ML20149L800

Proposed Tech Specs 3/4.7.1.1, Safety Valves, 3.0.4, 3/4.3.2, ESF Actuation Sys Instrumentation, & 3/4.4.4, Steam Generators & Surveillance Requirements 4.0.3 & 4.0.4

ML20149L800
Person / Time
Site:	San Onofre
Issue date:	02/22/1988
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13303A829	List: ML20149L800
References
TAC-66970, TAC-66971, NUDOCS 8802250045
Download: ML20149L800 (180)

Text

e NPF-10/15-228 ATTACHMENT A (EXISTING SPECIFICATION) 8802250045 000222 PDR P ADOCK 05000361 PDR '

TAllLE 3.7-1 z

SIEAM LINE SAFEIY VALVES PER 100P S

?

h C

VALVI NUM8ER tIfI S[lIING (1 1%)* ORIFICE SIZE Line No. I Line No. 2

a. 2PSV-8401 2PSV-8410 1100 psia 16 in2

b. 2PSV-8402 2PSV-8411 1107 psia 16 in2

c. 2PSV-8403 2PSV-8412 1114 psia 16 in2 cl. 2PSV-il404 2PSV-8413 '

1121 psia 16 in2

e. 2PSV-840S 2PSV-8414 1128 psia 16 in2 R

s

f. 2PSV-8406 2PSV-8415 1135 psia 16 in2 7 9 2PSV-8407 2PSV-8416 1142 psia

~ 16 inz

h. 2PSV-840ll 2PSV-1141/ 1149 psia 16 in2

i. 2PSV-8409 2PSV-8418 1155 psia 16 inz A

The lif t setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature achi pressure.

v-re-tr -

.a

• O c.

i

e NPF-10/}S.ggg ATTACHMENT 8 (EXISTING SPECIFICATION) 4

E Z

I

_ S z z 2 2 2 2 2 2 2 n n n n n n n n n E i i i i i i i i i C

I 6 6 6 6 6 6 6 6 6 g F

I 1 1 1 1 1 1 1 1 1 i

n R t O a r

e p

o l

a i

n m

o n

t a

e v

l a

v P e 0 " h

) t 0

1  %

1 f

R o E I s P ( a a a a a a a a a n S G i

s i

s i

s i

s i

s i

s i

s i i o

s s i E N p p p p p p p p p t 1 V I i

- L T 0 7 4 7 A T 1

8 5 2 9 5 d 0 0 1 2 2 3 4 4 5 n V E 1 1 1 1 1 1 1 1 1 o

3 S 1 1 1 1 Y

1 1 1 1 1 c E T I t

1 E f n

8 F I e

A A L i T S b

E m N a I

t o t

M d A n f

i o S p s

e 2 r 0 r 1 2 3 4 5 6 7 8 o 1 1 1 1 1 1 1 o

4 4 4 4 4 4 4 1

4 1

c 4

N 8 8 8 8 8 8 8 8 8 l

- - - - - - - - - l e V V V V V V V V V a n S S S S S S S S S h i

P P P P P P P P P s L 3 3 3 3 3 3 3 3 3 e

re.

ur R su E

ss B es -

M re pr l

i p -

N g 1

E 2 nl e V

1 0 0 3

0 4 5 6 7 8 9 i n 0 0 0 0 0 0 t a L o 4 4 4 4 4 4 4 4 4 t A N 8 8 8 8 8 8 8 8 8 ee V - - - - - - - - - sr e V V V V V V V V V u n S S S S S S S S S tt i P P P P P P P P P f a I 3 3 3 3 3 3 3 3 3 i r l e p

em h e l t D

a. b c d e f g h i

• 5C - ~

$* @?M&3H '" 7 _

4 :  : t ,. ! i l: :! l

NPF-10/15-228 ATTACHMENT C (PROPOSE 0 SPECIFICATION) i 1

l l

l l

1 i

l

s TABLE 3.7-1 STEAM LINE SAFETY VALVES PER LOOP Lift Settina (1 1%)*

1100 psia 1107 psia 1

1114 psia 1121 psia 1128 psia 1135 psia 1142 psia 1149 psia 1155 psia

• The lift setting pressure shall correspond to ambient conditions of the .

valve at nominal operating temperature and pressure.

SAN ONOFRE - UNIT 2 3/4 7-2 -

NPF-10/15-228 ATTACHMENT 0 (PROPOSE 0 SPECIFICATION)

i-TABLE 3.-7-1 STEAM LINE SAFETY VALVES PER LOOP Lift Settina (i 1%)*

1100. psia 1107 psia 1114 psia 1121 psia i 1128 psia l 1135 psia 1142 psia i 1149 psia 1155 psia t

• The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.

I f

i SAN ONOFRE - UNIT 3 3/4 7 2 .

t i

t

-- - - - - - - - , , , ..r. .,, - , - , . _ , , - , , , , , - - , . , . . , , , , , , - - - , . -,- -- --- , ,- . , , ,

DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-10/15-228 This is a request to revise Technical Specification 3/4.7.1.1, "Safety Valves."

Existing Specifications Unit 2: See Attachment A Unit 3: See Attachment B Proposed Specifications Unit 2: See Attachment C Unit 3: See Attachment 0 Description The proposed change would modify Technical Specification 3/4.7.1.1, "Safety Valves" by revising Table 3.7-1 to remove the valve number designations and the valve orifice size for the main steam line code safety valves. This will preclude the necessity of setting a specific valve at a specific setting. The safety analysis assumes that the main steam line code safety valves are set with nine staggered set pressures per loop. There is no basis for specifying which of the nine valves per 1000 is set to a specific lift pressure. The required lift settings will remain unchanged by this revision.

Safety Analysis The proposed changes discussed above shall be caemed to involve a significant hazards consideration if there is a positive finding in any one of the following areas:

1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The purpose of this change is to decouple specific valves from a specific lift setting. In addition, the change removes the valve orifice sizes from the table. The main steam line code safety valve I lift settings assumed in the safety analysis will not be changed.

Therefore, operation of the facility in accordance with this proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

l l

o Respon'se: No The operation of the plant will not be modified by this change. The required main steam line code safety valve lift settings will not be changed. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?

Response: No The main steam line code safety valve lift settings assumed in the safety analysis are not altered by this change. Therefore, the proposed change will not involve a significant reduction in a margin of safety.

The Commission has provided guidance concerning the application of standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideration. Example (i) relates to a change which is a purely administrative change to Technical Specifications:

for example, a change to achieve consistency throughout the Technical Specifications. The main steam line code safety valves are similar in function and purpose to the pressurizer code safety valves. The valve numbers for the pressurizer cude safety valves are not listed in the Technical Specifications. The removal of the valv? designat1cr.s from Table 3.7-1 will not affect the function of the main steam line code safety valves since each specific lift setting assumed .n the safety analysis will still be required.

The proposed change may be considered to provide consistency throughcut the Technical Specifications since it removes the valve numbers for the main steam line code safety valves and the necessary correlation between the individual valves and the required lift settings as well as the valve orifice sizing.

Therefore, the proposed change is similar to ex6mple (i) in that the deletion of the valve designation for the lift settings and the valve orifice size for the main steam line code safety valves is a purely administrative change to achieve consistency throughout the Technical Specificacions.

Safety and Sionificant Hazards Determination Based on the above safety analysis, the proposed change does not involve a significant hazards consideration in that it does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or dif ferent kind of accident f rom any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. In addition, it is concluded that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (2) this action will  ;

not result in a condition which significantly alters the impact of the station j on the environment as described in the NRC final Environmental Statement.  ;

BRO:8142F i

DESCRIPTION Of SAFETY ANALYSIS Of PROPOSE 0 CHANGE NPF-10/15-238 This is a request ic revise Technical Specification 3.0.4 and Surveillance Requirements 4.0.3 and 4.0.4. In addition, the request will also include revision to BASES for all specifications in Sections 3.0 and 4.0 and l inconsistent application of exceptions to Specification 3.0.4 pertinent to twenty-five (25) Technical Specifications.

Existing Specifications t

Unit 2 - See Attachment A Unit 3 - See Attachment B ProDosed Specifications Unit 2 - See Attachment C Unit 3 - See Attachment 0 Description The proposed change would revise the applicability of Limiting Conditions for Operation (LCO) and Surveillance Requirements Technical Specification 3.0.4 and Surveillance Requirements 4.0.3 and 4.0.4, on the basis of Generic Letter 87-09 entitled "Sections 3.0 and 4.0 of the Standard Technical Specifications (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements." The proposed change would incorporate a provision in Technical Specification 3.0.4 allowing entry into an operational mode or specified condition in accordance with ACTION requirements when conformance to them would permit continued operation for an unlimited period of time. It would add a provision in Surveillance Requirement 4.0.3 allowing a delay for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of some applicable ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. It would also revise Surveillance Requirement 4.0.4 to include a provision which would not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. The revision to BASES for all specifications in Sections 3.0 and 4.0 would provide a better justification supporting their applicability. Inconsistent application of exceptions to Specification 3.0.4 affecting twenty-five (25) existing Technical Specifications would be modified to comply with the new provision of Specification 3.0.4.

Safety Analysis l

The proposed changes discussed above shall be deemed to involve a significant hazards consideration if there is a positive finding in any one of the following areas:

l i

l

-2

1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequence of an accident previously evaluated?

Response: No The proposed change would redefine the applicability of an LCO in comoliance with NRC's regulatory requirements. It would provide time to obtain a temporary waiver of a surveillance requirement that could not otherwise be completed because of some prescribed plant conditions and would therefore minimize the potential for a plant upset and an unnecessary challenge to safety systems. Therefore, operation of the facility in accordance with this proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change does not alter the configuration of the plant or its operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. j

3. Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?

Response: No l

The proposed change was endorsed by the NRC and is consistent with )

the guidance provided in Generic letter 87-09. The proposed change allowing mode entry under special I.COs and time delay for l surveillance would be in conformance with the ACTION requirements I establishing an acceptable level of safety permitting, continued operation of the facility for an unlimited period to time.

Therefore, the proposed change will not involve a significant reduction in a margin of safety.

The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideraticns. Example (i) relates to a purely administrative change to technical specifications: for example, a l change to achieve consistency throughout the technical specifications, correction of an error, or a change in nemenclature. Example (vii) relates to a change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in i keeping with the regulations. i I

l l

l l

I l

The proposed change would incorporate all pertinent provisions provided in Generic Letter 87-09 entitled "Sections 3.0 and 4.0 of the Standard Technical Specification (STS) on the Applicability of Limiting Conditions for Operation and Surveillance Requirements.' It would include those acceptable modifications endorsed by the NRC which would result in improved Technical Specifications for SONGS 2 and 3 and are consistent with the recommendations of NUREG-1024, ' Technical Specifications - Enhancing the Safety impact,'

and the Commission Policy Statement on Technical Specification Improvements (52 FR 3788). Thus, the proposed change complies with Example (vii) of 48 FR 14870.

The proposed change would also revise twenty-five (25) Technical Specifications shown in Table 1 to resolve inconsistent application of exceptions to Specification 3.0.4 pursuant to the guidance provided in Generic Letter 87-09. The revision would delete any statement or phrase which incorporates such exceptions in the existing Technical Specifications to achieve consistency with NRC's regulatory position. Thus, the proposed change complies with Example (1) of 48 FR 14870.

Safety and Sionificant Hazards Determination Based on the above discussion, the proposed change does not involve a significant hazards consideration in that it does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or dif ferent kind of accident from any accident previously evaluated; or (3) involve a significant reduction in margin of safety. In addition, it is considered that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (2) this action will not result in a condition which significantly alters the impact of the station ca the environment as described in the NRC final Environmental Statement.

SPW:8702f 1

i l

l

\

1 l

l TABLE 1. TECHNICAL SPECIFICATION INCORPORATING INCONSISTENT APPLICATION )

0F EXCEPTIONS TO SPECIFICATION 3.0.4 Section Number Title 3.3.1 Reactor Protective Instrumentation 3.3.2 Engineered Safety feature Actuation System instrumentation 3.3.3.2 Incore Detectors 3.3.3.3 Seismic Instrumentation 3.3.3.4 Meteorological Instrumentation 3.3.3.8 Radioactive liquid Effluent Monitoring System 3.3.3.9 Radioactive Gaseous Effluent Monitoring Systen 3.3.3.10 Loose-Part Detection Instrumentation 3.4.8.3.1 RCS Temperature 1 235'T 3.4.9 Structural Integrity 3.7.7 Sealed Source Contamination 3.9.9 Containment Purge Isolation System 3.9.12 fuel Handling Building Post-Accident Cleanup filter System 3.11.1.2 Dose 3.11.1.3 Liquid Waste Treatment 3.11.1.4 Liquid Holdup Tanks 3.11.2.2 Dose - Noble Gas 3.11.2.3 Dose - Radiotodines, Radioactive Materials in Particulate form and Tritium 3.11.2.4 Gaseous Radwaste Treatment 3.11.2.5 Explosive Gas Mixture 3.11.3 Solid Radioactive Waste 3.11.4 Total Dose 3.12.1 Monitoring Program 3.12.2 Land Use Census 3.12.3 Interlaboratory Comparison Program

I l

NPF-10/15-238 ATTACHNENT =A=

1

i l

3/s i.:v! :NG Con::T::Ns rCt :stu?:C4 AND SURvE!'.LAN I si:U!3!W{y*$ i 3/a.C A80LI:A!!L: Y -

t:u: :ss C:No:T::n ::t :oruT::s 1 3.0.1 Com:liance with the Limiting Conditions for Operation c:ntained in the succeecing specifications is recuired during the OPERATICNAL M00!$ or einer concitions specified therein; except that ucon f ailure to meet the Limiting C:ncisions for Cperation, tne associated ACT:CN requirements sna11 he met.

3.0.2 NoncoCJ114nce with a sDecification shall exist when the requirements of l tne Limiting Concition for Operation and/or associated ACTION requirements are )

not met witnin the specified time intervals. If tau Limiting Condition for '

0:eration is restored prior to expiration of the specified time intervals, c:mpletion of tne ACTION requirements is not recuired.

l 3.0.3 When a Limiting Condition for Operation is not met, except as proviced j in tne associated ACTION requirements, within one hour, action shall be i initiatec to place the unit in a MODE in which the specification does not-  !

apply by placing it, as applicaole, in: 1

1. At least HOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT $HUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 4

3. At least COLO $ HUT 00WN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. )

I where corrective measures are completed that peenit e eration under the ACT N i recuirements, the ACTION a.ay be taken in 3 c2rcance with tne specified time limits as measured from the time of failure to meet the Limiting Condition for C:eration. Exceptions to tnen requirements are stated in the incivicual saecifications.

l This scocification is not applicaole in MODE 5 or 6. l 3.0.A Entry into an OPERATICMAL HOCE or other specified condition shall not {

te made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION recuirements. This provision shall not prevent passage through or to CPERATIONAL MODES as recuirac to comoly with ACTION requirements. Exceptions to these requirements are )

stated in the individual $pecifications. j SAN ONOFRf= UNIT 2 3/4 0 1

' W817 Int ,

188L:0a!!'.! v 5;'4v!!LL2't ! Rf0Vit!*EN'S 4.0.1 surveillance Recuirements sna11 ce acclicaele curing the CoERAT: NAL M00!S or otner conditions soecified for individual Limiting Concittens for Oseration unless otnerwise stated in an indivicual Surveillance Requirement.

a.C.2 f aca surveillance Aequirement shall es performed witnin tne specified time interval wita:

a.

A maximum interval, anda11ewaele extension not to exceed 25% of the surveillance

c. The comcined time interval for any 3 consecutive surveillance intervals not to exceed 3,25 times the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the OPERASILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the incivicual specifications. Surveillance Aequirements do not have to me perfereed on inopera:1e equionant.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not es made unless the Surv6111ance Aequirement(s) associated with the Limiting Concition for Operation have been performed within the stated surveillance interval or as etnerwise specified, a.0.5 Surveillance Reevirements for intervice insoection anc testing of ASME Coce :1 ass 1, 2 and 3 components small ne applicaole as follows:

a. Inservice inspection of ASME Coce Class 1, 2 and 3 cosconents and inservice testing ASME Code Class 1, 2 and 3 pumos and valves small De performed in accordance with Section XI of the ASME Boiler anc Pressure vessel Coca and applicaele Addenda as recuired my 10 CFA 50, Section 50.55a(g), except where soecific written reifef has eeen granted by the' Commission pursuant to 10 CFR 50, Section 50.55a(g)

(8)(i),

b. Surveillance intervals specified in Section XI of the ASME Soiler and Pressure vessel Code and apolicaole Accenda for the inservice inspection and testing activities recuired my sne ASME Soiler and Pressure vessel Code and applicaele Addenda sna11 be acclicaole as follows in tasse Technical 5:ecifications:

SAN ONCF M-U!i!T 2 3/4 0-2 II A 7 N

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

)

N S 8 t.E NT A * * :N

.  ::a.--: : : a.

. . . .. - . u.. .yc

+

. w a- .y

.. . ....se. -.

. .. ....-. y :.g -::.. 3 ... y 3.3.1 As a mini. mum, :ne rea:::e ;r :ective instrumentation enanneis ane

y: asses of Ta:1e 3.3-1 snail te CPEAA3.! witn AIS CN5! T*.Y!S as sa:wn ir.

Ta:1e 3.3-2.

A 8 8 '. : : a ! ! '. ! ?v : As sacwn in TaDle 3.3-1.

A-*::N:

As sn:=n in Table 3.3-1.

SL'8VE!'.'. ANCE R E UIR EWENTS 4.3.1.1 !aen reacter protective instr'.menta:f on enannel shall te gemenstratec' C8 IRA!Li by tre erformance of tne CHANNEL CHICX, CHANNEL CALI5 RAT:CN anc

.dANNEL FUNCT*0NAL IIST c;trations for the iMCCES and at t?.e f reQuencies $30'=n in Ta:1e 4.3-1.

4.3.1.2 The legic for tne ty: asses small ce ca. mens: ate: C8EAA5'.i :-1:e ::

es:n te: :r starius unless perf:rmec =vring ns =re:e:ing 92 cays. Tne :::a1

y: ass fa.cti:n snall te dem:nstrated C8EAABLE at least en:e :er la m:ctns

-' . ; OM ANN!'. C A'.*! RAT N testing of en:n :nansel affe::ec Oy :y: ass

e-ati:n.

4.3.1.3 ine 8EACTCR TAI? SYSTE.M Ri3?CN5! T w! of esca reae::e :-4: "..::i:n small :e cemenstrated to De witnin its limit at least once er 18 m:9:ns.

Ia:n test sna11 include at least one enannel per function swen ina all enancels are testad at least once every N times 18 men ns *nere N is :. e :: 21 nu.:er of re .ncant enannels in a specific rea: or tri: fun: tion as sa wn in

ne "Total No. of Channels" column of Ta:1e 3.3-1.

4.3.1.4 The isolation characteristics of ea:n CIA isolation amplifier anc eacn optical isolator for CIA Calculater :: Core ?rcts::1:n Calcula::e casa transfer sna11 be verified at least once per 18.tontns caring the savt::=n :er tne f=11owing tests:

a. 7:e tne CIA : sition isolation'am:lifiers:

1 w':n 120 v:!:s AC (!C H:) a::'ies f: a ' ass: 30 se:: :s a: :ss t.e ca::u:. tre res: a; :n :ne i :.: ::es :: ex:st:

C.315 velts 20.

SAN ON;Fli-UN 72 3/4 3-1 FH i 71982

i 7:!LE 3.3-1 f :-tinueel 7:!'.E N072 :cy n -

W! .a tr.e :r:tactive system tri: breakers in the closed ;ositien, the CEA c.-ive system :a:a le of CIA withera-al, and feel in the rea::: P vessel.

The pr:vis:: s of Specification 3.0.4 are not appitcacle.

-4 (a) Trio eay be manually bypassed above 10 % of RATED THERMAL PCWER; by: ass '

shall,be aut:matically recoved when THERMAL PCWER is less than or etual to .0 '% of RATED THERMAL POWER.

(b) Trip may be manually bypassed belcw 400 psia; bypass shall be at:::atically removed whenever pressurizer pressure is greater than er e:ual to 400 psia.

-4 (c) Trip may be manually bypassed below 10 % of RATED THERMAL POWER; bypass shs11 te au;':matically removed when THERMAL PCWER is greater than or ~1 During testing pursuant to -

e:ual to 10 % of RATED THER.4AL POWER. 1 5:!cial Test Exception 3.10.3, trip may be manually bypassed belev 5% of i RATED THERMAL POWER; bypass shall be automatically removed when ThERPAL l PWER is greater tnan or a;0al to 5% of RAIED THERMAL POWER.

l

(:) Tr': .sy be bypassed during testing pursu' ant to Special Test 1 i

Ex:eiti:n 3.10.3. I 1

i (e) See 5:e:ial Test Exce:tien 3.10.2. 1 i

(f) Ea:n :nannei shall be c:::rised of two trip breakers; actual trip legi: I srsil be cre-cut-of-two taken twice.

(g) Trip may be by;assed below 55% RATED THERMAL PCVER.

ACTION STATEMENTS I l

AT*:N1 -

Witn the number of channels OPERABLE ene less than recuirst :y tne Minimum Channels CPERAELE requirement, restore tne inc;erable channel to CPERABLE status within AS hcurs er be in at least HOT STANOBY within tne next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/cr 0;sa :ne protective system trip breakers.

ACTION 2 -

With the number of channels OPERABLE one less than the Total i Num er of Channels, STARTUP anc/or PC%ER OPERATICN may c:nti .e  !

pr:vided the inoperable channel is placed in the by;asseo or ,l tri::ec c:ndition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the incperasle enan.nel is ty;assed, the desiratility of =aintaining this chancel in tne bypassed c adi* ion shall be reviewed in ace:r:anca with

. 5:acificati:n 6.5.1.5e. The channel snall be returned :

CPERAE E status no later than curing tne next COLO Shut::bN.

MAY i 61963 5:1 C.'.**EE ';.'CT 2 3/4 3-4 '

A.'*.ENCMENT NO 15

i

ss :vvis"'?::N )

3/4 32 ENGIN!!tE3 SAFETv *EATU:E A:TUA7!ON Sv5 Eu !N574'.'v!N'a ::N

.:": :N; C;N*.: 209 80R C8 ERAT:0N '

3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation -

cnannels anc cymasses snown in Taele'3.3-3 shall be OPERA 3LE witn their tris set:oints set cansistent witn the values snown in the Trip Setpoint column cf Tamle 3.3-4 anc with RESPONSE TIMES as snown in Tamle 3.3 5.

A :8'. ! CA!! L:TY: As shown in Table 3.3-3."

A ?!ON: -

a.

With an E5FAS instrumentation channel trip setpoint less conservative e than the value shown in the Allowable Values column of Table 3.3-4, ceclare the enannel inoperable and apply the amplicaele ACTION recuirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with sne Trip Setooint value,

b. With an E5FAS instrumentation channel inoperable, take the ACTION snown in Taele 3.3-3.

SU:v!!LLANCE REOU?REMENTS

" 3.2.1 Each ESFAS instrumentation enannel sna11 ce cemenstrate: 08ER'!LE :y re :erformance of the CHANN!L CHECK, CHANNEL CALIBRATICN ard CHANNEL

'UN"T!;NAL TEST c:erations for the MODES anc at tne frecuencies snown in Ta:1e 4.3-2.

4.3.2.2 The logic for the bypasses shall be demonstrated OPERASLE curing the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass oceration.

The total typass function shall be demonstrated CPERABLE at least once per 18 months curing CHANNEL CALIBRATION testing of each channel affected by typass operation, a.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per la montas.

Each test shall include at least one channel per function such tnat all enannels are tested at lesst once every N times 18 montns wnere N is the total cur:er of recuncant enannels in a see:ific ESFAS function as snown in the "Tetal No. of Onannels" Column of Tasle 3.3-3.

'5ee scectaf Test Exception 3.10.5

- 1

\

SAN ONCFRE-UNIT 2 3/4 3-13 F[g } 7 ggg

i i

l TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trio function may be eynassed in this M00E when pressurizer pressure is ,

less tnan 400 psia; bypass small be automatically removec wnen pressuri:er '

pressure is grea;

• than or equal to 400 psia.  ;

l (b) An SIAS signal is first necessary to enable CSAS logic.

(c) Actuated equipment only; does not result in CIAS.

8 The provisions of Specification 3.0.3 are not applicable.

The provisions of Specification 3.0.4 are not applicable.

With irradiated fuel in the storage pool.

ACTION STATEMENTS ACTION 8 -

With the numeer of CPERA8LE channels one less than the Total Nuncer of Channels, restore the inoperable channel to OPEAA8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAN08Y within tne next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 houas.

ACTION 9 -

With the numeer of channels OPERA 4LE one less than the Tots)

Nuncer of Channels, STARTUP and/or P0kER ODERATION say continue provided the inoperaale channel is placed in tte bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the incpertale channel is bypassed, the desiraD111ty of maintaining this enannel in the Dynassed condition shall be reviewed in accorcance with Soecification 6.5.1.6e. The enannel shall be returned to CPERA8LE status no later than during tne next COLD SHUTDCVN. +

With a channel process measurement circuit that affects multipis functional units inoperaale or in test, typass or trip all associated functional units as If stad Delow. ,

Process Measurement Circuit Functional Unit 8ypassed

1. Containment Pressure - High containment Pressure - Hfgh (ESF)

Containment Pressure - Mign (RPS)

2. Steam Generator Pressure -

Low Steam Generator Pressure - Low Steam Generator &? I and 2 (EFAS)

3. Steas Generator Level Stone Generator Level - Low Steam Generator Level Nign Staan Generator AP (EFAS) l b

SAN CNCFR!-UN:72 3/4 3-13 Amendment No. 4 ne i~") s . ".

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

1 l

l INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION i

3.3.3.2 The incore detection systen shall be OPERAOLE with:

a. At least 75% of all incore detector locations, and '

b. A minfeum of wt' o quadrant syneetric incore detector locations per core quadrant.

l i

An OPERABLE incere detector location shall consist of a fuel assembly '

containing a fixed detector string with a minious of four OPERA 8LE rhodium  ;

detectors or an OPERA 8LE movanle incore detector capable of mapping the '

location.

P APPLICA8ILITY: When the incore detection systee is used for monitoring: I

a. AZIMUTHAL POWER TILT,

b. Radial Peaking factors, c, Local Power Density,

d. DNS Margin.

ACTION:

With the incere detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERA 8LE:

a. By perf0rmance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use if  !

7 or inore days have elasped since the previous check and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DN8 margin:

b. At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.

l 1

SAN ONOFRE-UNIT 2 3/4 3-41 AMEN 0 MENT No. 49 1

. . . . . _ _ . . _ . . - .. . ..m. .. _..

i:$ sc"!NTa7:0N

!!!!u:: :NS 4L'*EN'a-* N

'.:v:~:NO : N :-* N ::R C3!R ::N 3.3.3.3 ins seismic monit: ring instrumentation shown in Taste 3.3-7 shall ::

OPERABLE. '

8 8 8'.!0a!!' !*v: At all times.

.A.:.~,*' *= N., .

4. With one or more seismic monitoring instruments ino: era:1e for m: e inan 30 days, prepare and sucait a Scecial Report ts tne Commissie-

ursuant to Scecification 6.9.2 within the next 10 ' days outlining  !

ne cause of the malfunction anc tne plans for restoring tne ,

instruient(s) to CPERABLE status. '

b. TheprovisionsofSpecifica5fons3.0.3and3.0.4arenota:clica:1e. '

SUTVEILLANCE REOUIRESENTS 4.3.3.3.1 Each of the a: eve seismic m:nitoring instrumer. s shall te emenstrate: OPERA!LE by the cerforman:e of :ne CHANNEL CHECX, CHANNEL GAL:3

.a:1e 4.3-4. RAT:CN anc CHANNEL FUNCT :NAL ?!$7 ::erations at tne frecuencies snown f-4.3.3.3.2 !aca of -ne above seismic m: nit:ri ; inst.uments wht:n is 1::ess':'a

uris.; =c-er c:eration anc which is actuatec curing a seismic event (:r.e or more valic casemat accelerations of 0.0!g or greater) sna11 be rest: rec to CPERASLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> anc a CMANNEL CALI5 RATION performed wit-ir 5 cays.

Cata small be retrieved from tne ac:essible actuatec instruments a-:

analy:sc to determine the magnitude of tne vibratory grounc motion. A S:e:ial Recort shall be prepared and suositted to the Commission pursuant ts 3pecification 6.9.2 within 10 days cascribing the magnitude, frequency s:ee rum and resultant effect uoan facility features importan to safety. Ee:S of ne a: eve seismic monitoring instruments whien is actuated curing a seismic event (one or more valid basemat accelerations of 0.05g or greater) but is not ac:essible during power operation shall be restorec to CPERASLI status and a CHANNEL CALIBRATION performed the next time the :lant enters MC05 3 er below. A su::lemental report shall then be :re:ared and su:mitted t: tre C::missi:n witnin 10 days cursuant to 5:e:4fi:sti:n 5.9.2 ces:ri:ing :ne a::iticra' ca a fr:s iness instruments.

l i

\

\

SAN CNCFRE-UN!i 2 3/4 3-42

ss :.;vis a-*:N

,..........;.3 u

. .. ...... .. y. <. .c . ..; ; s 2. .... .,

.... .,... . . . y v. ..y..-..y

.s c.r.g;..r.y .

