Text

Proposed Tech Specs,Consisting of Proposed Change PCN-238, Incorporating Changes Authorized by Generic Ltr 87-09 Re Elimination of Unnecessary Restrictions on Mode Changes
	ML20237F052
Person / Time
Site:	San Onofre
Issue date:	12/22/1987
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML13303A820	List: ML20237F052;
References
	GL-87-09, GL-87-9, NUDOCS 8712290327
	Download: ML20237F052 (135)
	v • d • e

{{#Wiki_filter:.... 3/4 ':v!~!No CONCITIONS 'CR Cp{ oat:CN AND $URVEI'.LAN0! O!OU 4!wgy 3 3/a.C ado'.!CA!!L!?Y L:u:~43 CON 0!??ON "CR OCERATION 3.0.1 Com:liance with the Limiting Conditions for Operation contained in the succeecing' specifications is reovired during sne OPERATIONAL M00!S or etner concisions specified therein; except that upon failure to meet the Limiting. C ncitions for Cperation, the associated ACT CN requirements shall be met. 3.0.2 Noncompliance with a specification shall exist when the requirements of tne Limiting Condition for Operation and/or associated ACTION requirements are not met witnin the specified time intervals. If tne Limiting Concition for 0: era-fon is restored prior to expiration of the specified time intervals, c mpletion of tne ACTION requirements is not required. 3.0.3 When a Limiting Concition for Operation is not met, except as provicec in tne associated ACTION requirements, within one hour, action'shall be initiates to place the unit in a MODE in which the specification does nets apply by placing it, as applicaole, in: 1. At least HOT STAN08Y within the next 6 hours. 2. At least HOT 5HUTDOWN within the following 6 hours and - 3. At least COLD SHUT 00WN within the suosequent 24 hours. Where carrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accorcance with the soecified time limits as messaroc from the time of failure to meet the Limiting Ccncition for C:eration. Exceptions to these requirements are stated in the incivicual ' specifications. This specification is not applicaole in MODE 5 or 6. 3.0.A Entry into an OPERATIONAL MODE 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 requirements. This provision shall not prevent passage through or to OPERATIONAL MODES as recuirac to comply with ACTION requirements. Exceptions to these requirements are stated in the individual Specifications. 8712290327 871222 PDR ADOCK 05000361 p PDR SAN ONOFRS-UNIT 2 3/40-1 '1PEB171981

l A88L::a!!L!*v 50tv!!'.'.a't:E REOUIRE*E"5 4.0.1 Surveillance Reevirements shall'te apolicable during the OPERATIONAL MODIS or otner conditions specified for individual Limiting Concitions for Operation unless otnerwise stated in an indivicual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval witn: A maximum allowable extension not to exceed 25% of the surveillance a. interval, and 2. The comeined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times tne specified surveillance interval. 4.0.3 ~ Failure to perform a Surveillance Requirement within'the specified time-interval sna11 constitute a failure to meet tne OPERA 8!LITY requirements for a Limiting Condition for Operation. Eyceptions to these requirements are. stated in the individual specifications. Surveillance Requirements de not have to be performed on inoperaole equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall net be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed witnin the stated surveillance interval or as otnerwise specified. 2.0.5 Surveillance Reevirements for inservice inspection and testing of ASME C:ce : lass 1, 2 and 3 camponents sna11 be applicaole as follows: Inservice inspection of ASME Code Class 1, 2 and 3 components and a. inservice testing ASME Code Class 1, 2 and 3 pumos and valves small ce performed in accordance with Section XI of the A5ME Soiler and Pressure Vessel Code and applicaele Addenda as recuired by 10 CFA 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)(1). b. Surveillance intervals specified in Section XI of the ASME Soller and Pressure Vessel Code and applicaele Addenda for the inservice inspection and testing activities required by the-A5ME toiler and Pressure Vessel Code and applicable Addenda sna11 to acclicaele as follows in tasse Tecnnical Specifications: SAN ONOFRE* UNIT 2 3/4 0-2 N AIN

i f 2 i ? 3 'a 3 NS~8LMENTA? N 3 3-

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.i L ..u.-.s2 .-.s-.--.y :.g. 47..y .i [ 3.3.1 As a minimum, ne rea:: r protective instrumentation enanneis anc sy: asses of Tacle 3.3-1.sna11 to CPERA3 E witn RE580NSE T*MES as sn:-n ir. Ta:1e 3.3-2. .h r A88L!C EIL:?v: As shown in Taele 3.3-1. [ 4 AC CN: i . i As snown in Table 3.3-1. t t SL'RVEILLANCE RECU!REw!NTS 1 4.3.1.1 Eaca reac ce protective instrumentation. channel shall ce cemenstsateci .[. C8ERABLE by tre performance of the CHANNEL Ch!CK, CHANNEL CALI5AAT:CN and 1-CHANNEL FUNCT:CNAL TE3T cperations for the MCOES anc'a the frequencies snc n in ia:1e 4.3-1. l. 4.3.1.2 The logic for tne cy: asses shall. be cemenstratec C8!RABLE ;-ice :: I en:n rea:::r startuo unless perf:rmed curing tne =re:ecing 92 days. :Tne :::a1 j. Oy: ass f;nction snall De cemenstrated OPERABLE at leas en:e :er 18 mentes' {;

-'r; CHANNEL CALIBRAT:CN testing cf en: channel affectec Oy y: ass

eratien.

4.3.1.3 Ine REACTCR TRIP SYSTEM RESPCNSE T:ME of esca react:r : 4: fun: i:n scall ce cemenstrated to be witnin its limit at least once car 18 men:ns. Ea:n tes: sna11 include at least one enannel per function ~suen tna: all~ cacarels are tested at least once every N times 18 mentns wnere N is One :::a1 l num:er of recuncant enannels in a specific rea::=r tri: fun::f on as sa:wn in

ne " Total No. of Channels" column of Taele 3.3-1.

4.3.1.4 The isolation enaracteristics of each CEA isolation amplifier and eacn optical isolator for CEA Calculater to Core Protection Calcula::P cata i transfer sna11 be verified at least once per 13 montas curing ne snut::wn per - tne following tests: For the CEA position isolation'amelifiers: a. t. Wdta 12C volts AC (!C H:) a::11ec f:P a; 'ess: 33 se:: :s. a:r:ss tre cut:u, tre res: n; :n ne in:. ::es n: ex:se: 0.015 vel;s 2C. SAN CNCFRE-UNIT 2 3/4 3-1 FEB i 71982: ~

l 7:!LE 3.3-1 (0 -tinued) 1 T !' ! NO 17.*CN i a With .e pr:tactive system tri: breakers in the clcsed ;:esitien, the CEA crive systam ca;:able of CEA withdra al, and fuel in the rea:::r vessel.

The pr:visicas of Specification 3.0.4 are not applicacle.

-4 (a) Trip may be manually bypassed above 10 % of RATED THERFAL PCWER; by:: ass shall be aut:matically removed when THERMAL PCWER is less than or qual to 10% of RATED THEUML POWER. (b) Trip may be manually bypassed belcw 400. psia; bypass shall be au::matically removed whenever pressurizer pressure is greater than c.- e:;al to 400 psia. (c) Trip may be manually bypassed below 10"#% of RATED THERMAL POWER: bypass shall be au;';matically removed when THERMAL POWER is greater than er. ecual to 10 % of RATED THERMAL POWER. During testing pursuant to Scecial Test Exception 3.10.3, trip.may be manually bypassed belew E% of R.-TED THEDML POWER; bypass shall be automatically removed when THERPAL P:WER is greater taan or eqdal to 5% of RATED THERMAL POWER. (c) Tri; may be bypassed during tes-ing pursuant ts Special Test-Ex:e;i-d en 3.10. 3. (e) See i;e:ial Test Exce:tien 3.10.2. (f) Ea:n :nannei shall be ccm::rised of two trip breakers; actual trip legi: sr:11 be cre-cut-f-two taken twice. (g) Trip may be bypassed belew EE% RATED THERMAL POWER. ACTION STATEMENTS I ACT*CN 1 Wita the number of channels OPERABLE ene less than recuired :y the Minimum Channels OPERABLE requirement, restore tne ) ir,c;:erable channel to CPERABLE' status within 18 hcurs er be in at least HOT STANDEY within the next 6 hours and/cr open *.ne ) protective system trip breakers. ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or PCWER OPERATICN may contin'.e -l pr:vided the inoperable channel is placed in the by;assee or tric::ed c:ndition within 1 hour. If the incperable enannei is by;&ssed, the desirability of maintaining this chancel i. tne bypassed ::ndition shall be reviewed in accordance with 5: pacification 6.E.1.5e. The ctannel snall be retur..ed :: OPERAELE status no later than curing tne next COLO IMUT:CbN. MM i 619% S-1 C:.;*EE.'N:7 2 3/4 3-4 A"ENCMENT S0. If \\'

ss :gu!N AT:3N 2/4 32 (NGNEERE3 SAFETv *EATUE A:TUA7!"N Sv5 Eu ! N 57 4"E s

a ? ! "N

.:": :N C:N*. : :04 con cog;;;;3n 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation c?.annels anc typasses shown in Taele'3.3-3 shall be OPERABLE witn their trio setpoints set consistent witn the values snown in the Trip 5etpoint column of Tasle 3.3-4 anc with RESPONSE TIMES as snown in Taele 3.3-5. a:8LICA!!L:TY: As shown in Table 3.3-3." A"7 ION: With an ESFAS instrumentation channel trip setpoint less conservative a. than the value snown in the AllowaDie Values column of Table 3.3-4, ceclare the cr.annel inoperable and apply the amplicaele ACTION requirement of Table 3.3-3 until the channel is restored to OPERASLE status with the trip setpoint adjusted consistent with the Trip Se point value. b. With an ESFA5 instrumentation channel inoperable, take the ACTION snown in Table 3.3-3. SURVEILLANCE REQUIREMENTS " 3.2.1 Each ISFAS instrumentation enannel snail be cem:nstrate: 08ER*!LE :y tre cerfrrmance of the CHANNEL CHECK, CHANNEL CALIBRATION and CNANNEL

UNCT "NAL TEST cperations for the MODES and at tne frequencies snown in Ta:1e 4.3-2.

4.3.2.2 The logic for the bypasses shall be demonstrated OPERABLE curing the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total typass function shall be demonstrated OPERABLE at least once per la months curing CHANNEL CALIBRATION testing of each channel affectec ey eypass operation. 4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each 15FAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one channel per function suen tnat all channels are tested at least once every N times 18 montes wnere N is the total nu :er of recuncant enannels in a spe:ific ESFA5 function as snown in the "Tctal No. of Cnannels" Column of Tamle 3.3-3. '5ee Special Test Exception 3.10.5 \\ SAN ONOFRE-UNIT 2 3/4 3-13 ((Jl}fgggg

s i \\ TABLE 3.3-3 (Continued) TABLE NOTATION (a) Trio function may be tysassee in this MODE when pressurizer pressure is - 1ess than 400 psia; bypass shall ba automatically removed when pressuri:er pressure is greater 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. t ACTION STATEMENTS ACTION 8 With the nunner of OPERA 8LE channels one less than the Total Nuecer of Channels, restore the inoperatie channel to OPERABLE status within 48 hours or be'in at least NOT STAN08Y within tne next 6 hours and in COLD SHUTDOWN within the following 34 hours. ACTION 9 - With the number of channels CPERA8LE one less than the Total ~ Nuncer of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperaale channel is placed in the bypassed or tripped condition within 1 hour. If the inoperaale channel is Dypassed, the destranility of maintaining this channel in the Dypassed condition shall be reviewed in accordance with Specification 6.5.1.6e. The channel shall be returned to CPERABLE status no later tnan during the _ next Cot.D SHUTDCWN. With a channel process measurement circuit that affects a multiple functional units inoperaale or in test, typass or. trip all associated functional units As listad below. Process Measurement Circuit Functional Unit Bypassed 1. Containment Pressure - High Containment' Pressure - High (ESF) Containment Pressure - Hign (RPS) 2. Steam Generator Pressure - Steam Generator Pressure'- Low Low Staan Generator AP 1 and 2 (EFAS) 3. Staas Generator Level Steam Generator Level - Low Steam Generator Level - Hign Staan Generator.17 (EFAS) i SAN CNCFRE-UNIT 2 3/4 3-19 Amendment No. 4- -*") U 90 t i ...-..............._...........--..,.sii i.==is. u s#

INSTRUMENTATION ) INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERA 8LE with: a. At least 75% of all incore detector locations, and b. A minimum of two quadrant 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 OPERABLE movanle incore detector capable of mapping the location. APPLICABILITY: 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 systes 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: By performance of a CHANNEL CHECK within 24 hours prior to its use if i< a. 7 or more days have elasped since the previous check and at least once per 7 days thereaf ter 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 ne'Jtron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core. SAN ONOFRE-UNIT 2 3/4 3-41 AMEN 0 MENT NO. I.9 s

ss suu!NTA7:0N si:su:: INS 4tu!N a*:09-L:v:~:NO ::N :~: N 8:R C2?RA*::N' 3.3.3.3 Tne seismic monitoring instrumentation shown in Taste.3.3-7 snali :e CPERABLE.

888'. CA!!L:?Y: At all times. ACTION: Wita one or more seismic monitoring instruments inoperasle for m:re a. inan 30 days, prepare and suosit a Scecial Resort to.tne.Commissic.- cursuant to Specification 6.9.2 witnin the next-10' days outlining: ne cause of tne malfunction anc 'tne plans' for. restoring tne instrument (s)Jto OPERABLE status, The provisions of Specifications 3.0.3 and 3.0.4 are not a: plica:Te. b. SURVEILLANCE REQUIREw!NT$ a.3.3.3.1 Each of the a: eve seismic m: nit: ring instruments shall 2e cemenstratec OPERABLE by sne cerforman:e of tre CHANNEL-CMECK.~ CHANNEL CAL *3RATICN and CHANNEL FUNCTIONAL EST =cera-ions at tne frequencies snown i-Ta:1e 4.3-4. a.3.3.3.2 ince of the above seismi: m: nit: ring instruments whicP. is a::ess :*e i

urin; =c.er c:eration and which is actuatec durirg a seismic event (:ne or more valic basemat accelerations of 0.0!g or greater) snall be rest: rec to CPERABLE status within 24 hours and a CHANNEL _ CALIBRATION perfor ad witnir 5 cays.

Cata shall be retrieved from the ac:sssible actuated instruments and analy:ed to determine the magnitude of the vibratory groune motion. A 5:ecial Report shall' be precared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days oescribing the magnitude, frequency s:ec rum and resultant effect uson facility features importan to safety. Each of tne a:ove 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 sna11 be restored to OPERABLE status and'a CHANNEL CALIBRATION performed the next time the plant enters HC05 3 P below. A sucolemental report shall then be recared and su:mitted t: .t e - C:mmissi:n witnin 10 days pursuant t: 5:ecif1:ati n 6.9.2 ces:ri:ing tne 'a::itiona' cata fr:s tasse ins ruments. \\ FEB 17 22 SAN ONCFRE-UNIT 2 3/4 3-42 ._.-.nn

I ss :.p'!s a ::N vi E:::'.:-*:al !NS :'.'"Ev a :09 l '.:u- :sc ::y::- ;N ::t c:gqar:eN 3.3.3.4 The meteorologdeal monitoring instrumentation channels shown in Taole 3.3-8 sna11 se OPERA!LI. A:8' ::A!!L: v: At all times. ACTION: a. Witn one or more recuirac meteorological monitoring enannels inoperasle for more than 7 cays, pre:are and sutmit a Special to:o-: to tne Commission pursuant to Specification 6.9.2 within the nex-10 cays outlining tne cause of the malfunction and the plans forc, restoring the channel (s) to OPERABLE status. The provisions of Specifications 3.0.3 and 3.0.4 are not applicamle., b. SL'tVE:L'.ANCE RE0'.'!REMENTS 4.3.3.4 !a:n of the above meteorology:a1 monitoring instrumentation enan els s all :e :emonstra ed OPERA!Li oy tne perfo-mance of tne CHANNEL CHEOK anc OHANNE'. CA'.~5 RAT *0N o;e a-f ens at tne frequencies snow-in Ta:1e 4.3-5. i i l ( SAN CNCFRE-UNIT 2 3/4 3-45 ({g g y ggg[

1 , INSTRUMENTATION RADI0ACT!YE LIQUID EFFLUENT MONITORING INSTRUMENTATION LINITING CON 0! TION FOR OPERATION 3.3.3.8 The radioactive liquid effluent eenitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alare/ trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANbAL (00CM). APPLICA8!LITY:- At all times." ACTION: With a radioactive liquid effluent monitoring indrementation a. channel alare/ trip setpoint less conservative than required by the above specification, lamediately suspend the release of radioactive liquid effluents sonitored by the affected channel or declare the-channel inoperable. t b. With less than the ainlaus number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrurent.to OPERABLE status within 30 days and, additionally, 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 6.9.1.13b are not appitcable. 4 SURVEILLANCE REQUIRO WITS i 4.3.3.8.1 Each radioactive liquid effluent monitort ' instrumentation channel shall be demonstrated OPERA 8tf by performance of the L CHECK, SOURCE CHECK, CHAlelEL CALIBRATION and CHAftlEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8. 4.3.3.8.2 At least once per 4 hours, all pumps required to be providing dilu-tion to meet the site radioactive effluent concentration limits of Spec' fica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure. "see special Test Exception 3.10.5. SAN ONOFRE-UNIT 2 3/4 3-63 AMEN 0 MENT NO. $7 -_-_Q-

~! INSTRUMENTATION RA0!0 ACTIVE GASEOUS _ EFFLUENT MONITORING INSTRUMENTATION t.IMITING CON 0! TION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPER/BLE with their alare/ trip setpoints set to I ensure that the limits.of Specification 3.11.2.1 are. net exceeded.. alarm / trip setpoints of these channels shall be determined in accordance with-The-the 00CM. AP8LICABIL' ITY: As shown in Table-3.3-138 ACTION: j With a radioactive gaseous effluent monitoring instrumentation a. channel alars/ 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 lesh than the minimum number of radioactive gaseous effluent i monitoring instrumentation channels OPERABLE.-take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to OPERABLE 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 ths -j inoperability was not corrected in a timely manner. j j i The provisions of Specifications c. applicable. 3.0.3, 3.0.4, and 6.9.1.13b'are not- .5 SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel sna11 be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURC CHECK, CHANNEL CALIBRATION.and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9. 1 i i "See 5pecial Test Exception 3.10.5 JAN 111985 i SAN ONOFRE-UNIT 2 3/4 3 64 AMENDMENT NO. 31

l INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The loose-part detection system shall be OPERA 8LE. APPLICA8ILITY: ~ MODES 1 and 2. ACTION: With one or more loose part detection system channels inoperable for a. more than 30 days, prepare and submit a Special Report to the Consission pursuant 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 OPERA 8LE status.- b. The provisions of Specifications 3.0.3 and 3.0.4 are not' applicable. SURVE.tLLANCE REQUIREMENTS 4.3.3.10 OPERA 8LE by performance of a:Each channel of the loose part detection sys CHANNEL CHECX at least once per 24 hours, a. b. CMANNEL FUNCTIONAL TEST at least once per 31 days, and CHANNEL CALIBRATION at least once per 18~ months. c. JANliSE SAN ONOFRE-UNIT 2 '3/4 3-75 AME!CSENT No. 31

