ML053430168

Application to Amend the Technical Specifications to Delete the Requirements for Fuel Handling Isolation Signals and Fuel Handling Building Post-Accident Cleanup Filter Systems

ML053430168
Person / Time
Site:	San Onofre
Issue date:	12/06/2005
From:	Katz B Southern California Edison Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML053430168 (79)

Text

I SOUTHERN CALIFORNIA Brian Katz Vice President

_ES EDISON' An EDISON INTERNVATIONAL 11Cornpany December 6, 2005 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOs. 50-361 and 50-362 PROPOSED CHANGE NUMBER (PCN) 521 APPLICATION TO AMEND THE TECHNICAL SPECIFICATIONTO DELETE THE REQUIREMENTS FOR FUEL HANDLING ISOLATION SIGNALS AND FUEL HANDLING BUILDING POST-ACCIDENT CLEANUP FILTER SYSTEMS

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Southern California Edison (SCE) hereby requests an amendment to the Technical Specifications (TS) for the San Onofre Nuclear Generating Station, Units 2 and 3.

The proposed amendment will delete TS Limiting Condition For Operation (LCO) 3.3.10, "Fuel Handling Isolation Signal (FHIS)," and TS LCO 3.7.14, 'Fuel Handling Building Post-Accident Cleanup Filter System," and their associated Surveillance Requirements.

The proposed amendment will also delete the Fuel Handling Building Post-Accident Cleanup Filter Systems from the Ventilation Filter Testing Program in administrative TS 5.5.2.12. SCE has concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of 'no significant hazards consideration' is justified.

SCE requests approval of the proposed License Amendment by November 30, 2006, with the amendment being implemented within 60 days of approval of this amendment request.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated California State Official.

IN1 P.O. Box 128 San Clemente. CA 92674-0128 949-368-9275 Fax 949-368-9881

Document Control Desk December 6, 2005 If you should have any questions regarding this submittal, please contact Mr. Jack Rainsberry at 949-368-7420.

Sincerely,

Enclosures:

1. Notarized affidavit

2. Licensee's evaluation of the proposed change Attachments:

1. Description and Assessment of Proposed Change

2. Existing Technical Specification Pages, Unit 2

3. Proposed Technical Specification Changes, Unit 2

4. Revised Technical Specification Pages, Unit 2

5. Existing Technical Specification Pages, Unit 3

6. Proposed Technical Specification Changes, Unit 3

7. Revised Technical Specification Pages, Unit 3

8. Summary of Licensee Commitments cc: B. S. Mallett, Regional Administrator, NRC Region IV, N. Kalyanam, NRC Project Manager, San Onofre Units 2 and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, California Department of Health Services, Radiologic Health Branch

Enclosure 1 Page 1 of 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )

EDISON COMPANY, ET AL. for a Class 103 ) Docket No. 50-361 License to Acquire, Possess, and Use )

A Utilization Facility as Part of ) Amendment Application No. 239 Unit No. 2 of the San Onofre Nuclear )

Generating Station )

SOUTHERN CALIFORNIA EDISON COMPANY, et al. pursuant to 10CFR50.90, hereby submit Amendment Application No. 239. This amendment application consists of Proposed Change Number (PCN) 521 to Facility Operating License NPF-10. PCN-521 is a request to delete Technical Specification (TS) 3.3.10, Fuel Handling Isolation Signal (FHIS), TS 3.7.14, 'Fuel Handling Building Post-Accident Cleanup Filter System," and to remove the latter system from the Ventilation Filter Testing Program in TS 5.5.2.12 for San Onofre Nuclear Generating Station Unit 2.

State of California County of San Diego Brian Katz, Vice President Subscribed and sworn to (or affirmed) before me on this +/-I .h day of b)(e( , 2005, by SXe 2,w-personally known to me ereproved to me on th basis of sati ... ...t ' .':ince-to be the person who appeared before me.

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Enclosure I Page 2 of 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )

EDISON COMPANY, ET AL. for a Class 103 ) Docket No. 50-362 License to Acquire, Possess, and Use )

A Utilization Facility as Part of ) Amendment Application No. 223 Unit No. 3 of the San Onofre Nuclear )

Generating Station )

SOUTHERN CALIFORNIA EDISON COMPANY, et al. pursuant to 10CFR50.90, hereby submit Amendment Application No. 223. This amendment application consists of Proposed Change Number (PCN) 521 to Facility Operating License NPF-1 5. PCN-521 is a request to delete Technical Specification (TS) 3.3.10, 'Fuel Handling Isolation Signal (FHIS), TS 3.7.14, 'Fuel Handling Building Post-Accident Cleanup Filter System," and to remove the latter system from the Ventilation Filter Testing Program in TS 5.5.2.12 for San Onofre Nuclear Generating Station Unit 3.

State of California County of San Diego Brian Katz, Vice President Z Subscribed and sworn to (or affirmed) before me on this day of D2 .

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,2005, by &?YLCL6 V personally known to me prnv-d tn me on the bass of catis to ocbe the person who appeared before me.

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PCN-521 ENCLOSURE 2 ATTACHMENT I DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGE

LICENSEE'S EVALUATION

Subject:

The proposed change is a request to delete Technical Specification 3.3.10,

'Fuel Handling Isolation Signal (FHIS)," and Technical Specification 3.7.14

'Fuel Handling Building Post-Accident Cleanup Filter System," and to remove the Fuel Handling Building Post-Accident Cleanup Filter System from the Ventilation Filter Testing Program in Technical Specification 5.5.2.12.

4.0 TECHNICAL ANALYSIS

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Regulatory Requirements/Criteria

7.0 REFERENCES

8.0 PRECEDENT Page 1 of 12

1.0 DESCRIPTION

This letter is a request to amend Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station Units 2 and 3 (SONGS 2 & 3), respectively.

The proposed change would delete Technical Specification (TS) 3.3.10, 'Fuel Handling Isolation Signal (FHIS)," and TS 3.7.14, 'Fuel Handling Building Post-Accident Cleanup Filter System,' and would also remove the Fuel Handling Building Post-Accident Cleanup Filter System from the Ventilation Filter Testing Program in TS 5.5.2.12. This submittal demonstrates that the FHIS and the Fuel Handling Building Post-Accident Cleanup Filter System do not meet any of the four regulatory criteria of 10 CFR 50.36 for inclusion in the Technical Specifications.

2.0 PROPOSED CHANGE

The proposed change will delete TS 3.3.10, 'Fuel Handling Isolation Signal (FHIS)," and TS 3.7.14 'Fuel Handling Building Post-Accident Cleanup Filter System," and will remove the Fuel Handling Building Post-Accident Cleanup Filter System from the Ventilation Filter Testing Program in TS 5.5.2.12.

At this time SONGS 2 & 3 do not plan to implement modifications to physically remove the filters or charcoal adsorbers from the system design.

Southern California Edison (SCE) will implement a Licensee Controlled Specification (LCS) change to transfer the operability and functional requirements of the isolation and cleanup systems to the LCS. The required surveillances will include the current requirements to test the system operation, including automatic isolation on high radiation. In this transfer the Fuel Handling Building Post-Accident Cleanup Filter System (PACFS) Limiting Condition for Operation requirement for two operable systems will be reduced to one system operable during movement of irradiated fuel in the fuel building. Completion Times for both FHIS and PACFS inoperabilities will be revised from 'Immediately' to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />' to allow for orderly completion of the Required Action after discovery of inoperability. The Fuel Handling Building PACFS will be removed from the Ventilation Filter Testing Program of TS 5.5.2.12, and testing of the charcoal adsorbers and the high efficiency particulate air filters will no longer be required. The LCS for FHIS will continue to require the surveillances currently contained in SRs 3.3.10.1, 3.3.10.2, 3.3.10.3, 3.3.10.4, 3.3.10.5. The LCS for PACFS will continue to require the surveillances currently contained in SRs 3.7.14.1 and 3.7.14.3. This will ensure a conservative defense in depth position by testing the initiation function of the FHIS system.

The Fuel Handling Building (FHB) airborne radiation monitors 2RE7822G1 and 2RE7823G2 (Unit 2) and 3RE7822G1 and 3RE7823G2 (Unit 3) (all four together identified as 2(3)RE7822G1 and 2(3)RE7823G2) provide for the automatic isolation of the FHB Ventilation System. As noted in the following Section, automatic isolation of the FHB Ventilation System is not a required safety function. However, the operability function will be maintained by moving the operability requirements for these monitors into the LCS.

The deletion of TS 3.3.10 and TS 3.7.14 will affect TS Table of Contents pages iii, iv, vii, and viii. These pages will reflect that TS 3.3.10 and TS 3.7.14 and their Bases are deleted.

Markups of the deleted Technical Specifications are provided in Enclosure 2 Attachments 3 and 6.

Page 2 of 12

The TS Bases for TS 3.3.10 and TS 3.7.14 will be deleted. As SONGS has a Technical Specification Bases change control program, and because this proposed change is straightforward (i.e., deletion of entire sections), a markup of the affected Bases pages is not provided in this license amendment request.

This license amendment request documents that the potential radiological consequences of a design basis fuel handling accident inside the Fuel Handling Building (FHA-FHB),

modeled without mitigation by the FHIS and the FHB PACFS, are within the guidelines of 10CFR100 for an individual at the Exclusion Area Boundary (EAB) and an individual at the Low Population Zone (LPZ) outer boundary, and are within the limits of 10CFR50, Appendix A, General Design Criterion 19 for a Control Room operator. Because these systems are not necessary for protection of members of the public and plant personnel, it is not appropriate to classify them as engineered safety features. Therefore, upon NRC approval of this amendment request, SCE intends to revise the Updated Final Safety Evaluation Report (Reference 7.1) to remove designations of these systems as engineered safety features.

3.0 BACKGROUND

The Fuel Handling Building Ventilation System (FHBVS) is designed to maintain a suitable environment for equipment operation and personnel access during normal operation. A subsystem, the FHB PACFS, is designed to mitigate the consequences of a release of radioactivity during normal operation and Anticipated Transients. On this basis, this subsystem is currently classified and designed as an Engineered Safety Features (ESF) air cleanup system. The design basis of the FHBVS is unchanged by this license amendment request. The FHBVS distributes air throughout the building from areas of low potential radioactivity to areas of higher potential activity. The design basis accident of interest for this system is the FHA-FHB. During fuel handling operations, a controlled space in the spent fuel pool area is maintained by closing the doors of the building. FHB airborne radiation monitors 2(3)RE7822G1 and 2(3)RE7823G2 will initiate isolation of the normal ventilation system and automatically initiate the filtration flow path upon detection of radioactivity released from a dropped fuel assembly.

4.0 TECHNICAL ANALYSIS

Updated Final Safety Analysis Report (UFSAR) Sections 15.7 and 15.10.7 document the various accidents that may occur inside the FHB. The event with the most severe offsite and control room radiological dose consequences is the FHA-FHB.

Per UFSAR Sections 15.7.3.4 and 15.10.7.3.4, the FHA-FHB dose analysis postulates the inadvertent dropping of a fuel assembly during fuel handling operations, and the consequent rupture of 60 fuel rods in the dropped assembly.

