ML13309A107

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Amend 143 to License DPR-13,incorporating Tech Spec Changes That Reflect Mod to Safeguards Load Sequencer Sys
ML13309A107
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 02/28/1991
From: Dyer J
Office of Nuclear Reactor Regulation
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ML13309A106 List:
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DPR-13-A-143 NUDOCS 9103040342
Download: ML13309A107 (21)
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UNITED STATES

?

0 NUCLEAR REGULATORY COMMISSION X

(WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 143 License No. DPR-13

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensee) dated September 28, 1990, with supplements dated January 14, 30, and 31, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, Provisional Operating License No. DPR-13 is amended by changes to the Technical Specifications as indicated in the attachment to this amendment, further, by revising paragraph 3.B. and by adding paragraph 3.N to read as follows:

9103040342 910228 PDR ADOCK 0o00206 P

PDR

-2 B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 143, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.

N. Plant Modification to Eliminate Single Failure Susceptibility of Vital Bus Automatic Transfer Function Southern California Edison Company shall modify the electrical distribution system to ensure that the availability of a power source for vital buses 1, 2, 3, and 3A is not subject to a single failure susceptibility. The plant modification shall satisfy the design requirements of the safety-related portions of the existing electrical distribution system and shall be operable prior to restart from the Cycle 12 refueling outage.

3. This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION James E. Dyer, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 28, 1991

ATTACHMENT TO LICENSE AMENDMENT NO. 143 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 1

i ii i

iiiii xi xi xii xii xiii xiii xiv xiv xv xv 3.5-1 3.5-1 3.5-3 3.5-3 3.5-3a 3.5-5b 3.5-5b 3.5-5c 3.7-5 3.7-5 3.7-6 3.7-6 4.1-la 4.1-2 4.1-2 4.4-4 4.4-4

APPENDIX A TECHNICAL SPECIFICATIONS LIST OF EFFECTIVE PAGES Page Amendment No.

Page Amendment No.

Page Amendment No.

i 3.0-1 43, 56, 64, 83 3.3-3 25, 38, 86, 124, 11 130 130, 142 111 3.0-2 56, 64, 83, 130, 3.3-4 25, 37, 124, 130 iv T31 135 3.3-5 25, 130 v

90, 130, 131 3.0-3 135 3.3-6 25, 102, 120, 130 vi 90, 130, 131 3.0-4 135 3.3-7 25, 102, 130 vii 90, 102, 130, 131 3.1-1 29, 38, 70, 83, 3.3-8 25, 38, 122, 130 viii 90, 130 91, 96, 130 3.3-9 25, 38, 122, 130 ix 90, 91, 102, 130 3.1-2 29, 83, 96, 130 3.3-10 25, 130 131 3.1-3 43, 77, 103, 130 3.3-11 NRC Order x

90, 91, 130, 131 3.1-4 77, 130 4/20/81, 130 xi 55, 92, 102, 110, 3.1-5 77, 125, 130 3.3-12 NRC Order 111, 130, 131, 3.1-6 77, 102, 130 4/20/81, 130 xii 56, 58, 71, 79, 3.1-7 77, 102, 103, 130 3.4-1 29, 82, 125, 130 83, 104, 117, 130, 3.1-8 43, 102, 103, 130 3.4-2 29, 130

