Text

Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11
	ML20148R405
Person / Time
Site:	San Onofre
Issue date:	06/30/1997
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20148R351	List: ML20148R375; ML20148R405;
References
	NUDOCS 9707070384
	Download: ML20148R405 (52)
	v • d • e

1

. 1 NPF-10/15-475 1

l l

4 i

i ATTACHMENT "A" (Existing Specifications) i Unit 2 l

l 9707070384 97 fDR ADOCK0500h1 PDR _.

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.. Im P :,.,g.' i

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(18) Initial Test Program (Section la. SEA)

SCL shall conduct the post-fuel loacing initial test program !

(te.t forth in Section 14 of the San Onofre Units 2 anc !

3 Final Safety Analysis Re' port, as amenced) without r.ating any major mocifications to tnis program unless such modifica.

tions have been icentified anc have received prior WRC approval. Major mocifications are defined as: t L

a. Elimination of any test icentified in Section la of

. i the Final Safety Analysis Repo,rt. as einendec. as being 1 - essential.

b. Modificatf orr'of test objectives. metnoes, or acceptance l

criteria for any test identified in Section la of the Final Safety analysis Report as amencec, as being e ssential . -

c. Performance of any test at a power 1evel different '

Inan that descriced in tne test procedure.

d. Failure to complete any tests incluce in the descriDed program (plannec or scheculed for power levels up to

( ,i the authorized power level). ;

! (19) WUREh-0737 Conditions (Section 22)

( Lach of the following concitions shall be complette to the.

satisfaction of the NRC. Each item references the related -

subpart of Section 22 of the sex anc/cr its supplements.

. a.

Snift Technical Advisor (I. A.1.1. SSER til t

SCE shall provice a fully trained on-shift technical advisor to th! shif t supervisor (watch engineer).

b. Shif t Manning (I. A.l.3. 55ER r1. 55Ed f 5).

SCE shall develop and implement administrative procecures to limit the working hours of incivicuals of the nuclear power plant operating staff who are responsible for manipulatin9 plant controls or for acusting on-line systems ,and equipment affecting plant safety which would have an imediate fr@act on public health anc safety. .

Adequate shif t coverage shall be c.afntainec without routine l

l heavy use of overtime, liowever, in the event that unforesse".

problems require substantial amounts of overtime to l be usec. tae following guidelines shall be followed:

s

] '

l EES J 71982

l 1ov Pever

, l.'

. -s-l

1. An individual shall not be permt ted to weet more then

, , 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-h'our pe riod,. nor ee_re 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 ex:1uding shif t. turnover time).

3. A break of 'at lea:t eight hours shall be allowed between work periods (including snif t turnover time).

' 4. Tne use of overtime shall be considered on an individual basis and not for the entire staff on a safft.

Any deviation from the above guidelines shall be authori:ed by the sittien manager, his deputy the operations manager, or t higher levels of management, in at:ordance with established proc,edures 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 ex:essive hours have no; been assigned'. Routine deviation,from the above guidei tnes it nat authorized.

I c. Indeoendent Sa'fety Enoineerino Grove (I.B.1.2 SSER 'll

~

3CI shall have an on-site independent safety engineering group. '

d..' Procedures for Transients and Accidents (I .C.1. SSIR 81 53*A fl. Abtn Po) *

' By May 1, 1982 SCI thall provide emergency procedure cuidelines-

Emergency proce,dures based on' guidelines approved by the NRC shall be implemented prior to snrtup following the first refueling outage,

e. Procedures for Yerifying Correct Perfore-ance of Oceratino A:uvaties u .c.o, ssta e1)

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

f. Control Room Design

Review (l.D.1. 55IR #1)

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

1.

t

..) Prioritite the control room annunciator vindows.

FEB U 1962

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

. . ..y . ...

RPS Instrumentation--Operating l 3.3.1 1 t SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY 1

SR 3.3. I' '.6 l

-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 2 15% RTP.

u Verify linear power subchannel gains of the 120 days ;

excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs. -)

. 1 i

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 reducin THERMAL POWER I below 1E-4% RTP and o ly if reactor trip circuit breakers (RTC8s) are closed.

Perform CHANNEL FUNCTIONAL TEST on each 30 days on a channel except power range neutron flux.

t. STAGGERED TEST l

BASIS i

I i L SR 3.3.1.8 - - - -1

NOTE-------------------- '

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power range neutron flux channels.

120 days l' (continued) b ~_.

SAN ONOFRE--UNIT 2 3.3-6 Amendment No. 4Gf,133 P

- , , -, - .e w. - . - ,. -w -

RPS Instrumentation--Shutd:wn' 3.3.2 !

f.

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l l

i SR 3.3.2.4 -------------------NOTE .

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION on each 24 months logarithmic power channel, including bypass removal function.

SR 3.3.2.5 Verify RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS

\.

l i

1

\ . ';.

N.

SAN ONOFRE--UNIT'2 3.3-13 Amendment No. 127

l. .

ESFAS Instrumentation

)

3.3.5

.i

'. SURVEILLANCE REQUIREMENTS (continued) .

SURVEILLANCE N

' FREQUENCY SR 3.3.5;2 -

ferform a CHANNEL FUNCTIONAL TEST ESFAS channel. 30 daysof oneach a'-

STAGGERED TEST BASIS SR 3.3.5.3 ,

Perform a CHANNEL FUNCTIONAL TEST120 of each days ESFAS channel bypass removal function.

SR 3.3.5.4 Perform a CHANNEL CALIBRATION of Function

~5, 18 months "

Recirculatic'n Actuation Signal, including bypass removal functions.

SR 3.3.5.5 Perform a CHANNEL CALIBRATION of each ESFAS 24 months channel, with the exception of Function 5, !

including bypass removal functions.

i' SR 3.3.5.6

. Verify ESF RESPONSE TIME is within limits.

24 months on a STAGGERED TEST ;

BASIS '

'SR 3.3.5.7 Perform a CHANNEL FUNCTIONAL TESTonce automatic bypass removal channel.

oil each within 120 days prior to each reactor startup i

i l

SAN ONOFRE--UNIT 2 3.3-25 Amendment No. W,133 i

l . ;

l* ,

~ l

. FHIS 3.3.10 I '

SURVEILLANCE REQUIREMENTS l SURVEILLANCE l FREQUENCY !

I 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 Perfom a CHANNEL FUNCTIONAL TEST on 92 days required FHIS radiation monitor channel. 4 Verify radiation monitor setpoint Allowable Values: j AirborneGaseod5:s6E4cpmabove background.

i 1

1 l

l SR 3.3.10.3 ------------ NOT E------------ -

Testing of Actuation Logic shall include the i l

actuation of each initiation relay and -

verification of the proper operation of each

, ignition relay. . !

( __ _

i

{

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

\

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

required FHIS Manual Trip logic.

l t

SR 3.3.10.5 Perfom a CHANNEL CALIBRATION en required 18 months !

FHIS radiation monitor channel.

l l

i' SAN ONOFRE--UNI 7 2 3.3-43 Amendment No. 127 l

. . PAM Instru:n2ntation

.:.- 3.3.11 Tabla 3.3.11 1 (pag 31 of 1)

, Post Accident Monitoring Instrumentation

( .

CONCITICNS REFERENCED FROM i FUNCTION RECUtRED !

