Text

Proposed Change Number NPF-10/15-551, License Amendment Request, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (Ptlr)
	ML050320294
Person / Time
Site:	San Onofre
Issue date:	01/28/2005
From:	Nunn D; Edison International Co, Southern California Edison Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	GL-96-003
	Download: ML050320294 (159)
	v • d • e

SOUTHERN CALIFORNIA t>

I ^

I N DwMight E. Nunn

_ EDJISO V)U1 ice President An EDISON INTERNATIONAL Company January 28, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

San Onofre Nuclear Generating Station Units 2 and 3 Docket Nos. 50-361 and 50-362 Proposed Change Number NPF-10115-551 License Amendment Request, "Reactor Coolant System (RCS)

Pressure and Temperature Limits Report (PTLR)"

Dear Sir or Madam:

Pursuant to 10CFR50.90, Southern California Edison (SCE) is submitting Enclosure 2

'Proposed Change Number (PCN)-551" to request an amendment to SCE Licenses NPF-10 and NPF-15 to change the Technical Specifications for San Onofre Units 2 and

3. The proposed change revises Technical Specifications 1.1 "Definitions," 3.4 "Reactor Coolant System," and 5.7 "Reporting Requirements" to relocate the RCS pressure-temperature curves and limits from the Technical Specifications to a licensee-controlled document identified as the PTLR.

Generic Letter (GL) 96-03: Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits, allows the relocation of Technical Specification RCS Pressure-Temperature Limits to a licensee-controlled document, provided that the parameters for constructing the curves and setpoints are derived using a methodology approved by the NRC. The parameters for constructing RCS pressure and temperature limits in the licensee-controlled PTLR document is based on the methodology approved by the NRC in CEOG Topical Report CE-NPSD-683-A. Relocating the RCS Pressure-Temperature Curves and Limits from the Technical Specification to the PTLR is consistent with GL 96-03. SCE has determined that a "no significant hazards consideration" is appropriate.

SCE is making no new commitments that would result from NRC approval of the proposed amendments.

The Unit 2 and 3 PTLR documents are included with this amendment request as Enclosures 4 and 5, respectively. SCE requests that these amendments be implemented within 60 days from the date of issuance.

A-YI P.O. Box 128 San Clemente, CA 92674-0128 949-368-1480 Fax 949-368-1490

Document Control Desk January 28, 2005 Should you have any questions or require additional information, please contact Mr. Jack Rainsberry at (949) 368-7420.

Sincerely, Enclosures

1. Notarized affidavit, Unit 2

2. Notarized affidavit, Unit 3

3. Proposed Change Number (PCN)-551

4. Unit 2 PTLR

5. Unit 3 PTLR cc:

B. S. Malleft, Regional Administrator, NRC Region IV B. M. Pham, 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, Department of Health Services, Radiological Health Branch 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 Unit No. 2 of the San Onofre Nuclear)

No. 233 Generating Station)

SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 233. This amendment application consists of Proposed Change No. NPF-10-551 to Facility Operating License NPF-10. Proposed Change No. NPF-10-551 is a request to revise the Technical Specification's (TS)

Reactor Coolant System (RCS) to relocate the RCS Pressure/Temperature curves, Heatup/Cooldown curves, and Low Temperature Overpressure Protection (LTOP) enable temperatures, from the TS to a licensee-controlled document referred to as the RCS Pressure and Temperature Limits Report (PTLR).

State of California County of San Diego Dwight E. Nun ice President ubscribed and sworn to (or affirmed) before me on this &>wV day of r

?2,2*1 by Pilw i ItULI/

personally known to me or proved to me on thc basis of atifatory evidence to be the person who appeared before me.

COn.son g 1375470 Notary Public 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 Unit No. 3 of the San Onofre Nuclear)

No. 217 Generating Station)

SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 217. This amendment application consists of Proposed Change No. NPF-15-551 to Facility Operating License NPF-15. Proposed Change No. NPF-15-551 is a request to revise the Technical Specification's (TS)

Reactor Coolant System (RCS) to relocate the RCS Pressure/Temperature curves, Heatup/Cooldown curves, and Low Temperature Overpressure Protection (LTOP) enable temperatures, from the TS to a licensee-controlled document referred to as the RCS Pressure and Temperature Limits Report (PTLR).

State of California County of San Diego Pi Dwight E. Nut Vice President Subscribed and sworn to (or affirmed) before me on this ____

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by D>(;lr g

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day of personally known to me or-provedto me on he-basis-of-satisory evId to be the person who appeared before me.

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Notary Public COMMWn It 1375470

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ENCLOSURE 3 Proposed Change Number (PCN)-551 San Onofre Units 2 and 3

LICENSEE'S EVALUATION DESCRIPTION AND NO SIGNIFICANT HAZARDS ANALYSIS FOR PROPOSED CHANGE NPF-10/15-551 RELOCATION OF REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE CURVES FROM THE TECHNICAL SPECIFICATIONS TO A PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

San Onofre Nuclear Generating Station Units 2 and 3 EXISTING TECHNICAL SPECIFICATIONS Unit 2: see Attachment A Unit 3: see Attachment B PROPOSED TECHNICAL SPECIFICATIONS (highlight for additions, strikeout for deletions)

Unit 2: see Attachment C Unit 3: see Attachment D PROPOSED TECHNICAL SPECIFICATIONS (with changes)

Unit 2: see Attachment E Unit 3: see Attachment F PROPOSED TECHNICAL SPECIFICATION BASES CHANGES (provided for information)

Unit 2: see Attachment G (typical for both units)

1.0 INTRODUCTION

As one of the improvements to the standard technical specifications, the NRC staff agreed with the industry that the reactor coolant system (RCS) pressure and temperature curves and limits may be relocated outside the Technical Specifications (TS) to a licensee-controlled document, to enable the licensee to maintain these limits efficiently and at a lower cost. Issuance of NRC Generic Letter 96-03, "Relocation of the Pressure Temperature Limits Curves and Low Temperature Overpressure Protection System Limits," allowed the relocation of RCS pressure and temperature limits from the Technical Specifications to a licensee-controlled document, provided that the parameters for constructing the curves and setpoints are derived using NRC approved methodology.

The methodology for constructing the curves and limits including the revised curves and limits, which are valid until 32 effective full power years (EFPY), is provided in the PTLR. The methodology used is that described in the NRC approved Combustion Engineering topical report NPSD-683-A "The Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP Setpoints from the Technical Specifications."

2.0 PROPOSED CHANGE

This proposed change will allow Southern California Edison to make periodic updates to the RCS Pressure and Temperature (P/T) curves, Heatup and Cooldown curves, and Low Temperature Overpressure Protection (LTOP) enable temperatures more efficiently, without the requirement for a Technical Specification change amendment request to be submitted to the NRC for approval.

The proposed change revises the Technical Specifications by relocating the RCS Pressure and Temperature Limits, Heatup and Cooldown Curves and LTOP enable temperatures from the Technical Specifications to a licensee controlled RCS PTLR or specification. This submittal includes request for approval of the Unit 2 and Unit 3 RCS PTLRs that provide P/T curves and describe the methodology for constructing the curves and limits. The limiting P/T curves and data will be generated in a format similar to the P/T curves and data in SCE's existing Technical Specification and used until 32 EFPY as indicated in Appendix A of the PTLRs.

The following Technical Specifications are affected by this proposed change to revise the Technical Specifications by relocating the RCS Pressure and Temperature Limits, Heatup and Cooldown Curves and LTOP enable temperatures from the Technical Specifications to a licensee controlled RCS PTLR or specification. Technical Specifications tables of contents for 3.4.12.1 and 3.4.12.2, specification 1.1 Definitions, 3.4.3 RCS Pressure and Temperature (P/T) Limits, 3.4.6 RCS Loops - Mode 4, 3.4.7 RCS Loops - Mode 5, Loops Filled, 3.4.12.1 and 3.4.12.2 Low Temperature Overpressure Protection (LTOP)

System, 5.7 Reporting Requirements, and the supporting TS Bases Changes.

The PTLR is referenced in place of specific values in the Technical Specifications.

3.0 BACKGROUND

UFSAR 5.3.2, "Pressure-Temperature Limits," describes the operating conditions and bases for determining these limits.

All components in the RCS are designed to withstand the effects of cyclic loads due to RCS temperature and pressure changes. These cyclic loads could be 2

introduced by normal unit load transients, reactor trips, or startup and shutdown operation.

During plant startup and shutdown the rates of RCS temperature and pressure changes are limited to 60 degrees Fahrenheit/hour (0F/h) heatup and 100 (0F/h) cooldown. The design number of cycles for heatup and cooldown is based upon a rate of 1 00F/h and for cyclic operation.

The maximum allowable RCS pressure at any temperature is based upon the stress limitations for brittle fracture considerations. These limitations are derived by using the rules contained in Sections III and Xl of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, including Appendix G, Protection Against Nonductile Failure, and the rules contained in 10 CFR 50, Appendix G, Fracture Toughness Requirements.

Pressure and Temperature Curves and Limits:

The initial heatup and cooldown curves for San Onofre Units 2 and 3 were based in part on the fracture toughness properties of the primary coolant pressure boundary materials and on the expected changes in the toughness of the beltline region materials as a result of neutron irradiation. The initial predicted changes in toughness as a function of irradiation were based on the conservatively developed curves. These initial predictions were similar to or more conservative than predicted fracture toughness made on the basis of Regulatory Guide 1.99, Revision 1.

Post irradiation surveillance data are used to adjust the plant limit curves consistent with Regulatory Guide 1.99, Revision 2.

During plant life operation surveillance capsules are removed periodically from their location in the reactor vessel for testing at certain intervals of effective full power years (EFPY). The data obtained are compared with that used to develop the predicted curves and limits shown in the Technical Specifications. If this information indicates anomalies to the existing predictions the curves will be updated to reflect actual data.

Licensee amendments are submitted to the NRC for updating the pressure-temperature curves and limits following the removal and testing of surveillance capsules, consistent with 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements." Maintenance of RCS pressure and temperature within these prescribed curves and limits ensures that the integrity of the reactor coolant pressure boundary is maintained.

3

Proposed amendment The proposed change will relocate the RCS pressure-temperature curves and limits from the Technical Specifications to the PTLR as allowed by GL 96-03.

Eliminating the process of an amendment request for changes to the curves and limits will result in a resource savings for the licensee and the NRC. Future changes to the RCS pressure-temperature curves and limits would not require an amendment change to the Technical Specifications.

The pressure-temperature curves and limits in the PTLR are based on the Unit 2 and 3 post irradiation surveillance data from the surveillance capsule removed during the Cycle 11 and 12 refueling outages, respectively. They are valid until 32 EFPY and will be updated as necessary with the removal of capsules in the future.

4.0 TECHNICAL ANALYSIS

10 CFR 50.60 requires all light water nuclear power reactors to meet the fracture toughness and material surveillance program for the reactor coolant pressure boundary as set forth in 10 CFR 50 Appendix G "Fracture Toughness Requirements" and Appendix H "Reactor Vessel Material Surveillance Program Requirements." The purpose of Appendix H is to require a material surveillance program to monitor changes in the fracture toughness properties of ferritic materials (plates and welds) in the reactor vessel beltline region of light water nuclear power reactors resulting from exposure of these materials to neutron irradiation and temperature. Fracture toughness data are determined based on the testing and analysis of material specimens exposed to irradiation by neutrons in surveillance capsules, which are withdrawn periodically from the reactor vessel and used as described in Sections IV and V of Appendix G. The surveillance capsule withdrawal schedule is shown in Updated Final Safety Analysis Report (UFSAR) Table 5.3-12.

Surveillance capsules were removed from Unit 2 during the Cycle 11 refueling outage and from Unit 3 during the Cycle 12 refueling outage. Fracture toughness test results of the surveillance capsules and results of sections IV and V of Appendix G require changes to the RCS P/T curves and limits. The RCS P/T curves and limits presently reside in the Technical Specifications. An amendment to the Technical Specifications would be required for changes made to the pressure and temperature limits. This proposed amendment change of relocating the RCS P/T curves and limits, including the changes, to a licensee-controlled document, is consistent with GL 96-03.

Calculation of the adjusted reference temperature (ART) for the limiting plate and weld in the beltline region was performed consistent with Regulatory Guide 1.99, Revision 2. The adjusted reference temperature values developed are used to derive the P/T curves and limits for San Onofre Units 2 and 3. The adjusted 4

reference temperature includes the effect of exposure of the material to neutron irradiation.

P/T Curves and Limits for Unit 2 and 3 were performed consistent with 10 CFR 50 Appendix G and are based upon the principles of Linear Elastic Fracture Mechanics found in the ASME Boiler and Pressure Vessel Code Section Xl, Appendix G. The analyses use the crack initiation reference stress intensity factor KIc for determining the fracture toughness of the material. The use of KIc as the basis for establishing the reference fracture toughness limit, KIR, value for the vessel is found in ASME Xl Appendix G. Pressure and temperature values are adjusted for instrumentation uncertainties, and the effects of RCS static and dynamic pressure heads.

Low Temperature Overpressure Protection (LTOP) enable temperatures are determined in accordance with the ASME Code Section Xl, Appendix G. The LTOP system protects the RCS pressure boundary integrity by ensuring that the RCS pressure remains below the applicable P/T limits of 10 CFR 50 Appendix G.

The RCS pressure and temperature curves and limits, which are valid until 32 EFPY, are provided in the PTLR.

This change does not impact the UFSAR safety analysis and complies with GL 96-03 and 10 CFR 50, Appendices G and H.

10 CFR 50 Appendix H requires a material surveillance program to monitor changes in the fracture toughness properties of ferritic materials (plates and welds) in the reactor vessel beltline region, of light water nuclear power reactors, resulting from exposure of these materials to neutron irradiation and the thermal environment. 10 CFR 50 Appendix G provides the requirements for determining pressure and temperature limits for protecting the reactor coolant system's pressure boundary integrity until end of life (EOL). Removal, testing and analysis of the Unit 2 and 3 surveillance capsules resulted in changes to the RCS pressure and temperature limits requiring NRC approval.

5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Southern California Edison (SCE) 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 Amendment," as discussed below:

1.

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

5

Response: No.

This proposed change revises the Technical Specifications by relocating the reactor coolant system (RCS) Pressure and Temperature Limits, Heatup and Cooldown Curves and Low Temperature Overpressure Protection (LTOP) enable temperatures from the Technical Specifications to a RCS Pressure and Temperature Limits Report (PTLR). Relocation of this information will not impact the activity to update the RCS pressure and temperature curves and limits in accordance with the requirements of 10 CFR 50 Appendix G and H to ensure the reactor coolant system's pressure boundary integrity will be protected until end of life (EOL). Consequently, this proposed change is determined to not contribute to the probability of or the initiation of accidents.

There is no change to the safety analysis.

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

2.