4.1 Current Licensing Basis FHA-FHB Dose Analysis The current FHA-FHB analysis of record (AOR) was performed using the methodology described in SONGS UFSAR Sections 15.7.3.4,15.10.7.3.4, Appendix 15B, Appendix 15.10.B (Reference 7.1) including the assumption that the FHB is open to the outside environment. The AOR uses the assumptions and Page 3 of 12

methodology of Regulatory Guide 1.25 (Reference 7.2) and Standard Review Plan 15.7.4 (Reference 7.4). Table 1 lists the primary assumptions and input parameters employed in the FHA-FHB dose AOR associated with the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the event as described in the UFSAR.

Consistent with the FHA-FHB dose AOR described in the UFSAR, the FHA-FHB dose analysis supporting this license amendment request does not model the generation of an Engineered Safety Feature Actuation System (ESFAS) fuel handling [building]

isolation signal (FHIS). The FHB normal ventilation exhaust is assumed to remain in operation throughout the FHA-FHB event. In addition, consistent with the FHA-FHB dose AOR described in the UFSAR, the FHA-FHB dose analysis supporting this license amendment request does not credit iodine and aerosol removal by the filters present in the FHB PACFS.

The only differences between the FHA-FHB dose AOR described in the UFSAR and the FHA-FHB dose analysis supporting this license amendment request are in the following input parameters:

1) 1000 cfm of unfiltered in-leakage into the control room, ratherthan the 10 cfm modeled in the FHA-FHB dose AOR, and

2) 1.75 radial peaking factor (RPF), rather than the 1.71 RPF modeled in the FHA-FHB dose AOR.

Table I lists the primary assumptions and input parameters employed in the FHA-FHB dose analysis associated with the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of the event.

The following assumptions reflect the discretionary conservatism of the analysis:

1) The fuel rod gap region is assumed to contain 12 percent of the fission product iodine inventory. This value is consistent with the current licensing basis. This value exceeds the 8 percent recommended by Regulatory Guide 1.183 (Reference 7.5) and Regulatory Guide 1.195 (Reference 7.6).

2) The spent fuel pool (SFP) water overall effective decontamination factor (DF) for iodine is assumed to be 100. This value is consistent with the current licensing basis. This value is smaller than the DF of 200 recommended by Regulatory Guide 1.183 and Regulatory Guide 1.195.

3) The total control room unfiltered inleakage rate is assumed to be 1000 dim, representing 990 cfm of unfiltered inleakage via the control room envelope (CRE) boundary, plus 10 cfm of unfiltered inleakage due to control room ingress and egress. The assumed unfiltered inleakage rate exceeds the CRE inleakage rate of 259 cfm (including uncertainty) based on CRE tracer gas test results (Reference 7.7). The assumed unfiltered inleakage rate also greatly exceeds the 10 cfm modeled in the FHA-FHB dose analysis of record.

The FHA-FHB dose analysis assumes that failure of the fuel rods results in an instantaneous release of all the noble gas and iodine gap activity in each failed fuel rod into the spent fuel pool water. The iodine and noble gas bubbles released from the damaged fuel pins pass up through the 23 feet of SFP water covering the Page 4 of 12

damaged fuel. The iodine and noble gas released from the SFP water are assumed to collect in the FHB atmosphere and be exhausted to the environment within two hours.

The acceptance limits for offsite radiation exposure are contained in Standard Review Plan (SRP) Section 15.7.4 (Reference 7.4), which defines "well within" 10 CFR Part 100 to be 25% or less of the 10 CFR 100 values. The resulting values for offsite doses are listed in Table 2.

TABLE I INPUT PARAMETERS USED FOR CALCULATING FHA-FHB RADIOLOGICAL CONSEQUENCES Source Term and FHB Parameters Proposed UFSAR (AOR)

SourceTermand_____Parameters_ Value Value Core Thermal Power, MWt 3,458 3,458 Time Between Plant Shutdown and Accident, hours 72 72 Radial Peaking Factor 1.75 1.71 Number of Damaged Fuel Rods 60 60 Fission Product Gases in Fuel Rod Gap Region, %

Krypton-85 30 30 Other Noble Gases 10 10 Iodine 12 12 Fraction of Gap Activity Released to the Spent Fuel Pool 100 100 W ater, % _ _ _ _ _ _ _ _ _ _ _ _

Minimum Water Depth Above Damaged Fuel Rods, feet 23 23 Spent Fuel Pool Water Decontamination Factors:

Nobles Gases 1 1 Iodine 100 100 Airborne Iodine Forms, %

Elemental 75 75 Organic 25 25 Fuel Handling Building model Fuel Handling [Building] Isolation Signal (FHIS) Not modeled Not modeled FHB Post-Accident Cleanup Filter System iodine removal Not modeled Not modeled Activity Release Duration from FHB, hours 2 2 FHB Net Free Volume, cubic feet 365,305 365,305 FHB Air Exhaust Flow Rate, cfm 25,581 25,581 Proposed UFSAR (AOR)

Exclusion Area Boundary (EAB) Parameters (0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) Value Value Atmospheric Dispersion Factor to EAB, sec/mi 2.72e-4 2.72e-4 Thyroid Inhalation Dose Conversion Factors ICRP-30 ICRP-30 EAB Breathing Rate, m3/sec 3.47e-4 3.47e-4 EAB Occupancy Factor 1.0 1.0 Proposed UFSAR (AOR)

Low Population Zone (LPZ) Parameters (0 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) Value Value Atmospheric Dispersion Factors to LPZ, sec/mr 7.72e-6 7.72e-6 Thyroid Inhalation Dose Conversion Factors ICRP-30 ICRP-30 LPZ Breathing Rate, m3/sec 3.47e-4 3.47e-4 LPZ Occupancy Factor 1.0 1.0 Page 5 of 12

TABLE I INPUT PARAMETERS USED FOR CALCULATING FHA-FHB RADIOLOGICAL CONSEQUENCES Proposed UFSAR (AOR)

Control Room (CR) Parameters (0 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) Value Value Atmospheric Dispersion Factor to CR, sec/m3 3.1e-3 3.1e-3 Thyroid Inhalation Dose Conversion Factors ICRP-30 ICRP-30 CR Breathing Rate, m4/sec 3.47e-4 3.47e-4 CR Occupancy Factor 1.0 1.0 CR Volume, cubic feet 266,920 266,920 CR Normal HVAC System Operation (0 to 3 minutes):

Normal Operation Unfiltered Inflow Rate, cfm 5,820 5,820 Total Unfiltered Inleakage Rate, cfm 1,000 10 CR Isolation (switchover to CREACUS), minutes 3 3 CREACUS Operation (3 minutes to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />):

Filtered Inflow Rate, cfm 4,400 4,400 Filtered Recirculation Rate, cfm 59,869 59,869 Total Unfiltered Inleakage Rate, cfm 1,000 10 Inflow and Recirculation Filter Efficiencies, %

Elemental Iodine 95 95 Organic Iodide 95 95 Particulates 99 99 Table 2 CALCULATED RADIOLOGICAL CONSEQUENCES Exclusion Area Boundary Dose SRP 15.7.4 Limits (0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose)

Thyroid 18.8 Rem 75 Rem Whole Body < 0.1 Rem 6 Rem Low Population Zone Dose SRP 15.7.4 Limits (event duration dose)

Thyroid 0.5 Rem 75 Rem Whole Body < 0.1 Rem 6 Rem Control Room Operator Dose GDC-19 (and SRP 6.4) Limits (event duration dose)

Thyroid 9.3 Rem 30 Rem (equivalent to 5 Rem WB)

Whole Body <0.1 Rem 5 Rem Beta Skin 1.2 Rem 30 Rem (equivalent to 5 Rem WB)

The offsite dose consequences are within the SRP Section 15.7.4 limits of 75 Rem thyroid and 6 Rem whole body. The calculated offsite doses are higher than the doses currently documented in UFSAR Section 15.10.7.3.4 due to the modeling of a 1.75 RPF, rather than the 1.71 RPF currently modeled in the FHA-FHB dose AOR.

Page 6 of 12

General Design Criterion 19 of 10 CFR Part 50 Appendix A specifies that adequate radiation protection is to be provided to permit access and occupancy of the control room under accident conditions without personnel exposures in excess of 5 Rem whole body (WB) or its equivalent to any part of the body for the duration of the accident. The SRP Section 6.4 (Reference 7.3) limits are 5 Rem whole body gamma and 30 Rem thyroid inhalation for the control room operator. The resulting values for control room operator doses are listed in Table 2. The control room doses are higher than the doses currently documented in UFSAR Section 15.10.7.3.4 due to differences in the following input parameters:

1) 1000 cfr of unfiltered in-leakage into the control room, rather than the 10 cfm modeled in the FHA-FHB dose AOR, and

2) 1.75 RPF, rather than the 1.71 RPF modeled in the FHA-FHB dose AOR.

Based on the evaluation, SCE concludes that the radiological consequences of removing both Technical Specifications 3.3.10, 'Fuel Handling Isolation Signal (FHIS)," and 3.7.14, "Fuel Handling Building Post-Accident Cleanup Filter System,"

remain acceptable.

4.2 Impact on Alternative Source Term FHA-FHB Dose Analysis Full-scope implementation of the Alternative Source Term (AST) methodology requires re-analysis of the Updated Final Safety Analysis Report (UFSAR) Chapter 15 accident analyses, including the FHA-FHB. Pursuant to 10 CFR 50.90, Southern California Edison had previously submitted Amendment Application Numbers 231 and 215 for San Onofre Units 2 and 3, respectively. These amendment requests, referred to as Proposed Change Number PCN-555, would revise the SONGS 2 & 3 accident source term used in the design basis radiological consequences analyses (Reference 7.8).

Consistent with the scope of this license amendment request, the FHA-FHB AST dose analysis previously submitted with PCN-555 does not model the generation of an ESFAS FHIS. The FHB normal ventilation exhaust is assumed to remain in operation throughout the FHA-FHB event.

Consistent with the scope of this license amendment request, the FHA-FHB AST dose analysis previously submitted with PCN-555 does not credit iodine and aerosol removal by the filters present in the FHB PACFS.

Approval of this license amendment request will not alter the modeling in the FHA-FHB AST dose analysis. Consequently, approval of this license amendment request will not impact the FHA-FHB AST dose analysis previously submitted with PCN-555.

4.3 Technical Analysis Conclusion The proposed change is to delete TS 3.3.10 and TS 3.7.14, and to remove the FHB PACFS from the Ventilation Filter Testing Program in TS 5.5.2.12. SONGS 2 and 3 will implement Licensee Controlled Specification changes to maintain a requirement for the operability of the FHBVS outside the requirements of the Ventilation Filter Testing Program of TS 5.5.2.12.