] l REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE I 23E*F LIMITING CONDITION FOR OPERATION 3.4.8.3.1 At least one of the following overpressure protection systems shall ~ be OPERABLE: The Shutdown Cooling System Relief Valve (PSV9349) with: a. 1) A lift setting of 406 2 10 psig*, and-2) Relief Valve isolation valves 2NV9337, 2MV9339, 2HV9377 and 'I 2Mvf378 open, or, The Reactor Coolant System dooressurized with an RC5 vent of greater - D. than or equal to 5.6 square inenes. APPt.ICASILITY: MODE 4 when the teamerature of any one RCS cold leg is less [ snan or equal to 235'F; MODE 5; MODE 6 with the reactor vessel head on. ACTION: With the SDC5 Relief Valve inoperable, reduce T,,, to less than a. 200*F, depressurize and vent the RC5 through a greater than or equal to 5.6 square inch vent within the next 8 hours. With one or both 50C5 Relief Valve isolation valves in a single b. 50C5 Relief Valve isolation valve pair (valve pair 2HV9337 and 2MV9339 or valve pair 2HV9377 and 2MV9378) closed, open the closed valve (s) within 7 days or reduce T,,, to less than 20 W, decres- . surize and vent the RCS through a greater than or equal to 5.6 inch vent within the next 4 hours. In the event either the 50C5 Relief Valve or an RCS vent is used to ] c. eitigate an RC5 pressure transient, a Special Report sna11 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 transient, the effect of the SDC5 Relief Valve or RCS vent on the transient and any corrective action necessa, y to prevent r I recurrenca. d. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS I i 4.4.8.3.1.1 The SDCS Relief Valve shall be demonstrated OPERA 8LE by: i Verifying at least once per 72 hours when the 50C5 Relief valve is a. being used for overpressure protection snat 50C5 Relief Valve i isolation valves 2HV9337, 2MV9339, 2HV9377 and 2HY9378 are open. For valve temperatures less than or equal to 130*F. SAN ONOFRE-UNIT 2 3/4 4-32 Amendment No. 4 "'t A 6 E

I R! ACTOR C00!. ANT sys gu 3.4.9 5*RUCTURAL IN !"U::*v L:M:-*NG CON : TION FOR 08 ERAT 0N 3.4.9 ine structural integrity of ASHE Code Class 1, 2 and 3 components I sna11 be maintainec in accordance witn Specification 4.4.9. ] Adol!CAE!L:*Y: ALL MCDES AC*:0N: With the structural integrity of any ASME Code Class 1 component (s) a. not conforming to the aoove reavirements, restore the structural integrity of the affected cosconent(s) to within its limit or isciate the affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F above the minimum temperature required by NOT considerations. b. With the structural integrity of any ASMS Code Class 2 comoonent(s) not conforming to the above requirements, restore the structural-integrity of the affected component (s) to within its limit or-4 isolate the affected component (s) prior to increasing the Reactor ( Coolant System temperature amove 200'F. 1 With the structural integrity of any ASMS Code Class 3 component (s) c. not conforming to the above requirements, restore tne structural integrity of tne affectec coconent to within its limit er isolate the affected coconent from service, The provisions of Scarification 3.0.4 are not acclicaole. d. SURVEILLANCE REQUIREMENTS

4. 4. 9 In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspectec per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

k SAN ONOFRE-UNIT 2 3/4 4-34 FE81 7 W

s' ANT Sv$7 EMS 3/4.7.7 SEALED SOUR:t 00NT w:Na?!CN .L:w: :N3 00N0**!:N FOR 08 ERA 7?ON 3 3.7.7 !ach sealed source containing racicactive material either in excess of 100 microcuries of esta anc/or. gamma emitting material = or 5 microcuries of --I alona emitting material shall be free of greater than or equal to 0.005 microcuries of removaole contamination. ADSLICABILITY: At all times. ACTION: With a sealed source having removable contamination in excess of the a. teove limit, witneraw the sealed source from use and either: 1. Decontaminate and repair the sealed' source, or 2. Dispose of the sealed source in accorcance'with Commission Regulations. b. The provisions of Specifications-3.0.3 and 3.0.'4 are not applicable. ~ SURVEILLANCE REQUIREMENTS a.7.7.1 Test Requirements - Eacn sealed source shall be tested for leakage anc/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 startuo sources and fission detectors previously suojected to core flux) shall be tasted at the frequencies described below. a. Sources in use - At least once per six months for.all sealed sources containing radioactive material:. 1. With & half-life greater than 30 days (excluding Hydrogen 3), ane 2. In any form otner inan gas. \\. SAN ONCFRE-UNIT 2 3/a 7-24 . FES,17.1982

1

(. )

RE:UEL*NG 03ERATIONS o' s 3/4.9.9 CONTAINMENT URGE !!CLA* ION SYSTEM L:MI :NG~ CON I'."ICN FOR CPERATICN t 3.9.9 The containment purge isolation sy/cen shall be OPERA 8LE. Apo' !CABILITY: During CORE ALTERATIONS or movement of irradiated fuel within tne containment. 8 s ACTION: With the containment purge isolation system inoperable, close each of the containment purge pene; rations providing cirect access from the containment atmoschere to tne outside atmosphere.1 ' The, provisions of Specification 3.0.4 are not applicab?e. f SURVEILLANCE REQUIREMENTS 4.9.9 The containment purge isolation systes shall be demonstrated CPERA!LE within 72 hours prior to the start of and at least oned per 7 days during CORE ALTERATIONS by verifying that containment purge valve isolation occurs on manual initiation and on a high radiation test signal. t 1 h ss t A n v %.. r SAN CHOFRE-UNIT 2 3/4 9-10 FEB 17 W __.._____m._________._

EE:JELING :DE:A*:CNS 3 A.9.'.2 'LEL HANDL:NG BUILO!NG POST-ACC: CENT CLEANt;D :IL*ER 5<5~EW LIMITING CCNDITION FCR OPERATICN 3.9.12 7.o indecandent fuel handling building post accident cleanup filter systems shall be OPERABLE. APDLICAJILITY: Whenever irradiated fuel is in the storage pool. ACTION: With one fuel handling building post-accident cleanup filter system a. inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the-g OPERABLE fuel handling building post-accident cleanup filter rystem is capable of being powered from an OPERA 8LE emergency puwer source and is in operation and discharging through at least one train of HEPA filters and charcoal absorbers. With no fugl handling building post-accident cleanup filter system b. OPERABLE, suspend all operations involving movement of fuel'within the storage pool or operation of fuel handling machine over tne storage pool until at least one fuel handling building post-accident cleanup filter system is restored to OPERA 8LE status, The provisions of Specification 3.0.4 are not applicable. c. SURVEILLANCE REQUIREMENTS ~ l 4.9.12 The above required fuel handling building post-accident cleanuo filter systems shall be demonstrated OPERA 8LE: i At least once per 31 days on a STAGGERED TEST BASIS by initiating, a. from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours with the heaters on. At least once per 18 months or (1) after any structural maintenance b. on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the systso by: SEP 3 0 'iii SAN ONCFRE-UNIT 2 3/4 9-13 AMEN 0 MENT NO. 35

~ RAC;0 ACTIVE U#LUE$lTS CCSE LIM! !wG CONCI*!ON FOR OPERxTION 3.11.1.2 The dose or dose consitaent to an individual from radioactive-materials in liquid affluents released, from each reactor unit, from tne site (see Figure 5.1-4) sna11 be limited: During any calendar quarter to less than or equal to 1.5 ares to the a. total bocy and to less than or equal to 5 area to any organ, and b. During any calendar year to less than or saval to 3 area 13 the s total body anc to less the.n or equal to 10 nres to any organ. AP8LICA81LITY: At all times. ACTION: I With the calculated dose from the release of radioactive' materials - a. in liquid effluents exceeding any of the above limita in lieu of i any other report reovired by Specification 6.9.1, prep,are and suosit to the Cossaission 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 the releases anc the proposed actions to be taken to assure that subsequent releases will be in compliance with Specification 3.11.1.2 The provisions of spe-ifications 3.0.3, 3.d.4 and 6.9.1.13b are not b. applicable. SURVEILLANCE REQUIREMENTS i 4.11.1.2 pose Calculations. Cumulative dose contributions from liouid 31 days. affluents snM1 ne estarsined in accorcance with the CDCM at least once SAN ONOFRE-UNIT 2 3/4 11-5 FEB 1 7 582 ,, _ _ _ _ _ _ _ _ _ _ - - - - " - - - - - - - - - - - - ^ - ' ' ^

RADI0 ACTIVE EFrLUENTS LIOUID WASTE 78EATw!NT L:u:~:N3 CONDITION FOR OPERATION 3.11.1.3 The liquid radvasta treatment systes shall be OPERA 8LE. The-accropriate portions of tne system shall be used to reduce the radioactive materials in liquid wastes prior to their disenarge when the projected doses due to the liquid effluent from the site (see Figure 5.1-4) when averaged over 31 days, would exceed 0.06 mres to the total body or 0.2 ares to any organ." APPLICABILITY: At all times. ACTION: With the liquid radwaste treatment system inoperable for acre than a. 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. l Report which includes the following information: 1 1. Identification of the inoperable equipment or subsystems and the reason for inoperability, i 2. Action (s) taken to restore the incperable equipment to OPERABLE 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 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 restaste treatment systes shall be demonstrated OPERABLE by operating the liquid radweste treatment systes equipment for at least 1hainuts.s at least once per 92 days unless the liquid raowaste system has been utilized to process radioactive liquid affluents during ine previous 92 days. Per renctor unit t l FU $ ' : SAN ONOFRE-UNIT 2 3/4 u-6 FE817 rest

e. t 0 : 0.::T !*.'E E ::'. U E'!'_5 i.??L:: N! LOUP T:NM5 L:u: TING C"NSITION FOR 0?! EAT!09 3.11.1.4 The quantity of racicactive material contained in each outside tem;crary 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. ACT:CN: With the quantity of radioactive material in any outside temperary a. tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank c:ntents to within the limit. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REOU!EE.WENTS 4.11.1.4 The quantity of radioactive material contained in each outside temocrary tank sna11 be determined to be within the above_ limit by analyzing a representative sample of the tank's contents at least ence per 7 days wnen ra:1ca:tive matarials are being added to the tank. 1 9 ---__m es:,,.E:u g m u.7 -.~

~- ,,, j RA0!OACTIV! EFFLUEN 5 005[ - NOBLE CASES LIMI ING CONDI* ION FOR OPERATION 1 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 guarter: Less than or equal to 5 arad for gaw.a 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 ganna radiation and less than or squal to 20 arad for beta radiation. AP8LICA8ILITY: At all times. ACTIOM With the calculated air dose free radioactive noble gases in gaseous a. i effluents exceeding any of the aeove limits, in lieu of any other report required by Specification 6.S.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 (s) and defines the corrective ac*. ions taken to reduce releases and the pr::osec corrective actions to be taken to assure that sucsequent releases will be in compliance witn Specification 3.11.2.2. b. The provisions of Specifications 3.0.3 and 3.0. A are not applica:1s. SURVEILLANCE REQUIREMENTS 4.11.2.2 Deze Caleviations Cumulative dose contributions for the current calencar cuarter anc current calendar year shall be determined in accorcance with the CDCM at least once per 31 days. <a SAN ONOFRE-UNIT 2 ,3/4 11-12 FEB17 M2 - a

RADIOACTIVE EFFLUENTS DOSE - RA010100!NES. RADIOACTIVE MATERIALS IN PARTICULATE FORM AND LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from tritius, radiofodines 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 ores to any argan and, b. During any calendar year:.Less than or equal to 15 ares to any organ. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result c. of burning contaminated oil. APPLICABILITY: At all times. ACTION: With the calculated dose from the release of tritius, rodleiodines, a. and radioactive materials in particulate fom, with half lives - 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 3.11.2.3. b. The provisions of Specifications-3.0.3 and 3.0.4 are not applicable. SU'RVEILLANCE REQUIREMENTS 4.11.2.3 Qose 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. SAN ONOFRE-UNIT 2 3/4 11 AMEN 0 MENT No. 52

l RADI0 ACTIVE ErrLUENTS GASECUS RADWASTE TREAWENT LIM:*:NG CONCITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM'and the VENTILAT TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEQUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive natorial gaseous waste prior to their discharge when the projected gaseous effluent air cosas due to gaseous affluent releases from the-site (see Figure 5.1-3), when averaged over 31 days, would exceed 0.2 arad for gassa radiation and 0.a arac for beta radiation. The sopropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous wasta prior to their discharge when.the projected doses due to gaseous affluent releases from the site (see Figure 5.1-3) when averaged over 31 days would exceed 0.3 ares to any organ." APPLICABILITY: At.all times. y AC' ION: With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VEhT M a. EXHAUST TREATMENT SYSTEM inoperable for more than 31 days or 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 submit To the Commission within 30 days, pursuant to Specification E.9.2, a Special Report'which includes the following information: 1. Identification of the inoperable equipment or subsystems and the reason for inoperacility, 2. Action (s) taken to restore the inoperable equipment to OPERABLE 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 applicaole. SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site shall be projected at least onca per 31 days, in accordance with the 00CM. 4.11.2.a.2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EX TREATMENT SYSTEM shall be' demonstrated CPERA8LE by operating the GASE005 RADWASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM ecuiement for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process racicactive gaseous effluents curing the previous 92 cays. "These cosas are per reacto,r unit.- SAM ONOFRE-UNIT 2 3/4 11-14 FE817 tN2

RA :0ACTI'!! E::LL'EST5 E.:LCs:'t! G:5 P:X'U:t L:F!T n3 c N0! TION FCE OPERATICH 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to lessLthan or equal to 2% by volume whenever the hydrogen concentratica exceeds 4% by vcluse. APPLICABILITY: At all times. ACTION: With the concentration of oxygen in the waste gas holdup system ~ a. greater than 25 by volume out less than or equal to 45 by voluse,. restore the concentration of oxygen to within the limit within. 48 hours. b. With the concentration of oxygen in the weste gas holdLp system 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 Z% by volume within 48 hours. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas holdup system 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 OPERA 8LE by Table 3.3-13 of specification 3.3.3.9. i 1 Mff i 8 ton SAN CNOFF.E-UN*T 2 2/4 11-15 Avrwr#F4T N1 If

1 ) 41 i RADIOACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE i LIy! TING CONDITION FOR OPERATION 3.11.3 The solid radweste system shall be OPERA 8LE and used,'as applicable 'in 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. APPLICA81LITY: At all times." ACTION: With the packaging requirements of 10 CFR Part 20 and/or 10 CFR-a. Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes free the site. b.' With the solid radwesta systee inoperable for more than 31 days, in lieu of any other report required by Specification 6.9.1. prepare-and submit to the Commission within 30 days pursuant to 5pecifica-tion 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

status, 3.

A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes. and 4. Summary description of action (s) taken to prevent a recurrence. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. i SURVEILLANCE REQUIREMENTS ) 4.11.3.1 The solid radweste system shall be demonstrated OPERABLE at least once per 92 days by: Operating the solid radwaste systes at least once in the previous-a. 32 days in accordance with the PROCESS CONTROL PROGRAM, or b. Verification. of the existance of a valid contract for SOLIDIFICATION to be performed by a contractor in accorcance with a PROCESS CONTROL PROGRAM. "See Specification 6.13.1. y SAN ONOFRE-UNIT 2 3/4 11-17 p: "pa i 7 m2

h l RADIOACTIVE EFFLUEN'S 3/4. n.4 TOTAL 005E J t.!MI*:NG CONDITION FCR OPERATION' j 3.11.4 The dose or dose conmiitment to any member of the public, due to 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 arem) over 12 consecutive montds. ~. APPLICA8!LITY: At all times. ACTION: a. With the calculated doses from the release of radioactive materials-in liquid or gaseous affluents exceeding twice the limits of ' 5 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.a. or 3.11.2.3.b in lieu of any other report required by i Specification 6.9.1, prepa,re and submit a 5;mcial Report to the. Director, Nuclear Reactor Regulation, U.S. Nuclear Regulatory. Casuiission, Washington, D.C. 20555, within 30 days, which defines 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 fuel cycle sources (dose) to a seaber of the public from uranius -l (including all effluent pathways and direct radiation) for a 12 consecutive sonth period that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 3.11.4, and if the release condition resulting in violation of 40 CFR ISO has not already been corrected, 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 i 190.11(b). Submittal of the report is' considered a timely request, and a variance is granted until staff action on the request is completa. The variance only relates to the J limits of 40 CFR 190, and does not apply in any way to the require-ments for dose limitation of 10 CFR Part 20, as addressed in other J sections of this technical specification. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.4 Dese Calculations Cumulative dose contributions from liquid and gaseous af fluents saan ne determined in acecreance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the 00CM.' i 4 i SAN ONOFRE-UNIT 2 3/4 H-19 'I*'!" E s i 7 198 2 a

. -.. ~... - - - -. h 3/4.I2 RADIOLOGICAL ENVIRONMENTAL MONITORING ] a 3/4.12.1 MONITORING 8ROGRAM t.IMITING CONDIT!0N FOR Op! RATION 'l 3.12.1. The radiological environmental sonitoring program shall be conducted i as specified in Table 3.12-1. l APPLICA8ILITY: At all times. o ACTION: j With the. radiological'e' environmental monitoring program not being i a. conducted as specified in Table 3.12-1, in lieu of any other report-required by Specification 6.9.1, prepare and submit to the Coa-ainsion, in the Annual Radiological Operating Report, a description H 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 is any calendar quarter, in' lieu of any other report required by' Specification 6.9.1, prepare and submit to the Commission 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. tho' sampling medium, this report shall be submitted if:

i 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 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 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. With fresh leafy vegetable samples or fleshy vegetable samples unavail-c. able from 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 by Table 3.12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations, d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. j i SAN ON0FR!-UNIT 2 3/4 12-1 2 EU.'.,.. RB 1719U - 1 1

1 l

7. G OLO3ICAL ENVI:.ON" ENTAL MONI'CRING i

I'.12.2 LAND USE CENSUS LiviTIN3 CONOITICN FOR OPERATION

i

'i 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 nearest garden" of ~ greater than 500 square f eet producing fresh leafy vegetatles in each of the 15 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 also identify the locations of all ailk 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. APPLICABILITY: At all times. ACTION: With a land use census identifying a location (s) which yields a a. calculated dose or dose coenitment greatse 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 Commission 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 coraitment 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 or dose commitment via the same exposure pathway may be deleted from this monitoring program after October 31 of the year in which tnis land use census was conducted. i The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. SURVEILLANCE REQUIRE"ENTS l 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 results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census. g i 61983 SAN C:C.RE-UNIT 2 3/4 l2-11,.- Ay,t:;o:c;.40.16