RECU1 RED CHANNELS ACTICN F.1

.* .- j

1. I Excore Neutron Flut 2 G

2. Reactor Coolant System Hot leg Tempwature 2 (1 per steam G ;

generator) l

3. Reactor Coolant System Cold Log Tempwature 2 (1 per steam G gencator)

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

5. Reactor Vessel Watw Levd 2(d) H

6. Containment Sump W,etw Level (wide range)

2 G

7. Containment Pressure (wide range) 2 G 8.

Containment toolation Valve Positian 2 per p agn flow G l

9. Containment Area Radiation (high range) 2 H

10. Containment Hydrogen Mc.nitors 2 O

11. Pressurtzer Level l 2 G '

12. Steam Gen water Watw Level (wide range) 2 per steam genwater G

13. Condensate Storege Tank Level )

2 O f 14 Core Exit Temperature - Quadrant 1 i 2(*I O

15. Core Exit Tempwature - Quadrant 2 I

2*I 'G 1

i

16. Core Exit Temperature - Cuadrant 3 1 2(*) G

17. Core Exit Temperature - Quadrant 4 2(*I G

18. Auxf!!ary Feedwatw Flow .

1 per steam genwater G

19. Containment Pressure (narmw range) 2 G !

20. Reactor Coolant System Subcooling Margin Monitor i 2 0

21. Pressurtzer Safety Valve Position Indication 1 per vaive G

22. l Containment Temperature 2 G

23. Containment Water Level (narrow range) \

2 G

24. HPSI Flow Cold Log 1 pc cold leg G

25. HPS1 Flow Hot Leg 1 per hot leg G

26. Steam Une Pressure 2 per steam generator G 27 RefueGng Water Storage Tank Level 2 O (a)

Not requireo tot isotauon varves wnose associateo penetranon is isoiateo by at least one closeo and de. activated va!ve secured. automatic valve, closed manual valve, blind flange, or check valve with !!cw through the (b) Onh one position Indication channells required for penetration flow r paths w'th only one insta!!ed control room Indication channel l

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

(d) '

A channel consists of eight sensors in a probe. A channet is CPERABLE if four or more sensors, one se head and three sensors in the lower head are OPERABLE.

SAN ONOFRE--UNIT 2 3.3-47 Amendment No. 4 N ,130

! 1. .

l RCS Loops-H00E S, Loops Filled -

[ .

3.4.7 '

t ACTIONS (continued) _

CONDITION REQUIRED ACTION

.- .- COMPLETION TIM ;

i B. No SDC train /RCS loop B.1 in operation. Suspend ~all Imediately operations involving ;

reduction in RCS t baron concentration.

I !

EN.Q l

B.2 Initiate action to

Imediately t

restore required SDC

.- train /RCS loop to t operation. i SURVEILLANCE REQUIREMENTS

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

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 150% (wide range).

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

, OPERABLE. l I

a l

l i

i l-I SAN ONOFRE--UNIT 2 3.4-23 Amendment No. 127

l . LTOP System 3.4.12.1 l

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature 5 256*F LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isolated or I

depressurized to less than the limit specified in Figure 3.4.3-2 and at least one of the following overpressure protection systems shall be OPEPABLE:

a.

The Shutdown Cooling System Relief Valve (PSY9349) with:

~

1) A' lift setting of 406 10 psig,

2) Relief Valve isolation valves 2HV9337, 2HV9339, 2HV9377, and 2HV9378 open, -

or,

b. The Reactor Coolant System depressurized with an RCS vent of greater than or equal to ,6 square inches.

APPLICABILITY: MODE 4 when the temperatu e of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, MODE 5, and

MODE 6 when the head is on the reactor vessel.

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

SIT isolation or depressurization to less than the Figure 3.4.3-2 limit is only required when SIT pressure is greater than or equal to the maximum RCS pressure for the existing l

RCS cold leg temperature allowed by the P/T limit curves provided in Figure 3.4.3-1 and Figure 3.4.3-2.

l L-SAN ONOFRE--UNIT 2 3.4-30 Amendment No. 127 l

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

', . gy AFW System 3.7.5

[ SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path and in both steam supply flow ,

steam turbine driven pump,that paths is to notthe locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 ---- '

NOTE-- - ---

Not required to be performed for the .

turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam generators.

Verify the developed head of each AFW pump 31 days on a at the flow test point is greater than or STAGGERED TEST <

equal to the required developed head. BASIS k.

SR 3.7.5.3 -----

NOTE- --- -- -

Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam generators. -

Verify each AFW automatic valve actuates to 24 months the correct position on an actual or simulated actuation signal when in MODE 1, 2, or 3 except valves HV-8200 and HV-8201.

(continued) i ki-,

t SAN ONOFRE--UNIT 2 3.7-14 Amendment No.127

, - AFW System 3.7.5 l '

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR '3.7.5.4 --------- ---NOTE-----------

Not required to be performed for the 24 months ;

^

turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam generators. !

l Verify each AFW pump starts automatically on an actual or simulated actuation signal I l

when in MODE 1,.2, or 3. .

SR 3.7.5.5 Verify the proper alignment of the required Prior to AFW flow paths by verifying flow from the entering MODE 2 condensate storage tank to each steam whenever unit generator.

has been in

, MODE 5 or 6 for

> 30 days i.

i, i

t h

l l

s, ,

SAN ONOFRE--UNIT 2 3.7-15 Amendment No. 127

. Procedures, Programs, and Manuals !

5.5 i 5.5 Procedures, Programs, and Manuals 5.5.2.8.

Primary Coolant Sources Outside Containment Program (continued)i i

system (post-accident sampling return piping only). The program shall include the following: ,

a. :

P'reventive maintenance and' periodic visual inspection requirements; and i

~

b. .

Integrated cycle leak or intervals test requirements for.each system at refueling less.- j 5.5.2.9 Pre-Stressed concrete Containment Tendon Surveillance Program ,

This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its l!

corrosion protection medium, to ensure containment structural integrity. Program itself is relocated to the LCS. a 1

5.5.2.10 Inservice Testing Program This program provides controls for inservice testing of ASME Code t

, Class 1, 2, and 3 components including applicable supports. Program i itself is relocated to the LCS. -

\

5.5.2.11- Steam Generator (SG) Tube Surveillance Program i

This program provides controls for monitoring SG tube degradation.

Each SG shall be demonstrated OPERABLE by meeting the requirements !

of. Specification 5.5.2.11 and by meeting an augmented inservice - i inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:

a. SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG specified in Table 5.5.2.11-1.

b. SG Tube Sample Selection and Inspection The SG tube minimum sample size in:pection result ;

i classification, and the correspo,nding action required shall be ;

as specified in Table 5.5.2.11-1. . The inservice inspection of SG tubes shall be performed at the frequencies specified in j Specification 5.5.2.11.e and the inspected tubes shall be verified acceptable per the acceptance criteria of 3 Specification 5.5.2.11.f. The tubes selected for each l inservice inspection shall include at least 3% of the total l

s.

