ML20101R654

Amends 31 & 20 to License NPF-10 & NPF-15,respectively, Modifying Tech Specs Re Radioactive Effluent Monitoring Instrumentation

ML20101R654
Person / Time
Site:	San Onofre
Issue date:	01/11/1985
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20101R658	List: ML20101R654 ML20101R672
References
TAC-54714, TAC-54715, TAC-54716, TAC-54717, TAC-54718, TAC-54719, TAC-54720, TAC-54721, NUDOCS 8502040838
Download: ML20101R654 (66)

Text

{{#Wiki_filter:c, =.. gg, ~ -..x, 3 ~ .. h [o UNITED STATES 'g .8 NUCLEAR REGULATORY COMMISSION o g y WASHINGTON, D. C. 20555 / SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET N0. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-10 1. The Nuclear Regulatory Comission (the Comission) has found that: A. The applications for amendment to the license for San Onofre Nuclear Generating Station, Unit 2 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The' City of Anaheim, California (licensees) dated March 2 and April 2, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations 'as set forth in 10 CFR Chapter I; B. The. facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the Comission; C. .There is reasonable assurance: (i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; -D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; OhMg PDR

_3 ~ ~

== ~ ~ ~ . E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2..

Accord'ingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows: (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Append.ix B, as revised throuah Amendment No. 31, are hereby incoroorated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 3. This amendment is' effective as of the date of issuance and shall be fully implemented by January 31, 1985. FOR THE NUCLEAR REGULATORY COMMISSION g L George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing

Attachment:

Chances to the Technical Specifications Date'of Issuance: January 11, 1985 d

' ~ ~ - x Januzry 11, 1985 ~ ' 3-ATTACHMENT TO LICENSr %MENDMENT N0. 31 FACILITY OPERATING LICENSE NO. NFF-10 DOCKET NO. 50-361 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages a.e identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages. Amendment Paaes Ovhrleaf Pages v 3/4 3-18 3/4 3-17 3/4 3-21 3/4 3-22 3/4 3-25 3/4 3-26 3/4 3-33 3/4 3-34 3/4 3-35 3/4 3-36' 3/4 3-37 3/4 3-38 3/4 3-39 3/4 3 40 3/4 3-51 3/4 3-52 3/4 3-53 3/4 3-53a 3/4 3-54 3'/4 3-55 3/4 3-56 3/4 3-68 3/4 3-67 3/4 3 - 3/4.3 -

3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75

-3/4-3-76 )

p ' I $l TABLE 3.3-3 (Continued) z E! ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION NI MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS-TO TRIP OPERABLE MODES ACTION 9. CONTROL ROOM ISOLATION (CRIS) a. Manual CRIS (Trip Buttons) 2 1 1 All 13*# b. Manual'SIAS (Trip Buttons) 2 sets of 2/ unit 1 set of 2 2 sets of 2/ unit 1,2,3,4 8 c. Airborne Radiation i. Particulate / Iodine 2 1 1 All 13*# ii. Gaseous 2 1 1 All 13*# s 7: d. Automatic Actuation Logic 1/ train 1 1 All 13*# v b 10. T0XIC GAS ISOLATION (TGIS) a. Manual (Trip Buttons) 2 1 1 All 14*#, 15*# b. Chlorine - High 2 1 1 All 14*#, 15*# c. Ammonia - High 2 1 1 All 14*#, 15*# d. Butane / Propane - High 2 1 1 All 14*#, 15*# e. Carbon Dioxide - High 2 1 1 All 14*#, 15*# f. Automatic Actuation Logic 1/ train 1 1 All 14*#, 15*#

i. s TABLE 3.3-3 (Continued)' z j EN61NEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 5 MINIMUM ch' TOTAL NO. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION N 11. FUEL HANDLING ISOLATION (FHIS) a. Manual (Trip Buttons) 2 1 1 16*# b. Airborne Radiation

i. -Gaseous 2

1 1 16*# ii. Particulate / Iodine 2 1 1 16*# c. Automatic Actuation Logic 1/ train 1 1 16*# 12. CONTAINMENT PURGE ISOLATION (CPIS) w? a. Manual (Trip Buttons) 2 1 1 6 17b*# b. Airborne Radiation (2RT7804-] or 2RT7807-2) i. Gaseous 2 1 1 1,2,3,4 17a 6 17b*# ii. Particulate 2 1 1 1,2,3,4 17a 6 17b*# iii. Iodine 2 1 1 6 17b*# c. Containment Area Radiation (Gamma) 2 1 1 1,2,3,4 17 (2RT7856-1 or 2RT7857-2) 6 17b*# d. Automatic Actuation Logic 1/ train 1 1 1,2,3,4 17

(

6 17b*# 6, o M

D Table 3.3-3 (Continued) TABLE NOTATION With the number of channels OPERABLE less than required by the ACTION 13 minimum channels OPERABLE requirement, within 1 hour initiate and maintain operation of the control room emergency air cleanup system in the emergency (except as required by ACTIONS 14,15) mode of operation. ACTION 14 With the number of channels OPERABLE one less than the total l number of channels, restore the inoperable channel to OPERABLE status within 7 days or within the next 6 hours initiate and maintain operation of the control room emergency air cleanup system in the isolation mode of operation. With the number of channels OPERABLE less than required by the ACTION 15 minimum channels OPERABLE requirement, within 1 hour initiate and maintain operation of the control. room emergency air cleanup system in the isolation mode of operation. ACTION 16 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12. With the number of channels OPERABLE less than required by the ACTION 17 minimum channels OPERABLE requirement, operation may continue provided that the purge valves are maintained closed. ACTION 17a - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1. (Mode 1, 2, 3, 4 only) ACTION 17b - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, close each of the contain-ment purge penetrations providing direct access from the contain-ment atmosphere to the outside atmosphere. o SAN ONOFRE-UNIT 2 3/4 3-21 Amendment No. 31

us e Q TA8LE 3.3-4 N 8 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES E M ALLOWABLE N FUNCTIONAL UNIT TRIP VALUE VALUES 1. SAFETY INJECTION (SIAS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Containment Pressure - High 5 2.95 psig i 3.14 psig c. Pressurizer Pressure - Low 1 1806 psia (1) 1 1763 psia (1) d.' Automatic Actuation Logic Not Applicable Not Applicable 2. CONTAIPMENT SPRAY (CSAS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Containment Pressure -- High-High 1 16.14 psig 5 16.83 psig m S c. Automatic Actuation Logic Not Applicable Not Applicable Y g 3. CONTAINMENT ISOLATION (CIAS) a. Manual CIAS (Trip Buttons) Not Applicable Not Applicable b. Manual SIAS (Trip Buttons)(5) Not Applicable Not Applicable c. Containment Pressure - High 1 2.95 psig 5 3.14 psig d. Automatic Actuation Logic Not Applicable Not Applicalsle 4. MAIN STEAM ISOLATION (MSIS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Steam Generator Pressure - Low 1 729 psia (2) 1 711 psia (2) c. Automatic Actuation Logic Not Applicable Not Applicable 5. RECIRCULATION (RAS) a. Refueling Water Storage Tank 18.5% of tap span 19.27% 1 tap span 2 17.73% b. Automatic Actuation Logic Not Applicable Not Applicable

'9 vs 3E ' TABLE 3.3-4 (Continued) hk ENGINEERED SAFETY FEATURE ACTUATION' SYSTEM INSTRUMENTATION TRIP VALUES

L T

E ALLOWABLE E3 FUNCTIONAL UNIT TRIP VALUE VALUES m 11. FUEL HANDLING ISOLATION (FHIS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Airborne Radiation

i. Gaseous 5 1.3 x 102 cp,**

5 1.4 x 102 cpm ** ii. Particulate / Iodine 5 5.7 x 104 cpm ** 5 6.0 x 1)* cpm ** c. Automatic Actuation Logic Not Applicable Not Applicable T D? 12. CONTAINMENT PURGE ISOLATION (CPIS) a. _ Manual (Trip Buttons) Not Applicable Not Applicabie b. Airborne Radiation i. Gaseous (6)(7) (6)(7) ii. Particulate (6)(7) (6)(7) iii. Iodine (6)(7) (6)(7) h c. Containment Area Radiation (Gamma) < 325 mR/hr (MODES 1-4) < 340 mR/hr (MODES 1-4) 3 2.4 mR/hr (MODE 6) 52.5mR/hr(MODE 6) d. Automatic Actuation Logic Not Applicable Not Applicable E. I 9

