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| | issue date = 11/20/1978 | | | issue date = 11/20/1978 |
| | title = Forwards Appl for Amend to Facil Operating Lics#DPR-31 & DPR-41.Proposed Amend Addresses Overpressure Mitigating Sys (Oms).Discusses Limiting Conditions for Oper of Reactor Coolant Sys | | | title = Forwards Appl for Amend to Facil Operating Lics#DPR-31 & DPR-41.Proposed Amend Addresses Overpressure Mitigating Sys (Oms).Discusses Limiting Conditions for Oper of Reactor Coolant Sys |
| | author name = UHRIG R E | | | author name = Uhrig R |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = STELLO V | | | addressee name = Stello V |
| | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) |
| | docket = 05000250, 05000251 | | | docket = 05000250, 05000251 |
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| =Text= | | =Text= |
| {{#Wiki_filter:P.O.BOX 013100,'IAMI, FL 33101 yglg>>+/ri vvtx%FLORIDA POWER&LIGHT COMPANY November 20, 1978 L-78-368 Director of Nuclear Reactor Regulation Attention: | | {{#Wiki_filter:P. O. BOX 013100,'IAMI, FL 33101 yglg>> |
| Hr.Victor-Stello, Director Division of Operating Reactors U.S.Nuclear Regulatory Commission Washington, D.C.20555. | | +/rivvtx% |
| | FLORIDA POWER & LIGHT COMPANY November 20, 1978 L-78-368 Director of Nuclear Reactor Regulation Attention: Hr. Victor- Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
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| ==Dear Hr.Stello:== | | ==Dear Hr. Stello:== |
| Re: Turkey Point-Units'and 4 Docket Nos.50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power&Light Company submits herewi th three (3)signed originals and forty (40)conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41.This submittal is being submitted in response to a July 19, 1978 letter from fir.A.Schwencer of your staff, in accordance with our letter of October 19, 1978.The proposed amendment, which addresses the operability and surveillance of the Turkey Point Units 3 and 4 Overpressure Hi tigating System (OHS), is described below and shown on the accompanying Technical Specification pages bearing the-date of this letter in the right hand corner.Pa e 3.1-1 New Specification 3'..l.a.5 addresses the starting of a reactor coolant pump wnen the reactor coolant system is in the'low temperature RCS overpressure protection range.Pa e 3.14-1 New Specification 3.14 gives the Overpressure Hitigati ng System (OHS)limiting conditions for operation.
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| Pa e 4.15-1 New Specification 4.15 gives the OHS surveillance requirements.
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| Pa es B3.1-1 B3.14-1 and B4.15-1 New and revised Bases sections are provided in support of the 0HS.M~~p't'Eh''JLIIIQ,.
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| ~",.<'IjiI'gpg~8~m>0l 6 I PEOPLE..~SERVING PEOPLE Director of Nuclear Reactor Regulation Page Two The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.They have concluded that it does not involve an unreviewed safety question.Implementation of the OMS at Turkey Point has proceeded in two phases.Phase I addressed the circuitry needed to add the Power Operated Relief Valve (PORV)low setpoint feature and associated alarms.Phase II addresses (1)OMS-arming/.
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| valve-position interlock circuitry and (2)redundant nitrogen supply to the PORV's.Phase I has been completed on both Units 3 and 4.It was our intent to implement Phase II during the refueling outages in 1978, but due to equip-ment procurement delays we have not been able to do so.All of the modifica-tion design work has been completed and all necessary parts are on order.Phase II is scheduled for implementation as soo'n as parts are avai,lable and plant conditions permit.lie expect to.complete Phase I I during the 1979 refuel-ing outages, which are both scheduled for Spring 1979.This, proposed change is being submitted for the convenience of the Comnission.
| |
| Accordingly, we have determined that it does not require the payment of a license amendment fee in accordance with 10 CFR 50 part 170.Very truly yours, Robert E.Uhrig Vice President REU/fiAS/cf Attachment cc: Mr.James P.O'Reilly, Region II Robert Lowenstein, Esquire TABXZ OP CO;)TENTS (Continued)
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| Section 3.7 3.8 3.9 3.10 3.11 3.12 3.13 3.14 4 4.2 4.3 4 4.6 4.7 4.8 4.9!O'.11 4.12 4.13 4.14 4.15 El cctriczl Systems Stean Power Conversion Systems Radioactive Haterizls Release Liquid Pastes Gaseous Pastes'Cont inerized Pastes Refueling Hiscel3.aneous Radioactive Haterizls Sources Cask.Hzndling Shod: Suopressors (snubbers)
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| Overpressure Mitigating System SURVKXLI<~~CE REQUX~HTS Operational.Safety Reviee Reactor Coolant System Xn Service Xnspect:ion.
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| Reactor Coolart System Xntegrity Containment Tests.Xntegrzted..Leakage Pate Test-Post Operational Local Penetration Tests Report of Test Results Xsolztion Valves Residual Heat Removal System Tendon Surveillance End Anchorage Concrete Surveillance Liner Surveillance-Safety Xnjection Emergency Containment Cooling Systems'mergency Contzi'nrent Piltering znd Post Accident Containment Vent Systems Emergency Pover System Periodic Tests Hain Ste~>.Xsolation Valves Auxiliary Peed-ater System Reactivity Pwomalies Environmentz2..Radiation Survey'adioactive.Materials Sources Surveillance Shack Suppressors (snubbers)
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| Overpressure Mitigating System~Pa e 3+7~1~3 8-3.-3.9-3.'.9-3.3.9-2 3.9-3;3.10-1 3 s 11.~1-3 12 1 3;13-3.3.14-1 fl 1 1 4.2-1 43'1 4-4-2, 4.4-1 f~f!,-1 4.4-2 4 4-3 4 4-3 44 l, f4%4-6 4.4-6 4.5-3.4.6.1 f~.7-.3.4.8-1 4.9-1 4.1O-1..4.12-3 4-13-i 4-.3.4-.1.
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| 4.15-1 5.5.1 5.2 5 3 5.4 6.6.1 6.2.6.3 6.4 6.5 6.6 6.7!6 8 6.9 DESIGN PE~TURKS Site Reactor Containment Fuel" Storage AD~EXHISTP~iTXVE CONTROLS Responsibility, Organization Facility Staff Qualifications Training Revie~and Audit Reportzble Occurrence Action Safety Limit Violation Procedures Reporting Requirements 5&1 1 5.1-3.5&2 1 5%3 5.4>3.6.1-3.6-3.6-1, 6-5 6-5 6-S 6-14 6-14 6-14 6-16
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| ===3.0 LINITIN===
| | Re: Turkey Point- Units' and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power & Light Company submits herewi th three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41. This submittal is being submitted in response to a July 19, 1978 letter from fir. A. Schwencer of your staff, in accordance with our letter of October 19, 1978. |
| CON)ITIONS FOR OPEeeATION'.1 REACTOR COOLANT SYSTEM A licabilit Applies to the operating st.atus of the Reactor Coolant System.~ob'e tlv e: To specify those limiting conditions for operation of the Reactox Coolant System which must be met to assure safe reactor operation.
| | The proposed amendment, which addresses the operability and surveillance of the Turkey Point Units 3 and 4 Overpressure Hi tigating System (OHS), |
| a.Reactor Coolant Pum s 1.A minimum of ONE pump shall be in operation when the react:or is in power operation, except during low power physics tests.2.A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be i.n operation during reactor coolant boron concent:ration,reduct:ion.
