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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4511996-04-24024 April 1996 Proposed Tech Specs 3.11.B/4.11.B Re Crescent Area Ventilation ML20101H6741996-03-27027 March 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101H3821996-03-22022 March 1996 Proposed TS Table 3.2-2 Re Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20101F8411996-03-22022 March 1996 Proposed Tech Specs,Implementing BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20097A2271996-02-0101 February 1996 Proposed Tech Specs,Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2991996-01-25025 January 1996 Proposed Tech Specs Re EDGs Surveillance Testing ML20097J6691996-01-25025 January 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24- Month Operating Cycles ML20095F7091995-12-14014 December 1995 Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code ML20094R6981995-11-30030 November 1995 Proposed Tech Specs,Extending Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6641995-10-25025 October 1995 Proposed Tech Specs Extending Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5401995-09-15015 September 1995 Proposed Tech Specs Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6561995-07-21021 July 1995 Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] |
Text
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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO CONTAIhMENT ISOLATION
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR P0'elER PLANT DOCKET NO. 50-333 FEBRUARY 2, 1980 1945 042
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Pn Y19 9 PT FTT f *rt Pt hTT e a tt e; PS T19 tY rM A f =es NT 0%nbers la parentteses are hered to cus'cre on fallwing pegeen elgral co.:ee are listed on followirg pages)
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ra e s Location Foao r Drynll valve Tyg,e Clostra t o Cten Esf. to to Clm Isoletten Time Dereal Ramerke and it e tool.ted ren tretten ts) (5)<s) crm, Dr. veil (3)<s) sie .I (7) s ec e race,itec.
Core Sprer Mantes = t-2104.8 to Cate as s outsid. Ae ax w t applical,le Clee.4 Fw riew Core Spray to I 16A,9, to Cete Ac A Outelde Ac Not applicable Open
.ector EM ute (10) l Core sprar to 1-16 A , a to Cate Ac p
A outende Ac aM Raector hot arplicatile Closed vote (10) * (r J Core 8 prey to -ISA,s ao neck (1) A In sde Reacter note O) aav. flow Not applicable Closed Testable aeck valve wie (1,te)
Core 8 peer Test to I-!!ca,a toclde Ac 3 Outelde Ac G,De 43 Sec 8.ppreestce tool Closed Care Spray F w 1 217A,3 PO Cate Ac 5 Outelde Ac R;1 Eactism hot applicable Open CC Drywe ll Equip =s a.t Z-19 ho Flug Ac 3 Insida
- Ac A.F.EM 33 Sec Opea Drat o Swas, Discta rge
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Dryvsil Equireent 1-19 A0 Flug Air /Ac 3 Outelde 8prira A.F,aN Nct a;plicable Closed (17)
Dreta Samp Ctecharge Cr C
Drywell Floor D sfo I-18 ed Flug So., ci e c t.. r s e Ac 3 lastie As A F,tM 33 sec Open b g
CD -
A Drywell Floor Crato I-14 AO Flug Air /Ac 3 Outelde Sprics A .F.Dt Niat epplic able Open Sway Elect.arge Note (18) i Travoltog Incore I-35A,3,C,0 Implosive Dc & Outelde De Probe thest De Not applicable Open One valve se sach line Travette-a locore I-351,B,C,D 80 tall Ac & Outelde Ac A,F,EV Pr et e Nt applicable Opea One valve on each llae Mte (14) f Travoltog incore I-35B Check Fud flow & Outelde
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Process tev, tiew Not applicable Closed Frobe Furge EPCI - Turbine I-Il M0 Cate Ac & Inside Ac Staae 9 pply L.EM 20 Sec Opea ) Sigral "G" opeas velve.
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EPCI - Turbine I-Il M0 Cete ) closes valve, Dc & Outelde Dc l tM 20 sec closeJ)
Steam Supply
- x. ens ne No. es , jd 201 Drywell Floor Manual Drain Sump X-18 Gate Manual B Outside Manual NA Note (18) Closed Note (18)
Discharge Drywell Floor.
Drain Sump X-18 M0 Gate AC B Outside AC A,F 30 Sec Open Note (18) 1
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JAFNPP ,.
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~* NOTES FOR T*GLE 3.7.1 (CONT'D)
- 9. ,
- 10. Coincident signals "C' and "T" open valves. Special fnterlocks permit testing these valves by manual switch except when automatic signals are present.