_y. vs E -TABLE 3.3-4 (Continued) 'O l{ TABLE NOTATION Ae 1 25 (1) Value may be decreased manually, to a minimum of greater than or equal to 300 psia, as pressurizer pressure is reduced, provided the margin between the pressurizer and this value is maintained at -d less than or equal to 400 psia;* the setpoint shall be increased automatically as pressurizer pressure os is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automatically removed,whenever pressurizer is greater than or equal to 400 psia. (2) Value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached. (3) % of the distance between steam generator upper and lower level instrument nozzles. s (( (4) Inverse time relay set value 3165V, trip will occur within the tolerances specified in Figure 3.3-1 g, for the range of bus voltages. e (5) Actuated equipment only; does not result in CIAS. (6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alare/ trip should an inadvertent release occur. (7) Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 2RT-7804-1 shall be determined by the 00CM. AVariable setpoints are for use only during normal, controlled plant heatups and cooldowns. M AA Above normal background. Si 5 e

r . w J TABLE 4.3-2 (Continued) ENGINEERED SAFETY' FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o 55 CHANNEL MODES FOR WHICH 5E ' CHANNEL-CHANNEL FUNCTIONAL SURVEILLANCE - (( FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED 25. U 11. FUEL' HANDLING ISOLATION (FHIS) no a. Manual (Trip Buttons). N.A. N.A. R N.A. b. Airborne Radiation

i. Gaseous S

R M ii. Particulate / Iodine S R M c. Automatic Actuation Logic N.A. N.A. R(3) 12. CONTAINMENT. PURGE-ISOLATION (CPIS) a. Manual (Trip Buttons) N.A. N.A. R N.A. b. Airborne Radiation i. Gaseous S R M 1,2,3,4,6 EI ii. Particulate W R M 1,2,3,4,6 iii. Iodine W R H 6 i' c. Containment Area Radiation U$ (Gamma) S R M 1,2,3,4,6 d. Automatic Actuation Logic N.A. N.A. R (3) 1,2,3,4,6 TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS. (2) Deleted. (3) Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation relay and verification of the OPERABILITY of each initiation relay. g (4) A subgroup relay test shall be performed which shall include the energization/de-energization of each g subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays exempt from testing g during plant operation shall be limited to only those relays associated with plant equipment which cannot be operated during plant operation. Relays not testable during plant operation shall be tested m E during each COLD SHUTDOWN exceeding 24 hours unless tested during the previous 6 months. !5 (5) Actuated equipment only; does not result in CIAS. g With irradiated fuel in the storage pool.

wT-r-O6 1 INSTRUMENTATION 3/4.3;3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be'0PERABLE with their alarm / trip setpoints within the oecified limits. APPLICA8ILITY: As shown in Table 3.3-6.* ACTION: a. With a radiation monitoring channel alarm / trip setpoint exceeding the -value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable. b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6. \\; _c.- The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. t SURVEILLANCE REQUIREMENTS t I 4.3.3.1 'Each radiation monitoring instrumentation channel shall be demonstrated l OPERABLE by the performance of.the CHANNEL CHECY., CHANNEL CALIBRATION and CHANNEL

FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.

"SeeSpecialiestException3.10.5. SAN ONOFRE-UNIT 2 3/4 3-34 AMENDMENT NO. 31

.w TABLE 3.3-6 g RADIATION MONITORING INSTRUMENTATION-o MINIMUM k CHANNELS . APPLICABLE ALARM / TRIP MEASUREMENT g INSTRUMENT , OPERABLE MODES SETPOINT RANGE ACTION 1. Area Monitors [ . a. Containment - High 2 ^ 1, 2, 3 10 R/hr 1-10s R/hr 18, 18a Range 4 10 R/hr 19 (2RT-7820-1 and 2RT-7820-2) b. Containment - Purge 1 1,'2, 3, 4 10 1-105 mR/hr 17 Isolation 6' 17b (2RT-7856-1 or 2RT-7857-2) c. Main Steam Line 1/line 1, 2, 3 1 mR/hr (low); 10 1-104'mR/hr; 18 y A Channel consist of 1 R/hr (high) 2RT-7874A.and 4 1 mR/hr (low); 19 w 2RT-7875A or 1 R/hr (high) w 2RT-78748 and 2RT-78758 2. Process Monitors 1 a. Fuel Storage Pool Airborne (2RT-7822-1 or 2RT-7823-2) i. Gaseous 1 101 -107 cpm 16 ii. Particulate / Iodine 1 101 -107 cpm 16 b. Containment Airborne (2RT-7804-1 or e 2RT-7807-2) 5 i. Gaseous 1 1,2,3,4 101 - 107 cpm 17a 5 6 17b M ii. Particulate 1 1,2,3,4 101 - 107 cpm 17a 4 6 17b i g iii. Iodine 1 6 101 - 107 cpm 17b c. Control Room Airborne M (2/3 RT-7824-1 or 2/3 RT-7825-2) ~ i. Particulate 1 All 101 - 107 cpm 13 ii. Gaseous 1 All 101 107 cpm 13

.s ~ d TABLE 3.3-6 (Continued) a j ~ RADIATION MONITORING INSTRUMENTATION m MININJM E... CHANNELS APPLICABLE. ALARM / TRIP-MEASUREMENT .h INSTRtMENT . OPERABLE MODES SETPOINT RANGE ACTION i [ .3. Noble Gas Monitors ) a. Plant Vent Stack Wide Range. ~(2RT-7865-1 or 3RT-7865-1)- 1 1,2,3 ' Per 00CM 10 7-105 pCi/cm3 19 Normal ^ Range (2RT-7865-1, 3RT-7865-1 or I 2/3RT-7808) 11 4 Per 00CM 10 8-10 1 pCi/cm3 19 w1

b. - Condenser Evacuation System Wide Range w

J. (2RT-7870-1) 1 1,2,3(1) Per 00CM 10 7-10s pCi/cm3 19 m Normal Range (2RT-7818 or 1 4 (1) Per 00CM 10 s-102 pCi/cm3 19 -l 2RT-7870-1) h , 5 (1) With any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed. j E l 5 5 ~

^ TABLE 3.3-6 (Continued) ACTION STATEMENTS ACTION 13 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, within 1 hour initiate and maintain operation of the control room emergency air cleanup system in the emergency (except as required by ACTIONS 14, 15) mode of operation. ACTION 16 With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12. ACTION 17 .With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, operation may continue provided that the purge valves are maintained closed. ACTION 17a - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1. (Mode 1, 2., 3, 4 only) ACTION 17b - With the-nunber of channels OPERABLE less than rt: quired by the I minimum channels OPERABLE requirement, close eech of the contain-ment purge penetrations providing direct access from the contain-ment atmosphere to the outside atmosphere. ACTION 18 With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirer;nt, either restore the inoperable channel to OPERABLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours. ACTION 18a - With both channels inoperable, restore the inoperable channel (s) to OPERABLE status within 48 hours, or be in HOT SHUTOOWN within the next 12 hours. ACTION 19 With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel (s) to OPERABLE status within 72 hours, or: 1) Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2) Prepare and submit a Special Report to the Commission pur-suant to Specification 6.9.2 within 14 days following initi-ation of the pre planned alternate outlining the action .taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

1. In accordance with Engineered Safety Feature trip value specified by Table 3.3-4.

• With irradiated fuel in the storage pool.

ACTIONS 13, 16, 17, 17a and 17b are repeated from Table 3.3-3 for reference. SAN ONOFRE-UNIT 2 3/4 3-37 AMENDMENT NO. 31

m E TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS g T CHANNEL MODES FOR WHICH E CHANNEL CHANNEL FUNCTIONAL-SURVEILLANCE -4 INSTRUMENT . CHECK . CALIBRATION TEST. IS REQUIRED m 1. Area Monitors a. Containment - High Range S R M 1,2,3,4 (2RT-7820-1, 2RT-7820-2) b. Containment - Purge Isolation S. R M 1,2,3,4,6 (2RT-7856-1, 2RT-7857-2) c. Main Steam Line S R M 1,2,3,4 'R (2RT-7874A, 2RT-7875A, [ 2RT-7874B, 2RT-78758) h 2. Process Monitors a. Fuel Storage Pool Airborne (2RT-7822-1, 2RT-7823-2) i. Gaseous ii. Particulate / Iodine b. Containment Airborne (2RT-7804-1, 2RT-7807-2) i. Gaseous 1,2,3,4,6 ii. Particulate 1,2,3,4,6 iii. Iodine 6 1 h c. Control Room Airborne g (2/3RT-7824-1, g 2/3RT-7825-2) 3 i. Particulate All ii. Gaseous All en

~> R vs $E ETABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH SE CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE El INSTRUMENT CHECK CALIBRATION TEST. IS REQUIRED ro PROCESS MONITORS (Continued) 3. Noble Gas Monitors a. Plant Vent Stack _D R Q 1, 2, 3, 4 (2RT-7865-1, 3RT-7865-1, 2/3RT-7808) b. Condenser Evacuation System D P. Q 1, 2, 3, 4(1) j' (2RT-7870-1, 2RT-7818-1) Y e; NOTES:

1. n accordance with Table 4.3-2 surveillance requirements for these instrument channels.