These changes are justified by the fact that the FHA-FHB dose analysis demonstrates that Page 7 of 12

offsite and control room doses will remain within the acceptance criteria with no credit for FHIS actuation, and no credit for iodine and aerosol removal by the filters present in the FHB PACFS. Because these systems are not necessary for protection of members of the public and plant personnel, it is not appropriate to classify them as engineered safety features.

Therefore, upon NRC approval of this amendment request, SCE intends to revise the Updated Final Safety Evaluation Report (Reference 7.1) to remove designations of these systems as engineered safety features.

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Southern California Edison has evaluated whether or not a significant hazards consideration is involved with the proposed amendments by focusing on the three standards set forth in 10 CFR 50.92, Issuance of amendments,' as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The Fuel Handling Building (FHB) Post-Accident Cleanup Filter System (PACFS) and its initiating radiation monitors are not involved in the initiation of any accidents. The PACFS is not credited with providing any supplemental filtration of releases from an accident occurring in the FHB. The PACFS was designed to provide an accident mitigation function by isolating the system and filtering the radioiodines that may be released from a damaged fuel assembly in the event of a Fuel Handling Accident (FHA). The charcoal adsorber was the primary component that supported this filtration function. However, the FHA dose consequences analysis has demonstrated that doses due to the FHA, to both the public and the control room operators, remain well within regulatory acceptance limits even assuming no credit for either isolation or filtration. The charcoal filtration function is not required and need not be tested.

Thus, there is no required safety function provided by either the ventilation system or the airborne radiation monitor in the event of a fuel handling accident Therefore, the proposed changes do not involve a significant increase in the probability or consequences of any accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The FHB PACFS and its initiating radiation monitors do not initiate any accidents.

The PACFS was designed to provide an accident mitigation function by isolating the system and filtering the radioiodines that may be released from a damaged fuel assembly in the event of a Fuel Handling Accident. Analysis shows that the isolation and filtration functions are not required. The charcoal adsorber cannot influence any Page 8 of 12

accident initiators. The deletion of the Technical Specification requirements does not impact this conclusion and does not influence any new potential accident scenarios in any way.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The FHB PACFS and its initiating radiation monitors were designed to provide an accident mitigation function by filtering the radioiodines that may be released from a damaged fuel assembly in the event of a Fuel Handling Accident. Analysis of the FHA in the FHB demonstrates that the margin of safety provided by the Technical Specification requirement will not change. Since the control room charcoal adsorber is capable of accommodating the design basis loss of coolant accident fission product halogen loadings, which are more limiting than the fuel handling accident loadings, more than adequate design margin is available with respect to postulated FHA releases. The margin of safety, in terms of the dose limitations of I OCFR100 and 10CFR50 Appendix A, General Design Criterion 19, has not been significantly reduced.

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

Based on the above, Southern Califomia Edison concludes that the proposed amendments present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of 'no significant hazards consideration' is justified.

5.2 Applicable Regulatory Requirements/Criteria 5.2.1 10 CFR 50.36. "Technical Specifications" 10 CFR 50.36(c)(2)(ii) states: "A technical specification limiting condition for operation of a nuclear reactor must be established for each item meeting one or more of the following criteria:

"(A) Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary."

The San Onofre Nuclear Generating Station Units 2 and 3 (SONGS 2 & 3) Fuel Handling Isolation Signal (FHIS) instrumentation is used to detect airborne radioactivity resulting from a FHA-FHB, not to detect a degradation of the reactor coolant pressure boundary.

Page 9 of 12

'(B) Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.'

The SONGS 2 & 3 FHIS and FHB PACFS represent systems and not process variables, design features, or operating restrictions.

'(C) Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier."

The SONGS 2 & 3 FHIS and PACFS are designed to mitigate the consequences of fuel rod failures caused by a fuel handling accident inside the FHB (FHA-FHB). The fuel rods are fission product barriers. However, the licensee has shown that the consequences of a postulated FHA-FHB are acceptable without credit for operation of the FHIS and PACFS. Therefore, the FHIS and PACFS are not part of the primary success path for accident response.

'(D) Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.'

The licensee has shown that the FHIS and PACFS are not significant to public health and safety because these systems are not needed to mitigate the consequences of a FHA-FHB. Testing of the PACFS under the Ventilation Filter Testing Program is not required.

Therefore, the SONGS 2 & 3 FHIS and PACFS do not meet any of the four regulatory criteria for inclusion in the Technical Specifications and may be deleted from the Technical Specifications.

5.2.2 10 CFR 100.11. "Determination of exclusion area, low population zone, and population center distance" [for Stationary Power Reactor Site Applications Before January 10. 19971 10 CFR 100.11 (a) sets forth guidelines for the exposure of individuals at the boundaries of the exclusion area and low population zone to radiation released from hypothetical accidents at nuclear power plants. For the FHA-FHB at SONGS 2 & 3, analysis shows that these guidelines are met without any mitigation from the FHIS and PACFS. Therefore, deletion of the FHIS and PACFS from the SONGS 2 & 3 Technical Specifications would have no affect on individuals so exposed.

5.2.3 10 CFR 50. Appendix A. "General Design Criteria for Nuclear Power Plants" General Design Criterion 19 - Control room General Design Criterion 19 requires adequate radiation protection to permit access and occupancy of the control room under accident conditions, and sets forth dose limits for control room personnel for the duration of an accident. For the FHA-FHB at SONGS 2 & 3, analysis shows that these limits are met without any mitigation from Page 10 of 12

the FHIS and PACFS. Therefore, deletion of the FHIS and PACFS from the SONGS 2 & 3 Technical Specifications and discontinuation of PACFS filter testing would have no affect on personnel so exposed.

General Design Criterion 61 - Fuel storage and handling and radioactivity control General Design Crterion 61 requires fuel storage and handling systems to be designed with appropriate containment, confinement and filtering systems. The proposed change would not implement design modifications to the FHIS and PACFS.

Specifically, Southern California Edison does not plan to physically remove the filters or charcoal adsorbers from the PACFS design. The LCS will continue to require the surveillances currently contained in SRs 3.3.10.1, 3.3.10.2, 3.3.10.3, 3.3.10.4, 3.3.10.5, 3.7.14.1 and 3.7.14.3. The FHB airborne radiation monitors 2(3)RE7822G1 and 2(3)RE7823G2 will continue to provide for the automatic isolation of the FHB Ventilation System.

Moreover, for the FHA-FHB at SONGS 2 & 3, analysis has shown that regulatory limits and guidelines are met without any mitigation from the FHIS and PACFS.

Therefore, deletion of the FHIS and PACFS from the SONGS 2 & 3 Technical Specifications would have no affect on "appropriate t system design.

5.2.4 Regulatory Requirements/Criteria Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

Page 11 of 12

7.0 REFERENCES

7.1 San Onofre Nuclear Generating Station (SONGS) 2 & 3, Updated Final Safety Analysis Report.

7.2 Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors," 1972.

7.3 NUREG-0800, US NRC Standard Review Plan Section 6.4.

7.4 NUREG-0800, US NRC Standard Review Plan Section 15.7.4.

7.5 Regulatory Guide 1.183, "Altemative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Plants," July 2000.

7.6 Regulatory Guide 1.195, 'Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors,"

May 2003.

7.7 SCE Letter to U.S. Nuclear Regulatory Commission, 'Docket Nos. 50-361 and 50-362, Response to Generic Letter 2003-01, 'Control Room Habitability', Tracer Gas Test Results, San Onofre Nuclear Generating Station Units 2 and 3",

September 17, 2004.

7.8 San Onofre Nuclear Generating Station, Units 2 and 3, Docket Nos. 50-361 and 50-362, Proposed Change Number (PCN) 555, Alternative Source Term, is a request dated December 27, 2004 for full-scope implementation of the alternative source term described in Regulatory Guide 1.183.

8.0 PRECEDENT By letter dated November 21, 2001, NRC staff approved license amendment number 176 for the Waterford Steam Electric Station, Unit 3, to delete TS 3.9.12, "Fuel Handling Building Ventilation System," and TS 3.3.3.1 requirements for the Fuel Storage Pool area radiation monitors. (TAC No. MB2462, ADAMS accession number ML013270214)

By letter dated December 12, 2003, NRC staff approved license amendment number 248 for Three Mile Island Unit 1 to delete the TS requirements for the auxiliary and fuel handling building air treatment system. (TAC No. MB6695, ADAMS accession number ML033140383)

Page 12 of 12

PCN-521 ENCLOSURE 2 ATTACHMENT 2 EXISTING TECHNICAL SPECIFICATION PAGES, UNIT 2

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . . . . . . . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start . . . . 3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . 3.3-39 3.3.10 Fuel Handling Isolation Signal (FHIS) . . . . . . 3.3-42 3.3.11 Post Accident Monitoring Instrumentation (PAMI) . 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . 3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . . . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . . 3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . 3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . . 3.4-13 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . . 3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . . 3.4-16 3.4.6 RCS Loops- MODE 4 ... . . ..... 3.4-18 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . . 3.4-21 3.4.8 RCS Loops- MODE 5, Loops Not Filled . . . . . . . 3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . . 3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . 3.4-28 3.4. 11 Not Used 3.4. 12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 2560 F . . . . . . . 3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 2560 F . . . . . . . . 3.4-35 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . . 3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . . 3.4-39 3.4.15 RCS Leakage Detection Instrumentation . . . . . . 3.4-44 3.4.16 RCS Specific Activity . . . . . . . . . . . . . . 3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . 3.5-1 3.5.2 ECCS- Operating . . . . . . . . . . . . . . . . . 3.5-4 3.5.3 ECCS-Shutdown . . . . . . . . . . . . . . . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . . . . . . . 3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . 3.5-11 (continued)

SAN ONOFRE--Unit 2 ii i Amendment No. 127

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks . . . . . . . . . . . . 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . . . 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . . . . 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . . . 3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . . . 3.6-21 3.6.7 Not Used I 3.6.8 Containment Dome Air Circulators . . . . . . . 3.6-25 3.7 PLANT SYSTEMS .................. 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) 3.7-16 3.7.7 Component Cooling Water (CCW) System. 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System . . . . . . . . . . . . 3.7-27 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources- Operating . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources -Shutdown . . . . . . .. 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and St arting Air . . . 3.8-20 3.8.4 DC Sources- Operating . . . . . . . . . . . . . . 3.8-23 3.8.5 DC Sources- Shutdown . . . . . . . . . . . . . . . 3.8-27 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . 3.8-30 3.8.7 Inverters - Operating . . . . . . . . . . . . . . . 3.8-34 3.8.8 Inverters- Shutdown . . . . . . . . . . . . . . . 3.8-36 3.8.9 Distribution Systems -Operating . . . . . . . . . 3.8-38 3.8.10 Distribution Systems -Shutdown . . . .. . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 2 iv Amendment No. 159

