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| {{#Wiki_filter:ITABLE3.7-2Continued SAFETYRELATEDHYDRAULIC SNUBBERS* | | {{#Wiki_filter:I TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS* |
| FPLLOCATIONHARKNO.NO.SYSTEMSNUBBERINSTALLED ACCESSIBLE ORONLOCATIONANDELEVATION INACCESSIBLE AorIHIGHRADIATION ZONE**YesorNoESPECIALLY DIFFICULT TOREMOVEYesorNo033034036037038039040041042043044047HS649-319HS548-5HS649-314HS649-314HS649-310HS649-304AHS548-9NS548-9BF549-7BF549-7BF549-8BF549-17HS,HS,MS,HS,MS,HS,HS,HS,BF,BF,BF,BF,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,ReactorBldg.,Elev.,82'lev.82'lev.55'lev.55'lev.50'lev.30'lev.50'lev.50'lev.40'lev.40'lev.40'lev.36'AIIIAIIIIIANoNoNoNoNoNoNoNoNoNoNoNoNoYesYesYesNoNoYesYesCOC7 TABLE3.7-2Continued SAFETYRELATEDHYDRAULIC SNUBBERS*
| | FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE A or I Yes or No Yes or No 033 HS 649-319 HS, Reactor Bldg., El ev., No No 82'lev. |
| FPLLOCATIONHARKNO.NO.SYSTEMSNUBBERINSTALLED ACCESSIBLE ORONLOCATIONANDELEYATIONINACCESSIBLE AorIHIGHRADIATION ZONE**YesorNoESPECIALLY DIFFICULT TOREMOVEYesorNo052BF549-17BF,ReactorBldg.,Elev.36'53SI968-210SI,ReactorBldg.,Elev.16'58SI969-1216SI,ReactorBldg.,Elev.18'ANoNoNoNoNo
| | 034 HS 548-5 HS, Reactor Bldg., A No No I |
| 'ql TABLE3.7-2Continued SAFETYRELATEDHYDRAULIC SNUBBERS* | | 82'lev. |
| FPLLOCATIONMARKNO.NO.SYSTEMSNUBBERINSTALLED ACCESSIBLE ORONLOCATIONANDELEVATION INACCESSIBLE (AorI)HIGHRADIATION ESPECIALLY DIFFICULT ZONE**TOREMOVE(YesorNo(YesorNo081SI676-67SI,RAB,Elev.4'82SI676-67SI,RAB,Elev.4'83SI676-105SI,RAB,Elev.4'AANoNoNoNoNoNo
| | 036 HS 649-314 MS, Reactor Bldg., No No 55'lev. |
| >>NIr.~il TABLE3.7-2Continued SAFETYRELATEDHYDRAULIC SNUBBERS* | | 037 HS 649-314 HS, Reactor Bldg., I No 55'lev. |
| FPLLOCATIONMARKNO.NO.SYSTEMSNUBBERINSTALLED ACCESSIBLE ORHIGHRADIATION ESPECIALLY DIFFICULT ONLOCATIONANDfLEYATIONINACCESSIBLE ZONE**TOREMOYEAorIYesorNoYesorNo084SI676-105SI,RAB,Elev.4'12SI676-4505SI,RAB,Elev.7'ANoNotDCOC)
| | 038 HS 649-310 MS, Reactor Bldg., I No No 50'lev. |
| TABLE3.7-2Continued SAFETYRELATEDHYDRAULIC SNUBBERS*
| | 039 HS 649-304A HS, Reactor Bldg., A No Yes 30'lev. |
| FPLLOCATIONHARKNO.NO.SYSTEMSNUBBERINSTALLED ACCESSIBLE OR-HIGHRADIATION ESPECIALLY DIFFICULT ON,LOCATIONANDELEVATION INACCESSIBLE ZONE**.TOREMOYEAorIYesorNoYesorNo102HS-649-313 CC,RAB,Elev.26'No VVn SAFETY'EVALUATION Re:St.LucieUnit1DocketNo.50-335SnubbersI.Introduction Thisevaluation supportsaproposedchangetoTable3.7-2(SAFETYRELATEDHYDRAULIC SNUBBERS).