| | is described below and shown on the accompanying Technical Specification pages bearing the -date of this letter in the right hand corner. |
| 3.Reactor power shall not exceed 10%of rated power unless at least THO reactor coolant pumps are in operation. | | Pa e 3.1-1 New Specification 3 '..l.a.5 addresses the starting of a reactor coolant pump wnen the reactor coolant system is in the 'low temperature RCS overpressure protection range. |
| 4.Reactor power shall not exceed 45%of rat:ed power with only two pumps in operation unless the overtemperature AT t:rip setpoint:, K , for two loop operati.on, ha been set at 0.8 5.A reactor coolant pump shall not be started when cold leg temperature is<275'F unless steam gen-erator secondary water temperature is less than 50'F above, t: he RCS temperature (including instrument error).b.Steam Generators l.A minimum of TWO steam generators sh,.ll be operable when the average.coolant temperature is above 350F.c.Pressurizer Safet'alves l.ONE valve shall be operable whenever the head is on the reactor.vessel except during hydrostatic test:s.2.THRFE valves shall be operable when the reactor coolant average temperature i.s above 350F or the reactor is cr'tical.3-1-1 11/20/78 3.14 OVERPRESSURE MITIGATING SYSTEM the low temperature RCS overpressure protection range when the RCS is not vented through at least a 2.20 square inch area.~Ob'ective: To minimize.the possibility of an overpressure transient which could exceed the limits of 10 CFR 50, Appendix G.temperature RCS overpressure protection range.2.Valves HOV->'<-843 A, MOV-~-843 B, MOV->'-866 A, and MOV-~-866 B shall be closed in the low temperature RCS overpressure protection range.3.If any of the valves in 3.14.2 are found to be open while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 8 hours: a b.c block the corresponding flow path to the reactor vessel, close the valve, or depressurize and vent the RCS through an opening with an area of at least 2.20 square inches.4.Two pressurizer power operated relief valves shall be operable in the low temperature RCS overpressure protection range.a.If one power operated relief valve is inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within 7 days: (1)restore operability of the power operated relief valve, or (2)depressurize and vent the RCS through an opening with an area of at least 2.20 square inches.b.If both power operated relief valves are inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 24 hours: (1)restore operability of at least one power operated relief valve, or (2)depressurize. | | Pa e 3.14-1 New Specification 3. 14 gives the Overpressure Hitigati ng System (OHS) limiting conditions for operation. |
| and vent the RCS through an opening with an area of at least 2.20 square inches.3.14-1 11/20/78 4.15 OVERPRESSVRE MITIGATING SYSTEM Applies to periodic surveillance of the'Overpressure xiii'tigating System.~Ob ective: To demonstrate operability of the Overpressure Mitigating System.1.Within 1 month prior to operation in a condition where the PORV would be required to be operable, the pressurizer power operated relief valve actuation circuitry shall be functionally tested.The functional test need not include actual valve operation.
| | Pa e 4.15-1 New Specification 4.15 gives the OHS surveillance requirements. |
| 2.Hhile in the low temperature RCS overpxessure protecti.on range, verify daily that no more than one charging pump is operable.3.t&ile in the low temperature RCS overpressure protection range, verify daily that valves MOV->'-843 A, HQV-+-843 B, MOV-"'-866 A, and HOV->'-866 B are closed.4.While in the low temperature RCS overpressure protection range, verify weekly that the isolation valve for each operable pressurizer power operated relief valve is open.5.While in the low temperature RCS overpressure protection range, the pressurizer power operated relief valve actuation circuitry shall.be functionally tested monthly.The functional test need not include actual valve operation..
| | Pa es B3.1-1 B3.14-1 and B4.15-1 New and revised Bases sections are provided in support of the 0HS. |
| 6.Testing shall be in accordance with an approved pump and valve test program.4.15-1 1'1/20/78 BASES FOR LIMITING CONDITIONS FOR OPERATION, REACTOR COOLANT SYSTEM 1.0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss of flow occurs.The flow provided will keep DNBR well above 1.30.When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor.Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.The residual heat removal pump will circulate the reactor coolant system volume in approximately one half hour.Each of the pressurizer safety valves is designed to relieve 293,330 lbs.per hr.of saturated steam at the valve set point.Below 350 F and 450 psig in the Reactor Coolant System, the Residual Heat Removal System can remove decay heat and thereby control system temperature and pressure.If no residual heat were removed by any of the means available the amount of steam which could be generated at safety valve lifting, pressure would be less than the capacity of a single valve.Also, two safety valves have capacity gxeatpy than the maximum surge rate resulting from complete loss of load.The 50'F limit on maximum differential between steam, generator secondary water temperature and reactor coolant temperature assures that the pressure transient caused by starting a reactor coolant pump when cold leg temperature is<275,'F can be relieved by operation of one Power Operated Relief Valve (PORV).The 50 F limit iricludes instrument error.2.Pressure/Tem erature Limits All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations.
| | M~ ~ p 't |
| The various categoxies of load cycles used fox design purposes axe provided in B3.1-4 11/20/78 BASES FOR LIMITING CONDITIONS OF OPERATION OVERPRESSURE MITIGATING SYSTEM The operability of two PORV's or an RCS vent opening of greater than or equal to 2.20 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 cold legs are<275 F." Either PORV has adequate relieving capability to protect the RCS from overpressurizat9on when the transient is limited to either (1)the start of an idle RCS with the secondary water temperature of the steam generator<50'F above the RCS cold leg temperature (includes margin for instrument error)or (2)the start of a HPSI pump and its injection into a water solid RCS.B3.14-1 11/20/78 B4.15 BASES FOR SURVEILLANCE RE UIREMENTS OVERPRESSURE MITIGATING SYSTEM The specified testing of the Overpressure Mitigating System (OMS)will verify its operability.
