design Review -(1.D.1 SSER #1)

Prior to exceeding five (5) percent power, SCE shall:

1.

Prioritize the control room annunciator windows.

FEB f 7 862 l

l RPS Instrumentation--Operating l

3.3.1 l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.6

NOTE.-------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 215% RTP.

Verify linear power subchannel gains of the 92 days excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.

SR 3.3.1.7

NOTES-------------------

1.

The CPC CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC.

2.

Not required to be performed for logarithmic power level channels' until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reducing THERMAL POWER below 1E-4% RTP and only if reactor trip circuit breakers (RTCBs) are closed.

= -_

Perform CHANNEL FUNCTIONAL TEST on each 92 days channel except power range neutron flux.

SR 3.3.1.8

NOTE----

Neutron detectors are excluded from the CHANNEL CALIBRATION.

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

Perform CHANNEL CALIBRATION of the power 92 days range neutron flux channels.

(continued)

SAN ON0FRE--UNIT 2 3.3-6 Amendment No. 127 1

CPIS 3.3.8 i

i SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

l l

SR 3.3.8.2

NOTE--------------------

I This SR is applicable in MODES 1, 2, 3, and 4 only.

j 1

Perform a-CHANNEL FUNCTIONAL TEST on each 92 days required. containment radiation monitor channel. Verify setpoint is in accordance with the following:

l Containment Gaseous Monitor: s 2X background; Containment Area Gamma Monitor: s 340 mR/hr.

L SR 3.3.8.3

NOTE--------------------

This SR is only applicable during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment.

i Perform a CHANNEL FUNCTIONAL TEST on 92 days required containment radiation monitor I

channel. Verify setpoint is in accordance with the following:

Containment Gaseous l

Monitor: s 2X background; Containment Area Gamma Monitor: s 2.5 mR/hr.

l (continued) l l

SAN ON0FRE--UNIT 2 3.3-37 Amendment No. 127

FHIS 3.3.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform a CHANNEL CHECK on required FHIS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months radiation monitor channel.

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required FHIS radiation monitor channel.

Verify radiation monitor setpoint Allowable Values:

Airborne Gaseous: s 6E4 cpm above background.

l SR 3.3.10.3

NOTE--------------------

~

i Testing of Actuation Logic shall include the actuation of each initiation relay and i

verification of the proper operation of each l

ignition relay.

i l

l Perform a CHANNEL FUNCTIONAL TEST on 18 months i

l required FHIS Actuation Logic channel.

1 SR 3.3.10.4 Perform a CHANNEL. FUNCTIONAL TEST on 18 months required FHIS Manual Trip logic.

l SR 3.3.10.5 Perform a CHANNEL CALIBRATION on required 18 months FHIS radiation monitor channel.

l l

4 1

SAN ON0FRE--UNIT 2 3.3-43 Amendment No. 127

PAM instrumentation 3.3.11 Table 3.3.11 1 (page 1 of )

Post Ace.ident Monitoring Instrunentation l

CONDITIONS REFERENCE 0 FRCN i

FUNCTICN REQUIRED i-REQUIRED CHANNELS ACTION F.1 I

1.

Excore Neutron Flux 2

G 2.

Reactor Coolant system Hot Leg Temperature 2 per loop G

3.

Reactor Coolant System Cold Leg Temperature 2 per loop G

l 4 Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor vessel Water Level 2(d)

H 6.

Containment Sunp Water Level (wide range) 2 G

I 7.

Containment Pressure (wide range) 2 G

8.

Containment Isolation Valve Position 2 per pene g g n flow G

path 1

9.