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

Response: No.

This proposed change revises the Technical Specifications by relocating the RCS Pressure and Temperature Limits, Heatup and Cooldown Curves and LTOP enable temperatures from the Technical Specifications to a RCS PTLR to document removal, testing and analyzing the surveillance capsule. This document will be updated by SCE to reflect the testing and analysis of specimens.

Removal, testing and analyzing the surveillance capsule resulted in changes to the RCS pressure and temperature limits. These changes are required to maintain the RCS pressure boundary integrity until EOL. Changes to the RCS pressure and temperature curves and limits will not create a new or different kind of accident.

There is no change to the safety analysis.

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

3.

Does the proposed change involve a significant reduction in a margin of safety?

6

Response: No Pressure and temperature curves and limits are provided as limits to plant operation for ensuring RCS pressure boundary integrity and maintained until EOL. Changes to the RCS pressure and temperature curves and limits, resulting from the removal, testing and analyzing of a surveillance capsule, are only made within the acceptable margin limits maintaining the required margin of safety.

There is no change to the safety analysis.

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

Based on the above, SCE 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 10 CFR 50.60 requires all light water nuclear power reactors to meet the fracture toughness and material surveillance program for the reactor coolant pressure boundary, as set forth in Appendices G "Fracture Toughness Requirements" and H "Reactor Vessel Material Surveillance Program Requirements" of 10 CFR 50. Regulatory Guide 1.99, Revision 2 provides guidance in calculating the adjusted reference temperature (ART) for the limiting plate and weld in the beltline region. NRC Generic Letter GL 96-03, "Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits," allows relocating the pressure and temperature curves and limits outside the Technical Specifications to a licensee-controlled document.

The proposed change is in accordance with GL 96-03, Regulatory Guide 1.99, Rev. 2, and 10 CFR 50 Appendices G and H.

In conclusion, based on the considerations discussed above, (1j 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 amendments 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, the reactor vessel, located within the restricted area, as defined in 10 CFR 20 or would 7

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 amendments meet 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 these proposed amendments.

7.0 REFERENCES

7.1 Code of Federal Regulations, Title 10, Part 50, Section 50.60, "Acceptance Criteria for Fracture Prevention Measures for Light Water Nuclear Power Reactors for Normal Operation."

7.2 Code of Federal Regulations, Title 10, Part 50, Appendix G, "Fracture Toughness Requirements."

7.3 Code of Federal Regulations, Title 10, Part 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements."

7.4 U.S. Nuclear Regulatory Commission, "Radiation Embrittlement of Reactor Vessel Materials," Regulatory Guide 1.99, Revision 2.

7.5 ASME Boiler and Pressure Vessel Code, 1995 Edition and addenda through the 1996 Addenda, Section Xl, Appendix G, "Fracture Toughness Criteria for Protection Against Failure."

7.6 Westinghouse calculation CN-CI-04-37, SONGS Unit 3 RCS Pressure-Temperature Limits and LTOP Enable Temperatures for 32 EFPY, Revision 1.

7.7 Westinghouse calculation CN-CI-02-54, SONGS Unit 2 RCS Pressure-Temperature Limits and LTOP Enable Temperatures for 32 EFPY, Revision 3.

7.8 SCE calculation M-001 1-071, SONGS Unit 2 Adjusted Referenced Temperature for 20 & 32 EFPY, Revision 2.

7.9 NRC Generic Letter 96-03: Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits.

7.10 San Onofre Nuclear Generating Station Updated Final Safety Analysis Report, (August,2003).

8

7.11 SO23-923-M93 Rev. 3/ WCAP-16005-NP, San Onofre Nuclear Generating Station Unit 2 RCS Pressure and Temperature Limits Report, Rev. 03 7.12 S023-923-M97 Rev. 0 / WCAP-1 6167-NP, San Onofre Nuclear Generating Station Unit 3 RCS Pressure and Temperature Limits Report, Rev. 00 7.13 SCE calculation M-001 1-074, SONGS Unit 3 Adjusted Referenced Temperature for 20 & 32 EFPY, Revision 0.

7.14 Combustion Engineering topical report NPSD-683-A "The Development of a RCS Pressure and Temperature Limits Report or the Removal of P-T Limits and LTOP Setpoints from the Technical Specifications," Revision 06.

7.15 Framatome ANP, BAW-2408, Analysis of the 263 0 Capsule, Southern California Edison Company, San Onofre Unit 2 Nuclear Generating Station.

7.16 Framatome ANP, BAW-2454, Analysis of the 263 ° Capsule, Southern California Edison Company, San Onofre Unit 3 Nuclear Generating Station.

7.17 Code Case N-640, "Alternative Reference Fracture Toughness for Development of P-T Limit Curves for ASME Section Xl, Division 1" PCN551 textRi 9

PCN-551 Attachment A (Existing Pages)

SONGS Unit 2

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start

.... 3.3-32 Containment Purge Isolation Signal (CPIS)

.... 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI)

. 3.3-44 Remote Shutdown System

............. 3.3-48 Source Range Monitoring Channels

........ 3.3-51 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 REACTOR COOLANT SYSTEM (RCS).........

RCS DNB Pressure, Temperature, and Flow Limits RCS Minimum Temperature for Criticality RCS Pressure and Temperature (P/T) Limits Pressurizer Heatup/Cooldown Limits....

RCS Loops-MODES 1 and 2.........

RCS Loops -MODE 3............

RCS Loops -MODE 4............

RCS Loops-MODE 5, Loops Filled RCS Loops -MODE 5, Loops Not Filled Pressurizer....i..........

Pressurizer Safety Valves.

Not Used

.... 3.4-1

.... 3.4-4

.... 3.4-5

.... 3.4-13

.... 3.4-15

.... 3.4-16

.... 3.4-18

.... 3.4-21

.... 3.4-24

.... 3.4-26

.... 3.4-28 Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature

2560F Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 2560F.......

RCS Operational LEAKAGE RCS Pressure Isolation Valve (PIV) Leakage...

RCS Leakage Detection Instrumentation.....

RCS Specific Activity.............

EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS -Operating ECCS-Shutdown.

Refueling Water Storage Tank (RWST)

Trisodium Phosphate (TSP)

. 3.4-30

. 3.4-35

. 3.4-37

. 3.4-39

. 3.4-44

. 3.4-47 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5

. 3.5-1

. 3.5-4

. 3.5-8

. 3.5-9

. 3.5-11 (continued)

SAN ONOFRE--Unit 2 Amendment No. 127

Definitions 1.1 1.1 Definitions OPERABLE-OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a.

Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER (RTP)

REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

SAN ONOFRE--UNIT 2 1.1-5 Amendment No. 188 1

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 With the reactor vessel head bolts tensioned*, the Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4.3-1, 3.4.3-2, 3.4.3-3, 3.4.3-4, 3.4.3-5, and Table 3.4.3-1 during heatup, cooldown, and inservice leak and hydrostatic testing with:

a. A maximum heatup of 600F in any 1-hour period with RCS cold leg temperature greater than or equal to 650F.

b. A maximum cooldown as specified by Figure 3.4.3-3 in any 1-hour period with RCS cold leg temperature less than or equal to 160 0F. A maximum cooldown of 1000F in any 1-hour period with RCS cold leg temperature greater than 1600F.

c. A maximum temperature change of 100F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

d. A minimum temperature of 650F to tension reactor vessel head bolts.

I With the reactor vessel head bolts detensioned, (except the pressurizer) temperature shall be 1 cooldown of 600F in any 1-hour period.

the Reactor Coolant System imited to a maximum heatup or

With the reactor vessel head bolts detensioned, RCS cold may be less than 650F.

leg temperature SAN ONOFRE--UNIT 2 3.4-5 Amendment No. 147-172 1

RCS P/T Limits

3.4.3 APPLICABILITY

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

< 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

SAN ONOFRE--UNIT 2 3.4-6 Amendment No. 127

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

.4 SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates within limits specified in Figure 3.4.3-1, Figure 3.4.3-2, Figure 3.4.3-3, Figure 3.4.3-4, Figure 3.4.3-5, and Table 3.4.3-1.

30 minutes

.4 SR 3.4.3.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H. The results of these examinations shall be used to update Figures 3.4.3-1 through 3.4.3-5.

Recalculate the Adjusted Reference Temperature in accordance with Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials,"

May 1988.

In accordance with requirements of 10CFR 50 Appendix H SAN ONOFRE--UNIT 2 3.4-6a Amendment No. 127

RCS P/T Limits 3.4.3

-T---1---.-,

5 5

5 5 5

.I 30_

rL 0.

w U,

G LU c.C C-,M tr LO VI.1 ac LOWEST SERVICE TEMP - 2W'F Acceptable operating n right of the InserNice toli (A~ppicabte In modes o

-M Modes I and 2)

U Acceptable operating r right of the heatUp curvi In addtion. In Modes I operating rogion is to th core critical curve.

20CO

INSE lork *:

the Dte curve her than plon - to the p In all nodes.

and 2 the l right of the RVICE TESTS U HEATUP j '. ;: t+,-

-. t St?

I S

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50 100 150 200 250 300 360 A 60 INDICATED RCS TEMPERATURE VF) -Tc Figure 3.4.3-1 SONGS 2 HEATUP RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Normal Operation SAN ONOFRE--UNIT 2 3.4-7 Amendment No. 44-+;-172 l

RCS P/T Limits 3.4.3 250o I.

I..

I.

I

-T -

- ------ I--

w U,

0-w il FE S.?

2 w

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LOWEST SERVICE COOLDOWN TEMP -209'F

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.. gT,.-

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.Opersiong Acceptable

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g is I-a5 so to 10 200 2W0 30 350 INDICATED RCS TEMPERATURE (-F) -TC FIGURE 3.4.3-2 SONGS 2 COOLDOWN RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Normal Operation 3.4-8 Amendment No. 1-27,172 SAN ONOFRE--UNIT 2

RCS P/T Limits 3.4.3 120 110 100 LLI-1 I-J§ W0 70 60 Co

?0 IC 0

60 70 g0 go 100 110 2o l

130 140 150 160 170 180 19 200 2,0 INDICATED RCS TEMPERATURE OF) -Tc NOTE:

A MAXIMUM COOLDOWN RATE OF 1000F/HR IS ALLOWED AT ANY TEMPERATURE ABOVE 160 0F FIGURE 3.4.3-3 SONGS 2 RCS PRESSURE/TEMPERATURE LIMITS MAXIMUM ALLOWABLE COOLDOWN RATES (UNTIL 20 EFPY)

Normal Operation SAN ONOFRE--UNIT 2 3.4-9 Amendment No. 127-,172 1

RCS P/T Limits 3.4.3 1c C.

0 (n

w E

Ti 1

1 I

IT I

vI I*

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T LOWEST SERVICE COOLDOWN TEMP 209'F o

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. *.I j;I r.2...!....................o.

l*two; Unaxepiable Operating Region 150sc Acceplable Operatirng Region I

/

.3 500 s-MINIMUM BOLTUP TEMP a65OF I

. I I

I.

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I.

I iS 10 so 50 100 2

250 3

INDICATED RCS TEMPERATURE (F) -Tc 330 40 FIGURE 3.4.3-4 SONGS 2 COOLDOWN RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Remote Shutdown Operation 3.4-10 Amendment No. 127-,172 SAN ONOFRE--UNIT 2

RCS P/T Limits 3.4.3 El I.

uJ 8

60 70 s0 PO 100 110 120 100 140 150 160 170 1¶0 IC0 2m0 210 INDICATED RCS TEMPERATURE (F) -Tc NOTE:

A MAXIMUM COOLDOWN RATE OF 100 0F/HR IS ALLOWED AT ANY TEMPERATURE ABOVE 168 0F FIGURE 3.4.3-5 SONGS 2 RCS PRESSURE/TEMPERATURE LIMITS MAXIMUM ALLOWABLE COOLDOWN RATES (UNTIL 20 EFPY)

Remote Shutdown Operation SAN ONOFRE--UNIT 2 3.4-11 Amendment No. 4-27-172 I

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 Low Temperature RCS Overpressure Protection RanQe Operating Period. EFPY Until 20 (Normal Operation)

Until 20 (Remote shutdown Operation)

Cold Leg Temperature, TF During During Heatup Cooldown

256

238

238 Heatup operations are not normally performed from the Remote Shutdown panels.

SAN ONOFRE--UNIT 2 3.4-12 Amendment No. 127

RCS Loops -MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

-__----------------NOTES---------------------------

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

2.

No RCP shall be started with any RCS cold leg temperature

2560F unless:

a. Pressurizer water volume is < 900 ft3, or

b. Secondary side water temperature in each steam generator (SG) is < 100IF above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 2 3.4-18 Amendment No. +/-2-,175 1

RCS Loops-MODE 5, Loops Filled 3.4.7 NOTES

4. No reactor coolant pump or more of the RCS cold unless:

(continued)---------------------

(RCP) shall be started with one leg temperatures

2560F a.The pressurizer water volume is < 900 ft3 or b.The secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6.

All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 2 3.4-22 Amendment No. 127

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature

2560F LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isolated or depressurized to less than the limit specified in Figure 3.4.3-2 and at least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2)

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

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

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

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

SAN ONOFRE--UNIT 2 3.4-30 Amendment No. +27, 147

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Figure 3.4.3-1 and Figure 3.4.3-2.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in Figure 3.4.3-1 and Figure 3.4.3-2.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 2HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 2HV9339 or valve OPERABLE SDCS Relief pair 2HV9377 and Valve isolation valve 2HV9378) closed.

pair.

(continued)

SAN ONOFRE--UNIT 2 3.4-31 Amendment No. 127

LTOP System 3.4.12.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. SDCS Relief Valve E.1 Reduce Tavg to less 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

than 200F, depressurize RCS and OR establish RCS vent of 2 5.6 square inches.

Required Action and associated Completion Time of Condition A, C, or D not met.

OR LTOP System inoperable for any reason other than Condition A, C, or D.

SAN ONOFRE--UNIT 2 3.4-32 Amendment No. 127

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

+

SR 3.4.12.1.1

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

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed.

The requirement to rack out the HPSI pump breaker is satisfied with the pump breaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the limit specified in Figure 3.4.3-2.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations (continued)

SAN ONOFRE--UNIT 2 3.4-33 Amendment No. 127

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

NOTES----------------

1. Only required to be performed when the SDCS Relief Valve isolation valve pair is inoperable.

2 The power-lock open requirement is satisfied either with the AC breakers open for valve pair 2HV9337 and 2HV9339 or the inverter input and output breakers open for valve pair 2HV9377 and 2HV9378, whichever valve pair is OPERABLE.

SR 3.4.12.1.4 Verify the OPERABLE SDCS Relief Valve isolation valve pair (valve pair 2HV9337 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 2HV9339, or valve pair 2HV9377 and 2HV9378) is in the power-lock open condition.