131, 3.1-9 77, 102, 130 3.4-3 82, 125, 130 xiii 31, 5E, 58, 79, 3.1-10 Change No. 14, 38, 3.4-4 82, 125, 130, 138 83, 84, 91, 117, 102, 130 3.5-1 83, 117, 130, 130, 131, 3.1-11 Change No. 14, 38, 3.5-2 43, 56, 58, 83, xiv
131, 102, 130 117, 128, 130 xv 3.1-12 Change No. 14, 92, 3.5-3 43, 56, 58, 83, 1.0-1 31, 56, 59, 83, 130 117, 121, 122, 130, 117, 130 3.1-13 Change No. 14, 92, 1.0-2 31, 56, 59, 83, 130 3.5-4 3?, 58, 83, 117, 104, 117, 130 3.1-14 Change No. 14, 118, 121, 128, 130 1.0-3 31, 56, 59, 79, 102, 130 3.5-5 83, 117, 130 83, 104, 117, 130 3.1-15 Change No. 14, 3.5-5a 1.0-4 31, 56, 59, 79, 102, 130 3.5-5b 83, 117, 130 3.1-16 Change No. 14, 3.5-5c 1.0-5 77, 79, 83, 117, 102, 130 3.5-6 7,11, 25, 35, 55, 130 3.1-17 Change No. 14, 56, 111, 130 1.0-6 79, 83, 96, 117, 102, 130 3.5-7 7, 11, 25, 35, 49, 130 3.1-18 Change No. 7, 37, 55, 56, 111, 122, 1.0-7 58, 83, 117, 130 55, 91, 119, 130 130 1.0-8 56, 83, 117, 130 3.1-19 Change No. 7, 55, 3.5-8 11, 49, 111, 122, 2.1-1 43, 55, 97, 117, 119, 130 130 130 3.1-20 37, 55, 119, 130 3.5-9 11, 25, 56, 111, 2.1-2 43, 97, 117, 121, 3.1-21 58, 59, 83, 130 130 130 3.1-22 58, 130 3.5-10 56, 130 2.1-3 43, 117, 121, 122, 3.1-23 83, 130 3.5-11 56, 130 130 3.2-1 102, 130 3.5-12 56, 130 2.1-4 43, 117, 121, 122, 3.2-2 25, 102, 130 3.5-13 56, 130 130 3.3-1 25, 37, 86, 124 2.1-5 43, 97, 117, 121, 130 122, 130 3.3-2 25, 130 2.1-6 55, 130 SAN ONOFRE -

UNIT 1 i

AMENDMENT NO. 143

LIST OF EFFECTIVE PAGES (Cont.)

Page Amendment No.

Page Amendment No.

Page Amendment No.

3.5-14 56, 130 3.8-1 25, 36, 37, 3.14-26 130, 131 3.5-15 58, 83, 130 73, 77, 130 3.15-1 79, 130 3.5-16 58, 83, 130 3.8-2 36, 77, 130 3.15-2 79, 90, 91, 3.5-17 58, 83, 130 3.8-3 25, 36, 73, 105, 130 3.5-18 58, 72, 130 77, 130 3.15-3 79, 90, 91, 3.5-19 58, 83, 125, 130 3.8-4 36, 73, 77, 130 105, 130 3.5-20 125, 130 3.8-5 36, 73, 77, 130 3.16-1 79, 130 3.5-21 58, 83, 117, 124, 3.9-1 3, 10, 112, 130 3.16-2 79, 90, 91, 125, 130 3.9-2 3, 10, 112, 130 105, 130 3.5-22 64, 82, 125, 130 3.10-1 7, 8, 112, 122, 3.16-3 79, 90, 91, 3.5-23 58, 82, 125, 130 130 105, 130 3.5-24 58, 82, 125, 130 3.10-2 7, 112, 122, 130 3.16-4 79, 90, 91, 3.5-25 58, 82, 125, 129, 3.11-1 7, 8, 11, 35, 105, 130 130 55, 112, 117, 3.16-5 79, 130 3.5-26 79, 90, 105, 130 122, 130 3.16-6 79, 90, 130 3.5-27 79, 90, 130 3.11-2 7, 11, 112, 3.16-7 79, 90, 130 3.5-28 79, 130 117, 122, 130 3.17-1 79, 90, 91, 3.5-29 79, 90, 105, 130 3.12-1 14, 130 105, 130 3.5-30 79, 90, 130 3.13-1 21, 63, 81, 130 3.17-2 79, 90, 130 3.5-31 79, 90, 130 3.13-2 21, 63, 81, 130 3.18-1 79, 91, 105, 130 3.5-32 83, 130 3.14-1 31, 44, 93, 130, 3.18-2 79, 90, 130 3.5-33 83, 130 131 3.18-3 79, 130 3.5-34 83, 91, 130 3.14-2 31, 130, 131 3.18-4 79, 130 3.6-1 25, 56, 58, 3.14-3 31, 130, 131 3.18-5 79, 130 73, 130 3.14-4 31, 93, 130, 131 3.18-6 79, 130 3.6-2 Change No. 7, 3.14-5 31, 130, 131 3.18-7 79, 91, 105, 130 56, 130 3.14-6 130, 131, 134 3.18-8 79, 90, 130 3.6-3 58, 99, 130 3.14-7 130, 131 3.18-9 79, 90, 105, 130 3.6-4 58, 71, 99, 130 3.14-8 130, 131 3.19-1 79, 90, 105, 130 3.6-5 58, 59, 71, 3.14-9 130, 131 3.20-1 102, 130 99, 130 3.14-10 130, 131 3.20-2 102, 130 3.6-6 58, 59, 83, 130 3.14-11 31, 93, 130, 131 4.0-1 83, 130, 135, 137 3.7-1 25, 52, 68, 3.14-12 31, 130, 131 4.0-2 83, 130, 135, 137 84, 130, 134, 136 3.14-13 31, 130, 131 4.0-3 135 3.7-2 25, 84, 106, 130, 3.14-14 31, 130, 131 4.0-4 135 134, 136 3.14-15 31, 93, 130, 131 4.1-1 29, 56, 83, 3.7-3 25, 84, 130, 134, 3.14-16 31, 130, 131 117, 130 136 3.14-17 31, 130, 131, 134 4.1-la 3.7-4 25, 52, 68, 84, 3.14-18 31, 130, 131 4.1-2 7,22, 83, 117, 106, 130, 134, 136 3.14-19 130, 131 122, 130, 3.7-5 25, 52, 68, 84, 3.14-20 130, 131 4.1-3 117, 130 106, 120, 130, 134, 3.14-21 130, 131 4.1-4 25, 29, 70, 136, _