| | 040 HS 548-9 HS, Reactor Bldg., I No Yes 50'lev. |
| Severalsnubbersonthelistaredeletedbecausetheyarescheduled tobereplacedbymechanical snubbersduringthenextrefueling outage(Spring1980).Onlysmallersnubbersofthe3kip(3000inch-pounds) and10kipsizewillbeaffectedbythechangeover (seeattachedlist)-II.Evaluation Thesnubbersinquestionaredesignedandinstalled forseismicconsiderations.
| | 041 NS 548-9 HS, Reactor Bldg., I No Yes 50'lev. |
| Thatis,theirdesignfunctionistoaccommodate pipemovementcausedbyslowthermalexpansion, butto"lock-up" topreventpotentially damagingtransient movementduringapostulated seismiceventofsufficie'nt magnitude.
| | 042 BF 549-7 BF, Reactor Bldg., I No 40'lev. |
| ThePacificScientific (PSA)mechanical snubberswhichweproposetouseoperateonan"acceleration limiting" basis.PSAsnubberspermitthermalmovementsincetheacceleration
| | 043 BF 549-7 BF, Reactor Bldg., I No No 40'lev. |
| .associated withthermalmovementisverylow,buttheylimitseismicinducedacceleration to0.02g..Mechanical snubberswouldactuallyallowlessmovementthanhydraulic snubbersunderseismicconditions because
| | 044 BF 549-8 BF, Reactor Bldg., I Yes 36' 40'lev. |
| ~g~k~~~~' | | 047 BF 549-17 BF, Reactor Bldg., A Yes CO C7 |
| ofhydraulic snubberlockupdelaysassociated withachieving-thelockupvelocity, activation ofthelockupmechanism, andcompression ofthehydraulic fluid.Therefore, basedonseismicfunctional requirements, theplannedreplacement ofhydraulic snubberswithmechanical snubberswouldbeanimprovement.
| | |
| PacificScientific performed extensive testingindeveloping thePSA3(3kip)andPSA10mechanical sriubbers.
| | TABLE 3. 7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS* |
| Thepurposewastoevaluatetheiroperability undertheadverseconditions expectedinmanyapplications, suchashighhumidity, hightemperature, andvibration.
| | FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEYATION INACCESSIBLE ZONE** TO REMOVE A or I Yes or No Yes or No 052 BF 549-17 BF, Reactor Bldg., Elev. 36'53 No No SI 968-210 SI, Reactor Bldg., Elev. 16'58 No SI 969-1216 SI, Reactor Bldg., Elev. 18' A No No |
| Thesnubbersoperatedfavorably underalltestconditions.
| | |
| PSA3andPSA10mechanical snubbersarecurrently inuseatSt.Lucie(seeAmendment 31toFacilityOperating LicenseDPR-67)andatalargenumberofotherreactorsites.Theuseofthesesnubbershasbeenpreviously evaluated bytheCommission andfoundtobeacceptable.
| | 'ql TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS* |
| III.Conclusions Basedontestingandoperating experience, theuseofPSAmechanical snubbersshouldimprovetheoperability oftheseismicsupportsystem.Inconclusion, (1)theproposedchangedoesnotincreasetheprobability orconsequences ofaccidents ormalfunctions ofequipment important tosafetyanddoesnotreducethemarginofsafetyasdefinedinthebasisforanytechnical specification, therefore, thechangedoesnotinvolveasignificant hazardsconsideration, (2)thereisreasonable assurance thatthehealthandsafetyofthepublicwillnotbeendangered by operation intheproposedmanner,and(3)suchactivities willbeconducted incompliance withtheCommission's regulations andthe-issuanceofthisamendment willnotbeinimicaltothecommondefenseandsecurityortothehealthandsafetyofthepublic. | | FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE (A or I) (Yes or No (Yes or No 081 SI 676-67 SI, RAB, Elev. No No 4'82 SI 676-67 SI, RAB, Elev. A No No Elev. 4' 4'83 SI 676-105 SI, RAB, A No No |
| ~~rSnubberChaneoutPSLThefolios(ing hydraulic snubbersarescheduled tobereplacedbymechanical snubbersduringtheSpring1980refueling outage:V3KipSize10KipSizeTagNo.HarkNo.TagNo.HarkNo.035061066073.074076077079080086087088089090091092093096106107110111114HS-1076-3164 HS-549-11 (SI-970-1248) | | |