/ RA0*.0LCO:: t ENV:R0'"E' TAL PON! 04?N3 / 3/4.12.3 INT!?tA!:tATCRy. C:.'9:::!CN ; Gt:M LIM [TINGCONDITIONFOROPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied'as part-of an Interlateratory Comparison Program which has been approved by the Commission. APPLICABILITY: At all times. ACTION: With analyses not being performed as required above, report the - a. corrective actions taken~ to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. D. SURVEILLANCE REQUIREMENTS As$mmaryoftheresultsobtainedaspartoftheaboverequired 4.12.3 Interlateratory Ccmparison Program and in.acesrdance with the CDCM shall te includec in the Annual Radiological Environmental Operating Aaport. MRY161983 SAN CNCFEE-UNIT 2 3/4.12-12 AME*::::E::T *:0,16

3/a. 0. APPLICABILI"Y, BA5!$ 1 'i The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveillance D Requirements within Section 3/4. 3.0.1 This specification defines the applicability of each specification - in terms of defined OPERATIONAL-MODES or other specified conditions and is i) provided to oelineate specifically wnen each specification is applicable. .1 3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual-Limiting Condition'for Operation and associated ACTION. requirement. 3.0.3 This specification delineates the seasures to be taken'for circumstances not directly provided for in the ACTION statements and whose - occurrence would violata the intent cf a specification. For example, Specification 3.6.2.1 requires two Containment spray systems to be OPERABLE' and provides explicit ACTION requirements if one spray system is inoperaale. Under the tems of Specification 3.0.3, if both of the required Containment Sorey Systems are inoperable, within one hour measures must be. initiated to place the unit in at least NOT STANOSY within the next 6 hours, in at least HOT SHUTDOWN within the following 6 hours,land in COLD $HUTDOWN.in the suesequent 24 hours. 4 3.0.4 This specification provides that entry intd an OPERATIONAL MODE or other specified applicatflity condition must be made with-(a) the full com-pienent of required systems, equipment or componenta OPEAA8LE and (b) all-other parameters as specified in tne Limiting Conditions for Operation being met witnout regard for allowable deviations and out of' service provisions contained in the ACTION statements. The intent of this provision is to insure that facility operation is'not initiated with either required equipment or systems'inoperaale or other specified limits being exceeded. j Exceptions to this specification have been provided for a limited 'numeer of specifications when startup with inoperable' equipment would not ' affect plant safety. These exceptions are stated in the ACTION statements'of the* appropriate specifications. 'I s sad DNOFRE-UNIT 2 8 3/4 0-1 FE:: " ;r FEB 171982

BASES 'This specification ensures 'that the surveillance activities 4.0.4 I associated with a Limiting Condition for Operation have been performed within - tne specified time interval prior to entry into an OPERATIONAL MODE or otner applicable condition. The intent of this prevision is to ansure that surveil-lance activities have been satisfactorily demonstrated on a current basis as reevired to meet the OPERABILITY requirements of the Limiting Candition for Operation. Under the terms of this specification, for example, during initial plant startup or following extended plant outages, the applicable surveillance activities sust be performed within the stated surveillance interval prior to '4 placing or returning the system or equipment inte OP.ERABLE statua. 4.0.5 This specification er.sures 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 will be perfomed in accordance with a periodically updated version of Section XI of the ASME leiler and Pressure vessel Code and Addenda as required by 10 CFR 50.55a. Relief from any of the ancve reevirements has' been provided in writing by the Commission 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 applicable Addenca. 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 tems of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Seiler and Pressure Vessel Ccde and applicable Addenda. For example, the requirements of Specification 4.0.4 tu perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME leiler and Pressure vessel Code provision wnich allows pueos to be tested up to one week after return to normal operation. And for example, the Technical Specification definition of OPERA 8LE does not ciant a grace period before a device that is not casable of performing its specified function *is declared inaperable and takes precedence over the ASME Boiler and Pressure Vessel Code prevision wnich allows a valve to be incapable of performing its spectfied function for up to 24 hours before being declared inoperable. 1 SAM ONCFRE-UNIT 2 8 3/4 0-3 1 .,,n. FEB 17 IM.2 ~s . l; ,t

NPF-10/15-238 i i 1 l ATTACHMENT "B" i i 4 e a

e- ~ 5 d'"M ~ ( ~3/4 LINI. TING CONDITIONS FOR UpERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY LIMITING:COMOITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL N00E5 or other Conditions for Operation, the associated ACTION requireme 3.0.1 Noncomp1.iance with a specification.sball 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 intervals, completion off the ACTION requirements is not required. 3.0.3 . in,the associated. ACTION requirements, within one hour;' ac 1 .i initiated to place the unit in a MODE in which the specificattes does not-. apply by placing it, as applicable, in: y- ., ~.. : % 4..e,.' ..v 1. At least NOT STAN08Y within the next 8 hours, At least HDT SHUTDOWN within the following 6 hours;' and - .2.* w. *4 3.~ ( At least COLD SHUTDOWN within the subsequent 24 hours. /- Where corrective seasures are completed that permit operaties unser the ACTION requirements, the ACTICM may be taken in accordance with the specified tier limits as osasured from the time of failure to meet the Limiting Condition: for Operation., Exceptions to these requirements are stated in the <ndividual specifications. This specification is not applicable in MODE 5 or 6. 3.0.4 Entry into an OPERATIONAL M00E 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 requireatnts. This provision shall not prevent passage through or to OPERATIONAL M00E5 as required to comply with ACTION requirements. Exce stated in the individual Specifications. ptions to these requirements are e / NOV 15 E2 SAN ONOFRE-UNIT 3 3/4 0-1

y_ s-.~. .y I APPLICA81LITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance-Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting conditions for , Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 ' Each surveillance Requirement shall be performed within the f5cified time interval with: ~ A anximum allowable extension not to exceed 25% of the surva.falanc a. interval, and b. The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval. . M...o. p . c'F 4.0.3 Failure to perform a Surveillance Requirement within~the specified ime. interval shall constitute a failure to esat the OptRABILITV' requirements Limiting Condition for Operation.. Exceptions to these requirements are s a in the individual specifications. " Surveillance Requirements de not have, he performed on inoperable equipment. 'J. ~ T 4.0.4 Entry into an OPERATIONAL MDOE or other specified condition shall not be made unless the surveillance Requirement (s) associated with the Limiting 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 Code Class 1, 2 and 3 components shall be applicable as follows: Inservice inspection of ASME' Code Class 1, 2 and 3 components and a. inservice testing A$fE Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section.50.55a(g)..ancept where specific written relief has been i granted by the Ceam~iasion pursuant to 10 CFR 50, Section 50.55a(g) (6)(i). 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: l SAN ONOFRE-UNIT 3 3/4 0-2 l I

s i e 3/4.3 INSTRUMENTATION -I q c 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 4 3.3.1 As a minimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2. APPLICABILITY: Asshownin, Tele 3.3-1. 4 ACTION: As shown in Table 3.3-1. .t SURVEILLANCE REQUIREMENTS ~ ~

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4 t

4.3.1.1 Fach react 4r protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANIIEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1. k 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 OPERABLE at least once per 18 months duringCHANNELCALIBRATIONtestingofeachchannelaffected;bybypass operation. 4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function ~ 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 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 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, l FortheC'Fhpositionisolationamplifiers: f a. ~ 1. Witfr-120 volts AC (60 Hz) applied for at least 30 seconds ~ across the output, the reading on the input does not exceed O.015 volts DC. .1'l / ~ NOV 151982 SAN ON0FRE-UNIT 3 3/4 3-1

I ~ e j TABLE 3.3 (Continued) TABLE NOTATION 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 (a) Trip any be manually bypassed above 10'41 of RATED THERMAL POWER; bypass j shall.,he automatically. removed when THERMAL POWER is less than or equal 1 to 10 1 of RATED THERMAL POWER. (b) Trip say be manually bypassed below 400 psia; bypass shall be-4 automatically removed whenever pressurizer. pressure is greater than or equal to 400 psia. EI 1i ~4 'of RATED THERMAL POWER; bypass (c) Trip may be manually bypassed below 10 5 shall 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 any be manually bypassed below 5 -r RATED THERMAL POWER; bypass shall be automatically removed when THERMAL 1..e POWER is greater than or equal.to 55.of RATED THERMAL POWER. (d) Trip may be bypassed during testing' pursuant to special Test Exception 3.10.3._ (e) See Special Test Exception 3.10.2. t (f) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out of-two taken twice. ~ (g) Trip may be bypas' sed below 555 RATED THERMAL POWER. ~ ~

..s.

s ACTION STATEMENTS.: ACTION 1 With the number 'of channels OPERA 8LE'one less than required by - the Minimum Channels OPERA 8LE requirement, restore the - inoperable channel to 0PERABLE status within 48 hours or be in ',at least NOT STAND 8Y within the next 6 hours and/or open the djM[".pmtective systas trip bmakers. ;,.. ACTION 2" With the nueber of channels OPERA 8LE '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 1 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 ' ~ OPERAELE status no later than during the next COLD SHUTDOWN. / ./ (. ~ NOV 151362 SAN ONOFRE-UNIT 3

3/4 3-4 I

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i 1 1 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUMENTAT LINITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERA 8tE with their trip

)

setpoints set consistent with the values shown in the Trip 5etpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.* APPLICA8ILITY: As shown in Table 3.3-3. ACTION: With an ESFA5 instrumentation channel trip setpoint less conservative a. than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inopera61e and apply the applicable ACTION + requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the tri Setpoint value.J./ p setpoint adjusted consistent with the Trip. b. With an E5FAS instrumentation channel inoperable' take'the ACTION shown in Table 3.3-3. SURVEILLANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2. r.;.3 The logic for'the bypes'ses shall be demonstrated OPER BLE during th ~ 4.3.2.2 at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total' bypass function ~ shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION, testing of each channel,affected by i bypass operation. l 4 4.3.2.3 The ENGINEERED SAFETY FEATURES RE5p0NSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18'aonths. 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 I number of redundant channels in a specific ESFAs function as shown in the " Total No. of Channels" Column of Table 3.3-3. i l " Continuous sonttoring 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 refueling i outage.- Containment airtorpe monitor 3RT-7804-1 or 3RT-7807-2 and associates sampling media shall perfors these functions prior to initial criticality. From initial criticality to.the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sasgillag media shall perfore the above required functione. EV 15 Ist2. Se '"0FRE-UNIT 3 3/4 3 13 5

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TA8LE 3.3-3 (Continued) TABLE NOTATION i (a) Trip function may be bypassed in this M00E when pressurizer pressure is less than 400 psia; bypass shall be automatically removed when pressurizer-i pressure is greater than or equal to 400 psia. (b) An SIAS signal is first necessary to enable CSAS. fog'c. i (c) Actuated equipment only; does not result in CIAS.' i e f The provisions of Specification 3.0.3 are. not apphicable. ~ The previsions of Specification 3.0.4 are not applicable. With irradiated fuel in the storage pool. f ACTION STATEENTS ACTION 8 With the numbef of OPERA 8LE channels one less than the Total Number of Channels, restore the inoperable channel to CPERA8tf status within 48 hours or be in at least NOT STAfSSY within the next 6 hours and in COLD SHUTDOlst within the fe11 swing 30 hours. f 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 jnoperable channel is placed in the bypassed or tripped condition within 1 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 CPERABLE status no later.than during the next COLD SHUTDOWN. 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. 9,. Process Mea'urement Circuit Functional Unit 8ypassed s 1. Containment Pressure - High Containment Pressure - High (ESF) I Containment Pressure - High (RPS) 2. Staan Generator Pressure - Steam Generator Pressure - Low Low steam Generator AP 1 and 2 (EFAS) 3. Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator AP (EFAS) l 4$M SAN ONOFRE-UNIT 3 3/4 3-19

l i l INSTRUMENTATION INCORE DETECTOR $ j LINITING CONDITION FOR OPERATION - 1 3.3.3.2 The incore detection system shall be OPERABLE with: At least 755 of all incore detector locations, a$d a. A minimum of two quadrant synestric incore _ detector locations per b. core quadrant. An 0PERABLE incore detector location shall consist of a fuel assembly'~ containing a fixed detector string with a minimum of four OPERABLE rhodium detectors or an OPERABLE movable <ncore detector capable of mapping the location. ,1 APPLICABILITY: When the intore detection system is used for monitoring: a. AZImlTHAL POWER TILT, b. Radial Peaking Factors, c. Local Power Density, d. DNS 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 and 3.0.4 are not applicable. SURVEILLANCE REQUIRBEltf5 t 4.3.3.2 The incore detection system shall be demonstrated CPERABLE: By performance of a CHANNEL CHECK within 24 hours prior to its use if a. 7 or more days have elapsed 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 DNS margin: b. At least once per 3 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. J SAN ONOFRE - UNIT 3 3/4 3-41 AMENO W IT NO. 38 i

INSTRUMENTATION SEI5NIC INSTRUMENTATION

LINITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERA 8LE.

APPLICA8ILITY: -At all times. q ACTI R ~ y With one or more satseic monitoring instruments inoperable for more a. 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 3 the cause of the malfunction and the plans for restoring the instrument (s) to 0PERABLE status.. gg' j b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.t .) J '\\ SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments'shall be - demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations 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 0PERABLE status within 24 hours and a CHAlelEL UiIBRATION performed within ~ i 5 days.- Data shall be retrieved from the accessible actuated instruments and analyzed to determine the magnitude of the vibratory around action. A Special ( Report shall be prepared and submitted to the Commission pursuant to-Specification 4.9.2 within 10 days describing the magnitude, frequency spectrum 'and resultant effect upon facility features taportant 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 0PERA8LE status and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below.. A, supphoentabreper.t shall then be prepared and submittad to the Commission within 10 days pursuant to Specification 6.9.2 describing the additional data tros these instruments. 4 " Shared system with San Onofre - Unit 2. SAN ON0FRE-UNIT 3 3/4 3-42 g$ 1I t

.) 1 } INSTRUMENTATION t METEOR 0 LOGICAL INSTRUMENTATION" ( LINITING CONDITION FOR OPERATION 3.3.3.4 The seteorolo ical sonitoring instrumentation channels shown in Table 3.3-8 shall be 0 ERABLE. APPLICA81LITY: 1tt all' times. ACTION: '~ With one or more required meteorological sonitoring channels a. inoperable for more than 7 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 channel (s) to 0PERABLE status. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5. m ; ' y5, a i -;.~$. % .J 4 " Shared system with San Onofre - Unit 2. gy ib SAN ON0FRE-UNIT 3 3/4 3-45

~~ ~~ ~ INSTRUMENTATION RA0!0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shoun in Tele 3.3-12 shall be OPERA 8LE with their alare/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. Ths alam/ trip setpoints of these channels shall be determined in accordance with the OFF5ITE 00$E CALCULATION MANUAL (00CN). APPLICABILITY: At all times. ACTION: With a radioactive liquid effluent monitoring instrumentation a. channel alare/ trip setpoint less conservative than required by the above specification, immeeistely suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. 3 b. With less than the einfaue nuder of radioactive liquid effluent. monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Emert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) reesta inoperable for greater than 30 days, explain in the next Samiannual Radioactive Effluent Release Report uhy 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 applicable. SURVEILLANCE REQUI _D8MBff5 4.3.3.8.1 Each radioactive 11guld effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CNANNEL CHECK, SOURCE CHECK, CNAfgEL CALIBRATION and CNAfstEL FUNCTIONAL TEST operatior.s at the frequencies shown in Table 4.3-8. 4.3.3.8.2 At least once per 4 hours, all pumps required to be providing dilu-tion to aset the site radioactive effluent concentration limits of Specifica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure. SAN ONOPRE - UNIT 3 3/4 3-64 AfSRDWif NO. 46 ~

INSTRUMENTATION RADI0 ACTIVE GASE0US EFFLUENT NONITORING INSTRUMENTATION LINITING ColeITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels thown 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 alare/ trip setpoints of these channels shall be determined in accordance with the 00CM." APPLICABILITY: As shown in Table 3.3-13 ACTION: With a radioactive gaseous affluent monitoring instrumentation a. channel alara/ trip setpoint less conservative thkn 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 minimum number of radioactive gaseous affluent monitoring instrumentation channels 0PERA8LE, take the ACTION shown in Table 3.3-13. Exert best efforts to return the instrument to OPERA 8LE status within 30 days and, additionally, if the inoperable instrument (s) remain 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. { The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not c. applicable. SURVEILLANCE REQUIREMENTS ~ I.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPEAABLE by performance of the CHANNEL CHECKSOURCE CHECK, CHANNEL CALI8 RATION and CHANNEL FUNCTIONAL TEST operations a,t 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 voltee (8-inch and 42-inch) containment purge prior to startup following the first refueling outage.