Containment Area Radiation (high range) 2 H

10. Containment Hydrogen Monitors 2

G l

11. Pressurizer Level j

'2 G

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

13. Condensate Storage Tank Level 2

G V.. Core Exit Temperature-Quadrant 1 2(c) a

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

G j

16. Core Exit Tenperature-Quadrant 3 2(c) g

17. Core Exlt Temperature-Quadrant 4 2(c) l g

18. Auxiliary Feedwater Flow 1 per steam generator G

19. Containment Pressure (narrow range) 2 G

i

20. Reactor Coolant System Subcooling Margin Monitor 2

G

21. Pressurizer Safety Valve Position Indication 1 per valve G

}

22. Containment Tenperature 2

G l

23. Containment Water Level (narrow range) 2 G

24. HPS! Flow Cold Leg 1 per cold leg G

l

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 l

de activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

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

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

l (d) A channet consists of eight sensors in a probe.

A channel is OPERABLE if four or more sensors, one l

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

I i'

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

. ~ _ _ _. _. -

RCS Loops--MODE 5, Loops Filled 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME i

^

B.

No SDC train /RCS loop B.I Suspend all Immediately in operation.

operations involving reduction in RCS boron concentration.

8,N_Q B.2 Initiate action.to Immediately restore required SDC l

train /RCS loop to

[

operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQliENCY SR 3.4.7.1 Verify at least one RCS loop or SDC train 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is in operation.

SR 3.4.7.2 Verify required SG secondary side water 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months level is 2 50% (wide range).

I SR 3.4.7.3 Verify the second required RCS loop, SDC 7 days train or steam generator secondary is OPERABLE.

SAN ON0FRE--UNIT 2 3.4-23 Amendment No. 127

,.,.._,,,----s

._,,.-.4-,

n,--,.

.---...-.---n-.

Refueling Water Level 3.9.6 3.9 REFUELING OPERATIONS t

3.9.6 Refueling Water Level LCO 3.9.6 Refueling water level hall be maintained 2 23 ft above the s

top of reactor vessel flange.

APPLICABILITY:

During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, During movement of irradiated fuel assemblies within containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME i

1 A.

Refueling water level A.1 Suspend CORE Immediately i

not within limit.

ALTERATIONS.

E A.2 Suspend movement of Immediately irradiated fuel i

assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify refueling water level is 2 23 ft 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months above the top of reactor vessel flange.

t l

i

}

SAN ON0FRE--UNIT 2 3.9-10 Amendment No. 127 l

'- '~~

l 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 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 l

requirements, and acceptance criteria, all in accordance with l

applicable ASTM standards. The purpose of the program is to establish the following:

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

l 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 t.n absolute specific gravity within limits, and a kinematic viscosity 9 40 C of greater than or equal to 4.1 when tested in accordance with ASTM-D975-81.

l b.

At least once every 92 days by obtaining a sample of fuel oil l

in accordance with ASTM-D2276-81 and verifying that particulate contamination is less than 10mg/litar when checked in accordance with ASTM-D2276-83, Method A.

l i

i SAN ON0FRE--UNIT 2 5.0-20 Amendment No. 127

NPF-10/15-466 l

ATTACHMENT "B" l

(Existing Specifications) l Unit 3 l

l l

4

RPS Instrumentation--Operating l

3.3.1 l

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

l SR 3.3.1.6

NOTEJ-------------------

Not required'to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 2 15% RTP.

Verify linear power subchannel gains of the 92 days excore detectors are consistent with the values used to establish the shape l

I annealing matrix elements in the CPCs.

I SR 3.3.1.7

NOTES-------------------

1.

The CPC CHANNEL FUNCTIONAL TEST shall

~

include verification that the correct values of addressable constants are l

installed in each OPERABLE CPC.

2.

Not required to be performed for logarithmic power level channels until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reducing THERMAL POWER below 1E-4% RTP and only if reactor trip circuit breakers (RTCBs) are closed.

l Perform CHANNEL FUNCTIONAL TEST on each 92 days channel except power range neutron flux.

i SR 3.3.1.8

NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 92 days l

range neutron flux channels.

1 l

(continued)

SAN ONOFRE--UNIT 3 3.3-6 Amendment No. 116 l

CPIS 3.3.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2

NOTE--------------------

This SR is applicable in H0 DES 1, 2, 3, and 4 only.