4 (continued) ;

SAN ONOFRE--UNI; 2 5.0-13 Amendment No. 127

_ _ _- __.._,_. _- _ . . . . _ ~ . . - _ . _ _ - . _ _ _ _ _ __ ._ _ . . _ _ . . . _ . __

a-Procedures, Programs, and Manuals

i. 5.5

~

5.5 Procedures, Programs, and Manuals (continued)

.. 5.5.2.11 Steam Generator Tube Surveillance Program TABLE 5.2.11-1 (page 1 of 1)

STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS 1st sample Inspection 2nd sample Inspection 3rd Septe Inspection ~

sample size Action Action Result Recs. sired Action Result septred Result Required A miniasm of C1 tone i

s tubes per M/A N/A N/A l N/A SG C2 Plug C-1 i

! Nane N/A N/A defective l tubes and Flug ;

inspect an W/A N/A '

defective additional 25 t@es and I

tt6es in this C1 N/A j

! inspection an SG i additionat 4s C2 Plug l

te ms in this defective

! SG. tees.

C3 Perform action for <

C 3 result of first sample.

C-3 Perfons N/A N/A action for '

C 3 result of first sam le.

C-3 Inspect att Att other SCs Nane M/A N/A teos in this C1

SG, plug defective - I t

' te es and same sGs C 2 Perform l'

inspect 23 M/A N/A but no other action for t e es in each is C 3 C-2 result of l other sG. second

~

Motification t

to stC Aaditional sc Inspect att l-pursuant to is C-3 j tubes in each N/A N/A 10CFR50.r2 i SG and plus 1

defectives.

l 118 0s Notification

! to Nac "

pursuant to 10CTRSO.72.

i S = 3 N/n % Where N is the number of SGs in the unit and n is the number of !

i SGs inspected during inspection period.

(continued)_

SAN ONOFRE--UNIT 2 5.0-18 Amendment No. 127

NPF-10/15-475 ATTACHMENT "B" (Existing Specifications)

Unit 3 l

RPS Instrumentation--Operating 3.3.1 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 2 15% RTP.

Verify linear power'subchannel gains of the 120 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 irclude 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 30 days on a channel except power range neutron flux. STAGGERED TEST BASIS SR 3.3.1.8 -------------------NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 120 days range neutron flux channels. l (continued) l l

SAN ONOFRE--UNIT 3 3.3-6 Amendment No. MG,122

. .. ,_ m .. . . __-..m . . _ _ . _ , _ . . _ . _ . . _ _ . _ . . _ . . _ _ _ . _ . _ . ~ . _ . . . . _ . . _ . . _ _ . _ . _ _ _

. RPS Instrumentatien-Shutdown 3.3.2 !

it SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l .

r SR 3.3.2.4 -------------------NOTE--------------- '

Neutron detectors are excluded from' CHANNEL CALIBRATION. ,

i Perform a CHANNEL CALIBRATION on each 24 months ,

logarithmic power channel, including bypass !

l removal function. !

i*

SR 3.3.2.5 Verify RPS RESPONSE TIME is within limits. i 24 months on a ;

STAGGERED TEST BASIS '

.5

i i i I

l t SAN ON0FRE--UNIT 3 3.3-13 Amendment No. 116

. . - - - .-.. -.. .- ---..-.- _ .-.-. - --..--.-..--.-._.~.--.

4- ESFAS Instrumentation l 3.3.5

SURVEILLANCE REQUIREMENTS (continued) .

! ~

' SURVEILLANCE

.- FREQUENCY .!

r. .. ,.

SR 3.3.5.2' Perform a CHANNEL FUNCTIONAL TEST of each 30 days on a ESFAS channel.

' STAGGERED TEST BASIS L

SR 3.3.5.3 Perform a CHANNEL FUNCTIONAL TEST of each 120 days ,

ESFAS channel bypass removal function.

~

I l

i i

SR 3.3.5.4 t

!' Perform a CHANNEL' C' LI8 RATION of Function 18 months !

l 5, Recirculation Actuation' Signal, includi'ng bypass removal functions. !

l l

SR 3.3.5.5 Perform a CHANNEL CALIBRATION of each ESFAS24 months channel, with the exception of Function 5, -

including bypass removal functions. ,

l I l

SR 3.3.5.6 Verify ESF RESPONSE TIME is within limits.*

24 months on a l STAGGERED TEST BASIS !

SR 3.3.5.7 Perform a CHANNEL FUNCTIONAL TEST on each Once within automatic bypass removal chan'nel. 120 days prior to each reactor 1

startup I

Verification of the RESPONSE TIME of the 30 subgroup relays identified in the February 18, 1997 Edison letter is not applicable until return to Mode 4

(.

from the Unit 3 Cycle 9 refueling outage, with the additional' commitments made in,the February 18, 1997 letter. The safety justification for not !

performing this testing is also included in the February 18, 1997 letter. .i !

l l

l 1

SAN ONOFRE--UNIT 3 3.3-25 Amendment No. !!!,122,127

._. -.- . ~ _ . . _ _ _ _ . _ _.. _ _ ._..... _ _ . _ . - . . _ . _ _ . - _ _ _ . _ . _ . _ _ _ .

FHIS ;I 3.3.10 j SURVEILLANCE REQUIREMENTS 1 SURVEILLANCE -. ,

. FREQUENCY !

SR 3.3.10.1 a Perform a CHANNEL CHECK on required FHIS !

radiation monitor channel. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I !

1 l

l SR 3.3.10.2 k l Perform a CHANNEL-FUNCTIONAL TEST on 92 days

required FHIS radiation monitor channel. l Verify radiation monitor. setpoint Allowable i

Values:

! , Airborne Gaseous: s 6E4 cpm above i background.

l I

4 SR 3.3.10'3 ------

--NOT E----------------

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

verification of the proper operation of each ignition relay.

\ i-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

! require ^d FHIS Manual Trip logic.

)

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

1 l

l 5

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

PAM Instrumentation l

,a .

3.3.11. !

Table 3J.11 1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONCmCNS unRENCEo racM ,

FUNCTION REQUIRED REQtFRED CHANNELS ACTION F.I . I

l. i. Escore Neuemn Fhat !

1 2 G

2. Reactor Coolant System Hot Leg Temperature 2 (! per steam G generator) .

l

3. Reactor Coolant System Cold Leg Temperature !

2 (1 per steam G e l

generator) 4 Reactor Coolant System Pressure (wide range) 2 G i S. Reactor vesselWater Level

! 2(4 H .

6. ' Containment Sump V(ater Level (wide range) 2 0

7. Containment Pressure (wide range) ' 2 0 i

8. Containment isolation Valve Position 2 per peneg Sow G

9. Containment Area Radiation (high range) 2 H i

10. Containment Hydrogen Monitore 2 0 .

11. Pressurtter Level

! 2 G

12. Steam Generator Water Level (wide rangs)

2 per steam generator G

13. Condensate Storage Tank Level 2 G '

14. Core Exit Temperature -Quadrast 1 2(*) G

. 15. Core Exit Temperature - Quadrant 2 2(4 G

16. Core Exit Tempwature - Quadrant 3 2(*I G 17 Ct.,re Exit Temperature -Quadrant 4 ht(*) G

18. Auxiliary Feedwater Flow 1 per steam gene,retor 'G

19. Containment Preneure (narrow range) 2 G

20. Reactor Coolant System Subcooling Margin Monitor 2 0 21 Preasurtter Safety Valve Position Indication 1 per valve G

22. Containment Temperature 2 G

23. Chment Water Level (narrow range) 2 G 24 IiPSI Flor Cold Leg 1 per sold leg ' O

25. HPSIFlow Het Leg 1 per hot leg . G

26. Steam Une Pressure 2 per steam generator G

27. Refueling Water Storage Tank Level 2 G I

ta; Not requirec tot isotation varves wnose assocasteo penetrauon a notaneo ey at le ut one cioseo and de.ectivated automatic valve, closed manual valve. blind Sange, or check valve with Sow through the valve secured.

l I

(b) Only ons ;osition Indication channel is required for penetration Sow paths with only one Installed '

control room Indication channet . -.

