ML20246L138

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Amends 74 & 62 to Licenses NPF-10 & NPF-15,respectively, Revising Tech Spec 3/4.8.2.1, DC Sources, to Increase Interval for 18 Month Surveillance Tests to at Least Once Per Refueling Interval
ML20246L138
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/30/1989
From: Knighton G
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20246L143 List:
References
NUDOCS 8907180351
Download: ML20246L138 (16)


Text

{{#Wiki_filter:. _. c ' ' f' UNITED STATES j p, NUCLEAR REGULATORY COMMISSION 5 WASHINGTON, D, C. 20555 E- %,...../ SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-361 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-10 1. The Nuclear Daoulatory Corsssion (the Comission) has found that: A. The application for amendmer.t to the license for San Onofre Nuclear Generat'ng Station, Unit 2 (the facility) filed by Southern California Edison Company (SCE) on behalf of itself and San D' ego Gas and Electric Company, the City of Riverside, Californ:aand.theCityofAnaheim, California (licensees) ' dated December 29, 1988, complies with the standards and req)uire-ments of the Atomic Energy Act of 1954, as amended (the Act, and the Comission'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 regulations of the Comission; 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 activitics will be condu:ted in compliance with the Comission's regulations; 'O. 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 Comission's regulatic,ns and all applicable requirements have been satisfied. 8907180351 890630 PDR ADOCK 05000361 P PDC a_

if t... p.... 2. Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this-license amendment, and paragraph-2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows: (2)-TechnicalSpecifications The Technical _ Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 74, are hereby incorporated .in the license. SCE shall operate the facility in accordance with the. Technical Specifications and the Environmental-Protection Plan. 3. This license amendment is effective at of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance. FOR THE NUCLEAR REGU TORY COMMISSION Ge rge. Knighton, ' rector Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Attachmci.c: ' Changes to the Technical Specifications Date.of Issuance: June 30, 1989

l '\\,fG. l ATTACHMENT TO LICENSE AMENDMENT N0.74 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 l Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. AMENDMENT PAGE 3/4 8-9 3/4 3-10

. c.. ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum the following D.C. electrical sources shall be OPERABLE: 125-volt battery bank A (28007), and its associated full capacity a. charger. b. 125-volt battery bank B (2B008), and its associated full capacity charger. 125-volt battery bank C (2B009), and its associated full capacity c. charger. d. 125-volt battery bank D (28010), and its associated full capacity charger. APPLICABITY: MODES 1, 2, 3 and 4. ACTION: a. With one of tne required battery banks inoperable, restore the inoperable battery bank to OPERABLE status within 2 hours or be in at.least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. b. With one of the required full capacity chargers inoperable, demonstrate the OPERABILITY of its associated battery bank by performing Surveil-lance Requirement 4.8.2.1.a.1 within one hour, and at least once per 8 hours thereafter. If any Category A limit in Table 4.8-2 is not met, declare the battery inoperable. The provi; ions of Specification 4.0.2 are not applicable. c. l. SURVEILLANCE REQUIREMENT 4.8.2.1 Each 125-volt battery bank and charger shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that: 1. The parameters in Table 4.8-2 meet the Category A limits, and 2. The total battery terminal voltage is greater than or equal to 129 volts on float charge. SAN ONOFRE-UNIT 2 3/4 8-9 AMENDMENT NO. 74

ELECTRICAL POWER SYSTEM SURVEILLANCE RE0VIREMENTS (Continued) b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110-volts, or battery overcharge with battery terminal voltage above 150 volts, by verifying that: 1. The parameters in Table 4.8-2 meet the Category B limits, 2. There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 150 x 10 6 ohms, and 3. The average electrolyte temperature of ten connected cells is above 60 F. At least once per refueling interval

  • by verifying that:

l c. 1. The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, 2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, 3. The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10 6 ohms, and 4. The battery charger will supply at least 300 amperes at 125-volts for at least 12 hours. d. At least once per refueling interval

  • by verifying that the l

battery capacity is adequate to supply and maintain in OPERAB!M status all of the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test. At least once per 60 months, during shutdown, by verifying that the e. battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test required by Surveillance Requirement 4.8.2.1d. f. Annual performance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer s rating.

  • For cycle 4 only, this surveillance interval may exceed the 24 month refueling interval but may not extend more than 60 days beyond the last successful completion of the Specification 4.8.2.1.b surveillance conducted prior to exceeding 24 months..