SR 3.4.12.1.5 Verify that SDCS Relief Valve isolation 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months valves 2HV9337, 2HV9339, 2HV9377, and 2HV9378 are open when the SDCS Relief Valve is used for overpressure protection.

SR 3.4.12.1.6 Verify SDCS Relief Valve Setpoint.

In accordance with the Inservice Testing Program SAN ONOFRE--UNIT 2 3.4-34 Amendment No. 4-2+, 143

LTOP System 3.4.12.2 SURVEILLANCE REQUIREMENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > 2560F LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2)

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

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are greater than the enable temperatures specified in Table 3.4.3-1.

NOTES----------------------------

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 130'F.

SAN ONOFRE--UNIT 2 3.4-35 Amendment No. 127

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

Not Used Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (1-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator-once every three years.

5.7.1.6 5.7.1.7 (continued)

SAN ONOFRE--UNIT 2 5.0-29 Amendment No. +63, 168 1

PCN-551 Attachment B (Existing Pages)

SONGS Unit 3

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start 3.3-32 Containment Purge Isolation Signal (CPIS)

. 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI) 3.3-44 Remote Shutdown System.3.3-48 Source Range Monitoring Channels.

3.3-51 REACTOR COOLANT SYSTEM (RCS)...........

RCS DNB Pressure, Temperature, and Flow Limits..................

RCS Minimum Temperature for Criticality...

RCS Pressure and Temperature (P/T) Limits..

Pressurizer Heatup/Cooldown Limits......

RCS Loops-MODES 1 and 2...........

RCS Loops-MODE 3..............

RCS Loops-MODE 4..............

RCS Loops-MODE 5, Loops Filled.......

RCS Loops-MODE 5, Loops Not Filled.....

Pressurizer.................

Pressurizer Safety Valves Not Used Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < 2460F......

Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > 2465F......

RCS Operational LEAKAGE...........

RCS Pressure Isolation Valve (PIV) Leakage..

RCS Leakage Detection Instrumentation.

RCS Specific Activity............

..3.4-1

..3.4-4

..3.4-5

..3.4-13

..3.4-15

.. 3.4-16

..3.4-18

..3.4-21

..3.4-24

.. 3.4-26

..3.4-28

..3.4-30

..3.4-35

..3.4-37

..3.4-39

..3.4-44

..3.4-47 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS-Operating..........

ECCS -Shutdown.

Refueling Water Storage Tank (RWST)

Trisodium Phosphate (TSP)

....... 3.5-1 3.5-1 3.5-4

....... 3.5-8

....... 3.5-9

....... 3.5-11 (continued)

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

Definitions 1.1 1.1 Definitions OPERABLE-OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RATED THERMAL POWER (RTP)

REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

SAN ONOFRE--UNIT 3 1.1-5 Amendment No.

179 1

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 With the reactor vessel head bolts tensioned*, the Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4.3-1, 3.4.3-2, 3.4.3-3, 3.4.3-4, 3.4.3-5, and Table 3.4.3-1 during heatup, cooldown, and inservice leak and hydrostatic testing with:

a. A maximum heatup of 60'F in any 1-hour period with RCS cold leg temperature greater than or equal to 650F.

b. A maximum cooldown as specified by Figure 3.4.3-3 in any 1-hour period with RCS cold leg temperature less than or equal to 1470F. A maximum cooldown of 100'F in any 1-hour period with RCS cold leg temperature greater than 147 0F.

c. A maximum temperature change of 10F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

d. A minimum temperature of 650F to tension reactor vessel head bolts.

With the reactor vessel head bolts detensioned, the Reactor Coolant System (except the pressurizer) temperature shall be limited to a maximum heatup or cooldown of 600F in any 1-hour period.

With the reactor vessel head bolts detensioned, may be less than 650F.

RCS cold leg temperature I

SAN ONOFRE--UNIT 3 3.4-5 Amendment No. 441-&-163 1

RCS P/T Limits

3.4.3 APPLICABILITY

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

' 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

SAN ONOFRE--UNIT 3 3.4-6 Amendment No. 116

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates within limits specified in Figure 3.4.3-1, Figure 3.4.3-2, Figure 3.4.3-3, Figure 3.4.3-4, Figure 3.4.3-5, and Table 3.4.3-1.

30 minutes SR 3.4.3.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H. The results of these examinations shall be used to update Figures 3.4.3-1 through 3.4.3-5.

Recalculate the Adjusted Reference Temperature in accordance with Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials,"

May 1988.

In accordance with requirements of 10CFR 50 Appendix H SAN ONOFRE--UNIT 3 3.4-6a Amendment No. 116

RCS P/T Limits 3.4.3 rs r rrr S

Ul C

Uj cc W1 5

N 2w0 LOWEST SERVICE TEMP - 209'F J Acceptable operalNg regi right of the Inselrtco tests (Appilcibte In nodes otha ModeI 1and 2)

Acceptable opersafng regk right of the heatup curve In In addition. in Modes 1 BfnC operutirg region is to the rl eore crtcal curve.

MI NIMUM BOLTUP TEMP.65'F

S 1

SI l *

INSERVICE TESTS U HEATUP

\\

oI

\\

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N On - to the f--

-- curve r than

. i t:

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.of

-X

1 CIA

,/.

S.

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t..

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i so too ISO 200 250 300 INDICATED RCS TEMPERATURE (F)

-Tc 360 "O

FIGURE 3.4.3-1 SONGS 3 HEATUP RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Normal Operation SAN ONOFRE--UNIT 3 3.4-7 Amendment No. +/-+6v-163 1

RCS P/T Limits 3.4.3 3SOO 3000 0.

aro w

cc D

2500 cn rn 111 LOWEST SER{VICE COOLDOWN TEMP

209F

\\

a 1 a..

a...._

_ l...........~

_w_+___;+_

tSJ 20 0t Sa r

. Unacceptable at Oeai.....*/__...__.i.S Region t-S.

Operating Rego 00 i

T.MP F

0 so

¶00 ISO 200 250 300 350 400 INDICATED RS TEMPERATURE (OF) -T*

FIGURE 3.4.3-2 SONGS 3 COOLDOWN RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Normal Operation SAN ONOFRE--UNIT 3 3.4-8 Amendment No. 4--6-,163

RCS P/T Limits 3.4.3 UL-0 0

00 0

0 I I

I I

I I I I

I I

.I I

60 70 80 90 100 110 120 130 142 150 160 170 180 190 202 210 INDICATED RCS TEMPERATURE (OF)-T NOTE: A MAXIMUM COOLDOWN RATE OF 100 0F/HR IS ALLOWED AT ANY TEMPERATURE ABOVE 147 0F FIGURE 3.4.3-3 SONGS 3 RCS PRESSURE/TEMPERATURE LIMITS MAXIMUM ALLOWABLE COOLDOWN RATES (UNTIL 20 EFPY)

Normal Operation SAN ONOFRE--UNIT 3 3.4-9 Amendment No. +/-1-6--163 1

RCS P/T Limits 3.4.3 I

I t

5 I

I LOWE5T SERYVICE TEM^P a 209'F l

~~I.

-- I v I I.

I I

COOLOOWN

/

I.

. T T I.._

0.S 0.

C a:

cc 4C z

.... --1 - !- -

1 4

_ /

25s

t.

a 4

..'_t*-.

Unacceptabl..

Operating..........

Region r

Acceptabl8

.Operating

-i n

! ~*

igo 4./

.1.6..........

.OTU

.....;L TEMP.*65'F I I.

II J.

I.L.1-1 II I

I 1~

I 1a I I I

I. I 15s 0

so 100 ISO 200 250 x

INDICATED RCS TEMPERATURE (F) -Tr

&5O FIGURE 3.4.3-4 SONGS 3 COOLDOWN RCS PRESSURE/TEMPERATURE LIMITATIONS UNTIL 20 EFPY Remote Shutdown Operation SAN ONOFRE--UNIT 3 3.4-10 Amendment No. 446--163 l

RCS P/T Limits 3.4.3 120 110 l00 r

so 7D 60

0 40 30 IC 60 70 I0 90 100 110 120 U

140 1 0 150 17D 180 190 m

210 INDICATED RCS TEMPERATURE (OF) -Tc NOTE:

A MAXIMUM COOLDOWN RATE OF 100'F/HR IS ALLOWED AT ANY TEMPERATURE ABOVE 155 0F FIGURE 3.4.3-5 SONGS 3 RCS PRESSURE/TEMPERATURE LIMITS MAXIMUM ALLOWABLE COOLDOWN RATES (UNTIL 20 EFPY)

Remote Shutdown Operation SAN ONOFRE--UNIT 3 3.4-11 Amendment No. 44-67163 1

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 Low Temperature RCS Overoressure Protection Range Operating Period, EFPY Until 20 (Normal Operation)

Until 20 (Remote shutdown Operation)

Cold Leg Temperature, OF During During Heatup Cooldown

246

225

225 Heatup operations are not normally performed from the Remote Shutdown panels.

SAN ONOFRE--UNIT 3 3.4-12 Amendment No. 116

RCS Loops -MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

___ ---------------- NOTES---------------------------

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature

2460F unless:

a. Pressurizer water volume is < 900 ft3, or

b. Secondary side water temperature in each steam generator (SG) is < 100IF above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 3 3.4-18 Amendment No. +4-6,166 1

RCS Loops-MODE 5, Loops Filled 3.4.7

NOTES I

4.

No reactor coolant pump or more of the RCS cold unless:

(continued)---------------------

(RCP) shall be started with one leg temperatures

2460F a.The pressurizer water volume is < 90o ft3 or b.The secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6.

All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 3 3.4-22 Amendment No. 116

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature

2460F LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isolated or depressurized to less than the limit specified in Figure 3.4.3-2 and at least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2)

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

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in Table 3.4.3-1, MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

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

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

SAN ONOFRE--UNIT 3 3.4-30 Amendment No. +i-6, 139

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Figure 3.4.3-1 and Figure 3.4.3-2.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in Figure 3.4.3-1 and Figure 3.4.3-2.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 3HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 3HV9339 or valve OPERABLE SDCS Relief pair 3HV9377 and Valve isolation valve 3HV9378) closed.

pair.

(continued)

SAN ONOFRE--UNIT 3 3.4-31 Amendment No. 116

LTOP System 3.4.12.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. SDCS Relief Valve E.1 Reduce T,, to less 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

than 200F, depressurize RCS and OR establish RCS vent of 2 5.6 square inches.

Required Action and associated Completion Time of Condition A, C, or D not met.

OR LTOP System inoperable for any reason other than Condition A, C, or D.

SAN ONOFRE--UNIT 3

3. 4-32 Amendment No. 116

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1.1

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

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed. The requirement to rack out the HPSI pump breaker is satisfied with the pump breaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the limit specified in Figure 3.4.3-2.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations (continued)

SAN ONOFRE--UNIT 3 3.4-33 Amendment No. 116

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY NOTES----------------

1. Only required to be performed when the SDCS Relief Valve isolation valve pair is inoperable.

2 The power-lock open requirement is satisfied either with the AC breakers open for valve pair 3HV9337 and 3HV9339 or the regulating transformer output breakers open for valve pair 3HV9377 and 3HV9378, whichever valve pair is OPERABLE.

SR 3.4.12.1.4 Verify the OPERABLE SDCS Relief Valve isolation valve pair (valve pair 3HV9337 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and 3HV9339, or valve pair 3HV9377 and 3HV9378) is in the power-lock open condition.

SR 3.4.12.1.5 Verify that SDCS Relief Valve isolation 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months valves 3HV9337,

3HV9339, 3HV9377, and 3HV9378 are open when the SDCS Relief Valve is used for overpressure protection.

SR 3.4.12.1.6 Verify SDCS Relief Valve Setpoint.

In accordance with the Inservice Testing Program SAN ONOFRE--UNIT 3 3.4-34 Amendment No. +-6,134

LTOP System 3.4.12.2 SURVEILLANCE REQUIREMENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > 2460F LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2) Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are greater than the enable temperatures specified in Table 3.4.3-1.

NOTES----------------------------

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 130'F.

SAN ONOFRE--UNIT 3 3.4-35 Amendment No. 116

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

Not Used Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

5.7.1.6 5.7.1.7 (continued)

SAN 6NOFRE--UNIT 3 5.0-29 Amendment No. +54--159 1

PCN-551 Attachment C (Proposed Pages)

(Redline/Strikeout Pages)

SONGS Unit 2

TABLE OF CONTENTS 3.3 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start

.... 3.3-32 Containment Purge Isolation Signal (CPIS)

.... 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI)

. 3.3-44 Remote Shutdown System

............. 3.3-48 Source Range Monitoring Channels

........ 3.3-51 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 REACTOR COOLANT SYSTEM (RCS)

RCS DNB Pressure, Temperature, and Flow Limits RCS Minimum Temperature for Criticality.

RCS Pressure and Temperature (P/T) Limits Pressurizer Heatup/Cooldown Limits......

RCS Loops -MODES 1 and 2...........

RCS Loops -MODE 3..............

RCS Loops -MODE 4..............

RCS Loops-MODE 5, Loops Filled RCS Loops -MODE 5, Loops Not Filled.....

Pressurizer Pressurizer Safety Valves Not Used Low Temperature Overpressure Protect.inn.(ITOP)

System, RCS Temperature

2564 FPTLR Limit Low Temperature Overpressure Protertinn (I TOP)

System, RCS Temperature > 256-FPTLR Limit RCS Operational LEAKAGE...........

RCS Pressure Isolation Valve (PIV) Leakage..

RCS Leakage Detection Instrumentation....

RCS Specific Activity............

EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS -Operating ECCS-Shutdown................

Refueling Water Storage Tank (RWST)

Trisodium Phosphate (TSP)

.. 3.4-1

.. 3.4-4

.. 3.4-5

.. 3.4-13

.. 3.4-15

.. 3.4-16

.. 3.4-18

.. 3.4-21

.. 3.4-24,

.. 3.4-26

.. 3.4-28

.. 3.4-30

.. 3.4-35

.. 3.4-37

.. 3.4-39

.. 3.4-44

.. 3.4-47 I

.. 3.5-1

.. 3.5-4

.. 3.5-8

.. 3.5-9

.. 3.5-11 (continued)

SAN ONOFRE--Unit 2 ii i Amendment No. 1+7

Definitions 1.1 1.1 Definitions OPERABLE-OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND TEMPERATURE LIMITS REPORT. (PTLR)

RATED THERMAL POWER (RTP)

The'PTLR is the unit specific document that

'provides the reactor vessel pressure and' temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. 'These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.7.1.6.'

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

(continued)

SAN ONOFRE--UNIT 2 1.1-5 Amendment No. 4-88

Definitions 1.1 1.1 Definitions REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

Amendment No..

SAN ONOFRE--UNIT 2

1.