Perform a CHANNEL FUNCTIONAL TEST on each92 days required containment radiation monitor channel.

Verify setpoint is in accordance with the following:

Containment Gaseous Monitor: 5 2X background; Containment Area Gamma Monitor: s 340 mR/hr.

SR 3.3.8.3

NOTE== -- - ------------

This SR is only applicable during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment.

i

)

Perform a CHANNEL FUNCTIONAL TEST on 92 days i

required containment radiation monitor channel.

Verify setpoint is in accordance jf with the following:

J Containment Gaseous Monitor: s 2X background; Containment Area Gamma Monitor: s 2.5 mR/hr.

(continued)

SAN ON0FRE--UNIT 3 3.3-37 Amendment No. 116 t

l 1

FHIS 3.3.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i

l l

SR 3.3.10.1 Perform a CHANNEL CHECK on required FHIS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i

radiation monitor channel.

l SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required FHIS radiation monitor channel.

Verify radiation monitor setpoint Allowable Values:

Airborne Gaseous: s 6E4 cpm above background.

SR 3.3.10.3

NOTE--------------------

---=-

Testing of Actuation Logic shall include the actuation of each initiation relay and verification of the proper operation of each ignition relay.

Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Actuation Logic channel.

SR 3.3.10.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Manual Trip logic.

SR 3.3.10.5 Perform a CHANNEL CALIBRATION on required 18 months FHIS radiation monitor channel.

SAN ON0FRE--UNIT 3 3.3-43 Amendment No. 116

PAM Instrumentation l

3.3.11

[

I Table 3.3.11-1 (page 1 of 1) l Post Accident Monitoring Instrunentation l

CONDITIONS REFERENCED FROM REQUIRED FUNCTION

\\

REQUIRED CHANNELS ACTION 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 Temperature 2 per loop G

4.

Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor vessel Water Level 2(d)

H 6.

Contairunent Sump Water Level (wide range) 2 G

7.

Containment Pressure (wide range) 2 G

8.

Contairunent Isolation Valve Position 2 per pene{ g n flow G

path 9.

Containment Area Radiation (high range) 2 H

10. Contairunent 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 IZ '}

G

16. Core Exit Tenperature-Quadrant 3 2(c) g

17. Core Exit Temperature -Quadrant 4 2(c) a

18. Auxiliary Feedwater Flow 1 per steam generator G

19. Contairunent Pressure (narrow range) 2 G

20. Reactor Coolant System Sthcooling Margin Monitor 2

G

21. Pressurizer Safety Valve Position Indication 1 per valve G

22. Contairunent Temperature 2

G

23. Contalrnent Water Level (narrow range) 2 G

24. HPSI Flow Cold Leg 1 per cold leg C

23. 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 automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

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

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

i l

SAN ONOFRE--UNIT 3 3.3-47 Amendment No. 116 l

t

RCS Loops-MODE 5, Loops Filled 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

No SDC train /RCS loop B.1 Suspend all Immediately in operation.

operations involving reduction in RCS boron concentration.

N1Q B.2 Initiate action to Immediately restore required SDC train /RCS loop to operation.

1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify at least one RCS loop or SDC train 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is in operation.

l l

SR 3.4.7.2 Verify required SG secondary-side water 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months level is 2 50% (wide range).

SR 3.4.7.3 Verify the second required RCS loop, SDC 7 days train or steam generator secondary is OPERABLE.

i

(

SAN ON0FRE--UNIT 3 3.4-23 Amendment No. 116

... ~.. - - - - -

I i

t Refueling Water Level i

3.9.6 i-l

.3.9.

REFUELING OPERATIONS 3.9.6 Refueling Water Level 6

j LCO 3.9.6 Refueling water level shall be maintained 2 23 ft above the top of ~ reactor vessel flange.

4 i

i r

APPLICABILITY:

.During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, During movement of irradiated fuel assemblies within i

containment.