| | 'Eh''JLIIIQ,. ~ |
| The capacity of one pressurizer Power Operated Relief Valve is sufficient to relieve potential overpressure transients when the RCS is in the low temperature overpressure protection range.Proper functioning of the OMS combined with selected administrative controls will demonstrate the integrity of the system.B4.15-1 STATE OF FLORXDA))COUNTY OF'ADE)ss Robert E.Uhrig, being first duly sworn, deposes and says: That he is a Vice President of Florida Power 6 Light Company, the Licensee herein;That he has executed the foregoing document;that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is.authorized to execute the document on behalf of said Licensee.Robert E..Uhrig Subscribed and sworn to before me this day of l9 78 NOTARY PUBLIC, and for the county of Dade,-State of Florida NOTAI rlJQLID GTAiE Dt'LDGIDA GT tA'GGG WY CO.'~V,.S.OH OV nGS t.V,GCH n', tSaZ Ny commission expires GONG 9 TftGlj MAY.':AAD CON NG AGB;CY}}
| | IjiI'gpg |
| | ~8~m>0l 6 I PEOPLE .. ~ SERVING PEOPLE |
| | |
| | Director of Nuclear Reactor Regulation Page Two The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board. |
| | They have concluded that it does not involve an unreviewed safety question. |
| | Implementation of the OMS at Turkey Point has proceeded in two phases. Phase I addressed the circuitry needed to add the Power Operated Relief Valve (PORV) low setpoint feature and associated alarms. Phase II addresses (1) OMS-arming/. |
| | valve-position interlock circuitry and (2) redundant nitrogen supply to the PORV's. Phase I has been completed on both Units 3 and 4. It was our intent to implement Phase II during the refueling outages in 1978, but due to equip-ment procurement delays we have not been able to do so. All of the modifica-tion design work has been completed and all necessary parts are on order. |
| | Phase II is scheduled for implementation as soo'n as parts are avai,lable and plant conditions permit. lie expect to .complete Phase I I during the 1979 refuel-ing outages, which are both scheduled for Spring 1979. |
| | This, proposed change is being submitted for the convenience of the Comnission. |
| | Accordingly, we have determined that it does not require the payment of a license amendment fee in accordance with 10 CFR 50 part 170. |
| | Very truly yours, Robert E. Uhrig Vice President REU/fiAS/cf Attachment cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire |
| | |
| | TABXZ OP CO;)TENTS (Continued) |
| | Section |
| | ~Pa e 3.7 El cctriczl Systems 3+7~1 ~ |
| | 3.8 Stean Power Conversion Systems 3.9 3 8-3.- |
| | Radioactive Haterizls Release 3.9-3. |
| | Liquid Pastes '.9-3. |
| | Gaseous Pastes |
| | 'Cont inerized Pastes 3.9-2 3.10 Refueling 3.9-3 3.11 Hiscel3.aneous Radioactive Haterizls Sources ; 3.10-1 3.12 Cask .Hzndling 3 s 11.~1 |
| | -3 12 1 3.13 Shod: Suopressors (snubbers) 3;13-3. |
| | 3.14 Overpressure Mitigating System 3.14-1 SURVKXLI<~~ CE REQUX~HTS 4 Operational .Safety Reviee fl 1 1 4.2 Reactor Coolant System Xn Service Xnspect:ion. 4.2-1 4.3 Reactor Coolart System Xntegrity 43'1 4 Containment Tests 4-4-2, |
| | . Xntegrzted..Leakage Pate Test Post Operational 4.4-1 Local Penetration Tests f~ f!,-1 Report of Test Results 4.4-2 Xsolztion Valves 4 4-3 Residual Heat Removal System 4 4-3 Tendon Surveillance 44 l, End Anchorage Concrete Surveillance f4%4-6 Liner Surveillance- 4.4-6 Safety Xnjection 4.5-3. |
| | 4.6 Emergency Containment Cooling Systems 4.6. 1 |
| | 'mergency Contzi'nrent Piltering znd Post Accident 4.7 Containment Vent Systems f~.7-.3. |
| | 4.8 Emergency Pover System Periodic Tests 4.8-1 4.9 Hain Ste~>.Xsolation Valves 4.9-1 |
| | !O'.11 Auxiliary Peed-ater System 4.1O-1.. |
| | Reactivity Pwomalies 4.12 Environmentz2..Radiation 4.12-3 4.13 Sources Surveillance Survey'adioactive.Materials 4-13-i 4.14 Shack Suppressors (snubbers) 4.15 Overpressure Mitigating System 4-.3.4-.1. |
| | 4.15-1 |
| | : 5. DESIGN PE~TURKS 5&1 1 5.1 Site 5.1-3. |
| | 5.2 Reactor 5&2 1 5 3 Containment 5 %3 5.4 Fuel" Storage 5.4>3. |
| | : 6. AD~EXHISTP~iTXVE CONTROLS 6.1-3. |
| | 6.1 Responsibility, 6-3. |
| | 6.2 Organization 6-1, |
| | .6.3 Facility Staff Qualifications 6-5 6.4 Training 6-5 6.5 Revie~ and Audit 6-S 6.6 Reportzble Occurrence Action 6-14 6.7 Safety Limit Violation 6-14 |
| | !6 8 Procedures 6-14 6.9 Reporting Requirements 6-16 |
| | |
| | 3.0 LINITIN CON)ITIONS FOR OPEeeATION'.1 REACTOR COOLANT SYSTEM A licabilit Applies to the operating st.atus of the Reactor Coolant System. |
| | ~ob |
| | ' e t lv e: To specify those limiting conditions for operation of the Reactox Coolant System which must be met to assure safe reactor operation. |
| | : a. Reactor Coolant Pum s |
| | : 1. A minimum of ONE pump shall be in operation when the react:or is in power operation, except during low power physics tests. |
| | : 2. A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be i.n operation during reactor coolant boron concent:ration,reduct:ion. |
| | : 3. Reactor power shall not exceed 10% of rated power unless at least THO reactor coolant pumps are in operation. |
| | : 4. Reactor power shall not exceed 45% of rat:ed power with only two pumps in operation unless the overtemperature AT t:rip setpoint:, K , for two loop operati.on, ha been set at 0.8 |
| | : 5. A reactor coolant pump shall not be started when cold leg temperature is < 275'F unless steam gen-erator secondary water temperature is less than 50'F above, t:he RCS temperature (including instrument error). |
| | : b. Steam Generators |
| | : l. A minimum of TWO steam generators sh,.ll be operable when the average. coolant temperature is above 350F. |
| | : c. Pressurizer Safet 'alves |
| | : l. ONE valve shall be operable whenever the head is on the reactor .vessel except during hydrostatic test:s. |
| | : 2. THRFE valves shall be operable when the reactor coolant average temperature i.s above 350F or the reactor is cr'tical. |
| | 11/20/78 3-1-1 |
| | |
| | 3.14 OVERPRESSURE MITIGATING SYSTEM the low temperature RCS overpressure protection range when the RCS is not vented through at least a 2.20 square inch area. |
| | ~Ob 'ective: To minimize .the possibility of an overpressure transient which could exceed the limits of 10 CFR 50, Appendix G. |
| | temperature RCS overpressure protection range. |
| | : 2. Valves HOV->'<-843 A, MOV-~-843 B, MOV->'-866 A, and MOV-~-866 B shall be closed in the low temperature RCS overpressure protection range. |
| | : 3. If any of the valves in 3.14.2 are found to be open while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 8 hours: |
| | a block the corresponding flow path to the reactor vessel, |
| | : b. close the valve, or c depressurize and vent the RCS through an opening with an area of at least 2.20 square inches. |
| | : 4. Two pressurizer power operated relief valves shall be operable in the low temperature RCS overpressure protection range. |
| | : a. If one power operated relief valve is inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within 7 days: |
| | (1) restore operability of the power operated relief valve, or (2) depressurize and vent the RCS through an opening with an area of at least 2.20 square inches. |
| | : b. If both power operated relief valves are inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 24 hours: |
| | (1) restore operability of at least one power operated relief valve, or (2) depressurize. and vent the RCS through an opening with an area of at least 2.20 square inches. |
| | : 3. 14-1 11/20/78 |
| | |
| | 4.15 OVERPRESSVRE MITIGATING SYSTEM Applies to periodic surveillance of the'Overpressure xiii'tigating System. |
| | ~Ob ective: To demonstrate operability of the Overpressure Mitigating System. |
| | : 1. Within 1 month prior to operation in a condition where the PORV would be required to be operable, the pressurizer power operated relief valve actuation circuitry shall be functionally tested. The functional test need not include actual valve operation. |
| | : 2. Hhile in the low temperature RCS overpxessure protecti.on range, verify daily that no more than one charging pump is operable. |
| | : 3. t&ile in the low temperature RCS overpressure protection range, verify daily that valves MOV->'-843 A, HQV-+-843 B, MOV-"'-866 A, and HOV->'-866 B are closed. |
| | : 4. While in the low temperature RCS overpressure protection range, verify weekly that the isolation valve for each operable pressurizer power operated relief valve is open. |
| | : 5. While in the low temperature RCS overpressure protection range, the pressurizer power operated relief valve actuation circuitry shall. be functionally tested monthly. The functional test need not include actual valve operation.. |
| | : 6. Testing shall be in accordance with an approved pump and valve test program. |
| | : 4. 15-1 1'1 /20/78 |
| | |
| | BASES FOR LIMITING CONDITIONS FOR OPERATION, REACTOR COOLANT SYSTEM |
| | : 1. 0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss of flow occurs. The flow provided will keep DNBR well above 1.30. When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor. |
| | Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place. The residual heat removal pump will circulate the reactor coolant system volume in approximately one half hour. |
| | Each of the pressurizer safety valves is designed to relieve 293,330 lbs. per hr. of saturated steam at the valve set point. |
| | Below 350 F and 450 psig in the Reactor Coolant System, the Residual Heat Removal System can remove decay heat and thereby control system temperature and pressure. If no residual heat were removed by any of the means available the amount of steam which could be generated at safety valve lifting,pressure would be less than the capacity of a single valve. Also, two safety valves have capacity gxeatpy than the maximum surge rate resulting from complete loss of load. |