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

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 h.ed and ihree onsors in the lower head are OPERABLE SAN ONOFRE--UNIT 3 3.3-47 Amendment No. 4 M ,119

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

CONDITION %

REQUIRED ACTION

.. COMPLETION TIME M

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

. boron concentration.

! AND B.2 Initiate action to Innediately restore required SDC train /RCS loop to operation.

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

SR 3.4.7.2 ,

Verify required SG secondary side water level is 150% (wide range). 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months j

SR 3.4.7.3

' Verify the second required RCS loop, SDC 7 days train or steam generator secondary is

, OPERABLE.

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

i .

r

. ,LTOP System 1 3.4.12.1 '

[ 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System I RCS Temperature s 246*F LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isolated or i depressurized to less than the limit specified in Figure !

3.4.3-2 and at least one of the following overpressure '

J protection systems shall be OPERABLE:

a.

. The Shutdown Cooling System Relief Valve (PSV9349) with:

j

1) A lift setting of 406 10 psig, i' 2)

Relief Valve isolation valves 3HV9337, 3HV9339* 3HV9377' and 3HV9378 open, or, a

b. i The Reactor Coolant System depressurized with an RCS vent of !

greater than or equal to 5.6 square inches.

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, f

MODE 5, and .

MODE 6 when the head is on the reactor vessel.

i

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

SIT isolation or depressurization to less than the Figure 3.4.3-2 limit is only required when SIT pressure is greater

than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves

^

provided in Figure 3.4.3-1 and Figure 3.4.3-2.

SAN ON0FRE--UNIT 3 3.4-30 Amendment No. 116

AFW System'

/ 3.7.5 t

, SURVEILLANCE REQUIREMENTS ,

SURVEILLANCE FREQUENCY.

SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path and in both steam supply flow steam turbine driven pump,that paths is to notthe locked, sealed, or otherwise secured in l

! position, is in the correct position.

~

SR 3.7.5.2 NOTE -- ------

Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam -

generators. -

Verify the develop ~ed head of each AFW pump 31 days on a i at the flow test point is greater than or STAGGERED TEST equal to the required developed head. BASIS t

t SR 3.7.5.3 NOTE------ ------------

Not required to be performed for the '

turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam '

generators.

Verify each AFW automatic valve actuates to 24 months the correct position on an actual or simulated actuation signal when in MODE 1, 2, or 3 except valves HV-8200 and HV-8201.

(continued) l l

C

\

SAN ONOFRE--UNIT 3 3.7-14 Amendment No. 116

AFW System 3.7.5 ;

} [ l SURVEILLANCE REQUIREMENTS (continuad) j SURVEILLANCE FREQUENCY SR 3.7.5.4

NOTE------------------- 24 months Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam generators.

j Verify each AFW pump starts automati ly on an actual or simulated actua signal when in MODE 1,. 2, or 3.

SR 3.7.5.5 Verify the proper alignment of the required 1

AFW flow paths by verifying flow from the Prior to !

entering MODE 2 1 condensate storage tank to each steam generator. whenever unit 4 has been in M00E 5 or 6 for

> 30 days 1

E, 4

SAN ONOFRE--UNIT 3 3.7-15 Amendment No. 116

. Procedures, Programs, and Manuals 5.5 '

5.5 Procedures, Programs, and Manuals 5.5.2.8 Primary Coolant Sources Outside Containment Program (continued) system (post-accident sampling return piping only). The program shall include the following: i i

a. Preventive maintenance and periodic visual inspection i

requirements; and i' b.

Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.2.9 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. Program itself is relocated to the LCS.

5.5.2.10 Inservice Testing Program

)

This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. Program j itself is relocated to the LCS. '

5.5.2.11 Steam Generator (SG) Tube Surveillance Program This program provides controls for monitoring SG tube degradation.

Each SG shall be demonstrated OPERABLE by meeting the requirements of Specification 5.5.2.11 and by meeting an augmented inservice inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:

a. SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG specified in Table 5.5.2.11-1.

4

b. SG Tube Sample Selection and Inspection The SG tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.5.2.11-1. The inservice inspection of SG tubes shall be parformed at the frequencies specified in

. Specification 5.5.2.11.e and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.2.11.f. The tubes selected for each inservice inspection shall include at least 3% of the total (continued)

SAN ONOFRE--UNIT 3 5.0-13 Amendment No. 116

. . j

l Procedures, Programs, and Manuals i

5.5 '.

5.5 Procedures Programs, and Manuals 1

(continued) 5.5,.2.11 i Steam Generator Tube Surveillance Program TABLE 5.2.11-1.(page I of 1) 1 STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS i 1st sar9te Inspection 2-d sangte Inspection l 3rt! Casple Inspection i

1 sample size Action Result Required Action Action Result Required assult Required A minisus of C1 None s ethes per .. N/A N/A I N/A sG N/A C-2 Plus C-1 mane defective N/A N/A tthes and plug Inspect an N/A N/A additional 25 unfective ttbes in this tthes and C1 N/A SG inspection an i additional 43 C2 Plug I ttbes in this defective SG.

tubes.

C3 Perform 1 action for {

C 3 result of 1 first saepte.

C3 Perform N/A - N/A action for ,

C 3 result of

) first sapple. !

%*3 Inspect att Att other SGs l

None N/A tthes in this C-1 N/A SG, plug defective tthes and Some SGs C-2 Perform inspect 23 N/A N/A but no other action for tubes in each is C-3 other SG. C 2 result of second Notification -

to NRC pt.rsuant to Additional SG Inspect all

' isC3 tihes in each N/A loCFRso.72 N/A SG and plug defectives.

tthes Notification to kRC pursuant to sacrRso.72.

S - 2 '4/n % Where N is the number of SGs in the unit and n is the numb SGs inspected during inspection period.

(continued)

SAN ONOFRE--UNIT 3 5.0-18 Amendment No.116

4 NPF-10/15-475 4

)

ATTACHMENT "C" (ProposedSpecifications)

Unit 2

Ud ?%.

l , , -

(' I (18) _ Initial Test Program (Section 14. SER)

. 501. shall conduct the post-fuel loading initial test program (s.tt forth in Section 14 of the San Onofre Units 2 and

- 3 Final Saft:y Analysis Report, as amenced) witncut r.ating any major mocifications to tnis program unless such modifica- .

tions have been 1

ntified anc have received prior WRC i

approval. Major socifications are defined as:

. a. Elimination of any tist identified in Section la of j_

the Final Safety Analysis Repo.rt. as einendec. as being t.

- essential.

b.

Modification of test objectives. methocs, or acceptance l

l criteria for any test ideatified in Section la of the Final Safety calysis Report, as amenoec as being essential. -

l .

. c. Performance of any test at a power level cifferent snan that cescrioed in tne' test procedure.

d. Failure to coe.plete any tests inclueec in the cescrited program (plannec or scheCuied for power 1tvt1s up to 7 ,)

the autnerized power level).