I With irradiated fuel in the storage pool. (1) With any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed. 9e n 8

l -3675 110 VOLTS 100 U E s N W I hw 10 f I / / / / ~

1. 280,0 VOLTS 2.610.13 SECONDS O VOLTS 1.01.05 SECONDS 1.0 2400 2800 3200 3600 4000 BUS VOLTAGE Figure 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING k

SAN ONOFRE-UNIT 2 3/4 3-40

hk;. -f S4 ~ . INSTRUMENTATION ' ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitcring instrumentation channels shown in Table 3.3-10 shall be OPERABLE. APPLICABILITY: MODES'1,-2 and 3.* ACTION: a. With one or more accident monitoring channels inoperable, take the ACTION shown in Table 3.3-10. b. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.6. Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performancelof the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. t "See Special Test Exception _3.10.5. SAN ONOFRE-UNIT 2 3/4 3-51 Amendment No. 31 2..

vs 'E-TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION 2 '? E REQUIRED MINIMUM Z NUMER OF' -CHANNELS m INSTRUMENT CHANNELS OPERABLE ACTION 1. . Containment Pressure - Narrow Range 2 1 20, 21 .2. Containment Pressure'- Wide Range 2 1 20, 21 3. Reactor Coolant Outlet Temperature - 2 1 20, 21 .THot. I I*"9') 4. Reactor Coolant Inlet Temperature - 2 1 20, 21 T I "*"9') Cold 5. Pressurizer Pressure - Wide Range 2 1 20, 21 2 1 20, 21 g 6. Pressurizer Water Level 7. Steam Line Pressure 2/ steam 1/ steam 20, 21 generator generator 8. Steam Generator Water Level Wide Range 2/ steam 1/ steam 20, 21 generator generator 9. Refueling Water Storage Tank Water Level 2 1 20, 21 10. Auxiliary Feedwater Flow Rate 1/ steam N.A. 20 generator 11. Reactor Coolant System Subcooling 2 1 20, 23 Margin Monitor h 12. Safety Valve Position Indicator 1/ valve N.A. 20 l 13. Spray System Pressure 2 1 20, 21 h 14. LPSI Header Temperature 2 1 20, 21 g 15. Containment Temperature 2 1 20, 21 16. Containment Water Level - Narrow Range 2 1 20, 21 e

m $E TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION (CONTINUED)~ E. EE REQUIRED MINIMUM -4 NUMBER OF CHANNELS oa INSTRUMENT CHANNELS OPERA 8LE ACTION 17. Containment Water Level - Wide Range 2 1 20, 21 18. Core Exit Thermocouples 7/ core 4/ core 20, 21 quadrant quadrant 19. Cold Leg HPSI Flow 1/ cold leg N.A. 20 20. Hot Leg HPSI Flow 1/ hot leg N.A. 20 k Y l l B; i E! l si E!a 5 l {

TABLE 3.3-10 (Continued) ACTION STATEMENTS ACTION 20 - With the number of OPERABLE accident monitoring channels less than the Required Number of Channels, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours. ACTION 21. With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least HOT SHUTDOWN within the next 12 hours. 1 SAN ONOFRE-UNIT 2 3/4 3-53a Amendment No. 31 e

F o vs E TABLE 4.3-7 b ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ET E CHANNEL CHANNEL U INSTRUMENT CHECK CALIBRATION ~ 1. Containment Pressure - Narrow Range M R 2. Containment Pressure - Wide Range M R 3. Reactor Coolant Outlet Temperature - THot (W& Range) M R 4. Reactor Coolant Inlet Temperature -TCold ( Range) M R 5. Pressurizer Pressure (Wide Range) M R 6. Pressurizer Water Level M R j 7. Steam Line Pressure M R w 8. Steam Generator Water Level (Wide Range) M R E 9. Refueling Water Storage Tank Water Level M R 10. Auxiliary Feedwater Flow Rate M R 11. Reactor Coolant System Subcooling Margin Monitor M R 12. Safety Valve Position Indicator M R 13. Spray System Pressure M R 14. LPSI Peader Temperature M R 15. Containment Temperature M R 16. Containment Water Level (Narrow Range) M R

17. Containment Water Level (Wide Range)

M R 18. Core Exit Thermocouples M R

l m E TABLE 4.3-7 . ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREENTS (CONTINUED) E? E CHANNEL CHANNEL Q INSTRUNENT CHECK CALIBRATION m 19. Cold Leg HPSI Flow M R 20. Hot Leg HPSI Flow M R ( ~ s N ~ Y g; l G E E -s 8 W

m -- INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDI1 ION FOR OPERATION 3.3.3.7 - As a minimum, the' fire detection instrumentation for each fire detection zone shown in Table 3.3-11 shall be OPERABLE. APPLICA8ILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE. ACTION: With the number of OPERABLE fire detection instrument (s) less than the minimum number b? ERA 8LE requirement of Table 3.3-11: a. Within I hour establish a fire watch patrol to inspect the zone (s). with the inoperable' instrument (s) at least once'per hour, unless the instrument (s) is located inside the containment, then inspect the . containment at least once per 8 hours or monitor the containment air temperature at least once per hour at the locations listed in', Specification 4.6.1.5. b. The, provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.7.1 Each of the above required fire detection instruments which are accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during plant operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours unless performed in the previous 6 months. 4.3.3.7.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months. 4.3.3.7.3 The non-supervised circuits associated with detector alarms between the instruments and the control room shall be demonstrated OPERABLE at least i once per 31 days. 4.3.3.7.4 'Following a seismic event (basemat acceleration greater than or equal to 0.05 g): a. Within 2 hours each zone shown in Table 3.3-11 shall be inspected for fires, and b. Within 72 hours an engineering evaluation shall be performed to verify the OPERABILITY of the fire de'tection system in each zone s shown in Table 3.3-11. s SAN ONOFRE-UNIT 2 3/4 3-56 m s, _ _ _. _, _ - _ _. J

TABLE 4.3-8 (Continued) TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:* 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. P (2) The. initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or -using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. . (3) CHANNEL CHECK shali consist of. verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours on days on which continuous, periodic, or batch releases are made. F0L

• If.the instrument controls are not.in the operate mode, procedures shall require that the channel be. declared inoperable.

SANdNOFRE-UNIT 2 3/4.3-67 2

INSTRUMENTATION RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE 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 ODCM. APPLICABILITY: As shown in Table 3.3-13* ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable. b. With less than the minimum number of radioactive gaseous effluent 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 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. c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable. -SURVEILLANCE REQUIREMENTS 4.3.3.9 ~ Each radioactive gaseous 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 4.3-9. "See Special Test Exception 3.10.5-SAN ONOFRE-UNIT 2 3/4 3-68 AMENDMENT No. 31 2.

m ' TABLE 3.3-13 RADI0 ACTIVE GASE0US EFFLUEtiT MONITORING INSTRUMENTATION MINIMUM CHANNELS [ INSTRUMENT OPERABLE APPLICABILITY ACTION 5 1. WASTE GAS HOLDUP SYSTEM a. Noble. Gas Activity Monitor - Providing Alarm and Automatic c3 Termination of Release - 1 35 2/3 Rf-7808, 2 RT-7865-1 or 3 RT - 7865-1 b. Process Flow Rate Monitoring Device 1 36 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a. Hydrogen Monitor 2 39 b. Oxygen Monitor 2 39 3. CONDENSER EVACUATION SYSTEM w a. Noble Gas Activity Monitor - 2RT - 7818 or 1 2RT - 7870-1 1 37 w b. Iodine Sampler 1 40 E c. Particulate Sampler i 1 40 d. Associated Sample Flow Measuring Device 1 36 36 e. Process Flow Rate Monitoring Device 1(4) 4. PLANT VENT STACK a. Noble Gas Activity Monitor - 1 37 - 2/3 RT - 7808, 2RT-7865-1 or 3RT-7865-1 b. Iodine Sampler 1 40 c. Particulate Sampler 1 40 d. Associated Sample Flow Measuring Device 1 36 e. Process Flow Rate Monitoring Device 1(5) 36 P h 5. CONTAINMENT PURGE SYSTEM E a. thble Gas Activity Monitor - Providing E Alarm and Automatic Termination of Release - 2RT - 7828 or 2 RT-7865-1(1) 1(2) 38 b. Iodine Sampler 1(2) 40 40 c. Particulate Sampler 1(2) M d. Process Flow Rate Monitoring Device 1(3) 36 e. Associated Sample Flow Measuring Device 1(2) 36

TABLE 3.3-13 (Continued) TABLE NOTATION At all times. During waste gas holdup system operation (treatment for primary system offgases).