ACTIONS l

CONDITION REQUIRED ACTION COMPLETION TIME A.

Refueling water level A.1

~ Suspend CORE Immediately not within limit.

ALTERATIONS.

AND I

A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

)

SR 3.9.6.1 Verify refueling water level is 2 23 ft 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months above the top of reactor vessel. flange.

SAN ONOFRE--UNIT 3 3.9-10 Amendment No. 116

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 Diesel Fuel Oil Testing Program l

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:

i At lease once per 92 days and from new fuel oil prior to i

a.

l 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-0975-81.

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.

l l

i i

SAN ON0FRE--UNIT 3 5.0-20 Amendment No. 116

NPF-10/15-466 l

l 1

l l

i I

i ATTACHMENT "C" l

(Proposed Specifications)

Unit 2 t

I I

1 i

I

'Im Pcm 4

}

(18)

Initial Test Program (Section 14. SER)

J 5

SCL shall conduct the post-fuel loading initial test program i

(set forth in Section 14 of the San Onof re Units 2 and 3 Final Safety Analysis Report. as amenced) witnuut making i

any major modifications to this program unless such modifica-l tions have been ide'ntified and have received prior WRC approval. Major modifications are defined as:

Elimination of any test identified in Section 14 of a.

the Final Safety Analysis Report as amended, as being i

essential.

b.

Modification of test objectives, methocs, or acceptance j

f criteria for any test identified in Section 14 of the 4

l Final Safety analysis Report, as amenoec. as being l

e ssential.

1 Performance of any test at a power level different c.

tnan that described in tne test procedure.

1 d.

Failure to complete any tests incluoed in the describec j

program (plannec or scheduled for power levels up to the authori2ed power level).

(19) NUREb-0737 Conditions (Section 22)

J i

Lach of the following concitions shall be completec to the satisf action of the WRC. Each item references the related 4

3 subpart of Section 22 of the SER anc/or its supplements.

)

Shif t Technical Advisor (I. A.1.1. SSEk #1) a.

1 SCE shall provice a iully trained on-shift technical lt

{

gavisortotheshiftsupervisor(watchengineer).

/

i b.

Shif t Manning (I. A.1.3. SSER el. SSER WS) 4 SCE shall develop and implement administrative procedures l

to limit the working hours of individuals of the nuclear power plant operating staff who are responsible for manipulating i

plant controls or for adjusting on-line systems and equipment affecting plant safety which would have an imediate impact on public healtn anc safety.

1 i

Adequlte shif t Coverage shall be maintainec without routine heavy use of overtime. However, in the event tnet unforesten 5

problems require substantial amounts of overtime to be followed:

pe used, the following Quidelines chall i

)

FEB J 71982

1m Wr j

f _.

An individual shall not be permitted to work more then /

I

}

1.

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shif t turnover time).

2.

An individual shall not be pemitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 7a hours in any 48-ho,ur period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period (all excluding shif t turnover time).

3.

A break of at least eight hours shall be allowed between work periods (including shif t turnover time).

l 4.

The use of overtime shall be considered on an individual t

basis and not for the entire staf f on a shif t.

Any deviation from the above guidelines shall be authorized by or j

the station manager, his deputy, the operations manager, higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime will be reviewed monthly by the station manager or his designee to assure that excessive l

hours have not been assigned. Routine deviation from the above guidelines is not authorized.

y g

Indeoendent Safety Encineerino Groue (1.B.1.2. SSER 81) c.

SCE shall have an on-site independent safety. engineering group.

)

d.

Procedures for Transients and Accidents II.C.1. SSER dl.

55iR r2. 55LR n i By May 1,1982, SCE shall provide emergency procedure guidelines.

Emergency procedures based on guidelines approved by the NRC shall be implemented prior to startup following the first refueling outape, Procedures for Verifying Correct Performance of Operating e.

Activities U.C.6. 55ER el)

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

f.