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . B 3.3-145 B 3.3.10 Fuel Handling Isolation Signal (FHIS) B 3.3-152 B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) .B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . .B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . .B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits .B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . .B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .B 3.4-9 B 3.4.4 RCS Loops -MODES 1 and 2 . . . . . . . . . . . . .B 3.4-23 B 3.4.5 RCS Loops -MODE 3 . . . . . . . . . . . . . . . .B 3.4-27 B 3.4.6 RCS Loops -MODE 4 . . . . . . . . . . . . . . . .B 3.4-31 B 3.4.7 RCS Loops -MODE 5, Loops Filled . . . . . . . . .B 3.4-36 B 3.4.8 RCS Loops-MODE 5, Loops Not Filled . . . . . . .B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .B 3.4-51 B 3.4. 11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature - 256°F . .. . . . .B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 256°F . . . . . . . .B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage .B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation .B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . . B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . B 3.5-1 B 3.5.2 ECCS -Operating . . . . . . .. . . . . . . . . . B 3.5-11 B 3.5.3 ECCS- Shutdown . . . . . . . . . . . . . . . . . . B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) . . . . . . . B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . .B 3.6-1 B 3.6.1 Containment. . . ... B 3.6-1 B 3.6.2 Containment Air Locks . . . . . . .. . . . . . .B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . . . . . . . .B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . . . . . . . .B 3.6-27 B 3.6.5 Containment Air Temperature . . . . . . . . . . .B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System . . . . . . .B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . . . . . . . .B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . . . . . . . .B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . . . . . . . .B 3.6-53 (continued)

SAN ONOFRE--Unit 2 vii Amendment No. 127

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS . . .... . .. . . .. . . . .. . . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . . B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . . B 3.7-39 B 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . B 3.7-43c B 3.7.8 Salt Water Cooling System (SWC) . . . . . . . . . B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . . B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) ...... . ......... .. . B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System. . . . . . . . . . . . . B 3.7-63 B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . .B 3.8-1 B 3.8.1 AC Sources- Operating . . . . . . . . . . . . . .B 3.8-1 B 3.8.2 AC Sources -Shutdown . . . . . . .B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Ai r . . . B 3.8-36 B 3.8.4 DC Sources- Operating . . . . . . . . . . . . ..B 3.8-46 B 3.8.5 DC Sources-Shutdown . . . . . . . . . . . . . ..B 3.8-56 B 3.8.6 Battery Cell Parameters . . . . . . . . . . . . .B 3.8-60 B 3.8.7 Inverters- Operating . . . . . . . . . . . . . . .B 3.8-67 B 3.8.8 Inverters - Shutdown . . . . . . . . . . . . . . .B 3.8-71 B 3.8.9 Distribution Systems -Operating . . . .. . . . .B 3.8-75 B 3.8.10 Distribution Systems -Shutdown . . . . . . . . . .B 3.8-84 B 3.9 REFUELING OPERATIONS . . . . . . . 3.9-1 .B B 3.9.1 Boron Concentration . . . . . . . . . . . . . . B 3.9-1 .

B 3.9.2 Nuclear Instrumentation . . . . . . . . . . . .B 3.9-5 .

B 3.9.3 Containment Penetrations . . . . . . . . . B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation -High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation -Low Water Level . . . B 3.9-21 B 3.9.6 Refueling Water Level . . . . . . . . . . . . ..B 3.9-25 .

SAN ONOFRE--Unit 2 viii Amendment No. 129

FHIS 3.3.10 3.3 INSTRUMENTATION 3.3.10 Fuel Handling Isolation Signal (FHIS)

LCO 3.3.10 One FHIS channel shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel in the fuel handling building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Actuation Logic, A.1 Place one OPERABLE Immediately Manual Trip, or Fuel Handling required channel of Building Post gaseous radiation Accident Cleanup monitor inoperable System train in during movement of operation.

irradiated fuel assemblies. OR A.2 Suspend movement of Immediately irradiated fuel assemblies in the fuel handling building.

(continued)

SAN ONOFRE--UNIT 2 3.3-42 Amendment No. 127

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

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

Verify radiation monitor setpoint Allowable Values:

Airborne Gaseous:

• 6E4 cpm above background.

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

Testing of Actuation Logic shall include the actuation of each initiation relay and verification of the proper operation of each initiation relay. I Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Actuation Logic channel.

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

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

SAN ONOFRE--UNIT 2 3.3-43 Amendment No. +-17,147

Fuel Handling Building Post-Accident Cleanup Filter System 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System LCO 3.7.14 Two Fuel Handling Building Post-Accident Cleanup Filter System trains shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Fuel Handling A.1 Restore Fuel Handling 7 days Building Post-Accident Building Post-Cleanup Filter System Accident Cleanup train inoperable. Filter System train to OPERABLE status.

B. Required Action and B.1 Place OPERABLE Fuel Immediately Associated Completion Handling Building Time of Condition A Post-Accident Cleanup not met during Filter System train movement of irradiated in operation.

fuel assemblies in the fuel building. OR B.2 Suspend movement of Immediately irradiated fuel assemblies in the fuel building.

(continued)

SAN ONOFRE--UNIT 2 3.7-27 Amendment No. 127

Fuel Handling Building Post-Accident Cleanup Filter System 3.7.14 CONDITION REQUIRED ACTION COMPLETION TIME C. Two Fuel Handling C.1 Suspend movement of Immediately Building Post-Accident irradiated fuel Cleanup Filter System assemblies in the trains inoperable fuel building.

during movement of irradiated fuel assemblies in the fuel building.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Operate each Fuel Handling Building Post- 31 days Accident Cleanup Filter System train for 2 10 continuous hours with the heaters operating.

SR 3.7.14.2 Perform required Fuel Handling Building In accordance Post-Accident Cleanup Filter System filter with the VFTP testing in accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.14.3 Verify each Fuel Handling Building Post- 24 months Accident Cleanup Filter System train actuates on an actual or simulated actuation signal.

SAN ONOFRE--UNIT 2 3.7-28 Amendment No. 127

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5.5.2. 11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation systems, "Control Room Emergency Air Cleanup System" and "Fuel Handling Building Post-accident Cleanup Filter System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested per the methodology of ASTM D3803-1989 at 300 C and 70%

relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate. I Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued)

SAN ONOFRE--UNIT 2 5.0-19c Amendment No. ,4-0,187

PCN-521 ENCLOSURE 2 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION CHANGES, UNIT 2

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . . . . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start . . . . 3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . 3.3-39 3.3.10 Fuel Handling Isolation Signal (F[III)Nt e- .. 42 3.3.11 Post Accident Monitoring Instrumentation (PAMI) . 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . 3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . .. 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . 3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . 3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . . 3.4-13 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . . 3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . . 3.4-16 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . . 3.4-18 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . . 3.4-21 3.4.8 RCS Loops- MODE 5, Loops Not Filled . . . . . . . 3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . 3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . 3.4-28 3.4. 11 Not Used 3.4. 12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 256 0F . . . . . . . 3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 256 0F . . . . . . . . 3.4-35 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . . 3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . . 3.4-39 3.4.15 RCS Leakage Detection Instrumentation . . . . . . 3.4-44 3.4.16 RCS Specific Activity . . . . . . . . . . . . . . 3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . .3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . .3.5-1 3.5.2 ECCS -Operating . . . . . . . . . . . . . . . . .3.5-4 3.5.3 ECCS -Shutdown . . . . . . . . . . . . . . . . . .3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . .3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . * .3.5-11 (continued) i . i Amendment No. 127' SAN ONOFRE--Unit 2

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks . . . .. . . . . . . . . 3.6-3 3.6.3 Containment Isolation Valves . . . . . .. . . . 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . . . . . 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . . 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . 3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . . . . 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators . . . . . . . . 3.6-25 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Fuel Ikindling Buildit- 1.0eAidnt Gleanup rilter systI: t .tt..d-3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level .. . . .. . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources- Operating . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources- Shutdown . . . . . . . . . . . . . . . 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . . 3.8-20 3.8.4 DC Sources- Operating . . . . . . . . . . . . . . 3.8-23 3.8.5 DC Sources- Shutdown . . . . . . . . . . . . . . . 3.8-27 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . 3.8-30 3.8.7 Inverters - Operating . . . . . . . . . . . . . . . 3.8-34 3.8.8 Inverters - Shutdown . . . . . . . . . . . . . . . 3.8-36 3.8.9 Distribution Systems -Operating . . . . . . . . . 3.8-38 3.8.10 Distribution Systems -Shutdown . . . . . . . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 2 iv Amendment No. +59

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start . . . . . . . B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS). . B 3.3-135 B 3.3.9 flnntrnl Room Isolation Signal (CRIS). . B 3.3-145 B 3.3.10 Not UsedFuel Handling Isalation Signal (FIIIS)

B 3.3. 11 Post Accident Monitoring Instrumentation (PAMI) B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits . B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . . B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . B 3.4-9 B 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . . B 3.4-23 B 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . . B 3.4-27 B 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . . B 3.4-31 B 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . . B 3.4-36 B 3.4.8 RCS Loops -MODE 5, Loops Not Filled . . . . . . . B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . . B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 256 0 F . . . . . . . B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 256°F . . . . . . . . B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . . B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . . B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation . . . . . . B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .. . . . . . . B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . .. . . . . . B 3.5-1 B 3.5.2 ECCS- Operating . ...... .... B 3.5-11 B 3.5.3 ECCS -Shutdown . . . . . . . . . . . . . . . . . . B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) . . . . . . . B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . . B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . . . . . . B 3.6-1 B 3.6.2 Containment Air Locks . . . . . . . . . . . . . .B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . . . . . . . .B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . . . . . . . .B 3.6-27 B 3.6.5 Containment Air Temperature . . .. . . . . . . .B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System . . . . .B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . . . . . . . . B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . . . . . . . . B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . . . . . . . . B 3.6-53 (continued)

SAN ONOFRE--Unit 2 vii Amendment No. +2-7

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS. . . ..... B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System. .B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . . B 3.7-39 B 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . B 3.7-43c B 3.7.8 Salt Water Cooling System (SWC) . . . . . . . . . B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . . B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . B 3.7-56 B 3.7.12 Not Used B 3.7.13 NnO II-;d B 3.7.14 Not UsedFuel Handling Building Post Accident Cleanup Filter System. . . . . . . . . . . . . B3.7 63 B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . .. . . . .B 3.8-1 B 3.8.1 AC Sources- Operating . . . . . . . . .. . . . .B 3.8-1 B 3.8.2 AC Sources- Shutdown . . . .. . . . . B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . .B 3.8-36 B 3.8.4 DC Sources -Operating . . . . . . . . . .. . . .B 3.8-46 B 3.8.5 DC Sources -Shutdown . . . . . . . . . .. . . . .B 3.8-56 B 3.8.6 Battery Cell Parameters . . . . . . . .. . . . .B 3.8-60 B 3.8.7 Inverters -Operating . . . . . . . . . .. . . . .B 3.8-67 B 3.8.8 Inverters-Shutdown . . . . . . . . . .. . . . .B 3.8-71 B 3.8.9 Distribution Systems -Operating . . . .. . . . .B 3.8-75 B 3.8.10 Distribution Systems -Shutdown . . . . .. . . . .B 3.8-84 B 3.9 REFUELING OPERATIONS . . . . . . . B 3.9-1 B 3.9.1 Boron Concentration . . . . . . . . . . . . . . . B 3.9-1 B 3.9.2 Nuclear Instrumentation . . . . . . . . . . . . . B 3.9-5 B 3.9.3 Containment Penetrations . B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation- High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation- Low Water Level . . . . . . . . . B 3.9-21 B 3.9.6 Refueling Water Level . . . . . . . . . . . . . . B 3.9-25 SAN ONOFRE--Unit 2 viii Amendment No. 4 FI..1 3.3. 10 3.I-HS{-RdMENTATION+

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AR-TONS CONDITION REQUIRED ACTION COMPLETION TIME A. Actuation Logic, A.1 Placc one OP[RABLE Immediately Manual Trip, or Fuel llandling reguired channcl of Building Pest gaseug radi at'o Aeeident Cleanup oniatIr inapUraH-e System train in urg movemer..t-. apfratian irradiated fuei assembli es. eR A.2 Suspend rnovement of Ifmmfledi-aele-y irradiated fuel assemblies in the fuel hand!ling!

building.