• • • MODES 1-4 with any main steam isolation valve and/or any main steam iso-lating bypass valve not fully closed.

(1) Provided 2RT-7865-1 is equipped to automatically terminate containment purge release. (2) Prior to completion of DCP53N, Containment Airborne Radiation Monitor 2RT-7804-1 performs the functions of 2RT-7828. 2RT-7804-1 is not equipped to monitor purge flow. (3) Prior to completion of DCP53N, 2RT-7865-1 may perform this function for l minipurge only. Otherwise comply with ACTION 36 if another means of continuously monitoring purge flow is not available. (4) 2RT-7818 is not equipHd i.o monitor process flow, If another means of con-tinously monitoring process flow is not available, then comply with ACTION 36. (5); 2/3 RT-7808 is not equipped to monitor plant vent stack flow. If another i means of continuously monitoring plant vent stack flow is not available, j then comply with ACTION 36. i i ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) : may be released to the environment provided that prior to initiat-ing the release: a. At least two independent samples of the tank's contents are analyzed, and b. At least two. technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway. ACTION 36 With the number of channels OPERABLE less than required by the ~ Minimum Channels OPERABLE requirement, effluent releases via this pathway may-continue provided the flow rate is estimated at least once per 8 hours. Systemdesigncharacteristicsmaybeused-l to estimate flow. ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for gross activity within 24 hours. SAN ONOFRE-UNIT-2 3/4 3-70 AMENDMENT NO. 31

i TABLE 3.3-13 (Continued) TABLE NOTATION ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway OR Prior to completion of DCP53N, and with Plant Vent Stack Monitor 2RT-7865-1 not capable of terminating containment purge release, PURGING may continue using 2RT-7865-1 provided that: 1) Plant Vent Stack Monitor 2RT-7865-1 is aligned to the purge stack for the duration of the purge; and, 2) Plant Vent Stack Monitor 2/3 RT-7808 or 3RT-7865-1 is OPERABLE and aligned to the plant vent stack; and, 3) When. PURGING is complete, 2RT-7865-1 is realigned to the plant vent stack; and, i I 4) In the event of a high activity alarm during the PURGE + from any of 2RT-7865-1, 3RT-7865-1 or 2/3 RT-7808, an operator immediately suspends containment PURGING and realigns 2RT-7865-1 to the Plant Vent Stack. ACTION 39 - Withthenumberofchannn[isOPERABLEonelessthanrequiredby the Minimum Channels OPERABLE requirement, operation of this system may continue provided that the remaining OPERABLE channel is aligned to the waste gas surge tank. With two channels inoperable, operatio'n of.this system may continue provided that j grab samples are taken at least once per 4 hours and analyzed i within the following 4 hours. i ACTION 40 -- With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided samples are con-tinuously collected with auxiliary sampling equipment as required in Table 4.11-2. SAN ONOFRE-UNIT 2 3/4 3-71 AMENDMENT NO. 31

TABLE 4.3-9 h RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

D CHANNEL' MODES FOR WHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE

[ INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination'of Release - 2/3 RT-7808, 2RT-7865-1, 3RT-7865-1 P P R(3) Q(1)

b. Process Flow Monitoring Device P

N.A. R Q ^ 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE w '1 GAS MONITORING SYSTEM "4

a. Hydrogen Monitor (continuous)

D N.A. Q(4) M N

b. Oxygen Monitor (continuous)

D N.A. Q(5) M

c. Hydrogen Monitor (periodic)

D N.A. Q(4) M

d. Oxygen Monitor (periodic)

D N.A. Q(5) M 3. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor -

2RT - 7818, 2RT - 7870-1 D M R(3) Q(2)

b. Iodine Sampler W

N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A. g

d. Associated Sample Flow g

Measuring Device D N.A. R Q E

e. Process Flow Rate Monitoring E

Device (2RT-7870-1) D N.A. R Q c-i 8

o W ' TABLE 4.3-9 (Continued) z RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS A l c CHANNEL MODES FOR WHICH j'i CHANNEL SOURCE CHANNEL FUNCTIONAL SURVEILLANCE INSTRUME,sI ro CHECK CHECK CALIBRATION TEST IS REQUIRED 4. PLANT VENT STACK

a. Noble Gas Activity Monitor -

2/3 RT - 7808, 2RT - 7865-1, 3RT-7365-1 D M R(3) Q(2)

b. Iodine Sampler W

N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A.

d. Associated Sample Flow w1 Measuring Device.

D N.A. R Q T

e. Process Flow Rate Monitoring d

Device D N.A. R Q 5. CONTAINMENT PURGE SYSTEM (7)

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of Release - 2 RT - 7828, 2 RT-7865-1 0 P(6) R(3) Q(1)

b. Iodine Sampler W

N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A.

d. Process Flow Rate Monitoring m

Device D N.A. R Q

e. Associated Sample Flow Measuring

[ -Device D N.A. R Q

6 TABLE 4.3-9 (Continued) TABLE NOTATION

• At all times.

During waste gas holdup syst'em operation (treatment for primary system offgases).

• • • Modes 1-4 with any main steam isolation valve and/or any main steam isola-ting valve bypass valve not fully closed.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:# 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists # : 1. Instrument indicates measured levels above the alarm setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. (3).The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or ~ using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (4)- The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. .One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen. -(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. --One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen. (6) Prior to each release and at.least once per month. (7) Prior to completion of DCP53N, these surveillance requirements are to he performed on the instrumentation indicated by Table 3.3-13.

1. If the instrument controls are not set in the operate mode, procedures shall call.for declaring the channel inoperable.

AMENDMENT No. 31 SAN ONOFRE-UNIT 2 3/4 3-74 - ~

~- INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.10 The loose part detection system shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTION: a. With one or more loose part detection system channels inoperable for c more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status. b. LThe provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.10 Each channel of the loose part detection system shall be demonstrated OPERABLE by performance of a: a. CHANNEL CHECK at least once per 24 hours, b. . CHANNEL FUNCTIONAL TEST at least once per 31 days, and c. CHANNEL CALIBRATION at least once 'per 18 months. SAN ONOFRE-UNIT 2 3/4 3-75 AMENDMENT NO. 31

O INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least one turbine overspeed protection system shall be OPERABLE. . APPLICABILITY: MODES 1, 2* and 3.* ACTION: a. With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours, or close at least one valve in the affected steam lead or isolate the turoine from the-steam supply within the next 6 hours. b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours isolate the turbine from the steam supply. SURVEILLANCE REQUIREMENTS ~4.3.4 The above. required turbine overspeed protection system shall be demonstrated OPERABLE: a. -At least once per 7 days by cycling each of the following valves throughgat least one complete cycle from the running position. 1. Four high pressure turbine stop valves. 2. Four high pressure turbine control valves. 3. Six low pressure turbine reheat stop valves. 4. Six low pressure turbine reheat intercept valves. b. At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position. At least'once per_18 months _ by performance of a CHANNEL CALIBRATION c. on the turbine overspeed protection systems. d. At least once per 40 months by disassembling at least one of each of _the~above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

• With any main steam line isolation valve and/or any main steam line isolation

-valve bypass valve not fully closed. SAN ONOFRE-UNIT 2 3/4 3-76 AMENDMENT NO. 31

je9 UNITED STATES 3" NUCLEAR REGULATORY COMMISSION . j - a j WASHINGTON D. C. 20555 %,'...... s/ -SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS-AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA 'THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 . SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. NPF-15 J 1. The Nuclear Regulatory Commission (the Comnission) has found that: ~ The applications for amendment to the license for San Onofre Nuclear A. Generating Station, Unit 3 (the facility) filed by the Southern California Edison Company on behalf of itself and San Diego Gas and Electric Company, The City of Riverside and The City of Anaheim, California.(licensees) dated March 2 and April 2, 1984, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the.Act) and the Commission's regulations as set forth in 10 -CFR Chapter I; B.

The facility will operate in conformity with the applications, as amended, the provisions of the Act, and the regulations of the

' Commission; There'is reasonable assurance: (i) that the activities authorized C.; by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in.10 CFR Chapter I; -The Iissuance of this' license amendment will not be inimical to the D. common defense and. security or to the health and safety of the public; t j d v -w

s ^ J .p_ E.- The issuance of this amendment is in accordance with 10 CFR Part 51 of_the Commission's regulations'and all applicable requirements have been satisfied. 2.