3.14-22 130, 131 96, 117, 130 3.7-6 134, 136, 3.14-23 130, 131 4.1-5 25, 29, 70, 3.7-7 134, 136 3.14-24 130, 131 96, 130 3.7-8 136 3.14-25 130, 131 4.1-6 25, 29, 56, 70, 100, 122, 130, 134 SAN ONOFRE -

UNIT 1 ii AMENDMENT NO.

143

LIST OF EFFECTIVE PAGES (Cont.)

Page Amendment No.

Page Amendment No.

Page Amendment No.

4.1-7 25, 29, 36, 4.3-3 24, 58, 87, 118, 4.10-1 13, 94, 130 77, 103, 130, 142 130 4.10-2 13, 94, 130 4.1-8 77, 125, 130 4.3-4 24, 87, 130 4.11-1 14, 109, 130 4.1-9 77, 122, 125, 130 4.3-5 24, 75, 87, 130 4.11-2 14, 109, 130 4.1-10 117, 130 4.3-6 75, 87, 130 4.12-1 91, 130 4.1-11 25, 130 4.3-7 58, 130 4.13-1 18, 113, 4.1-12 Change No. 5, 25, 4.3-8 58, 59, 83, 130 130 130 4.3-9 58, 83, 130 4.14-1 21, 33, 63, 81, 4.1-13 79, 130 4.4-1 Change No. 12, 25, 130 4.1-14 79, 90, 130 56, 82, 84, 95, 4.14-2 21, 63, 81, 130 4.1-15 79, 130 104, 123, 130, 136 4.14-3 21, 63, 81, 130 4.1-16 79, 130 4.4-2 25, 84, 130, 136 4.14-4 21, 63, 81, 105, 4.1-17 79, 90, 130 4.4-3 25, 56, 82, 84, 130 4.1-18 79, 130 117, 130, 134, 136 4.15-1 31, 37, 38, 44, 4.1-19 58, 130 4.4-4 25, 82, 84, 95, 130, 131 4.1-20 58, 130 104, 123, 124, 130, 4.15-2 31, 44, 130, 131 4.1-21 58, 130 134, 136, 4.15-3 31, 130, 131 4.1-22 58, 83, 130 4.4-5 84, 130, 136 4.15-4 130, 131 4.1-23 58, 83, 117, 125, 4.4-6 25, 56, 84, 104, 4.15-5 130, 131 130 123, 130, 136 4.15-6 31, 130, 131 4.1-24 58, 109, 130 4.4-7 25, 56, 84, 130, 4.15-7 31, 130, 131 4.1-25 58, 130 134, 136 4.15-8 130, 131 4.1-26 58, 82, 125, 130 4.4-8 136 4.15-9 130, 131 4.1-27 58, 82, 125, 130 4.4-9 136 4.15-10 130, 131 4.1-28 65, 82, 125, 130 4.4-10 136 4.15-11 130, 131 4.1-29 65, 125, 130 4.5-1 Change No. 10, 38, 4.15-12 130, 131 4.1-30 82, 130 79, 130 4.16-1 31, 101, 115, 130, 4.1-31 83, 130 4.5-2 79, 90, 130 133 4.1-32 83, 130 4.5-3 79, 130 4.16-2 37, 101, 115, 130, 4.1-33 83, 130 4.5-4 79, 130 133 4.1-34 119, 130 4.5-5 79, 130 4.16-3 37, 101, 115, 130, 4.1-35 119, 130 4.5-6 79, 130 133 4.2-1 25, 37, 54, 114, 4.6-1 38, 79, 130 4.16-4 37, 55, 101, 115, 130 4.6-2 79, 90, 130 130, 133 4.2-2 25, 37, 114, 130 4.6-3 79, 130 4.16-5 37, 91, 101, 105, 4.2-3 25, 37, 114, 130 4.6-4 79, 130 115, 130, 133 4.2-4 25, 37, 114, 124, 4.6-5 79, 130 4.17-1 79, 130 130 4.6-6 79, 130 4.18-1 79, 130 4.2-5 25, 37, 114, 124, 4.6-7 79, 130 4.18-2 79, 130 130 4.6-8 79, 130 4.18-3 79, 130 4.2-6 37, 114, 130 4.6-9 79, 130 4.18-4 79, 130 4.2-7 NRC Order 4.7-1 Change No. 14, 46, 4.18-5 79, 130 4/20/81, 54, 130 130 4.18-6 79, 130 4.3-1 24, 58, 75, 130 4.8-1 91, 130 4.19-1 79, 105, 130 4.3-2 5, 24, 58, 75, 87, 4.9-1 Change No. 14, 130 118, 130 4.9-2 130 SAN ONOFRE - UNIT 1 iii AMENDMENT NO.