3.3.3.4 The meteorolog':a1 m:nitoring instrumer.tation enannels shown in Tacle 3.3-8 snall to CPERABLI.

a : 8'. :0 23 :'. : ~v: At all times.

A0*!lN:

a. Wita one or more reovirac meteorological sonitoring enannels ino:erasle for more taan 7 cays, presare and su:mit a Special to:o-t to tne Com. mission pursuant to Specification 6.9.2 within tne nex-10 cays outlining tne cacsa of tne malfunction and the plans for-restoring the channel (s) to CPERABLE status,

c. ThePovisions of Specifications 3.0.3 and 3.0.4 are not accli:anle.,

S'.'iv!! L '. A N :E t! '. t!wyNTS 4.3.3.4 !a:n of tne above meteorologi:a1 monitoring instrumentation enan els s .all :e :eronstra ac OPERABLE :y the perfo man:e of tne CMANNEL CHE:K an:

~:-ANN!'. *A'.*iRAT::N o;e ations at tne frecuer.:tes snow- in Ta:1e 4.3-5.

I r

(

$AN CNCFRE i.lNIT 2 3/4 3-45 gg g 7 g j

___ ~

l

,INSTRUNENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LINITING CONDITION F3R OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shell be OPERA 8LE with their alars/ trip setpoints set to ensure that the liatts of Specification 3.11.1.1 are not exceeded. The alare/

trip setpoints of these channe?s shall N deterzined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (00CM).

APPLICA8!LITY: At all times."

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alare/ trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid sffluents monitored by the affected channel or declare the channel inoperable.

b. With less than the minima neber of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown i in Table 3.3-12. Exert best efforts to return the instrument to OPERA 8LE status within 30 days and, additionally, if the inoperable i instrument (s) remain inoperable for greater than 30 days, explain in the next Sesianaual Radioactive Effluent Release Report why the inoperability was not corrseted in a timely manner.

c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable. ,

SURVEILLANCE REQUIRDENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation cha:mel shall be demonstrated CPfRA8LE by performance of the CHANNEL CHECK, SOURCE - -

CHECK, CH400EL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilu-tion to meet the site radioactive affluent concentration limits of Spec' fica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure.

"5ee special Test Exception 3.10.5.

SAM ONOFRE-UNIT 2 3/4 3-43 AMEN 0 MENT NO. 57

. _ _ . - - - - - - - . - _ . x .-- -

-1 INSTRUMENTATION i RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION t.!MITING CONDITION FOR OPEhTION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels \

l shown in Table 3.3+13 shall be OPERABLE with their alara/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The )

alarm the 00CM. / trip setpoints of these ctannels shall be determined in accordance with ApeLI,CA8ILITY: A3 shown in Table 3.3-13"  !

l ACTION:

a.

With a radioactive gaseous effluent m nitoring instrumentation channel alare/ trip satsoint loss ce,nservative than required by the above Specification, immediately suspend the release of radioactive ,

gaseousinoperania.

channel effluents monitored by the affected channel or declare the '

I b.

With less than the minimum number of radioactive gaseous effluent i monitoring instromentation channels CPERA8LE, take the ACTION shown I in Table 3.3-13.

Exert best efforts to return the instrument to i OPERARLE status within 30 days and, additionally, if the inoperable instru4ent(r) remain inoperable for greater than 30 days, explain l in the next. Semiannual Radioactive Effluent Release Report why the ',

tropsrability was not corrected in a timely manner, i i

c.

The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not aorlicable.

.50RVE!U.{NgjEQUIREWEN75 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be de.constrstec OP!RABLE by performance of tne CHANNEL CHECK, SOURCE CHECX, CHANNEL CALIBKATION ced CHANNEL FUNCTIONAL TEST operations at the frequencies shoen in Table 4.3-9.

l l

"See 5peciaT Test Exception 2.10.5

• JAN i 1585 SAN ON0FREaVNIT 2 3/4 3-64 AxottmINT 30. 31

_ _ _ __ _ __ - _ . ___.._.--__.____i__. _ _ _ _ _ _ _ . _

INSTRUN(NTATION LOOSE-PART DETECTION INSTRUMENTATION '

l LIMITING CON 0! TION FOR OPERATION 3.3.3.10 The loose part detection systes shall be OPERA 8LE.

APPLICA81LITY: MODES 1 and 2.

j ACTION:

. I a.

With one or more loose part detection system channels inoperable for more than 30 days prepare and submit a Special Report to the Commission pursuan,t to Specification 6.9.2 within the next 10 day outlining the tne channel (s)cause of the to OPERA 8LEmalfunction status, and the pir.ns for restoring b.

The provisions of Specifications 3.0 3 and 3.0.4 are not applicable.

SURVE!LLANCE REQUIREMENTS

=

4.3.3.10 OPERABLE by performance of a:Each channel of the loose part detection syste a.

CNANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per 18 months.

i JAN 11505 SAN ONCFRE-UNIT 2 3/4 3-75 AMENUMENT NO. 31

H I

REACTOR COOLANT SY$ TEM -

CVERPRES$URE PROTECTION SYSTEMS l i

RCS TEWDERATURE I 235

• LIMITING CON 0! TION FOR OPERATION 3.4.8.3.1 At least one o De CPERA8LE:

the following overpressure protection systems shall a.

The Shutdown Cooling System Relief Valve (PSY9349) with:

1) A lift setting of 406 2 10 psig*, and

2) Relief Valve isolation valves 2HV9337, 2HV9339, 2HV9377 and 2HV9378 open, or, c.

The Reactor Coolant Systes dooressurized with an RCS vent of greater than or equal to 5.6 square inenes.

APDLICA8!!.ITY:

MODE 4 wht;. .he tamoerature of any one ACS cold leg is less tnan ce squa' to 235'F; MODE 5; MODE 6 with the reactor vessel head on. l ACTION: )

t a.

With the SDCS Relief Yalve inoperacle, reduce T,,, to less than MC*F, accetssurize and vent the RCS through a greater than or equal e 5.6 square inch vent witnin the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. i t

e. L'ith one et both 50C5 Relief Valve isolation valves in a single 50C5 Relief Valve isolation valve pair (valve pair 2HV9337 anc ,

1 2HV9339 or valve pair 2HV9377 and 2HV9378) closed, open the closed valve (s) within 7 days or reauce 7,yg to less than 200'F. cecres-surize and vent, the RCS through a greater than or equal to 5.6 inch vent within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,  :

(

c. i In the event either the ADCS Relief Valve or an RCS vent is i; sed to mitigate an RCS pressure transient, a Soecial Recart snall be prepared and subettted )

within 30 days.to the Commission pursuant to Specification 6.9.2 The report shall describe the circums.ances initi- l ating the transient, the effect of the SDC5 Relief Valve or RCS vent  ;

on the transient and any corrective action necessary to prevent recurrence, {

d.

The provisions of Specification 3.0.4 are not applicaele.

1 SURVE!LLANCE REQUIREMENTS 4.4.4.3.1.1 The SDCS Relief Yalve shall be demonstrated OPERA 8LE Dy:

a.

Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the 50C5 Relief Valve is ceing used for overpressure prot 6ction tnat 50C5 Reiter valve isolation valves 2%'1337, 2HV9339, 2HV9377 anc 2Hv9378 are open.

'For valv e t emocratures less si.an or equal to 130*F.

A CNCFRE % IT 2 3/a 4 32 Amencment No, a 4

"" i *

. - - - '* C I

stacTOR C00LaNT Sys?!w 3.4.9 $?tUCTURA'. IN !M: v L:M:*:NG CON : TION FOR OD! TAT!ON 3.4.9 ine structuril integrity of ASHE Coos Class 1, 2 and 3 comconen.s snail be maintainec in ace:rcancu vita Specification 4.4.9.

A88t!0A!!L:T ALL MCCES ACTION:

a.

With the st*uctural integrity of any ASME Code Class 1 component (s) not confarming to the aoove requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected comoonent(s) orier to increasing the Reactor Coolant System temoerature mere than 50*F above the minimum temperature recuired by NOT consicerations.

b.

With the structural integrity of any ASME Code Class 2 comconent(s) '

not conforming to the above recuirements, rettore the structural integrity of the affected component (s) to within its limit or i isolate the affected component (s) prior to increasing the Reactor Coolant Systes temperatura aoove 200'F.

c.

With the structural integrity of any ASME Code Class 3 c moonent(s) not cenforming to the above requirements, restore the structural integrity of the affectec com:enent to within its limit or isolate the affectec cor.conent from service.

c. The provisions of $ cec'ification 3.0.4 are act a::licaole. I i

SURv!!LLANCE REOUIREMENTS i

I 4.4.9 In addition to the recuirements of Specification 4.0.5, each React:r i

Coolant Pwo flywheel shall be insoecteo per the recommendations of Regulat: y Position C.4.b of Regulatory Guide 1.14, Revision 1. August 1975.

1 l

1

( l 1

SAN CNCFR!-UNIT 2 3/4 4'3a R$ 17 %

)

D', ANT $VSTIMI 3,'a . 7. 7 SIAL!O SOUR 0! : NTAMINa? ION L:w!":N3 00N0!*!0N FOR ODERATION l

3.7.7 !ach seale.d source containing racioactive material either in excess of 100 microcuries of esta anc/or gamma emitting material or 5 alcrocuries of alena emitting material shall be free of greater than or equal to 0.005 microcuries of removaole contamination.

A88LICABILITY: At all times. I l

ACTION:

a. With a sealed source having removable contamination in excess of the aeove limit, witneraw the sealed source free use and either:

. 1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission '

Regulations. .

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REOUTP!MENTS a.7.7.1 Test Recuirements - Eacn sealed source shall be tested for leakage anc/cr contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Costaission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample, 4.7.7.2 Test Frequencies - Each category of sealee sources (excluding startue sources and fission cetteters pr.:viously suojected to core flux) shall be tested at the frequencies described below,

a. Sources in use - At least once per six months for all sealed sources containing racioactive saterial:

1. With a n;.lf-life greater than 30 days (excluding Nyer:;en 3),

anc

2. In any form ciner inan gas.

\.

SAN ONCFRE-UNIT 2 3/4 7-24 ,. *I FU) 7. f982

i RE:UELING C3 ERAT::NS 3 'a. 9. 9 C Maisugy; =ggc; : scla ::N SYSTEM L:M: :NG :N:!7ICN FOR CPERATICN 3.9.9 The containment purge isolation systes shall be OPEAA8LE.

AP8LICABILITY: Ouring CORI ALTERATIONS or movement of irradiated fuel witnin tne containment.

ACTION: -

With the containment surge isolation system inoperable, close each of the contairment surge pene!. rations providing direct access from the containment atmoschere to the outside atmosphere. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE0V!REu! WS 4.9.9 The containment purge isolation systen shall be demonstratec CPERA!.'!

within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least onca per 7 cays curing C;RE ALTERATIONS by verifying that containment purge valve isolation occurs on manual initiation and on a high radiation test signal.

SAN CNOFRE-UNIT 2 3/4 9-10 -

FEB i 71982

1 l

l

• !:JE.ING : !:A*:CNS 3 a.9.'.2

'UEL HANDL:NG Bu!LC!sG PC5'-aCC::ENT CLEANLD :!L'ER $<! Ew l

L:w! TING CCNDITICN FCR CAERATICN 3.9.12 T.o incocendent fuel handling building post-accident cleanuo filter systems inall De OPERABLE.

A P D L IC A9 !'.!TY:

Whenever irradiated fuel is in the storage pool.

ACT CN: 1 l

1 a.

k'ith one fuel har.dling building post-accident cleanuo filter system i i9 operable, fuel movement within the storage pool or operation of '

fuel handling machine over the storage pool may proceed pro'vided the 05ERABLE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERA 8LE emergency power source anii is in operation and discharging through at least one train of HEFA filters and charcoal absorbers.

b.

Wita no fugl handling building post-accident cleanuo filter system CPEPABLE, suspend all ocerations involving movement of fuel within the storage pool or operation of fuel handling machine over the storige pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERA 8LE status,

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RECUIREMENTS 4.9.12 The abovo required fuel handling buildirg post accicent cleanuo filter systems sna11 be demonstrated OPERA 8LE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

b.

At least once per 18 months or (1) after any structural maintenance on the HL:PA filter or charcoal adsorber housings, or (2) folicwing painting, fire or chemical release in any ventilation zone communicating with the system by:

i SEP 3 0 'i55 SAN ONCFRE-UNIT 2 3/4 9-13 AMENCMENT H0. 35

. . . . . . . . . . . . _ l

. . . . . . ,j Ra0ICACTIVE grrLUERT5 l CCSE LIM: !NG CONC!*!CN FOR ODERATION 3.11.1.2 The dose or desa couaitment to an individual free radioactive materials (see Figure in 5.1 liquid

4) effluents released, from eacn reactor unit, from sne site shall be limited:

a.

During any calendar quarter to less than or equal to 1.5 eres to the total boey and to less than or equal to 5 area to any organ, and

b. l During any calendar yesr to less than or equal to 3 area to the '

total body and to less than or equal to 10 area to any organ.

Apol!CAltLITY: At all times, 1 t

ACTION: .

a.

Vith the calculated cose from the release of radioactive materials -

in liquid effluents exceeding any of the taove limits in lieu of j any other report required by Specification 6.9.1, prep,are and suosit i to the Commission within 30 days, pursuant to Specification 6.9.2, a )

Special Aeport which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce the releases!i the proposed actions to be taken to assure that subsequent releases will be in compliance wita Specification 3.11.1.2

b. l The provisions of specifications 3.0.3, 3.0.4 and 6.9.1.13b are not applicatie. I j

l SURVEILLANCE REQUIREMENTS 4.11.1.2 Dese calculations. Cumulative dose contributions frsa lieutd effluenta 31 says. snall ne oetermined in accorcance with the 00CM at least c'nce per SAN ON0FRE-UNIT 2 3/4 11-5

1 i

i l

RADICACTIVE EFrLUENTS LIOUID VASTE T8EATw!VT L:9: :N3 CONDITION FOR OPERATION ,

. 1 l

3.11.1.3 The liquid radwaste treatment systes shall be OPERA 8LE. The l a:propriate portions of the system shall be used to reduce the radioactive materials in licuid wastes prior to their disenarge when the projected ecses due to the liquid effluent free the site (see Figure 5.1-a) when averagte ever 31 days, would exceed 0.06 seem to the total bocy or 0.2 area to any organ."

APPLICABILITY: At all times.  !

ACTION:

a. With the liquid radwaste treatment system inoperable for acre than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu'er any other report required by Specification 6.9.1, prepare and subett to the Commission within 30 days pursuant to Specification 6.9.2 a Special.

Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the incperable equipment to CPERABLE status, and

3. Sumary description of action (s) taken to prevent a recurrence.

b. Tr.e provisions of Specifications 3.0.3 and 3.0.4 are not a: plica:1e.  !

l SURVEILLANCE REQUIREMENTS l l

4.11.1.3.1 Ocses due to liquid releases shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.1.3.2 The liquid radwaste treatment systes shall be demonstrated CPERABLE by operating the liquid radwaste treatment systes equipment for at least ihminutes at least once per 92 days unless the liquid radwaste systes has been utilized to *process radioactive liquid affluents during the pre <icus 92 days.

Per reactor unit E!! i ' q -

SAN CHOFRE-UNIT 2 3/4 U 6 FE8171982

At?!YE E::'.U!';~5 e.!!L:: F '. '.: P ? - N 5'. 5 L:u:7;nc c:s titoy ;;R cograT;cy 3.11.1.4 The quantity of radioactive material contained in each outside te ;orary tank shall be limited to les:

tritium and dissolved or entrained noble gases.than or equal to 10 curies, excluding APPLICA3?LITY: At all times.

AC?!CN:

4.

With the quantity of radienctive material in any outside temperary tank exceeding the above limit, im.iediately suspend all additions of radioactive contents to material within theto limit, the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank b.

The provisions of Specifications 3.0.1 and 3.0.4 are not applicable.

SURV!: LLANO: REOU!:.Eu!N?S -

4.11.1.4 The quantity of radioactive material contained in each outside tet.:orary tank sna11 be determined to be within the above limit by analytte.; a re:resentative sample of the tank's contents at least cnce per 7 days wnen ra:icactive catarials are.being added to the tank.

MAY161**:-

IA.s es:.: t-untr 2 3<a 11 7 un -un~ ea - -

t RA0!0ACTty! gprLUEC S 00$( = NC8LE CASES

'!w!

. :NG CONO ?!ON FOR CP! RATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, fr:e each reactor unit, from the site (see Figure 5.1-3) shall be limites to the following:

a. During any calendar overter:

Less than or equal to 5 arad for gama radiation and less than or equal to 10 arad for beta radiation and,

b. During any calendar year: Less than or equal to 10 arad for gama l

radiation and less than or equal to 20 arad for beta radiation.

APDLICABILITY: At all times.

AtticM a.

With the calculatsd air dose free radioactive netle gases in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification E.9.2, a Scecial Report which identifies the cause(s) for exceedir; the limit (s) and defines the corrective actions taken to reduce reiaases anc tne c:: esse corrective actions to be taken to assure that sucsequent releases will be in compliance with Specification 3.11.2.2.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not acclica:1e.

SURVEf t. LANCE REQUIREMENTS 4.11.2.2 Cose Calculations Cueulative dose contributions for the current calencar cuarter anc current calencar year shall be determined in ac:creance i with the C0CM at least once per 31 days, '

1 I

l 1

i SAN ONOFR!-UNIT 2 ,3/4 11-12

'~c' *: , . . .

\

I FE517 21

RADICACTTVE EFFLUENTS t 00SE - RA0!OICOINES, RADI0ACTtyr MATERIALS IN PARTICULATL FORM AND TRIT!uM LINITING CON 0! TION FOR OPERATION 3.11.2.3 The dose to an individual from tritium, radiciodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mese to any organ and,

b. During any calendar year: Less than or equal to 15 ares to any organ.

l c.

Less of than contaminated burning 0.1% of the limits oil. of 3.11.2.3(a) and (b) as a result

{

APPLICASILITY: At all times.

ACTION:

I

a. With the calculated dose from the release of tritium, radiofodines, and radioactive materials in particulate form, with half lives greater than 4 days, in gaseous effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.3.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the 00CM at least once per 31 days.

i SAN ONOFRE-UNIT 2 3/4 11-13 AMENOMENT NO. 52

I RACICACTIVE rerLUENTS l

GASECUS RA0 WASTE M EAWENT UM:*:NG CONCITION FOR OPERATION 3.11.2.4 The GASIOUS RADWASTE TREATMENT SYSTEM and the VENTILATI TREATMENT SYSTEM shall be OPERA 8LE. The appropriate portions of the GASECUS RA0VASTE TREATMENT SYSTEM shall be used to reduce radioactive material gaseous waste prior to their disenarge wnen the projected gaseous effluent air cosas due to gaseous affluent releases from the site (see Figure 5.1-3), wnen averaged over 31 days, would exceed 0.2 arad for gamma radiation and 0.4 mrac for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive natarials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site (see Figure 5.1-3) when averages over 31 days would exceed 0.3 area to any organ."

APoLICA8ILITY: At all times. .

AC' ION:

a.

• With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTIL EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or with gaseous waste being discharged without treatment and in excess of the aoove limits in lieu of any other report required by Specifica-tion 6.9.1, prepa,re and submit to the Commission within 30 days, pt swant to Specification E.9.2, a Special Report which includes tne following information:

1.

Identification of the inocertole equipment or sutsystems ar.

tne reason for inoperacility,

2. Action (s) taken to restore the inoperable equipment to OPERA 3LE status, and .

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.  !

SURVEILLANCE REQUIREMENTS I

4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.2.4.2 The CASIOUS RADWASTE TREATMENT SYSTEM and YENTILATION EXH TREATMENT SYSTEM thall be demonstrated CPERA8L! by ocerating the GASECUS RA0 WASTE TREATMENT SYSTEM equipment and VENTILATION EXMAUST TREATMENT SYSTEM ecuitment for at least 15 minutes, at least once per 92 days unless the acoropriate system has been utilized to process racicactive gaseous affluents curing tne previous 92 cays.

4 "These cases are per reacto,r unit.

SAM CNOFRE UNIT 2 3/4 U-14 * -

FEB 17 WI

RA ::ACT!'!! i::'.UE!.73_

I :lts:'!! G:3 :r'Us!

L:v!T;NG c N:li!ON FCt 0;i4ATION 3.11.2.5 The cen:entration of oxygen in the waste gas holdup system shall be limited to less than or equal to Z% by volume whenever the hydrogen concentration excee s 4% by vcluse.

APPLICA3!(ITY: At all times. -

ACTION:

a.

' With the cencontration of oxygen in the weste gas holdup systes greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

b.

With the concentration of oxygen in the weste gas holdup systes greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within one hour and less than or equal to 2%

by volu=e within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. '

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE tiOUIREMENTS .

a.11.2.5 The c:ncentrations of hydrogen and oxygen in the waste gas holdus system shall be determined to be within the above limits by continuously moni-toring the waste gases in the waste gas holdup systes with the hydrogen and oxygen monit:rs required CPERABLE by Table 3.3-13 of Specification 3.3.3.9.

i M8Y16tef?

SAN CNCFRI-UNIT 2 2/4 11-15 surwr/4NT N9 If

l l

l R10!0 ACTIVE EFFLUENTS l

3/4.11.3 SOLIO RA0!OACTIVE WASTE i L!w!T!NG CON 0!Tf0N FOR QPERATfDN j

3.11.3 The solid reewaste systes shall be OPEAA8LE and used, as amplicante in 1 accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICA3fLITY: At all times." .

ACTION:

a. With the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged  ;

solid radioactive wastes free the site.  !

b. With the solid radwaste system inoperable for more than 31 days, in lieu of any other report required by Specification 4.9.1, prepare  !

and submit to the Cassission within 30 days pursuant to Specifica* '

tien 6.9.2 a Special Report which includes the following information:

1. Identification of the inoperable equipment er subsystees and  !

1 the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to CPERAILE status ,

3. A cascription of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, ano 1

4. Summary description of action (s) taken to prevent a recurrence.

i

c. The previsions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid redweste system shall be demonstrated OPERA 8LE at least once per 92 days by:

a. Operating the solid redwaste systee at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or b.

Verifiestion of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accorcance with a PROCESS CONTROL PROGRAM.

"SeeSpecif$ cation 6.13.1.  !

I,  !

1AN ONOFRE-UNIT 2 3/4 11-17 f

": '

"FE317 lu2 .i l

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

l l

RADICACTIVE (FFt.UENTS 3/4.11.4 TOTAf OCSE q

t.!M!*:NG CONDITICN FOR OeERATION 1 l

3.11.4 The dose or dose consitzent to any member of the public, due to q releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 ares to the total body or any organ "

(except the thyroid, which shall be limited to less than or equal to 75 ares) over 12 consecutive months. -

APPLICA8tLITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive saterials in liquid or gaseous affluents exceeding twice the limits of

$cecification 3.11.1.2.a. 3.11.1.2.b. 3.11.2.2.a. 3.11.7. 2.b.

3.11.2.3.a. or 3.11.2.3.b Specification 6.9.1, prepareinand lieusubmit of anyaother Special report Reportrequired to the by .

Director, Nuclear Reactor Re Commission, Washington, D.C.gulation, 20555, within U.S.

30Nuclear Regulatory days, which defines ,

i the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4 This Special Report shall include an analysis which estimates the radiation exposure (dese) to a member of the public f u anius '

fuel cycle sources (including all effluent pathways and hirect radiation) for a 12 consecutive month period that includes the release (s) covered by this recort. If the estimated ecse(s) exceeds the limits of Specifica* ion 3.11.4, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the prr, visions of 40 CFR 190 and including the specified information of I 190.11(b). Sunnittal of the report is considered a timely request, and a variance is granted untti staff action on the requ'est is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the reevire-ments for dose limitation of 10 CFR Part 20, as addressed in other 11 sections of this technical specification.

b. The provisior.: of specifications 3.0.3 and 3.0.4 are not appitcable.

$URVEllt.ANCE RECUIRFAfMTS ,

e- , ,

4.11.4 Dese Calculatiens Cumulative dose contributions from liquid and gaseous effluents snall ne determined in accercance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with sna 00CN.

I

! N I .

i l

SAN CH0FRE UNIT 2 3/4 11-19

• N * ' $ ."

RB17 282

- . , - - - -- w -w. - .- -. ..,y- - - - . -. g. , w. - - - - . - - . - - - - .

.....,_,j l

. 3/a.12 RAOIOLOOICAl. ENVIRONw!NTAL % NITORING 3/a.12.1 MONITORING DRCGRAM t.!M! TING CON 0! TION FOR OPERATION 3.12.1 The radiological environmental monitoring pregram shall be conducted as specified in Taale 3.12-1. .

APPt.ICA8 t t.ITY: At all times.

ACTION:

i

4. With the radiological s'nvironmental sonitoring progran not being conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, preparc and submit to the Coe-sission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the l plans for preventing a recurrence.

l

b. With the level of radioactivity in an environmental sampling medium I exceeding the reporting levels of Table 3.12-2 when averaged over any calendar quarter, in lieu of any other report required by

• Specification 6.9.1, prepare and submit to the Consission within 30 days from the end of the affected calendar quarter a Report pursuant to Specification 6.9.1.13. When more than one of the

' radionuclides in Table 3.12-2 are detected in the sampling medium,  !

this report shall ce submitted if: 1 concentration (1) , concentration (2) + ***> 1.0 limit level (1) limit level (2) -

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be subeitted if the potential annual dose to an individual is equal to or greater than the calendar year limita of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level'of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With fresh leafy vegetable samples or fleshy vegetable samples unavail-able from one or more of the sample locations required by Table 3.12-1, in lieu of any other report required by Specification 4.3.1, prepare i

' and submit to the Commission within 30 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavail-ability of samples and identifies 1ccations for obtaining replacement saneles. The locations from which samples were unavailable may then j be deleted from those required by Table 3.12-1, provided the locations f rom wnich the replacement samples were obtained are acted to the environmental monitoring program as replacement locations.

d. The provisions of Specifications 3.0.3 and 3.0.4 are rot applicaele.

I A

\ I SAN ONO N UNIT 2 3/4 12-1  !

1. U .' * . , , ,

I RB 17 M2

. MMC:!Cu EWI:.ON"!N n MONI*Ct!NG

't .12. 2 LAND USE CINSUS i.tvi?:N3 Co'GITICN FOR OPERATION 3.12.2 A 1 sed use census shall he conducted and shall identtiy the location cf the nearest milk animal, the nearest residence and the neavest garden" of greater than 500 square feet pr: .cing fresh leafy ve;etable's in each of the is meteorological sect:rs within a distana ef five miles. l'or elevated releaises as defined in Regulatory Guide 1.111. Revision 1. Ju'y 1977, the land use census shall also identify the locations of all oilk animals and all gardens of greater than 500 square feet producing free leafy valetables in each of the 16 meteorological sectors within a distance of three miles.

AP P t.ICA81LITY: At all times.

ACTtcN:

a. With a land use census identifying a location (s) which yields a calculated dose or cose coersitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.9.1., prepare and submit to the Co.ufssion within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s),

b.

With a land use census identifying a' location (s) which yields a calculated dose or dose comit. ment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, in '

lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, a Special Report which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose er i dose commitment via the same exposure pathway may be deleted fres I this monitoring progras after October 31 of the year in wnica tais land use census was conducted,

c. The provisions of Specifications 3.0.3 and 3.0.4 are net applicable, SURVEILUNCE REQUIRE.*ENTS -

i 4.12.2 The land use census shall be conducted at least once per 12 zonths l tetween the dates of June 1 and Octcher 1 using that information which will provide the best results, such as by a dest-to-door survey, aerial survey, or by consulting local agriculture authorities.

I Broad leaf vegetation sampling ray be performed at the site bcundary in the cirectron sector with the hignest 0/Q in lieu of the garden census.

g 16 @

SAN CNOTRI-UNIT 2 ..

3/4 l2-11 .-

i Art,';cgc !;g, lg i ,

i 1

e R10

T.00*:1L ENV: t!':"I' TAL .CN! CR!' 3 1 2/4.12.3 INTERL*!:rt;Cty C:!;::*50.9 ;;;ct:n {

l LIMITING CCN0! TION FOR CP'RATICN l

l 3.12.3 Analyses shall be performed on radioactive materials supplied as part  :

of an Interlateratory Comparison Program whten has been approvec ey the Commission. .

APPLICalILITY: At all times. l ACTICN:

a.