Accordingly, the license is amended by changes to the Technical Specifica-

.tions as indicated.in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as.follows: (2)1 Technical Specifications -The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan _ contained in Appendix B, as revised through ' Amendment No. 20, are hereby incorporated 'in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. - 3.. This amendment is effective as of.the date of issuance and shall be' fully limplemented-by January 31, 1985. FOR THE NUCLEAR REGULATORY COMMISSION h (.. bM. G George W. Knighton, Chief Licensing Branch No. 3 Division of. Licensing

Attachment:

Changes to_the. Technical Specifications-Date of issuance: January 11,1 1985- 'e-v-.*

January 11, 1985 ATTACHMENT TO LICENSF AMENDMENT NO. 20 FACILITY OPERATING LICENSE N0. NPF-15 DOCKET h0. 50-362 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of chance. Also to be replaced are the following overleaf pages to the amended pages. Amendment Pages Ovei'ieaf Paoes 3/4 3-18 3/4 3-17 .3/4 3-21 3/4 3-22 3/4-3-25 3/4 3-26 3/4 3-33 -3/4 3-34 3/4 3-35 3/4 3-36 3/4 3-37 3/4 3-38 '3/4 3-?9 3/4 3-40 3/4 3-51 3/4 3-52 -3/4 3-53 3/4 3-54 3/4 3-55 3/4 3-56 3/4 3-69 3/4 3-70 3/4 3-71 3/4 3-72 3/4 3-73 3/4 3-74 3/4 3-75 3/4 3 - -3/4'3-77 E

en 3 o. TABLE 3.3-3 (Continued) g z ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o E . h! MINIMUM a. TOTAL NO. CHANNELS CHANNELS' APPLICABLE FUNCTIONAL UNIT- '0F CHANNELS-TO TRIP OPERABLE MODES ACTION -{ 9. CONTROL ROOM ISOLATION (CRIS) a, ' Manual CRIS (Trip Buttons) 2 1 1 All 13*# b. Manual:SIAS (Trip Buttons) 2' sets of 2/ unit 1 set of 2 2 sets of 2/ unit 1, 2, 3, 4 8 c. Airborne Radiation i. Particulate / Iodine 2 1 1 All 13*# ii. Gaseous 2 1 1 All 13*# u,); d. Automatic Actuation Logic 1/ train ,1 1 All 13*# u, i C 10. T0XIC GAS ISOLATION (TGIS) a. Manual (Trip Buttons) 2 1 1 All 14*#, 15*# b. Chlorine - High 2 1 1 All 14*#, 15*# c. Ammonia - High-2 1 1 All 14*#, 15*# d. Butane / Propane - High 2 1 1 All 14*#, 15*# e. Carbon Dioxide - High 2 1 1 All 14*#, 15*# f. Automatic Actuation Logic 1/ train 1 1 All 14*#, 15*#

TABLE 3.3-3'(Continued) 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION -o5 k MINIMUM a TOTAL NO. CHANNELS CHANNELS APPLICABLE z FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE' MODES ACTION 11. FUEL HANDLING ISOLATION (FHIS) 16*# a. Manual (Trip Buttons) 2 1 1 b. Airhsene Radiation 16*#

i. Gaseous 2

1 1 16*# ii. Particulate / Iodine 2 1 1 c. Automatic Actuation 16*# Logic 1/ train 1 1 12. CONTAINMENT PURGE ISOLATION (CPIS) w a. Manual (Trip Buttons) 2 1 1 6 17b*# b. Airborne Radiation (3RT-7804-1 or 3RT-7807-2 i. Gaseous 2 1 1 1,2,3,4 17a 6 17b*# ii. Particulate 2 1 1 1,2,3,4 17a 6 17b*# iii. Iodine 2 1 1 6 17b*# c. Containment Area ~ Radiation (Gamma) 2 1 1 1,2,3,4 17 (3RT-7856-1 or 3RT-7857-2) 6 17b*# d. Automatic Actuation P; Logic 1/ train 1 1 1,2,3,4 17 6 17b*# s 3 8 6

S w - Table 3.3-3 (Continued) TABLE NOTATION Withithe number of channels OPERABLE less than required by the ACTION 13

minimum channels OPERABLE requirement, within 1 hour initiate and maintain operation of.the control room emergency air cleanup system in the emergency (except as required by ACTIONS.14, 15) mode of operation.

With the number'of channels OPERABLE one less than the total ACTION 14 number _of channels, restore the inoperable channel to OPERABLE status within 7 days ~or within the next 6 hours initiate and maintain operation of the control room emergency air cleanup . system in the isolation mode of operation. ACTION 15 - With the number of channels OPERABLE less than regu' ired by the minimum channels OPERABLE requirement, within 1 hour initiate and maintain operation of the control room emergency air ' cleanup; system in the isolation mode of operation. With the number of channels OPERABLE less than required by the ! ACTION 16 minimum channels OPERABLE requirement, comply with the ACTION requirements of_ Specification 3.9.12. With the number of channels-0PERABLE less than required by the ' ACTION 17 minimum channels OPERABLE requirement,_ operation may continue provided that the. purge valves are maintained closed. ~ ACTION 17a - With the number of channels OPERABLE less_than required by the . minimum channels OPERABLE requirement, comply with the ACTION requirements ~of Specification 3.4.5.1. (MODE 1, 2, 3,4 only) ACTION 17b - ' With the number, of channels OPERABLE _less than required by the ^ minimum channels OPERABLE requirement, close each of the contain-

ment purge penetrations providing direct access from the con-tainment atmosphere,to the outside atmosphere.

U ~ ^ t (SAN ONOFRE-ONIT.3-3/4 3-21 AMEN 0 MENT NO. 20 x.y~*

g TABLE 3.3-4 ENGINEERED SAFETY' FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES o .k TRIP VALUE VALUES . ALLOWABLE R ' FUNCTIONAL UNIT 1. SAFETY INJECTION (SIAS) a. Manual (Trip Buttons) Not Applicable. Not Applicable ] b. . Containment Pressure High 1 2.95 psig 5 3.14 psig. Pressurizer Pressure - Low 1 1806 psia (1) 1 1763 psia (1) c. d. Automatic Actuation Logic Not Applicable Not Applicable 2.. CONTAINMENT' SPRAY (CSAS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Containment Pressure -- High-High 5 16.14'psig i 16.83 psig c. Automatic Actuation Logic Not Applicable Not Applicable g y 3. CONTAINMENT ISOLATION (CIAS) g a. Manual CIAS (Trip Buttons) Not Applicable Not Applicable b. Manual SIAS (Trip Buttons)(5) Not Applicable Not Applicable c. Containment Pressure - High 1 2.95 psig 5 3.14 psig d. Automatic Actuation Logic Not Applicable Not Applicable 4. MAIN STEAM ISOLATION (MSIS) a. Manual (Trip Buttons) Not Applicable Not Applicable b. Steam Generator Pressure - Low ' 1 729 psia (2) 1 711 psia (2) c. Automatic Actuation Logic Not Applicable Not Applicable 5. RECIRCULATION (RAS)- a. Refueling Water Storage Tank 18.5% of tap span 19.27% 1 tap span 1 17.73% b. Automatic Actuation Logic Not Applicable Not Applicable O 4 i

m; . n. .y , _ r r-dr;..u s.t' <r: O., in .4;

s.,

TABLE 3.3-4 (Continued); _q $0 1, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES o.8n Ni ALLOWABLE E FUNCTIONAL UNIT TRIP VALUE VALUES-35 .c 11. FUEL HANDLING ISOLATION (FHIS) us a. Manual (Trip Buttons) Not Applicable Not Applicable b. Airborne Radiation

i. Gaseous i 1.3 x 102 cpm **

1 1.4 x.102 cpm ** ii. Particulate / Iodine 1 5.7 x 104 cpm ** $ 6.0 x'104 cpm ** u,- c. Automatic Actuation Logic Not Applicable Not Applicable A 12. CONTAINMENT PURGE ISOLATION (CPIS) u2 d> i a. Manual-(Trip Buttons) Not Applicable Not Applicable b. ' Airborne Radiation i. Gaseous (6)(7) -(6)(7) ii. Particulate (6)(7) (6)(7) iii. Iodine (6)(7) (6)(7) ~ c. Containment Area Radiation (Gamma) < 325 mR/hr (MODES 1-4) < 340 mR/hr (MODES 1-4) 7 2.4 mR/hr (Mode 6) I 2.5 mR/hr (MODE 6) Q d. Automatic Actuation Logic Not Applicable Not Applicable E Ga 8

'( b TABLE 3.3-4 (Continued) -TABLE NOTATION o E,s -. (1) Value may be decreased manually, to a mi,nimum of greater than'or equal to'300 psia, as pressurizer. 5 5: pressure is reduced, provided the margin between the. pressurizer and this value is. maintained at. 25 'less than or equal to 400 psia;* the:setpoint shall be increased automatically as pressurizer pressure -d is increased until the trip setpoint is' reached. ' Trip may be manually bypassed below 400 psia; . bypass-shall be' automatically removed whenever pressurizer is greater than or equal to 400 psia. (2) Value~may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained at. less than or equal to 200 psi;* the setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached. (3) % of the distance between steam generator upper and lower level instrument nozzles. .(4). Inverse time relay set value'3165V, trip will. occur within the tolerances specified in Figure 3.3-1 u2 30 for the range of bus voltages. (5) Actuated' equipment only; does not result in CIAS. (6) The trip setpoint shall be set sufficiently high to prevent spurious alarms / trips yet sufficiently low to assure an alarm / trip should an inadvertent release occur. (7) Prior to the completion of DCP 53N, the setpoints for Containment Airborne Radiation Monitor 3RT-7804-1 shall be determined by the ODCM. nVariable setpoints are for use only-during normal, controlled plant heatups and cooldowns. AA Above normal background, b $a 5 8 8 O 4 gg