SAN ON0FRE-UNIT 2 3/4 8-10 AMENDMENT NO.74 l

I u. 24 fg'o [6 UNITED STATES

  • '8 7 NUCLEAR REGULATORY COMMISSION h'

WASHINGTON, D. C. 20555 4 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CALIFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.62 License No. NPF-15 1. The Nuclear Regulatory Comission (the Commission) hrs found that: A. The application for amendment to the license for San Onofre NuclearGeneratingStation, Unit 3(thefacility)filedby Southern California Edison Company (SCE) on. behalf of itself and San Diego Gas and Electric Company, the City of Riverside, California and the City of Anaheim, California (licensees) dated December-29, 1988, complies with the' standards and require-ments 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 o)erate in conformity with the ap)11 cation, the provisions of tie Act, and the regulations of tie Commission; C. There is reasonable assurance (1) 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.

z, n 1. 2.. 2.- Accordingly, the license.is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows: -(2) Technical Specifications The Technical Specifications contained in Appendix A, and- -the Environmental Protection Plan contained-in Appendix B, as revised through Amendment No. 62, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 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 RE LATORY COMMISSION George. Knighto irector. Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance: June 30, 1989

ATTACHMENT TO LICENSE AMENDMENT N0.62 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change. AMENDMENT PAGE 3/4 8-9 3/4 8-10 1

) ' ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum the following D.C. electrical sources shall be OPERABLE: 125-volt battery bank A (38007), and its associated full capacity a. charger. b. 125-volt battery bank B (3B008), and its associated full capacity charger. 125-volt battery bank C (38009) and its associated full capacity-c. charger. d. 125-volt battery bank D (3B010) and its associated full capacity charger. APPLICABILITY: MODES l, 2, 3 and 4. ACTION: With one of the required battery banks inoperable, restore the a. inoperable battery bank to OPERABLE status within 2 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. b. With one of the required full capacity chargers inoperable, demonstrate the OPERABILITY of its associated battery bank by performing Surveil-lance Requirement 4.8.2.1.a.1 within I hour, and at least once per 8 hours thereafter..If any. Category A limit in Table 4.8-2 is not met, declare the battery inoperable. The provisions of Specification 4.0.2 are not applicable. c. SURVEILLANCE REQUIREMENTS 4.8.2.1 Each 125 volt battery bank and charger shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that: 1. The parameters in Table 4.8-2 meet the Category A limits, and 2. The total battery terminal voltage is greater than or equal to 129-volts on float charge. SAN ONOFRE-UNIT 3 3/4 8-9 AMENDMENT NO. 62

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b. At least once per 92 days and within 7 days after a battery discharge with battery terminal voltage below 110-volts, or battery overcharge with battery terminal voltage above 150-volts, by verifying that: ) 1. The parameters in Table 4.8-2 meet the Category B limits, 2. There is no visible corrosion at either terminals or connectors, l or the connection resistance of these items is less than 150 x 10 6 ohms, and j \\ 3. The average electrolyte temperature of ten connected cells is ) above 60 F. At least once per refueling interval

  • by verifying that:

c. 1. The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, 2. The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, 3. The resistance of each cell-to-cell and terminal connection is less than or equal to 150 x 10 6 ohms, and 4. The battery charger will supply at least 300 amperes at 125-volts for at least 12 hours. d. At least once per refueling interval

  • by verifying that the l

battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or simulated emergency loads for the design duty cycle when the battery is subjected to a battery service test. At least once per 60 months, during shutdown, by verifying that the e. battery capacity is at least 80% of the manufacturer's rating when subjected to a performance discharge test. Once per 60 month interval, this performance discharge test may be performed in lieu of the battery service test required by Surveillance Requirement 4.8.2.1d. f. Annual perfo mance discharge tests of battery capacity shall be given to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 10% of rated capacity from its average on previous performance tests, or is below 90% of the manufacturer s rating. i

  • for cycle 4 only, this surveillance interval may exceed the 24 month refueling interval but may not extend more than 60 days beyond the last successful completion of the Specification 4.8.2.1.b surveillance conducted prior to exceeding 24 months.

l SAN ONOFRE-UNIT 3 3/4 8-10 AMENDMENT NO.62

.~ [; y. REVISED 6/30/89 REACTIVITY CONTROL SYSTEMS CE DROP TIME: LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or equal'to 145 inches, shall be less than or equal to 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until the CEA reaches its 90 percent = insertion position with: T,yg greater tha'n or equal'to 520*F, and l a. b. All reactor coolant pumps operating. APPLICABILITY: MODES I and 2. ACTION: With the drop time of'any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within six hours. SURVEILLANCE REQUIREMENTS c,.g. 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality: I' a. For all CEAs following each removal and reinstallation of the reactor vessel head, b. 'For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c. 'At least once per refueling interval. e SAN ON0FRE-UNIT 2 3/4 1-20 AMENDMENT NO. 73 ,5