With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Raciological Environmental Operatir.g Aaport.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURv!ILLANCE RECUIREMENTS 4.12.3 A sEmmary of the results cetained as part of the above required Interlateratory Comparison Program anc in accordance with the CCCM shall te inclucac in tP4 Annual Radiological Environmental Operating Aaport.

l e

'l e

l IW 161983 SAN Cf:CFF.E-UNIT 2 3/4 12-12 f'.*!*::,' !,';T *:0. 16

l l

.. . . . . . . . . . . . . ~ . . l 3/4.0 APPL!!ABILI?Y l

. SA$!$

The specifications of this section provide the general requirements applica31e to each of the Limiting Conditions for Operation and Surveillance Aequirements within Section 3/4 3.0.1 This specification defines the applicantlity of each specification in teres of defined CPERATIONAL Mocts or other specified conettions and is provided to delineate specifically wnen each specification is applicaale.

3.0.2 This specification defines those conditions necessary to constitute compliance with the teres of an individual Limiting Condition for Operation and associataa ACTION requirement.

3.0.3 This specification delineates the seasures to be taken for i circumstances not directly provided fo* in the ACTION statements and whose occurrence would violate the intent of a specification. For example, Specification 3.6.2.1 reewires two Containment $ pray Systems to be CPERA4LE and pesvices explicit ACTION requirements if one spray system is inopertale. .

Under the teres of Specification 3.0.3, if both of the required Containment Soray Systems are inoperable, within one hour measures must be initiated to place the unit in at least MOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOWN in the sucsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0.4 This specification provices that entry into an OPERATIONAL MODE or other specified applicanility condition must be made with (a) the full cae-plement of requires systess, equipment or conconentJ CPERA4LE and (b) all other parameters as specified in the Limiting Cenettions for Operation being met witneut regard for allowaale deviations anc out of service provisions contained in the ACTION statements.  !

The intent of this prevision is to insure that facility operation is not I initiated with either reevired equipment or systems inoperaale or other i specifies limits being asceened.

j Exceptions to this specification have been provided for a limited nunoer of specifications when startup with inoperable equipment would not affect I plant safety. These exceptions are stated in the ACTION statements of the

• appropriate specifications.

1

$Ad CMOFRE-UNIT 1 5 3/4 0-1 FEt : " r: .

FEt i 7 M82 ,

_- - . .- - - - - - --\

q d

l l

BA5t$ i 4.0.4 'This specification ensures that tM surveillance activities associated with a Limiting Conettien for Operation nave seen performee witnin tne specified time interval prior ta entry into an CPERATIONAL M00( or otMr -

applicaale condition. The intant of this provision is to ensure that surveil-lance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERASILITY requirements of the Limiting Condition for Operation.

Under the terms of this specification, for example, during initial plant startup or following extended plant outages, the applicable surveillance activities must be perfereed within the states surveillance interval prior to placing or returning the system or equipment inta CPERA8LI statua.

4.0.5 This specification ensures that inservice inspection of A5ME Case Class 1, 2 and 3 conoonents and inservice tasting of ASME Caos Class 1, 2 and 3 pumps and valves will be performed in accorsance with a periodically updated versich of Section XI of the ASME Boiler and Pnssure Vessel Cees and Aedenda as neutred by 10 CFR 50.55a. Relief from any of the aseve reevirements has been provised in writing by the Cosmission and is not a part of these Technical Specifications.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicaele Addenca.

This clarification is provised to ensure consistency in surveillance intervals  :

thougneut these Technical Specifications and to reeeve any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the teres of this specification, the more restrictive requirements of the Technical Specifications taka pncedence over the ASME Seiler and P Mssure Vesse) Case and applicaale Aetenea. For example, the n ovi neents of

$pecification 4.0.4 to perform surveillance activities prior ta entry into an CPERATICMAL M00t er other specified appif canility condition takes precedence over the ASMC Seiler and Pressure Vessel Code provision wnich allows pumos to be tasted up ta one ween after return ta normal operation. And for example, the Technical Specification eefinition of CPERABLE does not grant a grace period before a device that is not casaale of performing its specifies .

function'is esclared inoperaale and takes precedence over the ASME Boiler and Prsssure Yessel Code prevision which allows a valve to be incapable of

' performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being dectand i ineperable.

i l

l l

l 5AM CO'i UNIT 2 8 3/4 0-3 I

.. . . .. . .. . . . . . . . . FEB 17 IM.2  !

I

NPF-10/15-238 ATTACHMENT "B" 1

l l

l I

l

5 '"' *'

~

l' 1/4 T LINI.ING CON 0!TIONS F01t OPERATION AND SURVEILLANCE REQ l

3/4.0 APPLICA8ILITY LIMITINE COM0! TION FOR OPERATION i

3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is requind during the OPERATIONAL M00E5 or other Conditions for Operation, the associated ACTION requirem 3.0.2 Noncomp1.!ance with a specification shall exist when the requirements of the Limiting Condition for Operation and/or associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified t<ae intervals, completion of. the ACTION requirements is not required. /

-.j 3.0.3 When a Limiting Condition for Operation is not eet, except as provided

,in,the associated. ACTION n quirements, within one hour; action shall be )

initiated to place the unit in a MODE in which the specificattes does not ,'

apply by placing it, as applicable, in: '

w

., , . . 4 lw. . . .p. .

r

, .w -

1. . , 3  ;,. ,.

.2.' At least NOT STAN04Y within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ,

3.

At least HOT SHUTDOWN within the followingy8and hours-  %' . *.""

( At least COLD SHUTDOWN within the subsequent 24 heurer.

Where corrective esasures are complated that permit operaties unser the ACTION requirements, the ACTION say be taken in accordance with the specified tier lietts as measured from the time of failure to meet the Limiting Candition: for Operation.'

specifications. Exceptions to these requirements are stated in the <ndividual

~

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not '

be made unless the conditions of the Limiting Condition for Operation are met without reliance on provisions contained in the ACTION requirements. This provision shall not prevent passage through or to OPERATIONAL ICOES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications.

I

- i l

c' /

SAN ONOFRE-UNIT 3 3/4 0-1  !

I I

a ;. ~~.'

O I: . .

. . 1 I  :

APPLICA81LITY 1

l i $URVEILLAMCE REQUIREMENTS '

i 4

4.0.1 Surveillance-tequirements shall be appitcable during the OPERATIONAL l

l MODES or other conditions specified for individual Limiting conditions for l

, operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each surveillance Requirement shall be performed within the specified j time interval with: l

a. (

A anximum allowable extension not to exceed 255 of the surytf11anca_ .

interval, and I l

1

b. The combined time interval for any 3 consecutive surveillance intervals not ta exceed 3.$5 times the specified surveillance t .

interval. .

l

. i. . .p.

. :P.

4.0.3 Failure to perform a Surveillance Requirement within the specified fee interval shall constitute a failure to meet the OptRASILITV' requirements a

Limitirm Candition for Operation. . Exceptione to these requirements are s in the < ndivitual specifications.

performed on inoperable equipment. Surveillance Requirements de not,have

~

be 4.0.4 Entry into an OPERATIONAL M00f or other specified condition shall not I be made unless the Surveillance Asw irement(s) asseslated with the Lietting (

Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.  !

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME i Code Class 1, 2 and 3 cagenents shall be applicable as fellows:

l

a. Inservice inspection of ASME' Code Class 1, 2 and 3 components and i

inservice testing ASE Code Class 1, 2 and 3 pumps and valves shall

' be perfereed in accordance with Section XI of the ASME Seiler and 1 Pressure Vessel Code and applicable Addenda as required by 10 CFR 50 Sectiest 90'. 55a(s) granted by the Cam..ancept where specific written reifef has b j (6)(1). . . . .

i

b. Surveillance intervals specified in Section XI of the ASME loller and pressure vesse) Code and appitcable Addenda for the inservice.

inspection and testing activities required by the ASE Better and Pressure Vessel Code and applicable Addenda shall be applicable as follows irtthese Technical Specifications':

1 l ...

1 j ,'

j i g i5 W '

i i SAN ONOFRE-UNIT 3 3/4 0-2 l

l l

g -, - - se-- y e- + ,w ,-

-.mw-eewe ------v---w,--*_ --

---

ww-- - - w------^,w- e - m =w--=-eNw'unv-*-'

~

l 3/4.3 INSTRLMENTATION --

3/4.3.1 REACTOR PROTECTIVE INSTRLMENTATION l LINITING CON 0! TION FOR OPERATION 3.3.1 As a sinimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shalf be OPERA 8LE with RESPONSE TINES as shown in Table 3.3 2.

APPLICA8!LITY: As shown in,, Table 3.3-1. ,, , ,,

a' ACTION: .

As shown in Table 3.3-1. .

t SURVEILLANCE REQUIREMENTS '

.n ,

W '

4 .

t ': .

4.3.1.1 Each reacidr protective instrumentation channel shall be demonstrated OPERA 8LE by the performance of the CHANNEL CNECX, CHANNEL CALIBRATION and

~ CHANNEL FUNCTIONAL TEST operations for the WE5 and at the frequencies shown in Table 4.3-1.

S 4.3.1.2 The logic for the bypasses shall be demonstrated 0PERA8LE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERA 8LE at least once per la months during CHANNEL CALIBRATION testing of each channel affected-by bypass i operation. .

4.3.1.3 TheREACTdRTRIPSYSTEMRESPONSETIMEofrachreactortripfunction shall be demonstrated to be within its Itait at least once per 18 months.

Each test shall include at.least one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.3-1.

4.3.1.4 The isolation characteristics of each CEA isolation amplifier and i

each optical isolator for CEA Calculator to Core Protection Calculator data I transfer shall be verified at least once per 18 months during the shutdown per the following tests:

a. For the CEh position isolation amplifiers: '

l. With-120 volts AC (60 Hz) apptled for at least 30 seconds across the output, the reading on the input does not exceed 0.015 volts DC.

/

NOV 151982 SAN ONOFRE-UNIT 3 3/4 3-1 d

l

. t s

t TA8LE 3.3-> feontinued)

TABLE NOTATION i

a With the protective system trip breakers in the closed position, the CEA drive systes capable of CEA withdrawal, and fuel in the reactor vessel.

'The provisions of Specification 3.0.4 are not, applicable. ,

(a) Trip may be manually bypassed above 103 of RATED THERMAL POWER; bypass shall to 10 ke automatically removed when THERMAL POWER is less than or equal -

T of RATED THERMAL POWER. . ..

(b) Trip say be manually bypassed below 400 psia; bypass shall be automatically removed whenever pressurizer pressure is greater than or equal to 400 psia. .

.U

' (c) TripsaybemanuallybypassedbelowloiofRATEDTHERMALPOWER; bypass b

• sha11 be aut tically removed when THERMAL POWER is greater than or

equal to 10 of RATED THERMAL POWER. During testing pursuant to Special Test Exception 3.10.3, trip may be manually bypassed below 5 3 RATED THERMAL POWER; bypass shall be automatically removed when THERMALL .

-

POWER is greater than or equal.to 55 of RATED THERMAL POWER.

(d) Trip may be bypassed during testing' pursuant to Special Test y Exception 3.10.3.

(e) See Special Test E.xception 3.10.2. .

(f) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out tif two taken twice. , ,.

(g) Trip may be bypassed below 55X RATED THERMAL POWER. ,

4 ,. ..... .. -

ACTION STATEMENTS -

...o .... . . .

ACTION 1 -

With 'the n, umber 'of channels OPERA 8LE 'one less than required by the Minleum Channels OPERA 8LE requirement, restore the -

inoperable channel to 0PERA8LE status within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> or be in

.s

',at least NOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the

..,g. { protective system trip breakers. .. ,, ,  !

~ : ..

ACTION 2 .

' With the number of channels OPERABLE one less than the Total l Number of Channels, STARTUP and/or POWER OPERATION say continue  !

provided the inoperable channel is placed in the bypassed or '

tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is l bypassed, .the desirability of maintaining this channel in the  ;

bypassed condition shall be reviewed in accordance with l 4

Specification 6.5.1.6e. The channel shall be returned to I

OPERA 8LE status no later than during the next COLD SHUTDOWN.

/ .'

. NOV 15 IS62 SAN ON0FRE-UNIT 3 :3/4 3 4 1 l i I

INSTR l MENTATION 3/4.3.2 a ENCINEI'ED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTAT 1.INITINGCON0}TIONFOROPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFA3) instrumentation channels and bypasses shown in Yable 3.3-3 shall be OPERAtt.E with their trip setpoints set consistent with the values shown in the Trip setn int column of 4 Table 3.3-4 and w Mh RESPONSE TIME 5 as shown in Table 3.3-5." ,

APP (!CA8!LITY: As stnown in Table 3.2-3. *

-~

ACTION:

a.

With an ESFA5 instrumentation channel trip setpeint less conservative than the value shown in the Allowable Values column of Table 3.3 4, declare the channel inoperdle and apply the appitcable ACTION requirement of Table 3.3-3 util the channel is restored to OPERASLE status with the trip setpeint adjusted consistent with the Trip Setpointvalue.17 .

b.

With an E5FAS instrumentation cht.nnel inoperable, take the ACTION shown in Table 3.3-3. i SURVEft.LAMOE REQUIREMENTS 4.3.2.1 Each E5FA5 instrumentation channel shall be demonstrated OPERA 8LE by  !

the performance of the CHANNEL CNECK, CHANNEL CALIBRATION and CHAlstEL FUNCTIONAL TEST operations for the M00E5 and at the frequencies shown in Table 4.3-2. v. .

4.3.2.2 The log 1c forbbypes'ses shall be demonstrated OPER ALE du at power CHANNEL Ft98CTIONAL TEST of channels affected by bypass operation.

The total bypass function shall be demonstratad CPERA8LE at least once per 18 months bypass during CHAletEL CALISRATION, testing of each channel affected by operation. *

• t

! 4.3.2.3 The ENGINEERED SAFETY FIATURES RESPONSE TIME of each ESFAs shall be desenstrated to he within the limit at least once per la months.

t Each test chall include at len t one channel per function such that all channels are tested at,1dast mee every N times 18 months where M is the total number of redundant channels in a spe:1fie ESFA5 function as shown in the "Total No. of Channals" Colqun of Table 3.3-3.

i l

Continuous monitoring and sampling of the containment purge exhaust directly j

from the purge staev shall be provised for the low and high volume (8-inch and 42-inch) containment purge prior to startup fellowing the first refueling outage.

Containment airtorpe monitor 3RT-7004-1 er 3RT-7807-2 and associates

• sempting media shall pcrfom these functions prior te initial criticality.

i Free initial criticality to.the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sampBng media shall j perfore the above mquired functions. l l SAw "1FRE-UNIT 3 NOV 15 !!!2 I

3/4 3 13 '

I

l l

l l

TA8LE 3.3 3 (Continued) '

TAlt.E NOTATION (a) Trip function may be bypassed in this M00f when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressun is greater than er equal to 400 psf a.  ;

(b) An $1A5 signal is first necessary to enable CSA5 leg'ic.

(c) Actuated equipment only; does not result in CIAS.

9 The provis1ons of Spectf f cat 1on 3.0.3 are, net applfcable.

The provisions of Specification 3.0.4 are not applicable.

i **

With irradiated fuel in the storage pool.

{

ACTION STATEMENTS .

.r ~1 ACTION 8 -

With the numbei of OPERA 8LE channels one less than the Total Number of Chasnels. restore the inoperable channel to CPEAASLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAM8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOW within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 9 -

With the number of channels OPERA 8LE ene twas than the Total !

Number of Channels STAATUP and/or POWEA OPERAT10N may continue provided the inoper,able channel is placed in the bypassed er tripped conditien within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is bypassed, the'. desirability of asintaining this channel' in i the bypasse(condition shall be mytowed in accordance with

' specification 8.5.1.6e.

The channel shall be returred to 0*ERARLE status ne later than during the next COLD SHUTDOW. l With a channel process measurement etreuit that affects oultiple functional units inoperable or in test, bypass or trip all associated

. . . , . functional units as listed below.

Process Mea'eurement Circuit Functfenal Unit typassed t

1. Containment Pressure - High . Containment Pressure High (ESF)

Containment Pressure - High (RPS)

2. Steam Generator Pressure -

Low Steas Generator Pressure - Low Steam Generator AP 1 and 2 (EFAS)

' 3. Steam Generator Level Steam Generster Level - Low 5taas Generatar Lesel - High ,

! Steam Generator AP (EFAS) l

/

i i -

t l

p 15 M SAN ON0FRE-UNIT 3 3/4 3 13

l l

l INSTRUNENTATIGH INCORE DETECTOR $

l LINITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERA 8LE with:

a. A01ea's t 75X of all incore detector locations, a$d

b. ijjnfaus 5f Ewo quadrar,t symmetric incore detector locations per I core quM rent.  !

I I

An OPERA 8LE incore detector location chall consist of a fuel assembly  !

containing a fixed detector strino with a minious of four OPERA 8LE rhodium detectors p en OPERA 8LE wavable incore detector capable of mapping the location. - '

i A,PfLZ431LITY: Wh ? the incere datection system is used for monitoring: l

a. AZIMiflWL?OWhR TILT, -

b. Radial Peadag Factors, .

c. Local Power Gensity,

d. BM8 Margin. '

ACTION:

With the incore $et.aWan'systes.lmrable, do not use the system for the -

above applicabl9 u ni @ ring or calibration functions. The provisions of Specificat hns 3.0 3 vsd 3.0.4 are not appitcable.

SURVEILLAN 1 E R TRD O TS _  ;

4. 5. 't The coh detecf5 ystem shall be demonstrated OPERA 8LE:

a. By performance ef s QiANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use if  ;

7 or more dayt havet elapsed since the previous check and at least 3 l once per 7 dag tlhireafter when required for monitoring the AZINUTHAL POWER TILT, Paqel peeking fr;$ tors, local powcr density ce DN8 margin: )

b. kleak once par 18 modus by perforseme of a CHANEL CALIBRATION operation which exempts the neutten detwcLors but includes all slectronic components. The neutron detectors shall be calibrated )

prior to installation in the reactor core.  ;

l SAM ONCFRf a l

t 117 ) f ' 3/4 3-41 AMEM0 MENT N0. 38 l i

, /

INSTRW4ENTATION SEISMIC INSTRUMENTATION

• t.INITING CONDITION FOR OPERATICM 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERA 8LE.

J .

APPLICA81LITY: -At all times.

ACTION- '- * ' ' " - ' '

a. With one or more seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.'9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERA 8LE status. . g'

+

b.

The provisions of Specifications 3.0.3 ana 3.0.4 are not applicable.;

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be -

demonstrated OPERA 8LE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-4. - * -

1

.. ~<* . . .

4.3.3.3.2' Each of the above seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event (one or I

' more valid bassent accelerations of 0.05g or greater) shall be restored to 0PERA8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION pe formed within 5 days.-

Data shall be retrieved from the accessible actuated instruments and analyzed to determine the segnitude of the vibratory ground motion. A Special Report shall be prepared and suhaitted to the Commission pursuant to

, $ pacification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon facility features important to safety. Each of the above seismic monitoring instruments which is actuated during a seismic event (one or more valid basemat accelerations of 0.05g or greater) but is not accessible during power operation shall be restored to OPERA 8LE status and a CHANNEL CALIBRATION perfonned the next time the plant enters H00E 3 or below.. A supp% tat.repor-t shall then be prepared and suositted to the

- Commission withih 10 days pursuant to Specification 6.9.2 describing the additional' data from these instruments.

! "shared system with san Onofre - unit 2.

l l . l SAN ONOFRE-UNIT 3 l3/43-42

$$ 15 l

J

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION" LIMITING CONDITION FOR OPERATION 3.3.3.4 The seteorological monitoring instrumentation chinnels shown in o

Table 3.3-8 shall be OPERA 8LE.

., APPLICA8ILITY: -At aI1 times.

ACTION: -

4. With one or more requirec meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Ccamission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for .  !

restoring the channal(s) to OPERA 8LE status,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS l 4.3.3.4 Each of the above seteorological monitoring instrumentation channels shall'be demonstrat2d OPERA 8LE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-!.

e e 8 eS

~ .

{

.r%=.p..:6-

~

O 0

1 1

1 x l l Shared system with San Onofre - Unit 2.

l I

%\' 1 D SAN ON0FRE-UNIT 3 3/4 3-45

l t

l l

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION

, 3.3.3.8 The rad!wetive Ifquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the 11alts of 5,m ification 3.11.1.1 are not exceeded. The alare/

trip setpcints of these ch&nnels shall be determined in accordance with the OFF5tTE 005E CALCULATION MANUAL (00CM).

APPt.!CA81LITY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alara/ trip setpoint less conservative +.han required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. l b.

With less than the einfaum number of radioactive liquid effluent monite.'ing instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to 0PERA8LE status within 30 days and, additienally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in the next Seelannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.136 are not applicable.

SURVEILLANCE WEOUIREMENTS 4.3.3.8.1 Each radioactive 11guld effluent monitoring instrumentation channel st'all be demonstrated OPERA 8LE by performance of the CHANNEL CHECX, SOURCE CHECK, CHNOIEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilu-tion to meet the site radioactive effluent concentration limits of Specifica-tion 3.11.1.1 discharge shall be determined to be operating and prwiding dilution to the structure, t

1 SAN ON0FRE - UNIT 3 3/4 3-64 MWOW(T NO. 44 i

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

1

1 INSTRtMENTATION RADI0 ACTIVE GASEOUS EFFLUENT NONITORIM INSTRUNENTATION I .

i U NITING Cole! TION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the Ifnits of Specification 3.11.2.1 are not exceeded. The alare/

the trip setpoints of these channels shall be determined in accordance with 00CN.*

APPLICA8ILITY: As shown in Table 3.3-13 ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alare/ trip setpoint less conservative than required by the abovo Specification, immediately suspend the release of radioactive gaseous channel inoperable, effluents sonitored by the affected channel or declare the b.

With less than the minimum number of radioactive gaseous effluent monitoring instruasntation channels OPERA 8LE, take the MTION shown in Table 3.3-13.

Exert best efforts to return the instret to OPERA 8LE status within 30 days and, additionally, if the inoperable instrument (s) runin inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c.

The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicatie.

SURVEILLANCE REQUIREMENTS

'4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demenstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CluMMEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

• Continuous monitoring and sampling of the containment purge exhaust directly from the purge stack shall be provided for the low and high voline (8-inch and 42-inch) containment purge prior to startup following the first refueling outage.

Containment airborne monitor 3RT-7804-1 or 3RT-7307-2 and associated sampling media shall perfore these functions prior to initial criticality.

From initial criticality to the startup following the first refueling outage i containment airborne monitor 3RT-7804-1 and associated sampling media shall perfore the above required functions. I i

JAN 111985 SAN ON0FRE-UNIT 3 3/4 3-69 l

M WE M NT NO. 20

f INSTRtMENTATION h 4

, a LOOSE-PART DETECTION INSTRUNENTATION d t.INITING ColWITION FOR OPERATION

.i l

3.3.3.10 The loose part detection systes shall be OPERA 3LE. L APPt.!CA81LITY: NODES 1 and 2. -

ACTION:

a. With one or more loose part det ion system channels inoperable for sore than 30 days, prepare and it a Special Report to the i 4

Commission pursuant to specification 4.9.2 within the next 10 days il outlining the cause of the salfunction and the plans for restoring U the channel (s) to OPERA 8LE status.

b.

j The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

F SURVEILLANCE REQUIRENENTS 4.3.3.10 OPERA 8LE by performance of a-Each channel of the loose part detection syst!

a.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, I b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per la months.

1 1

l JAN 111985 1 SAN ON0FRE-UNIT 3 3/4 3-76 ANOWENT NO. 20

i i

REACTOR COOLANT SYSTEM OVERPRf550RE PROTECTION SYSTEMS -

RCS TEMPERATURE I 285'F LIMITING CONDITION FOR OPERATION 3.4.8.3.1 At least one of the following overpressure protection systees shall be OPERA 4LE:

, s. The Shutdown Cooling Systen Relief Valve (PSV9349) with: i

' 1) A lift setting of 406

• 10 psig*, and

2) Relief valve isolation valves 3HYS337, 3HV9339, 3HV9377, and 3HV9370 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 285'F; M00t 5; M00E 6 with the reactor vessel head on.

s ACTION:

a. With the SOCS Relief Valve inoperable, reduce T,,, to less than 200*F, depressurize and vent the RCS through a greater than or equal to 5.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With one or both 50C5 Relief Valve isolation valves in a single 50C5. Relief Valve isolation valve pair (valve pair 3NY9337 and 3HV9339 or valve pair 3NV9377 and 3HY9378) cTosed, open the closed valve (s) within 7 days or reduce T to less than 200*F, depres-surite and veut the RCS through a Mater than or equal to 5.6 inen vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. In the event,either the 50C5 Relief Valve or an RCS vent is used to mitigata an RCS pressure transient, a special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initi-ating the transtant,.the effect of the 50C5 Relief Yalve or RCS vent on the transient and any corrective action necessary to prevent recurrence.

d. The provisions of specification 3.0.4 are not applicable.

SURVEILt.ANCE REQUIREMENTS 4.4.8.3.1.1 The 50C5 Relief Valve shall be doeonstrated OPERA 8LE by:

a. Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the SOCS Relief Valv.e i.s  !

being used for overpressure protection that SDC5 Relief Valve  !

isolation valves 3HV9337, 3HY9339, 3HV9377, and 3HV9378 are open.

/

\ -

"The lif t setting. pressure applicable to valve temperatures of less than or equei to uC*F.

I SAN ONOFRE-UNIT 3 3/4 4-33 N1

1

,- '% * \

tl

!I L

REACTOR CO0t. ANT SYSTEM }

3.4.9 STRUCTURAL INTEGRITY .

LIMITING CON 0! TION FOR OPERATION 3.4.9 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.9.

J Appl.!CASILITY: ALL MODES M:

'I a.

With the structural integrity of any ASE Code Class 1 component (s) not conforming to the above requirments, restore the structural integrity of the affected component (s) to withirt its limit or isolate the affected component (s) prior te increasing the Reactor

(.

?

Coolant System temperature more than 50*F above the minimum -

+

. temperature required by NOT considerations.

b.

With the sc vetural integrity of any AS E Code Class 2 component (,

not confort ng to the above requirements, restore the structural

• integrity on the affected component (s) to within its limit er isolate the affected component (s) prior to increasing the Reactor Conlant System temperature above 200*F.

c. With the structural integrity of any ASME Code Clasr 3 component (s) not conforming to the above- requirements, restore the structural integrity of the affected component to within its 11af t or isolate the affected camponent from service.

d. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCEREQUIREMNf5 4.4.9 Is' addition to the requirements of Specification 4.0.5, each Reactor Coelant pump flywheel shall be inspected per the recommendations of Regulatory Position C'.4.b of Regulatory Guide 1.14, Revision 1 August 1975.

/

h -

e em SAN ONOFRE-UNIT 3

- \$1 3/4 4-34

PLANT SYSTEMS -

3/4.7.7 SEALED $00RCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7 Each sealed source containing radioactive asterial either in excess of 100 microcuries of beta and/or gamma esitting material or 5 aicrocuries of

' alpha emitting asterial shall be free of greater than or equal to O.005 microcuries of removable contamination.

APPLICAATI TTY: At all times.-

ACTION:

a. With a sealed source having removable contamination in excess of the above limit, withdrew the sealed source from use and either:

1. Decontaminata and repair the sealed source, or I

2. Dispose of the sealed source in accordance with Condission Regulations.

b.

The provisions of Specifications.3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS c ,

4.7.7.1 Test Requirements - Fach sealed source shall be tested for leakage.

and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Consission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 aferocuries per test sample.

4.7.7.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequencies described below.

a. Sources in use - At least once per six months for all sealed sources containing radioactive material:

1. With a half-life greater than 30 days (excluding Hydrogen 3),

and

2. In any form other than gas. y NOV 151981 SAM OMOF8T-UNIT 3 3/4 7-25

\

REFUELING OPERATIONS I

i 3/4.9.9 CONTAINMENT PURGE ISCLATION SYSTEM '

LIMITING CONDITION FOR OPERATION i

3. 9. 9 The containment purge isolation systas shall be OPEAA8LE.

APPLICA81LITY:

Ouring CORE ALTERATIONS or movement of irradiated fuel within

, the conta1neent.

ACTION:

- With the containment purge isolation system inoperable, close each of the '

containment purge penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provisions of Specification 3.0.4  !

are not applicable. .

.A

. I SURVEILLANCE REQUIREMENTS

. . ~ .

4.9.9 The containment purge isolation system shall be demonstrated OPERA 8LE l within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior..to.the. start of and at least once per 7 days during CORE ALTERATIONS by verifying ~that containment purge valve isolation occurs on manual initiation and on a high radiation test signal. .

/

~

NOV 151982 SAN ONOFRE-UNIT 3 3/4 9-10

, . , , - . , - . , - - , , - . , , , - . , . - . . _ . _ , , . - ,,,-,..,,.,-.,._,--_._..n._. , , , ,

1 l

l REFUELING OPERATIONS 3/4.9.12 FUEL NAN 0 LING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEN LINITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter systees shall be OPERA 8LE.

APPLICA8!LITY: Whenever irradiated fuel is in the storage pool.

ACTION:

a.

With one fuel handling building post-accident cleanup filter system inoperable, fuel movement within the storage pool or operation of fuel handling eachine over the storage pool may proceed provided the OPERA 4LE fuel handling building post-accident cleanup filter system is capable of being powered from an OPEAA8LE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal absorbers.

b.