Control Room Design Review -(!.0.1. 55ER #1)

Prior to exceeding five (5) percent povar, SCE shall:

1.

Prioritize the control room annunciator windows.

FEB 171962

RPS Instrumentation--Operating 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.6

--- - - - - - - -- ---- -- -- N OT Ei-- -- - -- -- -- --- - - - --

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 2 15% RTP.

Verify linear power subchannel gains of the 92 days excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.

SR 3.3.1.7

NOTES-------------------

1.

The CPC CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC.

i 2.

Not required to be performed for logarithmic power level channels until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reducing THERMAL POWER i

below 1E-4% RTP and only if reactor trip circuit breakers (RTCBs) are closed.

_ _=-.______

Perform CHANNEL FUNCTIONAL TEST on each u "92 oays channelcnreant fnwar rance neutron r# W SR 3.3.1.8

NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 92 days range neutron flux channels.

(continued) i I

i SAN ON0FRE--UNIT 2 3.3-6 Amendment No. 127 1

CPIS 3.3.8 e

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2

NOTE--------------------

This SR is applicable in MODES 1, 2, 3, and 4 only.

Perform a CHANNEL FUNCTIONAL TEST on each 92 days required containment radiation monitor channel. Verify setpoint is in accordance with the following:

Containment Gaseous Monitor: I l i n h;n r d ;" "

4 Containment Area Gamma Monitor: s 340 mR/hr.

SR 3.3.8.3

NOTE--------------------

This SR is only applicable during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment.

Perform a CHANNEL FUNCTIONAL TEST on 92 days required containment radiation monitor channel.

Verify setpoint is in accordance with the following:

Containment Gaseous Monitor:-

1" i;; b, _,,J, 9 -C Containment Area Gamma Monitor: s 2.5 mR/hr.

y (continued) 4 4,;p gaf skatt be, s44 s d /s.lant i

a e-at.~/+ p y+ ffPl si u. r w q tw iPM$m, ew 6(e m f

gWtt wverW h oce.u.r.

x.

A SAN ON0FRE--UNIT 2 3.3-37 Amendment No. 127

l I

i l

FHIS i

3.3.10 i

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform a CHANNEL CHECK on required FHIS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months radiation monitor channel.

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required FHIS radiation monitor channel.,

u__4,u

. 24..:

___4.__

_1 K,..

.. 'f g,, b ;~p'~ y ;if'sL yi h" l! f "

< drek +4h kifL'to pvwnf spwi a *Ime=s/&ipt yf i

.m m...~....

oocuu. 2 -.

L * - li e w n e e ss A a w l

Sv4A'sJ+*4 - 1./ b ansvr* en else /Mg ablel *

\\

twt he q secident occ u r.

i i

SR 3.3.10.3

=-

- - = = - -

= NOTE--------------------

Testing of Actuation Logic shall include the i

actuation of each initiation relay and verification of the proper operation of each ignition relay.

j Perform a CHANNEL FUNCTIONAL TEST on 18 months l

required FHIS Actuation Logic channel.

i SR 3.3.10.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months l

required FHIS Manual Trip logic.

SR 3.3.10.5 Perform a CHANNEL CALIBRATION on required 18 months FHIS radiation monitor channel.

SAN ON0FRE--UNIT 2 3.3-43 Amendment No. 127 l

r PAM Instrumentation 3.3.11 1

Table 3.3.11 1 (page 1 of 1)

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

Excore Neutron Flux l

2 G

2.

Reactor Coolant System Hot Leg Temperature 2 Ger tog G

3.

Reactor Coolant System Cold Leg Temperature 2@

G 4 Reactor Coolant System Pressure (wide ranse) 2 G

5.

Reactor vessel Water Level 2(d)

H 6.

Containment Sump Water Level (wide range) 2 C

7.

Containment Pressure (wide range) 2 G

8.

Containment Isolation Valve Position 2 per pene g gn flow G

path 9.