| | The 50'F limit on maximum differential between steam, generator secondary water temperature and reactor coolant temperature assures that the pressure transient caused by starting a reactor coolant pump when cold leg temperature is < 275,'F can be relieved by operation of one Power Operated Relief Valve (PORV). The 50 F limit iricludes instrument error. |
| | : 2. Pressure/Tem erature Limits All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categoxies of load cycles used fox design purposes axe provided in B3.1-4 11/20/78 |
| | |
| | BASES FOR LIMITING CONDITIONS OF OPERATION OVERPRESSURE MITIGATING SYSTEM The operability of two PORV's or an RCS vent opening of greater than or equal to 2.20 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 cold legs are < 275 F." |
| | Either PORV has adequate relieving capability to protect the RCS from overpressurizat9on when the transient is limited to either (1) the start of an idle RCS with the secondary water temperature of the steam generator < 50'F above the RCS cold leg temperature (includes margin for instrument error) or (2) the start of a HPSI pump and its injection into a water solid RCS. |
| | B3. 14-1 11/20/78 |
| | |
| | B4. 15 BASES FOR SURVEILLANCE RE UIREMENTS OVERPRESSURE MITIGATING SYSTEM The specified testing of the Overpressure Mitigating System (OMS) will verify its operability. The capacity of one pressurizer Power Operated Relief Valve is sufficient to relieve potential overpressure transients when the RCS is in the low temperature overpressure protection range. Proper functioning of the OMS combined with selected administrative controls will demonstrate the integrity of the system. |
| | B4.15-1 |
| | |
| | STATE OF FLORXDA ) |
| | ) ss COUNTY OF'ADE ) |
| | Robert E. Uhrig, being first duly sworn, deposes and says: |
| | That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is. authorized to execute the document on behalf of said Licensee. |
| | Robert E.. Uhrig Subscribed and sworn to before me this day of l9 78 NOTARY PUBLIC, and for the county of Dade, |
| | -State of Florida NOTAI rlJQLID GTAiE Dt'LDGIDA GT tA'GGG WY CO.'~V,.S .OH OV nGS t.V,GCH n', |
| | Ny commission expires GONG 9 TftGlj MAY.':AAD CON NG AGB;CY tSaZ}} |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17355A4601999-10-26026 October 1999
Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted
ML17355A4301999-10-0808 October 1999
Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included
ML17355A4461999-10-0404 October 1999
Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std
L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999
Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included
ML17355A4291999-10-0404 October 1999
Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days
ML20212M1601999-09-28028 September 1999
Refers to 990908 Engineering Meeting Conducted at NRC Region II to Discuss Engineering Issues at Lucie & Turkey Point Facilities.List of Attendees & Copy of Presentation Handout Encl
ML17355A4251999-09-22022 September 1999
Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820
ML17355A4111999-09-0909 September 1999
Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08
ML17355A4131999-09-0707 September 1999
Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC
ML17355A4141999-09-0202 September 1999
Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830
ML17355A4041999-08-23023 August 1999
Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4
ML17355A4071999-08-23023 August 1999
Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity.
ML17355A4061999-08-23023 August 1999
Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included
ML17355A4001999-08-20020 August 1999
Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance
ML17355A3941999-07-27027 July 1999
Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01
ML17355A3871999-07-16016 July 1999
Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17355A3851999-07-14014 July 1999
Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept
ML17355A3711999-07-0606 July 1999
Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes
ML17355A3591999-06-30030 June 1999
Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17355A3571999-06-28028 June 1999
Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness
ML17355A3521999-06-18018 June 1999
Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves.
ML17355A3491999-06-0404 June 1999
Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions.
ML17355A3441999-05-27027 May 1999
Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031
ML17355A3451999-05-24024 May 1999
Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley
ML17355A2921999-04-22022 April 1999
Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330
ML20205M0431999-04-13013 April 1999
Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR
ML17355A2891999-04-0909 April 1999
Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001
ML17355A2861999-04-0505 April 1999
Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7
ML17336A0681999-04-0101 April 1999
Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4
ML17355A2751999-03-25025 March 1999
Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000
ML17355A2641999-03-19019 March 1999
Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence
ML17355A2651999-03-19019 March 1999
Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4.
ML17355A2621999-03-16016 March 1999
Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI
ML17355A2631999-03-12012 March 1999
Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit
ML20204C6991999-03-10010 March 1999
Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested
ML17355A2451999-03-0909 March 1999
Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3)
ML17355A2501999-03-0808 March 1999
Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl
ML17355A2441999-03-0101 March 1999
Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4
ML17355A2431999-02-25025 February 1999
Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE)
ML17355A2301999-02-18018 February 1999
Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4
ML17355A2361999-02-18018 February 1999
Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998
L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999
Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)
ML17355A2341999-02-18018 February 1999
Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations.
ML17355A2231999-02-0808 February 1999
Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance
ML17355A2031999-01-29029 January 1999
Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan
ML17355A2171999-01-20020 January 1999
Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI
ML17354B2241999-01-0606 January 1999
Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation
ML17354B2081998-12-15015 December 1998
Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II
ML17354B2091998-12-15015 December 1998
Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b)
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17355A4601999-10-26026 October 1999
Forwards Revised Epips,Including Revs to 0-EPIP-1102, 0-EPIP-1212,0-EPIP-20110,0-EPIP-20111,0-EPIP-20132, 0-EPIP-20133 & 0-EPIP-20201,per 10CFR50.54(q) & 10CFR50, App E.Epip 0-EPIP-20107,has Been Deleted
ML17355A4301999-10-0808 October 1999
Forwards Rev 16 of Updated Fsar.Info Accurately Reflects Plant Changes Made Since Previous Submittal.Rev Incorporates Changes Completed Between 971015 & 990408.Summary of Accuracy Review Changes & Instructions,Included
ML17355A4461999-10-0404 October 1999
Notifies NRC of Change in Commitment to Perform Periodic Testing of Critical Welds & Parts on Special Lifting Devices IAW NUREG-0612.Use of Ae Technology Will Provide Same Level of Testing Quality as Did NDE Methods Noted in ANSI Std
L-99-208, Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included1999-10-0404 October 1999
Forwards Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period Covering 971014-990408. Summary of PORV Actuations & Results of Plants SG Tube Insp,Which Occurred During That Time Included
ML17355A4291999-10-0404 October 1999
Forwards Response to NRC Telcon Questions Re License Amend Request Dtd 990727,proposing Amend on one-time Basis to Modify TS 3.8.1.1 & TS 3.4.3 & 3.5.2 to Extend Allowed Outage Time for EDG from 72 H to 7 Days
ML17355A4251999-09-22022 September 1999
Forwards NRC Form 536 in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Issued 990820
ML17355A4111999-09-0909 September 1999
Informs That Thermo-Lag Upgrades for Fire Zones 47,54,113, 114,115,116,118,119,120 & 143 Completed on 990726,per GL 92-08
ML17355A4131999-09-0707 September 1999
Forwards Revised Relief Request 20 Re Requirement to Perform Exams as Required by IWL-2524 & IWL-2525,Table IWL-2500-1 for Exempt Tendon Insp,Per Recent Discussions with NRC
ML17355A4141999-09-0202 September 1999
Documents That Util Has No Concerns or Challenges Related to site-specific Written Exam Administered at Plant on 990830
ML17355A4041999-08-23023 August 1999
Forwards Info to Support Assessment of Potential Risks Associated with Proposed Civil Aircraft Operations at Former Homestead Air Force Base to FP&L Turkey Point Nuclear Facility Units 3 & 4
ML17355A4071999-08-23023 August 1999
Informs That FPL Has Completed Review of Info Listed in Reactor Vessel Integrity Database,Version 2 & Found Listed Discrepancies,Re Closure of GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity.