With no fuel handling building post-accident cleanup filter system CPEAA8LE, suspend all operations involving movement of fuel within the storage pool or operation of fuel handling eachine over the storage pool until at least one fuel handling building post-accident cleanup filter systes is restored to OPERA 8LE status,

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling building post-accident cleanup filter systees shall be demonstrated OPERA 8LE:

a . u .a . )

a. At least once per 31 days on a $7AGGERED TEST 8 ASIS by initiating, from the control roce, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the-heaters on. ~ ,

4

b. At least once per 18 months or (1) after any structural saintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone I consunicating with the system by: l l

I l

SEP 3 01985 i san ON0FRE - unit 3 3/4 9-13 AMEN 0 MENT N0. 25 i i

l

I RADI0 ACTIVE EFFLUENTS 99)${

)

.l t,INITING CON 0! TION FOR OPERATION l

3.11.1.2 The dose or dose commitment to an individual free radioactive  !

materials (see Figure in 5.1-4) liquid effluents shall be limited: released, from each reactor unit, from the site l t

a.

. - During any calendar quarter to less than or equal to 1.5 ares to the -!

, total body and tg.1.ess than or equal to 5 ares to any organ, and i

b.

During any calendar year to less than or equal to 3 mrom to the tott.) body and to less than or equal to 10 ares to any organ.

APPLICA8It.ITY: At all times.

ACTION:

a. d t With the calculated dose from the release of radioactive materials

• in liquid effluents exceeding sny of the above Itaits, in lieu of' )

any other report required by Specification 6.9.1, prepare and submit I to the Ceanissiw within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the Itait(s) and. defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.1.2 b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicaele.

SURVEILLANCE REQUIRD WITS i

i 4.11.1.2 Dose Caleviations. Caulative dose contributions from liquid effluents 31 days. shall be detemined in accordance with the 00CM at least once per

' / };0'! 1 U UN

. 1 l

t SAN ON0FRE-UNIT 3 3/4 11-5

. _ _ . , . _ , _ . , . , _ , _ _ _ . , _ - . . . _ _ _ , _ r , ...... . _ _ _ . _, - . . . . - . . . . , - , _ . ,

4 RADI0 ACTIVE EFFLUENTS LIQUID WA$TE TREATMENT l LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment systes shall be OPERA 8LE. The appropriate portions of the systes shall be used to reduce the radioactive ,

j

• asterials in liquid wastes prior to their discharge when'the projected doses 1 due to the liquid affluent from the site (see Figure 5.1-4) when averaged over

. 31 days, would exceed 0.06 area to the totaT body or 0.2 ares to any organ."

APPLICA81LITY: At all times.

ACTION:

(

a.

With the liquid radweste treatant system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other.

report required by Specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information: -

, 1.

Identification of the inoperable equipment or subsystems and the reason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to CPERA8LE states, and 3.

Summary description,of action (s) taken to prevent a recurrence, b.

The provisions of Specifications 3.0.3 and 3.0.4 are not appitcable.

SURVEILLANCE REQUIREMENTS  !

4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.1.3.2 The liquid radweste treatment system shall be demonstrated CPERA8LE by operating the liquid radweste treatment system equipment for at least 15 minutes at least once per 92 days unless the liquid radwaste systen hasdays.

92 been utilized to process radioactive liquid affluents during the previous n -

Perreactorupit HOV 15 M82 SAM ON0FRE-UNIT 3 3/4 11-6 i

l

( RADICACTIVE EFFLUENTS LIQUID W LDtF TANKS LIMITING CON 0! TION FOR OPERiTION

3. u.1.4 The quantity of radioactive material contained in each outside temporary tritita tank shallorbeentrained and dissolved limited tonoble less than or equal to 10 curies, excluding gases.

o APPLICA81LITY: At all times. , _,

ACTION:

a.

With the quantity of radioactive material in any outside temporary tank exceeding the above limit, immediately suspend all additions of radioactive contents to antarialwithin the to the tank and within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> limit.

• reduce the tank b.

TheprovisionsofSpecifications3.0.3and3.0.4arenotapplicahe.

SURVEILLANCE REQUIRDENTS

4. U.1. 4 The quantity of radioactive material contained in each outside temporary tank shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

x v.!:

f i NOV 151982 SAN ONOFRE-UNIT 3 3/4 u-7

.E'

- kb~. ".

RADICACTIVE EFFLU(MTS 005 - N0s 0 sasEs .

A. .

LIMITING CONOTTTON FOR OPERATION l

3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following: -

. a. During any calendar quarter: Less than or equal to 5 arad for gamma radiation and less than or-equal--tede-erad for beta radiation and, b.. Curing any calendar year: Less than or equal to 10 erad for gamma radiation and less than or equal to 20 arad for beta radiation.

APPLICABILITY: At all times.

ACTION -

I d

a. With the calculated air dose free radioactive noble gases in gaseous effluents exceeding any of the above limits, in lieu of any otherf report required by Specification 8.9.1, prepare ano submit to the -

( Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the Ifeit(s) and defines the corrective actions taken to roouce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.2.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Cose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the 00CM at least once per 31 days.

[

- .NOV 151962 SAN ONOFRE-UNIT 3 3/4 11-12 .

RA0!0 ACTIVE EFFLUENT $

DOSE - RA0!0I00!NES RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM j l

l LINITING CON 0! TION FOR OPERATION l

3.11.2.3 The dose to an individual from tritius, radiofodines and radioact,ive materials in particulate fore with half-lives greater than 4 days in gaseous effluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 ares to any organ and,

b. During any calendar year: Less than er equal to 15 ares to any organ.

c. Less than 0.1% of the Itaits of 3. u.2.3(a) and (b) as a result of burning contaminated oil.

APPLICA8ILITY: At all times. .

M:

a. With the calculated dose free the release of trittua, radiofodines, and radioactive estarials in particulate fore, with half Ifves greater than 8 days. in gaseous effluents exceeding any.of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to '

reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with specification 3. u.2.3.

b. The previsions of Specifications 3.0,3 and 3.0.4 are not applicable.

SURVIILLANCE REQUIRDENTS

4. u.2.3 Does calculattenj Cumulative dose contributions for the current calendar quarter and current calender year shall be determined in accordance with the 00CM at least once w e 31 days.

I SAM ONOFRE-UNIT 3 3/4 H-13 AMEMOMENT NO. 41

i RADI0 ACTIVE EFFLUENTS i

GASE0US RADWASTE TREATMENT LINTTING C09CITION FOR OPERATION i

3.11.2.4 The GA$E005 RADWASTE TREATMENT SYSTEM .and the VENTILATION E TREATMENT SYSTEM shall be OPERA 8LE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous wasta prior to their discharge when the projected gaseous effluent air  !

doses due to gaseous effluent releases from the site (see Figure 5.1-3), when ,

averaged over 31 days, would exceed 0.2 ered for gassa radiation and 0.4 erad l for beta radiation. The appropriate portions of the VENTILATION EXMAUST TREATMENT SYSTEM shall he WJd to reduc's radioactive mat'arials in gaseous -

wasta prior to their Sscharge when the projected doses due to gaseous i effluent releases frM. the site (see Figure 5.1-3) when averaged over 31 days i would exceed 0.3 ares to any organ.",

, 1 APPLICA8ILITY: At all times.  !

ACTION:

? i a.

WiththeGASE005RADWASTETREATMENTSYSTEMand/ortheVENTILATION EXHAUST TREATNENT SYSTEM inoperable for more than 31 days or witA I I gaseous waste being discharged without treatment and in excess of '

the above limits in lieu of any other report required by Specifica-tion 6.9.1, prepa,re and submit to the Comission within 30 days,  ;

pursuant to Specification 6.9.2, 'a Special Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability.

" 2. Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and

3. Summary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIRDENTS I

4.11.2.4.1 Boses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.2.4.2 The GASE005 RADWASTE TREATNENT SYSTEM and VENTILATION EXHAU TREATMENT SYSTEM shall be demonstrated OPERA 8LE by operating the GASEOUS itA0 WASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATNENT SYSTEM l equipment for at least 15 minutes, at least once per 92 days unless the appropriate systes has been utilized to process radioactive gaseous effluents f during the previous 92 days. -

These doses are per reactor unit.

g/1. 5 B61.

SAM ON0FRE-UNIT 3 3/4 11-14 l

l

Q$7.}- .

1..

( RADICACTIVE EFFLUENTS -

EXPT.051VE 6AS MIXTURE t.INITING COM ITION FOR OPERATION

3. u. 2. 5 Yhe concentration of oxygen in the weste gas holdup system shall be limited to less than or equal to a by volume whenever the hydrogen concentration exceeds 4 by volume.

APPLICA8!LITY: At all times.

ACTION:

a.

With the concentration of oxygen in the weste gas holdup system greater than 3 by volume but less than er equal to 4 by volume, restore the concentration of oxygen te within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. -

b.

With the concentration of oxygen in the waste gas.helde system g, greater than 4 Wy volume, immediately suspend an additions of -7 weste gases .to the system and reduce the concentratten of oxygen tb less than 4 by volume within one hour and less them or equal to S by volume within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br />.

(

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS '

4. u. 2. 5 The concentrations of .Yj4,+n and oxygen in the weste gas holdup systen shall be determined to be within the above limits by continuously moni-toring the waste gases in the waste gas holdup system with the hydrogen and oxygen monitors required CPERA4LE by Table 3.3-13 of specification 3.3.3.9.

e

/

HOV 15192 SAM ONOFRE-UNIT 3 3/4 u-15

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

..b - f - r . ..

3 .,. 4.m.-

( RADI0 ACTIVE EFFLUENTS

• l 3/4.11.3 Sof.IO RADICACTIVE WASTE l

t.IMITING CONOTTION FOR OPERATION 3.11.3 The solid radweste system shall be OPERABLE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the 50LICIFICATION and packaging of radioactive wastas to ensure meeting the requirements of 10 CFR

• Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICA8ILITY: At all times."

ACTION:

a.

With the packaging requirements of 10 CFR Part 20'and/or 10 CFA Part 71 not satisfied, suspend shipments of defectively pachgd '-

solid radioactive wastas from the site. .

sj b.

With the solid radweste systendnoperable for more than 31 days, fn I lieu of any other report required by $pecification 6.9.1, presa  ;

and submit to the Consission within 30 dMys pursuant te Specift.

tion 6.5.2 a Special Report which includes the following. informat on:r 1.

Identification of the inoperable equipment er subsystaes and the reason for inoperability, 2.

Action (s) taken to rester the inoperable equipment to OPERABLE status. ' '

3.

A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastas, and 4.

Summary description of action (s) taken to prevent a recurrence.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

$URVEtt. LANCE REQUIRE ef75

• 4.11.3.1 The solid radwaste system shall be demonstrated CPERANLE at least once per $2 days by:

a.

Operating the solid radweste systas at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or b.

Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL

[ PROGRAM. /

"See Specification 6.13.1.

ygy 15 482 SAM ONCFRE-UNIT 3 3/4 11-17 4

f- .-

'E g.

[ RADIDACTIVE EFFLUENTS .

3/4.u.4 TOTAL 005E

- .hr '

1 LIMITING COICITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, free uranium fuel cycle sources shall 3

be limited to less than or equal to 25 seem to the total body or any organ (except the thyroid, which shall be lietted to less than or equal to 75 area) over 12 consecutive months.

AP5LICA81 LIT /: At all times.

ACTION:

a.

With the calculated doses from the release of radioactive saterials in liquid or gaseous effluents exceeding twice 14*11mits of Specification 3.11.1. 2.a. 3.11.1.2.b. 3.11.2.2.av 3.17.2.2.b.

3.11.2.3.a, or 3.11.2.3.b, in lieu of any otheit report. required Specification 6.9.1, prepare and submit a special Rupert to the

)

Directori Nuclear Reactor Regulation, U.Si Necteer Regulatory . 1 Commission Washington, D.C. 20555, within 30 daye, unicft dati i  !

[ the corrective actien to be taken to reduce subsequent reimases to i prevent recurrence of exceeding the limits of. Specificaties 3.u.4.

This Special Report shall include an analysis which estiestes the radiation exposure (dosa) to a member of the pubite from uranium l fuel cycle sources (including all effluent pathways and direct. l radiation) for a 12 consecutive month period 1that includes the l release (s) covered by this report. If the estimated dese(s) exceeds I the limits of Specification 3.u.4, and if the release condition resulting in violation of 40 CFR 190 has not already been carrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of $ 190. u(b). Submittal of the report is considered a timely request, and a variance is granted until staff action en the request is complete. The variance only relatas to~the limits of 40 CFR 190, and does not apply in any way to the require-menta for dose limitation of 10 CFR Part 20, as addressed in other

, sections of this technical specification.

b. The previsions of specifications 3.0.3 and 3.0.4 are not appitcable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dose calculations Cumulative dose contributions from liquid and gaseous affluents shall be detarsined in accordance with $ppcifications e

4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with tNe 00CM.

NOV 15 082 SAM ONOFRE-UNIT 3 3/4 u-19 L

l . l l '

l l

• i

(' 3/4.12 RA010 LOGICAL ENVIRONMENTAL MONITORING l l

3/4.12.1 W NITORING PROGRAM i

LIMITING CONDITION FOR OPERATION I i

3.12.1 The radiological environmental sonitoring program shall be conductec as specified in Table 3.12-1.

APPLICA8!LITY: At all times. -

ACTION:

a.

With the radiological environmental monitoring progree not being --- 4 conducted as specified in Table 3.12-1, in lieu of any other report i required by Specification 4.9.1, prepare and subett to the Coe- I mission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the planc for preventing a recurrence, b.

.I With the level of radioactivity in an environmental sampling medi exceeding the reporting levels of Table 3.12-2 when averaged ove any calendar quarter, in lieu of any other report requirst by Specification 6.9.1, prepare and submit to the Commission within 30 days free the end of the affected calendar quarter a Aspert f pursuant to Specification 6.9.1.13. When more than one of the  :

radionuclides in Table 3.12-2 are detected in the sampling medium, '

this report shall be submitted if:

i concentretian. (1) , concentration (2) + * * '> 1.0 limit level (1) limit level.(2) -

When radionuclides other than those in Table 3.12-2 an detected and are the result of plant effluents, this report shall be subsitted if the potential annual dose to an individual is equal to or gnater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not nquired if the sessund level of I radioactivity was not the result of plant effluents; however, in '

such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With fresh leafy vegetable samples or fleshy vegetable samples unavail-eble from one or more of the sample locations requi nd by Table 3.12-1, in lieu of any other report required by specification 6.9.1, prepare and submit to the Commission witMn 30 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavall-ability of samples and identifies locations for obtaining replacement

' samples. The locations free which samples were unavailable may then be deleted from those required by M a t 12-1, provided the locations from which the replacement samples were obtained an added to the environmental monitoring program as nplacement locatic.1. j

/ d.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

p 15 382 l SAN ONOFRE-UNIT 3 3/4 12-1 ~ ' '

i 1 1

}

. .h n, .,

RADIOLOGICAL ENVIRONMENTAL HONITORING 3/4.12.2 LAJS USE CENSUS t,INITING C0lWITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest afik animal, the nearest residence and the nearest garden

• of greater than 500 square feet producing fresh leafy vegetables in each of the 18 meteorological sectors within a distance of five miles. For elevated releases as defined in Regulatory Guide 1.111, Revision 1. July 1977, the land

• use census shall aise identify the locations of all ailk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in

. each of the 14 meteorological sectors within a distance of three siles.

APPLICA8ILITY: At' all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Spucification 4.11.2.3, in lieu of any other report required by Specification 6.9.1., prepare and submit to ,

Commission within 30 days, pursuant to Specification E.9.2, a ,-

Special Report which identifies the new location (s). -

b.

With a land use census identifying a location (s) which yields a-f calculated done or dose commitment via the same exposure pathway 20 percent greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, irr.

lieu of any other report required by Specification 4.9.1, prepare ';.

ahd submit to the Cosmission within 30 days, pursuant to Specifica '

tion 4.9.2, a Special Report which identifies the new location. Th's new 1ccation shall be added to the radiological environmental e monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose or dose comunitaent via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not appifcable.

$URVEILLANCE REQUIRD O TS 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide by the best consulting results, local such asauthorities.

agriculture by a door-to-door survey, aerial survey, or

^

8 road leaf vegetation sargling any be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.

e

/

ucy L 5 \WE SAN ONOFRE-UNIT 3 3/4 12-11 i

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

~

,_[*,5.~"*'$ ,. '.

( RADIOLOGICAL ENVIRO

• ENTAL McMITORING 3/4.12.3 INTIALA80RATORY COMPARISON PROGRAM LIMITING TTION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission.

APPLICA8!LITY: At all times.

, .ASCTTI2:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report,

b. The previsions of Specifications 3.0.3 and 3.0.4 are not applicable.

u. 4

$URVEILLANCE REQUIREMENTS '

w .

4.12.3 A summary of the results obtained as part of the abews' required Interlaboratory Comparison Program and in accordance with the 00CM shall be included in the Annual Radiological Environmental Operating Report.

e 80 NOV 151982 SAN ONOFRE-UNIT 3 3/4 12-12

l 1

(" 3/4.0 APFLICA81LITY l

l BASES The specifications of this section provide the general requirements applicable to each of the Limiting Ccnditions for 0peration and Surveillance Requirements within Section 3/4.

3.0.1 This specification defines the applicability.of each specification in tems of defined 9PERATIONAL 20E5 or other specified cocditions and is provided to delineate specifically when each specification is applicable.

3.0.2 This specification defines those conditioes necessary to I constitute compliance with the terms of an individual Liciting Condition for Operation and associated ACTION requirement.

3.0.3 This specification delineates the setsures to be taken for '

ciretastances not directly provided for in the ACTION statements and whose occurrence would violate the intent of a specification. For example.

" Specification 3.6.2.1 nouires two Containment Spray Systans te be OPERA 8LL and provides explicit ACTION requirements if one spray system is inoperable.

Under the terms of Specification 3.0.3, jf both of the required Containment Spray Systans an inoperable, wit.'.ir. one ' hour esasures must be initiated to I place the unit in at least NOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. in at least HOT SHUTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in COLD SHUTDOW in the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.0.4 This specification provides that entry into an OPERATIONAL N00E or other specified applicability condition must be ende with (a) the full com- ,

plement of required systase, equipment or components OPERA 8LE and (b) all '

other parameters as specified in the Limiting Conditions for Operation being met without regard.fot alloweblo deviations and out of service provisions contained in the ACTION statements.

~

4 The intent of this prevision is to insure that facility operation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded.

4  !

Ocaptions to this specification have been provided for a limited number of specifications when startup with inoperable equipment would not affect plant safety. These exceptions are stated in the ACTION statements of the appropriate specifications.

,. /

. . . . NOV 151952 SAN ONOFRE-UNIT 3 8 3/4 0-1 I  ;

i

. . _ _ _ _ _ - _ _ _ _ . _ _ _ . - . _ . . . _ . , _ _ . - . - _ , - - _ . _ , _ _ . _ . . . . _ _ _ . , - _ _ _ . . . . ,_ _ ,_._,,.n..nn-,_--

' )

c 8ASE5 -

)

l 4.D.L This specification provides that surveillance activities necessary to ensure the Lietting Conditions for Operation are met and will be performed i during the OPERATIONAL MODES or other conditions for which the Limiting Condi- d tions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.

Surveillance Requirements for Special Test Exceptions need only be performed

, when the Specia) Test Exception is being utilized as an exception to an

, individual specification.

420.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary- to provide operational flexibility because of scheduling and performance considerations. The phrase

."at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performanca of more frequent [

surveillance activities.

. ./ ' ' i The tolerance values, taken either individually or hec,u_tively over* 'A

'three test intervals, are sufficiently restrictive to ensure that tha .

reliability associated with the surveillance activity is not significantly degradx! beyond that obtained from the nominal specified interval.

( , . , 4 4.0.3 The provisions of this specification set forth the criteria for detaraination of compliance with the OPERASILITY requirementa of the Lfaiting Conditions for Operation. Under these criteria, equipment, systaes or components are assumed to be OPERA 8LE if the associated surveillance activ-ities have been satisfactorily performed within the specified time interval. -

Nothing in this provision is to be construed as defining equipment, systems or components OPERA 8LI, when such items are found or known to be inoperable although still meeting the Surveillance Requirements. '

)

1 i

l r /

"~' 15 1982 SAM ONOFRE-UNIT 3 8 3/4 0-2

l BASES 4 4.0.4wDris specification ensures that the surveillance activities associatedvith a Limiting Condition for Operation have been performed within the specified time intervat prior to entry into an OPERATIONAL MODE or other applicable condition.

The intent of this provision is to ensure that surveil-lance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERA 81LITY requirements of the Limiting condition for Operation.

Under the tares of this specification, for example, during initial plant

' startup or following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the systaa or equipment into OPERA 8LE status.

4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of AS M Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI' of the ASE Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. Relief from any of the above requirtiments ha been provided in writing by the Commission and te not a part' of these Techn, }

Specifications. 'e .

f Thisspecificationincludesaclarificationofthefrequenciesfor-performing the inservice inspection and testing activities required by section XI of the ASM 5eiler and Pressure Vessel Code and appitcable Addenda.

This clarification is provided to ensure consistency in surveillance intervals thoughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and tasting activities.

Under the teres of this specification, the more restr etive reqvf rements of the Technical Specifications take precedence over the ASME Soiler and Pressure Vessel Code and applicable Addenda. For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIbHAL MODE or other specified appitcability condition takes precedence over the ASME loiler and Pttssure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation. And for example, the Technical Specification definition of OPERA 8LE does not grant a grace period before a devica that is not capable of performing its specified  ;

function is declared inoperable and takes precedence over the ASME sotter and s Pressure Yassel Code provis % which allows a valve to be incapable of '

performing inoperable. its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared

,. /

NOV i 5 E'?

SAR CN0FRE-UNIT 3 8 3/4 0-3 l

l l

l l

NPF-10/15-238 4

ATTACHMENT "C" f

1

i i

I I

i 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS b 3/4.0 APPLICABILITY LINITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specificatione it required during the OPERATIONAL MODES or other conditions specified ther+1- except that upon failure to meet the Limiting Conditions for Operatiu. .ne associated ACTION requirements shall be met.

3.0.2 Noncompliance withr a specif Nation shall exist when the requirements of the limiting Condition for Operation ar.d/or associeted ACTION requirements are .i not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requireinents, within one hour, action shall be initiated to place the unit in a M00E in which the specification does not -

apply by placing it, as applicable, in:

1. At least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLD SHUT 00WN withia the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirement; the ACTION may be taken in accordance with the specified time limits as nMw.re d from the time of failure to meet the Limiting Condition for Operation. . e (1o.95 to these requirements are stated in the individual s pec i f i ca t'.ons .

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions of the Limiting Conditior; for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACf!ON requirements when conformance to them permits continued operation of the f;cility for an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual specifications.

SAN ONOFRE - UNIT 2 3/4 0-1 a

, ; y - -. . .. --

• c x lv .

\  %

, s ,a \ r T . ,

APPLICA64MY -

,~

s .. s ,

E.Phlidd!6f. dell.QMENTS,,,.

. - . y s - s

• 44,15 Suheillance Reg'uiremstM shall t'e,applichble during the OPERATIONAL N00ES 4r other conatbns specified for i~ndividual Limiting Conditions for Operathn un?ess otherwise stated in an indtyjdusi Serveillance Requirement.

,e , s -

4.0.2 Each Surteillar.ce Requirement shall be performed within the specified ,

time b,ttuvay . ,>

with:

, a. A'maximumallowabloextension.nottoexceed'!5kofthesurveillance '

'ditertai, arid J <

l 6 ,

-r, .. a

b. Sia caabined time interval for sny 3 consecutiv/sutvdillance intervals not to exceed 3.25,titms 'the specifind suppl 11ance

.iFier r a( e ,' -  %

4 [ ,

4.0.3 FailuretoperformaSurveillanc,eRequiremen(withintheallowe.i sutveillance interval, defined by specificatiory4.0.2,* shall constitute noncorpliance with the 0? ERA 0;LITY r.:quirements for ?. Limiting Condition for Operation. -The. time litalts of the ACTI6)N requiree.entsare, applicable at the tifw it is idsntified that a Survelihnce Re,quirement has not been performed.

The. aCUON rfquire:nents may be delaped for up 40 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tu, permit the completion of the surveillance when the allowable outage tiret limits of the '

ACTION requirments are less than 21, hour 2. 'Surtvillance Requirements do not have to be performeri on inoperab'a fquipme3t.  ?

s .

4.04

• Entry intian CPEWAT!D*fAL' dNE. or other specf hedio'ndition shall not be fandt unldt; the SurveiDat?.e Re$irerentti) assocYated with the Limiting l Condition for 9pertyion have been perfer%:d within the I$cted surveillance '

interval or as otherwit'e'icicified. This provision shall n'ot prevent passage through er to OPEl'ATIOMN. 3043 as required to comply with ACTION requirements.

4 '.0 . 5 Surveillance Rc'40irer$nts for intervice inspection aktesting of ASME C0deClass1,2,and3componenl4yhallbyappliep0leasfollows': -

a. . Inservice inspection of ASME code Cliss 1, 2 and 3 components and

.inservict testing ASME Code fiass i, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Ves'se) Code and applicable Addenda es required by i 10 CFR 50, SectNn 50.55a(gh except where, specific written I

relief has been granted by the' C W ission pursuant to 10 CFR 50,

.Secthi50.55a(g)(6)(1). ' ,

b. Surveillance intervals spe:ified.in Sectio 6 XI of the ASME Boiler and Pressura Vessel Code and apolicable Adde'ida for the inservice  ;

inspe: tion,and testing activities required by the ASME Boiler and  !

Dressure Vessel Code and abplicable Addenda shall be applicable as follows in these Technical Specificatiors:

4 4

SAN ONOFRE - UNIT 2 3/4 0-2

, p. - - - - - -. , - - - , , - n . ,.--.w -----

t

: : INS 8'.*EN?a ::s

, 3 -

.  ::a-t..-

. .:. ..y c , . w r. i : - . .,

.. ...s. .. ....

. . . .. . .. y r.g .:::a-.

y 3.3.1 As a m'nimum, tee sa:::P :P:tective instru.entation :na9 mets an:

f: asses o' Ta 1e 3.3-1 snail me CPEAA!.! wita RESFCN5! 7:.wi$ as sac n tr.

Ta:'e 3.3-2.

A 8 8 '. : : ! * '. : v: As snown in Tacle 3.3-1.

A *::N:

As sne n in Tarle 3.3-1.

SL'8v!! L'.AN ! E!!'.'! E!w!NTS 4.3.1.1 !a n rea:::e :Petective instrumentation cMannel ssall me :emenst. ate '

C854A!LI ty tre :er* r ance of sno CHANNEL Ch!CX, CHANNEL CAL *3 RAT CN and CsANNE. F.'NCT CNAL TEST c:erations for tne .MCCi; an: at ne 'rectancies sne -

i- Ta:ia 4.3-1 a.3.1.2 The legi: for ne :y: asses s all me cemens: ate: C8!RA5'.! :-1:r ::

en:n -en:::e startu: unless per':r e Owete; :ne =re:ectng $2 ca;<s. Tne :: al

':as: " n::icn snall :e cemenstrate: 08!RA!Li at lets: en:e :e- 18 T: ns

' ; :.-'NN!' . A'.!! RAT :N testin; " en:r. :nannel adfe:: : :j :y: ass

e - a'. : :n .

4.3.1.3 T e 8.!aC7CR TRIP $YSTEM R!37CN5! T;*! cf earn res:::.- :-4: ." n::i:9 snall e ce :nstrated to e witnin its limit at least once :er la te9:ns.

Ia:n test saali include at least one channel er fwn :ica swen Ms: all

nanret s r e tested at least onca every N times 18 menins unere N is tre :::a1

e. Oer of e:.ncant enannels in a specific res:: r tri: "w..ntion as sa:*n in

ne "Total No. c' Caannels" column of Tacle 3.3-1.

4. 3.1. 4 The isolation characteristics of esta CIA isolat en a.:it" er are d esca c:tical isolator for CIA Caleviat:r :: C:re ? rete::1:n Calcula::e ca:a transfer small be verifie: at least once per 18 montns caring ne sew:::=6 :er Ne following tests:

a. 8:e tre CIA ::siti:n is:14 ion'a.01tfiers:

1 A*:n 12C v:5:s AC (50 w:) a::?ie: ': 1: 'ess: 30 se:: :s a: :ts :Pe ca :::, se ret: n; :n :se i :.: ::es n:: es:se:

0.015 v:1:s -

1 l

I SAN ON;7t!-Un:7 2 3/4 3 '. j

- - - , , y

7:5.! 3.3-1 '::-ti veel

.-:.: ..I W:.h : e :.:tactive syste.. tri: breakers in the ci: sad ::si i:n, tre :!A

-ise s su- ca:a:le of CIA wi:n=ra al, a.-d feel in :ne rea:::r vesse!.

g (a) Tri: eay be ranually typassed above 10 a% of RATED THERPAL POLER; bytass snill be aut:matica11y removed when THEDtAL PCWEA is less taar er e:aal to 10'*. of RATED THEntAL POWEA.

