|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings of Safety-Related Power-Operated Gate Valves ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20203B1941997-12-0404 December 1997 Supplemental SE Accepting Proposed Changes Which Are Consistent W/Recognized Battery Stds & Station Blackout Rule ML20148T8571997-07-0303 July 1997 SER Accepting Temporary Use of Current Procedure for Containment R/R Activities Instead of Requirements of Amended 10CFR50.55a Rule to Be Reasonable ML20137D4961997-03-24024 March 1997 Safety Evaluation of Second 10-year Interval Inservice Insp Program Plan Requests for Relief CR-17 & CR-18 Commonwealth Edison Co,Lasalle County Station,Units 1 & 2 ML20135D4661996-12-0606 December 1996 Safety Evaluation Granting Relief Request RP-01 & Alternative Testing Imposed Per 10CFR50.55a(f)(6)(i) Based on Impracticality of Performing Required Testing ML20129D9401996-09-26026 September 1996 SER Accepting Licensee Cycle 8 Core Reload Design Submittal Re Application of Anfb Critical Power Correlation to Coresident GE9 Fuel as Described in TR EMF-96-021(P),Rev 1 ML20059E2871993-12-30030 December 1993 Safety Evaluation Supporting Amends 57,57,45,45,93,77,152 & 140 to Licenses NPF-37,NPF-66,NPF-72,NPF-77,NPF-11,NPF-18, DPR-39 & DPR-48 Respectively ML20128E4101992-12-0101 December 1992 Safety Evaluation Accepting Relief Requests RI-22 & RI-23 from ASME Code Requirements from Hydrostatic Pressure Testing Following Replacement of RCIC Steam Supply Inboard Isolation Valve as Part of ISI Program ML20059N0301990-08-22022 August 1990 Safety Evaluation Accepting Util Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping ML20154E5461988-09-0707 September 1988 Safety Evaluation Supporting Amends 60 & 40 to Licenses NPF-11 & NPF-18,respectively ML20151X0121988-08-16016 August 1988 Safety Evaluation Re Inservice Testing Program & Requests for Relief ML20237C8761987-12-16016 December 1987 Safety Evaluation Supporting Facility IGSCC Insp,Per Generic Ltr 84-11 ML20237C9091987-12-16016 December 1987 Safety Evaluation Supporting Licensee Response to IE Bulletin 79-26,Rev 1, Boron Loss from BWR Control Blades, Per License Condition 2.C(6) ML20205R6681987-04-0101 April 1987 Safety Evaluation Supporting Continued Use of Static O-Ring Differential Pressure Switches ML20211P2551986-12-15015 December 1986 Safety Evaluation Supporting Util Compliance W/License Condition 2.C.(25)(d) Requirements Re Mods to Six Fire Door Stops ML20214U8501986-12-0404 December 1986 Safety Evaluation Re Util 861006 Response to IE Bulletin 79-26,Rev 1, Boron Loss from BWR Control Blades, to Satisfy License Condition 2.C(13).Response Acceptable ML20214T3991986-12-0202 December 1986 Supplemental Safety Evaluation Accepting Licensee 860613 Analysis & Justification for Cable Separation Criteria to Resolve Deficiencies Described in Sser 7,App D ML20213G3181986-11-12012 November 1986 Safety Evaluation Accepting local-to-bulk Temp Difference of 12 F.Draft Technical Evaluation Rept Encl ML20215K8741986-10-21021 October 1986 Safety Evaluation Accepting Offsite Dose Calculation Manual Updated Through Rev 12.Changes Incorporated in Revs 11 & 12 Comply W/Tech Spec 6.8.2 ML20215K9631986-10-16016 October 1986 Safety Evaluation Granting Interim Acceptance of Process Control Program Updated Through 850718 ML20212Q7191986-08-29029 August 1986 Safety Evaluation Supporting Amend 27 to License NPF-18 ML20205F0791986-08-11011 August 1986 Safety Evaluation Supporting 860213 Procedures for Design of Single Angle Members for HVAC Hanger Frames for Plant. Related Info Encl ML20205C4051986-08-0707 August 1986 Safety Evaluation Supporting Facility Restart Following 860601 Feedwater Transient.Licensee Action Plan,Supplemented by Listed Actions,Adequate Basis for Restart & short-term Operation.Supporting Drawings & Matls Encl ML20206M6161986-06-23023 June 1986 Safety Evaluation Supporting Responses to Generic Ltr 83-28 Item 2.1 (Part 1) Re Equipment Classification ML20195D4121986-05-27027 May 1986 Safety Evaluation Summary of Inservice Testing Program for Pumps & Valves.Program Acceptable Subj to Listed Conditions in Encl SER ML20195D4171986-05-27027 May 1986 SER Re Pump & Valve Inservice Testing Program NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves1986-05-19019 May 1986 Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves ML20198B4221986-05-15015 May 1986 Supplemental Safety Evaluation Supporting Util Cable Separation Criteria Per Sser (NUREG-0519),App D.Addition of Zipper Tubing to Divisional Cables for Automatic Depressurization Sys Relief Valves Resolved NRC Concern ML20203N5531986-04-30030 April 1986 Safety Evaluation Concluding That Util IGSCC Insp Performed in Accordance W/Generic Ltr 84-11 & Satisfactory.Small Concerns Re long-term Growth of Small IGSCC Cracks Present But Not Detected During Insp Remain ML20140D6501986-03-19019 March 1986 SER Supporting Test Program,Results & Commitment for Nonqualified GE Control Switches.License Conditions 2.C.