ML17355A4061999-08-23023 August 1999
Forwards Semiannual FFD Performance Rept for Period of Jan- June 1999,for Turkey Point Units 3 & 4.List of Events Reported & Summary of Mgt Actions Taken,Included
ML17355A4001999-08-20020 August 1999
Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance
ML17355A3941999-07-27027 July 1999
Submits Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for FY00 & FY01
ML17355A3871999-07-16016 July 1999
Provides Supplement to FP&L Response to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants
ML17355A3851999-07-14014 July 1999
Informs That Pages Missing from 1998 Annual Radiological Environ Operating Rept, Contain Info Unrelated to ODCM- Specified Sampling & Were Not Included as Part of Rept
ML17355A3711999-07-0606 July 1999
Forwards Revised EPIPs 0-EPIP-20201, Maintaining Emergency Preparedness - Radiological Emergency Plan Training & 0-EPIP-20126, Off-Site Dose Calculations. with Summary of Changes
ML17355A3591999-06-30030 June 1999
Forwards Turkey Point,Unit 4 ISI Rept. Listed Repts Are Encl.No Eddy Current Exams Scheduled for Unit 4 Steam Generators
ML17355A3661999-06-30030 June 1999
Forwards Florida Power & Light Topical QA Rept, Dtd June 1999.Encl I Includes Summary of Changes Made to Topical QA Rept Since 1998
ML17355A3571999-06-28028 June 1999
Informs That Util Voluntarily Reporting Facility Readiness as Outlined in Suppl 1 to GL 98-01.Encl Is Y2K Readiness Disclosure for Units 3 & 4,reporting Status of Facility Y2K Readiness
ML17355A3521999-06-18018 June 1999
Forwards Response to NRC 990415 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves.
ML17355A3491999-06-0404 June 1999
Forwards Summary of Corrective Actions Implemented by FPL Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions.
ML17355A3441999-05-27027 May 1999
Modifies FPLs Consent to Confirmatory Order to Reflect Resolution of Four Issues Identified as Pending in L-99-031
ML17355A3451999-05-24024 May 1999
Requests Waiver of 520 Hours (13 Wks) Required Parallel Watchstanding in Control Room Prior to License Application Submittal for W Conley
ML17355A2921999-04-22022 April 1999
Forwards Rev 35 to Turkey Point EP & Revised EPIP 0-EPIP-20101, Duties of EC, Per Requirements of 10CFR50, App E & 10CFR50.54(q).Summary of Changes,Encl.Implementation Date for Both Documents Was 990330
ML17355A2891999-04-0909 April 1999
Forwards Relief Request 20, Exempt Tendon Insp, Requesting Relief from ASME Section XI Code,1992 Edition,Paragraph IWL-2521.1(c) Which Requires That Each Exempted Tendon Be Examined IAW IWL-2524 & IWL-2525.Approval Needed by 991001
ML17355A2861999-04-0505 April 1999
Forwards COLR for Turkey Point Unit 4,Cycle 18,IAW TS 6.9.1.7
ML17336A0681999-04-0101 April 1999
Expresses Support for FP&L Request for Waiver of Applicable Review Fees Upon FP&L Submittal of an Application for License Renewal for Turkey Point Units 3 & 4
ML17355A2751999-03-25025 March 1999
Informs NRC & Staff of Fp&Ls Plans to Submit License Renewal Application for Turkey Point Units 3 & 4 by End of Dec 2000
ML17355A2641999-03-19019 March 1999
Requests Changes to FPL Official Service List for Turkey Point,Units 3 & 4.Add s Franzone & Remove G Hollinger from All Correspondence
ML17355A2651999-03-19019 March 1999
Forwards Annual Radioactive Effluent Release Rept for Jan-Dec 1998 & Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point,Units 3 & 4.
ML17355A2621999-03-16016 March 1999
Forwards Special Rept as Result of Turkey Point Unit 3 End-of-Cycle 16 ISI of SG Tubes.Rept Summarizes Results of SG Tube ISI
ML17355A2631999-03-12012 March 1999
Forwards FPL Decommissioning Fund Status Repts for St Lucie, Units 1 & 2 & Turkey Point,Units 3 & 4.Rept for St Lucie, Unit 2 Provides Status of Decommissioning Funds for All Three Owners of That Unit
ML20204C6991999-03-10010 March 1999
Requests Amend to Turkey Point PSP to Modify Requirement to Post Security Officers to Provide Continuous Observation of Entire PA Perimeter in Event of Security Computer Failure. Change to Security Force Staffing Level Also Requested
ML17355A2451999-03-0909 March 1999
Submits Info on FPL Current Levels of Nuclear Property Insurance,Per 10CFR50.54(w)(3)
ML17355A2501999-03-0808 March 1999
Informs That Licensee Reviewed NRC 990228 Ltr Issuing Exemption Requested Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg.Tabulated Summary of Util Comments & Marked Copy of NRC Ltr & SER Encl
ML17355A2441999-03-0101 March 1999
Provides Update to Util Written Notices,Dtd 961120 & 970627 of Claim Involving Alleged Bodily Injury Arising Out of or in Connection with Use of Radioactive Matl at Units 3 & 4
ML17355A2431999-02-25025 February 1999
Informs That FPL Does Not Have Any Candidates from Turkey Point Scheduled to Participate in 990407,Generic Fundamentals Examination (GFE)
ML17355A2341999-02-18018 February 1999
Provides Response to RAI Re GL 97-01, Degradation of Crdm/ CEDM Nozzle & Other Vessel Closure Head Penetrations.
L-99-042, Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)1999-02-18018 February 1999
Forwards Rev 13 to Turkey Point Physical Security Plan,Per 10CFR50.54(p).Util Determined That Rev Does Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR2.790(a)(3)
ML17355A2361999-02-18018 February 1999
Forwards Tabulation of 1998 Occupational Exposure Data for Turkey Point,Units 3 & 4,per TS 6.9.1.2.a.Reactor Coolant Specific Activity Limits of 100/E-bar Mci Per Gram of Gross Radioactivity Were Not Exceeded During 1998
ML17355A2301999-02-18018 February 1999
Forwards Semiannual Fitness for Duty Performance Data for Period of 980701-981231 for Turkey Point Units 3 & 4
ML17355A2231999-02-0808 February 1999
Informs That Util Will Comply with Commitment with Respect to Units 3 & 4,in Response to Ja Zwolinski 990129 Ltr.Util Also Agrees to Incorporate Commitment Into Confirmatory Order Modifying License Effective Immediately Upon Issuance
ML17355A2031999-01-29029 January 1999
Forwards Rev 3 to Turkey Point Nuclear Plant Recovery Plan. Rev Does Not Decrease Effectiveness of Plan
ML17355A2171999-01-20020 January 1999
Forwards Listed ISI Repts for Turkey Point Unit 3,in Accordance with Provisions of ASME Code,Section XI
ML17354B2241999-01-0606 January 1999
Forwards Annual 10CFR50.46 Rept Re Changes To,Or Errors Discovered in ECCS Evaluation Models,Or in Application of Such Models That Effect Peak Clad Temp Calculation
ML17354B2081998-12-15015 December 1998
Informs That Fpl,In Cooperation with State of Fl & County Emergency Response Agencies,Will Conduct Exercise of Turkey Point Radiological Emergency Plan on 990210.Scenario Package Forwarded to Emergency Preparedness Section Chief,Region II
ML17354B2091998-12-15015 December 1998
Forwards Price Anderson Guarantees Annual Financial Rept,Per 10CFR140.21.Exhibit 1 Submitted to Satisfy Annual Financial Reporting Requirement of 10CFR50.71(b)
ML17354B2061998-12-0909 December 1998
Informs That Request for Exemption Specified in Section II.B.3 Will Not Be Needed Re Fire Rating of Raceway Fire Barriers in Open Turbine Bldg
ML17354B1981998-11-25025 November 1998
Forwards Scope & Objective for 1999 Plant Annual Emergency Preparedness Exercise.Objectives Developed in Conjunction with State & Local Govts.Exercise Scheduled for 990210
1999-09-09
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17348A5661990-09-14014 September 1990
Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule.