(:) Trip may te manually by:assed belew 400 psia; bypass shall be aut::atically re. moved whenever pressurizer pressure is greater t?an er e:.a1 to 4C0 psia.

(c) Trip may te manually bypassed belew 10 % of RATED THERMAL POWEA; bypass ses11 te aui': atically reteved when THERMAL PCWER is greater than er; e: val to 10 % of RATED THERMAL PCWER. Ou-ing testing purcuant to '

5:t:ial Test Exce:ti:n 3.10.3, trip may be manually bypassed telcw 5% of UTED THERMAL PCVER; bypass shall be automatically removed when ThiXPAL P .EE is greater tnan er epdal to 5% of AATED THERFAL PC*aER.

(:) Tr': tay te ty:assac during testing pursuant : 5;ecial Test Ex:sp;t:r.3.'.0.3.

( e ', Ste 5:e:ial Tes; Exce::i:n 3.'.3.2.

(f) Ea:n :nannel shall ta c:.:rfsed of'two trip breakers; a:tual tri: 1:;i:

s s'.1 te cre-:ut-:f-: o taxen twice.

(;) 7-i may be typassac below 55% RATED THERFAL PCWER.

ACT:0N STATE.u!NTS A T::N 1 -

With the num:er of channels CPE.UELE :. e less than re:uire: :y tne Minimus Channels CPE.UBLE requirement, rest:re :na i .::erable channel to CPERABL! itatus wi:nin 43 h:urs er te i .

a: least HOT STANCEY within tne next 6 neurs and/:r ::e:S .e protective system trip breakers.

A T!:N2 -

With the nueter of channels CPERABLE : e less than the T::a!

Nue:er cf Channels, STARTiJP ane/or PC%EA CPERATICN may c:::H.e pr:vi ad the inoperaele enannel is pla::: in :ne ty;assac Or tri::ec c:nditi:n within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If tne ine:eratie enar. ei is .,

I ty;assec, :na desiratility of =aint7ining this cr.anrei i- :re ty:assed ::ncitica shall te reviewec in ac::r:ance wita  :

5:a:ificati:n 6.5.1.Se. The enannel snall te returne: :: 1 CP!.UELE status no later tnan carin; :na next C:L2 5.-UT::bN.

MAY i 61963 sn ::.:: E .n:Tz 3/4 3 4  ::EstMEN .s:. 1i ,

J

l l :s3 :vuts : ::N 3 /4 ].2 (NOIN!!IE3 $4Fi?V iia?U ( a 7Ua?! N IV$'IW I N $ ?I'."d!N I A * ::N

,:":-.s C:N*.!*!0N 'OR C*i:17: N '

3.3.2 The in;ineered Safety Feature Actuation System (ESFAS) instrueentation caannels anc cypasses snown in Tacle 3.3-3 shall be OPERA 8LE with ineir tris set:sints set consistent with the values snown in the Trip Setpoint column of Tasle 3.3 a anc with RESPCN5! TIMES as snown in Tanle 3.3 5.

a:3LICa8!LTY: As shown in Table 3.3-3."

4 ?!ON:

a. With an E5FA5 instrumentation channel trip setpoint less conservative than the value shown in the Allowanle vslues column of Table 3.3-4, ceclare the channel incoeranle and acoly the aoplicamle ACTION requirement of Table 3.3-3 until the channel is restored to OPERA 3LE status with the trip setcoint adjusted consistent with the Trip Satcoint value.

b. Vith an ESFA5 instrumentation channel inoperable, take the A* TION snown in Tacle 3.3-3.

SL:v!!LLaNCE REOUIREWENTS 4.3.2.1 Each ESFAS instrv eatation enancel small ee cemenstrate: 08!s;!.! :y t e :er'ermance of the CHANNEL CHECX, CHANNEL CALI!RATICN afd CHANNEL

.N;T;; SAL TEST c:eraticas for the MO:E5 anc at tne frecuen:les snown in Ta:1e 4.3-2.

4.3.2.2 The logic for the bypasses shall be demonstrated CPERASLE curing the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass coeration.

Tne total typass function shall be demonstrated OPERABLE at least once :er 18 months curing CHANNEL' CALIBRATION testing of each channel affectec Dy ty; ass operation.

4.3.2.3 The ENGINEERED SAFFTY FEATURES RESPONSE TIME of eaca !$FAS function shall be demonstrated to be within tne limit at least once per 18 montns.

Each test shall include at least one channel per function suca tnat all enannels are tested at lesst once every N times 18 montes wnere N is tse total

u. :er of recuncknt enannels in a sce:ific ESFA5 function as sacwn in the "Tetal Nc. of Onannels" Column of Tamle 3.3-3.

'5ee Soecial Test Exception 3.10.5

\

SAN CNOFRE-UNIT 2 3/4 3 13 I[$ 1 7 ggg

l 1

l 1

l l

- \

l Tatti 3.3-3 (Continued)  !

TA8f,f W TATTC_N (a) Trio fune:1on may to eysassee in this M00E wnen pressurizer pressure is less tnan 400 psia; cypass sna11 be automatically removed when pressuri:er pressure is greater than er equal to 400 psia.

(b) An SIAS signal is first necessary to enaale CSA5 logic.

(c) Actuated equipment only; does not result in CIAS.

The 4 revisions of Specification 3.0.3 are not applicable.

8 Wita irraciated fuel in the storage pool.

ACTION STATEMENTS ACTION 8 -

With the nuncer of OPERA 8LI channels one less than the Total Nummer of Channels, restore the inoperaale Charnel te OPIAASLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAN08Y within tne next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> anc in COLD SHUTDCWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTICH 9 - '

With the numoer of channels CPEAA8LE one less than the Total Hummer of Channels, STARTUP ana/or PCWER CetAATION say continue provided the inoperaale enannel is placed in the typasses or trisced condition witnin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the ineoeraale enannel is typassed, the costrasility of maintaining this channel in tne cypassed condition shall be reviewed in accareance with Soecification 6.5.1.5e. The enannel shall be returnee to CP!AA8LE status no later than during the next COLD SHUTOCWN.

With a channel process measurement circuit that affects multiple functional units inoperaale or in test, typass or t-i; all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed

1. Containment Pressure - High Contairment Pressure - Hign (ESF)

Containment Pressure - Mign (RPS)

2. $ team Generator Pressure -

Low Steam Generater P-essure - Low Steam Generator 47 1 and 2 (EFAS)

3. Steae Generator Level Steae Generator Level - Low Steam Generator Level - Hign Steam Generator AP (EFA3) l l

SAs CsC n t-us:7 2 2/A 3-is Amenenent No. 4 l

.7.1 i :- l

INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incere detection systen shall be OPERA 8LE with:

a. At least 75% of all incore detector locations, and

b. A minimum of two cuadrant symmetric incore detector locations per core quadrant.

An OPERA 8LE incore detector location shall consist of a fuel assembly containing a fixed detector string with a minimum of four OPERA 8LE rhodium detectors or an OPERA 8LE novanle incore detector capable of mapping the location.

APPLICA8ILITY: When the incore detection system is used for monitoring:'

a. AZIMUTHAL POWER TILT,

b. Radial Peaking Factors,

c. Local Power Density,

d. ON8 Margin.

ACTION:

With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore detection systes shall be demonstrated OPERA 8LE:

a. By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use if 7 or more days have elasped since the previous chark and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DN8 margin:

b. At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.

i SAM ONOFRE-UNIT 2 3/4 3-41 AMEN 0 MENT NO. 49

S! a.Mi%727:09

!!!!u:: IN!*:L'UEN'a*:"N

':v: :s ::'::*::N ::9 C:!: '::N

• 3.3.3.3 Ine seismic conitoring instrumentation snavn in Ta:1e 3.3-7 sna:1 :

C7!RABLE.

A 8 8'. :a!!'.!*y: At all times.

a: : N:

a. Wita ene or etre seismic menitoring instruments inc= era:1e for m: e inan 30 cays. =re:are and summit a 5:ecial Re: ort ts tne Commissten cursuant ts 5:ecificatien 6.9.2 within tne next 10 cays outlinia; ine cause of :ne malfunesion anc tne plans for rest: ring tne -

instrument (s) to 07!RABLE status.

Tne provisions of 5:ecifications 3.0.3 are not a:clica:'s.

SU:ViiLLANCE REOUIREw!NTS 4.3.3.3.1 !a:n =f the a:ove seismi: : nit: ring instru=ents shall te

st. castrate: C7!RASti Oy the erfor .an:e of tre CHANNE'. CHICK, CHANNEL

• ALIERAT**f4 Ta:le 4.3-4. an: CHANNEL FLNCTICNAL ?!ST ::erations at tre frecuencies sn:wn f 3

a. 3. 3. 3. 2 !ac. of :ne above seismi: =: nit: ring inst.u ents snier. is a::sts'::a i

ur n; ::-er ::eration anc whien is actuatec curing a seismic even (:ne or mere vali: :asemat accelerations of 0.0!g or greater) snall be resterec 1: C7!RABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALI!RATICN perforted witnir 5 cays.

Casa sna11 be retrieved free the ac:essible actuatec instruments and analy:ec is cetermine the magnitude of tne vitratory grounc motion. A S:e:141 Re:cr shall be pre:ared and su mitted to the Commissica pursuant to 1 j

3:scification 6.9.2 within 10 days oescribing the magnituce, frettency s:e:- :

and resultant effect uten facility features im:ortan- to safety. Each of ne a:cve seismic monitoring instru=ents which is actwated :uring a seismic even:

(one or more valid basemat accelerations of 0.05g or greater) but is not ac:sssible during power operation shall be restorec to OPERABLE status and a *HANNEL CALIBRATION erformed the next time the :lant enters ,uCCE 3 :r telow. A su::lemental report shall then ce =recarec and su:mitted :: ?e C:::issi:e wi nin 10 cays cursuant :: 5:e:ffi:ati:n i.9.2 ces:ri:ir; :ne a::iti:ra? =a:a fr:: teese ins ruments.

I i

\ I l

SAN CNCFRE-UNIT 2 3/a 3-42 FE817;&t!  !

l i

\

l

si :.;*'!N a?!ON

)

s. r. :. . - . . - . a t '. s c. :. .. e. s :- . . y i

1

..it.-.s

.. w ..y. ..- .y :.g. c::. tat *.".N 1

3.3.3.a The metacrolog*:a1 monitoring instrumentation caanne,1s shown in Taoie 3.3-8 small se OPilABLI.

A : 8 '. : a ! ! '. : ~: At all times.

g ....

.. . . N.

a. Wita one or more reewired meteorological monitoring enannels inocerasle for more than 7 cays, ;recare anc su:mit a Special to: ort to tne Commission pursuant to Specification 6.9.2 within the next 10 cays outlining tne cause of the malfunesion and saa plans for resturing he enannel(s) to CPERA8L! status.

c. The ;rovisions of Specifications 3.0.3 are not acclicaole. . ,

S'.' #V!:L'.AN:I *!OL' 4Ew!NTS 4.3.3.4 Ea:n of the above meteorologi:a1 conitoring instrumentation enansels s al :e :er:nstrate: OPERABLI ty tne cerfor an:e of sne CHANNEL chi:A ano C.-ANN!'. "a':. 3 RAT::N c;e ations a the fre: wen:ies snow- in Ta:1e 4.3 5.

(

• SAN CNCFRE-UNIT 2 3/4'3-45 F))ggygggg

, INSTRUMENTATION RADICACTIVE LIQUID EFFLUENT NONITORING INSTRUNENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid affluent sonitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 8LE with their alars/ trip setpoints set to l ensure that the limits of Specification 3.11.1.1 are not exceeded. The alam/  !

trip setpoints of these channels shall be determined in accordance with the .!

0FFSITE 00$E CALCULATION MANUAL (00CM).

APPLICA8!LITY: At all times."

ACTION:

a. With a radioactive liquid affluent monitoring instroentation ~ i channel alara/ trip setpoint less conservative than required by the '

above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channat or declare the channel inoperable. '

b. With less than the sintaus number of radioactive 11guld effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instroent to 0PERA8LE status within 30 days and, additionally, if the insperable instrument (s) remain inoperable for greater than 30 days, explain in the next Sealannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

c. The p Nvisions of Specifications 3.0.3 and 6.9.1.13b are not applicable.

SURVEILLANCE REQUIRDENTS a

4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated CPERA8LE by performance of the CHANNEL CHECK, SOURCE CHECA, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pups required to be providinn dilu-tion to meet the site radioactive effluent concentratial limits of Spec' fica-tion 3.11.1.1 shall be detemined to be operating and providing dilution to the discharge structure.

"See special Test Exception 3.10.5.

SAN ONDFRE-UNIT 2 3/4 3-43 AMONMENT M0. 57 1

i

{

l INSTRUMENTATION RADI0 ACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION l 1

LIMITING CCN0! TION FOR OPERATION z l 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The l alarm / trip setpcints of these channels shall be determined in accordance with the 00CM. l ApoLICA8!LITY:

As shown in Table 3.3-13*

ACTION:

a.

With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable, b.

With less than the minimum number of radioactivo gaseous affluent monitoring instrumentation channels OPERA 8LE. take the ACTION shown in Taele 3.3-13.

Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inocersele for greater than 30 days, explain in the next Semiannual Radioactive Eti19ent Release Report why the inoperability was not corrected in a timely manner.

c. The Drovisions of Specifications 3.0.3 and 6.9.1.13b are not a:plicable.

. SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CMANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST coerations at the i frequencies shown in Table 4.3 9. l "See Special Test Exception 3.10.5 JAN 11585 SAN ONOFRE UNIT 2 3/4 3-64 '

4 AMENDMINT No. 31

l INSTRUMENTATION l l

l LOOS (-PART DETECTION INSTRUMENTATION I

_ LIMITING CON 0! TION FOR OPERATION t

3.3.3.10 The loose-eart detection system shall be OPERA 4LE.

AP8LICA8ILITY: MODES 1 and 2.

ACT,Ig:

a.

With than more one or30 more days loose part detection system channels inoperable for prepare and submit a Special Report to the Commission pursuan,t to Specification 6.9.2 within the next 10 day outlining the channelthe (s) cause of the malfunction to CPERA8LE status, and the plans for restoring

b. ~~~

The provisient of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 OPERABLE by performance of a:Each channel of the loose part detection synte 4.

CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

CHANN!L FUNCTIONAL TEST at least once per 31 days, and c.

CHANNEL CALIBRATION at least once per 18 months.

I JAN 11 INul SAN ONOFRE-UNIT 2 3/4 3-75 AMENDMENT No. 31

i REACTOR COOLANT SYSTEM OVERPtE55URE PROTECTICN SYSTEMS RCS TEMe!RA*URE $ 235" '

t,!w!?!NG CON !?!0N FOR OPER.ATION

- I 3.4.8.3.1 be OPEAA8LI:At least one of the following overpressure protection systems shall a.

The Shutdown Cooling Systes Relief Valve (PSVf349) with:

1) A lift setting of 408 10 poig*, and }

2)

Relief Valve isolation valves 2MV9337, 2HY9339, 2HV1377 ano 2HY9378 open, or, t.

The Reactor Coolant Systee dooressurized with an RCS vent of greater taan or equal to 5.6 square inenes.

ApoLICASIL!TY:

MODE 4 when the temperature of any one RC5 cold leg is less taan or equal to 235'F; MODE 5; MODE 6 with the reactor vessel head on.

ACTION:

a.

With the SDCS Relief Yalve inoperacle, reduce T,,, to less than 200*F, cecressurize and vent the RCS througn a greater than or ecual to 6.6 soware inch vent witnin the neat a nours, t.

With one or botn 50C5 Relief Valve isolation valves in a single SOCS Relief valve isolation valve pair (valve pair 2HV9337 ano  ;

2MV1339 or valve pair 2HV1377 and 2HV9378) closed, open the closec valve (s) within 7 days or reduce to less snan 200'f, ce:res-t T,,,

surize and vent the RCS through a greater than or equal to !.6 inen vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. }

In the event either the SDCS Relief Valve or an RCS vent is usec to mitigate an RCS pressure transiant, a Soecial Resort small be creparea anc submitted within 30 days.to the Commission pursuant to specification 6.9.2 The report shall describe the circumsunces initi-ating the transient, the effect of the 50C5 Relief Valve or RCS vent on the transient and any corrective action necessary to prevent recurrence. 1 I

SURVEILt.ANCE REQUIREMfMTS a.4.8.3.1.1 Tha SDC5 Relief Valve shall be demonstrated CPERA8L! by: <

a.

Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> wnen the 50C5 Relief valve is j teing used for overgressure protection tnat 50C5 Relief valve l isolation valves 2MV9337, 2MV9339, 2HY1377 ano 2HV9378 are open.

For valve temperat.res less than or squal to 130'F.

SAN ONOFRE-UNIT 2 3/4 4-32 ,

Aqn dmen t No . A i

m 16 E'

R!ac 04 000(aWT [v$*gu 3.A 9 $*RUCTURA'. !N !:: v t.:w: :N3 : N .**:0N r:a cagear;;y 3.4.9 Tne structural in'.agrity of ASHE Coca Class 1, 2 ane 3 com:enents snail ce maintainec in ac::r:ance wita Specification 4.4.5.

A 0 0 '. ! A!!'. *Y: ALL MCCl3 A* 0N:

a.

With the structural integrity of any ASME Coce Class 1 cseconent(s) not c:nfoning to the acove recuirements, restore the structural integrity of sne affected com:enent(s) to witnin its limit or isolate the affectec component (s) prior to increasing the Reactor Coolant System temeerature more than 50'F amove the minimum temperature recuirac Dy NOT consicerations. -

b.

With the structural inte;M ty of any ASME Coca Class 2 conconent(s) not conforming te the noeve recuirements, restore the structural

• integrity of the affected cass=nent(s) to within its limit or i isolate the affectec c:econent(s) criar to increasing the Acactor C:clant System tasserature acove 200'F.

c.

With the structural integrity of any ASME Coce Class 3 c: :anent(s) not conforming to the acove recuirements, restore the structu-al integ?ity of the affectec c:mmenent to witnin its limit er isolate tan affectec cor.:enent from service.

SURv!!L'. AN:t R!0UIR! MEWS 4.A.9 In acettien to the requirements of $cecification 4.0.5, eacs React:r Coolant Pune flywheel shall be inscoctec car the roccer.encati:ns of Regulat:ry Position C.4.0 of Regulatory Guice 1.14 Revision 1, August 19'5.

( -

l 1

l SAN CNCFR!* UNIT 2 J/4 4 34 g yg i

e . l l

_...c- ,. . . -

DLANT $V$?EMI 3/a.7.7 $EALED $0URCE 20N?aW:Na?! N L:w: :N3 CONO:*!!N cc; ::g;a;;;s 3.7.7 !ach sealed source containing radioactive material eitner in excess of 100 microcuries of tota anc/or gamma esitting material or 5 microcuries of alena emitting material shall be free of greater than or equal to 0.005 sierocuries of removaole contamination.

A88tICA8!L!*Y: At all times. '

A0Tf0N:

a. With a sealed source having removable contamination in excess of the t.'

acove 11 alt, witacraw the sealed source free use and either:

. 1. Decentaminate and repair the sealed source, or -

2. Dispose of the sealed source in accordance with Commission Regulations. .

b. The provisions of Specifications 3.0.3 are not a slicanle.

SURVEILLaN0! REOUIREMENTS 4.7.7.1 Test Recuirements - Eacn sealed source shall be tested for leama;e anc/or contamination ty:

a. The licensee, or

t. Other persons specific.111y authorized by the Commission or an Agreteent State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

4.7.7.2 Test Frequencies - Each category of sealed sources (exclucing startue sources and fission detectors previously sucjected to core flux) small be tested at the frequencies described Delow,

a. Sources in use - At least once per six months for all sealed sour:es

_. containing radioactive material:.

1. Vita a half life greater than 30 days (exclucing Hycrogen 3),

anc

2. In any form einer taan gas.

I I

l

( l SAN CNCFA!-UNIT 2 3/a 7-24 .. .

FE8),7.1982

R E "'.'i'. :NC :!:a ::ss 3: ?. 9 00'i* :'.'.'is :.: ! :::.A ::N svs r.:

......~.........I..R........,i

. . . . . . . . . ..:..s.

3.9.9 The containment surge isolation systes snall be CPERA2'I. .

A 8 8 LI"2 8 !'.!7Y: 0aring C Ri ALTIRAT!CNS or sovement of irractated f.el . t ..

Se Can*ainment,

.ag, g..... .

'witn :ne ::ntaineert :vege isolation systes inc:eraale, close each of ts.e

ntainment curge cenetratiens provicing cire:t access from tne c:ntain.est at:cs:nere to tne cutstes atmospnare.

5"tVI:'.LAN!! 4!!L':tiwiv*s 4.9.9 ine ::ntainment purge isolatien system small te dem:nstrate: :FERA!'.!

.itnin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior.to tne start of anc at leas en:e :er 7 cays curing ;;Ei A'.TilAT:0NS Dy verifying that contair, ment purge valve isolation oc:ges en manual initiation and on a hign raciation test signal, l

l i

1 l

l l

l l

l l

l I

SAN 0NCFRi-UNIT 2 3/4 9-10 .

FEB 1719t!

t!:JELING :DE:C! NS 3/4.9.12 CUEL MANDLING SutLO!NG 7057- AC0!OENT CLEANU8 !L'ER Sv!*!w L!w! TING CCN0! TION FOR 09!4ATION 3.9.12 T.o independent fuel handling building post-accicent cleanyo filter systems snall be OPERA 8LE.

ApoLICABILITY: Whenever irradiated fuel is in the storage pool.

ACT!CN:

a.

With one fuel handling building post-accident cleanuo filter system inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the OPERA 8LE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERA 8LE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal absorbers, b.

With no fugl handling building post accident cleanup filter system OPERABLE, suspend all operations involving movement of fuel within the storage pool or operation of fuel handling machine over the storage pool until at least one fuel handling building post accident cleanup filter system is restored to CPERA8LE status.

SURVEtt. LANCE REQUIREMENTS 4.9.12 The above required fuel handling building post accident cleanuo filter systems small be comonstrated CPERA8LE:

a.

At least once per 31 days on a $TAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal j adsorbers and verifying that the system operates for at least 10 nours with the heaters on,

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

SEP 30 355 SAN ONCFRE-UNIT 2 3/4 9-13 AMENCMENT NO. 36

R&OICACTIVE E'8LUEVT5 CCSE

( M: !N3 CONO *!CN FOR OpftATION 3.11.1.2 The cose or cosa consitzent to an individual free radioactive materials in licuid effluents released, free each reactor unit, from the site (see Figure 5.1-4) shall be limitee:

a.

During any calencar guarter to less than or equal to 1.5 ares to the total bocy and to less than or equal to 5 area to any organ, anc

b. During any calendar year to less than or soual to 3 area to the total boey and to less than or equal to 10 area to any organ, ap*LICAltLITY: At all times.

ACT!CH:

a.

With the calculated dose from the release of radioactive saterials .

in liquid effluents exceeding any of the teove limits, in lieu of any other resort rsouired by Specification 6.9.1, prepare and sweef t to the Commission within 30 days, pursuant to Specification 6.f.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce the releases anc the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.1.2

b. The provisions of specifications 3.0.3 and 6.9.1.133 a e mot a:plicamle.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dese Calculations. Cuculative dose contributions from licuid effluenta 31 days. sna11 os setermined in accorcance with the 00CM at least once per

[,-  !

SAN CNCFRf UNIT 2 3/4 11 5 FEB 17 f9t! I 1

l 1

RA0!OAC~IVE EFFLUENTS L!OUID WASTE TREATw!NT L'u!-*NG CON 0! TION FOR OD!4aTION 3.11.1.3 The liquid radwaste treatment systes shall be OPERA 8LI. The a:cropriate portions of the system shall be used to reduce the radioactive materials in licuid wastes prior to their discharge when the projected cases due to the liquid effluent from the site (see Figure 5.1-a) when averaged over 31 cays, would exceed 0.06 ares to the total bocy or 0.2 area to any organ."

ApDLICABILIH: At all times.

ACTION:

a. With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid wasta being discharged without treatment and in excess of the above limits, in liev'of any other report required by Specification 6.9.1 preoare and submit to the Commissionwithin30dayspursuantto$pecification6.9.2aSpecial.

Report which includes the following information:

1. Identification of the inoperable equipment or subsystems and the reason for inoperability,

2. Action (s) taken to restore the inoperable equipment to CPERA8LE status, and

3. Susanary description of action (s) taken to prevent a recurrence,

b. The provisions of Specifications 3.0.3 are net ap:licable.

SURv!!LLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.1.3.2 The liquid raswaste treatment system shall be demonstrated CPERABLE by operating the liquid raenaste treatment systes equipment for at

' least ih minutes at least once per 92 days unless the liquid raewaste systes has been utilized to process radioactive liquid effluents during the previcus 92 days.

• 4 i .

9 Per reactor unit SAN CHOFRE-UNIT 2 3/4 11 6 R817 t$t!

1

of : : 0.: * *.'E E ~ P.U I' ' 5

':!U:: FLOUP T AN5:5 l

L:u:;tsc c:s3titcy ist cog:AT cy 3.11.1.4 The quantity of radicactive material contained in each cutside I ter;crary tank shall te limited to les:

tritium and dissolved or entrained noble gases.than or equal to 10 curies, excluding A7Pl! cal!LITY: At all times.

ACTION: -

a.

With the quantity of radioactive material in any outside temporary tank exceeding the above limit, fr. mediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

h.

The provisions of Specifications 3.0.3 are not appilcable.

SURVI:LLAN0! RE0V!tiu!NTS -

4.11.1.4 The quantity of radioactive material contained in each outside B tet.:crary tank shall be determined to be within the above limit by analyting a rt:resentative sample of the tank's contents at least once per 7 days wnen ra:icactive catarials are being added to the tank.

MAY 16 M*:-

IAN CN 7?.i-UNIT 2 3/4 11*7 AP.!NDP.!NT NO. 18

RA0!0ACT!vt gerLUEN 5 005{ - NCl([ GA$($

(!w! NG CONOI?!ON FOR CP! RATION 3.11.2.2 The air cose due to noble gases released in gaseous effluents, free each reactor unit, from the site (see Figure 5.1-3) shall be limites to the following:

a. During any calendar cuarter: Less than or eoual to 5 stad for gamma raciation and less than or equal to 10 arad for beta radiation anc,

b. During any calendar year: Less than or equal to 10 arad for gasuna radiation and less than or equal to 20 arad for beta radiation.

AP8LICA8!LITY: At all times.

ACTION

a. With the calculated air dose free radioactive noble gases in gaseous effluents exceecing any of the aoove limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Ceaunission witnia 30 days, pursuant to Specification 6.9.2, a 50ecial Report watch identifies the cause(s) for exceeding the limit (s) and defines the corrective actions taken to reduce releases ana the r:::see corrective actions to be taken to assure that sucsequent releases will be in compliance vita Specification 3.11.2.2.

b. The provisions of Specifications 3.0.3 are not septica:1e.

SURVEILLANCE REQUIREMENTS 4.11.2.2 Case Calculations Cumulative dose contributions for the current calencar guarter ano current calendar year shall be detemined in acenecance with the CDCM at least once per 31 days.

1 l

l .

1 SAN ONOFRI-UNIT 2 3/4 11-12 ,

{

Fell ? m2 l 1

RA0!0 ACTIVE EFFLUENTS DOSE - RADIOI00!NES. RA0!0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIU __

LIMITING CON 0! TION FOR OPERATION 3.11.2.3 The dose to an individual from tritium, radiofodines and radioactive materials in particulate form with half-lives greater than 8 days in gaseous affluents released, from each reactor unit, from the site (see Figure 5.1-3) shall be Itaited to the following:

a. During any calendar quarter: Less than or equal to 7.3 area to any organ and,

b. During any calendar year: Less than or equal to 15 ares to any organ.

c. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result of burning contaminated oil.

APPLICA8!LITY: At all times.

ACTION:

a. With the calculated dose from the release of tritium, radiciodines, and radioactive materials in particulate form, with half lives 3 greater than 8 days, in gaseous effluwnts exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to ,

Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions taken to reduce releases and the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.3.

b. The provisions of Specifications 3.0.3 are not applicable.

$URVEILLANCE REQUIREMENTS

- 4.11.2.3 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the CDCM at least once per 31 days.

SAN ONOFRE-UNIT 2 3/4 11-13 i AMEN 0 MENT No. 52

RA010 ACTIVE EFRUENTS ca5E005 RACWASTE TREA*w!WT LIM!*:NG OCNC:~!CN FOR C9! RATION 3.11.2.4 The GASEOUS RADVASTE TREATMENT SYSTDi and the VENTILATION TREATMENT SYSTEM shall be OPERA 8LE. The appropriate portier.4 of the GASECUS RADWASTE TREATMENT SYSTEM snail be used to reduce radioactive materials ii gaseous waste prior to their discharge when the projected gaseous effluent air ooses due to gaseous affluent releases from the site (see Figure 5.1-3), wnen averaged over 31 days, would exceed 0.2 erad for gamma radiation and 0.4 mead for beta radiation. The appropriate portions of the VENTILATION EXNAusT TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due ta gaseous effluent releases from the site (see Figure 5.13) when averaged over 31 days would exceed 0.3 ares to any organ."