Containment Area Radiation (high range) 2 H

j

10. Containment Hydrogen Monitors 2

G l

11. Pressurizer Level l

2 G

l

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

13. Condensate Storage Tank Level t

2 G

14 Core Exit Temperature-Quadrant 1 2(C)

G

15. Core Exit Temperature -Quadrant 2 2(c) a

16. Core Exit Temperature -Quadrant 3 2(c) a

17. Core Exit Tenperature -Quadrant 4 2(*)

G

18. Auxiliary Feedwater Flow 1 per steam generator G

19. Containment Pressure (narrow range) 2 G

l

20. Reactor Coolant System Subcooling Margin Monitor 2

G

\\

21. Pressurizer Safety Valve Position Indication 1 per valve G

\\

l l

22. Containment Tenperature 2

G 23 Containment Water Level (narrow range) 2 G

t i

24. HPSI Flow Cold Leg 1 per cold leg G

25. HPSI Flow Hot Leg 1 per hot leg G

26. Steam Line Pressure I

2 per steam generator G

j

27. Refueling Water Storage Tank Level 2

G I

)

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

l 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.

(d) A channel consists of eight sensors in a probe. A channel is CPERABLE if four or more sensors, one sensor in the upper head ar4three sensors in the lower head are OPERABLE.

SAN ONOFRE--UNIT 2 3.3-47 Amendment No. 127 d

1 i

1

RCS Loops-MODE 5, Loops Filled 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

No SDC train /RCS loop B.1 Suspend all.

Immediately in operation.

operations involving reduction in RCS boron concentration.

MI!

B.2 Initiate action to Immediately

)

restore required SDC train /RCS loop to operation.

SURVEILLANCE REQUIREMENTS l

SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify at least one RCS loop or SDC train 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is in operation.

SR 3.4.7.2 Verify re i ed SG secondary. side water ~

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months level is 0% (wide range).

SR 3.4.7.3 Verify the second required RCS loop, SDC 7 days train or steam generator secondary is OPERABLE.

SAN ON0FRE--UNIT 2 3.4-23 Amendment No. 127

Refueling Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Refueling Water Level i

LCO 3.9.6 Refueling water level shall be maintained it 23 ft above the W ilM"'"'s Te M,op of reactor g 'gi' Q 'ge.

t el flan

%'iinE of eba '"A~ip~e7 ' M l b........

hwat es now.s

,a m._,.y e.t euw Wcat swk ew s ee tw +6Iy

eves, u

y APPOCABI ITYi "hN h5"YI'YrW^# " "

II

E ' *

-' '"I

~'~~~

us,a._

T ; Lit.: :E ' s = ' ' ' ' " = '" d l

During movement of irradiated fuel assemblies within containment.

a 1 4 of Ad.maan.4f/4s or CE44sa eu. wa wsei&** & "+"

f

- wi sumyw ane$o;t w.n~er u.

s nuk preum wsVi ***-s - k*N'u-ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

l A.

Refueling water level A.1 Suspend CORE Immediately not within limit.

ALTERATIONS.

AND l

A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

i l

1 SURVEILLANCE REQUIREMENTS 1

SURVEILLANCE FREQUENCY

%c SR 3.9.6.1 Ve ify4 refueling water level i., i C TL' 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

.L_...

AL_

A __

d'

.-. _i f1 _ _

_J idhk'Id% T'd '#k2".'4 %T M'""""' ~

.. % ~yweaya.

i l

l SAN ON0FRE--UNIT 2 3.9-10 Amendment No. 127 l

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 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.

", k m

1,_

" from new fuel oil prior to

....7.,

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 y 4 1 when tested in acenrdance with ASTM-D975-81.

Tt.9 IM i<ss h er ey*6 M9 e pag 7 yg b.