143

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS FIGURES FIGURES TITLE PAGE 2.1.1 Safety Limits Pressure, Temperature, 2.1-6 Power 100% Nominal Flow 3.1.3a San Onofre Unit 1 Reactor Coolant System 3.1-12 Heatup Limitations Applicable for the First 16 EPPY 3.1.3b San Onofre Unit 1 Reactor Coolant System 3.1-13 Cooldown Limitations Applicable for the First 16 EPPY 3.1.3c Effect of Fluence and Copper Content on 3.1-14 Shift of RTNDT for Reactor Vessel Steels Exposed to 5500 F Temperature 3.1.3d Fast Neutron Fluence (E>1 MEV) as a 3.1-15 Function of Full Power Service Life 3.5.1-1 4 kV Buses 1C and 2C Under-voltage Trip Setting 3.5-5c 3.5.2.1 Control Group Insertion Limits 3.5-9 5.1.1 Exclusion Area 5.1.-2 6.2-1

[Figure Deleted]

6.2-2

[Figure Deleted]

SAN ONOFRE-UNIT 1 xi AMENDMENT N 143

00 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS TABLES TABLES TITLE PAGE 1.1 Frequency Notation 1.0-7 1.2 Operational Modes 1.0-8 2.1 Maximum Safety Systems Settings 2.1-5 3.1.3.1 San Onofre Nuclear Generating Station Unit 1 3.1-16 Reactor Vessel Toughness Data (unirradiated) 3.3.5-1 Primary Coolant System Pressure Isolation Valves 3.3-12 3.5.1-1 Reactor Trip System Instrumentation 3.5-2 3.5.1-2 Reactor Trip System Instrumentation Trip Setpoints 3.5-5a 3.5.1-3 Reactor Trip System Instrumentation Response Times 3.5-5b 3.5.3-1 Accident Analyses Requiring Reevaluation in 3.5-12 the Event of an Inoperable Rod 3.5.5-1 Containment Isolation Instrumentation 3.5-16 3.5.5-2 Containment Isolation Instrumentation Trip 3.5-18 Set Points 3.5.6-1 Accident Monitoring Instrumentation 3.5-21 3.5.7-1 Auxiliary Feedwater Instrumentation 3.5-23 3.5.7-2 Auxiliary Feedwater Instrumentation Trip 3.5-25 Set Points 3.5.8.1 Radioactive Liquid Effluent Monitoring 3.5-27 Instrumentation 3.5.9.1 Radioactive Gaseous Effluent Monitoring 3.5-30 Instrumentation 3.5.10-1 Radiation Monitoring Instrumentation 3.5-33 3.6.2-1 Power Operated or Automatic Containment Isolation 3.6-5 Valve Summary 3.14.2-1 Required Sprinkler and Spray Systems 3.14-6 3.14.5.1 Fire Hose Stations 3.14-13 SAN ONOFRE-UNIT 1 xii AMENDMENT NO. W1/5$1/71/

