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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML20198H9941997-12-29029 December 1997 SE Supporting Approval of Application Re Long Island Power Authority Aquisition of Long Island Lighting Co,Subject to Discussed Condition ML20197C4771997-01-0303 January 1997 Safety Evaluation Supporting Nine Mile Point Unit 1 Reactor & Turbine Building Blowout Panels ML20197C4541997-01-0202 January 1997 Safety Evaluation Supporting Resolution of Nine Mile Point Reactor/Turbine Building Pressure Relief Panel Outside Design Basis Issue ML20056H4751993-08-27027 August 1993 Safety Evaluation Accepting Licensee Proposal for Continued Insp & Repair of Flaw in Weld Joining HPCS Nozzle Safe to safe-end Extension ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20245J0751989-04-25025 April 1989 Safety Evaluation Supporting Amends 114,30,141 & 33 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20205R1311988-10-31031 October 1988 Safety Evaluation Supporting Amend 101 to License DPR-63 ML20205Q5721988-10-31031 October 1988 SER Re Const Mod & Licensing of Company Facility-1 Cpdf. Licensee Technically Qualified to Modify Existing Facility in Such Way as to Assure Adequate Protection of Common Defense & Security ML20205Q5761988-10-31031 October 1988 SER Re Application for CP for Alchemie Facility-2 Oliver Springs.Licensee Technically Qualified to Construct & Operate Proposed Facility in Such Way as to Assure Adequate Protection for Common Defense & Security ML20205M5731988-10-26026 October 1988 Safety Evaluation Supporting Amends 108,25,134 & 26 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20155G4801988-09-28028 September 1988 Safety Evaluation Supporting Amends 107,23,132 & 24 to Licenses DPR-61,DPR-21,DPR-65 & NPF-24,respectively ML20195G5531988-06-24024 June 1988 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pools from Criticality Standpoint.Enrichment of Fuel to 4.5 Weight % U-235 May Be in Conflict W/ 10CFR51 Table S4 & Should Be Investigated by NRC ML20154H2171988-05-18018 May 1988 Safety Evaluation Accepting Util 880414 Submittal Re Reload Startup Physics Test Program ML20147D9631988-02-25025 February 1988 Safety Evaluation Accepting Util 860404 Evaluation of Environ Qualification of Equipment Considering Superheat Effects of high-energy Line Breaks for Plants,Per IE Info Notice 84-90 ML20147E9261988-02-23023 February 1988 Safety Evaluation Supporting Amends 100,14,125 & 15 to Licenses DPR-61,DPR-21,DPR-65 & NPF-45,respectively ML20236M9631987-11-0606 November 1987 Safety Evaluation Accepting Util Proposed ATWS Mitigating Sys Actuation Circuitry for Facilities,Per 10CFR50.62(c)(1) & Pending Final Resolution of Tech Spec Issue ML20236L2001987-10-30030 October 1987 Safety Evaluation Supporting Amends 11 to Licenses NPF-37 & NPF-66,respectively & Amend 1 to License NPF-72 ML20195G5501987-10-28028 October 1987 Safety Evaluation Accepting Proposed Reracking of Util Spent Fuel Storage Pool.Licensee May Be Required to Perform Addl Analyses to Verify Maint of Required Subcriticality If Staff Boraflex Studies Reveal Gap Development in Subj Boraflex ML20235A7331987-09-18018 September 1987 Safety Evaluation Re Installation of Alternate Rod Injection (ARI) Sys & Adequacy of Plant Reactor Coolant Recirculating Pump Trip (RPT) Sys,In Compliance W/Atws Rule 10CFR50.62. ARI & RPT Acceptable ML20195G5461987-08-21021 August 1987 Safety Evaluation Accepting Proposed Util Tech Specs Change to Increase Max Allowed Enrichment of Reload Fuel to 4.2 Weight % U-235 ML20236Y0221987-07-0808 July 1987 Safety Evaluation Clarifying Determination of Acceptability of Test Duration for Performance of Integrated Leak Rate Test at Plant ML20214M3361987-05-22022 May 1987 Safety Evaluation Supporting Util Rept Entitled, Rod Swap Methodology Rept for Startup Physics Testing ML20214M1491987-05-21021 May 1987 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 2) Re Established Interface W/Nsss or Vendors of Each Component of Reactor Trip Sys ML20153F3851987-05-0404 May 1987 SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21 ML20153F3671987-04-30030 April 1987 Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint ML20238C7121987-04-0808 April 1987 Safety Evaluation Concluding That Facility May Resume Operation W/O Leakage Control Sys But w/post-accident Leakage Mgt ML20207R6481987-03-11011 March 1987 Safety Evaluation Supporting Licensee Response to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification.Program Acceptable ML20212J4041987-03-0202 March 1987 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing. Licensee Meets NRC Position ML20212B5671987-02-24024 February 1987 Safety Evaluation Re Util Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Reliability On-Line Testing. Response Acceptable ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20211G4361987-02-14014 February 1987 Safety Evaluation