AT least once every u aays byg obtaining a sample of fuel oil in accordance with ASTM 0 275 M'and verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

I SAN ON0FRE--UNIT 2 5.0-20 Amendment No. 127

I l

NPF-10/15-466 l

l l

t I

l l

ATTACHMENT "D" (Proposed Specifications)

Unit 3 l

l l

l r

l 1

l 4

l RPS Instrumentation--Operating i

3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.6

NOTE i

Not required'to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER 2 15% RTP.

_____________________________-- =__==_______

Verify linear power subchannel gains of the 92 days excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.

SR 3.3.1.7

NOTES-------------------

1.

The CPC CHANNEL FUNCTIONAL TEST shall include verification that the correct values of addressable constants are installed in each OPERABLE CPC.

2.

Not required to be performed for logarithmic power level channels until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reducing THERMAL POWER below 1E-4% RTP and only if reactor trip circuit breakers (RTCBs) are closed.

Perform CHANNEL FUNCTIONAL TEST on each,,

92 days g

ch annel caveant nnwar -1.ge aa"rrnn r i " -?

SR 3.3.1.8

NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 92 days range neutron flux channels.

(continued) s SAN ON0FRE--UNIT 3 3.3-6 Amendment No. 116

CPIS 3.3.8 SURVEILLANCE RE UIREMENTS(continued)

SURVEILLANCE FREQUENCY SR 3.3.8.2

NOTE--------------------

This SR is applicable in MODES 1, 2, 3, and 4 only.

PerformaCHANNE[.FUNCTIONALTESToneach 92 days required containment radiation monitor channel.

Verify setpoint is in accordance with the following:

i Containment Gaseous I

Monitor: : ? " t a"-d 9 6 Containment Area Gamma Monitor: $ 340 mR/hr.

SR 3.3.8.3

-NOTE- ------------------

This SR is only applicable during CORE ALTERATIONS or during movement of irradiated fuel assemblies within containment.

\\

Perform a CHANNEL FUNCTIONAL TEST on required containment radiation monitor 92 days channel.

Verify setpoint is in accordance with the following:

Containment Gaseous i

Monitor e " " ' ' -

^

Containment Area Gamma Monitor: s 2.5 mR/hr.

=-

mf N

(continued)

A kg kl eiai skall k sef aM p'

d L tv M M eswiev$ alems/ $ $4 k-(

wat s.w i. %

skevid, en). '#n44 W eddAst. h/9 i

1 eco44 r.

i A

A-4 I

J i.

SAN ONOFRE--UNIT 3 3.3-37 l

Amendment No. 116 ll l

FHIS 3.3.10 l

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform a CHANNEL CHECK on required FHIS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months radiation monitor channel.

i s

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on 92 days required FH.IS radiation monitor chan,nel.

,, _ r n. w..,

c,_

$$iU5$. U W k Nih/E[ E /I k set wf6'+1mfgL3A.IlpyeesMapselevaaleems@s34#

l g.g.

.;. ; T : : dr : e Sv$$ % +f % %'isasure.s~ aleem/Q tkauffs f wl heWtiy accido.t occa,.

l SR 3.3.10.3

NOTE--------------------

l Testing of Actuation Logic shall include the i

actuation of each initiation relay and l

verification of the proper operation of each ignition relay.

Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Actuation Logic channel.

SR 3.3.10.4 Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Manual Trip logic.

SR 3.3.10.5 Perform a CHANNEL CALIBRATION on required 18 months FHIS radiation monitor channel.

SAN ONOFRE--UNIT 3 3.3-43 Amendment No. 116

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

Post Accident Monitoring Instrunentation CCNDITIONS REFERENCED FRCH REQUIRED FUNCTION

\\

REQUIRED CHANNELS ACTICN F.1 1.

Excore Neutron Flux 2

G 2.

Reactor Coolant System Hot Lag Tenperature 2@rtooo G

3.

Reactor Coolant System Cold Les Teeperature 2

C 4 Reactor Coolant System Pressure (wide range) 2 G

5.

Reactor Vessel Water Level 2(d)

H 6.

Contairveent Susp Water Level (wide range) 2 G

7.

Containment Pressure (wide range) 2 G

8.