| HS-549-11(S I-970-.1248) | | >> N Ir .~ |
| SI-972-6240 SI-973-240 SI-973-6224 SI-868-64 SI-868-163 SI-868-410 SI-676-129 SI-676-241(SI-676-250) | | il |
| CC-1899-48 CC-1852-6241 SPS-27SPS-417SPS-467SPS-777CC-1865-9 CH-3-40CH-3-75SI-676-247(SI-676-2475) | | |
| SI-676-247 5ASI>>972-6240 101103104105CC-17-1CC-21-5CC-21-1CC-23-2 0iPc4l'I~,t}}
| | TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS* |
| | FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND fLEYATION INACCESSIBLE ZONE** TO REMOYE A or I Yes or No Yes or No 084 SI 676-105 SI, RAB, Elev. No Elev. 7' 4'12 SI 676-4505 SI, RAB, A No tD CO C) |
| | |
| | TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS* |
| | FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR - |
| | HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE**. TO REMOYE A or I Yes or No Yes or No 102 HS-649-313 CC, RAB, Elev. 26' No |
| | |
| | V V n |
| | |
| | SAFETY 'EVALUATION Re: St. Lucie Unit 1 Docket No. 50-335 Snubbers I. Introduction This evaluation supports a proposed change to Table 3.7-2 (SAFETY RELATED HYDRAULIC SNUBBERS). Several snubbers on the list are deleted because they are scheduled to be replaced by mechanical snubbers during the next refueling outage (Spring 1980). Only smaller snubbers of the 3 kip (3000 inch-pounds) and 10 ki p size will be affected by the changeover (see attached list)- |
| | II. Evaluation The snubbers in question are designed and installed for seismic considerations. That is, their design function is to accommodate pipe movement caused by slow thermal expansion, but to "lock-up" to prevent potentially damaging transient movement duri ng a postulated seismic event of sufficie'nt magnitude. The Pacific Scientific (PSA) mechanical snubbers which we propose to use operate on an "acceleration limiting" basis. PSA snubbers permit thermal movement since the acceleration . |
| | associated with thermal movement is very low, but they limit seismic induced acceleration to 0.02g.. Mechanical snubbers would actually allow less movement than hydraulic snubbers under seismic conditions because |
| | |
| | ~ g ~ |
| | k |
| | ~ ~ |
| | ~ ~ ' |
| | |
| | of hydraulic snubber lockup delays associated with achieving- the lockup velocity, activation of the lockup mechanism, and compression of the hydraulic fluid. Therefore, based on seismic functional requirements, the planned replacement of hydraulic snubbers with mechanical snubbers would be an improvement. |
| | Pacific Scientific performed extensive testing in developing the PSA 3 (3 kip) and PSA 10 mechanical sriubbers. The purpose was to evaluate their operability under the adverse conditions expected in many applications, such as high humidity, high temperature, and vibration. |
| | The snubbers operated favorably under all test conditions. |
| | PSA 3 and PSA 10 mechanical snubbers are currently in use at St. Lucie (see Amendment 31 to Facility Operating License DPR-67) and at a large number of other reactor sites. The use of these snubbers has been previously evaluated by the Commission and found to be acceptable. |
| | III. Conclusions Based on testing and operating experience, the use of PSA mechanical snubbers should improve the operability of the seismic support system. |
| | In conclusion, (1) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margi n of safety as defined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by |
| | |
| | operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the-issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public. |
| | |
| | ~ |
| | r ~ |