(1g) wuRf.h-0737 Conditions (Section 22).

Each of the following concitions shall be completes to the.

satjsfaction of the NRC. Each item references the related

subpart of Section 22 of the SIx anc/or its suppiesents. .

l . . a. Shif t Technica1 Advisor (I. A.1.1. SSEk #1)

, . l SCE sha11 provice a fully trained on-shift technical ,

%lska aavisor to the shift supervisor (watch engineer). 7i!

b.4 (Shif t Manning (I. A.1.3. SSER rl. SSER E5).

i SCE shall develop and implement administrative procecures to limit the working hours of individuals of the nuclear ;

power piant operating staff who are responsible for manipulating '

plant controls or for adjusting on-line systems.and equipment i

affecting plant safety which would have an teraediate impact i on public besith anc safety. .

~

Adequate shift coverage shall be s.afntainec without routine

, heavy use of overtime. However. in the event that unforest?"'

3 rob) ems require substantial amounts of overtime to l ,- [e usec. tne following guidelines shall be followed: a EEB j 71c82

. . - . . . -. ~ _ . - . . . ~ - - _ _ - . . . - -- . -

.. t:

. 7:. , .

1 4- -

l

). .

r :

, 1. An individual shall net be permitted to work mere then :

16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (ex:1uding shif t turnover time).

{

2. An individual : hall not be permitted to work mere than

~

15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months in any 24-hourperied, nor :_ e than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hcur period, ner more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any

, seven day period (all er:1uding shif t. turnover time) .

\

3. A break of at lea:t eight hcurs shall be alloed between work periads (including snif: turnover time).

~

4. Tne use of overtime shall be c:nsidered on an indiiidual basis and,ne f:r the entire staf f on a shift.

Any deviation fr:m the above guidelines shall be authori:ed'by tne sta:icn manager, his deouty, the :perations manager, or higher levels of management, in ac:ordance with established i procedures and with documentation of the basis f:r grantir.g i the deviation. Controls shall be included in the pr::edu es such that individual overtime will be reviewed monthly by the sta:fon man'ager or his designet to assure that ex:essive hours have not been assigned. R:utine devia f =n. ft: . the at:ye quideiines is no: authorf:ed. 1 I c. Indeoendent Sa'fety Encineerino Group (I.B.1.2. SSER 41) 3CE shall have an on-site independent safety engineering group. -

i d..' Procedures for Transients and A::idents (l .C.1. 55ER 'h 5na re . 55:.5 rs)

By May 1,1982, SCI t, hall provide emergency procedure cuidelines. ;

Emergency procedures based on' guidelines approved by the NRC '

shall be implemented prior to snrtup following the first refueiing outspe.

e. Procedures for Yerifying Correct Performance of Operatine i

Activities ti .c.6. 55L A P 1 )

. Prior to fuel leading, SCE shall i:nple:nent a system i:r verifyini the correct performance of operating activities, and shall keep :.he system in effect thereaf.er.

f. Control Room Design' Review (I.O.1. SSER fil Prior to ex:eeding five ,(5) percent power, SCI shall-

1. Prioriti:e the control room annunciatsr windows.

FEB G 1962

~

4 RPS Instrumsntation--Operating 3.3.1 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 115% RTP.

Verify linear power subchannel gains of the 120 days

- excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.

SR 3.3.1.7 --------------- NO T E S---------------

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 k'. .

below IE-4% RTP and only if reactor trip circuit breakers (RTC8s) are closed.

,s Perform CHANNEL FUNCTIONAL-TESon each 30 days on a '

channel ::::;t ;r::r -- ;- --"Ttr:. F .. 0.* STAGGERED TEST I.

A A BASIS' l:

A -

SR 3.3.1.8 -------------------NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 120 days range neutron flux channels. ll (continued) k..; .

SAN ONOFRE--UNIT 2 3.3-6 Amendment No. 447, 133 4

I,

l RPS Instrumentation-Shutdown

! 3.3.2

(' SURVEILLANCE REQUIREMENTS (continued) l SURVEILLANCE FREQUENCY.

~

I SR 3.3.2.4 -------------------NOTE-------------------

Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION on each 24 months j logarithmic power channel, including bypass removal function.

SR 3.3.2.5 Verify RPS RESPONSE TIME is within limits. 24 months on a i STAGGERED TEST BASIS I mf

' . . . . . . . A)o T r , - , . -

l'

^

l

! pe.n k 44ee%s n ue W A-l

'l N. '

j i

k I

! i l s, ;

l-SAN 0NOFRE--UNIT 2 3.3-13 Amendment Nc. 127

,,.-m -e s- w- -

4

ESFAS Instrumentation

, '?' 3.3.5 SURVEILLANCE REOUIREMENTS (continued)

SURVEILLANCE ~

FREQUENCY SR 3.3.5'.2 )

Perform a CHANNEL FUNCTIONAL TEST of30each ESFAS channel. days on a i

STAGGERED TEST !

EASIS SR 3.3.5.3 Perform a CHANNEL FUNCTIONAL TEST of each 120 days ESFAS channel bypass removal function.

y % * -

SR 3.3.5.4 Perform a CHANNEL CALIBRATION of Function 18 months

5. Recirculation Actuation Signal, H' 'A - t - : 1 Er. d ;c. . O W ;p::: j

% A J ;

SR 3.3.5.5 Perform a CHANNEL CALIBRATION of each24 ESFAS

=cnths channel, with the exception of Functica 5, including bypass removal functions. .

l 1

SR 3.3.5.6 Verify ESF RESPONSE TIME is within limits.

24 months on a STAGGERED TEST BASIS SR 3.3.5.7 Perform a CHANNEL FUNCTIONAL TEST ononce eachwithin i'

automatic bypass removal channel.

120 days prior to each reactor startup i

=

i l

=

SAN ONOFRE--UNIT 2 3.3-25 Amendment No. W,133

i

, I FHIS- \

3.3.10 -

I SURVEILLANCE REQUIREMENTS SURVEILLANCE

. FREQUENCY 1

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' .

j

_ SR 3. 0.2

. Perform a CHANNEL FUNCTIONAL TEST on 92 days M # f a.P^ " ' ~ recuired FHIS radiation monitor channel.

iA ce saativ u_,ifyg9:t#r

,P ver

u. it:r ::t-+t "1:d1:

r

-a g %; ; -- "

v N Airborne Gaseous:g<ce; O r :kc:'--

b an-,,,.,a . - s k p a n.t j l &~ l M es 4"*

x n s w- x <

SR 3.3.10.3 ----------NOTE----------------

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

' :ridie= H an the proper operation of each mitiattw - i;;itic,c. relay.

( , _

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

4 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.