ML17348A5461990-09-0707 September 1990
Forwards 1990 Inservice Insp Refueling Outage Summary Rept of NDE Activities 900206-0404 First Refueling Outage Second Period Second Insp Interval.
ML17348A5501990-09-0707 September 1990
Forwards Jul 1990 Integrated Schedule Regulatory Rept for Facilities
ML17348A5521990-09-0606 September 1990
Forwards Matrix of Changes to Emergency Power Sys That Affect Revised Tech Specs Issued on 900828.Matrix Sent for Info & to Assist in NRC Review of No Significant Hazards Rept for Revised Tech Specs
ML17348A5431990-08-31031 August 1990
Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA
ML17348A5361990-08-27027 August 1990
Forwards Turkey Point Units 3 & 4 Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Health Physics Procedure HP-48, Process Control Program for Dewatering Radwaste Liners.
ML17348A5171990-08-24024 August 1990
Forwards Ref Matl in Preparation for Operator License Exams Scheduled for Wk of 901029,per NRC 900628 Request
ML17348A5041990-08-17017 August 1990
Forwards fitness-for-duty Program Performance Data for Jan-June 1990
ML17348A5051990-08-15015 August 1990
Forwards Monthly Operating Repts for Jul 1990 for Turkey Point Units 3 & 4 & Revise Rept for June 1990 for Unit 3
ML20059B0111990-08-14014 August 1990
Requests That Encl Intervenor Motion for Extension of Time to Appeal to Docketing & Svcs Branch Re Tech Spec Replacement Hearing Be Provided.Motion Inadvertently Omitted in Svc of Request on 900813
ML17348A4971990-08-10010 August 1990
Responds to Violations Noted in Insp Repts 50-250/90-18 & 50-251/90-18.Corrective Actions:Unit Stabilized in Mode 3, Operating Surveillance Procedures 3/4-OSP-089 Revised & Event Response Team Formed
ML17348A4701990-07-27027 July 1990
Forwards Rept Detailing Investigative Analysis of Unsatisfactory Blind Specimen Results,Identification of Causes & Corrective Actions Taken by Lab to Prevent Recurrence,Per Unsatisfactory Performance Testing
L-90-282, Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)1990-07-25025 July 1990
Forwards Rev 23 to Physical Security Plan.Plan Withheld (Ref 10CFR73.21 & 2.790)
ML17348A4281990-07-25025 July 1990
Forwards Decommissioning Financial Assurance Repts for Plants,Per 10CFR50.33(k) & 50.75(b)
ML17348A4691990-07-23023 July 1990
Forwards Addl Info on Emergency Power Sys Enhancement Project Re Load Sequencer,Programmable Logic Controllers & Implementation of Sys in Plant,Per NRC 900705 Request
ML17348A4191990-07-20020 July 1990
Advises That Comments on NRC Safety Evaluation Re Implementation of Station Blackout Rule Will Be Provided by 900921
ML17348A4201990-07-20020 July 1990
Forwards Revised No Significant Hazards Determination for Proposed Tech Specs 1.17 & 3.0.5 & Bases,Per 890605 Ltr
ML17348A4141990-07-20020 July 1990
Responds to Violations Noted in Insp Repts 50-250/90-14 & 50-251/90-14.Corrective Actions:Breakers Closed,Returning Monitoring Sys to Operable Level & Briefings Held to Explain Rvlms Sys Theory to Operations Control Room Personnel
ML17348A4171990-07-19019 July 1990
Forwards May 1990 Integrated Schedule Regulatory Rept for Plant
ML17348A4121990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount.
ML17348A4251990-07-17017 July 1990
Withdraws 900207 & 0424 Proposed Changes to Tech Specs Re Util Nuclear Review Board Composition
IR 05000250/19900131990-07-16016 July 1990
Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated
ML20055G8641990-07-16016 July 1990
Informs ASLB That Petitioners Ref to Several Telephone Contacts Between J Butler & M Gutman,Of ATI Career Training Inst Is Inadvertent Misstatement & Should Be Changed to Telephone Contact. W/Certificate of Svc
ML17348A4161990-07-16016 July 1990
Responds to Commitment Re Reverse Testing of Containment Isolation Valves Per Insp Repts 50-250/90-13 & 50-251/90-13. Corrective Action Plan Addresses Penetrations 16 & 53 for Unit 3 Only & Penetrations 11,47,54A & 54B for Both Units
ML17348A4151990-07-16016 July 1990
Provides Info Re Plant Implementation of 10CFR50.44 & NUREG- 0737,Item II.E.4.1 Re Hydrogen Recombiners,Per 900518 Meeting & Insp Repts 50-250/90-13 & 50-251/90-13.Agreement Re Use of External Recombiners Will Be Reactivated
ML17348A4041990-07-12012 July 1990
Forwards Addl Info Re Responses to NRC Questions on Piping Codes Used for Emergency Power Sys Enhancement Project
ML17348A3921990-07-12012 July 1990
Summarizes Facility Performance Since Last SALP Evaluation Period Which Ended 890731.Util Pursued Aggressive self- Assessment Program,Including Significant Internal or Outside Assessments in Areas of Operator Performance & EOPs
L-90-261, Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld1990-07-11011 July 1990
Forwards Rev 7 to Guard Training & Qualification Plan.Rev Withheld
L-90-259, Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))1990-07-11011 July 1990
Forwards Rev 22 to Physical Security Plan.Rev Withheld (Ref 10CFR2.790(a)(3))
ML17348A4321990-07-11011 July 1990
Forwards Rev 8 to Updated FSAR for Turkey Point Units 3 & 4. Rev Includes Activities Completed Between 890123 & 900122. Rept of Changes for Jul 1989 Through June 1990 Will Be Provided by 900901
ML17348A3941990-07-0909 July 1990
Forwards Requested Addl Info Re Emergency Power Sys Enhancement Project.Specific Detailed Changes Will Be Made to Procedures to Address Mods Affecting Equipment Relied Upon for Safe Shutdown
ML17348A3881990-07-0505 July 1990
Requests Audit of NRC Records to Independently Verify Reasonableness of Charges Assessed Against Util,Per 10CFR170 Svcs
ML17348A4311990-07-0505 July 1990
Documents Written & Verbal Request of Region II Personnel for Temporary Waiver of Compliance of Tech Spec 3.4.2.b.1 Re Allowable Out of Svc Time for One Emergency Containment Cooler from 24 H to 72 Hr W/Addl Reasons
ML17348A3851990-07-0303 July 1990
Responds to NRC Ltr Re Violations Noted in Insp Repts 50-250/90-08 & 50-251/90-08.Corrective Actions:Training Dept Increased Emphasis on Radiological Postings in Radiation Worker Training
ML17348A3711990-07-0303 July 1990
Responds to NRC 900524 Request for Addl Info on Emergency Power Sys Enhancement Project
ML17348A3671990-07-0303 July 1990
Confirms Util Intentions Not to Operate Beyond Refueling Outage That Represents Last Outage Re NRC Bulletin 89-001
ML17348A3841990-06-29029 June 1990
Forwards LER 90-11 on 900609 Re hi-hi Steam Generator Water Level Turbine Trip & Subsequent Reactor Trip Due to Failure of Switch in Feedwater Valve Controller Hand/Auto Station. W/O Encl
ML17348A3601990-06-29029 June 1990
Responds to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs. Test Procedures Developed & Under Mgt Review Reflecting Revised Inservice Testing Program
ML17348A3621990-06-28028 June 1990
Notifies That Senior Operator License SOP-20177-2 Will Be Terminated,Effective 900731
ML17348A3651990-06-28028 June 1990
Advises That Completion of safety-related motor-operated Valve Testing & Surveillance Will Be Completed by June 1990, Per Generic Ltr 89-10 Requirements
ML17348A3591990-06-27027 June 1990
Responds to Violations Noted in Insp Repts 50-250/90-09 & 50-251/90-09.Corrective Actions:Specialist Counselled on Importance of Stopping Procedure When Steps Conflict W/ Condition of Plant & Procedure Use Guidelines Reviewed
ML17348A3641990-06-27027 June 1990
Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions.