SAN ONOFRE--UNIT 2 3.3-42 Amendment No. +

3^I- In EREVAE LfCFQUEMEN+N SRn 3.1O.1 Perform a CHANNEL CHER or :_ iIed FH gu radiation monitoV c.,anr.,l.

SR 3.3.10.2 Perform a CIIANNLL FUNCTIONAL TEST ont 9-^ days, reg-%uired FHIS radiation monmitor ehannel.

Veri fy radi atioan fmonitor setpaintt Al oaabl e Airborne Gaseous. +/-6E4 epmn above SR~ 32.3.1O3 NOTE-Testing of Actuation LogiU shall includc the actuation of caeh initiation relay and verification of the proper operation of each imitiatio~n relay.

reguired FIRS A1tuation Logie 1hannt4.

U rcguirIdI FIRS anual Trip logiU.

SR 33..10.5 Perform a CHANNEL CALIBRATION on r-Ouir-d 1-8----h RIS radiation Vmolnitor channul .

SAN ONOFRE--UNIT 2 3.3-43 Amendment No. 127,147

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.asUC I GNDiTIN nrEIRED AGTeNM G LET-INe TME A. One Fuel Handling ^

A. lRestore FuCi Handling Idays Building Post Aeeidicttrn Btling ,-ot-Cleanup Filter System Aftident Clearfup train inoperable. Filter System trairn to OPERABLE status.

B. Required Antion and B.1 Place OPERABLE Fuc lmmediatey Associated Comnpletion Handling Building Time of Condition A Post-Accident Cleanup not-met durig rFiltcr System train movement of irradiated ation.

fuel assemblies in thte fuel buildingq.- eR B.2 Suspend movement of Immedi ately irradiated fuel assemblics in the fuel #build.

teonti nuea)

SAN ONOFRE--UNIT 2 3.7-27 Amendment No. 4-7~

r._ I lJ :_ n..:-I J: n__ ^ __: J. rlI tUe! liandiig uulI( ing lO t-AiCCdefit GLear1 up I iter bystem 3.7.14 ACTIONS (eontinued)

CON4+ON REQUIRED A-G+/-I=N GOMPLETfION TIME C. Two Fuel lHandling C.1 Suspcnd movement of immedi ate+y Building Post Accident irradiated fuel Cleanup Filter System assemblies in the trainsina erubl fUl bUTUIding.

during oveaent of irradiated fuel assamblics in the fuel SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY*

SR 3.7.14.1 Operate Fuel Handling Building Post Fuc ..n y-q Accident Clcanup Filter System train for t10 eantinuous hours with the heaters SR 3.7.14.2 Perform required Fuel Handling Building In aeerdanee Post Acident Clcanup Filtcr System filter with the V'FTP testing in accordance with the Ventilation Filter Testing Program (VFTP).

JR 3.7.14.3 Verify I aeh Fuel Handling Building Post4 months Accident Cleanup Filter System train actuates an an aetual or simnulated actuation signal.

SAN ONOFRE--UNIT 2 3.7-28 Amendment No. +2-,i

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Tube Surveillance Program (continued)

5. 5.2. 11. 1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5. 5.2. 11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation systemy7 "Control Room Emergency Air Cleanup System." and "Fuel kradling Building Post accideet Cleanup Filter System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested at 300C and 70%

per the methodology of ASTM D3803-1989 relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.

Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued)

SAN ONOFRE--UNIT 2 5.0-19c Amendment No. +4-G, A6g

PCN-521 ENCLOSURE 2 ATTACHMENT 4 REVISED TECHNICAL SPECIFICATION PAGES, UNIT 2

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start . . . . 3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . 3.3-39 3.3.10 Not Used 3.3. 11 Post Accident Monitoring Instrumentation (PAMI) . 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . . .3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . .3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . .3.4-13 3.4.4 RCS Loops -MODES 1 and 2 . . . . . . . . . . . . . 3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . .3.4-16 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . .3.4-18 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . .3.4-21 3.4.8 RCS Loops- MODE 5, Loops Not Filled . . . . . . . 3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . 3.4-28 3.4. 11 Not Used 3.4. 12. 1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 2560 F . . . . . . .3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 2560 F . . . . . . . .3.4-35 3.4.13 RCS Operational LEAKAGE . .3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . .3.4-39 3.4. 15 RCS Leakage Detection Instrumentation . . . . . .3.4-44 3.4. 16 RCS Specific Activity . . . . . . . . . . . . . .3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . 3.5-1 3.5.2 ECCS- Operating . . . . . . . . . . . . . . . . . 3.5-4 3.5.3 ECCS- Shutdown . . . . . . . . . . . . . . . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . . . . . . . 3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . 3.5-11 (continued) i . i SAN ONOFRE--Unit 2 Amendment No.

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . .. . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . .. . . 3.6-1 3.6.2 Containment Air Locks . . . . . . . . . . . . . . 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . . . . . 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . . . . . . 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . . . 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . .. . ..3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . .. . . 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators. .. . . 3.6-25 3.7 PLANT SYSTEMS ................ . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System. . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-1.21) . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Not Used 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources -Operating . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources -Shutdown . . . . . . . . . . 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . . 3.8-20 3.8.4 DC Sources -Operating . . . . . . . . . . . . . . 3.8-23 3.8.5 DC Sources -Shutdown . . . . . . . . . . . . . . . 3.8-27 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . 3.8-30 3.8.7 Inverters -Operating . . . . . . . . . . . . . . . 3.8-34 3.8.8 Inverters - Shutdown . . . . . . . . . . . . . . . 3.8-36 3.8.9 Distribution Systems - Operating . . . . . . . . . 3.8-38 3.8.10 Distribution Systems- Shutdown . . . . . . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 2 i v Amendment No.

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start . . . . . . . B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS). . B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS). . B 3.3-145 B 3.3.10 Not Used I B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) . B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . . B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . . B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits . B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . .B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . B 3.4-9 B 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . . B 3.4-23 B 3.4.5 RCS Loops -MODE 3 . . . . . . . . . . . . . . . .B 3.4-27 B 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . .B 3.4-31 B 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . .B 3.4-36 B 3.4.8 RCS Loops -MODE 5, Loops Not Filled . . . . . . .B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 256°F . . . . . . . B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 256°F . . . . . . . B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation . . . . . B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . .. B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . . .B 3.5-1 B 3.5.2 ECCS -Operating . . . . . . . . . . . .B 3.5-11 B 3.5.3 ECCS -Shutdown . . . . . . . . . . . . .. B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) .. B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . . .. B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . .. B 3.6-1 B 3.6.1 Containment . . .B 3.6-1 B 3.6.2 Containment Air Locks . . . . .. . . .B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . . .. B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . . .B 3.6-27 B 3.6.5 Containment Air Temperature . . . . . .B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System .B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . . .B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . . .. B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . . .. B 3.6-53 (continued)

SAN ONOFRE--Unit 2 vii Amendment No.

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS . ... B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . .B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . .B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . .B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . .B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . .B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . .B 3.7-39 B 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . B 3.7-43c B 3.7.8 Salt Water Cooling System (SWC) . . . . . . . . . B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . . B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Not Used B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . B 3.8-1 B 3.8.1 AC Sources- Operating . . . . . . . . . . . . . .B 3.8-1 B 3.8.2 AC Sources- Shutdown . . . .. B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ... B 3.8-36 B 3.8.4 DC Sources- Operating . . . . . . . . . . . ... B 3.8-46 B 3.8.5 DC Sources- Shutdown . . . . . . . . . . . . . . .B 3.8-56 B 3.8.6 Battery Cell Parameters . . . . . . . . . . .B 3.8-60 B 3.8.7 Inverters - Operating . . . . . . . . . . . . .. B 3.8-67 B 3.8.8 Inverters - Shutdown . . . . . . . . . . . . . . .B 3.8-71 B 3.8.9 Distribution Systems- Operating . . . . . . . . .B 3.8-75 B 3.8.10 Distribution Systems -Shutdown . . . . . . . . . .B 3.8-84 B 3.9 REFUELING OPERATIONS . . . . . . . . . . . . . . . . .B 3.9-1 B 3.9.1 Boron Concentration . . . . . . . . . . . . . . .B 3.9-1 B 3.9.2 Nuclear Instrumentation . . . . . . . . . . . . .B 3.9-5 B 3.9.3 Containment Penetrations . . . . . . . . .B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation -High Water Level . . . . . B 3.9-16 .

B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation -Low Water Level . 3.9-21 .B B 3.9.6 Refueling Water Level . . . . . . . . . . . B 3.9-25 .

SAN ONOFRE--Unit 2 viii Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3. 3-42 Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3. 3-43 Amendmnent No.

THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3 .7-27 Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK SAN ONOFRE--UNIT 2 3 .7-28 Amendment No.

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5.5.2.11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation system "Control Room Emergency Air Cleanup System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested at 30 0C and 70%

per the methodology of ASTM D3803-1989 relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.

Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued)

SAN ONOFRE--UNIT 2 5 .0-19c Amendment No.

PCN-521 ENCLOSURE 2 ATTACHMENT 5 EXISTING TECHNICAL SPECIFICATION PAGES, UNIT 3

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . . . . . . . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3.3.7 Diesel Generator (DG) -Undervoltage Start . . . .