1-5a I

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 The combination of.RCS pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within:the limits as-specified in the RCS PRESSURE-TEMPERATURE LIMITS REPORT (PTLR).

With the reaeter vessel head belts tensioned*, the Recaetor Coolant Sy team (exeept the -,rc uriu 1,,zer) temperature and prcssure shall be limited in accordance with the limit lines shown on Figurcs 3.4.3 1, 3.4.3 2, 3.4.3 3, 3.4.3-4, 3.4.3 5, and Table 3.4.3 1 during heatup, cooldown, and inservice leak and hydrostatic testing with.

a. A maximum heatup of 60°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period with RCS cold leg temperature greater than or equal to 65°F.

b. A maximum cooldown as specified by Figure 3.4.3 3 in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period with RCS cold leg temperature less than or cqual to 160 0F. A maximum cooldown of 100°F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period with RCS cold leg temperature greater than

-c. A maximum temperature change of 100F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

d. A minimum temperature of 65°F to tension reactor vessel head bolts.

With the reactor vessel head bolts detensioned, the Reactor Coolant System (except the pressurizcr) temperature shall be limited to a maximum heatup or cooldown of 600 U

in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

11ith the reactor vesse may be less than 654F.

1 head bolts detensioned, RCS cald leg tempcrature 3.4-5 Amendment No.

SAN ONOFRE--UNIT 2 1 7 t*

_/, I 1

RCS P/T Limits

3.4.3 APPLICABILITY

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

< 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

SAN ONOFRE--UNIT 2 3.4-6 Amendment No. -127 I

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS heatup and.rnnlfnwn rates within limits specified in the PTLRFigure 3.4.3 1, Figure 3.4.3 2, Fi7re 3.

3,11e 3.4.3 4, Fioure 3.4.3 5, an rie 3.4.3-1.

30 minutes SR 3.4.3.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H. The results of these pyaminations shall be used to update the PTLR -:1-3.4.3 1 through 3.4.3-5.

Rdclculate the Adjusted Reference Temperature in accordance with Regulatory r.c 1n-o, Revision 2, "Rladiation brittlment of Reaeter Vessel IMatrials,"

_,M r oGd1artAy-1988 In accordance with requirements of 10CFR 50 Appendix H SAN ONOFRE--UNIT 2 3.4-6a Amendment No. 1-27

RCS P/T Limits 3.4.3 LOWEST SERVICE

INSERVICE TESTS FHEATUP TEMP-209'F

+ Acceptable operating region - 10 the right of the InsorViC tests ourve (Applicable In modes other than Modes Is and 2)

_ Acceptable operating region-to the n

0 IddflIone Ina Mcres In and 2

I opErating region i6 to the right tho

,7 core criticiU curve.

0.0 w

t.1.

en,

~~~

a

/-

L, CORE__

OIwo CRITICAL 000 MINI"Irlm i0 50 1W 150 200 250 500 360 INDICATED RCS TEMPERATURE ( F) -Tc rPi i -I t 4 1-1

-SONGS 2 HIEATUP RCZ PRESSURIE/TEMPERATURE LIMIhTATIONS UNT1IL v0 A rrY SAN ONOFRE--UNIT 2 3.4-7 Amendment No.

127,172

RCS P/T Limits 3.4.3 Nc._

LOWEST SERVICE COOLDOWN TEMP -2094F 303 cc1 to2 Operating.

Rego 1500 Operating 0:

,s.

1l~r-Soo UJ 2000*

0 Pxpab

21.

a

Oeali 500

Rgin*

i

~~~INIMUMtcatax SOLtUP3...

Oeatn litimp ftu2-rj I

2 I N.

I I

I tt 1

I 15 U0 so too too 200 250 300 350 INDICATED RCS TEMPERATURE (°F) -Tc FIGIIRn 3 4 2-V

eAAinc, n

VrAAI rnijhtS nlfC rnrrcc,,nr lTraAnrnrATvInrl

~UI1J LI~V LLUH ~ ~

IL-YJuJJIVLFVILFI-I1..

v.s W.\\.

w.s,

-_L.

iLIM~

Irvis jAJ II J

I.LL LwLJ I I I£lcrmal Operation SAN ONOFRE--UNIT 2 3.4-8 Amendment No.

127,172

RCS P/T Limits 3.4.3 60 70 SC 00 10

¶10 120 130 AO0 150 160 170 lO 190 200 210 INDICATED RCS TEMPERATURE ('F) -Tc NOTE; A MAXIMUM GOOLDOWN RATE oF 100orlIl is A. i n irr AT ANY TEMPERATURE ABOVE ico0r FICURE 3.4.3 3 SONGS. RGS PRESSURE[/TrMPERATUmR OprMI MAIUMALOWABLE G-OU.B.1,1 RATES'r (UNTIL 20 EF-PY)

Normal Operation SAN ONOFRE--UNIT 2 3.4-9 Amendment No. 127,172

RCS P/T Limits 3.4.3 LOWEST SERVICE COOLDOWN TEMP. 209F

\\

~

a II W

\\

X

t.

^

il i

w......

-. :--::..* i-*-z-t to.:.

- i a

f 4

j..

.* - *. i -S..*+.

-l

o--

C..

2Qm

- *Una0ceptable...-*

-J Operating Region J

O/e~ra ing

j.

Region Fz

~~~Soo.,R**.....

i FAINMUM

__P

.65_

~~~.

I1.-I I

I i'

I I

50 100 160 200 250 300 350 INDICATED RCS TEMPERATURE ('F) -Tc FICURE 3.4.3 4 SONCG 2 C0OLDOWN RCE PRESSURE/TEMPERATUR[

I TkATTATTfMIC

IITrrTI,

'n rrnv

-K l

.,I U.. 1 l?-me-.t hiitiWn 1ir

.Af Ann SAN ONOFRE--UNIT 2 3.4-10 Amendment No. 127,172

RCS P/T Limits 3.4.3 68 70 PO 100 1

120 130 140 150 10 170

¶50 t0O 20o 210 INDICATED RCS TEMPERATURE (F) -Tc tNOTr A t^4AXIlUM GOnnDONl~s RATE OF 1nnor/l4110 Ir BI LOWED AT ANY TEMPERATURE ABOVE lr1600F FIGURE 3.4.3 5

%AAVT e

n t

nr-nnielnlrlr^ln I I0T JVW11 J

L

-L. Iv"W14 RATESI\\ Col~

UNTL 2L EFPY n l cL juill n

Re t

Shtdwn OperaTT IVTIVioft uU1 SAN ONOFRE--UNIT 2 3.4-11 Amendment No. 127,172

RCS P/T Limits 3.4.3 t

.L t

I I

A e T___ AA ner r

n

_s n.

LVJ I mperature ia65 Overpres ure PratptizCn R anm Overatin.q Peri3d. ErFry Gold Leq Temnra-tur, During Dur' g llcatup Cooldown.

Until 20 (NIrImal Operation)

I U256 U3 l Until 20 (Remote shutdown Operation) 23 kleatup operation; are nat normally performed from the Remote Shutdown panels.

SAN ONOFRE--UNIT 2 3.4-12 Amendment No. +2-T

RCS Loops-MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

NOTES---------------------------

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for 5 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature t fless than or equal to the 2564FLTOP, enable temperature specified in the PTLR unless:

a. Pressurizer water volume is < 900 ft3. or

b. Secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 2 3.4-18 Amendment No. 127,175

RCS Loops -MODE 5, Loops Filled 3.4.7

_ _---------------NOTES

4. No reactor coolant pump or more nft hp, R.CSrnl d 25&2ftemperature in the (continued)---------------------

(RCP) shall be startpd with one lon. temperatures

the PTLR unless:

a.The pressurizer water volume is < 900 ft3 or b.The secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6.

All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 2 3.4-22 Amendment No. 1,7

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature

256-FPTLR Limitl LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isnlated or dpnressurized to less than the limit specified in the PTLRFigure -3.4.3-- and at least one of the following' overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1)

A lift setting of 406 +/- 10 psig,

2)

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

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than orni al to the enable temperatures specified in Table 3.4.3-4the PTLR, MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

NOTE-------------_-_-_

SIT isolationnr-dpnrpsziri7Ation to less than the Figure 3.4.3 2 limitlimits in the PTLR is only required when SIT pressure is greater than or equal to the maximum RCS pressure rfnr the existing RCS cold leg temperature allowed by the PTLRP/T limit curves provided in Figure 3.4.3-1 and fgre SAN ONOFRE--UNIT 2 3.4-30 Amendment No. 127, 147

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in Figure 3.4.3 1. Andiriure 3.4.3 2the PTLR.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in Figure 3.4.2 1 and rinsire 3.4.3 2the PTLR.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 2HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 2HV9339 or valve OPERABLE SDCS Relief pair 2HV9377 and Valve isolation valve 2HV9378) closed.

pair.

(continued)

SAN ONOFRE--UNIT 2 3.4-31 Amendment No. 447-

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1.1

NOTE-------------_-_

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed.

The requirement to rack out the HPSI pump breaker is satisfied with the pump reaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the limit.

specified in Figure 3.4.3-2the PTLR.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations I

(continued)

SAN ONOFRE--UNIT 2 3.4-33 Amendment No. 1,7

LTOP System 3.4.12.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > 256-FPTLR Limit LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

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

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are grater than the enable temperatures specified in Table 3.4.3-1the PTLR.

NOTES----------------_

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 130 0F.

SAN ONOFRE--UNIT 2 3.4-35 Amendment No. +1^7

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and /or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 NatUsedREACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS Dressure an'd temDerature limits for heatuD. cooldown,'

low temoerature'oDeration. criticality, and -hydrostatic testino as well as'heatuD and cooldownrates shall be established andfdocumented in-the PTLR for the following:'

Technical SDecification 3.4.3 RCS Pressure and Temperature (P/T)- Limits, Technical Specification 3.4.6 RCS Loops -

MODE 4, Technical Specification 3.4.7 RCS-Loops'- MODE 5, Loops

Filled, Technical SDec'ification 3.4.12.1 Low'TemDerature OverDressure Protection (LTOP)'System RCS Temperature '

PTLR Limit, and Techn ical SDecification -3.4.12.2 Low Temoerature Overoressure Protection (LTOP)YSystem RCS Temperature > PTLR Limit.

b.

The analvtical 'methods used to determine the RCS Dressure and temnerature limits shall be those Dreviouslv reviewed and aDoroved bv. the NRC,' specifically those described in the following document:

(continued)

SAN ONOFRE--UNIT 2 5.0-29 Amendment No. 163, 168

Reporting Requirements 5.7 5.7 Reporting Requirement~ (continued) 5.7.1.6 Not.UsedREACTOR COOLANT-SYSTEM (RCS)

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR).-(continued)

CE NPSD-683-A, The Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and LTOP Setpoints from the Technical Specifications.

c.

The PTLR shall be'provided to the NRCiupon issuance:for each reactor vessel fluence period and for any.revision-or supplement thereto.

Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

5.7.1.7 (continued)

SAN ONOFRE--UNIT 2 5.0-29a Amendment No. 163, 168

PCN-551 Attachment D (Proposed Pages)

(Redline/Strikeout Pages)

SONGS Unit 3

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start 3.3-32 Containment Purge Isolation Signal (CPIS)

. 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI) 3.3-44 Remote Shutdown System

............. 3.3-48 Source Range Monitoring Channels

........ 3.3-51 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 REACTOR COOLANT SYSTEM (RCS)...........

RCS DNB Pressure, Temperature, and Flow Limits...

RCS Minimum Temperature for Criticality.

RCS Pressure and Temperature (P/T) Limits Pressurizer Heatup/Cooldown Limits......

RCS Loops -MODES 1 and 2...........

RCS Loops -MODE 3..............

RCS Loops -MODE 4..............

RCS Loops -MODE 5, Loops Filled.......

RCS Loops-MODE 5, Loops Not Filled.....

Pressurizer.................

Pressurizer Safety Valves Not Used Low Temperature Overpressure Protertinn (LTOP)

System, RCS Temperature

246°FPTLR Low Temperature Overpressure Protertinn (LTOP)

System, RCS Temperature > 246°FPTLR....

RCS Operational LEAKAGE...........

RCS Pressure Isolation Valve (PIV) Leakage..

RCS Leakage Detection Instrumentation....

RCS Specific Activity............

EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS-Operating...............

ECCS-Shutdown..

Refueling Water Storage Tank (RWST).

Trisodium Phosphate (TSP)

.. 3.4-1

.. 3.4-4

.. 3.4-5

.. 3.4-13

.. 3.4-15

.. 3.4-16

.. 3.4-18

.. 3.4-21

.. 3.4-24

.. 3.4-26

.. 3.4-28

.. 3.4-30

.. 3.4-35

.. 3.4-37

.. 3.4-39

.. 3.4-44

.. 3.4-47 I

.. 3.5-1

.. 3.5-4

.. 3.5-8

.. 3.5-9

.. 3.5-11 (continued)

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

Definitions 1.1 1.1 Definitions OPERABLE-OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

RATED THERMAL POWER (RTP)

The PTLR is the unit specific document that provides'.the reactor vessel pressure and temperature'limits,includinq heatup and cooldown rates, -for the current reactor vessel fluence period.". These pressure and temperature-limits "shal1 be.'determined for each fluence period.in accordance with Specification 5.7.1.6.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

(continued)

SAN ONOFRE--UNIT 3 1.1-5 Amendment No. 474

Definitions 1.1 1.1 Definitions REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

SAN ONOFRE--UNIT 3

1.

1-5a Amendment No.

I

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 The combination of RCS pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within the limits as specified in the RCS PRESSURE-TEMPERATURE LIMITS REPORT (PTLR).-

With the reactor vessel head bolts tensioned*, the Reactor Coolant System (except the pressurizer) tp t

and pressure shall be limited in accordance wit.. thie limit.

lines shown on Figurse 3.4.3 1, 3.4.3 2, 3.4.3 3, 3.4.3 4, 3.4.3 5, and Table 3.4.3 1 during heatup, cooldown, and inscrvica leak and hydrostatic testing with.

a. A maximum heatup of 600F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period with RCS cold leg temperature greater than or equal to 650g.

b. A maximum cooldown as specified by Figure 3.4.3 3 in any 1-hour period with RCS cold leg temperature less than or equal to 147F. A maximum cooldoAin of A

OFO in any 1-hour period with RCS cold leg temperature greater than 1470F.

c. A maximum temperature change of 104F in any 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

d.

A minimum temperature of 650F to tension reactor vessel head belts.

With the reactor vessel head bolts detensioned, the Reactor Coolant System (exeept the prassurizer) temperature shall be limited to a maximum heatup or cooldown of An= in any 1hour period.