O TABLE 4.3-2 (Continued) .y 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES'FOR WHICH A' CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE d. FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED 11. FUEL HANDLING ISOLATION (FHIS) a. Manual (Trip Buttons) N.A. N.A. R N.A. b. Airborne Radiation

i. Gaseous S

R M ii. Particulate / Iodine S R M c. Automatic Actuation Logic N.A. N.A. R(3) 12. CONTAINMENT PURGE. ISOLATION (CPIS) a. Manual (Trip Buttons) N.A. N.A. R N.A. b. Airborne Radiation i. Gaseous S R M 1,2,3,4,6 m) ii. Particulate W R M 1,2,3,4,6 iii. Iodine W R M 6 w J, c. ' Containment Area Radiation (Gamma) S R M 1,3,3,4,6 w d. Automatic Actuation Logic N.A. N.A. R (3) 1,2,3,4,6 TABLE NOTATION (1) Each train or logic channel shall be_tes'ted at least every 62 days on a STAGGERED TEST BASIS. (2) Deleted. (3) Testing of Automatic Actuation Logic shall include energization/de-energization of each initiation relay and verification of the OPERABILITY of each initiation relay. g (4) A subgroup relay test shall be performed which shall include the energization/de-energization of each R subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays exempt from testing 5 during plant operation shall be limited to only those relays associated with plant equipment which [6 cannot be operated during plant operation. Relays not testable during plant operation shall be tested 4 during each COLD SHUTDOWN exceeding 24 hours unless tested during the previous 6 months. ,5 (5) Actuated equipment only; does not result in CIAS. g With irradiated fuel in the storage pool.

~ 1 INSTRUMENTATION-3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION ^ LIMITING CONDITION FOR OPERATION 3.3.3.1.The radiation monitoring instrumentation channels shown in ' Table 3.3-6 shall be 0PERABLE with their alarm / trip setpoints within the specified limits.* APPLICABILITY: As shown in Table 3.3-6. ACTION: a. With a radiation monitoring channel alarm / trip setpoint exceeding the -value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours or declare the channel inoperable. Lb. With one or more radiation monitoring channels inoperable, take the -ACTION shown in Table 3.3-6. t - c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance ofz the CHANNEL CHECK, CHANNEL. CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the

frequencies shown in Table 4.3-3.

fi

• 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 airborne. 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. SAN ONOFRE-UNIT 3 3/4 3-34 AMENDMENT N0. 20

j';;

.~ j TABLE 3.3-6 4 2 RADIATION MONITORING INSTRUMENTATION 5itA MINIMUM J- -CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT' INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION g w-1. Area Monitors a. Containment - High 2 1,2,3 10 R/hr 1-10s R/hr 18, 18a Range 4 '.10 R/hr 19 (3RT-7820-l'and 3RT-7820-2) b. Containment - Purge 1 1,2,3,4 10 1-105 mR/hr 17 Isolation 6 17b (3RT-7856-1 or 3RT-7857-2) c. Main Steam Line 1/line 1, 2, 3 1 mR/hr (low); 10 1-104 mR/hr; 18 A channel consists of 1 R/hr (high) wa 3RT-7874A and 3RT-7875A or 4 j 1 mR/hr (low); 19 u' 3RT-78748 ana 3RT-7875B 1 R/hr (high) 2. Process Monitors a. Fuel Storage Pool Airborne (3RT-7822-1 or 3RT-7823-2) 101 -107 cpm 16 i. Gaseous 1 101 -107 cpm 16 ii. Particulate / Iodine 1 b. Containment Airborne (3RT-7804-1 or 3RT-7807-2) i. Gaseous 1 1,2,3,4 101 -107 cpm 17a 6 17b h ii. Particulate 1 1,2,3,4 101 -107 cpm 17a 6 17b iii. Iodine 1 6 101 -107 cpm 17b z c. Control Room Airborne ? (2/3 RT-7824-1 or 2/3 RT-7825-2) i. Particulate / Iodine 1 All 101 -107 cpm 13 w ii. Gaseous 1 All 101 -107 cpm 13 (.

1 TABLE 3.3-6 (Continued) 2 RADIATION MONITORING INSTRUMENTATION E-o. 3 ch - MINIMUM 25 CHANNELS APPLICABLE ALARM / TRIP ' MEASUREMENT -d INSTRUMENT OPERABLE. MODES SETPOINT RANGE ACTION-us 3. Noble Gas Monitors a. Plant Vent Stack 3 Wide Range (2RT-7865-1 1 1,2,3 Per ODCM 10 7 - 105 pCi/cm 19 or 3RT-7865-1) 3 Normal Range (2/3RT-7808 1 4-Per ODCM 10 8 - 10 1 pCi/cm 19 or 2RT-7865-1 or -3RT-7865-1) b. Condenser Evacuation Syste: u, 3 19 J, Wide Range (3RT-7870-1) 1 1, 2, 3(1) Per ODCM 10 7 - 105 pCi/cm 3 Normal Range (3RT-7818 1 4 (1) Per ODCM 10 6 - 102 pCi/cm 19 o' or 3RT-7870-1) (1) With any main steam line isolation valve and/or any main steam isolating valve bypass valve not fully closed. Si 8 s

-.x TABLE 3.3-6 (Continued) ^ ACTION STATEMENTS ~ With the number of channels OPERABLE less than required by the ACTION 13 minimum channels OPERABLE requirement, within 1 hour initiate and maintain. operation of the control room emergency air cleanup system in the emergency (except as required by ACTIONS 14, 15) mode of operation. ~With the number ~of channels OPERABLE less than required by the ACTION 16 minimum channels OPERABLE requirement, comply with the ACTION . requirements of Specification 3.9.12. With the number of channels OPERABLE less than required by the ACTION 17 minimum channels OPERABLE requirement, operation may continue provided that the purge valves are maintained closed. . ACTION 17a - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.5.1 (Mode 1, 2, 3, 4 only) ACTION 17b -- With.the number.of channels OPERABLE less than required by the minimum channels 0PERABLE requirement, close each of the con- .tainment purge penetrations providing direct access from the containment atmosphere to the outside atmosphere. ACTION 18 - With the number of channels OPERABLE one,ess than Minimum-l Channels OPERABLE requirement, either restore the inoperable channel to OPERf.BLE status within 30 days, or be in HOT SHUTDOWN within the next 12 hours.- ACTION.18a - With' both' channels inoperable, restore the inoperable channel (s) to OPERABLE status _within 48 hours, or be in HOT SHUTDOWN within .the next 12 hours. . ACTION 19_ -' 'With the number of OPERABLE Channels'less than required by the . Minimum Channels OPERABLE requirement, either restore the inoperable' Channel (s) to OPERABLE status within 72 hours, or: 1) . Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and 2)- Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following initiation of the pre planned alternate outlining the action taken, the cause of the_inoperability and the plans _ and schedule for restoring the system to OPERABLE -status. j )In accordance with Engineered Safety Feature trip value specified by Table 3.3-4.- n -- With irradiated fuel in the storage pool. D ACTIONS 13,116, 17, 17a and 17b_are repeated from Table 3.3-3 for reference. SAN ONOFRE-UNIT 3~ 3/4 3-37 AMEN 0 MENT NO. 20 g , ~-

y i TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH-i!E CHANNEL CHANNEL ' FUNCTIONAL SURVEILLANCE E INSTRUMENT' CHECK CALIBRATION ' TEST IS REQUIRED - 5 ] 1. ' Area Monitors a. Containment - High Range S R M 1,2,3,4 (3RT-7820-1, 3RT-7820-2) b. Containment - Purge Isolation S R. M. 1,2,3,4,6 (3RT-7856-1, 3RT-7857-2) c. Main Steam Line 5 R M 1,2,3,4 (3RT-7874A, 3RT-7875A, 3RT-78748, 3RT-78758). w1 2. Process Monitors Fuel Storage' Pool Airborne i a. (3RT-7822-1,3RT-7823-2) .i. Gaseous ii. Particulate / Iodine b. Containment Airborne (3RT-7804-1,3RT-7807-2) i. Gaseous 1,2,3,4,6 ii. Particulate-1,3,3,4,6 iii. Iodine 6 c. Control Room Airborne g (2/3RT-7824-1, 2/3RT-7825-2) n-E i. Particulate All ( li. Gaseous All a 5 9

a. l JU; TABLE 4.3-3 T. RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS z-o !k CHANNEL-MODES FOR WHICH N( CHANNEL CHANNEL FUNCTIONAL-SURVEILLANCE ~ 4 INSTRUMENT CHECK CALIBRATION TEST IS REQUIRED -4 PROCESS MONITORS (Continued) us 3. Noble Gas Monitors a. Plant Vent Stack 0 R Q 1,2,3,4 (2/3 RT-7808, 2RT-7865-1, 3RT-7865-1) b. Condenser Evacuation System 'D R Q 1,2,3,4(1) (3RT-7818,3RT-7870-1) R. La h$ NOTES:

1. n accordance with Table 4.3-2 surveillance requirements for these. instrument channels.