3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . 3.3-39 3.3.10 Fuel Handling Isolation Signal (FHIS) . . . . . . 3.3-42 3.3. 11 Post Accident Monitoring Instrumentation (PAMI) 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . . .3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . .3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . .3.4-13 3.4.4 RCS Loops -MODES 1 and 2 . . . . . . . . . . . . .3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . .3.4-16 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . .3.4-18 3.4.7 RCS Loops -MODE 5, Loops Filled . . . . . . . * *3.4-21 3.4.8 RCS Loops -MODE 5, Loops Not Filled . .3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .3.4-28 3.4.11 Not Used 3.4. 12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 246 0F . . . . . . .3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246 0F . . . . . . . .3.4-35 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . .3.4-39 3.4.15 RCS Leakage Detection Instrumentation . . . . . .3.4-44 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . . 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . 3.5-1 3.5.2 ECCS -Operating . . . . .. . . . . . . . . . . . 3.5-4 3.5.3 ECCS -Shutdown . . . . . . . . . . . . . . . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . . . . . . . 3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . 3.5-11 (continued)

SAN ONOFRE--Unit 3 ii i Amendment No. 116

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks . . . . . . . . . . . . . . 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . . . . . 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . .. 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . . 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . . . . 3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . . . . . 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators . . . . . . . . . 3.6-25 3.7 PLANT SYSTEMS . . . . . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) . . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) .... . . . ..... . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System . . . . . . . . . . . . 3.7-27 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources -Operating . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources -Shutdown . .3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . . 3.8-20 3.8.4 DC Sources -Operating . . . . . . . .. . . . . . 3.8-23 3.8.5 DC Sources -Shutdown . . . . . . . . . . . 3.8-27 3.8.6 Battery Cell Parameters . . . . . . . . . 3.8-30 3.8.7 Inverters -Operating . . . . . . . . . . . . . . . 3.8-34 3.8.8 Inverters-Shutdown . . . . . . . . . . . . . . . 3.8-36 3.8.9 Distribution Systems- Operating . . . ... . . . . 3.8-38 3.8.10 Distribution Systems- Shutdown . . . . . . . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 3 iv Amendment No. 150

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start . . . . . . B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) . . . B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . .B 3.3-145 B 3.3.10 Fuel Handling Isolation Signal (FHIS) . . . . . .B 3.3-152 B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) .B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . .B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . .B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits .B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . .B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .B 3.4-9 B 3.4.4 RCS Loops -MODES 1 and 2 . . . . . . . . . . . . .B 3.4-23 B 3.4.5 RCS Loops -MODE 3 . . . . . . . . . . . . . . . .B 3.4-27 B 3.4.6 RCS Loops -MODE 4 . . . . . . . . . . . . . . . .B 3.4-31 B 3.4.7 RCS Loops -MODE 5, Loops Filled . . . . . . . . .B 3.4-36 B 3.4.8 RCS Loops- MODE 5, Loops Not Filled . . . . . . .B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature

• 246OF . . . .. . .B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246°F . . . . . . . B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . .B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation . . . . . .B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . .. . . . .B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . . .. . . . .B 3.5-1 B 3.5.2 ECCS- Operating . . . . . . . . . . . . B 3.5-11 B 3.5.3 ECCS- Shutdown . . . . . . . . . . . . .. . . . .B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) .. . . . B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . . . .. . . .B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . . . . . . B 3.6-1 B 3.6.2 Containment Air Locks . . . . . . . . . . . . B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . . . . . . B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . . . . . . B 3.6-27 B 3.6.5 Containment Air Temperature . . . . . . . . . B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System . . . . . B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . . . . . . B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . . . . . . B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . . . . . . B 3.6-53 (continued)

SAN ONOFRE--Unit 3 vii Amendment No. 116

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS . . . . .... . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . . B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . . B 3.7-39 B3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . B 3.7-43c B 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . . B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . B3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System. . . . . . . . . . . . . B 3.7-63 B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . B 3.8-1 B 3.8.1 AC Sources -Operating . . . . . . . . . . . . . . B 3.8-1 B 3.8.2 AC Sources -Shutdown . . . B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . B 3.8-36 B 3.8.4 DC Sources -Operating . . . . . . . . . . . . . . B 3.8-46 B 3.8.5 DC Sources -Shutdown . . . . . . . . . . . . . . . B 3.8-56 B 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . B 3.8-60 B 3.8.7 Inverters -Operating . . . . . . . . . . . . . . . B 3.8-67 B 3.8.8 Inverters -Shutdown .. . . . . . . . .. . . . . B 3.8-71 B 3.8.9 Distribution Systems -Operating . .. . . . . . . B 3.8-75 B 3.8.10 Distribution Systems -Shutdown . . . . . . . . . . B 3.8-84 B 3.9 REFUELING OPERATIONS . . . . . .. . . B 3.9-1 B 3.9.1 Boron Concentration . . . . . . . . ... B 3.9-1 B 3.9.2 Nuclear Instrumentation . . . . . . .. . . . ...B 3.9-5 B 3.9.3 Containment Penetrations . . . . . . . . . B 3.9-9 B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation -High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation -Low Water Level . . . . B 3.9-21 B 3.9.6 Refueling Water Level . . . . . . . ... . . . . B 3.9-25 SAN ONOFRE--Unit 3 v ii i Amendment No. 118

FHIS 3.3.10 3.3 INSTRUMENTATION 3.3.10 Fuel Handling Isolation Signal (FHIS)

LCO 3.3. 10 One FHIS channel shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel in the fuel handling building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Actuation Logic, A.1 Place one OPERABLE Immediately Manual Trip, or Fuel Handling required channel of Building Post gaseous radiation Accident Cleanup monitor inoperable System train in during movement of operation.

irradiated fuel assemblies. OR A.2 Suspend movement of Immediately irradiated fuel assemblies in the fuel handling building.

(continued)

SAN ONOFRE--UNIT 3 3.3-42 Amendment No. 116

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

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

Verify radiation monitor setpoint Allowable Values:

Airborne Gaseous:

• 6E4 cpm above background.

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

Testing of Actuation Logic shall include the actuation of each initiation relay and verification of the proper operation of each initiation relay. I Perform a CHANNEL FUNCTIONAL TEST on 18 months required FHIS Actuation Logic channel.

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

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

(continued)

SAN ONOFRE--UNIT 3 3.3-43 Amendment No. +16-139

Fuel Handling Building Post-Accident Cleanup Filter System 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Fuel Handling Building Post-Accident Cleanup Filter System LCO 3.7.14 Two Fuel Handling Building Post-Accident Cleanup Filter System trains shall be OPERABLE.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel building.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Fuel Handling A.1 Restore Fuel Handling 7 days Building Post-Accident Building Post-Cleanup Filter System Accident Cleanup train inoperable. Filter System train to OPERABLE status.

B. Required Action and B.1 Place OPERABLE Fuel Immediately Associated Completion Handling Building Time of Condition A Post-Accident Cleanup not met during Filter System train movement of irradiated in operation.

fuel assemblies in the fuel building. OR B.2 Suspend movement of Immediately irradiated fuel assemblies in the fuel building.

(continued)

(continued)

SAN ONOFRE--UNIT 3 3.7-27 Amendment No. 116

Fuel Handling Building Post-Accident Cleanup Filter System 3.7.14 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two Fuel Handling C.1 Suspend movement of Immediately Building Post-Accident irradiated fuel Cleanup Filter System assemblies in the trains inoperable fuel building.

during movement of irradiated fuel assemblies in the fuel building.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.14.1 Operate each Fuel Handling Building Post- 31 days Accident Cleanup Filter System train for 2 10 continuous hours with the heaters operating.

SR 3.7.14.2 Perform required Fuel Handling Building In accordance Post-Accident Cleanup Filter System filter with the VFTP testing in accordance with the Ventilation Filter Testing Program (VFTP).

SR 3.7.14.3 Verify each Fuel Handling Building Post- 24 months Accident Cleanup Filter System train actuates on an actual or simulated actuation signal.

(continued)

SAN ONOFRE--UNIT 3 3.7-28 Amendment No. 116

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 5.5.2. 11. 1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5.5.2. 11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation systems, "Control Room Emergency Air Cleanup System" and "Fuel Handling Building Post-accident Cleanup Filter System." The frequency of testing shall be in I accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and I

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested 0

per the methodology of ASTM D3803-1989 at 30 C and 70%

relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.

Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued) 5.-19 Amndmnt N. 13-~ 17 SANNOFE--NIT3 SAN ONOFRE--UNIT 3 5.0-19c Amendment No. 4-3-, 178

PCN-521 ENCLOSURE 2 ATTACHMENT 6 PROPOSED TECHNICAL SPECIFICATION CHANGES, UNIT 3

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . .. .. 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3.3. 7 Diesel Generator (DG) -Undervoltage Start . . . .

3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . . 3.3-39 3.3.10 Fuel Handling c1lation Signral w u X lu 8ff J EyE l u T o1If[TUIsI JT11 (FiI)o.t,

\ *, . - ....

l:. .(I.. "AM.

.. > 4se-3.3.11 Post Accident Monitoring Instrumentation (PAMI) . 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . 3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . . . 3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . . 3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . 3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . . 3.4-13 3.4.4 RCS Loops-MODES 1 and 2 . . . . . . . . . . . . . 3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . . 3.4-16 3.4.6 RCS Loops-MODE 4 . . . . . . . . . . . . . . . . 3.4-18 3.4.7 RCS Loops -MODE 5, Loops Filled . . . . . . . . . 3.4-21 3.4.8 RCS Loops-MODE 5, Loops Not Filled . . 3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . . 3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . . 3.4-28 3.4. 11 Not Used 3.4. 12. 1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 246 0F . . 3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246 0F . . . . . . . . 3.4-35 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . . 3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . 3.4-39 3.4.15 RCS Leakage Detection Instrumentation . . . 3.4-44 3.4.16 RCS Specific Activity . . . . . . . . . . . . . . 3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . . 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . 3.5-1 3.5.2 ECCS -Operating . . . . . . . . . . . . 3.5-4 3.5.3 ECCS- Shutdown . . . . 3.5-8 3.5.4 Refueling Water Storage Tank (RWSi). . . 3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . 3.5-11 (continued)

SAN ONOFRE--Unit 3 111 Amendment No. 4-16

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . .. 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . .. 3.6-1 3.6.2 Containment Air Locks . . . . . . . . . . . . .. 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . . . .. 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . . . . . . 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . .. 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . .. 3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . . . .. 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators . . . . . . . . . 3.6-25 3.7 PLANT SYSTEMS . . . . . . . . . . . .. . . . . . 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs). . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System. . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) . . 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 fuel Handling Building Past-.. P d a q Cleanup Filtcr System Not Used 3.7.15 Not Usedl....