143 791/M3/1941 777T1/759/751

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS TABLES TABLES TITLE PAGE 3.14.6.1 Fire Detection Instruments 3.14-17 3.14.8.1 DSD and Alternate Shutdown Minimum Operable Equipment 3.14-24 3.18.1 Radiological Environmental Monitoring Program 3.18-3 3.18.2 Reporting Levels For Radioactivity Concentration 3.18-6 in Environmental Samples 4.1.1 Reactor Trip System Instrumentation Surveillance 4.1-2 Requirements 4.1.2 Minimum Equipment Check and Sampling 4.1-4 4.1.3 Minimum Frequencies for Testing, Calibrating, 4.1-10 and/or Checking of Instrument Channels 4.1.2.1 Radioactive Liquid Effluent Monitoring 4.1-14 Instrumentation Surveillance Requirements 4.1.3.1 Radioactive Gaseous Effluent Monitoring 4.1-17 Instrumentation Surveillance Requirements 4.1.4-1 Containment Isolation Instrumentation 4.1-20 Surveillance Requirements 4.1.5-1 Accident Monitoring Instrumentation 4.1-23 Surveillance Requirements 4.1.8-1 Auxiliary Feedwater Instrumentation 4.1-27 Surveillance Requirements 4.1.11.1 Radiation Monitoring Instrumentation 4.1-32 Surveillance Requirements 4.1.13-1 Leakage Detection Systems 4.1-35 4.4-1 Battery Surveillance Requirements 4.4-5 4.5.1.1 Radioactive Liquid Waste Sampling 4.5-2 and Analysis Program 4.6.1.1 Radioactive Gaseous Waste Sampling 4.6-2 an Analysis Program SAN ONOFRE-UNIT 1 xiii AMENDMENT NO: ?////7//7' 143 7 il3 / /93

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS TABLES TABLES TITLE PAGE 4.18.1 Maximum Values for the Lower Limits of 4.18-2 Detection (LLD) 6.2-1 Minimum Shift Crew Composition 6.2-4 SAN ONOFRE-UNIT 1 xiv AMENDMENT NO: 143

APPENDIX A As required by Section 3, Paragraph B, of Provisional Operating License DPR-13, any changes made to the San Onofre Nuclear Generating Station, Unit 1 Technical Specifications will be authorized by the Nuclear Regulatory Commission.

All changes to these Technical Specifications are indicated by a vertical line in the right-hand margin. The length of the line shows the extent of the changed material.

The amendment numbers assigned by the NRC appear in the lower right-hand corner of the page. In general, the highest amendment number is associated with the change bars on each page.

SAN ONOFRE-UNIT 1 xv AMENDMENT NO:

143

3.5 INSTRUMENTATION AND CONTROL 3.5.1 REACTOR TRIP SYSTEM INSTRUMENTATION APPLICABILITY:

As shown in Table 3.5.1-1.

OBJECTIVE:

To delineate the conditions of the Plant instrumentation and safety circuits necessary to ensure reactor safety.

SPECIFICATION:

As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.5.1-1 shall be OPERABLE with the SETPOINTS and RESPONSE TIMES as shown in Tables 3.5.1-2 and 3.5.1-3, respectively.

ACTION:

As shown in Table 3.5.1-1.

BASIS:

During plant operations, the complete instrumentation systems will normally be in service. (1) Reactor safety is provided by the Reactor Protection System, which automatically initiates appropriate action to prevent exceeding established limits. (2)

Safety is not compromised, however, by continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design. (1)(3) This Standard outlines limiting conditions for operation necessary to preserve the effectiveness of the reactor control and protection system when any one or more of the channels is out of service.

REFERENCES:

(1) Final Engineering Report and Safety Analysis, Section 6.