With the reactor vessel head bolts detensi may be less than 65F-.

oned, RCS cold 1eq temperature SAN ONOFRE--UNIT 3 3.4-5 Amendment No. 116,163

RCS P/T Limits

3.4.3 APPLICABILITY

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -----

NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

< 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

Amendment No. 4+6 l

SAN ONOFRE--UNIT 3 3.4-6

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4.

SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS heatup and rnnldnwn rates within limits specified in the PTLR.figure 3.4.3 1, iours 3-. 3 2, Hi ru 3.4.3 3, Figure 3.4.3 4, Figure 3.4.3 5, and Table 3.4.3 1.

30 minutes SR 3.4.3.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H. The results of these Pyaminations shall be used to update the PTLR.rFigures 3.4.3 1 through 3.4.3 5J.

Recalculate the Adjusted Rcference Temperature in accordance veith Regulatory Guide 1.9I, Revision 2, "Radiation SmH-/++1PM AC nf-P92AP*n VPIOCR21

.+r1" In accordance with requirements of 10CFR 50 Appendix H May-1988.

I woo aI SAN ONOFRE--UNIT 3 3.4-6a Amendment No. 44ge

RCS P/T Limits 3.4.3 4

I 5' '

I I

I

'p '

'l I

I I

I 4

I 1

LOWEST SERVICE

INSERVICE TESTS 8 HEATUP TEMP 2091 ow sr*

'}^

~~ 2s00

~.5. ;

a U,.

s AccepIab6e operaing rgion -lo the *J.

right of the Inservie tests curve (Applcable In rnodes other than Ui Modas 1 ard 2)

Z 8 a AccIPtabt operating region - tohe M

rnght of the heatup curve In all rrddes.

ry In addition, In Modes I and 2 the operating region is to the light of the core critical curve.

a LU C..

CORE CRITICAL 0NI~~~MUM.... __...,.,:

BOLTUPL 15 C I

I I

I

. I.

I I

I

, I -I-I I

I I

I S

I I -r I

S I

60 1M ISO MO 20 300 INDICATED RCS TEMPERATURE (F) -Tc I-Tr

,'II n

r' A

I

. I0 3M0 A

I AUUIXL-J.-T-J-L rn.rcun

'¶N virATi~n nfr nrprretinrr /TrrAnrnArltnr

.. J4J14.

sJ I (Lii I VIl'..

4 l~.4U~/I "I II L.IXIFI I UIL..

I?IjTiT!rA'rndeC (IP(TTI nfl rrnv L-L I IL Ifl II*UJII J

%JIlt I *L.

&I-I-iI SI Nfermal Operation SAN ONOFRE--UNIT 3 3.4-7 Amendment No. 116,163

RCS P/T Limits 3.4.3 IDC'EST SERVICE CODW T.EMP-2-9 u i

~

.2 26:

a.

wr Operating................

0j-

'-3 Regio MjIN'NjM

?

'3 TU a0a so 100 ISO 200 250 3W0 INDICATED RCS TEMPERATURE (°F) -Tc rTPIInr n

A n

n M5O I J.UVI'.L.

,.~

t-rAsp'r- -5 it~flI,-,rift nir nmrrr,,mr,

/,rrIj!rn~r ipnr

.JJI.JwivJ li

%.AJi-JLVJIIU2 AU. ~...U I &.I if L-l'.J I UI.L-I TlATTrA'TnUIe 11IIITO rin rrnv L.

I I"I(2 AL'JII.J U III A

L.~.

"I I-I Normal Operation1 SAN ONOFRE--UNIT 3 3.4-8 Amendment No.

116,163

RCS P/T Limits 3.4.3 ze S

p I

S S

S I

I I

S

_E 100 _1 l____

-H 70 80

_o 40-/_

30 20 10 _

Ii I.

I I I

I I.

I I

I I I

.I I.I I

I I

60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 A

T 14M I I A

A rflrsO

-ipTr tI rI"IRii 3.4.3-nP nI5 Ul*

,rin-nAr11l I

-IJ?

rS

_Ov_

Ilu.J a

i JJIJXL1 I LI1-I L.Ix I l i'sL.

L.

1 I, MAXItMLIM AL fVJARI r4 w

Cffl lf ATF (lINTI! 90 ErY)

Nrma1I ORlrA4ti n

,v--

.I SAN ONOFRE--UNIT 3 3.4-9 Amendment No. 116,163

RCS P/T Limits 3.4.3 LOWEST SEAVICE COOLDOWN TEMP *209'F 4...

.Accept able loco 0.Z-

~-

IN LOTU

7.

T.'

. 1..i I.,

. ..

2 I

j[,

I I

a f

Is so M~

IS 2O 200 M 8 INDICATED RCS TEMPERATURE ('F) -TG rTrilinr j

A A

&SO Ir-A~auI

.Jr,,-r HM~ITATIONS UNTIL 20 EFPY Rem

-S II L Zudown Operatift SAN ONOFRE--UNIT 3 3.4-10 Amendment No. 116,163

RCS P/T Limits 3.4.3 60 70 60 90 20 110 10 1o 160 1¶0 160 170 180 190 2

210 NOTE-A 114 I&IqgR~L<<TE~

F&MN LfAJM FZ) ffc I-cLOWEJD AT ANY TEMPERATURE ABOVE 15Z0F FIGURE 3.4.3 5 SONGSR 3 R hu PRECSE/nE MPErATURi tLIMT

-LOWAB E G rAVO g/l 4%IE (GNTI 20n EFP rY Remote Shutdown Operation SAN ONOFRE--UNIT 3 3.4-11 Amendment No. 116,163

RCS P/T Limits 3.4.3 Law Tem-verature RGS 0veflressure Prateetion Rlange On:eratinv Period.

FPY Col Le_ Temoeratur During Bur'ng HtIiGo I

Until 20 (Normal Operation) t 246

Hi Until 20 (Remote shutdown Operation) 225 leatup operation; arI not normally performed from the Remote Shutdown panls SAN ONOFRE--UNIT 3 3.4-12 Amendment No. 446

RCS Loops -MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops -MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

NOTES-----------------_-___

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a.

No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2. No RCP shall bp Startpd.with anv PCr rnld leg tomnoratime PC hn r nlAl 2nth 46°F LTOP enable temperature specified in the PTLR unless:

a. Pressurizer water volume is < 900 ft3, or

b. Secondary side water temperature in each steam generator (SG) is < 100HF above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 3 3.4-18 Amendment No. 116,166

RCS Loops-MODE 5, Loops Filled 3.4.7 NOTES 1

4. No reactor coolant pump nr, mnre nf thp RCS P

idrn]

temperature in the PTLR (continued)---------------------

(RCP) shall be started with one leg temperatures < 246°F the unless:

I a.The pressurizer water volume is < 900 ft3 or b.The secondary side water temperature in each steam generator (SG) is < 100'F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6. All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 3 3.4-22 Amendment No. 4-16

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature < 246°FPTLR Limit LCO 3.4.12.1 No more than two high pressure safety injection pumps shall be OPERABLE, the safety injection tanks shall be isolated or depressuri7Pd.to less than the limit specified in Figure 3.4.3-thePTLR and at least one of the following overpressure protection systems shall be OPERABLE:

I

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2) Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or pnilal-to the enable temperatures specified in Table 3.4.3-+the PTLR, MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

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

SIT isolation r nr-Pnrpcc iir;i7At.ion to less than the Figure 3.4.3 2 limitlimits in the PTLR is only required when SIT pressure is greate'r than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed Ey the PT4 i mi.-t..urves rviiuure 3.4.3 1 and fure-3-A73--aPTR.

D-l SAN ONOFRE--UNIT 3 3.4-30 Amendment No. 116, 139

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in figure 3.4.3 -1 annd riure 3.4.3-4the PTLR.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in Figure 3.4

1.

and riiiire 3.4.3 2the PTLR.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 3HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 3HV9339 or valve OPERABLE SDCS Relief pair 3HV9377 and Valve isolation valve 3HV9378) closed.

pair.

(continued)

SAN ONOFRE--UNIT 3 3.4-31 Amendment No. +1-6

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 4.

SR 3.4.12.1.1 NOTE-------------------

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed.

The requirement to rack out the HPSI pump breaker is satisfied with the pump breaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the-limit specified in Figure 3.4.3-2the PTLR.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations I

(continued)

SAN ONOFRE--UNIT 3 3.4-33 Amendment No. +16

LTOP System 3.4.12.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > 246-FPTLR Limit LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406

10 psig,

2) Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are groater than the enable temperatures specified in Table 3.4.3 ithel PTLR.

NOTES---------------------------

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 130 0F.

SAN ONOFRE--UNIT 3 3.4-35 Amendment No. +1-6

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and /or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 N4f4-Jll,,RFACTOR COnlANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS'REPORT (PTLR)

a.

RC S nrPssire and `tPmnpratilre limits for heattin. co'oldown, low temneratimre nnpratinn. rritiralitv. and hvdrostatic testino as well as heatiin and connldown rates shall She..

established and-documented in the PTLR-for the following:

Tpchniral Snpcification 3.4.3 RCS Pressure and Temperature (P/T) Limits, Technical Specification 3.4.6 RCS Loops.- MODE 4, Tprhniral Specification 3.4.7 RCS Loops -

MODE 5, Loops

Filled, Tprhn'iral Snpreifiratinn 3.4.1?.l low Temnpratijre Overnrpssure Protection (LTOP) System RCS Temperature

PTLR Limit, and Tprhniral Sner.ifiration 3.4.1?.? low TPmnprattirp Ovprnressure Protection (LTOP) System RCS Temperature > PTLR Limit.

b.

Thp analytical mpthnds u sep to determine the RCS nre.ssuir and tpmneratijre limits shall he thnse nrpvinijslv rpvipwed and annrnvpd hv'the NRC, specifically those described in the following document.;

(continued)

SAN ONOFRE--UNIT 3 5.0-29 Amendment No.

154,159

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.6 Noet UsedREACTOR COOLANT--'SYSTEM (RCS)

PRESSURE 'AND TEMPERATURE LIMITS REPORT (PTLR) -(continued)

CE NPSD-683-A, LThe Development of a RCS Pressure and Temperature Limits Report for'the Removal of P-T Limits and LTOP Setpoints from_.the Technical Specifications.

c.'

The PTLR shall be'providedlto theANRC upon issuance for each Freactor vessel fluence period and for any revision or

'supplement thereto.

Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

5.7.1.7 (continued)

SAN ONOFRE--UNIT 3 5.0-29a Amendment No.

PCN-551 Attachment E (Proposed Pages)

SONGS Unit 2

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

Instrumentation

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start

.... 3.3-32 Containment Purge Isolation Signal (CPIS)

.... 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI)

. 3.3-44 Remote Shutdown System

............. 3.3-48 Source Range Monitoring Channels

........ 3.3-51 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 REACTOR COOLANT SYSTEM (RCS)...........

RCS DNB Pressure, Temperature, and Flow Limits..................

RCS Minimum Temperature for Criticality...

RCS Pressure and Temperature (P/T) Limits Pressurizer Heatup/Cooldown Limits......

RCS Loops-MODES 1 and 2...........

RCS Loops-MODE 3..............

RCS Loops-MODE 4..............

RCS Loops-MODE 5, Loops Filled.......

RCS Loops-MODE 5, Loops Not Filled.....

Pressurizer.................

Pressurizer Safety Valves Not Used Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < PTLR Limit...

Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > PTLR Limit...

RCS Operational LEAKAGE...........

RCS Pressure Isolation Valve (PIV) Leakage..

RCS Leakage Detection Instrumentation.

RCS Specific Activity............

EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS -Operating ECCS -Shutdown......

Refueling Water Storage Tank (RWST)....

Trisodium Phosphate (TSP) 3.4-1

.. 3.4-1 3.4-4 3.4-5 3.4-13 3.4-15 3.4-16 3.4-18

.. 3.4-21 3.4-24 3.4-26

.. 3.4-28 3.4-30 3.4-35

.. 3.4-37 3.4-39

.. 3.4-44 3.4-47 I

I 3.5-1 3.5-1 3.5-4 3.5-8 3.5-9

. 3.5-11 (continued)

SAN ONOFRE--Unit 2 i ii Amendment No.

Definitions 1.1 1.1 Definitions OPERABLE - OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

RATED THERMAL POWER (RTP)

The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.7.1.6.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

(continued)

SAN ONOFRE--UNIT 2 1.1-5 Amendment No.

Definitions 1.1 1.1 Definitions REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

SAN ONOFRE--UNIT 2

1.

1-5a Amendment No.

I

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 APPLICABILITY:

The combination of RCS pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within the limits as specified in the RCS PRESSURE-TEMPERATURE LIMITS REPORT (PTLR).

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

< 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

SAN ONOFRE--UNIT 2 3.4-5 Amendment No.

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates within limits specified in the PTLR.

30 minutes I

SR 3.4.3.2 The reactor vessel material irradiation In accordance surveillance specimens shall be removed and with examined, to determine changes in material requirements of properties, as required by 10 CFR 50 10CFR 50 Appendix H. The results of these Appendix H examinations shall be used to update the PTLR.

I SAN ONOFRE--UNIT 2 3.4-6 Amendment No.

RCS P/T Limits 3.4.3 Figure 3.4.3-1 DELETED I

SAN ONOFRE--UNIT 2 3.4-7 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-2 DELETED I

SAN ONOFRE--UNIT 2 3.4-8 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-3 DELETED I

SAN ONOFRE--UNIT 2 3.4-9 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-4 DELETED I

SAN ONOFRE--UNIT 2 3.4-10 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-5 DELETED I

SAN ONOFRE--UNIT 2 3.4-11 Amendment No.

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 DELETED I

SAN ONOFRE--UNIT 2 3.4-12 Amendment No.

RCS Loops-MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops -MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

NOTES---------------------------

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2.

No RCP shall be started with any RCS cold leg temperature less than or equal to the LTOP enable:

temperature specified in the PTLR unless:

a. Pressurizer water volume is < 900 ft3. or

b. Secondary side water temperature in each steam generator (SG) is < 100IF above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 2 3.4-18 Amendment No.

RCS Loops -MODE 5, Loops Filled 3.4.7 NOTES

4. No reactor coolant pump or more of the RCS cold temperature in the PTLR (continued)---------------------

(RCP) shall be started with one leg temperatures s the unless:

I a.The pressurizer water volume is < 900 ft3 or b.The secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6. All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 2 3.4-22 Amendment No.

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature

PTLR Limit LCO 3.4.12.1 No more than two be OPERABLE, the depressurized to and at least one systems shall be high pressure safety injection pumps shall safety injection tanks shall be isolated or less than the limit specified in the PTLR of the following overpressure protection OPERABLE:

I I

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

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

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in the

PTLR, I

MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

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

SIT isolation or depressurization to less than the limits in the PTLR is only required when SIT pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PTLR.