3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources -Operating . . . . . . . . . . . . . . 3.8-1 3.8.2 AC Sources -Shutdown . . . . . . . . . . . . . 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and St arting Air . . . 3.8-20 3.8.4 DC Sources -Operating . . . . . . . . . . . . . . 3.8-23 3.8.5 DC Sources -Shutdown . . . . . . . . . . . . . . . 3.8-27 3.8.6 Battery Cell Parameters . . . . . . . . . . . . . 3.8-30 3.8.7 Inverters -Operating . . . . . . . . . . . . . . . 3.8-34 3.8.8 Inverters -Shutdown . . . . . . . . . . . . . . . 3.8-36 3.8.9 Distribution Systems- Operating . . . . . . . . . 3.8-38 3.8.10 Distribution Systems- Shutdown .. . . . . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 3 iv Amendment No. +SG

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start . . . . . . . B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) . . . B 3.3-135 B 3.3.9 Cnntrnl Room Isolation Signal (CRIS) . . . . . . B 3.3-145 B 3.3.10 Not UsedFuel llandling Isolation Signal (FI115)

B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . .B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . .B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . .B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits .B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . .B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .B 3.4-9 B 3.4.4 RCS Loops -MODES 1 and 2 . . . . . . . . . . . . .B 3.4-23 B 3.4.5 RCS Loops-MODE 3 . . . . . . . . . . . . . . . .B 3.4-27 B 3.4.6 RCS Loops-MODE 4 . . . . . . . . . . . . . . . .B 3.4-31 B 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . .B 3.4-36 B 3.4.8 RCS Loops- MODE 5, Loops Not Filled . . . . . . .B 3.4-42 B 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature

• 246°F . .. . . . .B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246°F . . . . . . . .B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIY) Leakage . . . .B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation .B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .. B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . .B 3.5-1 B 3.5.2 ECCS -Operating . . . . . . . . . . .B 3.5-11 B 3.5.3 ECCS -Shutdown . . . . . . . . . . . .. B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWST) .. B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . .B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . .. B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . .. B 3.6-1 B 3.6.2 Containment Air Locks . . . . . . . .. B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . .B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . .B 3.6-27 B 3.6.5 Containment Air Temperature . . . . .B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System .. B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . .B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . .B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . .B 3.6-53 (continued)

SAN ONOFRE--Unit 3 vii Amendment No. ++&

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS ........ . B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System. .B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . . B 3.7-39 B3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . B 3.7-43c B 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . . B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . B3.7-56 B 3.7.12 Not Used B 3.7.13 NntI 1ced B 3.7.14 Not Usedfuel Handling Building Post Accident C nup Filter System . .. . . . . . _B3. 63 B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . 3.8-1 .

B 3.8.1 AC Sources- Operating . . . . . . . B 3.8-1 .

B 3.8.2 AC Sources-Shutdown . . . 3.8-30 .

B 3.8.3 Diesel Fuel Oil, Lube Oil, and Start i ng Air . . . B 3.8-36 B 3.8.4 DC Sources- Operating . . . . . . . . . . . . . . B 3.8-46 B 3.8.5 DC Sources- Shutdown . . . . . . . . 3.8-56 .

B 3.8.6 Battery Cell Parameters . . . . . . B 3.8-60 .

B 3.8.7 Inverters -Operating . . . . . . . . 3.8-67 .

B 3.8.8 Inverters -Shutdown . . . . . . . . . B 3.8-71 B 3.8.9 Distribution Systems- Operating . . B 3.8-75 .

B 3.8.10 Distribution Systems-Shutdown . . . B 3.8-84 .

B 3.9 REFUELING OPERATIONS . . . . . . . . . . . . . B 3.9-1 B 3.9.1 Boron Concentration . . . . . . . . . . . . . B 3.9-1 .

B 3.9.2 Nuclear Instrumentation . . . . . . . B 3.9-5 B 3.9.3 Containment Penetrations . . . . . . B 3.9-9 .

B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation- High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation -Low Water Level . . . . . . . . B 3.9-21 B 3.9.6 Refueling Water Level . . . . . . . . . . . . . . B 3.9-25 SAN ONOFRE--Unit 3 viii Amendment No. ++8

J.3.10 I .- N T-RUMENTAT N

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I IAt.C r'r'l,,r-IIUIflAI I II I: I . I - -_U- UC I III I I Ib> vU &lII I I I I11 IITI 'Z LU I I 1u 1 1U Ilv 11-1 6ONiTOns REQUI+RED ACTIONG OeMLETrON TIME A. Actuation Logic, A.1 Place one OPERABLE immediattly Manuel Trip, or Fuel "land!llng required channel of Building Pes+

gascous radiation Accident Cleanup monitor inoperable System train in during movement . operafion.

irradiatcd fuei A.2 Suspcnd mnovement of Immediately irradiated fuel assemblies in the fuel hand!'n build ing SAN ONOFRE--UNIT 3 3. 3-42 Amendment No. i+1-

3.3.10 SURVEILLANCE FREQUCENC SR 3.3.10.1 Perform a CHANNEL CHECK on 4c1uird FIRS 1

+Phours-radiation monitor ehanrnel.

SR 3.3.10.2 Perform a CHANNEL FUNCTIONAL TEST an 92 days required FIIIS radiation monitor channel Verify radiation monitor setpoint Allowable Airborne Caseous. ! 6E4 cpm above ba,.gr.u d.

SR 3.3.10.3 NOTE Testing of Actuation Logic shall include the actuation of cach initiation relay and verifieation of the proper operation of each initliation relay.

Perform a CHANNEL FUNCTIONAL TEST on18 months required HIS Aetuation Logie channel.

SR 3.3.10.4 Perform a CHANNEL FUNCTIONAL TEST on 14m'onthst required HiTS Manual Trip logic.

SR 3.3.10.5 Perform a CHANNEL CALIBRATION on re^uired 18 months HIS radiation moanitor ehanrnel.

SAN ONOFRE--UNIT 3 3.3-43 Amendment No. 116, 139

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LII' LCO 3.7.14 Two Fuel Handling Building Post Accident Clcanup riltcer Systemn trains sh~all be OPERABLE-.

APPLICABILITY. Durn mo 'cant of irradiated fuel assemblies in the fuel bi- J IliLuI ACTIONS GONHi-fON REQUIRED ACTION LEIN-T-ME A. Onc FuEl llandlinfg A.1 Restore Fuel Handling 7 days Building Post AeeidenftBuligPs Cieanup Filter System Aeeident Clticnp train inoperable. Filter SystCm traUi to OPERABLE status.

B. Rcquired Action and 3.1 Place OPERABLE Fuel Immediately Asseeiated Comnpletion Ilarndling Bidn Time of Condition -A Post AceidemtClau not fet dringH~tilt Sjsteii train movement of irradiatedinpeaah fuel assemblies in the B3.2 Suspend moavement of T~~~~~~I

+ffmed-iately -- - rAi lAAI^A1 JILU1UIITI fI UU assemblies in the fulbuAifg-d+

%..JI I LIIUGU SAN ONOFRE--UNIT 3 3.7-27 Amendment No. ++6

I - 1: - - - I -l - J_ _n .--. r 1 _ _, .- _ r:

I IrS:ui IIn1I11 :r', I2-T 2;Trn7 I Iu1nI:r Ii IT

• *.' . jJOLLIII1 I -- I ll ll I I.Zly UU ACTIONS (continued)

CONBITION REQUIRED ACTION GOMPLETION TIME C. Twe Fuel Hand ling C.1 Suspend movement of U mmedI-ae+&y Building Post AUUident irradiated fulI Cleanup Filter System assemblics in the trains inoperable fuel building.

during movemcnt of irradiated fuel assemblies in the fuel building.

SRERILLANCE REQUIREMENTS SR 3.7.14.1 Operate each Fuel Handling Building Post 31 days Accident Cleanup Filter System train for t 10 continuous hours with the heaters SR 3.7.14.2 Pcrform require d Fuel Handling Building in aeardance Post Accident Cleanup Filter System filter with the VFTP testing in accordance with the Ventilation Filter Testing Program (vFTP).

SR 3.7.14.3 Verify each Fuel llandling Building Post- 24 months Accident Cleanup Filtcr System train actuates on an actual or simulated actuation signal.

SAN ONOFRE--UNIT 3 3.7-28 Amendment No. +1-6

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5.5. 2.11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation systemi7 "Control Room Emergency Air Cleanup System." and "Fuel arndling Building Post accident Cleanrup Filter System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested at 300C and 70%

per the methodology of ASTM D3803-1989 relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.

Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued)

SAN ONOFRE--UNIT 3 5.0-19c Amendment No. 1-32, 178&

PCN-521 ENCLOSURE 2 ATTACHMENT 7 REVISED TECHNICAL SPECIFICATION PAGES, UNIT 3

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Engineered Safety Features Actuation System (ESFAS)

Instrumentation . . . .. . . . . . . . . 3.3-22 3.3.6 Engineered Safety Features Actuation System (ESFAS)

Logic and Manual Trip . . . . . . . . . . . . 3.3-27 3 3.7 Diesel Generator (DG) -Undervoltage Start . . . .

3.3-32 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . 3.3-35 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . 3.3-39 3.3.10 Not Used 3.3.11 Post Accident Monitoring Instrumentation (PAMI) . 3.3-44 3.3.12 Remote Shutdown System . . . . . . . . . . . . . 3.3-48 3.3.13 Source Range Monitoring Channels . . . . . . . . 3.3-51 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . .3.4-1 3.4.1 RCS DNB Pressure, Temperature, and Flow Limits . . . . . . . . . . . . . . . . . . . .3.4-1 3.4.2 RCS Minimum Temperature for Criticality . . . . .3.4-4 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . .3.4-5 3.4.3.1 Pressurizer Heatup/Cooldown Limits . . . . . . . .3.4-13 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . .3.4-15 3.4.5 RCS Loops- MODE 3 . . . . . . . . . . . . . . . .3.4-16 3.4.6 RCS Loops- MODE 4 . . . . . . . . . . . . . . . .3.4-18 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . .3.4-21 3.4.8 RCS Loops- MODE 5, Loops Not Filled . .3.4-24 3.4.9 Pressurizer . . . . . . . . . . . . . . . . . . .3.4-26 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .3.4-28 3.4. 11 Not Used 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 246 0F . . . . . . .3.4-30 3.4. 12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246 0F . . . . . . . .3.4-35 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .3.4-37 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . .3.4-39 3.4.15 RCS Leakage Detection Instrumentation . . . . . .3.4-44 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .3.4-47 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) . . . . . . . 3.5-1 3.5.1 Safety Injection Tanks (SITs) . . . . . . . . . . 3.5-1 3.5.2 ECCS- Operating . . . . . . . . . . . . . . . . . 3.5-4 3.5.3 ECCS- Shutdown . . . . . . . . . . . .. 3.5-8 3.5.4 Refueling Water Storage Tank (RWST) . .. . . . . 3.5-9 3.5.5 Trisodium Phosphate (TSP) . . . . . . . . . . . . 3.5-11 (continued)

SAN ONOFRE--Unit 3 iii Amendment No.