I

• With irradiated fuel in the storage pool.

~ (1) With any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed. !E E !E Gs 8

r ( I 3675 i 110 VOLTS 100 U 'e N R l 10 f I / / [ / 2800 VOLTS l 2.610.13 SECONDS O VOLTS 1.01.05 SECONDS 1.0 2400 2800 3200 3600 4000 BUS VOLTAGE Figure 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING l SAN ONOFRE-UNIT 3 3/4 3-40 1

INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITINd CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE. APPLICABILITY: MODES 1, 2 and 3. ACTION: a. With'one or more accident monitoring channels inoperable, take the ACTION shown in Table 3.3-10. b. The' provisions of Specification 3.0.4 are oot applicable. SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring _ instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK an'd CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-7. e SAN ONOFRE-UNIT 3 3/4 3-51 AMENDMENT NO 20 La

-+ 3 33 m -. + (b a-4 5 .g* -TABLE 3.3-10 ~ ACCIDENT MONITORING INSTRUMENTATION o. g ..m <R' REQUIRED. MINIMUM c'-: NUMBER OF: CHANNELS l'i INSTRUMENT CHANNELS OPERABLE ACTION. w. .1. Containment Pressure - Narrow Range .2 1 20,- 21 ~

22.. Containment' Pressure - Wide; Range 2

1 20, 21 3. Reactor. Coolant Outlet Temperature ',THot (Wide Range) 2 1 20, 21 4. Reactor. Coolant' Inlet-Temperature - TCold (Wide Range) 2 1 20, 21 5. -Pressurizer-Pressure - Wide Range. 2 1 20, 21 6. Pressurizer Water Level 2 1 20, 21

7. ' Steam Line Pressure 2/ steam 1/ steam 20, 21 wA generator generator T

8. . Steam Generator Wa'ter Level - Wide. Range 2/ steam 1/ steam 20, 21 E-generator generator

9.. Refueling Water Storage Tank Water Level 2

1 20, 21

10. Auxiliary Feedwater Flow Rate 1/ steam N.A.

20 generator 11. Reactor Coolant System Subcooling Margin Monitor 2 1 20, 21 12. Safety Valve Position Indicator 1/ valve-N.A. 20 13. Spray System Pressure 2 1 20, 21 -14. LPSI Header Temperature 2 1 20, 21 15. Containment Temperature 2 1 20, 21 2 -16. Containment Water Level - Narrow Range 2 1 20, 21 e g

17. Containment Water Level - Wide Range 2

1 20, 21 H

18. Core. Exit ~Thermocouples 7/ core 4/ core 20, 21 quadrant quadrant

19. Cold Leg HPSI Flow 1/ cold leg N.A.

20

20. Hot Leg HPSI Flow 1/ hot leg N.A.

20 es

7-This page intentionally blank SAN ONOFRE-UNIT 3 3/4 3-53 AMENDMENT NO. 20 (.

F i TABLE 3.3-10 (Continued) ACTION STATEMENTS ACTION _20 - With the number of OPERABLE accident monitoring channels less than the Required Number of Channels, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours. ACTION 21 - With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 48 hours or be in at least HOT SHUTDOWN within the next 12 hours. -w e

SAN'ONOFRE-UNIT 3 3/4 3-54 AMEN 0 MENT NO. 20

e TABLE 4.3-7 50 - . ACCIDENT MONITORING-INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2~ o5n CHANNEL CHANNEL . INSTRUMENT CHECK CALIBRATION 4.

z 1.

Containment Pressure - Narrow Range M R ] 2. Containment Pressure - Wide Range M R 3. Reactor Coolant Outlet Temperature - THot (Wide Range) M R 4. Reactor Coolant Inlet Temperature -TCold (Wide Range)- M R 5. Pressurizer: Pressure (Wide Range) M R 6. Pressurizer Water Level M R '7. Steam Line Pressure M R R 8. Steam Generator Water Level (Wide Range) M-R b 9. Refueling Water Storage Tank Water Level M R h 10. Auxiliary Feedwater Flow Rate i M R 11. Reactor Coolant System Subcooling Margin Monitor M R 12. Safety Valve Position Indicator M R 13. Spray System Pressure M R 14. LPSI Header Temperature M R

15. Containment Temperature M

R

16. Containment Water Level (Narrow Range)

M R 17. Containment Water Level (Wide Range) M R 18. Core Exit Thermocouples M R 19. Cold Leg HPSI Flow M R g 20. Hot Leg HPSI Flow M R 8 l l I

This page intentionally blank m I O w- ' SAN ONOFRE-UNIT 3 3/4 3-56 AMENDMENT NO. 20

61 .9 t s INSTRUMENTATION . RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous effluent monitoring instrumentation channels "i shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that_the limits of Speci.fication 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM.* APPLICABILITY: As shown in Table 3.3-13 ACTION: a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous. effluents monitored by the affected channel or declare the channel inoperable. b. With less than the minimum number of radioactive gaseous effluent 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 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. c. The provisions of Specifications 3.0.3, 3.0.4, and 6.9.1.13b are not applicable. SURVEILLANCE REQUIREMENTS . 4.3.3.9 Each radioactive gaseous 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 4.3-9. ~ L

• 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 airborne 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. - SAN ON0FRE-UNIT 3 3/4 3-69 AMENDMENT N0. 20

TABLE 3.3-13' y- 'RADI0 ACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION o MINIMUM CHANNELS E INSTRUMENT -OPERABLE APPLICABILITY ' ACTION l 1. ' WASTE GAS. HOLDUP SYSTEM .E .a. Noble Gas Activity Monitor - Z Providing Alarm and Automatic 35' d Termination of' Release - 2/3 RT -7808, 1 2RT-7865-1 or 3RT-7865-1 36 b.- Process Flow Rate Monitoring Device 1 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM 39 a. Hydrogen Monitor 2 39 b. Oxygen Monitor-2 3. CONDENSER EVACUATION SYSTEM R a. Noble Gas Activity Monitor.3RT - 7818 or 37 3RT - 7870-1 'l 40 Y b. Iodine Sampler. 1-40 g c. Particulate Sampler l' d. Associated Sample Flow Measuring Device 1 36 36 e. Process Flow Rate Monitoring Device 1(4) 4. PLANT VENT STACK 37 a. Noble Gas Activity Monitor - 1 - 2/3 RT - 7808, 2RT-7865-1 or 3RT-7865-1 40 b. Iodine Sampler 1 40 c. Particulate. Sampler -l g 36 d. Associated Sample Flow Measuring Device 1 36 e. Process Flow Rate Monitoring Device 1(S) gl S. CONTAINMENT PURGE SYSTEM Noble Gas' Activity Monitor - Providing d a. Alarm and Automatic Termination of Release 38 3RT-7828 or 3kT-7865-1 (1) 1 (2) ~ El b. Iodine Sampler 1 (2) 40 c. Particulate Sampler 1 (2) 40 36 d. Process Flow Rate Monitoring Device 1 (3) e. Associated-Sample Flow Measuring Device 1 (2) 36

i TABLE 3.3-13 (Continued) TABLE NOTATION

• - At all times.

During waste gas holdup system operation (treatment for primary system offgases).

• • • MODES 1-4 with any main steam isolation valve and/or any main steam isolating valve bypass valve not fully closed.

(1)..Provided 3RT-7865-1 is equipped to automatically terminate containment purge release. (2) Prior to completion of DCP53N, Containment Airborne Radiation Monitor 3RT-7804-1 performs the functions of 3RT-7828. 3RT-7804-1 is not equipped to monitor purge flow. - (3) Prior.to completion of DCP53N, 3RT-7865-1 may perform this function for minipurge.only. Otherwise comply with Action 36 if another means of continuously monitoring purge flow is not available. (4) ~3RT-7818 is not equipped to monitor process flow. If another means -of continuously monitoring process flow is not available, then comply . with ACTION 36. (5) 2/3 RT-7808 is not equipped to monitor plant vent stack flow. If another means of continuously monitoring plant vent stack flow is not available, then comply with ACTION 36. ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release: a. At least two independent samples of the tank's contents are analyzed, and b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and1 discharge valve lineup; Otherwise, suspend releases of radioactive effluents via this pathway. ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at ~1 east once per 8' hours. System design characteristics may be used to estimate flow.'