(2) Final Engineering Report and Safety Analysis, Section 6.2 (3) NIS Safety Review Report, April 1988 SAN ONOFRE UNIT 1 3.5-1 AMENDMENT NO:

8, 117, 130

TABLE 3.5.1-1 (Continued) o REACTOR TRIP SYSTEM INSTRUMENTATION

-n MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTION UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

10.

Reactor Coolant Flow A. Single Loop 1/loop 1/loop in any 1/loop in each 1

6#

(Above 50% of Full Power) operating loop operating loop B. Two Loops 1/loop I/loop in two 1/loop in each 1####

6#

(Below 50% of Full Power) operating loops operating loop

11.

Steam/Feedwater Flow Mismatch 3

2 2

1#####

6#

12.

Turbine Trip-Low Fluid Oil Pressure 3

2 2

1####

6#

13.

Reactor Coolant Pump Breaker Position A. Single Loop 1/loop 1/loop in any 1/loop in each 1

6#

(Above 50% of Full Power) operating loop operating loop B. Two Loops 1/loop I/loop in two 1/loop in each 1####

6#

(Below 50% of Full Power) operating loops operating loop a

14.

4kV Bus 1C and Bus 2C 2/bus 1/bus from 1/bus from 1,2,3*,4*

1#

Undervoltage both buses both buses

TABLE 3.5.1-2 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

1. 4 kV Bus IC and 2C See Figure 3.5.1-1 See Figure 3.5.1-1 Undervoltage SAN ONOFRE UNIT 1 3.5-5a AMENDMENT NO:

143

TABLE 3.5.1-3 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME

1. 4 kV Bus 1C and 2C See Figure 3.5.1-1 Undervoltage SAN ONOFRE UNIT 1 3.5-5b AMENDMENT NO: 143

FIGURE 3.5.1-1 4 KV BUSES 1C & 2C UNDER-VOLTAGE TRIP SETTING LOSS OF BUS VOLTAGE ( CV-7) 11 1 0 0 12870 VOLTS (See note 3

~10 0

2400 VOLTS 3.1 SECONDS 4160 VOLTS-TO 0 VOLT 1.0 SECOND 1'

1600 2000 2400 2800 3200 3600 BUS VOLTAGE Notes: 1. Trip voltage tolerance: +/- 3 %

2. Trip time tolerance: +/- 10 %
3. Range for accurate relay operation: < 90 % of the tap voltage SAN ONOFRE - UNIT 1 3.5 - 5c AMENDMENT NO: 143

When one diesel generator is inoperable, there is an additional ACTION requirement to verify that all required systems, sub systems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE. In addition, the ACTION STATEMENT requires a verification that the steam-driven auxiliary feed water pump is OPERABLE in MODES 1, 2, and 3.

These requirements are intended to provide assurance that a loss of offsite power event will not result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable. The term verify as used in this context means to administratively check by examining logs or other information to determine if certain components are out-of-service for maintenance or other reasons. It does not mean to perform the surveillance requirements needed to demon strate the operability of the component. The Safeguards Load Sequencing System is designed so that each sequencer starts and loads its associated diesel generator and sequences the ECCS loads upon receipt of a safety injection signal (SIS) and concurrent loss of voltage on its respective 4160 volt bus (i.e., upon a SISLOP).

The total connected design load on each diesel generator is restricted to 6,000 kW or less. This requirement was the result of a crankshaft crack propagation analysis (see Reference 1).

The analysis postulated that the crankshaft initially has stress-induced surface cracks. The analysis then considered the effect of four types of diesel load histories on the growth of these cracks. Each load history consisted of repeated start stop cycles with some steady state operation at full load (6,000 kW) between each start and its stop. The analysis concluded that for a crankshaft with a detectable size crack (10 mils deep), the number of start-stop cycles required to enlarge the crack until it becomes self-propagating (18 mils deep) under the full load steady state stresses represents the effective life of the crankshaft.

During normal operations, the 480 volt system is considered OPERABLE if the four 480 volt buses and four station service transformers are OPERABLE with respective tie breakers open.

This will ensure that the 480V main breakers and transformers remain OPERABLE during the worst loading condition in case of a SIS without LOP.

The primary power source for Vital Buses 1, 2, 3, 3A, and 4 is Train A DC Bus 1. The alternate power source is available from MCC-2 through MTS-7. The 1987 RPS and ESF single failure analyses credited the Train B backup power to these vital buses through MTS-7.