Containment airborne monitor 3RT-7804-1 or 3RT-7807-2 and associat t sampling media shall perform these functions prior to initial criticality. From 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. JAN 11 G85 SAN ON0FRE-UNIT 3 3/4 3-69 AMENDMENT NO. 20

' INSTRUMENTATION \\ LOOSE-PART DETECTION INSTRUMENTATION 3 LIMITING CON 0! TION FOR OPERATION j d 3.3.3.10 The loose part detection system shall be OPERABLE. APPLICABILITY:, N00E5 1 and 2. ACTION: W1G one or more loose part detaytion system channels inoperable for a. more than 30 days, prepare and rubmit a Special Report to the Comeission pursuant to specification 6.9.2 within the next 10 days l outlining the cause of the selfunction and the plans for restoring the channel (s) to 0PERABLE status. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. N SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the loose part detection system shall be demonstrated OPERA 8LE by performance of a: I CHANNEL CHECK at least once per'24 hours, a. b. C E NNEL FUNCTIONAL TEST at least once per 31 days, and CHANNEL CALIBRATION at least once per 18 months. c. JAN 111985 SAN ON0FRE-UNIT 3 3/4 3-76 AfGOENT NO. 20 A

H 3 REACTOR COOLANT SYSTEM 'i 0VERPRE550RE PROTECTION SYSTEMS .I RCS TEMPERATURE I 285*F LIMITING CONDITION FOR OPERATION 3.4.8.3.1 At least one of the following overpressure protpction systems shall be OPERA 8LE: The shutdown Cooling system Relief Valve (PSV9349) with: s. 1) A lift setting of 40G

10 psig*, and -

2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or, b. The Reactor Coolant System depressurized with an RC5 vent of ' greater than or equal to 5.5 square inches. APPLICA81LITY: 5 ISOE 4 when the temperature of any one RCS cold leg is.less g than or equal to 285*F; IWOE 5; MODE 6 with the reactor vessel head on. s ACTION: With the 50C5 Relief Valve inoperable, reduce T,,, to less than a. 200*F, depressurize and vent the RCS through a greater than or equal to 5.8 square inch vent within the next 8 hours. b. With one or both SOCS Relief Valve isolation valves in a single SOC 5. Relief Valve isolation valve pair (valve pair 3HV9337 and 3HV9339'or valve pair 3HV9377 and 3HY9378) cTosed, open the closed. valve (s) within 7 days or reduce T to less than 200*F, depres-surite and vent the RC5 throu vent within the next 8 hours.gh a $Ister than or equal to 5.5 inch In the event either the 50C5 Relief Valve or an RCS vent is used to c. mitigate an~RCS-pressure transient, a Special Report shall be prepared and submitted to the Casmission 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 en the transient'and asqr corrective action necessary to prevent. recurrence. d. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS il 4.4.8.3.1.1 The SOCS Relief Valve shall be demonstrated OPERA 8LE by: Verifying at least once per 72 hours when the 50C5 Relief Valva i.s a. being used for overpressure protection that SOCS Relief Valve isolation valves 3NY9337, 3Hv9339, 3HV9377, and 3HV9378 are open. / '\\ - "The lift setting. pressure applicable to valve tosperatures of less than or equal ta uC*r.. SAN ONOFRE-UNIT 3 3/4 4 N1 i

.:.y g REACTOR CODUM SYSTEM 3.4.9 ainvG dRAL 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. APPLICA8ILITY. ALL 2 0E5 $El@ i With the structural integrity of any ASM Code Class'1 component (s) e. not conforming to the above requirements, restore the structural-integrity of the affected component (s) to within its limit er 1solate the affected camponent(s) prior to increasing the Reactor i Coelant System temperature more than 50*F above the minim a j temperature required by 2 7 considerations. et, b. With the structural integrity of any ASE Code Class 2 combonent( i not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its'11mit er isolate the~affected component (s) prior to increasing the Reactor Coolant System temperature above 200*F. With the structural integrity of any ASME Code Clasr 3 component (s) c. not conforming to the above requirements, restore the structural integrity of the affected component to within its limit or isolate the affected component from service. d. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCEREQUIRDWks l 4.4.9 Is' addition to the requirements of Specification 4.0.5, each Reactor Coolant Puum flywheel shall be inspected per the recommendations of Regulatory Positten C.4.b of Regulatory Guide 1.14. Revision 1 August 1975. / h g e ns 5An OmrRE-uwIT 3/4 4 3. g5 D

PLANT SYSTEMS 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.7 Each sealed source containing radioactive material Pither in excess of 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. APPt framit TTY. At all times.- ~ ACTION: With a sealed source having removable contamination in excess of the a. above limit, withdrew the sealed source free use and either: 1. Decontaminate and repair the sealed source, er I. 2. Otsposeofthesealedsourceins.:cordancewithCandission= Regulations. b. The provisions of Specifications.3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS a Test Requirene ks - Each sealed source shall be tested for leakage 4.7.7.1 and/or contamination by: a. The licensee, or b. Other persons specifically authorized by the Commission or an-i Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample, t 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. Sources in use - At least once per six months for all sealed-sources a. containing radioactive material: 1. With a half-life greater than 30 days (excluding Mydrogen 3), and 2. In any form other than gas. f NOV 151982 o SAN ONOF85-UNIT 3 3/4 7-25

REFUELING OPERATIONS 3/4.9.9 CONTAI M PURGE ISCLATION SYSTEN LINITING CON 0! TION FOR OPERATION 1 \\ 3.9.9 The containment purge isolation system shall be OPEAABLE. - I APPLICA81LITY: During CORE ALTERATIONS or movement of irradiated fuel'within the conta1nment. h 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' SURVEILLANCE REQUIREMENTS ..c% 4.5.9 The containment purge isolation system shall be demonstrated OPERA 8LE within 72 hours prior to the start of,and at-least once per 7 days during CORE ALTERATIONS by verifpigthist containment purge valve isolation occurs on manual initiation and on a high radiation test signal. 4 1 9 i / ' l I NOV i 51982 SAN ONOFRE-UNIT 3 3/4 9-10

L i i 1 REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CONDITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accident cleanup filter systems shall be OPERA 8LE. APPLICA81LITY: Whenever irradiated fuel is in the storage pool. ACTION: 1 With one fuel handling building post-accident cleanup filter system. a. Il inoperable, fuel movement within the storage pool or operation of fuel handling nachine over the storage pool any proceed provided the OPERA 8LE fuel handling building post-accident cleanup filter system is capable of being powered from an OPERABLE 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 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 OPERA 8LE status. The provisions of Specification 3.0.4 are not applicable. c. SURVEILLANCE REQUIREMENTS <t 4.9.12 The above required fuel handling butiding post-accident cleanup filter systems shall be demonstrated OPERABLE: a w;u a At least onie~per 31" days on a STAGGERED TEST BASIS by initiating, a. from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the systee operates for at least 10 hours j with th heanes 'on. ~ l b. At least once per 18 months or (1) after any structurst 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: i i f SEP 3 01985 SAN oNOFRE - UNIT 3 3/4 9-13 AMENDMENT NO. 25

1 i I RA010 ACTIVE' EFFLUENTS M!i LIMITING CON 0! TION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid affluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited: o 1 During any calendar quarter to less.than er equal to 1.5 ares to the a. , total body and tg. l.ess than or equal to 5 meen to any organ, and 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. i APPLICA8!LITY: At all times. ACTION: t { .i 't \\ With the calculated dose from the release of radioactive materf ah a. in liquid affluents exceeding any of the above Ifaits, in Iteu of* i { 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 I Special Report which identifies the cause(s) for exceeding the limit (s) and. defines the corrective actions taken to reduce the releases and the proposed actions to be taken to assure that subsequent releases l i will be in compliance with specification 3.11.1.2 b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicania. { SURVEILLANCE REQUIRDENT5 4.11.1.2 Dose Calculattens. Cumulative dose contributions from liquid effluents shall be determined in accordance with the 00CN at least once per 31 days. l i / 1;0V 15 UK i e enum SAN ON0FRE-UNIT 3 3/4 11-5

4 RA0!OACTIVE EFFLUENTS }.IQUIDWASTETREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwasta treatment system shall be OPERA 8LE. The appropriate portions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when'the projected doses e due to the Ifquid effluent from the site (see Figure 5.1-4) when averaged over 31 days, would exceed 0.06 ares to the totaT body or 0.2 ares to any organ." APPLICABILITY: At all times. ACTION: With the liquid radweste treatment systas inoperable for more than a. 31 days or with radioactive liquid weste beinti discharged without treatment and in excess of the above limits, 'n lieu of any other, report required by Specification 5.9.), prepare and submit to ther 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, ) j 2. Action (s) taken to restore the inoperable equipment to' OPERABLE 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 AEOUIREMENTS 4.11.1.3.1 31 days, in accordance with the ODCM. Doses due to liquid releases shall 4.11.1.3.2 The liquid radwasta treatment system shall be demonstrated OPERABLE by operating the liquid radweste treatment system equipment for at least 15 minutes at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid affluents during the previous 'i 92 days. g Perreactorujitt HOV 151982 SAM ONOFRE-UNIT 3 3/4 11-6

( RADI0 ACTIVE EFFLUENTS 1 LIQUID MOLDIF TANK 3 f LIMITING CONDITION FOR OPER TION 1

3. n.1. 4 The quantity of radioactive material contained in each outside' temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICA8ILITY: At all times. a ACTION: With the quantity of radioactive asterial in any evtside temporary a. tank exceeding the above limit, famediately suspend all additions of radioactive material to the tank and within 48 hours reduce the tank contents to within the limit. ? b. TheprovisionsofSpecifications3.0.3and3.0.4arenotappifcahe. SURVEILLANCE R8911RE 2fTS

4. n.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.

ms.. e NOV 151982 5AN ONOFRE-UNIT 3 3/4 n-7

U RADI0 ACTIVE EFFLUENT 5' 0051 _MIE(LAA5Es c.. Liin uius COISITION FOR OPERATION 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 Ifeited to the - following: a. During any calendar quarter: Less than or equal to 5 arad for gamma radiation and less than or-equal--te4g-erad for beta radiation and, b.. During any calendar year:- Less than or equal to 10 erad for gamma radiation and less than or equal to 20 erad for data radiation. MPLICASILITY: At all times. g 1 g d With the calculated air dose free radioactive noble gw os in gasedus a. effluentsexceedinganyoftheabovelimits,inIfeuofanyotheri report required by Specification 6.9.1, prepare and submit ta'thec ( Ceemission within 30 days, pursuant to Specification 6.9.2 a Specic1 Report which identifies the cause(s) for exceedinil $he limit (s) and defines the corrective actions taken to reduce fe' esses and the proposed j i cerfective actions to be taken to assure that subsequent releases will be in cespliance 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 Dose Calculations Cumulative dose contributions for the current calendar quartar and current calendar year'shall be determined in accordance with the 00CM at least once per 31 days. l f ,, j .MOV 151982 SAN ONOFRE-URIT 3 3/4 11-12

s RA0!0 ACTIVE EFFLUENTS 005E - RA0!OI00!NES RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM LINITING COM ITION FOR OPERATION c

3. u. 2. 3 The dose to an individual from tritius, radiefedines and radioactive materials in particulate fem with half-lives greater than 4 days in gaseous effluents released, free each reacter unit, free the site (see Figure 5.1-3) shall be limited to the fe11 ewing:

a. During any calender quarter: Less than er equal to 7.5 ares to any. organ and, - j b. During any calendar year: Less than er equal to 15 ares to any organ. c. Less than 0.25 of the limits of 3.u.2.3(a) and (b) as a result of burning contaminated eil. APPLICA81LITY: At all times. M: With the calculated dose from the release of tritium, radiefedines, a. and radioactive asterials in particulate form, with half lives greater than 8 days. in gessous effluente exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, I prepare and submit to the Commission within 30 days, pursuant to specification 8.9.2, 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 provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIRD effs

4. u.2.3 Dese Calculations Cumulative dose contributions for the current calendar guerter and current calender year sha11 he determined in accordance with the 00CN st least once per 31 days.

1 SAN ONOFRE-UNIT 3 3/4 u-U AMD W WIT NO. 41

I RADIOACTIVE EFFLUENTS 1 GASEQUS RA0 WASTE TREATMENT LIMITING CONDITION FOR Op(RATION 3.11.2.4 The GA5EDUS RA0 WASTE TREATMENT SYSTEM and the VENTILATION TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the.GASEQUS RA0 WASTE TREATENT SYSTEM shall be used to reduce radioactive materials in gaseous waste 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, weeld exceed 0.2 erad for gamma radiation and 0.4 erad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduc's radioactive mat'erials in gaseous -- waste prior to their discharge when the projected doses due to gaseous affluent releases from the site (see Figure 5.1-3) when averaged over 31 days would exceed 0.3 area to any organ.", APPLICA81LITY: At all times. AGE: WiththeGASEOUSRADWASTETREATMENTSYSTEMand/ortheVENTILAT!05 a. EXMAUST TREATMENT SYSTEM inoperable for more than 31 days or witR I gaseous waste being discharged without treatment and in excess of the above Itaits, in lieu of any other report required by Specifica-tion 5.9.1, prepara and submit to the Commission within 30 days, pursuant to Specification 5.9.2,'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. SURVEILLANCEasau!REMffs 4.11.2.4.1 Beses due to gaseous releases from the site shall be projected at least once per 31 days, in accordance with the 00CM. '.p 4.11.242 The GASEOUS RA0 WASTE TREAT M SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERA 8LE by operating the GASE0US RA0 WASTE TREATMENT SYSTEM equipment and VENTILATION EXHAUST TREATMENT SYSTEM equipment for at least 15 minutes, at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days. These doses are per reactor unit. g 1. 51981. SAN ONOFRE-UNIT 3 3/4 11-14

~ ~ 4.. ( RADIOACTIVE CFFLUENTS l pPLOSIVEGASNIXTURE. LIMITING ColGITION FOR OPERATION

3. M.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to a by volume whenever the hydrogen concentration exceeds 4 by volume.

APPLICABILITY: At all times. j ACTION: With the concentration of oxygen in the weste gas holdup system a. greater than 25 by volume but less than er equal to 4 by volume, restore the concentration of oxygen to within the limit within 48 hourg.

j a

b. With the concentration of oxygen in the waste sais.hsidup system greater than 4 by volume, immediately suspend an additions of -F.a weste gases.to the system and reduce the concentre Wen of oxygen th tess than 4 by volume within ong hour and less them er equal to S { i by volume within 48 hours. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. ~ SURVE!LLANCE REQUIREMENTS l i

4. u. 2. 5 The concentrations of hydrogen and oxygen in the weste gas holdup system 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 0PERA8LE by Table 3.3-13 of Specification 3.3.3.9.

e gryt 1 5 W 1 SAN ONOFRE-UNIT 3 3/4 11-15

. % :&. +. b ( RA0!0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RA0!0 ACTIVE WASTE LIMITING ColGITION FOR OPERATION 3.11.3 The solid radweste systas shall be OPERA 8LE and used, as applicable in accordance with ar PROCESS CONTROL PROGRAM, for the SOLIO!FICATION 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 westes-free the site. APPLICABILITY: At all times." J ACTIQN: 't With the packaging requirements of 10 CFA Part 20'and/or 10 CFR' a. Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastes free the site.. With the solid radusste systandnaperable for more taien 31 days, 6i - b. lieu of any other report required by Specification 6.9.1, prepa and submit to the Commission within 30 days persuant to Specifi (, tion 6.9.2 a Special Report which includes the following. Inforest one 1. Identification of the inoperable equipment er seheystems and the reason for inoperability, Action (s) taken to restehthe. inoperable equipment to OPERABLE 2.

status, 3.

A description of the alternative used for S$dIDIFICATION and packaging of radioactive westes, and 4. Summary description of action (s) taken to prevent a recurrence. The provisions of 5 specifications 3.0.3 and 3.0.4 are not applicable. c. 3 ,5 SURVEILLANCE REQUIRBWITS 4.11.3.1 The solid radweste system shall be demonstrated OPEAA3LE at least once per 92 days by: Operating the solid raesesta systas at least once in the previous. a. 92 days in accordance with the PgDCESS 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 g PROGRAM. / 4 "See Specification 6.13.1. gy 151982 ~ 4 SAN ONOFRE-UNIT 3 3/4 11-17 ~

Qgr- [.%. 1 [ RADIOACTIVE EFFLUENTS 3/4. u.4 TUTAL 00$f ~ ~ LIMITING COW ITION FOR OPERATION 3.11.4 The dose or. dose commitment to any member of the public, due to 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 aquel to 75 aces) over 12 consecutive months. APPLICABILITY: At all times. ACTION: n *. ![ With the calculated doses from the release of radioactive materials I a. in liquid or gaseous effluents exceeding twice tauk11mits of Specification 3.11.1.2.a. 3.11.1.2.b. 3.11.2.2.av3.17.2.2.b,; ( 3.11.2.3.a, or 3.11.2.3.b, in lieu of any othek report, required . Specification 8.9.1, prepare and submit a Special Ag,ert 24 the Directors Nuclear Reactor Regulation, U.Si 10sclose Watory-Commission, Washington 0.C. 20545, witJrie 30 dayev whieb dati i j the corrective action to he taken to reduce subsagenet reisease to prevent recurrence of anceeding the limits of. Specification 3.u.4. This Special Report shall include an analysis which estiestes the. radiation exposure (dose) to a member of the peelic free uranium fuel cycle sources (including all effluent pathueys and direct, radiation) for a 12 consecutive month period'.that includes the release (s) covered by this report. If the estiented dese(s) exceeds the limits of Specification 3. u.4, and if the release condition resulting in violation of 40 CFR 190 has not alree @ been corrected, 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 relates 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. .i SURVEILLANCE REQUIREE NTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous affluents shall be determined in accordance with 5ppcifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with tfie 00CN. e NOV 151981 SAN ONOFRE-UNIT 3 3/4 u-19 ]

/' 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION ~ 3.12.1 The radiological environmental sonitoring program shall be conducted as specified in Table 3.12-1. APPt.ICA81LITY: At all times. 4 ACTI0ft:. With the radiological environmental sonitoring progran not being - - a. conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Cee-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.nedi exceeding the reporting levels of Tabis 3.12-2 whom anvaged ove any calendar quarter, ' n lieu of any other report required by Specification 6.9.1, prepare and subelt to the Commission within 30 days from the end of the affected calendar quarter a Report g pursuant to Specification 6.9.1.13. When more than one of the radionuclides in Table 3.12-2 are detected. in the sampling medius, this report shall be submitted if: concentration. (1), concentration (2) + "*> 1.0 limit level (1) . limit level (z) When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be subettted if the potentia 1

annual dese 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 sessured level of radioactivity was not the result of plant effluents 1 however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.. { With fresh leafy vegetable samples or fleshy vegetable samples unavail-c. 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 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 locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from those required by a *_12-1, provided the locations from which the replacement samples were obtained are added to the environmental monitoring program as replacement locations., / d. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. NOV 15 t'!J SAN ONOFRE-UNIT 3 3/4 12-1 ~ ' '

h

( .=, ( RADIOLOGICAL __ ENVIRONMENTAL NONITORING i 3/4.12.2 LA88 USE CENSUS H LIMITING CWWITION FOR OPERATION. 3.12.2 A land use census shall be conducted and shall identify the location __ of the nearest allk animal, the nearest residence and the nearest garden" of greetar 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 1.1H Revision 1. July 1977 the land use census shall also identify the locations o,f all silk animals and all-gardens of greater than 500 square feet producing fresh _1eafy vegetables in each of the 16 meteorological sectors within a distance of three siles. APPLICA8ILITY: At'all times. g: 1 With a land use census identifying a location (s) which yields a a. calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, in lieu of any other report required by Specification 6.g.1., prepare and submit to-Commission within 30 days, pursuant to Specification 6.9.2,* a 5pecial Report which identifies the new location (s). b. With a land use census identifying a location (s) which yields a-calculated dose or dose commitment via the same exposure pathway g 20 percent greater than at a location from which samles are currently being obtained in accordance with Specificities 3.12.1,* in'. lieu of any other report required by Specification 8.9.1, prepare 'l and submit to the Commission within 30 days, pursuant to Specifica ' tion 5.9.2, a Special Report which identifies the new location. Tlie - new location shall be added to the radiological environmental monitoring program within 30 days. y the control station location, having the lowest calculated dose or 'T dose commitment 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. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. c. SURVEILLANCE REMJIR8 MENS 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 results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. " Broad leaf vegetation sampling may be perfonned at the site bounda direction sector with the highest 0/Q in lieu of the garden census. 4 / NOV 1519til SAN ONOFRE-UNIT 3 3/4 12-11

y, ..~ ~- o.', 4 e'. [ RADIOLOGICAL ENVIRO MENTAL McMITORING 3/4.12.3 11tTERLA80RATORY COMPARISON PROGRAM LINITING TTION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials suppifed as part of an Interlaboratory Comparison Program which has been approved by the Commission. APPLICA8ILITY: At all times. ACTION: With analyses not being performed as required above, report the a. corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. i b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. j.l .'V SURWILLANCE REQUIREMENTS k. I 4.12.3 A summary of the results obtained as part of the above' required Interlaboratory Comparison Program and in accordance with the 00CM shall be included in the Annual Radiological Environmental Operating Report. e l NOV 151982 SAN ONOFRE-UNIT 3 3/4 12-12 L----_-_----

~ \\ (~ 3/4.0 APPLICA8ILITY BASES The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for.0peration and Surveillance Requirements within Section 3/4. 3.0.1 This specification' defines the applicability.of each specification in terms of defined OPERATIONAL > WOES or other specified conditions and is provided to delineate specifically when each specification is applicable. 3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition for operation and associated ACTION requirement.- 3.0.3 This specification delineates the sensures to bar taken for circumstances 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 requires two Containment Spray Systems to be OPERA 8LE-ad 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 Systems are inoperable, within one' hour measures must be initiated to / place the unit in at least NOT STAN08Y within the next 6 hours. in at least HOT SHUTDOWN within the following 6 hours, and in COLD SHUTD0h00 in the subsequent 24 hours. 3.0.4 This specification provides that entry. into an OPERATIONAL MODE or other specified applicability condition must be sede with (a) the full com-piement of required systeme, equipment or components OPERA 8LE and (b) all other parameters as specified in the Limiting Conditions for Operation being met without regard.for allowable deviations and out of service provisions contained in the ACTION statements. I The intent of this previsien is to insure that facility opepation is not initiated with either required equipment or systems inoperable or other specified limits being exceeded. Exceptions 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. l / NOV 1519H SAN ONbeRE-UNIT 3 8 3/4 0-1 l 1 i

? ( 8ASE5 3 4.D.{;r This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL M00ES'or other conditions for which the Limiting Condi-tions for Operation are applicable. Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL M00E5 or other conditions are provided in the individual Surveillance Requirements. ) j Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exemption to an individual specification. A 0. 2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal j j surveillance interval. These tolerances are necessary to provide operational J flexibility because of scheduling and performance considerations. The phrase i ", at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities. ,.N T;three test intervals, are sufficiently restrictive to ensare that thaThe to 'A reliability associated with the surveillance activity is not ofgeificantly degraded beyond that obtained from the nominal specified interval. ( ,.,9 4.0.3 The provisions of this specification set forth the critaria for determination of compliance with the OPERABILITY requirements of the Limiting conditions for Operation. Under these criteria, equipment. systems or components are assumed to be OPERABLE if tne 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 0PERABLE, when such items are found or known to be. inoperable although still meeting the Surveillance Requirements. ' l l ..." 1 5 1981 SAN ONOFRE-UNIT 3 8 3/4 0-2 J

.e m BASE 5

4. 0. 42this specification ensures that the surveillance activities associated vith a Lietting Condition for Operation have been performed within the specified time intervat prior to entry into an OPERATIONAL MODE or other applicaLie 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 OPERABILITY requirements of the Limiting Condition for Operation.