ACTION 37 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,~ effluent releases via this pathway may continue provided grab samples are taken at least once per.12 hours'and these samples are analyzed for gross activity-within 24 hours. ACTION 38 - With the number of channels OPERABLE less than required b the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway OR Prior to completion of DCP53N, and with Plant Vent Stack Monitor 3RT-7865-1 not capable of terminating containment purge release, PURGING may continue using 3RT-7865-1 provided that: - SAN ONOFRE-UNIT 3 3/4 3-71 AMENDMENT N0. 20 [. m_

w

~ + A ~ ~ TABLE 3.3-13 (Continued) TABLE NOTATION 1) . Plant Vent Stack' Monitor 3RT-7865-1 is aligned to the purge stack for the duration of the purge; and, ^ 2) LPlant Vent Stack Monitor 2/3 RT-7808 or 2RT-7865-1 is OPERABLE and aligned to the plant vent stack; and, 3) When PURGING is complete, 3RT-7865-1-is realigned to the ~ plant vent stack; and, ?4) .In the event of a high activity alarm during the PURGE ~ b from any of 3RT-7865-1, 2RT-7865-1 or 2/3 RT-7808, an . operator immediately suspends containment PURGING and ' E realigns 3RT-7865-1 to the Plant Vent Stack. 'With the n'mber of channnels OPERABLE one.less than required by ' ACTION 39 -' u the Minimum Channels OPERABLE requirement, operation of this system may continue provided that the remaining OPERABLE-channel is aligned to the waste gas surge tank. With'two channels inoperable, operation ~of this system may continue provided that grab samples are taken-at least once per 4 hours and analyzed.within the following four hours. ACTION 410 - .With the number of channels OPERABLE less'than required by the Minimum Channels OPERABLE requirement, effluent releases via 1 the affected pathway lmay continue provided samples are con. tinuously collected with* auxiliary sampling equipment as required in Table 4.11-2. s 5 1 Y ' 4 l L.:. l SAN ONOFRE-UNIT 3: 3/4~3-72 AMENDMENT NO. 20-a s..

TABLE 4.3-9 h RADI0 ACTIVE GASEOUS EFFLUENT MONIT'ORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS SOURCE CHANNEL FUNCTIONAL SURVEILLANCE CHANNEL MODES FOR WHICH g CHANNEL 55' INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 1. WASTE GAS HOLDUP SYSTEM [ .a. Noble Gas Activity Monitor - Providing Alarm and Automatic Termination of Release - 2/3 RT-7808, 2RT-7865-1 or 3RT-7865-1 P P R(3) Q(1)

b. Process Flow Rate Monitoring Device P

N.A. R Q 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVE GAS MONITORING SYSTEM

a. Hydrogen Monitor (continuous)

D N.A. Q(4) M y

b. Oxygen Mo'nitor (continuous)

D N.A. Q(5) M U

c. Hydrogen Monitor (periodic)

D N.A. Q(4) M

d. Oxygen Monitor (periodic)

D N.A. Q(5) M 3. -CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor -

3RT - 7818, 3RT - 7870-1 D M R(3) Q(2)

b. Iodine'Sampier W

N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A.

d. Associated Sample Flow Measuring Device D.

N.A. R Q g

e. Process Flow Rate Monitoring g

Device (3RT-7870-1) D N.A. R Q l 4. PLANT VENT STACK N

a. Noble Gas Activity Monitor -

m 2/3 RT-7808, 2RT-7865-1, P or 3RT-7865-1 D M R(3) Q(2) Is

I ~ ~, TABLE 4.3-9 (Continued) . y ~ ' RADIOACTIVE' GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIRENENTS-o- E - R CHANNEL. MODES FOR WHICH '3 CHANNEL SOURCE CHANNEL FUNCTIONAL. SURVEILLANCE INSTRUMENT' CHECK CHECK CALIBRATION TEST IS REQUIRED 4. PLANT. VENT STACK (Continued) -b. Iodine. Sampler W N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A.

d. Associated Sample Flow Measuring Device

• D N.A.

R Q

e. Process Flow Monitoring Device D

N.A. R Q 5. CONTAINMENT PURGE SYSTEN(7) w1

a. Noble Gas Activity Monitor.-

w.4 Providing Alarm and Automatic i Termination of Release - 3RT-7828 or 3RT-7865-1 D P(6) R(3) Q(1)

b. Iodine. Sampler W

N.A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N. A.'

d. Process Flow Rate Monitoring Device D

N.A. R Q

e. Associated Sample Flow Measuring Device D

N.A. R Q h = it 15 5

m w, : 6-: s N. TABLE 4.3-9 (Continued) ~ TABLE NOTATION At a l times. l '**During~ waste. gas holdup system operation (treatment for primary system Voffgases).

• • • MODES 1-4Lwith any main steam isolation valve and/or any main steam

. isolating valbe bypass valve not fully closed. J (1) The CHANNEL FUNCTIONAL ~ TEST shall also demonstrate that automatic canyofthefollowingconditionsexists:gomalarmannunciationoccursif Lisolation ofLthis pathway and control r s - 1. . Instrument indicates measured levels above the alarm / trip setpoint. . 2. Circuit failure. 3. Instrument-indicates a downscale failure. 1(2)- The. CHANNEL FUNCTIONAL TEST shall also demonstrate that control roog: -alarm annunciation occurs if any of the following conditions exists 1. Instrument indicates measured levels above the alarm setpoint. - 2. . Circuit failure. '3. Instrument indicates a downscale' failure. (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National-Bureau of Standards or using standards.that have been obtained from suppliers.that participate .in measurement assurance activities with NBS; These standards shall . permit calibrating the system over its' intended range of' energy and measurement range. For subsequent CHANNEL. CALIBRATION, sources that have -been'related,to.the. initial calibration shall'be used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: t 1.

One volume percent-hydrogen, balance nitrogen, and 2.

.Four volume percent' hydrogen,Lbalance nitrogen. .(5). The CHANNEL CALIBRATION shallLinclude the use of standard gas samples

containing.a nominal

.l. 'One volume percent oxygen, balance nitrogen, and 2. Four volume percent oxygen, balance nitrogen.

(6) Prior.to each release and at.least once per month.

-(7). Prior to_ completion of DCP53N, these surveillance requirements are.to be performed on the instruments indicated by Table 3.3-13. '#If,the instrument controls are not set in the operate mode, procedures shall califfor declaring the channel inoperable.

SAN ONOFRE-UNIT 3 -

3/4 3-75 AMEN 0 MENT NO. 20 L

INSTRUMENTATION LOOSE-PART DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION ~ 3.3.3.10 The loose part detection system shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ? ACTION: a. With one or more loose part detection system channels inoperable for more.than 30 days, prepare and submit a Special Report to the Commission 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 OPERABLE ~ status. - b. ~Th'e provisions of Specifications 3.0.3 and_3.0.4 are not applicable. -SURVEILLANCE REQUIREMENTS' s 4.3.3.10 -Each channel of'the. loose part detection system shall be demonstrated OPERABLE by. performance of a: a. . CHANNEL CHECK at least'once per-24 hours, b. CHANNEL FUNCTIONAL' TEST at.least once per 31 days, and c. CHANNEL CALIBRATION at least once per 18 months. e mi.. i{T s. ! SAN'ONOFRE-UNIT 3 3/4 3-76' AMEN 0 MENT NO. 20

INSTRUMENTATION 3/4.'3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4. At least one turbine overspeed protection system shall be OPERABLE. APPLICABILITY: MODES 1, 2* and 3*. ACTION: a. With one stop valve or one control valve per high pressure turbine steam le~ad inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead inop-erable, restore the inoperable valve (s) to OPERABLE status within 72 hours, or close at least one valve in the affected steam lead or isolate the turbine from the steam supply within the next 6 hours, b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours isolate the turbine from the steam supply. SURVEILLANCE REQUIREMENTS 4.3.4 The above required turbine overspeed protection system shall be demonstrated OPERABLE: a. At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running nosition. 1. Four high' pressure turbine stop valves. 2. Four high pressure turbine control valves. 3. Six low pressure turbine reheat stop valves. 4. Six low pressure turbine reheat intercept valves. b. At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position. c. At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems. d. At:least once per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

• With any-main steam line isolation valve and/or any main steam line isolation h

valve bypass valve not fully closed. SAN ONOFRE-UNIT 3 3/4 3-77 AMENDMENT NO. 20 [_}}