I SAN ONOFRE--UNIT 2 3.3-43 Amendment No. 127

'.- ~

9am PAM Instrumentation 3.3.11 Trili 3.3.11 1 (page 1 of 1)

Poet Accident Monitoring Instrumentainn f CCNCrnCNS REFERENCED FRCM FUNCTION REQUtRe REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2 G

2. Reactor Coolant System Hot Leg Temperature 2 (1 per steem G generator) {

3. Reactor Coolant System Cold Leg Temperature 2 (1 per steem G 1 generator) 4, Reactor Coolant System Pressure (wide range) 2 G

5. An~r_Vmel Wedevel -- 2(d) H

6. Conainmenteeng$N,ats' Level (wide range) 2 G 1

7. Contamment Pressur ~~

? G

8. Containment isolation Vane Positfor: 2 per penetration flow G l path (a)(b)

9. Containment Area Radiat!on (high range) 2 H 1

10. Containment Hydrogen Monitors 2 G

11. Pressurtzer Level 2 0

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

13. Condensate Storage Tank Level

2 O i

14 Core Exit Temperature -Quadrant 1 2(c) G

15. Core Exit Temperature - Quadrant 2

. 2(C) G

16. Core Exit Temperature - Cuadrant 3 2(*) G

17. Core Exit Temperature - Quadrant 4 2(*) G

18. Auxiliary Feedwater Flow .

1 per steam generator G

19. Containment Pressure (narrow range) 2 G

20. Reactor Coolant System Subcoormg Margin Monitor 2 G

21. Pressurtzer Safety Vahre Position Indication 1 per valve G

22. Containment Temperature 2 0

23. Containment Water Level (narrow range) 2 0 24 HPSI Flow Cold Leg 1 per cold leg G 2L HPSI Flow Hot Leg 1 per hot leg G 2$. Steam Line Pressure 2 per steam generator G

27. Refueling Witer Storage Tank Level 2 G (a) Not requireo tor noiauon valvei. wnose associa:eo pene:raton as asoiateo ey at least one closee and de.ectivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indleadon channelis required for penetration flow paths with only one instatted control room indication channel I

(

... (c) A channet consists of two or rnore core exit thermocouples.

(d) A channel consists of eihht sensors in a probe. A channel is O.*ERABLE if four or more sensors, one sensor in the h.cd and thre. sensors in in. iower head are OPERABLE.

~

SAN ONOFRE--UNIT 2 3.3-47 Amendment No. 4M,130

e *

-. RCS Loops-MODE 5, loops Filled 3.4.7 i f,

ACTIONS (continued) '

CONDITION REQUIRED ACTION COMPLETION TIM B. No SDC train /RCS loop B.1 Suspend all in operation. Imediately operations involving reduction in RCS baron concentration.

. AND B.2 Initiate action to Imediately restore required SDC j

train /RCS loop to '

operation.

SURVEILLANCE REQUIREMENTS

~

SURVEILLANCE FREQUENCY ;

SR 3.4.7.1 Verify at least one RCS loop or SDC train

)

, is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

__ y -- ~v - w_ m ,

SR 3.4.7.2 Verify re i ed SG secondar 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I level is _ OY. (wide range)y side water 2 7 ^ _ _ - ~ - -

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

i SAN ONOFRE--UNIT 2 3.4-23 Amendment No. 127

LTOP System' i 3.4.12.1

(

3.4 REACTOR COOLANT SYSTEM (RCS) l 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature s 256*F LCO 3.4.12.1 No more than two high pressure safety injection pumps shall

be OPERABLE, the safety injection tanks shall be isolated or depressurized to less than the limit specified in Figure

- 3.4.3-2 and at least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift. setting of 406 10 psig,

2) Relief Valve isolation valves ZHV9337, 2HV9339, 2HV9377, and 2HV9378 open, or, b.

The Reactor Coolant System depressurized with an RCS vent of greater than or equal to 5.6 square inches.

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, MODE 5, and ,

y _

~ ,

MODE 6 when the head is on the reactor vessel..A tu it.cs ;1 ac+ vaaf*4 -

NOTE------------== & ---

SIT isolation or depressurization to less than the. Figure- ;

3.4.3-2 limit is only required when SIT pressure is greater !

than or equal to.the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in Figure 3.4.3-1 and Fi 3.4.3-2.

gure ------------------

t i

i I

L ,.

l l._

SAN ONOFRE--UNIT 2 3.4-30 Amendment No. 127 l

~. - . - _ _ _ _ - _ . . . , _ --

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

i g., ' \

AFW System 3.7.5

[ ' '

. SURVEILLANCE REQUIREMENTS SURVEILLANCE l

~

FREQUENCY j

SR 3.7.5.1 Verify each AFW manual, power operated, and

, 31 days automatic valve in each water flow path and i in both steam supply flow .

steam turbine driven pump, thatpathsis notto the locked, sealed, or otherwise secured in 1

position, is in the correct position.

i

~~'

SR 3.7.5.2 --

NOTE- - - - - - -

Not required to be performed for the .

< turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

after reaching 800 psig in the steam

generators.

i

Verify the developed head of each AFW pump 31 days on a at the flow test point is greater than or STAGGERED TEST equal to the required developed head. BASIS I.

SR 3.7.5.3 - - - - ----

NOTE -- -

Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

after reaching 800 psig in the steam generators.

Verify each AFW automatic valve actuates to 24 months the correct position on-an actual or l

simulated actuation signal : '; ."00: /'

J 2, e. ^r except valves HV-8200 and HV-8201.

.n -

(continued) l l

SAN ONOFRE--UNIT 2 3.7-14 Amendment No. 127 m

r_.. ._ . - + , . - - _ .

._ _ - . . _ . - . y .--

- AFW System' ,

3.7.5 l i .

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.5.4 -------------------NOTE------ --------

Not required to be performed for the 24 mcnths ;

turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reachin generators.. g 800 psig in the steam t

Verify each AFW pump starts automatically

> on an actual or simulated actuation signal ah;.' "00:1,2,:r?.*"

^ _

^ #

5 SR 3.7.5.5 Verify the proper alignment of the required Prior to AFW flow paths by verifying flow from the entering MCDE 2 condensate storage tank to each steam whenever unit generator, j- has been in

MODE 5 or 6 for 3 > 30 days 4

i 1

i' SAN ONOFRE--UNIT 2 3.7-15 Amendment No. 127

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

! Procedures, Programs, and Manuals

! 5.5 5.5 Procedures, Programs, and Manuals I

5.5.2.8 Primary Coolant Sources Outside Containment Program (continued) system (post-accident sampling return piping only). The program shall include the following:

a.

Preventive maintenance and periodic visual inspection requirements; and b.

Integrated cycle leak or intervals testless.

requirements for each system at refueling 5.5.2.9 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its corrosion protection medium, to ensure containment structural intecritt@ % s eed.~;r:,m ttself 4 r rQcated tn N t ts, 5.5.2.10 Inservice esting Program y uspdio~ od This program provides controls for, inservice testing n of ASME Code Class 1, 2 and 3 components including applicable supports. /rogram itself is located-te,the LCS.

% %~

y A rke.

]

5.5.2.11 _

Steam Generawr (Suj .uve surveisaance Program This program provides controls for monitoring SG tube degradation.

Each SG shall be demonstrated OPERABLE by meeting the requirements of Specification 5.5.2.11 and by meeting an augmented inservice inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:

a. SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG specified in Table 5.5.2.11-1.

b. SG Tube Sample Selection and Inspection The SG tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.5.2.11-1. The inservice inspection of SG tubes shall be performed at the frequencies specified in Specification 5.5.2.11.e and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.2.11.f. The tubes selected for each inservice inspection shall include at least 3% of the total

%e (continued)

SAN ON0FRE--UNIT 2 5.0-13 Amendment No. 127

. j y ,

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals i

(continued) v y --- .

5.5.2.11 Steam Generator Tube Surveillance Program

s. 5.1. Il -I TABLE 4 Wpage 1 of 1) _

! STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS 1st sample Inspection !