+ Under the teres 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 systas or equipment ints OPERABLE status. 4.0.5 This specification ensures that inservice inspection of' A5ME Code class 1, 2 and 3 components and inservice testing of ASE 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 requirements ha been provided in writing by the cammission and it not a part'of these Techn. } Specifications. / This specification. includes 'a clarification of the frequencies for performing the inservice inspection and testing activities required by. Section XI of the ASE Boiler and Pressure Vessel Code and applicable Addenda. This' clarification is provided ta ensure consistency in' surveillance 4ntervals thoughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. Under the tems 'of this' specification, the more restrhetive requirements of the Technical Specifications take precedence over the. ASE Boiler and Pressure Vessel Code and applicable Addenda.. For example, the requirements of Specification 4.0.4 ta perfors surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence over the ASME Boiler and pressure Vessel Code provision which allows pumps to be tested up to one week after return to normel operation.. And for example, the Technical Specification definition of OPERABLE does not grant a grace period before a device that is not capable of performing its specified function is declared inoperable and takes precedence over the ASME toiler and Pressure Wessel Code provision which allows a valve to be incapable of performing its specified function for up to 24 hours before being declared. inoperable. NOV151m SAN'ONOFRE-UNIT 3 8 3/4 0-3

I 1 l l NPF-10/15-238 I ATTACHMENT "C" I { I l

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS 3/4.0 APPLICABILITY LIMITING 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 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 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 STANDBY within the next 6 hours, 2. At least HOT SHUTDOWN within the following 6 hours, and 3. At least COLD SHUTOOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting 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 MODE 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 be made in accordance with ACTION requirements when conformance to them ) permits continued operation of the facility 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 l

APPLICA81LITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with: a. A maximum allowable extension not to exceed 25% of the surveillance interval, and 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 hours to permit the completion of the surveillance when the allowable outage time. limits of the ACTION requirements are less than 24 hours. Surveillance Requirements do not have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with 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: Inservice inspection of ASME Code Class 1, 2 and 3 components and a. inservice testing ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler 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)(1). 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~1n these Technical Specifications: SAN ONOFRE - UNIT 2 3/4 0-2

._= 'l 3: 3 :ss-: eves a ::s-r..- se. .y.c ;,.or..;

-..y

...-.s. -..,..-. y r g.:::a-. y 3.3.1' As a mi9f mum, ne *es:::r er:te: ive instrumentati:n :nanne's 43:

.<: asses of Tacle 3.3-1 sna11 ee CFERA!LE wita RESPONSE 7:MESuns sne-n ir.

Ta:*e 3.3-2. A88L:: !!L: v: As snown in Tacle 3.3-1. A* ::N: As smc*n in Tatle 3.3-1. SURVEILLANCE RE U REufNTS 4.3.1.1 Ea n rea:::r Or:: active instrumentation enannel shall De cemenstratec' 08ERAELI ty tre performance ef. tne OMANNEL CHECK, CHANNEL CAL:! RAT:CN.and

-ANNEL FUNCT:0NAL TEST c erations for tne MCCES anc at the frecuenefes sne-n in 74:le 4.3-1.

a.3.1.2 The legi: for the Oy: asses s all ce cemens: ate 08!RAELE :-ice :: es:n ree:::r starta: unless perf:rme: curing tne =re:ecing 92 cays. Tre :::a1 Oy: ass fun::icn small te cemenstratec OPERAELE at least en:e er 18 m:r s

-**; *eaNNEL CAL *!;AT*;N testing ef 'ea:.. :nannel af fe::e: Of y: ass

eat 1:n.

a.3.1 3 Tre 8.EA i;R TRI? SYSTEM RESPONSE T:ME.cf eacn rea:::e :-i: fan::i:n snall te cemenstrated to be witnin its limit at least once er 18 mc9:ns. Es:n test sna11 include at least one channel er functi:n suen 134: all

ancels are tested at least once every N times 18 mentns wnere N is :Pe :::a1 nue:er of *ecuncant enannels in a specific res::cr tri fun: icn as sn:wn in

ne "To ai No. cf Channels" ectumn of Tacle 3.3-1.

a.3.1.4 The isolation characteristics of each CEA isclation ae:1iffer anc eacn cotical isolator for CEA Calcula ce : C:*e Prcts::1:n Caleglat:r cata. transfer sna11 be verified at least once per 18 montas curing ne snut::=n :er the fc110 wing tests: F:r the CEA ;;sitice isclati:n'amelffiers: a. 1 W' n 120 velts AC (50 H:) a:: lie f: at ' east 30 se:: :s a:-:ss tre cut:ut, tre res: n; :n ne'it:.: ::ss n:: es:te: 0.015 vel:s :. SAN ;NCFR!-UN:T2 3/a 3-1 FEB 17 881 9 .,.. ~.. _ _ _.. - _ _ _. _. -.. . - -. - _ _ -.. = -, - - _. _.

i i r:!'.E 3.3-1 f :-t'.ce:) i m W';h : e ;r:tective system tri; breakers in the clesed ;:siti:n, tre *Ea

-ive 1,.sta

a:1:le of CEA -itnert-al, and f.el in tne rea:::r vesse!.

-4 (a) Tri; eay be manually ty;assee above 10 % of RATED THERMAL PCkER; by: ass shall te aut:matica11y removed when THERMAL PCwER is less than er e:.ai to 10 '% of RATED THERMAL power. (:) Trip may te manually bypassed belew a00 psia; bypass shall be at::matically removed whenever pressurizer pressure is greater than er e:.a1 to a00 psia. (c) Tri; may te manually bypassed telew 10 % of RATED THERMAL POWER; by; ass srsil te au;':matica11y removed when THERMAL PCWER is greater than cr; a: val to 10 % of RATED THERMAL PCWER. During testing pursuant to " 5:ecial Test Ex::::icn 3.10.3, trip may be manually bypassee telcw E% of RATE 3 THERMAL PCwER; bypass shall be automatically removed when THERMAL P* ER is greater tnan or e:041 to E% of RATED THERMAL PCWER. (:) Tr': Ex:e;may te typassec during testing purs ant is 5;ecial Test

i: n 3.~.0.3.

(e; See 5;e:ial Test Exce: i:n 3.~.?.2. (f) Ea:n :Pannei shall te c:m:rised f two trip breakers; actual tri; 1:gi: 3rall te cre-:st-:f-two taxen twice. (g) Tri; may be by;assed belew EE% RATED THERMAL PCVER. ACT*0N STATEMENTS A*T:*N 1 Wi:n the number of channels CPERAELE cre less than re:vire: :y tne Minimum Channels CPERAELE requirement, rest:re tr.e ine:erable channel to CPERABLE itatus wi:nin aS h:urs er te i. at least HOT STANCEY within the next 6 hcurs and/cr :;en t..e protective system trip breakers. A* TION 2 With the number of channels CPERAELE ne less than :te Tc;s! Num:er cf Channals, STARTUP anc/cr PChER CPERATICN may c:ntir.e I pr: viced the incperatie channel is place: in the by;asse: er ,i tri::ec c:nciti:n within 1 hour. If the inc;eratie enanrei fr ty;assec, the cesiratility of maintaining this ent.rei i. tre bypassed ::ncitien shall be reviewed in ac::r:ance.ith 5:e:ificati:n 6.5.1.Ee. The enannel sna11 te returne: t: CPERAELE status nc later inan curin; tne next COL 3 SHUT::bN. MAY i 619S3 spi 05:*;!-2::7 2 3/4 3-4 AMENtMENT NO. 15

q ;uu!A : ::N 3/43.2 ENGINEEEE3 SAFE?v EATU:E ACTUAT* N Sv5 E" !NS tuu!s a ::N

v: :s c:N'.!?!0N 80R C !::?:On 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation j

channels anc mypasses snown in Taele 3.3-3 shall be OPERA 8LE witn tneir tric set:cints set consistant with the values snown in the Trip 5et;cint c=1cmn of Tesle 3.3-4 anc with RESPONSE TIMES as snown in Tanle 3.3-5. A:8LICABIL!*Y: As shown in Table 3.3-3.* A07:0N: With an E5FAS instrumentation channel trip setpoint less conservative a. than the value snown in the Allowable Values column of Table 3.3-4, ceclare the enannel inoperable and aoply the acplicable ACTION requirement of Table 3.3-3 until the channel is restorec to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setooint value, With an ESFAS instrumentation channel inoperable, take the ACTION b. snown in Table 3.3-3. S'J:VEILLaNCE RE00!aEwENTS " 3.2.1 Eacn !$FAS instrumentation enannel shall te cemenstrate: 08ER"!>.E :y t e :er'e mance of the CHANNEL CHECK, CHANNEL CALIBRATION ard CHANNEL 'JNOT!NAL TEST coerations for the M0015 and at tne frequencies snown in I Ta:1e 4.3-2. 4.3.2.2 The logic for the bypasses shall be demonstrated OPERABLE curing the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total typass function shall be demonstrated CPERA8LE at least once per 18 montas curing CHANNEL'CALI8 RATION testing of each channel affected by typass operation. 4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFA5 function small be demonstrated to be within the limit at least once per 18 months. I Eacn test shall include at least one channel per function suen tnat all i cnannels are tested at least once every N times 18 mon *ns wnere N is the tCtal l ru.-:er of recuncant enannels in a scacific E5FA5 function as shown in tne "Ic.a1 No. of Onannels" Column of Tasle 3.3-3. .'See Special Test Exception 3.10.5 1 ( SAN ONCFRE-UNIT 2 3/4 3 13 gg g 7 g

TABLE 3.3-3 (Continued) TABLE NOTATION (a) Trio function may be byoassed in this MODE when pressurizer pressure is less snan a00 psia; Dynass sna11 be automatically removes wnen pressuri:er pressure is greater than or equal to 400 psia. (b) An SIAS signal is first necessary to enable C5A5 logic. (c) Actuated equipment only; does not result in CIAS. The provisions of Specification 3.0.3 are not applicaale. With irradiated fuel in the storage pool. ACTION STATEMENTS ACTION 8 With the numeer of CPERA8LE channels one less than the Total Nueer of Channels,; restore the inoperaale channel to OPERA 8LE' status within as hours or be in at least NOT STAN08Y within the next 6 hour's and in COLD SMUTDOWN within the following 30 hours. ACTICN 9 - With the numoer of channels OPERA 8LE one less than the Total Nuecer of Channels, STARTUP'and/or POWER OPERATION say continue provided the inoperaale enannel is placed in the bypassed or tripped condition within 1 hour. If the inoperaale enannel is typassed, the desirability of maintaining this channel in the Dypassed condition shall be reviewed in accordance_with Specification 6.5.1.5e. The channel shall be returned to CPERA8LE status no later than during the next COLD SHUTDCWN. With a channel process measurement circuit that affects multiple functional units inoceraale or in test, cypass or trip all associated functional units as listed below. Process Measurement Circuit Functional Unit typassed 1. Containment Pressure - High Containment Pressure - High (E!F) Containeer.t Pressure - Hign (RP5) 2. Steam Generator Pressure Stese Generater P' essure - Low Low Staas Generator AP 1 and 2 (EFAS) j 3. Steam. Generator Level Steae Generatar Level - Low Steam Generator Level - High Steam Generator.iP (EFA3) { l SAN CNCFRE-UN;T 2 1 3/4 3-19 Amendment No. 4 i N. i i :-

INSTRUMENTATION INCORE DETECTORS t.IMITING CONDITION FOR OPERATION ) 3.3.3.2 The incere detection system shall be OPERA 8LE with: i a. At least 75% of all incore detector locations, and b. A minimum of two quadrant symmetric incore detector locations per core quadrant. 1 An OPERA 8LE incore detector location shall consist of a fuel. assembly i containing a fixed detector string with a minimum of-four OPERABLE rhodium detectors or an OPERA 8LE movanle.incore detector capable of mapping the location. 4 APPLICA8ILITY-When the incore detection system is used for monitoring:, a. AZIMUTHAL POWER TILT, ) b. Radial Peaking Factors, c. Local Power Density, d. DN8 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 are not applicable. SURVEILLANCE REQUIREMENTS 1 i 4.3.3.2 The incore detection system shall be demonstrated 0PEkABLE: a. By performance of a CHANNEL CHECK within 24 hours prior to its use if j 7 or more days-have elasped since the previous check and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL i POWER TILT, radial peaking factors, local power density or DN8 margin: b. At least once per 18 months by perfomance of a CHANNEL CALIBRATION l operation which exempts the neutron detectors but includes all electronic coenonents. The neutron detectors shall be calibrated prior to installation in the reactor core. SAN ON0FRE-UNIT 2 3/4 3-41 AMEN 0 MENT N0. I.9 1

i

S! acPENTa7:0N SE:!u:: lv5 it'u!N a**:N 1

~ '.

v: : N ::s**-*:N ::R C:!R& ::N 3.3.3.3 ine seismic monitoring instrumentation snown in Table 3.3-7 shati :e CPERABLE.

8 8 8 '. * :43 :' !*v: At all times. ACT:0N: Witn one or more seismic monitoring instruments inocerasle for m: e a. inan 30 days pre:are and submit a Scecial Report ts tne Commissten cursuant to Spe:ificatien 6.9.2 within tne next 10 days outlining ne cause of ne malfunction anc tne plans for rest: ring tne ins rument(s) to CPERABLE status. b. The provisions of Specifications 3.0.3 are not a:slica:*e._ j ) SU:VEILLANCE REQUIRE.WENT$ ~~~ a.3.3.3.1 Ea:h cf the a:ove seismic m nit: ring instruments shall be cemenstrate: CPERABLE by the performan:e of tne CHANNE' CHECK. CHANNEL CAL:3 RAT "N anc CHANNEL FLNCTICNAL ~EST ::arations at ne frequencies sn:wn f.. Ta:1e a.3-4 ]

a. 3. 3. 3. 2 Eacs of :ne above seismi: m: nit: ring instruments wnica'is a::sss'::e

'l 1

urin; ::-er c:eration and whien is actuatec curing a seismic event (:ne or mere valic basemat accelerations of C.C5g or greater) snall be resterec i

to CPERASLE status within 24 hours ~and a CHANNEL CALI!RATICN performed wits.ir-j 5 cays. Casa shall be retrieved from the ac:essible actuatec instruments ar.: analy:ed :s determine the magnitude of.the vibratory grounc motion. A S:ecial Recort shall be prepared and submitted to the Commission pursuant to-Specification 6.9.2 within 10 days coscribing the magnitude, frequency s:ect um anc resultant effect unen facility features important to safety.. Each of :ne-a:ove seismic monitoring instruments which is actuated :uring a seismic event. (one or more valid basemat accelerations of 0.05g or greater) but is 3 i not ac:essible during power operation shall be restored ic OPERABLE status and a CHANNEL CALIBRATION performed the next time the plant enters MCOE 3 :r below. A su::lemental report shall then be precared and sutmitted t:.' e C:mmissi:n wit?.in 10 cays pursuant is 5:e:ffi:ation 6.9.2 ces:ri:ing ne a::itierai ca:a fr:2 :nese instruments. \\ FEB17ill!' $AN CNCFRE-L' NIT 2 3/4 3-42 i

i ss :veis a7::N ...... c. y c. ;.... s :-..., 6.------ -- 3 i l

u - s: 9 : : N =ct c:!qat:CN 3.3.3.4 The meteorological monitoring instrumentation enannels shown in Ta:1e 3.3-8 snall ce OPERABLE.