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

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in the PTLR.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 2HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 2HV9339 or valve OPERABLE SDCS Relief pair 2HV9377 and Valve isolation valve 2HV9378) closed.

pair.

(continued)

I I

SAN ONOFRE--UNIT 2 3.4-31 Amendment No.

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1.1

NOTE-------------_

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed.

The requirement to rack out the HPSI pump breaker is satisfied with the pump breaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the limit specified in the PTLR.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations I

(continued)

SAN ONOFRE--UNIT 2 3.4-33 Amendment No.

LTOP System 3.4.12.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > PTLR Limit LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

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

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are greater than the enable temperatures specified in the PTLR.

NOTES----------------------------

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 1300F.

SAN ONOFRE--UNIT 2 3.4-35 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

Technical Specification 3.4.3 RCS Pressure and Temperature (P/T) Limits, Technical Specification 3.4.6 RCS Loops - MODE 4, Technical Specification 3.4.7 RCS Loops - MODE 5, Loops

Filled, Technical Specification 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature

PTLR Limit, and Technical Specification 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > PTLR Limit.

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

(continued)

SAN ONOFRE--UNIT 2 5.0-29 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)

CE NPSD-683-A, The Development Temperature Limits Report for LTOP Setpoints from the Techni

c.

The PTLR shall be provided to reactor vessel fluence period supplement thereto.

of a RCS Pressure and the Removal of P-T Limits and ical Specifications.

the NRC upon issuance for each and for any revision or 5.7.1.7 Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

(continued)

SAN ONOFRE--UNIT 2 5.0-29a Amendment No.

I

PCN-551 Attachment F (Proposed Pages)

SONGS Unit 3

TABLE OF CONTENTS 3.3 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 INSTRUMENTATION (continued)

Engineered Safety Features Actuation System (ESFAS)

Instrumentation

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

Logic and Manual Trip

............ 3.3-27 Diesel Generator (DG) -Undervoltage Start 3.3-32 Containment Purge Isolation Signal (CPIS)

.... 3.3-35 Control Room Isolation Signal (CRIS)

...... 3.3-39 Fuel Handling Isolation Signal (FHIS)

...... 3.3-42 Post Accident Monitoring Instrumentation (PAMI) 3.3-44 Remote Shutdown System

............. 3.3-48 Source Range Monitoring Channels

........ 3.3-51 3.4 3.4.1 3.4.2 3.4.3 3.4.3.1 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12.1 3.4.12.2 3.4.13 3.4.14 3.4.15 3.4.16 REACTOR COOLANT SYSTEM (RCS)...........

RCS DNB Pressure, Temperature, and Flow Limits...

RCS Minimum Temperature for Criticality.

RCS Pressure and Temperature (P/T) Limits Pressurizer Heatup/Cooldown Limits......

RCS Loops-MODES 1 and 2...........

RCS Loops -MODE 3..............

RCS Loops-MODE 4..............

RCS Loops -MODE 5, Loops Filled.......

RCS Loops -MODE 5, Loops Not Filled Pressurizer Pressurizer Safety Valves..........

Not Used Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature < PTLR.

Low Temperature Overpressure Protection (LTOP)

System, RCS Temperature > PTLR......

RCS Operational LEAKAGE RCS Pressure Isolation Valve (PIV) Leakage..

RCS Leakage Detection Instrumentation....

RCS Specific Activity............

EMERGENCY CORE COOLING SYSTEMS (ECCS)

Safety Injection Tanks (SITs)

ECCS-Operating...............

ECCS-Shutdown.

i......

Refueling Water Storage Tank (RWST)

Trisodium Phosphate (TSP)

.. 3.4-1

.. 3.4-4

.. 3.4-5

.. 3.4-13

.. 3.4-15

.. 3.4-16

.. 3.4-18

.. 3.4-21

.. 3.4-24

.. 3.4-26

.. 3.4-28

.. 3.4-30 I

.. 3.4-35

.. 3.4-37

.. 3.4-39

.. 3.4-44

.. 3.4-47 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5

.. 3.5-1

.. 3.5-4

.. 3.5-8

.. 3.5-9

.. 3.5-11 (continued)

SAN ONOFRE--Unit 3 Amendment No.

Definitions 1.1 1.1 Definitions OPERABLE-OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the SONGS Units 2 and 3 UFSAR;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

RCS PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

RATED THERMAL POWER (RTP)

The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period.

These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.7.1.6.

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3438 MWt.

(continued)

SAN ONOFRE--UNIT 3 1.1-5 Amendment No.

Definitions 1.1 1.1 Definitions REACTOR PROTECTIVE SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM)

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

(continued)

SAN ONOFRE--UNIT 3 1.1I-5a Amendment No.I

RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 APPLICABILITY:

The combination of RCS pressure, RCS temperature and RCS heatup and cooldown rates shall be maintained within the limits as specified in the RCS PRESSURE-TEMPERATURE LIMITS REPORT (PTLR).

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE---------

A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.

shall be completed whenever this AND Condition is entered.

A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months acceptable for Requirements of LCO continued operation.

not met in MODE 1, 2, 3, or 4.

B. Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met.

B.2 Be in MODE 5 with 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months RCS pressure

< 500 psia.

C. ---------NOTE---------

C.1 Initiate action to Immediately Required Action C.2 restore parameter(s) shall be completed to within limits.

whenever this Condition is entered.

AND C.2 Determine RCS is Prior to Requirements of LCO acceptable for entering MODE 4 not met any time in continued operation.

other than MODE 1, 2, 3, or 4.

SAN ONOFRE--UNIT 3 3.4-5 Amendment No.

RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.4.3.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify RCS pressure, RCS temperature, and 30 minutes RCS heatup and cooldown rates within limits specified in the PTLR.

SR 3.4.3.2 The reactor vessel material irradiation In accordance surveillance specimens shall be removed and with examined, to determine changes in material requirements of properties, as required by 10 CFR 50 IOCFR 50 Appendix H. The results of these Appendix H examinations shall be used to update the PTLR.

I I

SAN ONOFRE--UNIT 3 3.4-6 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-1 DELETED I

SAN ONOFRE--UNIT 3 3.4-7 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-2 DELETED I

SAN ONOFRE--UNIT 3 3.4-8 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-3 DELETED SAN ONOFRE--UNIT 3 3.4-9 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-4 DELETED I

SAN ONOFRE--UNIT 3 3.4-10 Amendment No.

RCS P/T Limits 3.4.3 FIGURE 3.4.3-5 DELETED I

SAN ONOFRE--UNIT 3 3.4-11 Amendment No.

RCS P/T Limits 3.4.3 TABLE 3.4.3-1 DELETED I

SAN ONOFRE--UNIT 3 3.4-12 Amendment No.

RCS Loops -MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops or trains consisting of any combination of RCS loops and shutdown cooling (SDC) trains shall be OPERABLE and at least one loop or train shall be in operation.

NOTES---------------------------

1. All reactor coolant pumps (RCPs) and SDC pumps may be de-energized for

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature less than or equal to the LTOP enable temperature specified in the PTLR unless:

I

a. Pressurizer water volume is < 900 ft3. or

b. Secondary side water temperature in each steam generator (SG) is < 100'F above each of the RCS cold leg temperatures.

APPLICABILITY:

MODE 4.

SAN ONOFRE--UNIT 3 3.4-18 Amendment No.

RCS Loops -MODE 5, Loops Filled 3.4.7

NOTES

4. No reactor coolant pump or more of the RCS cold temperature in the PTLR (continued)---------------------

(RCP) shall be started with one leg temperatures

the unless:

a.The pressurizer water volume is < 900 ft3 or b.The secondary side water temperature in each steam generator (SG) is < 1000F above each of the RCS cold leg temperatures.

5. A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling trains to provide shutdown cooling flow provided the reactor has been subcritical for a period

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the RCS is fully depressurized and vented in accordance with LCO 3.4.12.1.

6. All SDC trains may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to Immediately SDC trains/RCS loops restore the required OPERABLE.

SDC trains/RCS loops to OPERABLE status.

AND OR Any SG with secondary side water level not A.2 Initiate action to Immediately within limit.

restore SG secondary side water levels to within limits.

(continued)

SAN ONOFRE--UNIT 3 3.4-22 Amendment No.

LTOP System 3.4.12.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature s PTLR Limit LCO 3.4.12.1 No more than two be OPERABLE, the depressurized to and at least one systems shall be high pressure safety injection pumps shall safety injection tanks shall be isolated or less than the limit specified in the PTLR of the following overpressure protection OPERABLE:

I I

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2) Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,

b.

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

APPLICABILITY:

MODE 4 when the temperature of any one RCS cold leg is less than or equal to the enable temperatures specified in the

PTLR, I

MODE 5, and MODE 6 when the head is on the reactor vessel and the RCS is not vented.

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

SIT isolation or depressurization to less than the limits in the PTLR is only required when SIT pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PTLR.

l SAN ONOFRE--UNIT 3 3.4-30 Amendment No. 139

LTOP System 3.4.12.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. With more than two A.1 Initiate action to Immediately HPSI pumps capable of verify a maximum of injecting into the two HPSI pumps RCS.

capable of injecting into the RCS.

B. SIT pressure is B.1 Isolate affected SIT.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C. Required Action and C.1 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion SIT to less than the Time of Condition B maximum RCS pressure not met.

for existing cold leg temperature allowed in the PTLR.

D. With one or both SDCS D.1 Open the closed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Relief Valve isolation valve(s).

valves in a single SDCS Relief Valve OR isolation valve pair (valve pair 3HV9337 D.2 Power-lock open the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and 3HV9339 or valve OPERABLE SDCS Relief pair 3HV9377 and Valve isolation valve 3HV9378) closed.

pair.

(continued)

I I

SAN ONOFRE--UNIT 3 3.4-31 Amendment No.

LTOP System 3.4.12.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1.1

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

A HPSI pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed.

The requirement to rack out the HPSI pump breaker is satisfied with the pump breaker racked out to its disconnected or test position.

Verify a maximum of two HPSI pumps are capable of injecting into the RCS.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.12.1.2

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

Required to be performed when complying with the LCO 3.4.12.1 Note.

Verify each SIT is isolated or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months depressurized less than the limit specified in the PTLR.

SR 3.4.12.1.3 Verify RCS vent 2 5.6 square inches is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for open when in use for overpressure unlocked open protection.

vent valve(s)

AND 31 days for locked, sealed, or otherwise secured open vent valve(s),

or open flanged RCS penetrations I

(continued)

SAN ONOFRE--UNIT 3 3.4-33 Amendment No.

LTOP System 3.4.12.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > PTLR Limit LCO 3.4.12.2 At least one of the following overpressure protection systems shall be OPERABLE:

a.

The Shutdown Cooling System Relief Valve (PSV9349) with:

1) A lift setting of 406 +/- 10 psig,

2) Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,

b.

A minimum of one pressurizer code safety valve with a lift setting of 2500 psia +/- 1%.

APPLICABILITY:

MODE 4 when the temperature of all RCS cold legs are greater than the enable temperatures specified in the PTLR.

NOTES---------------------------

1.

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

2.

The SDCS Relief Valve lift setting assumes valve temperatures less than or equal to 130 0F.

SAN ONOFRE--UNIT 3 3.4-34 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

(continued) 6.b "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology," CEN-635(S), Rev. 00, February 1999 6.c Letter, Stephen Dembek (NRC) to Harold B. Ray (SCE),

dated June 2, 1999, "San Onofre Nuclear Generating Station Units 2 and 3 - Evaluation of Reload Analysis Methodology Technology Transfer (TAC Nos. MA4289 and MA4290)"

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle-to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

Technical Specification 3.4.3 RCS Pressure and Temperature (P/T) Limits, Technical Specification 3.4.6 RCS Loops - MODE 4, Technical Specification 3.4.7 RCS Loops - MODE 5, Loops Filled, and Technical Specification 3.4.12.1 Low Temperature Overpressure Protection (LTOP) System RCS Temperature < PTLR Limit and, Technical Specification 3.4.12.2 Low Temperature Overpressure Protection (LTOP) System RCS Temperature > PTLR Limit.

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document:

(continued)

SAN ONOFRE--UNIT 3 5.0-29 Amendment No.

159

Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued)

CE NPSD-683-A, The Development of Temperature Limits Report for the LTOP Setpoints from the Technical

c.

The PTLR shall be provided to the reactor vessel fluence period and supplement thereto.

a RCS Pressure and Removal of P-T Limits and Specifications.

NRC upon issuance for each for any revision or 5.7.1.7 Hazardous Cargo Traffic Report Hazardous cargo traffic on Interstate 5 (I-5) and the AT&SF railway shall be monitored and the results submitted to the NRC Regional Administrator once every three years.

(continued)

SAN ONOFRE--UNIT 3 5.0-29a Amendment No.

I

PCN-551 Attachment G (Proposed Pages)

(Redline/Strikeout Pages)

SONGS Unit 2

RCS P/T Limits B 3.4.3 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.3 RCS Pressure and Temperature (P/T) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips.

This LCO limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation.

The PTLR contains>P/T limit curves-for heatup, cooldown, and inservice leak and hydrostatic (ISLH) testing, and data for the maximum rate of change of reactor coolant temperature (Ref.~ 1).

Each P/T limit curve defines an acceptable region for normal operation.

The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region.

The LCO establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB).

The vessel is the component most subject to brittle failure, and the LCO limits apply mainly to the vessel.

The limits do not apply to the pressurizer, which has different design characteristics and operating functions.

10 CFR 50, Appendix G (Ref. 2), requires the establishment of P/T limits for material fracture toughness requirements of the RCPB materials.

Reference 2 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests.

It mandates the use of the ASME Code,Section III, Appendix G (Ref. 3).

(continued)

SAN ONOFRE--UNIT 2 B 3.4-9 Amendment No. 427

RCS P/T Limits B 3.4.3 BASES (continued)

ACTIONS C.1 and C.2 (continued)

The Completion Time of "prior to entering MODE 4" forces the evaluation prior to entering a MODE where temperature and pressure can be significantly increased. The evaluation for a mild violation is possible within several days, but more severe violations may require special, event specific stress analyses or inspections.

Condition C is modified by a Note requiring Required Action C.2 to be completed whenever the Condition is entered.

The Note emphasizes the need to perform the evaluation of the effects of the excursion outside the allowable limits. Restoration alone per Required Action C.1 is insufficient because higher than analyzed stresses may have occurred and may have affected the RCPB integrity.

SURVEILLANCE SR 3.4.3.1 REQUIREMENTS.

Verification that operation is within the PTLRPressure tTemperatuife limits is required every 30 minutes when RCS pressure and temperature conditions are undergoing planned changes.

This Frequency is considered reasonable in view of the control room indication available to monitor RCS status.

Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits assessment and correction for minor deviations within a reasonable time.

Surveillance for heatup, cooldown, or ISLH testing may be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied.