Supporting Util 831110 Response to Generic Ltr 83-28,Item 4.5.2 Re on-line Testing for Reactor Trip Sys Reliability ML20153F3511987-02-0707 February 1987 Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21 ML20210T2571987-02-0606 February 1987 SER Re Util 850802 Submittal Describing Design Details of Steam Generator Blowdown & Auxiliary Steam Sys to Detect & Isolate High Energy Line Breaks.Sys Design Acceptable, However,Two Deviations from IEEE-STD-297 Criteria Apparent ML20210R2061987-02-0606 February 1987 Safety Evaluation Supporting Util 850517,0802,0823,1211 & 860429 Submittals Re Environ Effects of High Energy Line Breaks in Auxiliary Steam or Steam Generator Blowdown Sys. Design of Blowdown Sys Acceptable ML20238C6501987-02-0505 February 1987 Safety Evaluation Accepting MSIVs for Facility Operation Up to First Refueling,Contingent on Successful Completion of Preoperational Tests & Prototype Testing Program.Briefing for Commissioner Asselstine Re MSIVs & SALP Input Also Encl ML20238C5801987-02-0202 February 1987 Safety Evaluation Concluding That Facility May Resume Startup Testing & Operation for First Operating Cycle W/ Installed Refurbished Msivs.Necessity of Addl Leak Testing to Be Determined After Review of Prototype Test Results ML20209B1511987-01-28028 January 1987 SER Supporting Util Responses to Generic Ltr 83-28,Item 4.5.2 Re Reactor Trip Sys on-line Testing ML20209C3571987-01-23023 January 1987 SER Supporting Facility Design,Per Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability,On-Line Testing ML20209C2151987-01-21021 January 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges ML20215E0061986-12-12012 December 1986 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.1 (Part 1) Re Equipment Classification of Reactor Trip Sys Components ML20214J9911986-11-24024 November 1986 SER Re Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) on Equipment Classification (Reactor Trip Sys Components) at Selected GE BWR Plants.Part 1 Requirements Met 1999-06-07
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated ML18040A3491998-07-0202 July 1998 LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1011998-06-24024 June 1998 LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML18040A3451998-06-0404 June 1998 LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML20247R1141998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20217B0621998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 1999-09-30
[Table view] |
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1 LNCLOSURE I l
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NUCLE AR REGULATORY COMMISSION
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- ...e SAFETY EVALUATION PEPORT TEOINICAt SPECIFICATION CHANGE REQUEST TO THE MSlv NIAGARA M0 HAWK POWER CORPORATION e Niht P!LE POINT UNIT ?
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DOCKET NO. 50 410 l
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1.0 INTRODUCTION
l by letters dated Morch 11, 1987 and April 7, 1987, Niagara Mohawk Power Corporation submitted a request for revision of the Technical Specifica-tions, Appendix A to Operating License NPF-54 for Nine Mile Point Unit 2 (hMP-2). The proposed changes would allow Niagara Mohawk to install new l Main Stean isolation Valves (MSlys) at NMP-2.
The MSIV's perfortn several functions such as Primary Containment isolation and Reactor Coolant pressure boundary. The installed MSIV's were originally 1
conceived to meet the Reactor Coolant pressure boundary function and '
improve upon the Primary Containment leas tightness performed previously by ball valves. Industry experience described in N'JREG-1169 indicates that MSIV leakage has been a concern. However, experience with the ball valves has shown that they have not functioned as well as anticipated.
Delamination of the tungsten carbide coating causes wearing between the seat and the ball which causes valve leakage. Packing leakage has also been a problem. Therefore, NMP-2 MSIV's were modified.
The modification includes cutting out the existing eight main steam isolation valves and replacing them with wye-pattern globe valves. The wye-pattern globe valves will meet all the same design criteria that the original design requires. For example, the design will neet safety related seismic, and environmental qualifications; and IEEE 279 requirements. The valves are being purchased from Gene <al Electric who normally supply the valves as part of the NSSS contract.
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. . tl i vat uAllt3 The Prutt'(.tinn Syltem slyndig that provide the trip 1 for the wyp. pattern MSIVs are the some signals utilized in the ball valve des 1gn. The power supplies are tne same non-Class lE 120VAC supplied by UPS3A (Trip System l A) and UPS3B (Trip System B). The design utilizes the same electrical protection assemblies (EPA), distribution panels and the same cables.