ML17348A3861990-06-27027 June 1990
Advises That New Date for Submittal of Response to Insp Repts 50-250/90-09 & 50-251/90-09 Is 900702
ML17348A3551990-06-21021 June 1990
Responds to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Five Untraceable Circuit Breakers Installed in Unit 3 safety-related Sys.All Five Breakers Replaced W/Traceable Breakers
ML20055D9201990-06-20020 June 1990
Advises That Sp Frantz Will Represent Licensee in Argument Scheduled for 900710.Certificate of Svc Encl
ML17348A3181990-06-19019 June 1990
Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008
ML17348A2981990-06-12012 June 1990
Forwards Rev 16 to Topical QA Rept.
ML17348A2871990-06-0808 June 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor/Darling Model S350W Swing Check Valves or Valves of Similar Design. Bolt Replacement Performed
ML17348A2861990-06-0808 June 1990
Advises That Info Re Operating History of Select Fuel Assemblies Sent to ORNL Between 900419 & 26,per 900510 Request
ML17348A2781990-06-0404 June 1990
Forwards Emergency Power Sys Enhancement Project Repts, Reflecting Current Design Info
1990-09-07
[Table view] |
Text
P. O. BOX 013100,'IAMI, FL 33101 yglg>>
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FLORIDA POWER & LIGHT COMPANY November 20, 1978 L-78-368 Director of Nuclear Reactor Regulation Attention: Hr. Victor- Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Hr. Stello:
Re: Turkey Point- Units' and 4 Docket Nos. 50-250 and 50-251 Proposed Amendment to Facility 0 eratin Licenses DPR-31 and DPR-41 In accordance with 10 CFR 50.30, Florida Power & Light Company submits herewi th three (3) signed originals and forty (40) conformed copies of a request to amend Appendix A of Facility Operating Licenses DPR-31 and DPR-41. This submittal is being submitted in response to a July 19, 1978 letter from fir. A. Schwencer of your staff, in accordance with our letter of October 19, 1978.
The proposed amendment, which addresses the operability and surveillance of the Turkey Point Units 3 and 4 Overpressure Hi tigating System (OHS),
is described below and shown on the accompanying Technical Specification pages bearing the -date of this letter in the right hand corner.
Pa e 3.1-1 New Specification 3 '..l.a.5 addresses the starting of a reactor coolant pump wnen the reactor coolant system is in the 'low temperature RCS overpressure protection range.
Pa e 3.14-1 New Specification 3. 14 gives the Overpressure Hitigati ng System (OHS) limiting conditions for operation.
Pa e 4.15-1 New Specification 4.15 gives the OHS surveillance requirements.
Pa es B3.1-1 B3.14-1 and B4.15-1 New and revised Bases sections are provided in support of the 0HS.
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Director of Nuclear Reactor Regulation Page Two The proposed amendment has been reviewed by the Turkey Point Plant Nuclear Safety Committee and the Florida Power 8 Light Company Nuclear Review Board.
They have concluded that it does not involve an unreviewed safety question.
Implementation of the OMS at Turkey Point has proceeded in two phases. Phase I addressed the circuitry needed to add the Power Operated Relief Valve (PORV) low setpoint feature and associated alarms. Phase II addresses (1) OMS-arming/.
valve-position interlock circuitry and (2) redundant nitrogen supply to the PORV's. Phase I has been completed on both Units 3 and 4. It was our intent to implement Phase II during the refueling outages in 1978, but due to equip-ment procurement delays we have not been able to do so. All of the modifica-tion design work has been completed and all necessary parts are on order.
Phase II is scheduled for implementation as soo'n as parts are avai,lable and plant conditions permit. lie expect to .complete Phase I I during the 1979 refuel-ing outages, which are both scheduled for Spring 1979.
This, proposed change is being submitted for the convenience of the Comnission.
Accordingly, we have determined that it does not require the payment of a license amendment fee in accordance with 10 CFR 50 part 170.
Very truly yours, Robert E. Uhrig Vice President REU/fiAS/cf Attachment cc: Mr. James P. O'Reilly, Region II Robert Lowenstein, Esquire
TABXZ OP CO;)TENTS (Continued)
Section
~Pa e 3.7 El cctriczl Systems 3+7~1 ~
3.8 Stean Power Conversion Systems 3.9 3 8-3.-
Radioactive Haterizls Release 3.9-3.
Liquid Pastes '.9-3.
Gaseous Pastes
'Cont inerized Pastes 3.9-2 3.10 Refueling 3.9-3 3.11 Hiscel3.aneous Radioactive Haterizls Sources ; 3.10-1 3.12 Cask .Hzndling 3 s 11.~1
-3 12 1 3.13 Shod: Suopressors (snubbers) 3;13-3.
3.14 Overpressure Mitigating System 3.14-1 SURVKXLI<~~ CE REQUX~HTS 4 Operational .Safety Reviee fl 1 1 4.2 Reactor Coolant System Xn Service Xnspect:ion. 4.2-1 4.3 Reactor Coolart System Xntegrity 43'1 4 Containment Tests 4-4-2,
. Xntegrzted..Leakage Pate Test Post Operational 4.4-1 Local Penetration Tests f~ f!,-1 Report of Test Results 4.4-2 Xsolztion Valves 4 4-3 Residual Heat Removal System 4 4-3 Tendon Surveillance 44 l, End Anchorage Concrete Surveillance f4%4-6 Liner Surveillance- 4.4-6 Safety Xnjection 4.5-3.
4.6 Emergency Containment Cooling Systems 4.6. 1
'mergency Contzi'nrent Piltering znd Post Accident 4.7 Containment Vent Systems f~.7-.3.
4.8 Emergency Pover System Periodic Tests 4.8-1 4.9 Hain Ste~>.Xsolation Valves 4.9-1
!O'.11 Auxiliary Peed-ater System 4.1O-1..
Reactivity Pwomalies 4.12 Environmentz2..Radiation 4.12-3 4.13 Sources Surveillance Survey'adioactive.Materials 4-13-i 4.14 Shack Suppressors (snubbers) 4.15 Overpressure Mitigating System 4-.3.4-.1.