| | Snubber Chan eout PSL The folios(ing hydraulic snubbers are scheduled to be replaced by mechanical snubbers during the Spring 1980 refueling outage: |
| | V 3 Kip Size 10 Kip Size Tag No. Hark No. Tag No. Hark No. |
| | 035 HS-1076-3164 101 CC-17-1 061 HS-549-11 (S I-970-1248) 103 CC-21-5 066 HS-549-11(S I-970-.1248) 104 CC-21-1 073 . SI-972-6240 105 CC-23-2 074 SI-973-240 076 SI-973-6224 077 SI-868-64 079 SI-868-163 080 SI-868-410 086 SI-676-129 087 SI-676-241(SI-676-250) 088 CC-1899-48 089 CC-1852-6241 090 SPS-27 091 SPS-417 092 SPS-467 093 SPS-777 096 CC-1865-9 106 CH-3-40 107 CH-3-75 110 SI-676-247(SI-676-2475) 111 S I-676-247 5A 114 SI>>972-6240 |
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| | 0 iP c 4 l |
| | 'I |
| | ~,t}} |
|
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17228B5041996-06-0101 June 1996 Proposed Tech Specs Re Thermal Margin & RCS Flow Limits ML17228B3761996-01-0404 January 1996 Proposed Tech Specs Rectifying Discrepancy for Each St Lucie Unit & Providing Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3361995-11-22022 November 1995 Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15 ML17228B2451995-08-16016 August 1995 Proposed TS 3.6.6.1, Sbvs. ML17228B2421995-08-16016 August 1995 Proposed Ts,Reflecting Relocation of Selected TS Requirements Re Instrumentation & Emergency & Security Plan Review Process,Per GL 93-07 ML17228B1891995-06-21021 June 1995 Proposed Tech Specs Re Safety Injection Tank Surveillances ML17228B1811995-06-21021 June 1995 Proposed Tech Specs Re Time Allowed to Restore Inoperable LPSI Train to Operable Status ML17228B1791995-06-21021 June 1995 Proposed Tech Specs Re Extended Allowed Outage Time for EDGs ML17228B1471995-05-17017 May 1995 Proposed Tech Specs,Extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1441995-05-17017 May 1995 Proposed Tech Specs Re Administrative & Conforming Update ML17228B0901995-04-0303 April 1995 Proposed Tech Specs Re Incorporation of line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 for Licenses DPR-67 & NPF-16 ML17228B0591995-02-27027 February 1995 Proposed TS Re Sdcs Min Flow Rate Requirements ML17228B0521995-02-27027 February 1995 Proposed Tech Spec Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relays ML17228B0331995-02-22022 February 1995 Proposed TS 4.6.1.3,reflecting Deletion of Refs to Automatic Tester for Containment Personnel Air Lock ML17228A9921995-01-20020 January 1995 Proposed Tech Specs,Relocating Operability Requirements for Incore Detectors to (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillance 4.10.2.2,4.10.4.2 & 4.10.5.2 ML17228A9031994-11-0202 November 1994 Proposed Tech Specs 3/4.6.2.1 & 3/4.6.2.3,adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17228A8911994-10-27027 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML17228A6521994-07-28028 July 1994 Proposed Tech Specs Re LTOP Requirements for Power Operated Relief Valves,Per GL 90-06 ML17228A6591994-07-25025 July 1994 Proposed Tech Specs Implementing Enhancements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6561994-07-25025 July 1994 Proposed Tech Specs for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5771994-05-23023 May 1994 Proposed Tech Specs Removing Option That Allows HPCI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-06-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] |
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I TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS*
FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE A or I Yes or No Yes or No 033 HS 649-319 HS, Reactor Bldg., El ev., No No 82'lev.
034 HS 548-5 HS, Reactor Bldg., A No No I
82'lev.