Tne f ail safe de-energize to operate lugic f unction, used for the bail Vol v rs , remains wi th the wye-pa ttern valves. This logic control circuitry utilizes relay logic (co11-to-contact) operation to assure that actuatior of a single emergency trip sensor (i.e. , one-out-of-two in trip system A or B) will not cause inadvertent closure of the MSIVs. This is consistent ith the original design basis of NMP-2 whereby the logic is set up as a one-out-of-two taken twice logic (i.e. , one-out-of-two in trip system A and B are required to close the MSIVs). For example, a tripped sensor (reactor low-low water level) provide open contacts to a logic function which Causes the sensor relay in the associoted trip channel to de-energize. The open contacts from the de-energized sensor relay are connected in logic functions which cause a trip relay to de-energize.
Output f rom the de-energized t.1p relays are cor. Joined in one-out-of-two taken tWiCe logic which generates closure signals for the main steam isolation valves.
I Each wye-pattern MSIV contains two electrically operated solenoid valves, d three way pilot solenoid valve with two coils ad a test solenoid valve.
The two pilot solenoid coils on a MSIV are fed f om different trip systems.
Sinc the two (2) trip pilot solenoid coils are sup) lied power from two (2) different trip systems and both trip systenis must de-energize to operate, a transfer and isolation scheme (ball valve) is not required on the wye-pattern valves. This change and tne standard General Electric l control scheme have reduced the number of field cables.
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The new wye-pattern globe valves will use a three pusition selection switch (close-out-test) and a pushbutton switch for each valve. These switches are located in the centrol room and are similar to the ball valve design. ,
Niagara Mohawk has requested that a revision be made to the NMP-2 Technical Spe'ification Tables 2.2.1-1, 3.6.1.2-1 and 3.6.3-1 to address the ins; llation of the new MSIVs. Table 2.2.1-1 has been changed to account l
for dif ferences in the physical configuration of the position indicating switches between the ball valves and the new wye-pattern globe valves.
Industry experience has indicated that the current Nominal Trip Setpoint ,
of less than or equal to 61 closed car.not be met with the mounting brackets on the globe valves. N1agara Mohawk has proposed that the MSIV -
Closure setpoint be less than or equal to 8% closed to allow margin for 1 i
field adjustment. A corresponding allowable value of less than or equal to 12% closed has also been proposed to account for drif t (allowable value). Table 3.6.1.2-1 and 3.6.3-1 have been changed to alter the valve l designations to provide consistent notation for the type of valve installed. )
Wye-pattern globe valves are used at the Perry Nuclear Power Plant in the same application and have been approved with setpoints identical to those requested for NMP-2. The staff has found that the change of setpoints is appropriate for wye-pattern globe MSIVs, changing of the valve designations is an administrative change.
3.0 CONCLUSION
Based on the above evaluation, the staff concludes that the iatest design modificatiurm made to the MSIVs did not change the actuation control system logic or power supplies and is consistent with the original design basis for NMP-7.. The M51V limit switch inputs to the Reactor Trip System logic remains unchanged from the ball valve design. However, the trip setpoint from the ball valve has been changed from 94% open to 92% cpen
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4..
for the wye-pattern valve. We reviewed this 27 difference in setpoint and the supporting analysis and find the trip setpoint of 8% acceptable.
The staff concludes that the changes comply with the applicable regulatory acceptance criteria including the requirements of IEEE 279. We also conclude that the changes to Tables 2.2.1-1, 3.6.1.2-1 and 3.6.3-1 in the l technical specifications are acceptable. ;
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ENCLOSURE 2 i
ICSB/ DBL SALP INPUT 1
PLANT: hine Mile Point Unit 2 LICEhSEE: Niagara Mohawk Puwer Corporation DOCKET N0: 50-410 LICENSEE STATUS: OR SER SUEJECT: TECHNICAL SPECIFICATION CHANGE PERF0PflANCE PARAMETERS:
s (1) Management involvement in Assuring Quality (2) Approach to Resolution of Technical issues From a Safety Standpoint (3) Response to NRC Initiatives (4) Staffing (including Management)
(5) Reporting and Analysis of Reportable Events (6) Training and Qualification Effectiveness (7) Any Other SALP Functional Area PERFORMANCE HARRATIVE DESCRIPTION OF CATEGORY /
PARAMETER APPLICANT / LICENSEE'S PERFORMANCE RATING 1 No basis for assessment N/A 2 Understanding of issue generally 2 apparent 3 Generally timely responses 2 4 thru 6 No basis for assessment N/A OVERALL APPLICANT / LICENSEE PERFORMAtiCE RATING 2 1
_ _ - _ . - - - _ - - __ _ - _ - _ _ _ _ _ _ _ _ _ _ _ - _ - - .)