Contairvnent Isolation Valve Position 2 per

g flow G

9.

Contafrusent Area Radiation (high range) 2 H

l

10. Contafrunent Hydrogen Monitors 2

G l

11. Pressurizer Level l.

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 Tenperature-Quadrant 2 ZICI G

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

G

17. Core Exit Tenperature-Quadrant 4 2(c) a 1

18. Auxiliary Feedwater Flow 1 per steam generator G

19. Containment Pressure (narrow range) 2 G

i l

20 Reactor Coolant System Subcooling Margin Monitor 2

G

{

21. Pressurizer Safety Valve Position Indication 1 per valve G

l

22. Containment Tenperature 2

C i

23. Contafrunent Water Level (narrow range) 2 G

24. HPS! Flow Cold Leg 1 per cold leg G

23. HPS! Flow Hot Leg 1 per hot les G

i

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 irdication 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 thermoccuples.

1 SAN ON0FRE--UNIT 3 3.3-47 Amendment No. 116 1

RCS Loops-MODE 5, Loops Filled 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

No SDC train /RCS loop B.1 Suspend all Immediately in operation.

operations involving reduction in RCS boron concentration.

10 B.2 Initiate action to Immediately restore required SDC train /pCS loop to operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE.

FREQUENCY SR 3.4.7.1 Verify at least one RCS loop or SDC train 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is in operation.

SR 3.4.7.2 Verify required SG secondary side water 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months level is &$0% (wide range).

SR 3.4.7.3 Verify the second required RCS loop, SDC 7 days i

train or steam generator secondary is OPERABLE.

l SAN ON0FRE--UNIT 3 3.4-23 Amendment No. 116

1 Refueling Water Level 3.9.6

)

3.9 REFUELING OPERATIONS 3.9.6 Refueling Water Level LCO 3.9.6 Refueling water level shall be maintained 2 23 ft above the

..to.p o f reactor ves l ange..

b elow.........

4..............4 4,. =m=e.f l % e fees.54, h a =w..

23 W le g#%

feve '905 C942, t

(% end : :q'2:j C64 gien eko M et 1%. w,.;GI yedc%"mWf"Lc'ax,ununu-.;,;nt s;;a.,,: car

,:n-unistchinri nf ennten1 rnd drivo chs#&c, During movement of irra.diated fuel assemblies within containmen og A 4 ass 4=k%s ee cfAs w/A & NM4 F88*N.

L Q gh w A44 aassw6ses beh W er1K4 ACTIONS ass ** W s 8d M M

O M"

CONDITION REQUIRED ACTION COMPLETION TIME i

i A.

Refueling water level A.1 Suspend CORE Immediately not within limit.

ALTERATIONS.

AND l

A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY W

SR 3.9.6.I

. '!;i i fy4 refueling water level e b " '+'

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months N C '. A bias bup U [ I CdL k,UI VCbSC b l atiyd.

kA$$ h M4 8

bb m.m eeoks autk.

l l

I j

SAN ON0FRE--UNIT 3 3.9-10 Amendment No. 116 I

L-Procedures, Programs, and Manuals 5.5 i

l 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 l

applicable to the VFTP test frequencies.

5.5.2.13 Diesel Fuel Oil Testing Program i

This program implements required testing of both new fuel oil and i

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 i

establish the following:

i a.

JAo ie...

..J-from new fuel oil prior to r.,

v o,.

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, i

an API gravity or an absolute specific gravity within limits, and a kinematic viscosity 0 40 C of greater than or equal to 4 1 when tested in acenrdan

.P tw6 m em oc p ** )ce with ASTM-D975-81.

l D4067 b.

7st least once every 92 days obtaining a sample of fuel oil l

in accordance with ASTM-020~ - 1 and verifying that particulate contamination is less than 10mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

l t

l l

t SAN ONOFRE--UNIT 3 5.0-20 Amendment No. 116 l

l

<

ML20112D461

Text

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