3 :,8'. * : !! L :*v : At all times. ACT*CN; a. Wita one or more recuired meteorological meritering enannels-incperamle for mere than 7 cays, prepare and su:mit a Special to:c-t to tne Commission pursuant to Specification 6.9.2 within the next 10 cays outlining tne cause of the malfunction and the plans fcr. restoring the enannel(s) to CPERA8LE status. c. The previsions of Specifications 3.0.3 are not acclicasle. SUtVE:L'_ANCE E!OUIREVENTS a.3.3.a Eaca of the above meteorelegical monitoring instrumentation enannels s all :e ::.?:nstra ee OPERABLE Oy the performance of tne CHANNEL CHiOK anc C-ANNE' CA'*iRAT* N =pe ations at tne fre uenciss snow-in Ta:1e 4.1-5. 4 ( SAN CNCFRE-UNIT 2 3/4'3-45 ((gg7gggg

t , INSTRUMENTATION _ RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1 LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12. shall be OPERABLE with their alam/ trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The alare/. trip setpoints of these channels shall be determined in'accordance with the 0FFSITE 005E CALCULATION MANUAL (00CN). APPLICA81LITY: At all times." ACTION: With a radioactive liquid effluent monitoring instrumentation : a. channel alara/ trip setpoint less conservative than required by the above specification, lamadiately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. b. With less than the sinlaus number of radioactive liquid effluent monitoring instrumentation channels OPERABLE,.take the ACTION shown in Table 3.3-12. Exert best efforts to return the instriment to 0PERA8LE status within 30 days and, additionally, if the inoperable 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 timel canner. y The provisions of Specifications 3.0.3 and 6.9.1.13b are not c. applicable. SURVEILLANCE REQUIRDENTS 4.3.3.8.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfomance of the CHANNEL CHECK, SOURCE CHECK, CHAISIEL CALIBRATION and CHAf9IEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8. 4.3.3.8.2 At least once per 4 hours, 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. i "see special Test Exception 3.10.5. SAN ONDFRE-UNIT 2 3/4 3-63 AMENONENT N0. 57

1 l INSTRUMENTATION RADI0 ACTIVE GASECUS 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 df these channels shall be determined in accordance with the 00CM. j APDLICA8ILITY: As shown in Table 3.3-13* ACTION: With a radioactive gaseous effluent monitoring instrumentation a. 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. With less than the minimum numbe'r of radioactive gaseous effluent b. monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Tacle 3.3-13. Exert best efforts to return the instrument to OPERABLE status within 30 days and, additionally, if the inoperable instrument (s) remain 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. The provisions of Specifications 3.0.3 and 6.9.1.13b are not c. applicable. . SURVEILLANCE 4 REQUIREMENTS 4.3.3.9 Each radioactive gaseous affluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9. "See special Test Exception 3.10.5 JAN 11585 SAN ONOFRE-UNIT 2 3/4 3 64 AMINUMENT NO. 31

f INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 1 i 3.3.3.10 The loose part detection system shall be OPERA 8LE. APPLICA8ILITY: MODES 1 and 2. ACTION: With one or more loose part detection system channels inoperable for a. 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 cause of the malfunction and the plans for restoring the channel (s) to OPERA 8LE status, The provisions of Specifications 3.0.3 are not applicable. b. ~~~ SURVEILLANCE REQUIREMENTS 4.3.3.10 ~ OPERA 8LE by performance of a:Each channel of the loose part detection sys CHANNEL CHECK at least once per 24 hours, a. b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and i CHANNEL CALIBRATION at least once per 18 months. c. 1 -i JAN111BIl i SAN ONOFRE-UNIT 2 3/4 3-75 AMENDMENT No. 31

i i I REACTOR COOLANT $YSTEM OVERPRES5URE PROTECTION $YSTEMS RCS TEMPERATURE I 235er LIMITING CCNCITION FOR OPERATION 3.4.8.3.1 At least one of the following overpressure protection systems shall be OPERA 8LE: ) The Shutdown Cooling System Relief Valve (P$V9349) wita: a. 1) A lift setting of 405

10 psig*, and-

} 2) Relief Valve isolation valves 2HV9337, 2HV9339, 2HV9377 ane 2MV9378 open, or, b. The Reactor Coolant System dooressurized with an RCS vent of greater tnan or equal to 5.6 square incnes. ? APPLICA8ILITY: MODE 4 when the temperature of any one RCS cold leg is less tnan or equal to 235'F1 MODE 5; MODE 6 witn the reactor vessel head on. AEUS!!! With the SDCS Relief Valve inoperacle, reduce 7,,, to less than a. 200*F, eenressurize and vent the RCS through a greater than er equal to 5.6 square inen vent within the next 8 hours. b. With one or both $0C5 Relief Valve isolation valves in a single SDC5 Relief valve isolation valve pair (valve pair 2MV9337 ano 2MY9339 or valve pair 2HV9377 and 2Hv1378) closed, open the closed valve (s) within 7 eays or reeuce T,,, to less than 200*F, cepres-surize and vent the RC3 through a greater than or equal to 5.6 inch vent within the next 8 hours. In the event either the SOCS Relief Valve or an RCS vent is used to c. mitigate an RC5 pressure transient, a Special Report snell be preparse anc submitted to the.Casumission pursuant to Specification 6.9.2 within 30 days. 'Thd~ report shall describe the circumst.ances initi-ating the transient, the effect of the SDCS Relief Valve or RCS vent on the transient and any corrective action necessary to prevent recurrence. 2 SURVEILLANCE REQUIREMENTS a.4.8.3.1.1 The $0C5 Relief Yalve shall be demonstrated CPERA8LE Oy: Verifying at least once per 72 hours when the 50C5 Relief Valve is a. being used for overpressure protection that SOCS Relief Valve isolation valves 2MV9337, 2MY9339, 2HY1377 ano 2HV9378 are open. For valve temperatures less than or egual to 130*F. SAN ONCFRE-UNIT 2 3/4 4 32 Amendment No. a l im i 6 E

RE AC*04 000.' ANT $v$* w 3.4.9 5'RUCTURAL IN~E;8**v L:w:NG l0N!**:CN ::R 08E8AT :N 3.4.9 Tne structural integrity of ASME Caos Class 1, 2 anc 3 commenents snail be maintainec in ac:orean:e witn Specification 4.4.5. Apel::AE!L:~Y: ALL MODES A *:0N: Witn the structural integrity of any ASME Code class 1 comoonent(s) a. not conforming to the acove requirements, restore tne structural integrity of tne affected commenent(s) to witnin its limit or isolate tne affected component (s) prior to increasing the Reactor Coolant System temperature more than 50*F acove sne minimum temperature recuirec by NOT considerations. b. Witn the structural inte; Pity of any ASME Code Class 2 comconent(s) not conforming to the acove requirements, restore the structurai integrity of tne affected component (s) to witnin its limit or isolate the affected component (s) crier to increasing the Reac ce Coolant System temperature acove 200'F. i With the structural integrity of any ASME Coca Class 3 c:msonent(s) t. not conforming to the acove requirements, restore the structural integrity of the affectec comconent to within its limit er isolate ne affectec com:enent from service. SURVEILLANCE REQUIREMENTS 4.4.9 In addition to the requirements of Scarification 4.0.5, each React:r Coolant Pump flywheel shall be inscoctec per the recommendations of Requias:ry Position C.4.b of Regulatory Guide 1.14, Revision 1. August 1975. I I l 1 SAN ONCFRi-UNIT 2 3/4 4-34 f[${7llll

s' ANT SYSTEMS 3/t.7.7 SEALED SOUROI CONTAMINATION L:w: :N 00NO:~!0N FOR 0:!EA7:0N 3.7.7 Each seale.d source containing radioactive material either in excess of t 100 microcuries of meta anc/or gamma emitting material or 5 microcuries of alona emitting material shall be free of greater then or equal to 0.005 microcuries of removaole contamination. Ae*LICABILI7: At all times. ACTION: With a' sealed source having removable contamination in excess of the a. aoove-limit, withoraw 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 applicaele. SURVEILLANCE REQUIREMENTS 4.7.7.1 Test Requirements - Eacn sealed source shall be tested for leaxage anc/cr contamination by: a. The licensee, or b. Ctner persons specifically authorized )y 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 startuo sources and fission detectors previously sucjected 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), ane 2. In any form einer tr.an gas. ( SAN ONCFRE-UNIT 2 3/4 7-24 '~

1 RE.'E'.*NG 0: Eta- :N5 5

9. 9 0N a!'.EN

';;3E :5:'.A*:"N Sv5 E*

.........y ..,........y .a .-:-..s, ) 1 ( 3.9.9 The containment purge isolation system shall be OPERAE'E. a888.: *19 ? '.!TY: Caring CORE ALTERATIONS or movement of irraciated f.el wi tn -

e containment.

A*?*0N: I 'with ne c:ntainmer: : urge isolation system inocerable, close each cf tr.e contair. ment ourge genetratiens providing cirect access from tne c:ntainne-: atmes:nere te ne cc:sica atmospnare. SURVE:'. LANCE R50'J*REugy+$ 4.9.9 The containment purge isolatien system sna11 te demenstratec 0FERA!'I within 72 h urs prior to ne start of anc at least once per 7 cays curing ;"Ri A'. TERAT:0HS by verifying that containment purge valve isolation oc:urs en manual initiation and on a hign raciation test signal. i { SAN CNC.:Ri-UNIT 2 3/4 9-10 FE8171982

l E E:'J E L:NG CDE3A?!CNS 3/4.9.12 CUEL HANDLING BUILD!NG POST-ACC! CENT CLEANUP ~!L*ER Sv5'EM LIu! TING CCNOITION FOR OPERATION 3.9.12 Two independent fuel handling building post-accicent cleanuo filter. systems snail be OPERABLE. APPLICABILITY: Whenever irradiated fuel is in the storage pool. ACTION: With one fuel handling building post-accident cleanuD filter system a. inoperable, fuel movement within the storage pool or operation of fuel handling machine over the storage pool may proceed provided the OPERABLE 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 OPERABLE status. SURVEILLANCE REQUIREMENTS 4.9.12 The above required fuel handling building post-accident cleanup filter systems shall be demonstrated OPERA 8LE: At least once per 31 days on a STAGGERED TEST BASIS by initiating, a. f rom the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours with the heaters on. b. At least once per 18 months or (1) af ter 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 3 0 '.iii SAN ONCFRE-UNIT 2 3/4 9-13 AMEN 0 MENT NO. 36

1 1 RADIOACTIVE EFFLUENTS CCSE LIMI?!NG CON 0!*!CN FOR OPERATION ~ 3.11.1.2 The dose or dose commitment to an individual fron radioactive materials in liquid affluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited: i During any calendar. ouarter to less than or equal to 1.5 mrem to the { a. total bocy and to less than or equal to 5 arres to.any organ, and D 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 nres to any organ. AP8tICA8ILITY: At all times. ACTION: With the calculated dose from the release of radioactive materials - a. in liquid affluents exceeding any of the above liefts, in lieu of i any other report required by Specification 6.9.1, prepare and submit - to the Cossaission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (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 6.9.1.13b are not applicanie. 1 SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liouid affluents sna n se osterstned in accordance with the CDCM at least once per 31 days. i l l i SAN ONOFRE-UNIT 2 3/4 11 5 i i

RADIOACTIVE EFFLUENTS, LIOUID WASTE TREATWENT L:M!~:NG CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment systes shall be OPERA 8LE. 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 doses i due to the liquid effluent from the site (see Figure 5.1-4) when averaged over 31 days, would exceed 0.06 ares to the total booy or 0.2 area to any organ.2 APPLICABILITY: At all times. ACTION: With the liquid radwaste treatment system inoperable for more than a. 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 whien 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 OPERABLE status, and 3. Summary description of action (s) taken to prevent a recurrence. b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS I 4.11.1.3.1 Doses due to liquid releases shall be projected at least ones per 31 days, in accordance with the 00CM. 4.11.1.3.2 The Ifouid radwaste treatment systes shall be demonstrated. OPERA 8LE by operating the liquid radwaste treatment system equipment for at least 15 minutes at least once per 92 days unless the liquid raawaste system has been utilized tc process radioactive liquid effluents during the previous 92 days. "Per reactor unit SAN ONOFRE-UNIT 2 3/4 U-6 FD 17TN2

o.; :0A ~~VE E:~'.UEN S s LI?t:0.'*LO'JP ? NS:S L:u: TING CONSITION FOR 08 ERAT!CN 1 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 APPLICABILITY: At all times. i ACTICN: With the quantity of radioactive material in any outside tempcrary a. i tank exceeding the above limit, immediately suspend all additions of h radioactive material to the tank and within 48 hours reduce the tank l contents to within the' limit. b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQU!REu!NTS .n-4.11.1.4 The quantity of radioactive material contained in each outside tem:crary tank shall be determined to be within the above limit by analyting a re:resentative sample of the tank's contents at least once per 7 days vnen ra:ica:tive catarials are being added to the tank. MAY 161891 " "" ? ? ' I ' ?

RA0!0 ACTIVE EFFLUEN 5 DOSE - NC8LE GASES L!u! ING CONDI"!ON FOR OPERATION 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: i a. During any calendar guarter: Less than or ecual to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, b. During any calendar year: Less than or equal to 10 mead for gamma radiation and less than or equal to 20 arad for beta radiation, j APoLICA8ILITY: At all times. ACTION With the calculated air dose from radioactive noble' gases in gaseous s. i effluents exceecing any of the aeove limits, in lieu of any other report required by Specification 6.3.1, prepare and submit to the Commission witnin 30 days, pursuant to Specification 8.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and - defines the corrective actions taken to reduce releases and the pre::sec corrective actions to be taken to assure that sucsequent releases will be in compliance wita Specification 3.11.2.2. b. The provisions of Specifications 3.0.3 are not acclica:1e. SURVEILLANCE REQUIREMENTS i 4.11.2.2 Dese Calculations Cumulative dose contributions for the current calencar guarter anc current calendar year shall be determined in accorcance with the 00CM at least once per 31 days. \\ SAN ONOFRE-UNIT 2 3/4 11-12 FEB 171981

{ RADI0 ACTIVE EFFLUENTS DOSE - RADICI00!NES RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRIT!UM l LINITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individua1'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 (sea 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 4 organ and, .i b. During any calendar ytte: Less than or equal to 15 ares to any organ. Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result c. of burning contaminated oil. APPLICA8ILITY: At all times. ACTION: With the calculated dose from the release of tritium, radiciodines, a. and radioactive materials in. particulate fom, with half lives greater than 8 days. in gaseous efflueints 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 i subsequent releases'will be in compliance with Specification 3.11.2.3. 1 b. The provisions of specifications 3.0.3 are not appitcable. i 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. SAN ONOFRE-UNIT 2 3/4 11-13 AMENDMENT NO.c52 l

1 1 RADIOACTIVE EFRUENTS GASEOUS RADWASTE TREATWEW H d LIMI*!NG C*NCITION FOR OPERATION 3.11.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATl TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASECUS l RA0Wa:TE TREA7 MENT SYSTEM shall be used to reduce radioactive materials gaseous waste prior to their discharge when the projected gaseous affluent air esses due to gaseous affluent releases from the site (see Figure 5.1-3), wnen averaged over 31 days, would exceed 0.2 arad for ganna radiation and 0.4 erad for beta radiation. The appropriate port;ons of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive saterials in gaseous d 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 would exceed 0.3 area to any organ." APPLICABILITY (: At all times. ACTION: With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTI a. EXHAUST TREATMENT SYSTEM inoperatie for more than 31 days or 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,ra and suosit 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 sutsystems and the reason for inoperacility, 2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3. Summary description of action (s) taken to prevent a recurrence. ] b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 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 GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION E TREATMENT SYSTEM shall be demonstrated CPERA8LE by operating the GASEOUS RA0 WASTE TREATMENT SYSTEM ecuipment and VENTILATION EXHAUST TREATMENT SYSTEM ecuipment for at least 15 minutes, at least once per $2 days unless the appropriate system has been utilized to process raoicactive gaseous affluents curing the previous 92 days. i "These-doses are per reacto,r unit. SAM ONOFRE-UNIT 2 3/4 U-14 FU i7tN2

l l r,A : CACTI'!! E~~LL'ENT5 E :LC5:'JE G:5 P'X'U E L:R!T!'?G C NCITION FC9 OPERATION { 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall te Ifeited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by voluma. i APPLICABILITY: At all times. ACTION: With the concentration of oxygen in the waste gas holdup system a. 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 hours, With the concentration of oxygen in the waste gas holdup system b. 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 25 by volume within 48 hours. The provisiens of Specifications 3.0.3 are not applicable. c. SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above Ifmits by continuously moni-toring the waste gases in the waste gas holdup system with the hydrogen and oxygen eenitors required CPERABLE by Table 3.3-13 of Specification 3.3.3.9. MAY i 6 ige? 5A'i CNCF.EE-UNI 2 3/4 11-15 avrvnvrwr en 16

1 d ) i I RADIOACTIVE EFFLUENTS 3/4.11.3 SOLIO RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION j 3.11.3 The solid reewaste system shall be OPERABLE and used, as applicaele in 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. APPLICABILITY: At all times.*

I ACTION:

With the packaging requirements of 10 CFR Part 20 and/or 10 CFR a. Part 71. not satisfied, suspend shipments of defectively packaged solid radioactive wastas free the site. With the solid radwesta system inoperable for more than 31 days,' in b. 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 includes the following information: 1. Identification of the inoperable equipment or subsystans and the reason for inoperanility, 2. Action (s-) taken to restore the inoperable equipment to CPERA8LE

status, 3.

A description of the alternative used for 50LIDIFICATION and packaging of radioactive wastes, and 4. Summary description of action (s) taken to prevent a recurrence. The provisions of Specifications 3.0.3 are not applicable. c. SURVEILLANCE REQUIREMENTS 4.11.3.1 The solid radwesta systes shall be demonstrated OPERABLE at least once per 92 days by* l I Operating the solid radwaste system at least once in the previous a. 92 days in accordance with the PROCESS CONTROL PROGRAM, or I b. Verification of the existence of a valid contract for 50LIDIFI ATION i to be performed by a contractor in accorcance with a PROCESS CONTROL l PROGRAM. ? "See Speci fication 6.13.1. 2 SAN ONOFRE-UNIT 2 3/4 11-17 p-: ~n317 luz I

l l RADIOACTIVE EFFLUEN'S 3/4.11.4 TOTAL Dost J L!u!*MG CONDITION FOR OPERATION 3.11.4 The dose or dose conmiitment to any member of the public, due'to i 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. APPLICA8ILITY: At all times. ACTION: a. With the calculated doses from the release of radioactive materials 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.a, or 3.11.2.3.b, in lieu of any other report required by. Specification 6.9.1, prepare and submit 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 reduce subseovent 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 from uranium fuel cycle sources (including all effluent pathways and direct radiation) for a 12 consecutive month period that includes the 'l release (s) covered by this report. the limits of Specification 3.11.4, and if the release con (ditionIf the estima 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 provisions of 40 CFR 190 and including the specified information of i 190.11(b). Submittal of the report is considered a timely request, and a variance is granted until 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 require-ments 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 not applicable. ) 1 4 SURVEILLANCE REQUIREMENTS F i 4.11.4 Dese Calculations Cumulative dose contributions from liquid and gaseous efflurints snall ne determined in accorcance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the 00CM. i s SAN ON0FRE-UNIT 2 3/4 11-19 ns17 m2

( 3/A.12 RAC!0 LOGICAL ENVIRONh8 ENTAL MONITORING 3/a.12.1 MONITORING oROGRAM LIMITING CONOIT!ON FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1. ,j APPLICA8ILITY: At all times. ACTION: With the radiological s' environmental monitoring progras not being i a. conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and subsit to the Coe-sission, in the Annual Radiological Operating Report,' a description of the reasons for not conducting the progras as required and the plans for_ preventing a recurrence. b. With the level of radioactivity in an environmental sampling medius-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 Commission within - J 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 be submitted if: l concentration (1), concentration (2)~. ***> g*g. 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 subsitted 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 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 vegetable samples or fleshy vegetable samples unavail-able from one or more of the sample locations required by Tabir 3.12-1, in lieu of any other report required by specification 6.9.1, prepare and submit to the Consission 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 from which samples were unavailable may then 1 be deleted from those required by Table 3.12-1, provided the locations from 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 applicable. SAN ONOFR!-UNIT 2 3/4 12-1 FU17 22

r:0!0LOGICtt ENvit.3" ENTAL P.ONITCt!NG 2'.12.2 LAND USE CENSUS-Liv 1TI!43 CO'QITION FOR OPERATION 3.12.2 A lard use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden" of greater than 500 square feet producing fresh leafy vegetatles in each of the 16 meteorological sect:rs 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 also identify the locations of all milk 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. APPLICA81LITY: At all times, l ACTION: l With a land use census identifying a location (s) which yields a-a. calculated dose or dose commitment 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-j Commission 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 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, 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 1' environmental monitoring program within 30 days. The sampling location, excluding the control station location, having the lowest calculated dose er dose commitment via the same exposure pathway may be deleted fecm this monitoring program after October 31 of the' year in which this land use census was conducted. The provisions of Specifications 3.0.3 are net applicable. c. SURVEILLAfiCE REQUIRE"ENTS A.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 results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. = Broad leaf vegetation sampling may be performed at the site boundary in the , direction sector with the highest 0/Q in Ifeu-of the garden census. gi6 2 SAN ONO~RE-UNIT 2 3/4 12-11;.- APE.*:0'OT 40.16 -l

i / P.A0 '.0'.0 2 *. *

L ENV
RC':"!NT AL t*0N!TO R ING.