2nd ==te Irwoection 3rd sample Inspection !

sample size Action Result Recesired Action Action Result Resp. tired tesult Required A minimus of C-1 None 5 th per . N/A N/A N/A N/A SG C-2 Plug - 1 C-1 None l defective N/A N/A tthes and Plug f Inspect an N/A N/A l defective i additional e 2$

ytthesinthis tthes and C-1 N/A 1

j SG inspection an )

additional As C2 Plug l tthes in this defective sG. e.hes.

C-3 Perders l action for C-3 result of first sample.

i C3 Perform N/A N/A action for C 3 result of first ' supt e.

1 C-3 Inspect att Att other sss Nane N/A I

tthes in this C1 N/A l sG, plug defective tthes and same SGs C-2 Perform Inspect 25 but no other M/A N/A tthes in each action for is C-3 C 2 result of other SG.

second s

to NRC # !

pursuant.,to

} Ackfitional is C-3 SG Inspect all '

,--e- -

I tthes in each N/A N/A soc S 8t 50.*O, '-

gg g pg l defactives.

M Notification to NaC 4 4

j C*d' ._ . l l

5 = 3 N/n % Where N is the number of SGs in is the number of SGs inspected during inspection period.

4 (continued)

SAN ONOFRE--UNIT 2 5.0-18 Amendment No. 127

l n

NPF-10/15-475 I

i l

l I

l l

ATTACHMENT "D" (ProposedSpecifications)

Unit 3 l

l l

\

l l .

l ' RPS Instrumentation--Operating-

\

I 3.3.1 i

l t SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.6 -------------------NOTE--------------------

l 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.

t

! Verify linear power subchannel gains of. the 120 days excore detectors are consistent with the values used to establish the shape annealing matrix elements in the CPCs.

l - - .

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 t.

logarithmic pcwer 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.

-- g , -

Perform CHANNEL FUNCTIONAL TEST on each 30 days on a channel - ce;t y... . .a 3 ,, s e . . . 'i. .Ls STAGGERED TEST f A_ BASIS SR 3.3.1.8 -------------------NOTE--------------------

Neutron detectors are excluded from the CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION of the power 120 days range neutron flux channels. l l

(continued) 4 SAN ONOFRE--UNIT 3 3.3-6 Amendment No. F14,122 i

RPS Instrumentation-Shutdown l 3.3.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY-SR 3.3.2.4 ------------------ NO T E-------- -- - - -- ----- 4 Neutron detectors are excluded from CHANNEL CALIBRATION.

Perform a CHANNEL CALIBRATION on each 24 months logarithmic power channel, including bypass removal function.

i

~ '

l 4 SR 3.3.2.5 Verify RPS RESPONSE TIME is within limits.

l 24 months on a l l

STAGGERED TEST l BASIS v N f .

.. . v ore . . . . . . . . .

I Won eGks4ws a etMd.. *

{

i l

l

, ~

SAN ON0FRE--UNIT 3 3.3-13 Amendment No. II6 i

. w ESFAS Instrumentation 3.3.5

( SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.2 Perform a CHANNEL FUNCTIONAL TEST of each 30 days on a ESFAS channel. STAGGERED TEST BASIS SR 3.3.5.3 Perform a CHANNEL FUNCTIONAL TEST of each 120 days ESFAS channel bypass removal function.

v v v ... 3- x l

SR 3.3.5.4 Perform a CHANNEL CALIBRATION of Function 18 months 5, Recirculation Actuation Signal, f-? $ ; 5;n: :::::' frct*- : 9 A A A / "

SR 3.3.5.5 Perfonn a CHANNEL CALIBRATION of each ESFAS 24 months channel, with the exception of Function 5, -

including bypass removal functions.

(

SR 3.3.5.6 Verify ESF RESPONSE TIME is within limits.* 24 months on a i STAGGERED TEST BASIS , j SR 3.3.5.7 Perform a CHANNEL FUNCTIONAL TEST on each Once within automatic bypass removal channel. 120 days prior to each reactor ;

startup

Verification of the RESPONSE TIME of the 30 subgroup relays identified in the February 18, 1997 Edison letter is not applicable until return to Mode 4 from the Unit 3 Cycle 9 refueling outage, with the additional commitments made in.the February 18, 1997 letter. The safety justification for not performing this testing is also included in the February 18, 1997 letter.

SAN ONOFRE--UNIT 3 3.3-25 Amendment No. 115,122,127

1, FHIS 3.3.10 1 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.'

i SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST on MP ,h. Q reouired FHIS radiation monitor channel.

92 days i acc e . W' 4 4 .

uaVerif ...yb. _ di:t b.. :r!ter n t,.,. 'c.t A11 rd!: '-

j q @; ; - --~~

v i

~

N -

. h,-6 Airborne Gaseous: s/AL4.ft' 5:' 1... dr;;

kh

.ep,<u.t r

( elemeh'n;.d." se+%I m * ~ y ous

( Am/Me 4p, /_, GU k!N se *A! OC467=

A 's h A/

" SR 3.3.10.3 -

- NOT E------ ---

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

" " ic2+ #

the proper operation of each I

m.'tioiiew -f7 1t S ? relay. !

=

(

= -

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

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

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

=

l l

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

- - - - - .~ . _ .- ._- . _ -- - - - ~ . ~.

PAM Instrumentation

, , 3.3.11-Table 3.111 1 (pege 1 of 1)

Post Accident Monitoring instrumentation CCNCACNS REFERENCED FROM l REQUIRED '

FUNCTION REQUIRED CHANNELS ACTION F.1 l 1. Excore Neutron Flu

2 G t 1 '

2. Reactor Coolant Systeat Hot Leg Temperature 2 (1 per steam G l generator) l

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 Wake t avel , 2(d) g j

6. Containment Qatar Level (wide range) , 2 l~ . G i

7. Ce.% '..;-.% Pressure (wide range) 2 G

8. Containment Isolation VaAre Position 2 per penetration flow G path l*NDI

9. Containment Area Radiation (high range) 2 H

10. Containment Hydroger Monitors 2 G

{

11. Pressurfter Level 2 0

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

, 13. Condensate Storage Tank Level 2 G

., 14 Core Ed Temperature - Quadrant 1 2(*) G

15. Core Ed Temperature Quadrant 2 2(CI G

16. Core Ed Temperature -Quadrant 3 2(*) G 17 Core EdTemperature -Quadrant 4 2(*) G,

18. Auxmary Feedwater Flow 1 per steam generator G

19. Containment Pressure (narrow range) 2 G

20. Reactor Coolant System Subcooling Margin Mordter 2 0

21. Pressurtter 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. HPSt Flow Hot Leg 1 per hot leg G

25. Steam Une Pressure 2 per steam generator G

27. Refueling Water Storage Tank Level 2 G (a; twot requireo for isoiacon vasves wnose associateo penevanon is isoiateo by at seast one cioseo and de-activated automatic valve. closed manual valve, blind f!ange, of check valve with flow through the l valve secured.

l (b) Only one posrtion Indication channelis required for penetration flow paths with only one installed control room Indication channet * .

l

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

r (d) A channel consists of eight sensors in a probe. A channelis OPERABLE if four or more sensors, one sensor in the upper heed and three sensors in the lower head a.re OPEFABLE.