Correct operation of the safety injection system is assured by the operability of the load sequencers and the UPS for MOV-850C SAN ONOFRE - UNIT 1 3.7-5 AMENDMENT NO.

36/143

and MOV-358 (MOV-850C UPS). Correct operation of the recircu lation system is assured by the operability of the MOV-850C UPS which also supplies MOV-358.

Manual Transfer Switch 8 (MTS-8) provides the means to power MOV-883 and the MOV-850C UPS from either Train A or Train B.

However, due to single failure considerations and environmental effects, MTS-8 is normally powered from MCC-4 on Train B.

MOV-883 is the discharge valve from the RWST and must remain open during the safety injection phase and close with initiation of recirculation.

REFERENCE:

(1) Report No FaAA-84-12-14 (Revision 1.0), Evaluation of Trans ient Conditions on Emergency Diesel Generator Crankshafts at San Onofre Nuclear Generating Station, Unit 1.

SAN ONOFRE -

UNIT 1 3.7-6 AMENDMENT NO. I 1143

I. The reactor trip system response time of each reactor trip function listed in Table 3.5.1-3 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels" column of Table 3.5.1-1.

SAN ONOFRE -

UNIT 1 4.1-la AMENDMENT NO:

143

TABLE 4.1.1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS n

TRIP ACTUATING rn DEVICE CHANNEL CHANNEL CHANNEL OPERATIONAL ACTUATION c

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST

1. Manual Reactor Trip N.A.

N.A.

N.A.

R N.A.

2. Power Range, Neutron Flux S

D (2,3)

M N.A.

N.A.

R (3,4)

3.

Power Range, Neutron Flux, N.A.

N.A.

M N.A.

N.A.

Dropped Rod Stop

4.

Intermediate Range, S

R (3,4)

S/U (1),

N.A.

N.A.

Neutron Flux M

5. Source Range, Neutron Flux S

R (3)

S/U (1),

N.A.

N.A.

M

6.

NIS Coincidentor Logic N.A.

N.A.

N.A.

N.A.

M (5)

7.

Pressurizer Variable Low Pressure S

R M

N.A.

N.A.

8.

Pressurizer Pressure S

R M

N.A.

N.A.

M

9. Pressurizer Level S

R M

N.A.

N.A.

M

10. Reactor Coolant Flow S

R Q

N.A.

N.A.

z

11. Steam/Feedwater Flow Mismatch S

R M

N.A.

N.A.

12. Turbine Trip-Low Fluid Oil Pressure N.A.

N.A.

N.A.

S/U (1,6)

N.A.

P

13. Reactor Coolant Pump Breaker Position*

S R

R N.A.

N.A.

14. 4kV Bus 1C and Bus 2C Voltage N.A.

R R

N.A.

N.A.

  • Applicable to Item 6 in Table 2.1
1.

Simulating SISLOP*, and:

a. Verifying operation of circuitry which locks out non-critical equipment,
b. Verifying the diesel performs a DG FAST START from standby condition on the auto-start signal, energizes the emergency buses with permanently connected loads and the auto connected emergency loads** through the load sequencer (with the exception of the feedwater, safety injection, charging and refueling water pumps whose respective breakers may be racked-out to the test position) and operates for > 5 minutes while its generator is loaded with the emergency loads,
c.

Verifying that on the safety injection actuation signal, all diesel generator trips, except engine overspeed and generator differential, are automatically bypassed.

2. Verifying the generator capability to reject a load of 4,000 kW without tripping. The generator voltage shall not exceed 4,800 volts and the generator speed shall not exceed 500 rpm (nominal speed plus 75% of the difference between nominal speed and the overspeed trip setpoint) during and following the load rejection.

G. Manual Transfer Switches

1. Verify once every 31 days that the fuse block for breaker 8-1181 in MCC-1 for MTS-7 is removed.
2. Verify once every 31 days that MTS-8 is energized from breaker 8-14808 from MCC-4 and the cabinet door is locked, and that breaker 8-1122 from MCC-1 is locked open.
  • SISLOP is the signal generated by a sequencer on coincident loss of voltage on its associated 4160 volt bus (Bus IC or 2C) and demand for safety injection.
  • The sum of all loads on the engine shall not exceed 6,000 kW.

SAN ONOFRE - UNIT 1 4.4-4 AMENDMENT NO:

143

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