/ 3/a.12.3 INTERLAE O R ATC EY C*!** * *

SC'l * *00R *M LIMITING CONDITION 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.

APPLICA$ILITY: At all times. ACTION: With analyses not being performed as required above, report the a. corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Aeport. b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS A sEmmary of the results obtained as part of the above required 4.12.3 Interlateratory Comparison Program anc in accordance with the COCM shall be included in the Annual Radiological Environmental Operating Aaport. MAY 161983 SAM Ct:0Fni-UNIT 2 3/4 12-12 4.:gst:.:g:;7 :0,16

3/4.0 APPLICABILITY BASES Specification 3.0.1 throuah 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 of federal Regulations,10 CFR 50.36(c)(2): " Limiting conditions for operation are.the lowest functional 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 Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the~ Limiting Conditions for Operation is required for safe operation of the facility. The ACTION requirements establish'those remedial measures that must be taken within specified time 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 -I 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 the ACTION requirements continue to be met. The second type of: ACTION requirement specifies a time limit in which conformance to the conditions ofx 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 MODE 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 requirements 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 j for Operation are not met. { SAN ON0fRE - UNIT 2 8 3/4.0-1 i 2

I \\ 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 within the specified time interval constitutes compliance with a specification and (2) completion 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. Specification 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 ACTION requirements. One hour is t' allowed to prepare for an orderly shutdown before initiating a change in plant L 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 i nenner that is well within the specified ma

mum cooldown rate and within the cooldown capabilities of the facility assu.

g only the minimum required equipment is OPERABLE. This reauces therma s 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. -i 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 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 hours for the plant to be in the COLD SHUTDOWN 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 SHUTOOWN, or other applicable MODE, is not reduced, for example, if HOT STANDBY is reached in 2 hours, the j time allowed to reach HOT SHUTDOWN is the next 11 hours because the total time to reach HOT SHUTDOWN is not reduced frbm the allowable limit of 13 hours. 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. 1 SAN ONOFRE - UNIT 2 B 3/4.0-2 ) j

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 restoring equipment to OPERA 8LE 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 OPERATIONAL MODE or other specified condition may be made in accordance 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 Requirements stated in the Code of federal Regulations, 10 CfR 50.36(c)(3): i ' Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and j components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met." SAN ON0fRE - UNIT 2 8 3/4.0-3

s 3/4.0 APPLICABILITY BASES (Con't) Specification 4.0.1 establishes the requirement that surveillance 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 surveillance 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 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. l 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 facilitate surveillance scneduling 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 surveillance being l performed is the verification of conformance with the Surveillance 1 Requirements. These provisions are sufficient to ensure that the reliability l ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. l 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 OPERA 0!LITY 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 prevision 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 Requirem?nts. This 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 from the point in time it is identifird that a surveillance has not been performed and not at the time that the alkwed 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 ON0FRE '" IT 2 B 3/4.0-4

d l 3/4.0 APPLICABILITY i 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 requirement 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 requirements are less than 24 hours or a shutdown is required to comply with ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance is providcd to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performe6. 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 that may preclude completion of a surveillance. The basis for this allowance 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 surveillance. 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 limits 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, inoperable equipment has been restored to OPERABLE status. Surveillance 4.0.4 establishes the requirement that all applicable surveillance 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 condition 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 2 8 3/4.0-5

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 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 estabitshes 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 d' 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. t 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 OPERA 8LE 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 hours before being declared inoperable. 8701f SAN ONOFRE - UNIT 2 8 3/4.0-6

j i 6 -c NPF-10/15-238 ATTACHMENT "D" ) l l

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE0VIREMENTS i 3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION i 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 intervals, coanletion 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 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 STANDBY within the next 6 hours, j 2. At least HOT SHUTDOWN within the following 6 hours, and i 3. At least COLD SHUTDOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. This specification is not applicable in MODE S or 6. q 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions of the Limiting Condition for Operation are not 1 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 j be made in accordance with ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time, j This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements. Exceptions to these requirements j are stated in the individual specifications. l l SAN ONOFRE - UNIT 3 3/40-1 l

APPLICABII.ITY gjRVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during-the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for-Operation unless otherwise stated in an individual Surveillance Requirement. 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with: a.. A maximum allowable extension not to exceed 25% of the surveillance interval, and 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 OPERA 8ILITY 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 hours to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than'24 hours. Surveillance Requirements do not. have to be performed on inoperable equipment. 4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the~ Limiting Condition for Operation have been performed within the stated. surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with 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: l 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 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)(1). 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 ON0FRE - UNIT 3 3/4 0-2 D

~ 1 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a sinimum, the reactor protective instrumentation channels and bypasses of Table 3.3-1 shall be OPERA 8LE with RESPONSE TIMES as.shown in Table 3.3-2. ~ APPLICABILITY: As shown in,_ Table 3.3-1. 4 ACTION: As shown in Table 3.3-1. t SURVEILLANCE REQUIREMENTS W 4.3.1.1 Each reacidr protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MD0ES and at the frequencies shown ~ in Table 4.3-1. k 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 CALIBRATION testing of each channel affected;by bypass operation., s

4. 3.1. 3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor. trip function 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-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 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: For the CEA position isolation amplifiers: a. 1. With-120 volts AC (60 Hz) applied for at least 30 seconds across the output, the reading on the input does not exceed 0.015 volts DC. / - ~ ~ " NOV 151982 SAN CHOFRE-UNIT 3 3/4 3-1

r TA8LE 3.3 (Continued) TABLE NOTATION With the protective systes trip breakers in the closed position, the CEA drive systes capaDie of CEA withdrawal, and fuel in the reactor vessel. 0 (a) Trip may be manually bypassed above 10N of RATED THERMAL POWER; bypass shall.he automatically removed when THERMAL POWER is less than or equal to 10 7 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. (c) Tripmaybemanuallybypassedbelow10'kofRATEDTHERMALPOWER; bypass shall be sul tically removed when THERMAL POWER is greater than er. equal to 10 of RATED THERMAL POWER. During testing pursuant to Special Test Exception 3.10.3, trip may be annually bypassed below 5% et 3 RATED THERMAL POWER; bypass shall be automatically removed when THERMAL 1 v POWER is greater than or equal.to 5% of RATED THERMAL POWER. (d) Trip may be bypassed during testing pursuant to Special Test ( Exception 3.10.3. (e) See Special Test Exception 3.10.2. (f) Each channel shall.~ be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice. v. (g) Trip say be bypassed below 55% RATED THERMAL POWER. ACTION STATEMENTS ... +. ACTION 1 With the riumber 'of channels 0PERA8LE 'one less than required by the Minious Channels OPERABLE requirement, restore the - inoperable channel to CPERABLE status within 48 hours or be in

t least HOT STAN08Y within the next 6 hours and/or open the

.a .. e..:' protective systes trip breakers... ~f ';. 2 ACTION 2 With the number of channels OPERA 8LE 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. / \\. NOV 151962 SAN ONOFRE-UNIT 3 '3/4 3-4 I

a 1 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION. LIMITING CONDITION FOR OPERATION-3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERA 8tf with their trip setpoints set consistent with the values shown in the Trip 5etpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.* e APPLICA81LITY: As shown in Table 3.3-3. { I ~' ACTION: 'j With an ESFA5 instrumentation channel trip setpoint less conservative a. than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to CPERA8LE status with the trip setpoint adjusted consi6 tent with the Trip-5etpoint value.l q b. With an ESFAS instrumentation channel inoperable, take.the ACTION shown in Table 3.3-3. SURVEllt.ANCE REQUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated CPERA8LE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2. The logic for'the bypasses shall be demonstrated OPERA 8LE during th 4.3.2.2 at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated CPERA8LE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation. l 4.3.2.3_The ENGINEERED SAFETY FEATURES RESPONSE TIMC of each E shall be demonstrated to be within the Itait at least once per 18 months. Each test shall include at least one channel per function such that all j channels are tasted at least once every N times 18 months where N is the total I 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 refueling outage. Containment airborpe monitor 3RT-7804-1 or 3RT-7807-2 and associatec sampling media shall perfom these functions prior to initial criticality. From initial criticality to.the startup following the first refueling outage containment airborne monitor 3RT-7804-1 and associated sangil'ing media shall i perfom the above required functions. I O 15 l$i2 SA" -"0FRE-UNIT 3 3/4 3-13 1

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 first necessary to enable CSAS log'ic. (c) Actuated equipment only; does not result in CIAS. f The provisions of Specification 3.0.3 are not appifcable. m With irradiated 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 CPERA8LE status within 48 hours or be in at least NOT STAN08Y within the. next 6 hours and in COLD SHUTDOWN within the fellowing 30 hours. ACTION 9 - With the number of char.aels OPERA 8LE one less than the Tota Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 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. With a channel process measurement circuit that affects. multiple functional units' inoperable er in test, bypass or trip all associated functional units as listed below. Process Mea'urement Circuit Functional Unit Bypassed s 1. Containment Pressure - High Containment Pressure - High (ESF) Containment Pressure - High (RPS) 2. Steam Generator Pressure - Steam Generator Pressure - Low Low Steam Generator AP 1 and 2 (EFAS) 3. Steam Generator Level Steam Generator Level -' Low Steam Generator Level - High Steam Generator AP (EFAS) / MM M SAN ONOFRE-UNIT 3 3/4 3-19

i INSTRUMENTATION INCORE DETECTORS l LIMITING CONDITION FOR OPERATION 3.3.3.2 The incere detection system shall be OPERA 8LE with: At least 75% of all incore detector locations, abd a. b. A minimum of two quadrant 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 movable incere detector capable of mapping the j location. j l APPLICA8,ILITY: When the incore detection system is used for unitoring: j a. AZIMUTHAL POWER TILT, i b. Radial Peaking Factors, c. Local Power Density, d. DN8 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 system shall be demonstrated OPERA 8LE: By performance of a CHANNEL CHECK within 24 hours prior to its use if a. 7 or more days have elapsed since the previous check and at least once per 7 days thereafter when required for sanitoring the AZIMUTHAL POWER TILT, radial peaking factors, local power density or DN8 margin: b. At least once per 18 months by performance of. 4 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 SAN ON0FRE - UNIT 3 3/4 3-41 AMEN 0 MENT NO. 38 1

I )- U u INSTRUMENTATION SEISMIC INSTRUMENTATION" LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-7 shall be OPERA 8LE. 4 APPLICA8ILITY: -At all times. ACTION: ~ With one or more seismic monitoring instruments inoperable for'more a. 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 OPERABLE status, b. The provisions of Specifications 3.0.3 are not applicable. S SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above seismic monitoring instruments shall be. ~ demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations 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 besemat accelerations of 0.05g or greater) shall be restored to OPERA 8LE status within 24 hours and a CHANNEL CALIBRATION performed within 5 days. Data shall be retrieved from the accessible actuated instruments and analyzed to determine the segnitude of the vibratory ground action. A Special Reprt 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 OPERABLE status and a CHANNEL CALIBRATION performed the next time the plant enters MODE 3 or below. A supplemental report shall then be prepared and submitted to the Commission within 10 days pursuant to Specification 6.9.2 describing the additional data Tros these instruments. X Shared system with San Onofre - Unit 2. SAN ONOFRE-UNIT 3 3/4 3-42 $0i 1D

i ) I INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION" LIMITING' CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-8 shall.be OPERA 8LE. 4 APPLICA8ILITY; -At all times. ACTION: With one or more required meteorological monitoring channels a. inoperable for more than 7 days, prepare and submit a Special Reper; 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 channel (s) to 0PERA8LE status. b. The provisions of Specifications 3.0.3 are not' applicable. SURVEILLANCE REQUIREMENTS-4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5. ^ . e:.

~

1 J

E Shared system with San Onofre - Unit 2. I*' gg' i b SAN ON0FRE-UNIT 3 3/4 3-45

INSTRUMENTATION RADIDACTIVELIQUEEFFLUENTNONITORINGINSTRUMENTATION l J LINITING CONSI1r:J! FOR OPERATION 1 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERA 8LE with their alare/ trip setpoints set to' d ensure that the limits of Specification 3.11.1.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the. OFFSITE 005E CALCULATION MANUAL (00CN). 1 APPLICA8ILITY: At all times. ACTION: With a radioactive liquid effluent monitoring instrumentation a. channel alare/ 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 minimum number of radioactive liquid effluent monitoring instrumentation channels OPERA 8LE, take the ACTION shown in Table 3.3-12. Exert best efforts to return the instrument to. OPERA 8LE status within 30 days and, additionally,-if the inoperable instrument (s) remain inoperable for greater than 30 days, explain in s the next Semiannual Radioactive Effluent Release Report why the - inoperability was not corrected in a timely manner. The provisions of Specifications 3.0.3 and 6.9.1.136 c. are not-applicable. SURVEILLANCE REQUIREMENTS c 4.3.3.8.1 Each radioactive 11guld effluent monitoring instrumentation' channel shall be demonstrated OPERABLE 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 hours, all pumps required to be providing dilu-= tion to meet the site radioactive effluent concentration Itaits of Specifica-tion 3.11.1.1 shall be determined to be operating and providing dilution to the discharge structure. 1 i i SAN ONOFRE - UNIT 3 3/4 3-64 AMOENT NO. 46 i

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CON 0! TION FOR OPERATION l 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.* APPLICA8ILITY: As shown in Table 3.3-13 l ACTION: With a radioactive gaseous effluent monitoring instrumentation a. channel alarm / 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 instrument to OPERABLE status witnin 30 days and, additionally, if the inoperable instrument (s) remain 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. The provisions of Specifications 3.0.3 and 6.9.1.13b are not c. applicable. SURVEILLANCE REQUIREMENTS i '4.3.3.9 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.

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 refueling outage.

Containment irborne monitor 3RT-7804-1 or 3RT-7807-2 and associated sampling media shall perform these functions prior to initial criticality. From 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. JAN 11 E5 SAN ONOFRE-UNIT 3 3/4 3-69 AMENDMENT NO. 20

INSTRWENTATION LOOSE-PART DETECTION INSTRUMENTATION. LIMITING CONDITION FOR OPERATION ~ 3.3.3.10 The loose part detection systes shall be OPERA 8LE. APPLICA8ILITY: MODES 1 and 2. ACTION: With one or more loose part'detaption system channels inoperable for I a. more than 30 days, prepare and (ubmit 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 1 the channel (s) to OPERABLE status. b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.10 OPERA 8LE by performance of a:Each channel of the loose part detection sysi CHANNEL CHECK at least once per 24 hours, a. b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and CHANNEL CALIBRATION at least once per 18 months. c. 'b e I JAN 111985 SAN ONOFRE-UNIT 3 3/4 3-76 AMDOENT No. 20 )

i REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE 1 285'r LIMITING CONDITION FOR OPERATION 3.4.8.3.1 At least one of the following overpressure protection systems shall be OPERA 8LE: The Shutdown Cooling Systen Relief Valve (PSV9349) with: s. 1) A lift setting of 406 2 10 psig*, and 2) Reifef valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or, b. The Reactor Coolant System depressteized with an RCS vent of greater than or equal to 5.6 square inchci, j APPLICA8ILITY: MODE 4 when the temperature of any one RCS cold leg is less. tnan or equal to 285'F; MODE 5; N00E 6 with the reactor vessel head on. ACTION: With the SDCS Relief Valve inoperable, reduce T,,, to less than a. 200*F, depressurize and vent the RCS through a greater than or equal 1 to 5.6 square inch vent within the next 8 hours. b. With one or both SOCS Relief Valve isolation valves in a single SOCS Relief Valve isolation valve pair (valve pair 3HV9337 and 3HV9339 or valve pair 3HV9377 and 3HY9378) cTosed, open the closed valve (s)within7daysorreduceTlMaterthanorequalto56 inch to less than 200*F, depres-surize and vent the RCS through a vent within the next 4 hours. In the event either the SDCS Relief Valve or an RCS vent is used to c. 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-I ating the transient, the effect of the 50C5 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 SDCS Relief Valve shall be demonstrated CPERA8LE by: Verifying at least once per 72 hours when the SOCS Relief VaJve is a. being used for overpressure protection that SDCS Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 are open. / \\

The lift setting pressure applicable to valve temperatures of less than or equal to 130*F.

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

., h N 0",W(d' ~ REACTOR C00VWT SYSTEM 3.4.9 STRUCTURAL INTEGRITY LINITING 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. APPLICA8ILITY: ALL pWOE5 ACTION: I With the structural integrity of any ASME Code Class 1 component (s) a. 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 minimum j temperature required by NOT considerations. b. With the structural integrity of any ASIE Code Class 2 component ( 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 above 200*F.