SAN ONOFRE--UNIT 3 3.3-47 Amendment No. -1M,119

4 t

RCS Loops-MODE 5, Loop 5 Filled '

1 3.4.7 c ACTIONS (continued)

CONDITION REQUIRED ACTION i COMPLETION TIME _

i . .

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

in operation. Immediately operations involving reduction in RCS

i.

baron concentration.

4 S

B.2 Initiate action to Imediately restore required SDC j train /RCS loop to operation.

i s _

1 SURVEILLANCE REQUIREMENTS -

4 SURVEILLANCE

, FREQUENCY i

SR 3.4.7.1 Verify at least one RCS loop or SDC train j

is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months I

N N 5

v vv -

' { SR 3.4.7.2 Verify re i d SG secondary' side water i level is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months s0% wide A M ( ^ range). A.

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

d f

4 1

.m SAN ONOFRE-UNIT 3 3.4-23 Amendment No.' 116

. .-. - . .. . . . - . . - . - . . - .-- _ - . - . . - . . . - . . . . . ~ , . ~ ..

e.

LTOP System l

3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 1 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature s 246*F i l LCO 3.4.12.1 i'

No more than two high pressure safety injection pumps shall' be OPERABLE, the safety injection tanks shall be isolated or ,

l depressurized to less than De limit specified in Figure 3.4.3-2 and at least one of tne following overpressure protection systems shall be OPERABLE:

a.

The Shutdow.i Cooling System Relief Yalve (PSV9349) with:

l

1) A liff setting of 406 10 psig, l 2) Relief Valve isolation valves 3HV9337, 3HV9339' 3HV9377*

and 3HV9378 open,

or, b.

The Reactor Coolant System depressurized with an RCS vent of greater than or equal to 5.6 square inches.

i

. l APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, MODE 5, and - =

.y- ^

MODE 6 when the head is on the reactor vesselMM R83 D

. - _ __C___, , t_n A-SIT isolation or depressurization to less than the Figure 3.4.3-2 limit is only required then SIT pressure is greater than or equal to the maximum RC3 pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in Figure 3.4.3-1 and Figure 3.4.3-2.

m a,

. SAN ONOFRE--UNIT 3 3.4-30 Amendment No. 116

, .n

, 4

.. c. "

AFW System' 3.7.5

. SURVEILLANCE REQUIREMENTS

)

'. SURVEILLANCE FREQUENCY 1

SR 3.7.5.1 Verify each AFW manual, power operated, and 31 days automatic valve in each water flow path and in both steam supply flow

. steam turbine driven pump,that paths is to notthe locked, sealed, or otherwise secured in positian, is in the correct position.

SR 3.7.5.2 -

"'" NOTE Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam -

generators.

Verify the developed head of each AFW pump 31 days on a at the f?ow test point is greater than or STAGGERED TEST equal to the required developed head. BASIS

)

SR 3.7.5.3 ------

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

Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam ,

generators.

x, - -

Verify each AFW automatic valve actuates to 24 months the corre,ct position on an actual or l

simulatec ctuation signal 2.;.. ;.. rGC '," '

S 0, e.1 except valves HV-8200 and HV-8201.

w (continued) i .,

i C.

SAN ONOFRE--UNIT 3 3., 1 -

Amendment No. 116 1

l .

.j AFW System 3.7.5 i ,.

SURVEILLANCE REQUIREMENTS (continued)

(

SURVEILLANCE FREQUENCY SR 3.7.5.4 -------------------NOTE-------------------- 24 months Not required to be performed for the turbine driven AFW pump until 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after reaching 800 psig in the steam ;

generators. l v _ -

Verify each AFW pump starts automatically l 1

on an actual or simulated actuation signal

h;.. L. ".^;; ', 2, .. ;.L ,,

i

x. - P '

SR 3.7.5.5 Verify the proper alignment of the required Prior to AFW flow paths by verifying flow from the entering MODE 2 condensate storage tank to each steam whenever unit generator. '

has been in M00E 5 or 6 for i

> 30 days 1

)

h i

j

, i l 1 1

I i

l !

4 i

SAN ONOFRE--UNIT 3 3.7-15 Amendment No. 23':

s e Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals i

1 l i 5.5.2.8 I Primary Coolant Sources Outside Containment Program (continued) l system (post-accident sampling return piping orly). The program l shall include the following: ,

a.

Preventive maintenance and periodic visual inspection requirements; and b.

Integrated cycle leak test intervals requirements for each system at refueling or less.

5.5.2.9 Pre-Stressed Concrete. Containment Tendon Surveillance Program

! This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its corrosion protection medium, to ensure containment structural in+^ f + . " v3 ram useH is rei g + tk LN ,

5.5.2.10 c% e d Inservice 4T sting Program k 4 %~ad inservice n testing of ASME Code This1,program class providesinclu 2 and 3 components controls for$ing applicable #rogramsupp I

5.5.2.11 itself is located 4e rthe LCS.

'y x

. [%.

-j

){ ;

Steam menEnuri5y is L veM r_ rugram \

This program provides controls for monitoring SG tube degradation.

Each SG shall be demonstrated OPERABLE by meeting the requirements of Specification 5.5.2.11 and by meeting an augmented inservice inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:

a. SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG '

specified in Table 5.5.2.11-1.

b. SG Tube Sample Selection and Inspection The SG tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 5.5.2.11-1. The inservice inspection of SG tubes shall be performed at the frequencies specified in

. Specification 5.5.2.11.e and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.2.11.f. The tubes selected for each inservice inspection shall include at least 3% of the total

- (continued)

SA!: ONOFRE--UNIT 3 5.0-13 Amendment No. G6

}

. \

,;- Prccedures, Programs, and Manuals !

5.5 l

5.5 Procedures, Programs, and Manuals (continued) ,

l

5. m Gene Tube 5 11ance Program s s.2. ii. i TABLE :.:.11 (page 1 of 1) !

A A < -

STEAM GENERATOR TUBE INSPECTION j SUPPLEMENTAL SAMPLING REQUIREMENTS ,

1st Sample Inspection 2nd Sarrple Inspection l 3rd Sample Inspection Action Action Action i Sample Site RestJit RegJired Result Required Result RecpJired l I

A minimus of Cal None -

N/A N/A N/A N/A

"^

S tubes per SG C2 Plug C.1 None N/A N/A

[ defective

(( tiens arvi inspect an Plug defective N/A C1 N/A ;

1 l additional #. 2.8 nbes and N/A ttbes in this inspection an SG additional 43 C-a Plus j ttbes n this defe-C3 Perform action for C 3 result of first sample.

N/A C3 Perform N/A action for C-3 result of first sample.

C-3 Inspect all All other SCs None N/A .N/A

- tubes in this C1 SG P l ug e

defective ttbes and Some SCs C 2 Perfors N/A N/A i inspect 25 but no other action for ttb 5 in each is C-3 C 2 result of other SC. second Notification

sasc "le.

to NRC Additional SG Inspect all k pursuant to is C 3 t h in each ( N/A N/A McPN54rPE. SG and plug l toCFit50.*73 defectives.

{

[ ""**

i M { Notification k I

k to NPC I

[ pursuant to toc 3k W i+ -

S = 3 N/n % Where N is the number of SGs in tne unit and n is the number of SGs inspected during inspection period.

(continueu)

SAN ONOFRE--UNIT 3 5.0-18 Amendment No. 116 I

I

ML20148R405

Text

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