APplICA8It.I*f: At all times. '

ACTION:

a.

• With tne GASEOUS RADWASTE TREATHENT SYSTEM and/or the VENTILA l EXMAUST TREATMENT SYSTD; inoperaale for more than 31 days er with gaseous waste being discharged without treatment and in excess of the above limits in lieu of any other report required by Specifica-tion 6.9.1, prepa,re and sumett to the Commission within 30 days, pursuant to Specification E.9.2, a Special Report which includes tne following information:

1.

Identification of the inecerable equipment or sutsystems and the reason for inoperaciiity, l

2. Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and -

I

3. Susunary description of action (s) taken to prevent a recurrence,

b. The provisions of Specifications 3.0,3 are not applicable.

SURVEILLANCE REQUIREMENTS t

4.11.2.4.1 Deses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM.

4.11.2.4.2 The GASECUS RADWASTE TREATMENT SYSTEM and YENTILATION EXHA TREATMENT SYSTEM shall be cessnstrated CPERA8L! by operating the GASECUS DOVASTE TREATMENT SYSTEM ecuipment and VENTILATION EXMAUST TREATMENT SYSTEM ecuicment for at least 15 minutes, at least once per 92 days unless the acpropriate system has been utilized to process racioactive gaseous affluents curing the previous 92 days.

"These cases are per reacto,e unit.

I SAN ONCFRE-UNIT 2 1

' 3/4 11 14 i

FU i 71982 1

R A:'O AC !i !":'.'.'INTS *

! :tts:'/t 015 P X'U:t L:v!?:ys t;'i:! TION FCR OEERATICH 3.11.2.5 The cencontration of oxygen in the waste gas holdup system shall te  !

limited to less than or equal to Z% by volume whenever the hydrogen c:ncentrati:n ^

excents 4% by vciu:n.

APPLICA!!LITY: At all times.

ACTICN:

a.

With the cencontration of oxygen in the waste gas holdup systes greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the Ifait within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.

With the cencontration of oxygen in the waste gas holdup system greater than 4% by voluse, inmediately suspend all additions of ,

waste gases to the system and reduce the concentration of oxygen to less than 4% by volume within one hour and less than or equal to 25 ,

by volume within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. '

t

c. The previsiens of Specifications 3.0.3 are not applicable.

5URVEILLANCE RfCUIREMENTS .

4.11.2.5 The c:ncentrations of hydrogen and oxygen in the waste gas holduc system shall be cetermined to be within the above limits by continuously ment-t: ring the waste gases in the waste gas holdup system with the hyde: gen and '

exygen eenit:rs required OPERA 5LE by Table 3.3-13 of 5;ecification 3.3.3.5.

i t

t l

l MITi6Il??

I  !

3AN CNCFRI-UNIT 2 3/4 11-15 s u run'er w t u n ! !

RACICACT!vt EFFLUENTS  !

3/4.11.3 SOLID RADICACTIVE WA5TE L!w!TfNG CONDITION FOR OPERATION 3

i 3.11.3 The solid reewaste system shall be OPERA 8LE and used, as amplicaele in  !

accordance with a PROCESS CONTROL PROGRAM, for the 50L20!FICAT10N and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the .

site.  !

i APPLICASTLITY: At all times.a ,

ACTION:

I

a. I WitP. the packaging requirements of 10 CFR Part 20 and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid racioactive wastes from the site.

b. With the solid radweste system inoperable for more than 31 days, in )

lieu of any other report required by specification 4.9.1, presare and sunett to the Cameission within 30 days pursuant ta Specifica- ,

i tion 6.9.2 a Special Report which includes the following information:

1. l Identification of the inoperable equipment er sutsystems and the reason for inoperasility.

2. Action (s) taken to restore the inoperable equipment to OPERAELI s ta tus , ,

t i

3. A description of the alternative used for SCLIDIFICATION and packaging of radioactive wastas, and

4. Summary 6escription of action (s) taken to prevent a recurrence.

c. The previsions of Specifications 3.0.3 are not applicable.

, SURVE!LLANCE RE00!ROMENTS 4.11.3.1 The solid radweste systes shall be demonstrated OPERAILE at least once per 92 days by:

a. Operating the solid radwaste system at least once in the previous 1

i 92 days in accordance with the PROCESS CONTROL PROGRAM, or  !

b.

Verification of the existence of a valid contract for SOLIDIFICATION i to be performed by a contractor in accareance with a PROCESS CCNTROL I

{ PROGRAM.

"See Specification 6.13.1.

SAN ONOFRE UNIT 2 3/4 11-17

, f:1 -

R317 IM2 '

J n- - - - - - - , . - . - - -. ., - ----,__ -.. - - . - . _ . . . - - - _ - - - - _ , - - _ - _ . . - - - - - - ,

i l

RADICACT!vt E FLUEr5 3/a. n.4 TOTAL DOSE WW"*N3 CONDITION FOR CDERATION l

3.11.4 The dose or dose censitment to any member of the public, due to '

releases of radioactivity and radiation, free uranium fuel cycle sources shall be limited to less than or equal to 25 ares to the total body or any organ (except the thyroid, vnich shall be limitad to less than or equal to 75 area) l over 12 consecutive months. .

l APPLICABILITY: At all times.

EIg:

a.

With the calculated doses from the release of radioactive asterials in liquid or gaseous affluents exceeding twice the limits of Specification 3.11.1.2.a. 3.11.1.2.b. 3.11.2.2.a. 3.11.2.2.b.

3.11.2.3.4, or 3.11.2.3.b in lieu of any other report required by Seecification 6.9.1, prepa,re and subsit a Special Report to the .  !

Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory '

Commission, Washington, D.C. 20555, within 30 days, which defines the corrective action to be taken to nduce subsequent releases to prevent recurrence of exceeding the limits of Specification 3.11.4 This Special Report shall include an analysis which estimates the radiation exposure fuel cycle sources (dose) to a all (including member ef fluent of the puelic from pathways and direct uranius radiation) for a 12 consecutive month period that includes the release (s) cover, ./ this report. If the estimated dose (s) exceeds the limits of Soecification 3.11.4, and if the release concition resulting in violation of 40 CFR 190 has not already Deen corrected, the Special Report shall include a request for a variance in accarcance with the provisions of 40 CFR 190 and iricluding the specified information of I 190.11(b). Subsittal of the report is considered a timely request 2nd a variance is granted untti staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the recuire- '

ments for dose liettation of 10 CFR Part 20, as a6 dressed in other i sections of this tecnnical specification.

b. The previsions of Specifications 3.0.3 are not appilcante. -

SURVEILLANCE RECU!REMENTS i

4.11.4 Dese Calculatiens Cumulathe dose c:ntributions fr:a liquid and gaseous affluents snall ne determined in accordance vita Soecifications i 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accorcance with the 00CM.

\

! =

SAN ONOFRE UNIT 2 3/4 11-19 .

ns 17 52 >

3/a.12 RA0!0LOGt0AL EW!ROWENTAL "0NITORING 3/a.12.1 MONITORING DROGRAM '

LIMITING CON 0f?!0N OR s.'ERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Tacle 3.12-1. .

Apat !0A8II.!TY: At all times.

ACTION:

i a. With the radiological environmental sonitoring progran not being conducted as specified in Tabis 3.12-1, in lieu of any other report t mouired by Specification 4.9.1, prepare and sunett to the Com-mission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence,

b. With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table 3.12 2 when averaged over any calendar quarter, in lieu of any other report required by

• Specification 4.9.1, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter a Report pursuant te Specification 6.9.1.13. When more than one of the

' radionuclides in Table 3.12 2 are detected in the sampling medium, this report shall be submitted if:

concentration limit level (1)(1) . eencontration (2) * ***>~ 1*0 limit level (2)

When radionuclides other than those in Table 3.12-2 are detected and are the result of plant affluents, this report shall bt submitted if  ;

the potential annual dose to an individual is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2 '

and 3.11.2.3. This report is not required if the measured level'of radioactivity was not the result of plant afl. ; ants; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. l

c. With fresh leafy vegetable samples or flesny vegetabia samples unavail- 4 able from one or non of the sample locations required by Taala 3.12-1, I in 11eu of any other report requirtJ by Specification 4.9.1, prepara 1 and subeit to the Commission within 30 days, pursuant to Specific- l atton 5.3.2 a Special Report which identifies the cause of the unavail- l asiitty of sasoles and identifies locations for cetaining replacveent l saacles. The locations from which samples were unavailacle say then I be deleted from those required by Table 3.12-1, provided the locations from which the replacement sasoles were obtained are acced to the environmental ronitoring program as replacement locations.

d. The previsions of Specifications 3.0.3 are not applicaele.

{

I

, SAN ONOFRI UNIT 2 3/4 12-1 FE8171982

l l

l r O.L.".00 !C ? L E'g:N"! CAL MON!?CR!NG l i

2 ': .12. 2 LA':0 USE Civ!US

i. M T:N3 CON 31TICH FOR 085 TAT!0N 3.12.2 A lard use census shall be conducted and shall identify the location cf the nearest milk animal, the nearest residence and the nearett garden" of I

greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five ailes. For elevated i releases as cefined in Regulatory Guide 1.111 Revision 1 July 1977, the land i

use census shall also identify the locations of all mila animals and all )

gardens of greater than 500 square feet producing fresh leafy vegetables in  ;

each of the 16 meteorological sectors within a distance of three miles.

A P P'.ICA B I L ITY: At all times.

ACTION:

a.

With a land use census identifying a location (s) which yields a calculated Mose or dose coeviit. ment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other recort required by Specification 6.9.1., prepare and submit to the Coraission within 30 days, pursuant to Specification 6.1.2, a Special Report which identifies the new location (s),

b.

With a land use census identifying a ' location (s) which yields a calculated dose or dose corait. ment via the same exposure pathway 20 percent greater than at a location fron which sa:;1es are currently ceing ubtained in accordance with Specification 3.12.1, in lieu of any other report required by 3pecification 6.9.1, prepara and submit to the Commission within 30 days, pursuant to Specifica-tien 6.9.2, a Special Report which icentifies the new location. The new location shall be addad to the radiological environmental menitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose ce dose coraitment via the same exposurs pathway say be deleted fr:m this monitoring program after October 31 of the year in whien tais land use census was conducted.

c. The provisions of Specifications 3.0.3 are net a;;1(cabla.

SURVEILUNCE REQUIRE.*ENTS .

a.12.2 The land use census shall be conducted at le&st once per 12 conths between '.he dates of June 1 and October 1 using that information vnich will provide the best results, such as by a door-to-door survey, serial survey, or by consulting local agriculture authorities.

A

)

Broad leaf vegete. tion sampling ray be performed at the site boundary in the cirectien sector with the nighest 0/Q in If au of the gsrden census.

NY i 6 51 SAN CNOFRI-UNIT 2 ..

3/4 12-11..- RC;0Mn; .:c,1g

l l

/

Ra 0 :"'.C * * : L E N'/ : t * *:"I'C Al, .VC N ! 70 4 I N3 i

3/a.12.3 INT!?L:!:ttT0tY C:r):::!C.'s *::Ct:M

. . l tim! TING CON 0! TION FC4 CPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlateratory Comparison Progras which has teen approved by the Commission.

APPLICA!!LITY: At all times. '

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Ccamission in the Annual Radiological Environmental operating Report,

b. The provisions of Specifications 3.0.3 are not appitcabts.

i

+

$Utv!ILLANCE REOU REMENT!.

i

. I a.12. 3 A she. mary of the results obtained as part of the above recuired Interlateratory Cce;arison Program anf in accordance with tne COCM shall to included in the Annual Radiological ",nvironmental Operating Aaport. 1 1

i i

\

1 1

iW 16INI .!

SAN CfCFA! UNIT 2 3/4 12 12 A;.:{';;:.:{ ;T *;g,16 I

d, ,

a j

3/4.0_ APPLICABILITY ,

BASES _

Specific'ation 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code 3

l of federal Regulations, 10 CFR 50.36(c)(2).

"Limiting conditions for operation are the lowest functional capability 1

or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the lice: pee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

Spec'ificati% 3.'n.1 esM11shes the Applicability statement within each indivioual apet.ification as the requi.rement for when (i.e., in which OPERATIONM. MODCS or other specified< conditions) conformance to the Limiting Conditions for Operation 4.s required for safe operation of the facility. The ACTION requirements establish those renadial measures that must be taken within specified tip. lim ts when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited f.ontinued operation as long as the ACTION requirements continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a MOCE or condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met. The tinee limits of the ACTION requirer. tents are also applicable when a system or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service. In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if ,

the surveillance has not been completed. When a shutdown is required to '

comply with ACTION requirements, the plant may have entered a MODE in which a new specification becomes applicable. In this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

I i

l l

q SAN ONOFRE - UNIT 2 8 3/4.0-1

l 3/4.0 APPLICABILITY BASES (Con't)

Specification 3.0.2 establishes that noncompliance with a specification exists  !

when the requirements of the Limiting Condition for Operation are not met and I the associated ACTION requirements have not been implemented within the  !

specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance sith a specification and (2) completion of the j

remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdown ACTION requirements that must be l implemented when a Limiting Condition for Operation is not met and the l condition is not specifically addressed by the associated ACTION requirements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electricai grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Ope ra t i or. . Therefore, the shutdown may oe terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in the COLD SHUT 00WN MODE when a shutdown is required during the POWER MODE of '

operation. If the plant is in a lower MODE of operation when a shutdown is  ;

required, thq time limit for reaching the next lower MODE of operation l applies. However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTOOWN, or other applicable MODE, is not reduced. For example, if HOT STA,10BY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the l

time allowed to reach HOT SHUTOOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time j to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. 1 Therefore, if remedial measures are completed that would permit a return to l POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total ti:r.e allowed.

SAN ON0fRE - UNIT 2 B 3/4.0-2

.- .- .- a

i ,

i 3/4.0 APPLICABILI_TY l t 1 1

\

BASES (Con'tl '

l The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirrwnts for one specification results in entry into a MODE or condition of operation for

, another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified,the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits l of ACTION requirements for a higher MODE <f operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES S and 6, because the ACTION requirements of individual specificatioris define the j remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a l higher N00E of operation when the require:nents for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain cogliance with a specification by restoring equir> ment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimitad period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in accordar,ce with the provisions of the ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Pequirements stated in the Code of federal Regulations, 10 CFA 50.36(c)(3):

"Surveillance requirements are requirements relating to test, I calibration, or inspection to ensure that the necessary quality of systems and i components is ri.aintained, that facility operation will be within safety '

limits, and that the limiting conditions of operation will be met.'

l 1

l SAN ONOFRE - UNIT 2 B 3/4.0-3 l

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

I 3/4.0 APPLICABILITY l BASES (Con't)

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE cr other specified condition for which the assosiated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an GPERATIONAL M00E for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.  ;

5pecification 4.0.2 establishes the conditions under which the specified time -

interval for Surveillance Requirements may be extended. Item a. permits an I allowable extension for the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b.

limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval t,eyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that tlie most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval, Specification 4.0 3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that cu itutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting  ;

the Surveillance Requirements. This specification also clarifies that the ACTION requirersents are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is j identified that a surveillance ha; not been performed and not at the time that i the allowed surveillance interval was exceeded. Completion of the i Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specifications 4.0.3. However, this does not negate the fact that the failure to have SAN ON0fRE - UNIT 2 8 3/4.0-4

3/4.0 APPLICABILITY BASES (Con't) j performed the surveillance within the allowed surveillance interval, defined i by the provisions of Specification 4.0.2, was a violation of the OPERABILITY  !

requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Spec?fication requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

l If the allowable outage time limits of the ACTION requirements are less than 1 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, )

e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay i in implementing the ACT!0N requirements. This provides an adequate time limit I to complete Surveillance Requirements that have not been performed. The  ;

purpose of this allowarce is to permit the completion c? a surveillance before I a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a i surveillance. The basis for this allowance includes consideration for plant  !

conditions, adequate planning, availability of personnel, the time required to I perform the surveillance, and the safety significance of the delay in  !

completing the required surveillance. This provision also provides a time l limit for the completion of Surveillance Requirements that become applicable 1 as a consequence of MODE changes imposed by AC' ION requirements and for l completing Surveillance Requirements that are appiicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not  !

completed within the 24-hour allowance, the time limits of the ACTION  :

requirements are applicable at that time. When a surveillance is performed I within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated. l Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that, inoperable equipment has been restored to OPERABLE status.

Surveillance 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operatica specified in the Applicability statement. The purpose of this specificatior is to ensure that system and component OPERABILITY requirements or pararheter limits are met before entry into a MODE or condition for which these systems and component ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified l l

conditions assc:tated with plant shutdown as well as startup. l l

SAN ONOFRE - UNIT 2 8 3/4.0-5 l l

1

3/4.0 APPLICABILITY BASES (Con't)

Under the provisions of this specification, the opar. cable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for C)eration are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

Specification 4.0.5 establishes the requirements that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of_ '

the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows pumps and valves to be tested up to one week after return to normal operation. The Technical Specification definition  :

of OPERABLE does not allow a grace period before a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

8101F l

l 1

SAN ON0fRE - UNIT 2 8 3/4.0-6

NPF-10/15-238 ATTACHMENT "D"

1 s

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS l

3/4.0 APPLICA8ILITY

~

LINITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or'other conditions specified therein; except that-upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with.a specification shall exist when the requirements of the Limiting Condition for Operation and/or associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time interva'Is, ,

completion of the ACT!ON requirements is not required. '

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour, action shall be ,

initiated to place the unit in a MODE in which the specification does not , '

apply by placing it, as applicable, in:

1. At least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

2. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and

3. At least COLO SHUTOOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified tic?-

limits as measured from the time of failure to meet the Lic iting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL N00E or other specified condition shall not be made when the conditions of the Limiting Condition for Operation are not met and the associated ACTION requires a shutdown if they are not met within a '

specified interval. Entry into an OPERATIONAL MODE or specified condition may 3 be made in accordance with ACTION requirements when conformance to them '

permits continted operation of the facility for an unlimited period of time.  !

Ihis provision shall not prevent passage through or to OPERATIONAL NODES as required to comply with ACTION requirements. Exceptions to these requirements  ;

are stated in the individual specifications. t i

l SAN ONOFRE - UNIT 3 3/4 0-1 i

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

h h

APPLICABII.ITY I 0

SURVEILLANCE REOUIRENENTS i l

i, 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for 1 Operation unless otherwise stated in'an individual Surveillance Reauirement. D 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

a. A maximum allowable extension not to ex:eed 25% of the surveillance interval, and t,

b. The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval. ,

4.0.3 Failure to perform a Surveillance Requirement within the allowed -

surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition.for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.

The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do not have to be performed on inoperable equipment.

i; 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not '

be hade unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or es otherwise specified. This provision shall not prevent passage t through or to OPEPATIONAL MODES as required to comply blth ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler i and Pressure Vessel Code and applicable Addenda as required by  !

10 CFR 50 Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i). ,

t

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

8683F SAN ONOFRE - UNIT 3 3/4 0-2 l

. - _ - . . - - . , w

l

~

3/4.3 INSTRUMENTATION --

3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION l

3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shell be OPERA 8LE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICA8ILITY: Asshownin, Table 3.3-1. , ,. , , ,

~

ACTION: 1 As shown in Table 3.3-1. '

SURVEtt. LANCE REQUIREMENTS

.l. , f < ', -

4.3.1.1 Each reac56r protective instrumentation chanrel shall be demonstrated '

OPERABLE by the parformance of the CHANNEL CHECK, CHANNEL CALIBRATION and i

~ CHANNEL FUNCTIONAL TEST operations for the W)ES and at the frequencies shown in Table 4.3-1.

F' 4.3.1.2 The logic for the bypasses shall be demonstrated OPERA 8LE prior to each reactor startup unless performed during the preceding 92 days. The total bypass function shall be demonstrated OPERA 8LE at least once per 18 months during CHANNEL CALIBP.ATION testing of each channel affected -by bypass operation.  ;

4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function I shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one channel per function such that all {

channels are tested at least once every N times 18 months where N is the total l number of redundant channels in a specific reactor trip function as shown in l the "Total No. of Channels" column of Table 3.3-1, '

4.3.1.4 The isolation characteristics of each CEA isolation amplifier and each optical isolator for CEA Calculator to Core Protection Calculator data transfer shall be verified at least once per 18 months during the shutdown per the following tests:

?..

a. For the CEA position isolation amplifiers: '

1. Wittr-120 volts AC (60 Hz) applied for at least 30 seconds across the output, the reading on the input does not exesed 0.015 volts DC.

/

~~

NOV 151982 SAN ONOFRE-UNIT 3 3/4 3-1

,~ ,--w,--,, ,- ,-,,g- ,w----. . - - , - , . , ,.,,,,,,-,,-..,,,,.w, ._ --

_-,,,._-,,,,,.,,,_.,..,,-e .. , - . , - . . y _.,-,,,,s.,m, . , , - , , , , e--

r TABLE 3.3-F (Continued)

LABLENOTAit0N With the protective system trip breakers in the closed position, the CEA  !

drive system capable of CEA withdraw 41, and fuel in the reactor vessel.

0 (a) Trip may be manually bypassed above 10N of RATED THERMAL POWER; bypass

' shall.P automatically removed when THEid4AL POWER is less than or equal  :

to 101 of RATED THERMAL POWER. ,

(b) Trip say be manually bysassed below 400 psia; bypass shall be i automatically removed whenever pressurizer pressure is greatar than or l equal to 400 psia. . .

~

' (c) Tripmaybemanuallybypassedbelow10kofRATEDTHERMALPOWER; bypass shall be aul tically removed when THERMAL POWER is greater than or equal to 10 I>

~

of RATED THERMAL POWER. During testing pursuant to Special T :,t Exception 3.10.3, trip say be muually bypassed below 5% of -

RATED THERMAL POWER; bypass shall be automatically removed when THERMA U. :-

POWER is greater than or equal .to 5% of RATED THERMAL POWU.

(d) Trip may be bypassed during testing pursuant to Special Test Exception 3.10.3.

(

(e) See Special Test Exception 3.10.2. -

i (f) Each channel shall'be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.

(g) Trip say be bypassed below 55% RATED THERHAL POWER. -

.. ; 3 ,. . ,

ACTION STATEMENTS -

ACTION 1 -

With the number 'o[bhannels OPERA 8LE 'one less than required by the Minfeum Channels OPERA 8LE requirement, restore the -

. inoperable channel to CPERA8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in

'.at least HOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the

..g. .[ protective systes. trip breakers. .. ,

..~ .

~ . ~.

ACTION 2 - -

With the number of channels CPERA8LE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION say continue provided the inoperable channel is placed in the bypassed or tripped condition within I hour. If the inoperable channel is bypassed -the desirability of maintaining this channel in the -

bypassed condition shall be reviewed in accordance with Specification 6.5.1.6e. The channel shall be returned to OPERA 8LE status no later than during the next COLD SHUTDOWN.

/ .

h. -

NOV 15 IS62 SAN 0HOFRE-UNIT 3 3/4 3-4 I

1 i

INSTRUMENTATION 1

3/a.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATICN LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and bypasses snown in Table 3.3-3 shall be OPERA 81.E with their trip i setpoints set consistent with the values shown in the Trip setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.*

APPLICABILITY: As shown in Table 3.3-3. -

ACTION:

a.

With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3 a, i declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERA 8tE ,

status with the trip setpoint adjusted consistent with the Trip.

Setpoint value.l l

b. With an ESFAS instrumentation channel inoperable, take the ACTION  !

shown in Table 3.3-3.

SURVEILLANCE REQUIREMENT $

4.3.2.1 Each iSFAS instrumentation channel shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES ar.d at the frequencies shown in Table 4.3-2.

4.3.2.2 The logic for'the bypasses shall be demonstrated OPER 8LE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation.

The total bypas.s function shall be demonstrated OPERA 8LE at least once per 18 months bypass during CHANNEL CALIBRATION testing of each channel affected by operation.  ;

. t 4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS functio l shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one channel per function such that all i i

channels are tested at least once every N times 18 months where N is the total '

number of redundant channels in a specific ESFAS function as shown in the "Total No. of Channels" Column of Table 3.3-3.

"Continuous monitoring and sampling of the containment purge exhaust directly from the purge stack shall be provided for the low and high volume (8-inch and 42-inch) containment purge prior to startup following the first refue'eing outage. Containment airborpe sonitor 3RT 7804-1 or 3RT-7807-2 and associatec

' sampling media shall perform these functions prior to initial criticality.

From initial criticality to.the startup following the first refueling outage i containment airborne monitor 3RT-7804-1 and associated sampling media shall perfore the above required functions.

SA" '"0FRE-UNIT 3 3/4 3-13 W 15 ISi2

(

TABLE 3.3-3 (Continued)

TABLE NOTATION (a) Trip function may be bypassed in this MODE when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer pressure is greater than or equal to 400 psia.

(b) An SIAS signal is fi st necessary to enable CSAS log'ic.

(c) Actuated equipment only; does not result in CIAS.

The provisions of Specification 3.0.3 are not appitcable,.

a With irradiateo' fuel in the storage pool.

ACTION STATEMENTS ACTION 8 -

With the number of OPERA 8LE channels one less than the Total Number of Channels, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least NOT STAN08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

ACTION 9 -

With the number of channels OPERA 8LE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the Ptoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is bypassed, the. desirability of maintaining this channel in the bypassed conditfor shall be reviewed in accordance with Specification 6.5.1.64.

The channel shall be returned to 0PERA8LE status no later than during the next COLD SHUT 00Vn.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Mea'surement Circuit Functional Unit Bypassed

1. Containment Pressure - Ffgh Containment Pressure - High (ESF)

Containment Pressure - High (RPS)

2. Steam Generator Pressure -

Low Steam Generator Pressure - Low Steam Generator aP 1 and 2 (EFAS)

3. Steam Generator Level Steam Generator Level - Low Steam Generator Level - Hign Steam Generator aP (EFAS)

/

emM

- , , , . . _ _ . - - - , " * " " " " ~ ~ '

INSTRUMENJAM INCORE DETECTORS LIMITING CON 0! TION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERA 8LE with:

a. Atleast75%ofallincorecetectorlocations,a$d

b. A minimus of.two quadrant symmetric incore detector locations per core quadrant.

An OPERABLE incore detector location shall consist of a fuel assembly containing a fixed cetector string with a sinimum of four OPERA 8LE rhodium detectors or an OPERA 8LE movable incore detector capable of mapping the location.

APPLICA81LITY: When the incore detection system is used for monitoring:

a. AZIMUTHAL POWER TILT,

b. Radial Peaking Factors,

c. Local Power Density,

d. Ot:8 Margin.

ACTION:

With the incore detection system inoperable, do not use the system for the l aoove applicable monitoring or calibration functions. The provisions of Specifications 3.0.3 are not applicable.  !

SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore detection systes shall be demonstrated OPERA 8LE:

a. By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use if 7 or more days have elapsed since the prsvious check and at least i once per 7 days thereafter when required for monitoring the AZIMLOAL POWER TILT, radial peaking factors, local power density or DNP sirgin:

b. At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but inchdes all electronic components. The neutron detectors shall be calibrated ,

prior to installation in the reactor core.

I SAN ON0FRE - UNIT 3 3/4 3-41 AMENOMENT N0. 38 l

1 INSTRUMENTAYION

\

SEISMIC INSTRUMENTATION" l

LIMITING CONDITION FOR OPERATION l

3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall ee i

OPERA 8LE.

4 APPLICA8!LITY: -At all times.

ACTION: ~ -

a. With one or more seismic monturing instruments inoperable for more i than 30 days, prepare and submit a Special Report to the Commission  !

pursuant to Specification 6.9.2 within the next 10 days outlining j the cause of the salfunction and the plans for restoring the <

instrument (s) to OPERA 8LE status, l

b. The provisions of Specifications 3.0.3 are not applicable..

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be-demonstrated OPERA 8LE by the performance of the CHANNEL CHECX, CHANNEL  ;

CALIBRATION and CHANNEL FUNCTIONAL TEST ope *,ations at the frequencies shown in '

Table 4.3.-4. -

, 4.3.3.3.2 Each of the above seismic monitoring instruments which is accessible '

during power operation and which is actuated during a seismic event (one or more valid basemat accelerations of 0.05g or greater) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a CHANNEL CALIBRATION performed within 5 days.

, Data shall be retrieved from the accessible actuated instruments and analyzed to detarsine the magnitude of the vibratory ground niotion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum

'and resultant effect upon facility features important to safety . Each of the above seismic monitoring instruments which is actuated during a seismic event (one or more valid basemat accelerations of 0.05g or greater) but is not accessible during power operation shall be restored to OPERA 8LE status and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below. A supplemental- repor.t shall then be prepared and submitted to the Comission within 10 days pursuant to Specification 6.9.2 describing the additional data from these instruments. ,

"Shared system with San Onofre - Unit 2.