With the structural integrity of any ASME Code C1ast 3 component (s) c. not conforming to the above requirements, restore the structural integrity of the affected component to within its Itait or isolate the affected camponent from service. SURVEILLANCE REQUIREMENTS 4.4.9 Ia' addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 1975. / SAN ON0FRE-UNIT 3 3/4 4-36

') PLANT SYSTEM 5 3/4.7.7 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION ( 3.7.7 Each sealed source containing radioactive material either in excess of 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. APPLICA81LifY: At all times.- ACTION: With a sealed source having removable contamination in excess of the a. above limit, withdraw the sealed source from use and either: 1. Decontaminate and repair the sealed source, or f 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 semple. 4.7.7.2 Test Frequencies - Each category of sealed sources (excluding startup 4 sources and fission detectors previously subjected to core flux) shall be tested at the frequencies described below, Sources in use - At least once per six months for all sealed sources a. containing radioactive material: 1. With a half-life greater than 30 days (excluding' Hydrogen 3), and 2. In any form other than gas. i / NOV 151982 SAN ONOFD9 UNIT 3 3/4 7-25 1

REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The containment purge isolation systes shall be OPEAA8LE. APPLICA81LITY: During CORE ALTERATIONS or novement of irradiated fuel within the containment. 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. SURVEILLANCE REQUIREMENTS 4.9.9 The containment' purge isolation system shall be demonstrated OPERABLE within 72 hours 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. / \\ NOV i 51982 SAN ON0FRE-UNIT 3 3/4 9-10

q REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING SUILDING POST-ACCIDENT CLEANUP FILTER SYSTEM LIMITING CON 0! TION FOR OPERATION -l 3.9.12 Two independent fuel handling building post-accident cleanup filter systems shall be OPERA 8LE. APPLICA8!LITY: Whenever irradiated fuel is in the storage pool. ACTION: j With one fuel handling building post accident cleanup filter system a. inoperable, fuel' movement within the storage pool or operation of fuel handling aschine over the storage pool may proceed provided the QPERABLE fuel handling building post-accident cleanup filter system-1 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. j b. With no fuel handling building post-accident cleanup filter system OPERASLE, 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 OPERA 8LE status. SURVEILLANCE REQUIREMENTS i 4.9.12 The above. required fuel handling building post-accident cleanup filter systems shall be demonstrated OPERA 8LE: i At least once per 31 days on a STAGGERED TEST SA515 by initiating, a. from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours with the heaters on, b. At least once per la months or (1) after any structural maintenance-on the HEPA f11ter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by: i ) i i SEP 3 0 GB5 SAN ONOFRE - UNIT 3 3/4 9-13 AMEN 0 MENT NO. 25

v RADI0 ACTIVE EFFL',ENTS 005E LIMITING CONDITION FOR OPERATION ] l i 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site (see Figure 5.1-4) shall be limited: o During any calendar quarter to less than or equal to 1.5 mrom to the a. , total body and tg 1_ ss than or equal to 5 mrom to any organ, anc e b. During any calendar year to less than or equal to 3 arem to the total body and to less than or equal to 10 ares to any organ. APPLICA8ILITY: At all times. ACTION: 'S With the calculated dose from the release of radioactive materials a. 1 in liquid 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 1eport which identifies the cause(s) for exceeding the limit (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 are not appitcable. SURVEILLANCE REQUIREMENTS 4.11.1.2 Dose Calculations. Cumulative dose contributions from liquid effluents snail De determined in accordance with the 00CM at -least once per 31 days, f- };0*.' 1 U UI-esem SAN ONOFAE-UNIT 3 3/4 11-5

l RADIOACTIVE EFFLUENTS 1 l LIQUID WASTE TREATMENT -t LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment systes shall be OPERABLE. The appropriate portions of the system shall be used to reduce the radioactive saterials in liquid wastes prior to their discharge when'the projected doses 4 due to the liquid effluent from the site (see Figure 5.1-4) when averaged over e 31 days, would exceed 0.06 ares to the totai body or 0.2 ares to any organ." APPLICA8ILITY: At all times. ACTION: With the liquid radwaste treatment systes inoperable for more than a. 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 ths j Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following infomation: 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 Summary description,of action (s) taken to prevent a recurrence. 3. b. The provisions of Specifications 3.0.3 are not applicable. SURVEILLANCE REQUIREMENTS i 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 radwasta treatment system shall be demonstrated OPERA 8LE by operating the liquid radwaste treatment systen equipment for at least 15 minutes at least once per 92 days unless the liquid radwaste systes has been utilized to process radioactive liquid affluents during the previous 92 days. A Per reactor ujtit HOV 15 B02 SAN ONOFRE-UNIT 3 3/4 11-6

i l ( RADI0 ACTIVE EFFLUENTS LIQUID HOLDUF TANKS ) LIMITING CONDITION FOR OPERdTION The quantity o' radioactive material contained in each outside 3.11.1.4 f temporary tank shall be limited to less than or equal to 10 curies, exclucing tritiue and dissolved or entrained noble gases. e APPLICA8ILITY: At all times. ACTION: I With the quantity of radioactive asterial in any outside temporary a. tank exceeding the above. limit, fenediately suspend all additions of ] radioactive meterial to the tank and within 48 hours reduce the tank 1 contents to within the lieft. b. TheprovisionsofSpecifications3.0.3arenotapplicad,1e. j t SURVEILLANCE REQUIREMENTS f 4.11.1.4 The quantity of radioactive saterial 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. NOV 151982 1 SAN ONOFRE-UNIT 3 3/4 11-7 l' L

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~ l ( RADI0 ACTIVE EFFLUENTS 005E - N00LE GASES LIMITING CONDITION 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 mrad for gamma radiation and less than or-equal-to 40-erad for beta-radiation and, 1 b., During any calendar year: Less than or equal to 10 erad for gamma ( radiation and less than or equal to 20 arad for beta radiation, j APPLICA81LITY: At all times, i ACTION t u With the calculated air dose from radioactive noble gases in gaseous a. effluents exceeding any of the above limits, in Iteu of any otherg report required by Specification 6.9.1, prepare and submit to the-( Comeission 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 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 are not applicable. i i 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 per 31 days. J' ~ .HOV 151982 u 1 SAN ONOFRE-UMIT 3 3/4 11-12

RA010ACTRVE EFsLUENTS DOSE - RADI0 IODINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM AND TRITIUM LIMITING CON 0! TION FOR OPERATION 3.11.2.3 The dose to an individual from tritius, radiofodines and radioactive materials in particulate form 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 t's 7.5 ares to any organ and, b. During any calendar year: Less than or equal to 15 ares to any targan. } Less than 0.1% of the limits of 3.11.2.3(a) and (b) as a result c. of burning contaminated oil. APPLICABILITY: At all times. ACTION: With the calculated dose from the release of tritium, radiciodines, a. and radioactive materials in particulate form, with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, in Iteu of any other report rsquired by Specification 6.9.1, prepare and submit to the Consission within 30 days, pursuant to Specification 5.9.2, 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 previsions of Specifications 3.0.3 are not app 1tcable. SURVEILLANCE REQUIREMENTS 4.11.2.3 Dose Caleviations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance 1 with the 00CM at least once per 31 days. l f l SAN ON0FRE-UNIT 3 3/4 11-13 AMENOMENT No. 41 i

o f ) / I RADI0 ACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT 4 _d 1 A, LINITING CON 0! TION FOR OPE" RATION ^ 3.11.2.4 The GASEQUS RADWASTE TREATMENT SYSTEM and the VE TREATMENT SYSTEM shall be OPERA 8LE. The appropriate portions of the GASE0Vs RADWASTE TREATMENT SYSTEM shall be used to reduce rauS ctive mat a gaseous waste prior to their discharge when the projeded gaseous effluerd air d doses due to gaseous affluent releases from the site (see Figure 5.1-3), when - 4' averaged over 31 days, would exceed 0.2 erad for gamma radiation and 0.a arad for beta radiation..The appropriate portions of the VEffrILATION TXHAUST TREATMENT SYSTEM shall be used to reduc's radioactive eaticitit 'In gaseous -- -j wasta prior to their discharge when the projected desem due to gaseous effluent releases from the site (see Figure 5.1-3) whe.9 averaged over 31 days would exceed 0.3 ares to any organ.", APPLICABILITY: At all times. ACTION: I With the GASE005 RADWASTE TREATMEWT USTEM and/or the VENTILA a. EXMAUST TREATMENT SYSTEM inoperabib fOr more than 31 days or witA I gaseous waste being discharged w!thout' treatment and in excess of the above limits, in lieu of any other "etunt required by>1pecifica-tion 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, 'a Spec 1M Report which includes the following information: 1. Identification of the inopsrable:41uty9 ant or subsystems snd the reason for inoperability, l o ~ 2. Action (s) taken to restore the inoperab1A equ r. tnt to OPERABLE status, and , p (\\ / 'iT 3. Suasary description of action (s) taken u pHvbrt a recurrence. b. The provisions of Specifications'3.0,3 sre not applicable. SURVEILLANCE REQUIREMENTS ,s ^ .= \\, 4.11.2.4.1 Dose:, due to gaseous releases fra:t the site sM1 be pre.;ected at least once per 31 days, in accordanca with g.h. 00CM.', 1 i 1 q F 4.11.2.4 2 The GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATIC TREATMENT SYSTEM shall be demonstrated OPERABLE by operating the CAS?/ E RA0 WASTE TREATMENT SYSTEM equipment and WNTILATION EXMUST TREATMENf MS equipment for at least 15 minutes, at 11.tst once per 92-days unless' kne appropriate system has been utilized to process radioactive gaseous effluents (! 1 f during the previous 92 days. 4 A These doses are per reactor unit, f' g*g i 5 bbl. 1 SAN ONOFRE-UNIT 3 3/4 11-14 \\ l iy . t

j[ - .), y.. ( RADI0tCTIVE EFFLUENTS EXPT,051VE GAS MIXTURE J i .) /,,IMjTINGCONDITIONFOROPERATICL '( ,/ i 3 11.2.5 The concentration of oxygen in the waste gas holdup system shall be huited to less than or equal to 2% by volume whenever the hydrogen concentration excwe 4% by volume. i t APPLICA81LITY: At all times. ACTION: s With the concentration of citypsn in the wasts gas holdup system a. greater than 5 by volume but,% than or eqval to 4% by volume, s restore the secantration of oxygen to within the ifait within 48 hours. / s i b. With the conce'ntration of oxygen in the waste gas holdup system greater thap 4% by volume, immediately suspend all additions of g 'T waste gases A0 the system and reduce the concentration of oxygen th / by volume within 47, hours.1ess than 4% by va',use within one hour a e f. I The prov'ssions of Specification 3.0.3 are not applicable. c. ,., e r LRVEILLAbCE RECU.RW/MS ./. 8.t.2.M.The concentrations of'aydwgon and oxygen in t> waste gas holdup syi tes '.n.a71 De determinad to be within the above limits t / continuously moni-taping the waste gases'in the waste gas holduc syst m with the hydrogen and oxygernor,itorsrequiredOPERA8LEbyTaoles3.3-13;c93pecif$ cation 3.3.3.9. r i t

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- a, { ' y- .v J ( RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADIOACTIVE WASTE !LIMITINGCONDITIONFOROPERATION !n - \\ \\ l l 3.11.3 The solid radwaste system shall be OPEAABLE and used, as applicable in } accordance with a PROCESS CONTROL PROGRAM, for the SOLIDIFICATION and i packaging of radioactive wastes to ensure meeting the requirements of 10 CFR Part 20 anc of 10 CFR Part 71 prior to shipment of radioactive wastcs from the site. APPLICA8ILITY: At all times." ACTION: With the packaging requirements of 10 CFA Part 20'and/or 10 CFR a. T Part 71 not satisfied, suspend shipments of defectively packaged solid radioactive wastas from the site.. Withthesolidradwestesysteednoperableformerethen31 days,h b. lieu of any other report required by Specification 5.9.1, prepareg i and submit to the Commission within 30 days pursuant to Specificat l,' tico 6.9.2 a special Report which includes the following information: \\ [ 1. Identification of the inoperable equipment or sesystems and the reason for inoperability. 2. Action (s) taken to restors the inoperable equipment to OPERA 8LE status. 3. A description of the alternative used for SOLIDIFICATION and packaging of radioactive wastes, and 4. Summary description of action (s) taken to prevent a recurrence. ~.Thi. CNvisions of Specifications 3.0.3 are not applicable. c. i SyU,rJ6!Lth il REQUIRE W S 4.11.3.1 Tim wiid ra'dweste syster shall be demonstrated OPERA 8LE at least once per 92 days by: Operating the solid radwaste syster at least once in the previous a. 92 days in accordance with the PROCESS CONTROL PROGAAM, or b. Verificathin of the existance of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL { PROGRAM. / WE~5pnet fication 6.13.1. gy i 51982 . SAN ONOFRE-UNIT 3 3/4 11-17 A i

b. y [ RADI0 ACTIVE EFFLUENTS s 3/4. n.4 TOTAL 005E $r LIMITING CopWITION FOR OPERATION 3.11.4 The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 seem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 area) ( ever 12 consecutive months. APPLICA8ILITY: At all times. ACTION: With the calculated doses from the release of radioactive materials a. in liquid or gaseous affluents exceeding twice the.11mits of Specification 3.11.1.2. a. 3.11.1.2.b, 3.11.2.2.a. 3.1T.2.2.b. 3.11.2.3.a. or 3.11.2.3.b, in lieu of any othairc report. required Specification 6.9.1, prepare and submit a Special Supert to the Director. Nuclear Reactor Regulation, U.Si Nucteer Anguiatory Commission, Washington, D.C. 20555, within 30 dayr,totich defi i I [ the corrective action to be taken to reduce subsequest releases to prevent recurrence of exceeding the limits of Specification 3.n.4. This Special Report shall include an analysis which estimates the radiation exposure (dose) to a member of the pelic from uranium fuel cycle sources (including all effluent pathueys and direct, radiation) for a 12 consecutive month period'.that includes the release (s) covered by this report. If the estimated dose (s) exceeds the limits of Specification 3. n.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 provisions of 40 CFR 190 and including the specified information of f 190.n(b). Submittal of the report is considered a timely request, and a variance is granted until 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 require-ments 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 not applicable. i SURVEILLANCE REQUIREMENTS 4.11.4 Dose Calculations Cumulative dose contributions from liquid and gaseous affluents shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with ttfe 00CN. NOV i 5 B82 SAN ONOFRE-UNIT 3 3/4 11-19

i i / 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING j 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental sonitoring program shall be conducted as specified in Table 3.12-1. APPL.ICA8ILITY: At all times. ACTIOM: With the radiological environmental monitoring progran not being -- a. conducted as specified in Table 3.12-1, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Coe-mission, in the Annual Radiological Operating Report, a description of the reasons for not conducting t.he program as required and the plans for preventing a recurrence. b. With the level of radioactivity in an environmental sampling medip 1 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 Commission within, 30 days from the end of the affected calendar quarter a Report g 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: concentration.(1), concentration (2) + ***> 1.0 I limit level (1) limit level.(2) Wen radionuclides other than those in Table 3.12-2 are detected and are the result 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 Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the sessured 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. With fresh leafy vegetable samples or fleshy vegetable samples unavail-c. able from 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 from which samples were unavailable say then be deleted from those required by T=Ma 't 12-1, provided the locations from 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 applicable., NOV 15 BB2 SAN ONOFRE-UNIT 3 3/4 12-1 ~ ' "

I =*a ( RADIOLOGICAL ENVIRONMENTAL MONITORING-3/4.12.2 LAW USE CENSUS LIMITING COM ITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location - of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetahles in each of the 16 meteorological sectors within a distahce of five miles.

For. elevated releases as defined in Regulatory Guide 1.1M, Revision 1 July 1977, the lane use census shall also identify the locations of all milk animals and all gardens of greater than 500 square feet producing fresh leafy vegetables in' each of the 15 meteorological sectors within a distance of three siles. ~ APPLICA81LITY: At all times. ACTION: With a land use census identifying a location (s) which yields's a. calculated dose or dose commitment 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 Commission 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-8 calculated dose or dose commitment via the same exposure pathway' g 20 percent greater 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 5.9.1. prepare '. and submit to the Cammission within 30 days, pursuant to Specifica< tion 5.9.2, a Special Report which identifies the new location. Th'e new location shall be added to the radiological environmental monitoring program within 30 days. e The sampling location, excluding the control station location, having the lowest calculated dose or dose commitment 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. The provisions of Specifications 3.0.3 are not applicable. c. SURVEILLANCE REQUIRB etTS 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 results, such as by a door-to-door survey, serial survey, or by consulting local agriculture authorities. " Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest 0/Q in lieu of the garden census. / Key 15 BE SAN ONOFRE-UNIT 3 3/4 12-11

y. ,4 .o - ( RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERt.A80RATORY COMPARISON PROGRAM .~ y. LIMITINGC'lkf0!TIONFOROPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been kpproved by the Comeission. APPLICA8ILITY: At all times. ACTION: ' With analyses not being performed as required above, report the a. corrective actions taken to prevent a recurrence to the Commission-in the Annual Radiological Environmental Operating Report. s b. The provisions of Specifications 3.0.3 are not app 11 cable. jl SURY G LANCE REQUIREMENTS / 4.12.3 A senary of the results obtained as part of the above' required Interlaboratory Comparison Program and in accordance with the _00CM shall be included in the Annual Radiological Environmental operating Report. 3 j j / j s e eggs W NOV 15 at? SAN ONOFRE-UNIT 3 3/4 12-12

s i 3/4.0 APPLICABILITY [ } BASES } Specification 3.0.1 throuch 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 of federal Regulations, 10 CfR 50.36(c)(2): " Limiting conditions for operation are the lowest functional 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 f; permitted by the technical specification until the condition can be met." a Specification 3.0.1 establishes the. Applicability statement within_each individual specification as the requirement for when (i.e., in which q OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.1The ACTION requirements establish those remedial measures that must be taken within specified time 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 il 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-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 OPERA 8LE 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 MODE 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 requirements 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 requireinents, 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. SAN ON0fRE - UNIT 3 8 3/4.0-1

1 3/4.0 APPLICABILITY BA}ES (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 within the specified time interval constitutes compliance with a specification and (2) completion 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. Specification 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 specificaT1y addressed by the associated ACTION requirements. The purpose of this specification is to delineate the time 1 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 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 requirements are completed, the shutdown may be terminated. The time limits of the ACTION requirements are applicable j 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 mis'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 hours for the plant to be in the COLD SHUTDOWN 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 STANDBY is reached in 2 hours, the time allowed to reach HOT SHUTDOWN is the next 11 hours because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours. 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 ON0fRE - UNIT 3 8 3/4.0-2

l 3/4.0 APPLICABILITY BASES (Con't) .j The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one i 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 1 time than specified,the difference may be added to the allowable outage time l 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 Cortdition for Operation is not met in a lower MODE of operation. l 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 w'ien 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 restoring 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, l entry into an OPERATIONAL MODE or other specified condition may be made in accordance 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. l 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): " Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met." j SAN ONOFRE - UNIT 3 8 3/4.0-3 i

3/4.0 APPLICABILITY BASES (Con't) Specification 4.0.1 establishes the requirement that surveillance must be { performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise 3 stated in an individual Surveillance Requirement. The purpose of this specification is to ensure that surveillance 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 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 -i interval for Surveillance Requirements may be extended. Item a. permits an. allowable extension for the normal surveillance interval to facilitate i 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 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 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 OPERA 8LE 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 OPERA 8LE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This 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 from 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

R .) -) 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 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. If the allowable outage time limits of the ACTION requirements are less than 24 hours 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 j in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements 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 that may preclude completion of a surveillance. The basis for this allowance 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 surveillance. 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 limits 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 inoperable equipment has been restored to OPERABLE status. Surveillance 4.0.4 establishes the requirement that ali applicable surveillance 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 condition 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

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 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 Commissicn. 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 intervice inspection and testing activities. Under the terms of this specification, the more restrictive requirements of 4 the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda. The requirements of Specification 4.0.4 i 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 hours before being declared inoperable. 8701f l l l SAN ON0FRE - UNIT 3 8 3/4.0-6 ) l _ - -}}

ML20237F052

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