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- 11. Normal status position of valve (open or closed) is the
. - position during normal power operation of the reactor
(see " Normal Status" colura) .
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- 12. The specified closure rates are as required for
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containment isolation only.
- 13. Minimum closing time is' based on valve and line size.
- 14. Signal "A" or "F" causes automatic withdrawals of TIP probe. When probe is withdrawn, the valve automatically clo::es by mechanical action.
- 15. Reactor building ventilation exhaust high radiation m signal "Z" is generated by two trip untis. This 8 required one unit at high trip or both units at down O* ; scale (instrument failure) trip, in order to initiate isolation.
(l
- 16. Leak testing shall be accomplished in accordance with section ,
4.7.A.2.d.
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- 17. The valve opens during pir p out-of the drywell equipment sump.
Automatic isolaticn signals A and F override an open signal that might be present for su=p pts;p out.
8!
- 18. From Feb'ruary 2, 1980 until manual isolation valve RDW-77 is modified by installation of a power actuator (or until a power '
actuated valve is installed in place of RDN-77) the valve shall be maintained in the closed position except when pumping of the drywell floor drain sump is required.
Following modification of RDN-77 by installation of a power actuator (or replacement of the valve with a power operated valve) which utilizes the controls provided for isolation valve 20-MOV-82, the valve may be operated in the.same mode as that permitted for isolation valve 20-MOV-82 when that valve is fully operable.
From February 2,1980 until valve 20-MOV-82 is repaired and restored to a fully operable status it is exempted from the requirements of this Table.
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1945 044
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Amendment No. fD, /$ 4 of 4 d
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ATTACHMENT II SAFETY EVALUATION CONTAINMENT ISOLATION MODIFICATION 1
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 FEBRUARY 2, 1980 1945 045
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NUCLEAR SAFETY EVALUATION INTERIM OPERATION WITH VALVE 20-MOV-82 INOPERABLE Interim modification to primary containment boundary location to allow continued plant operation with the drywell floor drain sump discharge inboard isolation valve (20-MOV-82) electrically inoperable.
Plant Modification: F1 80-10 QA Category: I System Number: 20 (Radioactive Waste System)
Component: Pipe Designation 3"-WL-151-2 (Reference Figure 1)
Component
Description:
Piping Downstream of Outboard Primary Contain-ment Isolation Valve 20-A0V-83 Op to and Including Manual Isolation Valve RDW-77 Containment Penetration: X-18 A. DESCRIPTION
- 1) Background Drywell floor drain sump inboard isolation valve 20-MOV-82 has failed electrically in the open position during normal plant.
power operations. Valve 20-MOV-82 is located inside reactor containment, which is inerted with nitrogen and inaccessible during power operations. Section 3.7.D.2 of the James A.
FitzPatrick Nuclear Power Plant Technical Specifications states that in the event any isolation valve specified in Table 3.7-1 (Process Pipeline Penetrating Primary Containment) becomes in-operable, reactor power operation may continue, provided at least one (1) valve in the pipe line having the inoperable valve is in the mode corresponding to the isolation condition. Upon determining that the inboard isolation valve 20-MOV-82 was electrically inoperable in the open position, the outboard air-operated isolation valve 20-A0V-83 was shut.
Technical Specification Section 3.7.3 further states that if the requirements of Section 3.7.D.2 cannot be met, an orderly plant shutdown is to be initiated and the reactor placed in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 2) Problem Definition Because the contents of the drywell floor drain sump must be periodically pumped out of primary containment during normal plant operations, it is necessary to open the outboard isolation valve 20-A0V-83 for approximately 3 minutes out of every 100 minutes for the current sump accumulation rate.
1945 046
NUCLEAR SAFETY EVALUATION
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INTERIM OPERATION WITH VALVE 20-MOV-82 IN0PERABLE Page A. DESCRIPTION
- 2) Problem Definition - Continued This is undesirable from the standpoint of primary containment isolation because a single active component failure of the operable isolation valve (20-A0V-83) could prevent its closing, thereby resulting in a loss of primary containment integrity.