4.15-1
- 5. DESIGN PE~TURKS 5&1 1 5.1 Site 5.1-3.
5.2 Reactor 5&2 1 5 3 Containment 5 %3 5.4 Fuel" Storage 5.4>3.
- 6. AD~EXHISTP~iTXVE CONTROLS 6.1-3.
6.1 Responsibility, 6-3.
6.2 Organization 6-1,
.6.3 Facility Staff Qualifications 6-5 6.4 Training 6-5 6.5 Revie~ and Audit 6-S 6.6 Reportzble Occurrence Action 6-14 6.7 Safety Limit Violation 6-14
!6 8 Procedures 6-14 6.9 Reporting Requirements 6-16
3.0 LINITIN CON)ITIONS FOR OPEeeATION'.1 REACTOR COOLANT SYSTEM A licabilit Applies to the operating st.atus of the Reactor Coolant System.
~ob
' e t lv e: To specify those limiting conditions for operation of the Reactox Coolant System which must be met to assure safe reactor operation.
- a. Reactor Coolant Pum s
- 1. A minimum of ONE pump shall be in operation when the react:or is in power operation, except during low power physics tests.
- 2. A minimum of ONE pump, or ONE Residual Heat Removal Pump, shall be i.n operation during reactor coolant boron concent:ration,reduct:ion.
- 3. Reactor power shall not exceed 10% of rated power unless at least THO reactor coolant pumps are in operation.
- 4. Reactor power shall not exceed 45% of rat:ed power with only two pumps in operation unless the overtemperature AT t:rip setpoint:, K , for two loop operati.on, ha been set at 0.8
- 5. A reactor coolant pump shall not be started when cold leg temperature is < 275'F unless steam gen-erator secondary water temperature is less than 50'F above, t:he RCS temperature (including instrument error).
- b. Steam Generators
- l. A minimum of TWO steam generators sh,.ll be operable when the average. coolant temperature is above 350F.
- c. Pressurizer Safet 'alves
- l. ONE valve shall be operable whenever the head is on the reactor .vessel except during hydrostatic test:s.
- 2. THRFE valves shall be operable when the reactor coolant average temperature i.s above 350F or the reactor is cr'tical.
11/20/78 3-1-1
3.14 OVERPRESSURE MITIGATING SYSTEM the low temperature RCS overpressure protection range when the RCS is not vented through at least a 2.20 square inch area.
~Ob 'ective: To minimize .the possibility of an overpressure transient which could exceed the limits of 10 CFR 50, Appendix G.
temperature RCS overpressure protection range.
- 2. Valves HOV->'<-843 A, MOV-~-843 B, MOV->'-866 A, and MOV-~-866 B shall be closed in the low temperature RCS overpressure protection range.
- 3. If any of the valves in 3.14.2 are found to be open while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
a block the corresponding flow path to the reactor vessel,
- b. close the valve, or c depressurize and vent the RCS through an opening with an area of at least 2.20 square inches.
- 4. Two pressurizer power operated relief valves shall be operable in the low temperature RCS overpressure protection range.
- a. If one power operated relief valve is inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within 7 days:
(1) restore operability of the power operated relief valve, or (2) depressurize and vent the RCS through an opening with an area of at least 2.20 square inches.
- b. If both power operated relief valves are inoperable while in the low temperature RCS overpressure protection range, perform at least one of the following within the next 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
(1) restore operability of at least one power operated relief valve, or (2) depressurize. and vent the RCS through an opening with an area of at least 2.20 square inches.
- 3. 14-1 11/20/78
4.15 OVERPRESSVRE MITIGATING SYSTEM Applies to periodic surveillance of the'Overpressure xiii'tigating System.
~Ob ective: To demonstrate operability of the Overpressure Mitigating System.
- 1. Within 1 month prior to operation in a condition where the PORV would be required to be operable, the pressurizer power operated relief valve actuation circuitry shall be functionally tested. The functional test need not include actual valve operation.
- 2. Hhile in the low temperature RCS overpxessure protecti.on range, verify daily that no more than one charging pump is operable.
- 3. t&ile in the low temperature RCS overpressure protection range, verify daily that valves MOV->'-843 A, HQV-+-843 B, MOV-"'-866 A, and HOV->'-866 B are closed.
- 4. While in the low temperature RCS overpressure protection range, verify weekly that the isolation valve for each operable pressurizer power operated relief valve is open.
- 5. While in the low temperature RCS overpressure protection range, the pressurizer power operated relief valve actuation circuitry shall. be functionally tested monthly. The functional test need not include actual valve operation..
- 6. Testing shall be in accordance with an approved pump and valve test program.
- 4. 15-1 1'1 /20/78
BASES FOR LIMITING CONDITIONS FOR OPERATION, REACTOR COOLANT SYSTEM
- 1. 0 erational Com onents The specification requires that a sufficient number of reactor coolant pumps be operating to provide coast down core cooling in the event that a loss of flow occurs. The flow provided will keep DNBR well above 1.30. When the boron concentration of the Reactor Coolant System is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor.
Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place. The residual heat removal pump will circulate the reactor coolant system volume in approximately one half hour.
Each of the pressurizer safety valves is designed to relieve 293,330 lbs. per hr. of saturated steam at the valve set point.
Below 350 F and 450 psig in the Reactor Coolant System, the Residual Heat Removal System can remove decay heat and thereby control system temperature and pressure. If no residual heat were removed by any of the means available the amount of steam which could be generated at safety valve lifting,pressure would be less than the capacity of a single valve. Also, two safety valves have capacity gxeatpy than the maximum surge rate resulting from complete loss of load.
The 50'F limit on maximum differential between steam, generator secondary water temperature and reactor coolant temperature assures that the pressure transient caused by starting a reactor coolant pump when cold leg temperature is < 275,'F can be relieved by operation of one Power Operated Relief Valve (PORV). The 50 F limit iricludes instrument error.
- 2. Pressure/Tem erature Limits All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categoxies of load cycles used fox design purposes axe provided in B3.1-4 11/20/78
BASES FOR LIMITING CONDITIONS OF OPERATION OVERPRESSURE MITIGATING SYSTEM The operability of two PORV's or an RCS vent opening of greater than or equal to 2.20 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 cold legs are < 275 F."
Either PORV has adequate relieving capability to protect the RCS from overpressurizat9on when the transient is limited to either (1) the start of an idle RCS with the secondary water temperature of the steam generator < 50'F above the RCS cold leg temperature (includes margin for instrument error) or (2) the start of a HPSI pump and its injection into a water solid RCS.
B3. 14-1 11/20/78
B4. 15 BASES FOR SURVEILLANCE RE UIREMENTS OVERPRESSURE MITIGATING SYSTEM The specified testing of the Overpressure Mitigating System (OMS) will verify its operability. The capacity of one pressurizer Power Operated Relief Valve is sufficient to relieve potential overpressure transients when the RCS is in the low temperature overpressure protection range. Proper functioning of the OMS combined with selected administrative controls will demonstrate the integrity of the system.
B4.15-1
STATE OF FLORXDA )
) ss COUNTY OF'ADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is. authorized to execute the document on behalf of said Licensee.
Robert E.. Uhrig Subscribed and sworn to before me this day of l9 78 NOTARY PUBLIC, and for the county of Dade,
-State of Florida NOTAI rlJQLID GTAiE Dt'LDGIDA GT tA'GGG WY CO.'~V,.S .OH OV nGS t.V,GCH n',
Ny commission expires GONG 9 TftGlj MAY.':AAD CON NG AGB;CY tSaZ