This SR is modified by a Note that requires this SR be performed only during RCS system heatup, cooldown, and ISLH testing.

No SR is given for criticality operations because LCO 3.4.2 contains a more restrictive requirement.

NOTE:

Any change in RCS temperature of less than 10 degrees F in any one hour period during normal operation is not considered an RCS heatup/

cooldown. This type of transient is determined by ASME III Code Class 1 stress calculations to be an insignificant transient in the contribution to the component fatigue usage factor.

(continued)

SAN ONOFRE--UNIT 2 B 3.4-15 Amendment No. 127 05/30/00

RCS P/T Limits B 3.4.3 BASES (continued)

SURVEILLANCE REQUIREMENTS (continued)

SR 3.4.3.2 This SR verifies that the reactor vessel material irradiation surveillance specimens will be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H. The results of these examinations will be used to update the PTLR.Figures 3.4.3 1 through 3.4.3 5.

Also, the Adju-ted Rflefrtincz I enpe Ratur:

will be releulated IIIn Uc.rdane with Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel I1 It1..

so I1'1 1 I. I U4 I a It IU Ma REFERENCES

1. CE NPSD-683-A,'The Development of a RCS Pressure and Temperature Limits Report for the Removal of P-T Limits and'-LTOP Setpoints from the Technical Specifications'.

2.

10 CFR 50, Appendix G.

3. ASME, Boiler and Pressure Appendix G.

Vessel Code,Section III,

4. ASTM E185-73.

5.

10 CFR 50, Appendix H.

6. ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.

7.

UFSAR, Chapter 5.

SAN ONOFRE--UNIT 2 B 3.4-16 Amendment No. Ag2e

RCS Loops-MODE 4 B 3.4.6 BASES (continued)

LCO (continued) prohibits boron dilution with coolant at boron concentrations less than required to assure the SDM of LCO 3.1.1 is maintained when forced flow is stopped because an even concentration distribution cannot be ensured. Core outlet temperature is to be maintained at least 10F below saturation temperature so that no vapor bubble may form and possibly cause a natural circulation flow obstruction.

The response of the RCS without the RCPs or SDC pumps depends on the core decay heat load and the length of time that the pumps are stopped. As decay heat diminishes, the effects on RCS temperature and Pressure diminish. Without cooling by forced flow, higher heat loads will cause the reactor coolant temperature and pressure to increase at a rate proportional to the decay heat load.

Because pressure can increase, the applicable system pressure limits (pressure and temperature (P/T) limits or low temperature overpressure protection (LTOP) limits) must be observed and forced SDC flow or heat removal via the SGs must be re-established prior to reaching the pressure limit. The circumstances for stopping both RCPs or SDC pumps are to be limited to situations where:

a.

Pressure and temperature increases can be maintained well within the allowable pressure (P/T limits and LTOP) and 100F subcooling limits; or

b.

An alternate heat removal path through the SGs is in operation.

Note 2 requires that either of the following two conditions be satisfied before..an-RCP mav ho,tartPH with anvPrCS cold Jon tPmnPrit11rpR-IPcPk than nr Pniual to'the LTOP enable temperature specified'in the PTLR256-F.

a.

Pressurizer water volume is < 900 ft3; or

b.

Secondary side water temperature in each SG is < 100'F above each of the RCS cold leg temperatures.

Satisfying the above condition will preclude a large pressure surge in the RCS when the RCP is started.

An OPERABLE RCS loop consists of at least one OPERABLE RCP and an SG that is OPERABLE in accordance with the Steam Generator Tube Surveillance Program and has the minimum water level specified in SR 3.4.6.2.

(continued)

II SAN ONOFRE--UNIT 2 B 3.4-32 Amendment No. 127,175 12/20/00

RCS Loops -MODE 4 B 3.4.6 BASES (continued)

LCO maintained subcooled, and boron stratification affecting (continued) reactivity control is not expected.

Note 2 allows one SDC train to be inoperable for a period of up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided that the other SDC train is OPERABLE and in operation. This permits periodic surveillance tests to be performed on the inoperable train during the only time when such testing is safe and possible.

Note 3 allows one RCS loop to be inoperable for a period of up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided that the other RCS loop is OPERABLE and in operation. This permits periodic surveillance tests to be performed on the inoperable loop during the only time when such testing is safe and possible.

Note 4 requires that either of the following two conditions be satisfied before an RCP may be started with 'any-'RCS cold

-leg temperature less thanor equal to the LTOP enableI

'temperature specified in the PTLR:

a.

Pressurizer water volume must be < 900 ft3; or

b. Secondary side water temperature in each SG must be

< 100IF above each of the RCS cold leg temperatures.

Satisfying either of the above conditions will preclude a low temperature overpressure event due to a thermal transient when the RCP is started.

Note 5 specifies that a containment spray (CS) pump may be used in place of a low pressure safety injection (LPSI pump in either or both shutdown cooling trains to provide shutdown cooling (SDC) flow based on the calculated heat load of the core 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the reactor is sub-critical with the reactor coolant system (RCS) fully depressurized and vented in accordance with TS 3.4.12.

Note 6 provides for an orderly transition from MODE 5 to MODE 4 during a planned heatup by permitting removal of SDC trains from operation when at least one RCP is in operation.

An OPERABLE SDC train is composed of an OPERABLE SDC pump and an OPERABLE SDC heat exchanger.

SDC pumps are OPERABLE if they are capable of being powered and are able to provide flow if required.

An OPERABLE RCS loop consists of at least one OPERABLE RCP and an OPERABLE SG. An OPERABLE SG can perform as a heat sink when it has (continued)

SAN ONOFRE--UNIT 2 B 3.4-38 Amendment No. 127,175 I n Ion Innr

_7 V/V

RCS Temperature LTnP system

< PTLR256'F B 3.4.12.1 I

B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.12.1 Low Temperature Ovprnrpqqilrp Protection (LTOP) System RCS Temperature

PTLR Limit2562 F I

BASES BACKGROUND The LTOP System controls RCS pressure at low temperatures so the integrity of the reactor coolant pressure boundary (RCPB) is not compromised by violating the pressure and temperature (P/T) limits of 10 CFR 50, Appendix G (Ref. 1).

The reactor vessel is the limiting RCPB component for demonstrating such protection.

LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," provides the allowable combinations for operational pressure and temperature during cooldown, shutdown, and heatup to keep from violating the Reference 1 requirements during the LTOP MODES.

The reactor vessel material is less tough at low temperatures than at normal operating temperatures.

As the vessel neutron exposure accumulates, the material toughness decreases and becomes less resistant to pressure stress at low temperatures (Ref. 2).

RCS pressure, therefore, is maintained low at low temperatures and is increased only as temperature is increased.

The potential for vessel overpressurization is most acute when the RCS is water solid, occurring only during shutdown; a pressure fluctuation can occur more quickly than an operator can react to relieve the condition.

Exceeding the RCS P/T limits by a significant amount could cause brittle cracking of the reactor vessel.

LCO 3.4.3 requires administrative control of RCS pressure and temperature during heatup and cooldown to prevent exceeding the P/T limits.

The design basis of the LTOP assumes unrestricted flow from two HPSI pumps and three charging pumps (full charging capacity) without letdown.

Because there are three HPSI pumps and three charging pumps, the limitation on the number of HPSI pumps to be maintained OPERABLE during the specified MODES, along with isolating the Safety Injection Tanks, ensures that a mass addition to the RCS that exceeds the design basis assumptions of the LTOP will not occur. This limitation on the number of HPSI pumps that can provide (continued)

SAN ONOFRE--UNIT 2 B 3.4-55 Amendment No. 42-7

LTnP System RCS Temperature

PTLR256°F B 3.4.12.1 BASES (continued)

BACKGROUND makeup and injection to the RCS implements the guidance (continued) provided in Generic Letter 90-06.

With minimum coolant input capability, the ability to provide core coolant addition is restricted. The LCO does not require the makeup control system deactivated or the safety injection (SI) actuation circuits blocked.

Due to the lower pressures in the LTOP MODES and the expected core decay heat levels, the makeup system can provide adequate flow via the makeup control valve and, if needed, until the HPSI pump is actuated by SI.

Shutdown Cooling System Relief Valve Requirements The Shutdown Cooling System relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 1000F above the RCS cold leg temperatures or (2) inadvertent safety injection actuation with two HPSI pumps injecting into a water-solid RCS with full charging capacity and letdown isolated.

RCS Vent Requirements Once the RCS is depressurized, a vent exposed to the containment atmosphere will maintain the RCS at containment ambient pressure in an RCS overpressure transient, if the relieving requirements of the transient do not exceed the capabilities of the vent.

Thus, the vent path must be capable of relieving the flow resulting from the limiting LTOP mass or heat input transient and maintaining pressure below the P/T limits.

The required vent capacity may be provided by one or more vent paths.

The OPERABILITY of an RCS vent opening of greater than 5.6 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS rnid legs is less than or equal to that specified in the PTLR Pressure/Temperature Limits.

The vent path(s) must be above the level of reactor coolant, so as not to drain the RCS when open.

(continued)

SAN ONOFRE--UNIT 2 B 3.4-56 Amendment No. +24

LTOP System RCS Temperature

PTLR256-9F B 3.4.12.1 BASES (continued)

APPLICABLE SAFETY ANALYSES Safety analyses (Ref. 3) demonstrate that the reactor vessel is adequately protected against exceeding the Reference 1 P/T limits during shutdown. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with RCS rngd leg temperature greater than that specified in the PTLR.

Prssure/Tzmperature Limits.

In the event that no safety valves are OPERABLE and for RCS cold len tpmperature less than or equal to that specified in the PTLR, Pressurc/Temperature Limits the operating shutdown cooling relief valve, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

When the RCS is depressurized, an RCS vent to atmosphere sized 5.6 inches or greater may be used as an alternative to the SDCS Relief Valve.

I The actual temperature at which the pressure in the P/T limit curve falls below the pressurizer safety valve setpoint increases as the reactor vessel material toughness decreases due to neutron embrittlement.

Each time the P/T limit curves are revised, the LTOP System will be re-evaluated to ensure its functional requirements can still be satisfied using the relief valve method or the depressurized and vented RCS condition.

Reference 3 contains the acceptance limits that satisfy the LTOP requirements.

Any change to the RCS must be evaluated against these analyses to determine the impact of the change on the LTOP acceptance limits.

Transients that are capable of overpressurizing the RCS are categorized as either mass or heat input transients, examples of which follow:

Mass Input Type Transients

a.

Inadvertent safety injection; or

b. Charging/letdown flow mismatch.

Heat Input Type Transients

a.

Inadvertent actuation of pressurizer heaters;

b.

Loss of shutdown cooling (SDC); or (continued)

SAN ONOFRE--UNIT 2 B 3.4-57 Amendment No. 1-27

LTnP System RCS Temperature

PTLR256cF B 3.4.12.1 BASES (continued)

APPLICABLE Heat Input Type Transients (continued)

SAFETY ANALYSES

c.

Reactor coolant pump (RCP) startup with temperature asymmetry within the RCS or between the RCS and steam generators.

The following are required during the LTOP MODES to ensure that mass and heat input transients do not occur, which either of the LTOP overpressure protection means cannot handle:

a.

No more than two HPSI pumps OPERABLE.

b.

Deactivating the SIT discharge isolation valves in their closed positions when SIT pressure equals or exceeds the maximum RCS pressure for existing RCS cold leg temperature allowed by the Pressure/Temperature Limits.

Shutdown Cooling System Relief Valve Performance One SDCS Relief Valve isolation valve pair is capable of mitigating an LTOP event that is bounded by the limiting SDCS pressure transients. When one or both SDCS Relief Valve isolation valve(s) in one isolation valve pair becomes INOPERABLE, the other OPERABLE SDCS Relief Valve isolation valve pair is placed in a power-lock open condition to preclude a single failure which might cause undesired mechanical motion of one or both of the OPERABLE SDCS Relief Valve isolation valve(s) in a single isolation valve pair and result in loss of system function.

This power-lock open condition of the OPERABLE SDCS Relief Valve isolation valve pair is consistent with the guidance provided in Branch Technical Position ICSB 18 (PSB), "Application of the Single Failure Criterion to Manually-Controlled Electrically-Operated Valves."

RCS Vent Performance The RCS vent size will be re-evaluated for compliance each time the P/T limit curves are revised based on the results of the vessel material surveillance.

The RCS vent is passive and is not subject to active failure.

(continued)

SAN ONOFRE--UNIT 2 B 3.4-58 Amendment No. 1-27

LTnP System RCS Temperature s PTLR25'&F B 3.4.12.1 I

BASES (continued)

LCO (continued)

This LCO is required to ensure that the LTOP System is OPERABLE. The LTOP System is OPERABLE when the minimum coolant input and pressure relief capabilities are OPERABLE.

Violation of this LCO could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of an operational transient.

To limit the coolant input capability, the LCO requires at most two HPSI pumps capable of injecting into the RCS and the SITS isolated or depressurized to less than the Pressure/Temperature Limits.

LCO 3.5.3, "ECCS -Shutdown,"

defines the pump OPERABILITY requirements.

LCO 3.3.2, "Engineered Safety Feature Activation System (ESFAS)

Instrumentation," defines SI actuation OPERABILITY for the LTOP MODE 4 small break LOCA, as discussed in the previous section.

The elements of the LCO that provide overpressure mitigation through pressure relief are:

a. The Shutdown Cooling System Relief Valve; or

b. The depressurized RCS and an RCS vent.

The SDCS is OPERABLE for LTOP when both trains of isolation valves are open, its lift setpoint is set at 406 +/- 10 psig or less and testing has proven its ability to open at that setpoint. An RCS vent is OPERABLE when open with an area 2 5.6 square inches.

Each of these methods of overpressure prevention is capable of mitigating the limiting LTOP transient.

APPLICABILITY This LCO is applichlp-inMnnFl.4 whpnthp _tpmnPratitrpnf any PCS rnl d 1 pn. i Pc-1 than nr Pnilal to the LTOP enable temperature specified in the PTLR, 256&F rc-

,'-Temper-tu r& Limits, in MODE 5, and in MODE 6 when the reactor vessel head is on.

The pressurizer safety valves provide overpressure protertinn that meets the Reference 1 P/T lpimits above the LTOP enable temperatures specified in the PTLRPrresure/Temj'urature Limits. When the reactor vessel head is off, overpressurization cannot occur.

I (continued)

SAN ONOFRE--UNIT 2 B 3.4-59 Amendment No. 1-2-7

LTnP System RCS Temperature

PTLR256rF B 3.4.12.1 I

BASES (continued)

LCO LCO 3.4.3 provides the operational P/T limits for all MODES.

(continued)

LCO 3.4.10, "Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressurP nrotection during MODES 1, 2, and 3, and MODE 4 ahnve the LTOP enable temperatures specified in the PTLRPressurc/ Temperature Limits.