Technical Specification requirement 3.7.D.1-3 allows the opening of outboard isolation valve 20-A0V-83 if the inboard isolation valve 20-MOV-82 is inoperable, provided it is reclosed or the reactor is in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3) Interim Modification (Phase I)
The Phase I interim solution upgrades the quality classification of the piping downstream of outboard isolation valve 20-A0V-83 up to and including the first manual isolation valve RDW-77 (approximately 8 feet of piping) and implements special operating procedures in order to provide a redundant isolation feature.
A design review was conducted of the piping and manual valve (RDW-77) downstream of 20-A0V-83 and it was determined that the design criteria, installation procedures, and NDE requirements were identical to those utilized for the piping between the existing drywell isolation valves (20-MOV-82 and 20-A0V-83). In addition, seismic analysis of the piping up to and including the supports downstream of manual valve RDW-77 has been performed and satisfies the requirement that this piping would be operable following a seismic event. '
A Type "C" Local Leak Rate Test has been performed on the downstream piping in order to confirm that the addition of the piping to the containment boundary would not cause an unacceptable containment leak rate which could exceed 10CFR100 requirements as implemented by Technical Specifications. The results of this Type "C" test have been analyzed and confirm that the additional measured leakage is within the acceptance criteria established by the existing plant Technical Specifications for the combined leakage rate for all penetrations and valves subject to Type "B" and Type "C" tests.
Special operating procedures implemented as part of the Phase I interim modification includes the following:
a) The new isolation boundary established at manual isolation valve RDW-77 will remain isolated at all times except when the drywell floor drain sump is being pumped out (approximately 3 minutes out of every 100 minutes.)
b) An operator equipped with a dedicated communications ;ircuit is stationed at the manual valve during the pump out period. If containment iso'ation should be required during these short periods, the operator is instructed from the Control Room to immediately shut the manual isolation valve RDW-77.
The closing time of RDW-77 is approximately 16 seconds.
. . 1945 047
NUCLEAR SAFETY EVALUATION
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INTERIM OPERATION WITH VALVE 20-MOV-82 IN0PERABLE Page A. DESCRIPTION
- 4) Interim Modification (Phase II)
The Phase II solution upgrades the Phase I solution in that a motor-operator /or a new motor operated valve, is to be installed in place of manual valve RDW-77. The design on Phase II is in progress and will include additional seismic analysis to include the additional mass of a motor operator.
Electrical circuits and wiring included as part of the motor operator installation will be in accordance with the require-ments for Class 1E electrical systems.
B. JAFNPP FSAR REVIEW Section 5 (Containment System) of the JAFNPP Final Safety Analysis Report was reviewed to determine those areas affected by the implementation of this modification. There are no changes required to the assumptions used in the FSAR or other safety analysis reports by the implementation of this modification. Because the second isolation boundary during the interim pericd is provided by a valve external in location to the existing outboard isolation valve, Doth isolation boundaries are external to the primary containment. This is cnsidered acceptable as long as the piping external to the out-boaro isolation valve has an integrity at least equal to the contain-ment. From a piping design and support point of view, the sump pump discharge pipe (3"-WL-151-2) has an integrity at least equal to the '
containment. This change on an interim t' asis for the case of the sump pump discharge line does not change assumptions stated in FSAR.
It is further noted that a similar arrangement of primary containment isolation valves exists in other JAF systems.
JAFNPP Technical Specifications, Section 3.7 was reviewed. The safety aargins defined in the bases of the Technical Specifications are not reduced by the implementation of this modification.
C. SAFETY ANALYSIS CONCLUSIONS
- 1) The implementation of this interim modification does not increase the probability of occurence or consequences of an accident evaluated in the JAFNPP Final Safety Analysis Report or other safety analysis reports.
- 2) The implementation of this interim modification does not create the probability of an accident or malfunction of a different type than any previously evaluated.
- 3) The implementation of this interim modification does not reduce the margin of safety as defined in the bases of the JAFNPP Technical Specifications.
1945 048
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NUCLEAR SAFETY EVALUATION INTERIM OPERATION WITH VALVE 20-MOV-82 INOPERABLE Page C. SAFETY ANALYSIS CONCLUSIONS
- 4) The implementation of this interim modification does not constitute an unreviewed safety question pursuant to 10 CFR 50.59.
Prepared by: Date
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YAc'~d m A'1 tf a lA 20
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VictorM.Walz,'Electrig Maintenance Engineer Reviewed by: Date e %~?\ \.r.\u e 'lfk?O Robert Baker, Maintenance Superintendent
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1945 049
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