SAN ONOFRE-UNIT 3 3/4 3-42 $091D

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION" LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological sonitorfng instrumentation channels shown in 4

Table 3.3-8 shall be OPERA 8LE.

APPLICA8ILITY; -At ail times.

ACTION:

a. With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Resort to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the salfunction and the plans for .

restoring the channel (s) to OPERA 8LE status,

b. The provisions of Specifications 3.0.3 are not applicable. .

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above =steurological sonitoring instrumentation channels shal1~be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.

~

"Shared system with San Onofre - Unit 2.

SAN ONOFRE-UNIT 3 3/4 3-45

_ . _ _ _ ._ _ _ _ _ _ - . -i

L l

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION 3.3.3.8 The radioactive 11guld effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the lief ts of Specification 3.11.1.1 are not exceeded. The alarm /

trip setpoints of these channels shall be determined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (00CM).

APPL.!CA811.!TY: At all times.

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alars/ trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the  !

channel inoperable.  !

b. With less than the minimus number of radioactive liquid effluent I monitoring instrumentation channels OPERA 8LE, take the ACTION shown l in Table 3.3-12. Exert best efforts to return the instrument to CPERABLE status within 30 days and, additionally, if the inoperable l instrument (s) remain inoperable for greater than 30 days, explain in the next Semiannual Radioactive Effluent Release Report why the inoperanility was not corrected in a timely manner,

c. The provisions of Specifications 3.0.3 and 6.9.1.13b are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channet shall be daaonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.

4.3.3.8.2 At least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, all pumps required to be providing dilu- I tion to meet the site radioactive effluent concentration limits of Specifica-tion 3.11.1.1 discharge sh:11 be determined to be operating and providing dilution to the structure.

SAN ON0FRE - UNIT 3 3/4 3-64 AMN00ENT NO. 46 v , n, - - -, ,,-- ,,,.,-- - - - - , , ---, w r-,,,,,,.,_.,,__,_--,.,_,_w, --_,,__.,,_, , , , , - . - - - - . . . . , _ . _ , , . , _ _ _ _ , e,-,-m, m-e,.,,-a,em-,,-

i INSTRtMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERA 8LE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the 00CM.*

l APPLICA8ILITY: As shown in Table 3.3-13 A.CTION:

I a.

With a radioactive gaseous effluent monitoring instrumentation channel alars/ trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous affluents monitored by the affected channel or declare the '

channel inoperable.

b.

With less than the minimus' number of radioactive gaseous effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown '

in Table 3.3-13.

Exert best efforts to return the instrtment to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain inoperable for greater than 30 days, explain i in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner,

c. The provisions of Specifications 3.0.3 and 6.9.L13b are not i

applicable.  !

I SURVEILLANCE REQUIREMENTS i 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall bw demonstrated OPERA 8LE by performance of the CHANNEL CNECK, SOURCE I CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

"Continuous monitoring and sampling of the containment purge exhaust directly from the purge stack shall be provided for the low and high voltme (8-inch and 42-inch) outage. containment purge prior to startup following the first refueling Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associated sampling media shall perfore these functions prior to itiitial criticality.

Froa initial criticality to the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sampling media shall perform the above required functions.

! SAN ON0FRE UNIT 3 t

3/4 3 69 AMDCMENT NO. 20

(

INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION 3.3.3.10 The loose part detection systes shall be OPERA 8LE.

APPLICA81LITY: MODES 1 and 2.

ACTION:

a.

With one or more loose part detaption systes channels inoperable for more than 30 d.ays prepare and rubeit a Special Report to the Commission pursuan,t to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 CPERA8LEEach channel ofof the by performance a: loose part detection system shall be demonstrated a.

CHANNEL CNECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

l l

JAN 11 1985 SAN ONOFRE-UNIT 3 3/4 3-76 AMENDMENT No. 20

~. _ _ _ _ _ _ _ _ . . _ _ . _ _ _ _

l l

i REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE 1 285'F l

LIMITING CONDITION FOR OPERATION i

3.4.8.3.1 At least one of the following overpressure protection systems shall l be OPERA 8LE:

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

. 1) A lift setting of 406 2 10 psig*, and

2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or, b.

The Reactor Coolant Systes depressurized with an RC5 vent of greater than or equal to 5.6 square inches.

APPLICA8ILITY:

PCCE 4 when the temperature of any one RCS cold leg is less i than or equal to 285'F; M00E 5; MODE 6 with the reactor vessel head on.

ACTION:

a.

With the SOCS Relief Valve inoperable, reduce T,,, to less than ,

200'F, depressurize and vent the RCS through a greater than or equal to 5.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.  !

b.

With one or both SOCS Relief Valve isolation valves in a single 50C5 Relief Valve isolation valve pair (valve pair 3HV9337 and ,

3HV9339 or valve pair 3HY9377 and 3HV9378) cTosed, open the closed valve (s) within 7 days or reduce T to less than 200*F, depres-surizeandventtheRCSthrougha$Isterthanoraquelto5.6inen vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c.

In the event.either the 50C5 Relief Valve or an RCS vent is used to mitigate an RCS pressure transient, a Special Report shall be preparec and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initi-ating the transient,.the effect of the SOCS Relief Valve or RCS vent on the transient and any corrective action necessary to prevent recurrence.

SURVEILLANCE REQUIREMENTS 4.4.8.3.1.1 The SOCS Relief Valve shall be demonstrated CPERA8LE by:

a. Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the 50C5 Relief Valve is being used for overpressure protection that SDCS Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 are open.

/

\

"Tnt lif t setting. pressure applicable to valve temperatures of less than or 4

equal to 130*F.

SAN ON0FRE-UNIT 3 3/4 4-33 Ni

..$ " , -yid -

3 ,

e REACTOR C00 TANT SYSTEM 3.4.9 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.9 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.9.

APPLICA8!LITY: ALL MODES ACTION:

I a. With the structural integrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the sinimum temperature required by NOT considerations. h..,

b. With the structural integrity of any A5ME Code Class 2 component (sS/

not conforming to the above requirements, restore the structural -

integrity of the affected component (s) to within its limit or isolate the affected compoaent(s) prior to increasing the Reactor Coolant System temperature anove 200*F.

c. With the structural integrity of any ASME Code Clasr 3 component (s) no's confereing to the above requirements, restore the structural integrity of the affected conoonent to within its limit or isniate the affected component free service.

SURVEILLANCE REQUIRDENTS 4.4.9 In' addition to the requirements of Specification 4.0.5, each Reactor Coolant Pimp f1W1 shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

/

\

SAM ONOFRE-UNIT 3 3/4 4-36

i l

l l

PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION I LIMITING CON 0! TION FOR OPERATION 3.7.7 Each sealed source containing radioactive material either in excess of d 100 microcuries of beta and/or gamma emitting material or 5 microcuries of

' alpha emitting material shall be free of greater than or equal to O.005 microcuries of removable contamination.

APPLICA&IUTY: At all times.-

ACTION:

a. With a sealed source having removable contamination in excess or the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission Regulations.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.7.1 Test Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.  :

4.7.7.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission detectors previously subjected to core flux) shall be tested at the frequencies described below,

a. Sources in use - At least once per six montns for all sealed sources containing radioactive material:

i

1. With a half-life greater than 30 days (excluding Hydrogen 3),

and 1

\

2. In any form other than gas. ,e i

l NOV 151981 SAM ON0Fo!-UNIT 3 3/4 7-25

1 l

l l

RF. FUELING OPERATIONS l

3/4.9.9 CONTAINMENT DURGE ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The containment purge isolation system shall be OPERA 8LE.

APPLICA81LITY:

During CORE ALTERATIONS or movement of irradiated fuel within

, the containment.

ACTION:

- With the containment purge isolation systes inoperable, close each of the containment purge penetrations providing direct access from the containment atmosphere to the outside atmosphere.

SURVEILLANCE REQUIREMENTS 4.9.9 The containment purge isolation systes shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CCRE ALTERATIONS by verifying that containment purge valve isolation occurs on manual initiation and on a high radiation test signal. .

l

/

t NOVi51982 SAN ON0FRE-UNIT 3 3/4 9-10

REFUELING OPERATIONS 3/4.9.12 FUEL HAN0 LING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM -

I LIMITING CON 0! TION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter systems shall be OPERA 8LE.

t APPLICA8!LITY: Whenev'er irradi3ted fuel 's in the storage pool.

ACTION:

a. t With one fuel handling building post-accident cleanup filter systee inoperable, fuel movement within the storage poc) or operation of {

fuel handlfr,g nachine over the storage pool scy proceed provided the l

0PERA8LE fuel handling building post-accident cleanup filter sy:;tes is capable of being powered from an CPERA8LE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal absorters, b.

With no fuel handling building post-accident cleanup filter systes  ;

OPEAA8LE, suspend all operations involving movement of fuel within l the storage pool or operation of fuel handling nachine over the i storage pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERA 8LE status. j 1

SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling bui Wing post-accident cleanup filter systems shall be demonstrated CPERASLE:

a.

At least once per 31 days on a STAGGERED TEST 8 ASIS by initiating, free the control roce, flow through the HEPA filters and charcoal adsorters and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.

b. At least once per 18 months or (1) af ter any structural saintenance 1 on the HEPA filter or charcoal adsorber housings, or (2) following  !

painting, fire or chemical release in any ventilation zone communicating with the system by: j i

i l

SEP 3 01985 SAM QN0FRE - UNIT 3 3/4 9-13 AMEN 0 MENT Mo. 25

i t

/

RADI0 ACTIVE EFFLUENTS 00$E i l

i LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive l aaterials in liquid effluents released, from each reactor ur.it, from the site (see Figure 5.1-4) shall be limited:

J a.

During any calendar quarter to less than or equal to 1.5 area to the

, total body and to less than or equal to 5 seem to any organ, anc b.

During any calendar year to less than or equal to 3 area to the total body and to less than or equal to 10 ares to any organ.

APPLICA8ILITY: At all times.

_ ACTION:

a. .

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above Ilmits, in iteu of' any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the Ifmit(s) and. defines the corrective actices taken to reduce the releases and the proposed actions to be taker. to assure that subsequent releases will be in compliance with Specification 3.11.1.2 b.

The provisions of Specifications 3.0.3 are not applicaele.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Dese Calculations. Cumulative dose contributions from liquid effluents 31 days. shall be eetermined in accordance with the 00CM at least once per

. f- t',7.' 1 U UI.

m SAN ONOFRE-UNIT 3 3/4 11-5

---

n , . .,, ,, ,

1 RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATNENT LIMITING CONDITICN FOR OPERATION t 3.11.1.3 The liquid radwaste treatment system shall be OPERA 8LE. The appropriate portions of the system shall be used to reduce the radioactive e eaterials in liquid wastes prior to their discharge when'the projected doses due to the liquid affluent from the site (see Figure 5.1-4) when averaged over

. 31 days, would exceed 0.06 area to the totai body or 0.2 area to any organ."

APPLICA8!LITY: At all times.

ACTION:

a.

With the liquid radwaste treatment system inoperable for more than 31 days or with radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of any other, report reqaired by specification 6.9.1, prepare and submit to the Commission within 30 days pursuant to 3pecification 6.9.2 a Special Report which includes the following information:

, 1.

16entif' cation of the inoperable equipment or subsystems and the r&ason for inoperability, 2.

Action (s) taken to restore the inoperable equipment to OPERA 8LE status, and 3.

Summary description,of action (s) taken to prevent a recurrence.

b.

The provisions of Specifications 3.0.3 are not appifcable.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 31 days, in accordance Doses duewith to liquid releases shall be projected at least once per the 00CM.

4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated CPERA8LE by ope ating the liquid radwaste treatment systes equipment for at least 15 minutes at least once per 92 days unless the liquid radwaste system hasdays.

92 been utilized to process radioactive liquid effluents during the previous

=

Per reactor fu it HOV 151982 SAN ONOFRE-VMIT 3 3/4 11-6

{ _ . . _ _ - -

1

/

RADICACTIVE EFFLUENTS LIQUID HOUXF TANK 5 LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive saterial contained in each outside temporary tank shall be limited to less than er equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

J

, APPLICA8ILITY: At all times. . -

ACTION:

4.

With the quantity of radioactive material in any outside temporary tank exceeding the above limit, immediately suspend all additions of radioactive meterial to the tank and withit 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the Ifnit. *

b. The provisions of Specifications 3.0.3 are not applicats"1e.

I SURVEILLANCE REQUIREMENTS b 4.11.1.4 The quaniity of radioactive saterial contained in each outside temporary tank shall be determined to be within the above lia't by analy:ing a representative sample of the tank's contents at least once per 7 days wnen radioactive materials are being added to the tank.

NOV 151982 SAN ONOFRE-UNIT 3 3/4 11-7 l

_ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - ~ ~ ' - ' ~~'

' ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~'

j%: , .

[

RA010 ACTIVE EFFLUENTS DOSE - NO9LE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, frem each reactor unit, from the site- (see Figure 5.1-3) shall be Itaited to the following:

a. During any calendar quarter: Less than or equal to 5 arad for gamma radiation and less than pr-equal-te 44-erad for beta radiation and, b., Ouring any calendar year: Less than or equal to 10 arad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICA8ILITY: At all times.

ACTION 1 '*

a. With the calculated air dose free radioactive noble g6ses in gaseous effluents exceeding any of the above li its, in Iteu of any otherg report required by Specification 6.9.1, prepare and submit to the

( Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifles the cause(s) for exceeding the liait(s) and defines the corrective actions taken to reduce releases and the proposec '

corrective actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.2.2.

b. The provisions of Specifications 3.0.3 are not appitcable.

SURVEILLANCE REQUIREMENTS ._

4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accorcance with the 00CM at least once pes

• 31 days.

! /

g SAN ON0FRE-UNIT 3 3/4 11-12

.m..- , , ,-,--- , - _ , . . - . _ _ _ , . _ . - - . .m,- , , . - . _ , . _ _ _ , . _ _ _ . _ _ _ _ , , _._-,_,._.__-____,__,,-.,_..,s.,._ _w..._-_ . , , _ - . . . . - .

l 2

I i l

RA0f0ACTAVE EFFLUENTS 00SE - RADICI00!NES. RA010 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM l

i l LIMITING CON 0!T!0N FOR OPERATION l

3.11.2.3 The dose to an individual from trittua, radiciocines and radioactive saterials in particulate form with half-lives greater than 8 days in gaseous ef fluents relused, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:

a. During any calendar quarter: Less than or equal t'o 7.5 area to any argan and,

b. During any calendar year: Less than or equal to 15 ene to any organ.

c. Less thancontaminated 0.13 of the limits of burning oil. of 3.11.2.3(a) and (b) as a result APPLICA8!LITY: At all times.

ACTION:

a. With the calculated dose from the release of tritius, radiofodines, and radioactive eaterials tr. particulate fore, with half lives 1 greater than 8 days, in gaseous effluenta exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 4.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the carrective actions taken to i reduce releases and the proposed actions to be taken to assure that subsequent rolesses will be in compliance with Specification 3.11.2.3.

b. The provisions of Specifications 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4

4.11.2.3 Dese Caleviations Cumulative dose contributions for the current calendar quarter and current calendar year shall be detamined in accordance with the 00CM at least once per 31 days. t l

l SAN ONOFRE-UNIT 3 3/4 11-13 AMEMOMENT No. 41 i

1

1 RADI0 ACTIVE EFFLUENTS

, 1 GASEOUS RA0 WASTE TREATMENT LIMITING CON 0! TION FOR OPERATION 3.11.2.4 The GASEOUS RA0 WASTE TREATMENT SYSTEM and the VENTIL TREATMENT SYSTEM shall be OPERA 8LE. The appropriate portions of the GASE005 RA0 WASTE TREATMENT SYSTEM shall be used to reduce radir'ctive matarials gaseous waste prior to their discharge when the projected gaseous effit:ent Sir doses due to gaseous affluent releases from the site (see Figure 5.1-3), when  !

averaged over 31 days, would exceed 0.2 erad for gamma radiation a9d 0.4 erad i for beta radiation. The appropriate portions of the VENTILATICN EXHAUST I TREATMENT SYSTEM shall be used to reduc's radioactive materials in gaseous - -

waste prior to their discharge when the projected doses due to gaseous  !

effluent releases from the site (see Figure 5.1-3) when averaged over 31 days I would exceed 0.3 area to any organ.*

APPLICA81LITY: At all times.

ACTION:

a.

With the GASEOUS RA0 WASTE TREATMENT SYSTEM and/or the VENTILA EXHAUST TREATMENT SYSTEM inoperale for more than 31 ettys or witA I gaseous waste being discharged without treatment and in excess of the above limits, in lieu of any other report required by Specifica-tion 6.9.), prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, 'a Special Report which includes the following information:

1.

IdentificatM*. of the inoperable equipment or subsystees and the reason for inoperability,

' 2. Action (s) taken to resture the inoperable equipment to OPERA 8LE status, and

3. Samary description of action (s) taken to prevent a recurrence.

b. The provisions of Specifications 3.0.3 are not spolicable.

SURVEILLANCE REQUIRD etTS 4.11.2.4.1 Doses due to gaseous releases fram the site shall be projected at i least once per 31 days, in accordance with the 00CM. 1

4.11.2.4 J The GASEOUS RA0 WASTE TREATMENT SYSTEM and VENTILATION EX TREATHEXT SYSTEM shall be demonstrated OPERA 8LE by operating the GASE0US )

RA0 WASTE TREATMENT 5YSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the )

sporopriate systes has been utilized to process radioactive gaseous eff1.ents f during the previous $2 dcys. -

"these doses are per reactor unit.

g 15 bbl.

SAM ONOFRE-UNIT 3 3/4 11-14 I

e 1 l

A i

( RADICACTIVE EFF1.UENTS EXPl.05IVE GAS MIXTURE i

f!MITING CONOTTION FOR OPERATION l

3.11.2.5 The concentration of oxygen in tha waste gas holduo system shall be ,

limitsd to less than or equal to 25 by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICA81LITY: At all tioM.

ACTION.

a.

With the concentration of oxygen in the waste gas holdup systes  !

greater than 2% by volume but less than or equal to 4% by volume, restore the concentration of oxygen to within the limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. -

b.

With the concentration of oxygen in the weste gas holdup system g greater than 4% by volume, immediately swepend an additions of -v ,

waste gases .to the system and reduce the concentration of oxygen th less ths.n 4% by volume within one taur aind less than or equal to S by volume within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. i

( I

c. The provisions of Specifications 3.0.3 are net applicable.

SURVE!t. LANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas holduo systes shall be determined to b) within the above lief ts by continuously moni- .

t toring the waste gases in the weste gas holduo system with the hycrogen and oxygen monitors required CPERA8LE by T.sble 3.3-13 of Specification 3.3.3.9.

' /

~-

Hoy i 51982 SAN ONOFRE-UNIT 3 3/4 11 15 t

_ . _ _ _ _ _ . . _ . - . _ , _.________.._._____..__.__..L

l

~.s I g ,p.- .

v ;, .

l RADI0 ACTIVE EFFLUENTS -

3/4.11.3 SOLID RADICACTIVE WASTE l

LIMITING CONDITION FOR OPERATION l

.t .1 'i , 3 The solid radwaste system shall be OPERA 4LE and used, as applicable in accordance with a PROCESS CONTROL PROGRAM, for the SOLIO!FICATION and packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site.

APPLICABILITY: At all times."

ACTION:

a. With the packaging requirements of 10 CFR Part 20'and/or 10 CFR Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes from the site. I

b. With the solid radwasta system. inoperable for more than 31 days. in lieu of any other report required by Specification 6.9.1, prepare (

and subett to the Commission within 30 days pursuant to Specificaf tion 6.9.2 a Special Report whicti includes the following information:

(

). Identification of the inoperable equipment or subsystems and the reason for incperability,

2. Action (s) taken to restore the inoperable equipes-t to OPERA 4LE status, -

3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4 Susanary description of action (s) taken to prevent a recarrener.

c. The provisions of Specifications 3.0.3 are not applicable.

SURVEIL W E REQUIRD effs 4.11.3.1 The soH.i radwaste system shall be desmnstrated OPERA 8LE at least once per 92 days by:

a. Operating the solis radwasta system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or l O.

Veriff eation of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL g PROGRAM. /  !

l l

"See Specification 6.13.1.

15 W M ONOFRE-UNIT 3 3/4 11-17 M

M

t

[ RADI0 ACTIVE EFFLUENTS .

l 3/4.11.4 TOTAL DOSE

, $~

t.IMITING C0PCITION FOR OPERATION 3.11.4 The dose or dose commitment to any soeber of the public, due to i releases of radioactivity and radiation, from uranium fuel cycle sources shall  ;

d be limited to less than or equal to 25 ares to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 area) l over 12 consecutive months.

APPt.ICA81LITY: At all times.

ACTION: "

l a.

With the calculated doses from the release of radioactive saterials l in liquid or gaseous effluents exceeding twice the. limits of Specification 3.11.1.2.a. 3.11.1.2.b, 3.11.2.2.a. 3.11.2.2.b, i 3.11.2.3.a. or 3.11.2.3.b, in lieu of any othef: report. required tr3 !

Specification 6.9.1, prepare and submit a Special Supert to the i -

{

Director, Nuclear Reactor Regulation, U.Si Mucteer Regulatory Coewission. Washington. 0.C. 20555, within 30 daye, dich defined ef e

.j '

l

/ the corrective action to be taken to reduce sesequent releases to prevent r:currence of exceeding the limits of Specification 3.11.4 This Special Report shall include an analysis which estimates the radiation exH sure (dose) to a member of the PW11C from urani a fuel cycle sources (including all effluent pathways and direct.

radiation) for a 12 consecutive month period that includes the release (s) covered by this report. If the estimated dese(s) exceeds the limits of Specification 3.11.4, and if the release condition  !

resulting in violation of 40 CFR 190 has not already been corrected. l the Special Report shall include a request for a va: f ance in j

accordance with the provisions of 40 CFR 190 and including the specified information of I 190.11(b). Submittal of the report is 1 considered a timely request, and a variance is granted until staff l action on the request is complete. The variance only relates to the  !

limits of 40 CFR 190, and does not apply in any way to the require- 1 monta for dose limitation of 10 CFR Part 20, as addressed in other )

, sections of this technical specification,

b. The provisions of Specifications 3.0.3 are net appilcable.

SURVEILLANCE REQUIREMENTS 4.11.4 Dese Calculations Cumulativt dose contributions free liquid and gaseous effluents snail be determined in accordance with Specifications 4.11.1.2. 4.11.2.2, and 4.11.2.3, and in accordance with t4 00CM.

SAN ONOFRE-UNIT 3 3/4 11-19

)

i

/ 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological envirensental monitoring program shall be conductec as specified in Table 3.12-1.

APPLICA8!LITY: At all times. .

ACTIOM: .

a.

With the radiological environmental monitoring progran not being - -

conducted as specified in Table 3.12-1, in Iteu of any other report required by Specification 6.S.1, prepare and submit to the Coe-mission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, b.

l With the level of radioactivity in an environmental sampling medign any calendar quartar, in lieu of any other report req Specification 6.9.1, prepara and submit to the Cosumission within ,

30 days from the end of the affected calendar quarter a Report f pursuant to Specification 6.S.1.13. When more than one of the radionuclides in Table 3.12-2 are detectM in the sampling medium, this report shall be submitted if:

concentration. (1) , concentration (2) + * * *) 1.0 limit level (1) limit level (2) -

When radionuclides other than those in Table 3.12 2 are detected and are the rssult of plant effluents, this report shall be submitted if the potential' annual dose to an individual is equal to or greater than the calendar year limits of Specification 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the seasured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

c. With fresh leafy vegstable samples or fleshy vegetable samoles unavail-able free one or more of the sample locations required by Table 3.12-1,

! in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specific-ation 6.9.2, a Special Report which identifies the cause of the unavail-ability of samples and identifies locations for obtaining replacement samples. The locations free which samples were unavailable may then be deleted from those required W M a L 12-1. provided the locations f rom which the replacement samples were obtained are added to the environmental monitoring program as replacement locations.

/ d. The provisions of Specifications 3.0.3 are not appli:able.

HOV 15 382 SAN ONOFRE-UNIT 3 **

3/4 12-1

)

E. .. . .,

( RA0!0 LOGICAL ENVIRONMENTAL MONITORING 3/t.12.2 LAND USE CENSUS LIMITING C0fe! TION FOR OPERATION '

3.12.2 A land use census shall be conducted and shall idestify the location of the nearest milk animal, the nearest nsidence and the wrest garden" of greater than 500 square feet producing fnsh leafy vegetables in eac!* of the 16 meteorological sectors within a distance of five stlts. For elevated  !

releases as defined in Regulatory Guide 1.111 Revision 1 July 1977, the land t use census shall also identify the locations of all silk animals and all gardens of gnatar than 500 square feet producing fresh leafy vegetables in

- each of the 16 meteorological sectors within a distance of three siles.

APPLICA8ILITY: At all times. l ACTION:

a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values curnntly being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.9.1., prepare and submit to ,

Commission within 30 days, pursuant to Specification 6.9.2, a F Special ieport which identifies the new location (s). .

b. With a land use census identifying a location (s) which yields a' #

7 calculated dose or dose commitment via the same exposure pathway 20 percent g natar than at a location free which samples are currently being obtained in accordance with Specification 3.12.1, in lieu of any other report required by Specification 6.9.1, prepare '  ;

and submit to the Csemission within 30 days, pursuant to specifica-tion E.9.2, a Special Report which identifies the new location. Th'e new location shall be added to the radiological environmental i monitoring program within 30 days. The sampling location, excluding the control station location, having th) lowest calculated cose or dose commitment via the same exposure pathway may be delettd from this monitoring program af ter October 31 of the year in which this

) land use census was conducted.

c. The provisions of Specifications 3.0.3 are not applicaele.

i SURVEILLANCE REQUIRD Wif5 4.12.2 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1 using that information which will provide the best Msults, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities.

A

' troad leaf vegetation sampling may be performed at the site boundary in the dinction sector with the highest D/Q in lieu of the garden census.

, /

KCV i 619E 1 l SAN ON0FRE-UNIT 3 3/4 12-11 i

v w- T ,__

_ _ _ ___- . _ - - - - - - - - - - - - - ~ ~ - ~ ~I

l 1

.," C 1

( PA010t.0GICAL ENVIRONMENTAL McMITORING 3/4.12.3 INTIRLA80RATORY COMPARISON PROGRAM

'yu t.IMITING C000TTf0N FOR OPERATION 1

1 3.12.3 Analyses shall be performed on radioactive materials supplied as part j of an Interlaboratory Comparison Program which has been approved by the i Commission.

APPLICA87LITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmentti OperatiM Repert.

b. The provisions of Specifications 3.0.3 are not applicable.

.g .v SURVE!LLANCE REQUIREMENTS 4.12.3 A summary of the results obtained as part of the above' required Interlaboratory Comparison Program and in accordance with the 0004 shall be included in the Annual Radiological Environmental Operating Report.

I I

i i

s /  ;

NOV 15 HE2 SAM ONOFRE-UNIT 3 3/4 12-12

3/4.0 APPLICABILITY BASES _

Specification 3.0.1 through_].0,4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based '

on the requirements for Limiting Conditions for Operation stated in the Code of federal Regulations,10 CFR 50.36(c)(2):

"Limiting conditions for operation are the lowest functinnal capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicabliity statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL N00ES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The ACil0N requirements establish those remedial measures that must be taken within specified tinw limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements. In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as tne ACTION requirements continue to be net. The second type of ACTION requirement specifies a time limit in which confernence to the conditions of the Limiting Condition for Operation must be niet. This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a NODE or condition in which the specification no longer applies.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not

, met. The time limits of the ACTION requireme. t are also applicable when a system or component is removed from service :r surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the CJJpletion of a Surveillance Requirement when

, equipment is removed from service. In this case, the allowable outage time limits of the ACTION requirements ire applicable when this limit expires if the surveill:nce has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered a N00E in which a new specification becomes applicable. In this case, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable i? the requirements of the limiting Condition for Operation are not met.