APPLICABILITY Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event.

The Applicability is modified by a Note stating that SIT isolation or depressurization to less than the Pressure/

Temperature Limits only required when the SIT pressure is greater than or equal to the RCS pressure fnr the pyisting temperature, as allowed by the P/T limit 'in the PTLR-eurves Prvided. in the Preut.,

-/T pr.._

I I This Note permits the SIT discharge valve surveillance performed only under these pressure and temperature conditions.

ACTIONS A.1 With more than two HPSI pumps capable of injecting into the RCS, overpressurization is possible.

The immediate Completion Time to initiate actions to restore restricted coolant input capability to the RCS reflects the importance of maintaining overpressure protection of the RCS.

B.1 When the SIT pressure is greater than or equal to the maximum RCS pre,-Ire for the existing cold leg temperature allowed in the PTLRLressure/Temperature-Limits, an unisolated SIT r~equires isol ation within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(continued)

I I

SAN ONOFRE--UNIT 2 B 3.4-60 Amendment No. 127-

LTnP System RCS Temperature

PTLR256°2 l

B 3.4.12.1 BASES (continued)

ACTIONS B.1 (continued)

By isolating the SIT(s), the RCS is protected against the SIT tanks pressurizing the RCS in excess of the LTOP limits.

The Completion Time is based on operating experience that this activity can be accomplished in this time period and on engineering evaluation indicating that an event requiring LTOP is not likely in the allowed time.

C.1 If the Required Action and associated Completion Time of condition B is not met, the affected SIT(s) must be depressurized to less than the maximum RCS prpscsilre for the existing cold leg temperature allowed in the PTLRPressuref Temperature Limits within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

By d0nrpssurizing the SIT(s) below the LTOP limit stated in the PTLRrreszure/Tmperature Limits the RCS is protected against the SIT(s) pressurizing the RCS in excess of the LTOP limits.

The Completion Time is based on operating experience that this activity can be accomplished in this time period and on engineering evaluation indicating that an event requiring LTOP is not likely in the allowed time.

D.1 and D.2 The 24-hour Allowable Outage Time (AOT) for a single channel SDCS Relief Valve isolation valve(s) increases the availability of the LTOP system to mitigate low temperature overpressure transients especially during MODES 5 and 6 when the potential for these transients are highest (RCS temperatures between 800F and 1900F and the RCS is water-solid).

The 24-hour AOT implements the guidance provided in Generic Letter 90-06 (Ref. 6).

E.1 If the SDCS Relief Valve is inoperable, or if a Required Action and the associated Completion Time of Condition A, (continued)

SAN ONOFRE--UNIT 2 B 3.4-61 Amendment No. 127

LTOP System RCS Temperature

PTLR256°F B 3.4.12.1 BASES (continued)

ACTIONS E.1 (continued)

C, or D are not met, or if the LTOP System is inoperable for any reason other than Condition A, C or D, the RCS must be depressurized and a vent established within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . The vent must be sized at least 5.6 square inches to ensure the flow capacity is greater than that required for the worst case mass input transient reasonable during the applicable MODES.

This action protects the RCPB from a low temperature overpressure event and a possible brittle failure of the reactor vessel.

The Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to depressurize and vent the RCS is based on the time required to place the plant in this condition and the relatively low probability of an overpressure event during this time period due to increased operator awareness of administrative control requirements.

SURVEILLANCE SR 3.4.12.1.1 and SR 3.4.12.1.2 REQUIREMENTS To minimize the potential for a low temperature overpressure event by limiting the mass input capability, not more than two HPSI pumps are verified OPERABLE. The other pump is secured by verifying that its motor circuit breaker is not racked-in, or its discharge valve is locked closed and power is removed.

Additionally, the SIT discharge isolation valves are verified closed and d SrtivatPd InrCTT(s) are depressurized to less than the values in the PTLRP-reej Temperature Limits limit.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval considers operating practice to regularly assess potential degradation and to verify operation within the safety analysis.

SR 3.4.12.1.3 SR 3.4.12.1.3 requires verifying that the RCS vent is open 2 5.6 square inches is proven OPERABLE by verifying its open condition either:

a. Once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for a vent valve that is unlocked open; and (continued)

SAN ONOFRE--UNIT 2 B 3.4-62 Amendment No. +/-447

LTOP System RCS Temperature

PTLR256°F B 3.4.12.1 BASES (continued)

SURVEILLANCE SR 3.4.12.1.3 (continued)

REQU IREMENTS

b. Once every 31 days for a valve that is locked, sealed, or otherwise secured open and once every 31 days for open flanged RCS penetrations.

The passive vent arrangement must only be open to be OPERABLE.

This Surveillance need only be performed if the vent is being used to satisfy the requirements of this LCO.

The Frequencies consider operating experience with mispositioning of unlocked and locked vent valves, respectively.

SR 3.4.12.1.4 and SR 3.4.12.1.5 When one or both SDCS Relief Valve isolation valve(s) in one isolation valve pair becomes inoperable, the other OPERABLE SDCS Relief Valve isolation valve pair is verified in a power-lock open condition every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to preclude a single failure which might cause undesired mechanical motion of one or both of the OPERABLE SDCS Relief Valve isolation valve(s) in a single isolation valve pair and result in loss of system function.

This surveillance requirement, SR 3.4.12.1.4, is modified by two notes. Note 1 requires to perform this SR when the SDCS Relief Valve isolation valve pair is inoperable. Note 2 specifies that the power lock-open requirement is satisfied either with the AC breakers open for valve pair 2HV9337 and 2HV9339 or the regulating transformer output breakers open for valve pair 2HV9377 and 2HV9378, whichever valve pair is OPERABLE.

When both pairs of SDCS Relief Valve isolation valves are OPERABLE and the SDCS Relief Valve is used for overpressure protection, the isolation valves are verified open every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

SR 3.4.12.1.6 The SDCS Relief Valve Setpoint is verified periodically in accordance with the Inservice Testing Program.

(continued)

SAN ONOFRE--UNIT 2 B 3.4-63 Amendment No. 127 01/25/99

LTnP System RCS Temperature

PTLR256°F B 3.4.12.1 I

BASES (continued)

REFERENCES

1.

10 CFR 50, Appendix G.

2.

Generic Letter 88-11.

3.

UFSAR, Section 15.

4.

10 CFR 50.46.

5.

10 CFR 50, Appendix K.

6. Generic Letter 90-06.

SAN ONOFRE--UNIT 2 B 3.4-64 Amendment No. 1472

RCS Temperature LTnP System

> PTLR256°F B 3.4.12.2 I

B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.12.2 Low Temperature OvprnrpqqilrP Protection (LTOP) System RCS Temperature > PTLR Limit256°F I

BASES BACKGROUND The LTOP System controls RCS pressure at low temperatures so the integrity of the reactor coolant pressure boundary (RCPB) is not compromised by violating the pressure and temperature (P/T) limits of 10 CFR 50, Appendix G (Ref. 1).

The reactor vessel is the limiting RCPB component for demonstrating such protection.

LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," provides the allowable combinations for operational pressure and temperature during cooldown, shutdown, and heatup to keep from violating the Reference 1 requirements during the LTOP MODES.

The reactor vessel material is less tough at low temperatures than at normal operating temperatures. As the vessel neutron exposure accumulates, the material toughness decreases and becomes less resistant to pressure stress at low temperatures (Ref. 2).

RCS pressure, therefore, is maintained low at low temperatures and is increased only as temperature is increased.

The potential for vessel overpressurization is most acute when the RCS is water solid, occurring only during shutdown; a pressure fluctuation can occur more quickly than an operator can react to relieve the condition.

Exceeding the RCS P/T limits by a significant amount could cause brittle cracking of the reactor vessel.

LCO 3.4.3 requires administrative control of RCS pressure and temperature during heatup and cooldown to prevent exceeding the P/T limits.

In MODE 4 when the temperature of any RCS cold leg is greater than the enable temperatures specified in the PTLR rrIssuIe/Temperature Limits the LCO does not require the makeup control system deactivated or the safety injection (SI) actuation circuits blocked.

The LTOP System consists of the Shutdown Cooling System Relief Valve with both pairs of SDCS Relief Valve isolation valves open, or a minimum of one pressurizer code safety valve OPERABLE.

(continued)

I SAN ONOFRE--UNIT 2 B 3.4-65 Amendment No. +2-T

RCS Temperature LTOP System

> PTLR256°F B 3.4.12.2 I

BASES (continued)

BACKGROUND (continued)

Shutdown Cooling System Relief Valve Requirements The Shutdown Cooling System relief valve has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 1000F above the RCS cold leg temperatures.

Pressurizer Code Safety Valve Requirements The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psia.

Each safety valve is designed to relieve 4.6 x 105 lbs per hour of saturated steam at the valve setpoint plus 3% accumulation.

The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with RCS cold len temperature greater than that specified in the PTLR.

rre Surel/Tempraturc Limits I

APPLICABLE SAFETY ANALYSES Safety analyses (Ref. 3) demonstrate that the reactor vessel is adequately protected against exceeding the Reference 1 P/T limits during shutdown. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown with RCS oinld leg temperature greater than that specified in the PTLR.

Pressure/Temperature Limits In the event that no safety valves are OPERABLE and for RCS cold len temperature less than or equal to that specified in the PTLR Prrssure/Temperature Limit, the operating shutdown cooling relief valve, connected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

When the RCS is depressurized, an RCS vent to atmosphere sized 5.6 inches or greater may be used as an alternative to the SDCS Relief Valve.

I The actual temperature at which the pressure in the P/T limit curve falls below the pressurizer safety valve setpoint increases as the reactor vessel material toughness decreases due to neutron embrittlement.

Each time the P/T limit curves are revised, the LTOP System will be re-evaluated to ensure its functional requirements can still (continued)

SAN ONOFRE--UNIT 2 B 3.4-66 Amendment No. 1-27~

LTnP System RCS Temperature > PTLR2*56°F B 3.4.12.2 BASES (continued)

APPLICABLE be satisfied using the relief valve method or the SAFETY ANALYSES depressurized and vented RCS condition.

(continued)

Reference 3 contains the acceptance limits that satisfy the LTOP requirements. Any change to the RCS must be evaluated against these analyses to determine the impact of the change on the LTOP acceptance limits.

Shutdown Cooling System Relief Valve Performance One SDCS Relief Valve isolation valve pair is capable of mitigating an LTOP event that is bounded by the limiting SDCS pressure transients. When one or both SDCS Relief Valve isolation valve(s) in one isolation valve pair becomes INOPERABLE, the other OPERABLE SDCS Relief Valve isolation valve pair is placed in a power-lock open condition to preclude a single failure which might cause undesired mechanical motion of one or both of the OPERABLE SDCS Relief Valve isolation valve(s) in a single isolation valve pair and result in loss of system function. This power-lock open condition of the OPERABLE SDCS Relief Valve isolation valve pair is consistent with the guidance provided in Branch Technical Position ICSB 18 (PSB), "Application of the Single Failure Criterion to Manually-Controlled Electrically-Operated Valves."

LCO This LCO is required to ensure that the LTOP System is OPERABLE.

The LTOP System is OPERABLE when the minimum pressure relief capabilities are OPERABLE.

Violation of this LCO could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of an operational transient.

The elements of the LCO that provide overpressure mitigation through pressure relief are:

a.

The Shutdown Cooling System Relief Valve; or

b. A minimum of one pressurizer code safety valve.

The SDCS is OPERABLE for LTOP when both trains of isolation valves are open, its lift setpoint is set at 406 +/- 10 psig or less and testing has proven its ability to open at that setpoint. A pressurizer code safety valve is OPERABLE when (continued)

SAN ONOFRE--UNIT 2 B 3.4-67 Amendment No. 127T

LTOP System RCS Temperature > PTLR256-F B 3.4.12.2 I

BASES (continued)

LCO (continued) its lift setting is 2500 psia +/- 1% and testing has proven its ability to open at that setpoint.

Each of these methods of overpressure prevention is capable of mitigating the limiting LTOP transient.

APPLICABILITY This LCO is applicable in MODE 4 when the temperature of all RCS rnld legs are above the enable temperatures specified in the PTLRMressure'Temperature Limits.

When the temperature of any RCS cold leg is equal tn nr below the enable temperatures specified in the PTLRressure/Thmperature i-mits the Shutdown Cooling System Relief valve is used for overpressure protection or if the RCS is also depressurized, then an RCS vent to atmosphere sized 5.6 inches or greater can be used for overpressure protection. When the reactor vessel head is off, overpressurization cannot occur.

I LCO 3.4.3 provides the operational P/T limits for all MODES.

LCO 3.4.10, "Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3.

Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event.

ACTIONS A.1 With no pressurizer code safety valves OPERABLE and the SDCS Relief Valve INOPERABLE overpressurization is possible.

The 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Completion Time to be in MODE 5 and vented through a greater than or equal to 5.6 inch vent reflects the importance of maintaining overpressure protection of the RCS.

B.1 and B.2 The 24-hour Allowable Outage Time (AOT) for a single channel SDCS Relief Valve isolation valve(s) increases the (continued)

SAN ONOFRE--UNIT 2 B 3.4-68 Amendment No. +FW

RCS Temperature LTnP System

> PTLR256°F B 3.4.12.2 I

BASES (continued)

ACTIONS B.1 and B.2 (continued) availability of the LTOP system to mitigate low temperature overpressure transients during MODE 4.

The 24-hour AOT implements the guidance provided in Generic Letter 90-06.

SURVEILLANCE SR 3.4.12.2.1 REQUIREMENTS When the SDCS Relief Valve is being used for overpressure protection, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months both pairs of SDCS Relief Valve isolation valves are verified open to preclude a single failure condition that might occur if only one pair of isolation valves are open.

SR 3.4.12.2.2 The SDCS Relief Valve Setpoint is verified periodically in accordance with the Inservice Testing Program.

REFERENCES

1.

10 CFR 50, Appendix G.

2.

Generic Letter 88-11.

3. UFSAR, Section 15.

4.

10 CFR 50.46.

5.

10 CFR 50, Appendix K.

6. Generic Letter 90-06.

SAN ONOFRE--UNIT 2 B 3.4-69 Amendment No. 1,7

ML050320294

Contents

Text

Subject:

Dear Sir or Madam:

1.0 INTRODUCTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

3.4.3 APPLICABILITY

3.4.3 APPLICABILITY

_/, I 1

3.4.3 APPLICABILITY

3.4.3 APPLICABILITY

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ML050320294

Text

Subject:

Dear Sir or Madam:

1.0 INTRODUCTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

6.0 ENVIRONMENTAL CONSIDERATION

7.0 REFERENCES

3.4.3 APPLICABILITY

3.4.3 APPLICABILITY

_/, I 1

3.4.3 APPLICABILITY

3.4.3 APPLICABILITY

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