l REVISED 6/30/89 l 1 I EMERGENCY CORE COOLING SYSTEMS 1 SURVEILLANCE REQUIREMENTS i 1 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE: i a. At least once per 12 hours by verifying that the following valves are in the indicated positions with powe- +o the valve operators removed: Valve Number Valve Function Valve Position a. HV9353 SDC Warmup CLOSED i b. HV9359 SDC Warmup CLOSED c. HV8150 SDC(HX) Isolation CLOSED d. HV8151 SDC(HX) Isolation CLOSED e. HV8152 SDC(HX) Isolation CLOSED f. HV8153 SDC(HX) Isolation CLOSED g. HV0396 SDC Bypass Flow Control CLOSED h. HV8161 SDC(HX) Bypass Flcw OPEN Isolation i. HV9420 Hot Leg Injection CLOSED Isolation j. HV9434 Hot Leg Injection CLOSED Isolation k. HV8160 SDC Bypass Flow Control OPEN 1. HV8162 LPSI Miniflow Isolation OPEN m. HV8163 LPSI Miniflow Isolation OPEN b. At least once per 31 days by: 1. Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2. Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position. c. By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed: 1. For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2. Of the areas affected within containment at the completion of containment entry when CONTAINMENT INTEGRITY is established. d. At least once per refueling interval by: l 1. Verifying automatic isolation of the shutdown cooling system from the Reactor Coolant System when RCS pressure is simulated greater than or equal to 715 psia, and that the interlocks prevent opening the shutdown cooling system isolation valves when simulated RCS pressure is greater than or equal to 376 psia. SAN ONOFRE-UNIT 2 3/4 5-4 AMENDMENT NO. 73 l

I, REVISED 6/30/89 4. NEAUTIVITYCONTROLSYSTEMS .CEA DROP. TIME' y LIMITING CONDITION FOR OPERATION y 3.1.3.4 The' individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or' equal to 145 inches, shall be less I L than or~ equal to 3.2' seconds from when the electrical power is interrupted to L the CEA drive mechanism until the CEA reaches its 90 percent insertion position.- with: a. T greaterfthan or equal to 520 F, and gg b. All reactor coolant pumps operating. APPLICABILITY: MODES 1 and 2. ACTION: With the drop time of any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within six hours. SURVEILLANCE REQUIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality: a. For all CEAs following each removal and reinstallation of the reactor vessel head, b. For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of'those specific CEAs, and c. At least once per refueling interval. SAN ONOFRE-UNIT 2 3/4 1-20 AMENDMENT NO. 73

REVlSED 6/30/89 , CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTION: With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours. SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE: At least once per 6 months by verifying, during a recombiner system a. functional test, that the minimum heater sheath temperature increases to greater than or equal to 700 F within 90 minutes. Upon reaching 700 F, increase the power setting to maximum power for 2 minutes and verify that the power meter reads greater than or equal to 60 kw. b. At least once per refueling interval by: 1. Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits. 2. Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and 3. Verifying the integrity of the heater electrical circuits by i performing a resistance to ground test following the above I required functionai test. The resistance to ground for any J heater phase shall be greater than or equal to 10,000 ohms. i SAN ONOFRE-UNIT 2 3/4 6-27 AMENDMENT N0. 73 1 l

( pm_ _ - _ _ - _ - - _ - -) c REVlSED.6/30/89 L LREACTIVITY CONTRL', TEMS CEA DROP TIME MITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and regulating) CEA drop time, from a withdrawn position greater than or' equal to:145 inches, shall be less than or equal to'3.2 seconds from when the electrical power is interrupted to the CEA drive mechanism until.the CEA reaches its 90 percent insertion position with: 1-a. T greater than or equal to 520 F, and avg i b. All reactor coolant pumps operating. APPLICABILITY: MODES 1 and 2. ACTION: a. With the drop time of'any full length CEA determined to exceed the above limit, be in at least HOT STANDBY within 6 hours. SURVEILLANCE REQUIREMENTS 4l1. 3. 4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality: a. For all CEAs following each removal and reinstallation of the reactor vessel head, b. For specifically affected individuals CEAs following any maintenance - on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c. At least once per refueling interval. SAN ONOFRE-UNIT 3 3/4 1-20 AMENDMENT NO. 61 - __ _ _ --_ _ _- =___ _

9 ( */". ? ~ r,; l REVISED 6/30/89-k l a.. C0'NIA*1NMENTSYSTEMS i . ELECTRIC HYDROGEN RECOMBINERS l LIMITING CONDITION FOR OPERATION' l 3.6.4.2 Two-independent containment hydrogen recombiner systems shall be OPERABLE. I APPLICABILITY: ' MODES 1 and 2. ACTION: With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at-least HOT STANDBY within the next-6 hours. SURVEILLANCE REQUIREMENTS 4.6.4.2 Each hydrogen recombiner system shall be demonstrated OPERABLE: At-least once per 6 months by verifying, during a recombiner system - a. . functional; test, that the minimum heater sheath temperature ' increases t' greater than or equal to 700 F within 90 ininutes. Upon o reaching 700 F, increase'the power setting to maximum power for 2 minutes and verify that.the power meter reads greater than or equal to 60 kw. b. At least once per refueling interval by: 1. Performing a CHANNEL CALIBRATION of all recombiner instrumentation and control circuits. 2. . Verifying.through a visual examination.that there is no evidence of abnormal conditions within the recombiner enclosure (i.e., loose wiring or structural connections, deposits of foreign materials, etc.), and 3. Verifying the integrity of the heater electrical circuits by performing a resistance to ground test following the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to 10,000 ohms. SAN ON0FRE-UNIT 3 3/4 6-28 AMENDMENT NO. 61 1 = _ _ _ _ _ - - -.}}