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . . . . . . . 3.6-1 3.6.1 Containment . . . . . . . . . . . . . . . . . . . 3.6-1 3.6.2 Containment Air Locks . . . . . . . . . . . . . . 3.6-3 3.6.3 Containment Isolation Valves . . . . . . . . . . . 3.6-8 3.6.4 Containment Pressure . . . . . . . . . . . . . . . 3.6-16 3.6.5 Containment Air Temperature . . . . . . . . . . . 3.6-17 3.6.6.1 Containment Spray and Cooling Systems . . . . . . 3.6-18 3.6.6.2 Containment Cooling System . . . . . . . . . . . . 3.6-21 3.6.7 Not Used 3.6.8 Containment Dome Air Circulators . . . . . . . . . 3.6-25 3.7 PLANT SYSTEMS . . . ................. 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . . 3.7-7 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . . 3.7-9 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . . 3.7-11 3.7.6 Condensate Storage Tank (CST T-120 and T-121) 3.7-16 3.7.7 Component Cooling Water (CCW) System . . . . . . . 3.7-18 3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . . 3.7-19a 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . . 3.7-20 3.7.9 Not Used 3.7.10 Emergency Chilled Water (ECW) . . . . . . . . . . 3.7-22 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . 3.7-24 3.7.12 Not Used 3.7.13 Not Used 3.7.14 Not Used 3.7.15 Not Used 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . 3.7-29 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . 3.7-30 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . 3.7-32 3.7.19 Secondary Specific Activity . . . . . . . . . . . 3.7-35 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . . 3.8-1 3.8.1 AC Sources -Operating . . . . . . . . . 3.8-1 3.8.2 AC Sources -Shutdown . . . .. 3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and S tarting Air . . . 3.8-20 3.8.4 DC Sources -Operating . . . . . .. . . . 3.8-23 3.8.5 DC Sources -Shutdown . . . . . . .. 3.8-27 3.8.6 Battery Cell Parameters . . . . .. 3.8-30 3.8.7 Inverters -Operating . . . . . . . . . 3.8-34 3.8.8 Inverters- Shutdown . . . . . . .. 3.8-36 3.8.9 Distribution Systems - Operating . . . . . . . . . 3.8-38 3.8. 10 Distribution Systems- Shutdown .. . . . . . . . 3.8-40 (continued)

SAN ONOFRE--Unit 3 iV Amendment No.

TABLE OF CONTENTS B 3.3 INSTRUMENTATION (continued)

B 3.3.7 Diesel Generator Undervoltage Start . . . . . . . B 3.3-126 B 3.3.8 Containment Purge Isolation Signal (CPIS) . . . . B 3.3-135 B 3.3.9 Control Room Isolation Signal (CRIS) . . . . . . . B 3.3-145 B 3.3.10 Not Used I B 3.3.11 Post Accident Monitoring Instrumentation (PAMI) . B 3.3-159 B 3.3.12 Remote Shutdown System . . . . . . . . . . . . . . B 3.3-176 B 3.3.13 Source Range Monitoring Channels . . . . . . . . . B 3.3-181 B 3.4 REACTOR COOLANT SYSTEM (RCS) . . . . . . . . . . . . . B 3.4-1 B 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits . B 3.4-1 B 3.4.2 RCS Minimum Temperature for Criticality . . . . . B 3.4-7 B 3.4.3 RCS Pressure and Temperature (P/T) Limits . . . . B 3.4-9 B 3.4.4 RCS Loops- MODES 1 and 2 . . . . . . . . . . . . . B 3.4-23 B 3.4.5 RCS Loops- MODE 3. ............ B 3.4-27 B 3.4.6 RCS Loops- MODE 4. ............ B 3.4-31 B 3.4.7 RCS Loops- MODE 5, Loops Filled . . . . . . . . .B 3.4-36 B 3.4.8 RCS Loops -MODE 5, Loops Not Filled . . . . . . .B 3.4-42 B 3.4.9 Pressurizer.. ........... B 3.4-46 B 3.4.10 Pressurizer Safety Valves . . . . . . . . . . . .B 3.4-51 B 3.4.11 Not Used B 3.4.12.1 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature

• 246°F . . . . . . . B 3.4-55 B 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 246°F . . . . . . . .B 3.4-65 B 3.4.13 RCS Operational LEAKAGE . . . . . . . . . . . . .B 3.4-70 B 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . . . .B 3.4-76 B 3.4.15 RCS Leakage Detection Instrumentation . . . . . .B 3.4-82 B 3.4.16 RCS Specific Activity . . . . . . . . . . . . . .B 3.4-88 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) .B 3.5-1 B 3.5.1 Safety Injection Tanks (SITs) . . . . B 3.5-1 B 3.5.2 ECCS- Operating . . . . . . . . . . .. B 3.5-11 B 3.5.3 ECCS- Shutdown . . B 3.5-21 B 3.5.4 Refueling Water Storage Tank (RWSi) .. B 3.5-24 B 3.5.5 Trisodium Phosphate (TSP) . . . . . . B 3.5-30 B 3.6 CONTAINMENT SYSTEMS . . . . . . . . . . . B 3.6-1 B 3.6.1 Containment . . . . . . . . . . . . B 3.6-1 B 3.6.2 Containment Air Locks . . . . . . . . B 3.6-5 B 3.6.3 Containment Isolation Valves . . . . .B 3.6-13 B 3.6.4 Containment Pressure . . . . . . . . .B 3.6-27 B 3.6.5 Containment Air Temperature . . . . . B 3.6-30 B 3.6.6.1 Containment Spray and Cooling System .B 3.6-33 B 3.6.6.2 Containment Cooling System . . . . . .. B 3.6-43 B 3.6.7 Hydrogen Recombiners . . . . . . . . .B 3.6-48 B 3.6.8 Containment Dome Air Circulators . . . B 3.6-53 (continued)

SAN ONOFRE--Unit 3 vi Amendment No.

TABLE OF CONTENTS B 3.7 PLANT SYSTEMS . . . . . . . . . . . . . . . . . . . .B 3.7-1 B 3.7.1 Main Steam Safety Valves (MSSVs) . . . . . . . . . B 3.7-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) . . . . . . . B 3.7-7 B 3.7.3 Main Feedwater Isolation Valves (MFIVs) . . . . .B 3.7-13 B 3.7.4 Atmospheric Dump Valves (ADVs) . . . . . . . . . .B 3.7-17 B 3.7.5 Auxiliary Feedwater (AFW) System . . . . . . . . .B 3.7-23 B 3.7.6 Condensate Storage Tank (CST T-121 and T-120) . .B 3.7-35 B 3.7.7 Component Cooling Water (CCW) System . . . . . . .B 3.7-39 B3.7.7.1 Component Cooling Water (CCW)

Safety Related Makeup System . . . . . . . . .B 3.7-43c B 3.7.8 Salt Water Cooling (SWC) System . . . . . . . . .B 3.7-44 B 3.7.10 Emergency Chilled Water (ECW) System . . . . . . .B 3.7-49 B 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) . . . . . . . . . . . . . . . . . . . B 3.7-56 B 3.7.12 Not Used B 3.7.13 Not Used B 3.7.14 Not Used I B 3.7.15 Not Used B 3.7.16 Fuel Storage Pool Water Level . . . . . . . . . . B 3.7-68 B 3.7.17 Fuel Storage Pool Boron Concentration . . . . . . B 3.7-71 B 3.7.18 Spent Fuel Assembly Storage . . . . . . . . . . . B 3.7-74 B 3.7.19 Secondary Specific Activity . . . . . . . . . . . B 3.7-76 B 3.8 ELECTRICAL POWER SYSTEMS . . . . . . . . . . . . . . .B 3.8-1 B 3.8.1 AC Sources- Operating . . . . . . . . . . . . . .B 3.8-1 B 3.8.2 AC Sources -Shutdown . . . . . . .B 3.8-30 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air . . .B 3.8-36 B 3.8.4 DC Sources- Operating . . . . . . . . . . . . . .B 3.8-46 B 3.8.5 DC Sources- Shutdown . . . . . . . . . . . . . . .B 3.8-56 B 3.8.6 Battery Cell Parameters . . . . . . . . . . . . .B 3.8-60 B 3.8.7 Inverters- Operating . . . . . . . . . . . . . . .B 3.8-67 B 3.8.8 Inverters- Shutdown . . . . . . . . . . . . . . .B 3.8-71 B 3.8.9 Distribution Systems -Operating .. .. . . . . .B 3.8-75 B 3.8.10 Distribution Systems -Shutdown . . . . . . . . . .B 3.8-84 B 3.9 REFUELING OPERATIONS . . . . . . . . 3.9-1 .

B 3.9.1 Boron Concentration . . . . . . . . . . . .. B 3.9-1 .

B 3.9.2 Nuclear Instrumentation . . . . . . . . B 3.9-5 .

B 3.9.3 Containment Penetrations . . . . ... . ..B3.9-9 .

B 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation -High Water Level . . . . . . . . . B 3.9-16 B 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation -Low Water Level 3.9-21 .

B 3.9.6 Refueling Water Level . . . . . . . . . ..... B 3.9-25 .

SAN ONOFRE--Unit 3 viii Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK (continued)

SAN ONOFRE--UNIT 3 3.3-42 Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK I (conti nued)

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

THIS PAGE INTENTIONALLY LEFT BLANK (continued)

SAN ONOFRE--UNIT 3 3.7-27 Amendment No.

THIS PAGE INTENTIONALLY LEFT BLANK (continued)

SAN ONOFRE--UNIT 3 3.7-28 Amendment No.

Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.

5.5.2.11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.

5.5.2.12 Ventilation Filter Testing Program (VFTP)

This Program establishes the required testing of the Engineered Safety Feature filter ventilation system "Control Room Emergency Air Cleanup System." The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2. As a minimum the VFTP program shall include the following:

a. Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

b. Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1975 (see Note 1); and

c. Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested per the methodology of ASTM D3803-1989 at 300C and 70%

relative humidity to show acceptable methyl iodide penetration; and

d. Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate.

Note 1: Sample and injection points shall be qualified per ANSI N510-1975 unless manifolds have been qualified per ASME N510-1989.

HEPA testing will be conducted with DOP aerosol or suitable alternate.

(continued)

SAN ONOFRE--UNIT 3 5.0-19c Amendment No.

PCN-521 ENCLOSURE 2 ATTACHMENT 8

SUMMARY

OF LICENSEE COMMITMENTS

LIST OF REGULATORY COMMITMENTS The following table identifies those actions committed to by Southern California Edison in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Jack Rainsberry at 949-368-7420.

REGULATORY COMMITMENT DUE DATE SCE will implement the approved amendment Within 60 days of approval of this amendment request SCE will revise the Technical Specification (TS) Bases to delete the Within 60 days of Bases for TS 3.3.10 and TS 3.7.14 approval of this amendment request SCE will implement a Licensee Controlled Specification (LCS) Within 60 days of change to add the operability and functional requirements of the approval of this isolation and cleanup systems to the LCS. The required surveillances amendment request will include the current requirements to test the system operation, including automatic isolation on high radiation. In this transfer the Fuel Handling Building Post-Accident Cleanup Filter System (PACFS)

Limiting Condition for Operation requirement for two operable systems will be reduced to one system operable during movement of irradiated fuel in the fuel building. Completion Times for both FHIS and PACFS inoperabilities will be revised from 'Immediately' to "1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />" to allow for orderly completion of the Required Action after discovery of inoperability. The filtration Surveillance Requirement (SR) for testing of the charcoal adsorbers and the high efficiency particulate air (HEPA) filters will be deleted. The LCS for the Fuel Handling Isolation Signal will continue to require the surveillances currently contained in SRs 3.3.10.1, 3.3.10.2, 3.3.10.3, 3.3.10.4, 3.3.10.5. The LCS for PACFS will continue to require the surveillances currently contained in SRs 3.7.14.1 and 3.7.14.3.