036 HS 649-314 MS, Reactor Bldg., No No 55'lev.
037 HS 649-314 HS, Reactor Bldg., I No 55'lev.
038 HS 649-310 MS, Reactor Bldg., I No No 50'lev.
039 HS 649-304A HS, Reactor Bldg., A No Yes 30'lev.
040 HS 548-9 HS, Reactor Bldg., I No Yes 50'lev.
041 NS 548-9 HS, Reactor Bldg., I No Yes 50'lev.
042 BF 549-7 BF, Reactor Bldg., I No 40'lev.
043 BF 549-7 BF, Reactor Bldg., I No No 40'lev.
044 BF 549-8 BF, Reactor Bldg., I Yes 36' 40'lev.
047 BF 549-17 BF, Reactor Bldg., A Yes CO C7
TABLE 3. 7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS*
FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEYATION INACCESSIBLE ZONE** TO REMOVE A or I Yes or No Yes or No 052 BF 549-17 BF, Reactor Bldg., Elev. 36'53 No No SI 968-210 SI, Reactor Bldg., Elev. 16'58 No SI 969-1216 SI, Reactor Bldg., Elev. 18' A No No
'ql TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS*
FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE (A or I) (Yes or No (Yes or No 081 SI 676-67 SI, RAB, Elev. No No 4'82 SI 676-67 SI, RAB, Elev. A No No Elev. 4' 4'83 SI 676-105 SI, RAB, A No No
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TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS*
FPL LOCATION MARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON LOCATION AND fLEYATION INACCESSIBLE ZONE** TO REMOYE A or I Yes or No Yes or No 084 SI 676-105 SI, RAB, Elev. No Elev. 7' 4'12 SI 676-4505 SI, RAB, A No tD CO C)
TABLE 3.7-2 Continued SAFETY RELATED HYDRAULIC SNUBBERS*
FPL LOCATION HARK SYSTEM SNUBBER INSTALLED ACCESSIBLE OR -
HIGH RADIATION ESPECIALLY DIFFICULT NO. NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE**. TO REMOYE A or I Yes or No Yes or No 102 HS-649-313 CC, RAB, Elev. 26' No
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SAFETY 'EVALUATION Re: St. Lucie Unit 1 Docket No. 50-335 Snubbers I. Introduction This evaluation supports a proposed change to Table 3.7-2 (SAFETY RELATED HYDRAULIC SNUBBERS). Several snubbers on the list are deleted because they are scheduled to be replaced by mechanical snubbers during the next refueling outage (Spring 1980). Only smaller snubbers of the 3 kip (3000 inch-pounds) and 10 ki p size will be affected by the changeover (see attached list)-
II. Evaluation The snubbers in question are designed and installed for seismic considerations. That is, their design function is to accommodate pipe movement caused by slow thermal expansion, but to "lock-up" to prevent potentially damaging transient movement duri ng a postulated seismic event of sufficie'nt magnitude. The Pacific Scientific (PSA) mechanical snubbers which we propose to use operate on an "acceleration limiting" basis. PSA snubbers permit thermal movement since the acceleration .
associated with thermal movement is very low, but they limit seismic induced acceleration to 0.02g.. Mechanical snubbers would actually allow less movement than hydraulic snubbers under seismic conditions because
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of hydraulic snubber lockup delays associated with achieving- the lockup velocity, activation of the lockup mechanism, and compression of the hydraulic fluid. Therefore, based on seismic functional requirements, the planned replacement of hydraulic snubbers with mechanical snubbers would be an improvement.
Pacific Scientific performed extensive testing in developing the PSA 3 (3 kip) and PSA 10 mechanical sriubbers. The purpose was to evaluate their operability under the adverse conditions expected in many applications, such as high humidity, high temperature, and vibration.
The snubbers operated favorably under all test conditions.
PSA 3 and PSA 10 mechanical snubbers are currently in use at St. Lucie (see Amendment 31 to Facility Operating License DPR-67) and at a large number of other reactor sites. The use of these snubbers has been previously evaluated by the Commission and found to be acceptable.
III. Conclusions Based on testing and operating experience, the use of PSA mechanical snubbers should improve the operability of the seismic support system.
In conclusion, (1) the proposed change does not increase the probability or consequences of accidents or malfunctions of equipment important to safety and does not reduce the margi n of safety as defined in the basis for any technical specification, therefore, the change does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by
operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the-issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
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Snubber Chan eout PSL The folios(ing hydraulic snubbers are scheduled to be replaced by mechanical snubbers during the Spring 1980 refueling outage:
V 3 Kip Size 10 Kip Size Tag No. Hark No. Tag No. Hark No.
035 HS-1076-3164 101 CC-17-1 061 HS-549-11 (S I-970-1248) 103 CC-21-5 066 HS-549-11(S I-970-.1248) 104 CC-21-1 073 . SI-972-6240 105 CC-23-2 074 SI-973-240 076 SI-973-6224 077 SI-868-64 079 SI-868-163 080 SI-868-410 086 SI-676-129 087 SI-676-241(SI-676-250) 088 CC-1899-48 089 CC-1852-6241 090 SPS-27 091 SPS-417 092 SPS-467 093 SPS-777 096 CC-1865-9 106 CH-3-40 107 CH-3-75 110 SI-676-247(SI-676-2475) 111 S I-676-247 5A 114 SI>>972-6240
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