1 l

SAN ONOFRE - UNIT 3 8 3/4.0-1 '

m - - - - -

_. -. _._..-.___._c . . - . ,,-. _ _ _ ,

3/4.0 APPLICABILITY BASES (Con't)

Specification 3.0.2 establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements withir, the specified time interval constitutes compliance with a specification and (2) corspletion of the remedial measures of the ACTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Soecification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its AClION requirements. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant operation. This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures permitting limited continued operation of the facility under the provisions of the ACTION reouirements are completed, the shutdown may be terminated. The time limits of the ACTION requirementt are applicable from the point in time there was a failure to meet a limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in the COLD SHUTOOWN MODE when a shutdown is required during the POWER MODE of operation. If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation applies. However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced, for example, if HOT STAN0BY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the time ailowed to reach HOT SHUTOOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUT 00WN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

SAN ONOFRE - UNIT 3 8 3/4.0-2 s _

3/4.0 APPLICABILITY BASES (Con't)

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes applicable in less time than specified the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACTION requirements for a higher MODE of operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in'a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a ,

higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by estoring equipment to OPERABLE status or parameters to specified limits. Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a MODE change. Therefore, in this case, entry into an OPERATIchAL MODE or other specified condition may be made in accordance with the provisions of the ACTION requirements. The provisions of this specification should not, hea.% 'r, be interpreted as endorsing the failure to exercise good practh, restoring systems or components to  ;

OPERABLE status before plant startup.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Specifications 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of federal Regulations, 10 CFR 50.36(c)(3): l l

' Surveillance requirements are requirements relating to test, I calibration, or inspection to ensure that the necessary quality of systems and I components is maintained, that facility operation will be within safety 1 1

limits, and that the limiting conditions of operation will be met.'

i l

SAN ON0fRE - UNIT 3 8 3/4.0-3 i

3/'.0 APPLICABILITY BASES (Con't)

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL H0 DES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillances are pr formed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a. permits an allowable extension for the normal surveillance interval to facilitaie surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b.

limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 4.0.2 are based on engineering judgment and the recognition that the most probable result of any particular surveillant.e being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation.

Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this

, provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. 1.is specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply IrN the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specifications 4.0.3. However, this does not negate the fact that the failure to have SAN ONOFRE - UNIT 3 8 3/4.0 4

3/4.0 APPLICABILITY BASES (Con't) performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification re'quirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(8) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time limits of the ACTION tequirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance h provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requireraents that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required thit may preclude completion of a surveillance. The basis for this allwance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required serveillance. This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allowance, the time 'imits of the ACTION requirements are applicable at that time. When a surveillance is performed '

within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.

However, the Surveillance Requirements have to be met to demonstrate that 1 inoperable equipment has been restored to OPERABLE status.

Surveillance 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or conoitton for which these systems and component ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

SAN ONOFRE - UNIT 3 8 3/4.0-5 l  !

l i

l 1

3/4.0 APPLICABILITY BASES (Con't)

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during inittel plant startup or following a plant outage.

When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the facility in a lower MODE of operation.

Specification 4.0.5 establishes the requirements that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as reqJired by 10 CFR 50.55a. These requirements apply except when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This  ;

clarification is provided to ensure consistency in surveillance intervals j throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure j Vessel Code provision which allows pumps and valves to be tested up to one <

wen after return to normal operation. The Technical Specification definition i of OPERABLE does not allow a grace period before a component, what is not j capable of performing its specified function, is declared inoperable and takes  ;

precedence over the ASMC Boiler and Pressure Vessel Code provision which  ;

allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

8701F l

l I

SAN ONOFRE - UNIT 3 8 3/4.0-f.

b

1 I

DESCRIPTION OF PROPOSED CHANGE NPF-10/15-239 AND SAFETY ANALYSIS ,

l This is a request to revise Technical Specification 3/4.3.2, "Engineered i Safety Feature Actuation System Instrumentation". '

Existina Soecifications Unit 2: See Attachment "A" Unit 3: See Attachment "C" l Procostd Soecifications Unit 2: See Attachment "B" Unit 3: See Attachment "0"

)

0escriotion The proposed change revises Technical Specification (TS) 3/4.3.2, "Engineered Safety Feature Actuation System Instrumentation" (ESFAS). TS 3/4.3.2 snecifies the number of channels and type of instrumentation required to be operable, response times and periodic surveillance tests to verify operability, and actions to be taken when the minimum requirements are not met. The ESFAS instrumentation operability requirements include a response time for the Main Steam Line Isolation Valves (MSIV) which is specified in Table 3.3-5 "Engineered Safety Features Response Times". The MSIV response time is specified in two locations in Table 3.3-5, one associated with the Main Steam Isolation Signal (MSIS), the other associated with the Containment Isolation Actuation Signal (CIAS). When the San Onofre 2 & 3 Technical Specifications were originally issued, the MSIV response time was 5.0 seconds and was identified only with the MSIS entry on Table 3.3-5. Proposed change

' PCN-96 was submitted on November 30, 1984. PCN-96 increased the MSIV response time from 5.0 to 6.0 seconds and also added a response time of 6.0 seconds for  ;

the MSIV's under CIAS in Table 3.3-5. Prior to approval of PCN-96, SCE  :

submitted PCN-207 which increased the MSIV response times to 8.0 seconds. '

8ecause PCN-96 had not yet been approved, PCN-207 did not request that the CIAS entry response time in Table 3.3-5 be increased to 8.0 seconds. PCN-96, which Instituted a CIAS MSIV response time of 6.0 seconds, was approved by Amendments 45 and 35 for Units 2 & 3, respectively, on May 16, 1986.

Subsequently when PCN-207 was approved by Amendments 60 and 49 on August 14, 1987 an editorial discrepancy between the MSIV response times listed in Table l 3.3-5 under MSIS and CIAS was created. The proposed change would correct this  ;

editorial discrepancy by increasing the CIAS MSIV response time to 8.0 '

seconds. Note that Table 3.3-5 includes a 0.9 second allowance for

{

instrumentation propagation delay thus, the actual table entry is increased i frem 6.9 to 8.9 seconds. l i

?

1 Safety Analysis The proposed changes discussed above shall be deemed to involve a significant hanrds consideration if there is a positive finding in any one of the following areas:

1. Hill operation of the facility in accordance with this proposed change ,

involve a significant increase in the probability or consequences of an '

accident previously evaluated?

Response: No The proposed change corrects an editorial discrepancy between closure time for the HSIV's. The HSIV's are provided to prevent the blowdown of more than one steam generator in the event of a main steam line break.

The effects on the safety analysis of increasing response time to 8.0 seconds was evaluated in conjunction with approval of PCN-207 in Amendments 60 and 49 and were found to be acceptable. Because this proposed change merely corrects an editorial discrepancy, the proposed change does not result in an increase in the probability or consequences of a previously evaluated accident. '

2. Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change corrects an editorial discrepancy in the Technical Specifications, therefore it does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Will operation of the facility in &ccordance with the proposed change involve a significant reduction in a margin of safety? ,

Response: No The proposed change corrects an editorial discrepancy and therefore does not affect any margin of safety.

The Commission has provided guidance for determining whether a significant hazards exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards considerations.

Example (i) relates ;o a purely administrative change; for example, a change to achieve consistency in the Technical Specifications, correction of an error, or a change in nomenclature. In this case, the proposed change increases the CIAS response time for HSIV's listed in Table 3.3-5 from 6.9 to 8.9 seconds, including instrumentation delay. This change makes the CIAS MSIV response time consistent with that listed under HSIS in Table 3.3-5 as well as i

In Technical Specification 3/4.7.1.5 which lists the HSIV response time as 8.0 seconds, excluding instrumentation delay. Because this proposed change corrects an editorial discrepancy created by the issuance of Amendments 60 and 49, it is similar to Example (1).

Safety and Sianificant Hazards Determination Based on the above Safety Analysis it is concluded that: (1) the proposed '

change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; and (2) there is reasonable assurance that the health and safety of the public will not 5e endangered by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.

1 PS:ft:0475H r

r I

i l

I 4

l

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

NPF-10/15-239 ATTACHMENT "A" a

1 1

E i

I

Table 3.3-5 (continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC) i

2. Pressurizer Pressure-Low -

a. SIAS ,

(1) Safety Injection (a) High Pressure Safety Ir.jection 31.2*

(b) Low Pressure Safety Injection 41.2*

(c) Charging Pumps 31.28 (2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)

(4) Containment Spray (Pugs) 25.6*

(5) Containment Emergency Cooling (a) CCW Pumps 31.28 (b' CCW Valves (Note 4b) 23.2*

(c) Emergency Cooling Fus 21.28

3. Containment Pressure-Hip

a. SIAS l

(1) Safety Injection (a) High Pressure Safety Injection 41.08 (b) Low Pressure Safety Injection 41.0*

(2) Control Room Isolation Not Applicable j

(3) Containment Spray (Pumps) 25.4* l (4) Containment Energency Cooling (a) CCW Pumps 31.0*

(b) CCW Valves (Note 4b) 23.0*

(c) Emergency Cooling Fans 21.0*

b. CIAS i (1) Containment Isolation 10.98 (NOTE 2) l (2) Main Feedwater Isolation 10.9 and Backup Isolation Valves (HV 4048,  !

HV 4052 HV 1105, HV 1106, HV 4047, I HV 4051)

(3) CCW Valves (Note 4a) 20.9 (4) Mainsteam Isolation Valves (HV S204, 6.9 I HV 8205)

(5) Minipurge Isolation Valves 5.9

4. ContainmerL[Lessure-High-High CSAS Containment Spray 23.0" SAN ONOFRE - UNIT 2 3/4 3-28 AMEN 0 MENT No. 46 L . _ . _ _ _ _ _ . . _ _ _

NPF-10/15-239 ,

t i  ;

t i

l ATTACHMENT "B" 1

I l

1, i

. 1 I

I i

i l i

i j

l i

l 1

i i

l

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

r q

l l

Table 3.3-5 (continued)

INITIATING SIGNAL AND FUNCTION RESPONSE TIME (SEC)

2. Pressurizer Pressurn-Low

a. SIAS (1) Safety Injection (a) High Pressure Sefety Injection 31.28 (b) Low Pressure Safety Injection 41.28 (c) Charging Pumps 31.28 (2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)

(4) Containment Spray (Pumps) 25.6*

(5) Containment Emergency Cooling ,

(a) CCW Pumps 31.28 (b) CCW Valves (Note 4b) 23.2" (c) Emergency Cooling Fans 21.2"

. 3. Containment Pressure-High .

a. SIAS (1) Safety Injection (a) High Pressure Safety Injection 41.0*

(b) Low Pressure Safety Injection 41.0*

(2) Control Roon Isolation Not Applicable (3) Containment Spray (Pumps) 25.4*

l (4) Containment Emergency Cooling l (a) CCW Pumps 31.0*

(b) CCW Valves (Note 4b) 23.0" l (c) Emergency Cooling Fans 21.0"

b. CIAS i

(1) Containment Isolation 10.98 (NOTE 2)

(2) Main Feedwater Isolation 10.9 l

and Backup Isolation Valves (HV 4048, HV 4052 HV 1105, HV 1106, HV 4047, NV 4051)

(3) CCW Valves (Note 4a) 20.9 (4) Mainsteam Isolation Valves (HV 8204, 8,9 l

, HV 8205)

(5) Minipurge Isolation Valves 5.9

4. Containment Pressure - High-High CSAS Containment spray 23.0*

SAN ONOFRE - UNIT 2 3/4 3-28  :

NPF-10/15-239 ATTACHMENT "C"

Table 3.3-5 (continued)  !

INITIATING SIGNAL AMD FUNCTION RESPONSE TIME (SEC)

2. Pressurfter Pressure-Low i

SIAS (1) Safety Injection (a) High Pressure Safety Injection 31.2" (b) Low Pressure Safety Injection 41.2"  ;

(c) Charging Pumps 31.2" i (2) Control Room Isolation Not Applicable

. (3) Containment Isolation (NOTE 3) 11.2" (NOTE 2)

(4) Containment Spray (Pumps) 25.6*

(5) Containment Emergency Cooling I (a) CCW Pumps 31.2* i (b) CCW Valves (NOTE 4b) 23.2" 1 (c) Emergency Cooling Fans 21.2"  !

3. Containment Pressure-High

a. SIAS (1) Safety Inject. ion (4) High Pressure Safety injection 41.0*

(b) Low Pressure Safety Injection 41.0* -

(2) Control Room Isolation Not Applicable (3) Containment Spray (Pumps) 25.4" (4) Containment Emergency Cooling (a) CCW Pumps 31.0" (b) CCW Valves (NOTE 4b) 23.0" (c) Emergency Cooling Fans 21.0"

b. CIAS (1) Containment Isolation 10.9" (NOTE 2)

(2) Main Fee & vater lackup Isolation 10.9 and Backup Isolation Valves (HV 4048, W 4052, NV 1105, NV 1106, HV 4047, W 4051)

(3) CCW Valves (Note 4a) 20.9 (4) Mainsteam Isolation Valves (HV 8204, 6.9 HV 82C5)

(5) Minipurge Isolation Valves 5.9

4. Containment Pressure - High-High CSAS .

Containment Spray 23.0" SAN ONOFRE - UNIT 3 3/4 3-28 AMEi40 MENT NO. 35

e d

. NPF-10/15-239 ATTACHMENT "0"

Table 3.3-5 (continued)

INITIATING SIGNAL AND F, UNCTION RESPONSE TIME (SEC)

2. Pressupiter Pressure-Low SIAS

( (1) Safety Injection I

(a) High Pressure Safety Injection 31.2" (b) Low Pressure Safety Injection 41.2" (c) Charging Pumps 31.2*

(2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)

(4) Containment Spray (Pumps) 25,6" (5) Containment Emergency Cooling (a) CCW haps 31.2*

(b) CCW Valves (NOTE 4b) 23.2*

(c) Emergency Cooling Fans 21.2*

3. OntainmentPressure-High

, a. SIAS (1) Safety Injection (a) High Pressure Safety Injection 41.0" (b) Low Pressure Safety Injection 41.0" *

(2) Control Room Isolation Not Applicable (3) Containment Spray (Pumps) 25.4*

(4) Containment Emergency Cooling (a) CCW Pumps 31.0" (b) CCW Valves (NOTE 4b) 23.0*

(c) Emergency Cooling Fans 21.0"

b. CIAS (1) Containment Isolation 10.9* (NOTE 2)

(2) Main Feedwater lackup Isolation 10.9 and lackup Isolation Valves (HV 4044, NV 4052 HV 1105, NV 1106, HV 4047, NY 4051)

(3) CCW Valves (Note 44) 20.9 (4) Mainsteam Isolation Valves (HV 8204, 8,9 HV 8205)

(5) Minipurge Isolation Valves 5.9

4. Containment Pressure - High-High i CSAS .

Containment Spray 23.0" SAN ONOFRE - UNIT 3 3/4 3-28

• DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGE NPF-10/15-240 This is a request to revise Technical Specification 3/4.4.4, "Steam Generators."

Existina Soecifications:

Unit 2: See Attachment A Unit 3: See Attachment B Procosed Soecificationi:

Unit 2: See Attachment C Unit 3: See Attachment 0 Descriotign:

The proposed change would revise Technical Specification 3/4.4.4, "Steam l Generators." The survoillance requirements for inspection of the steam j generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam l

generator tubes maintains surveillance of the condition of the tubes in the {

event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion. In SCE's letter dated April 5, 1985, SCE documented the existence of and the corrective action for steam generator tube wear caused by vibration of an internal diagonal support ("batwing wear"). The corrective action program includes a full 100 percent eddy current inspection of all tubes j falling within the "batwing wear" area during every refueling outage and the l preventative plugging of tubes.

l l The Technical Specifications currently require that at least 50% of the tubes i

selected for the routine inservice inspection shall be located in those areas l where experience has indicated potential problems. This would require, for a 3% random sample, more than half of the sample be located in the "batwing i

' wear" area which reduces the size of the first random sample throughout the generator to be less than 1.5%. Additionally, since the "batwing wear" area contains tubes which are subject to the known wear mechanism, the sample base may be increased beyond the initial 3%. However, any additional tube inspection would focus exclusively on the problem areas. Thus, although the tubes experiencing "batwing wear" have been enveloped by the aforementioned program, the current Technical Specifications, when applied as written, would effectively reduce the extent of the random sample outside the wear area and cause unnecessary expansion of the steam generator tube inspection sample basc into the wear area for each inservice inspection.

The proposed change would revise the Technical Specification surveillance requirements to require a special "batwing wear" area inspection and remove this area from the general tube sample selection. This increases the random tube selection outside this well-defined area and provides for a better inspection program. In addition, because the wear phenomenon in the "batwing wear" area is well understood, the results would not be included in the inspection results classification. In summary, the proposed change will revise the Technical Specification surveillance requirements to exclude tubes from the "batwing wear" area from the first tube inspection sample base.

Safety Analysis San Onofre Units 2 and 3 Steam Generator Desian San Onofre Units 2 and 3 have essentially identical, mirror imaged, steam generator installations. Each unit has two Combustion Engineering (C-E) designed Model 3410 steam generators.

Each steam generator contains 9350 0111 annealed inconel 600 tubes arrayed in a triangular pitch U bundle. Thest tubes are supported along their vertical lengths by seven full diameter egp: rate supports and three partial diameter eggerate supports (see Figure 1). The bend and horizontal lengths of the tubes are supported by diagonal I"batwing") straps, which cross the tubes just below the start of the bend, ant as many as seven vertical support straps, depending on the horizontal length of the tube (see Figure 2). The vertical straps are connected in the out-of-plane dimension by horizontal straps. A stay cylinder is installed at the central portion of the tubesheet to permit reduction of tubesheet thickness. The region above the stay cylinder cannot be tubed, and forms a hollov cavity at the center of the tube bundle.

Deeration and Insoection History Unit 2 completed three cycles of operation in September 1987. Unit 3 is scheduled to complete three cycles of operation in April 1988.

The first inservice inspection of a C-E Hodel 3410 steam generator was performed at San Onofre Unit 2. This inspection provided indications of tube j

wear at "batwing" intersections for several tubes adjacent to the stay

ylinder cavity in both steam generators. As documented in SCE's letter to NRC dated April 5,1985, appropriate tube plugging and tube staking was performed. Subsequently, at Unit 3. an opportunity for inspection of this same region occurred in the middle of the first cycle of operation. This inspection confirmed that similar tube wear was occurring at both Units 2 and 3.

The ongoing, conservative tube plugging in this wear region has helped ensure a complete lack of tube leakage due to this wear phenomenon.

Hodelino \

The San Onofre Unit 2 and 3 steam generators were modeled using two phase flow tests, fatigue tests, and vibration tests to predict the extent of tubes affected by the "batwing" vibration. Results of these tests were used to develop a computer model to predict the extent and rate of wear far affected tubes.

Modeling worked performed by C-E defined the problem to be wear, in a limited region of the tube bundle, resulting from out-of-plane vibration of the "batwing" supports. High velocity two phase flow up the untubed stay cylinder cavity imparts a force on t% "batwing" supports, resulting in out-of-plane motion of the "batwing" against the tube, causing tube wear. The modeling work predicted that the wear phenomenon would be restricted to a small number of tubes, adjacent to the stay cylinder cavity, and would be self-1 %iting due

to the angle of contact of the "batwing" on the tube and reduction of "batwing" vibration deeper within the tube bundle. The C-E results were used as an input to determinations of the extent of the plugging patterns utilized.

Similar "batwing" wear has been found during inservice inspection of other Model 3410 steam generators. Field results continue to support the laboratory modeling prediction that wear progression at "batwing" support / tubing intersections would affect a limited number of tubes contained within a well defined area in the steam generator.

The proposed change discussed above shall be deemed to involve a significant hazards consideration if there is a positive finding in any of the following areas:

1. Hill operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of any accident previously evaluated? -

Response: No The "batwing waar" area of the steam generator tube bundle is subjected to a 100 percent eddy current inspection every refueling outage and tubes identified as having been subjected to the wear mechanism are preventatively plugged in accordance with conservative criteria. Tubes outside the "batwing wear" area continue to be inspected in accordance with the current Technical Specification requirements. The net effect of the change is to provide for a more significant random sample b outside the "5atwing wear" area y increasing from 1.5% the toinitial sample 3% while base simultaneously precluding unnecessary expansion of the overall sample beyond 3%.

Therefore, operation of the facility in accordance with the proposed change does not affect the probability or consequences of an accident previously evaluated.

2. Hill operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident i from any accident previously evaluated?

Response: No The proposed change does not alter the configuration of the plant or its operation. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accicient previously evaluated.

3. Hill operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?

Response: No

I The margin of safety invc' d in steam generator tube inspection ,

depends on the accuracy a -ompleteness of the examination. The wear mechanism is well de! 1 and well within the capability of inspection techniques to eft a :.'ively monitor. Using the predictive models and analysis, the hrt a of "batwing wear" is identified and will continuously be inspected. The current Technical specification surveillance requirements will be applied elsewhere in the steam generator to ensure tube integrity is appropriately monitored.

Therefore, the proposed change does not reduce the effectiveness of the staam generator tube inservice inspection program nor does it l involve a reduction in a margin of safety.

Safety and Stanificant Hazards Determination Based on the above Safety Analysis, it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed ch≱ and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.

BRD:9207F

_ - - - f

! I MAIN STEAM LINE NOZ2LE %

DRYERS mmmmmm mmqn -

I.

SEPARATORS U TURE " i n us . f3 3 SHROUD- _

i r

, ,a .

, , FEEDWATER 3

g j' ,.

7 NOZZLE (1)

VERTICAL g 'l l

, (

SUPPORT GRIDS  % i  ;

l-

[ l i

( i 1

bummmmu a m

OlAGONAL . .

FEEDWATER SPACER STRIPS - \\"_ , -

DISTRIBUTION qj ,, a RING

l. '

f u

U-TU8ES - I'j' j -

l EGGCRATE SUPPORTS -

Jl /\ 'p L '

~

TURE SHEET -- d l #'

HOT LEG ,-

INLET 5l l COLD LEG NOZZLE (1)

OUTLET NOZZLE (2)

.: FIGURE

! 1 SDNGS2 STEAM GENERATOR ARRANGEMENT

ONyAL n .

R

%_,3._..J  % > ,

% g. i

/

(

ugger s

/

/,

T CAL" STg p BATlytyg

/

k

,j 9_k . _ . . . . . ..

00GCRAyg I l

/

4 u

/

GENER tog '*'*" roea so,,,,

9

-, , - - - - , . _ - , - ,,,,,,,-.---,,_----,,,.--,--c,

o NPr.10/IS-240 ATTACHMENT "A" EXISTING UNIT 2 TECHNICAL SPECIFICATION

l l

l I

REACTOR COOLANT SYSTEM '

SURVEILLANCE REQUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).

, 2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 4.4.4.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from ,

those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the j following three categories:

1 j Cateaory Inspection Results C-1 Less than 5% of the total tubes inspected are ,

degraded tubes and none of the inspected tubes  ;

are defective.  ;

C-2 One or more tubes, but not more than 1% of the  ;

total tubes inspected are defective, or between '

5% and 10% of the total tubes inspected 'are '

degraded tubes.

C-3 More than 10% of the total tubos inspected arv degraded tubes or more than 1% of the inspected '

tubes are defective.

i Note: In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations

],

to be included in the above percentage calculations. '

i  ;

f i

I i

i SAN ON0FRE-UNIT 2 3/4 4-10 ' '

l

, FEb 17 N32  !

- - , . - - , - -- ---, - - - , - - , - - - - - , y-----,- - , - - . , , - . , , - - - - - - - -

• v -

-w - n. - , ,-r

)

NPF-10/15-240 l

i ATTACHMENT "B" EXISTING CNIT 3 TECHNICAL SPECIFICATION I

i i

I l

i l

l l

REACTOR COOLANT SYSTEM SURVEILL/.NCE REQUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inshection (pursuant to Specification 4.4.4.4.a.8) shall be performed on each selected tube. If any selected tube does not pereit the passage of the eddy current probe for 6 tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array whera tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories:

Category Inspection Results ,

C-1 Less than 5% of the total tubes inspected are i degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but .not more than 1% of the total tubes inspected ara defective, or between 5% and ICE of the total tubes inspected are degraded tubes.

C-3 More than 10% of the tetal tubes inspected are  !

degraded tubes or more than 1% of the inspected .

tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit '

significant (greater than 10%) further well penetrations i to be included in the above percentage calculations, t

i l

SAN ONOFRE-UNIT 3 3/4 4-10 NOV 1 5 EC2

NPF-10/15-240 ATTACHHENT "C" PROPOSED UNIT 2 TECHNICAL SPECIFICATION i

I l

i i

REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 4.4.4.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection,

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found. ,

2. The inspections include those portions of the tubes where imperfections were previously found.

d. Tubes within the following region may be excluded from the first sample:

All nonplugged tubes contained within the bounds of column 70 through column 106 will be inspected nominally 14 to 16 rows in from the untubed region adjacent to the tube sheet stay cap.

All nonplugged tubes in columns 69 and 107 will be inspected from row 29 through 35. '

No credit shall be taken for these tubes, if all tubes within the region are inspected, in meeting the minimum sample size requirements.

The results of each sample inspection shall be classified into one of the following three categories:

Cateaorv InsDection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 11 of the total tubes 1 inspected are defective, or between 5% and 10% of the i total tubes inspected are degraded tubes. '

i SAN ONOFRE-UNIT 2 3/4 4-10

REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)

Cateaory Inspection Results C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective. t Notes: (1) In all inspections, previously degrLied tubes must exhibit significant (greater than 10%) furc ..t wall penetrations to be included in the above percentage calculations. -

(2) The results of the 4.4.5.2.d examinations will not be included in the above percentage calculations in cases involving "batwing" and vertical strap wear.

1 I

L i

i 1 l I

1 SAN ONOFRE-UNIT 2 3/4 4-10A l

NPF-10/15-240 ATTACHHENT "D" PROPOSED UNIT 3 TECHNICAL SPECIFICATION

~

A REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued)

1. All nonplugged tubes that previously had detectable wall penetrations (greater than 20%).

2. Tubes in those areas where experience has indicated potential problems.

3. A tube inspection (pursuant to Specification 4.4.4.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.

c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:

1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.

2. The inspections include those portions of the tubes where imperfections were previously found.

d. Tubes within the following region may be excluded from the first sample:

All nonplugged tubes contained within the bounds of column 70 through column 106 will be inspected nominally 14 to 1( rows in from the untubed region adjacent to the tube sheet stay cap.

All nonplugged tubes in columns 69 and 107 will be inspected from row 29 through 35.

No credit shall be taken for these tubes, if all tubes within the region are inspected, in meeting the minimum sample size requirements.

The results of each sample inspection shall be classified into one of the following three categories:

Category Insoection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the ,

total tube; inspected are degraded tubes, j SAN ONOFRE-UNIT 3 3/4 4-10 j

s t

i

• REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) -

Cittgary Insoection Results C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Notes: (1) In all inspections, previously degraded tubes must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.

(2) The results of the 4.4.5.2.d examinations will not be included in the above percentage calculations in cases involving "batwing" and vertical strap wear.

l 4

l 1

I SAN ONOFRE-UNIT 3 3/4 4-10A j

DESCRIPTION OF PROPOSED CHANGE NPF-10/15-242 AND SAFETY ANALYSIS This is a request to revise the Facility Operating License Section 2..B.(6) concerning possession of byproduct and special nuclear material, ,

Existina Section Unit 2: SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of the facility.

Unit 3: SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

Pronosed Saecifications Unit 2: SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of San Onofre Unit 1 and Unit 2.

Unit 3: SCE, pursuant to the Act and 10 CFR Parts 30, 40, and 70 to to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of San Onofre Unit I and Unit 3.

Descriotion The proposed change revises Facility Operating License Section 2.8.(6) concerning possession of byproduct and special nuclear material. Section 2.B.(6) may be interpreted to include authorization for Southern California Edison (SCE) to possess such byproducts and special nuclear materials (e.g.

spent fuel) at Unit 2 which are produced only at Unit 2. However the intent of the application for an operating license and NRC approval of the operating license application was to include storage of Unit I spent fuel at both Unit 2 and Unit 3. The intent to store Unit i spent fuel at Unit 2 and Unit 3 is clearly documented many times in the Final Safety Analysis Report Sections 9.1.2 and 9.1.3, was reviewed and approved by the NRC during the operating 1 license process, and the NRC review and approval was documented in the NRC

• Safety Evaluation Report, Sections 9.1.2 and 9.1.3, dated February, 1981.

Safety Analysis The proposed changes discussed above shall be deemed to involve a significant  !

hazards consideration if there is a positive finding in any one of the following areas:

_ _ - - , - + - - - -

i

1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change only corrects an editorial discrepancy in Facility Operating License Section 2.8.(6). There is no change in the probability or consequences of a potential accident which has been previously evaluated.

2. Hill operation of the facility in accordance with this proposed change I create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No

~

The proposed change corrects an editorial discrepancy in the Facility

Operating License, therefore it does not create the possibility of a new i or different kind of accident from any previously evaluated.

3. Hill operation of the facility in accordance with the proposed change

, involve a significant reduction in a margin of safety?

Response: No The proposed change corrects an editorial discrepancy and therefore does

] not affect any margin of safety.

l The Commission has provided guidance for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of j

amendments that are considered not likely to involve significant hazards

considerations. Example (1) relates to a purely administrative change; for j example, a change to achieve consistency in the Technical Specifications, i correction of an error, or a change in nomenclature. In this case, the proposed change corrects a possible oversight error to provide clarification i that a complete review and approval of the storage of Unit I spent fuel at

! Unit 2 and Unit 3 has been conducted. Because this proposed change corrects an editorial discrepancy, it is similar to Example (1).

1 i Safety and Sianificant Hazards Determination Based en the above Safety Analysis it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; and (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this i

action will not result in a condttion which significantly alters the impact of the station on the environment as described in the NRC Final Environmental

) Statement.

l 1

1 l

V

- , - - - . , , - - . . - - . - -