(21)(c) & 2.C.(12)(a) for Units 1 & 2,respectively,will Be Satisfied When GE Switches Removed from Engine ML20210E0961986-02-0404 February 1986 Safety Evaluation Accepting Util 851113 Proposal for Amend Changing Tech Specs to Include Previously Approved Trip Setting on Low CRD Pump Discharge Water Header Pressure & to Delete Associated Surveillance Requirement ML20137D8081985-11-18018 November 1985 Safety Evaluation Supporting Use of Mechanical Stress Improvement Process in Primary Sys Stainless Steel Piping to Modify Residual Stress Pattern at Piping Butt Welds NUREG-0889, SER Conditionally Supporting Response to Procedures Generation Package1985-10-18018 October 1985 SER Conditionally Supporting Response to Procedures Generation Package ML20137S6391985-09-30030 September 1985 Safety Evaluation Supporting Elimination of Arbitrary Intermediate Pipe Breaks.Deviation from SRP Acceptable for Piping Sys Identified in Ref 2 Except Portion of RHR Sys Made of 304SS Matl ML20129D9511985-07-16016 July 1985 Safety Evaluation Supporting Acceptance Criteria for Firecode CT Gypsum Fire Stops ML20126K9121985-07-12012 July 1985 Revised SER Re Util 831105 & 850605 Responses to Generic Ltr 83-28,Item 1.1, Post-Trip Review Program. Program & Procedures Acceptable ML20129E8881985-05-24024 May 1985 SER of Util 831105 Response to Generic Ltr 83-28,Item 1.2 Re post-trip Review Data & Info Capabilities.Capabilities Acceptable 1999-10-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML20199E4601998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for LaSalle County Station,Units 1 & 2.With ML20207C7371998-12-31031 December 1998 Annual Rept for LaSalle County Station for Jan 1998 Through Dec 1998 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20206N2261998-12-0909 December 1998 LER 98-S03-00:on 981116,protected Area Was Entered Without Current Authorization for Unescorted Access Due to Programmatic Deficiency Error.Changed Badge Control Process ML20197K0981998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for LaSalle County Station,Unts 1 & 2.With ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings of Safety-Related Power-Operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3191998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for LaSalle County Station.With ML20154H6781998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151W0241998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for LaSalle County Station.With ML20237E2921998-08-21021 August 1998 Special Rept:On 980811,channel 5 of Lpms Became Inoperable. Caused by Channel Failed pre-amplifier Located Inside Primary Containment at Inboard Side of Electrical Penetration E-19.Initiated Repairs of Channel ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B4861998-07-31031 July 1998 Monthly Operating Repts for July 1998 for LaSalle County Nuclear Power Station Units 1 & 2 ML20236V7701998-07-31031 July 1998 Revised LaSalle Unit 1 Cycle 8 COLR & Reload Transient Analysis Results ML20236P8231998-07-14014 July 1998 Special Rept:From 980614-17,various Fire Rated Assemblies Were Inoperable for Period Greater than Seven Days.Caused by Test Equipment Being Routed Through Fire Doors.Established Fire Watches & on 980619 Assemblies Were Declared Operable ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L8041998-07-0606 July 1998 Safety Evaluation Granting Licensee 980304 Request for Second 10-yr Interval Pump & Valve IST Program Plan,Rev 2, Including Changes to 2 ASME Boiler & Pressure Vessel Code Relief Requests Previously Submitted in Rev 1 ML20236P3611998-06-30030 June 1998 Monthly Operating Repts for June 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20249C4891998-06-22022 June 1998 Special Rept:On 980522,Fire Detection Zone 1-31 Was Noted out-of-service for More than 14 Days.Detection Sys Was Taken out-of-service on 980508 to Prevent False Alarms During Hot Work Activities.Sys Was Returned to Operable Status 980528 ML20248M3101998-05-31031 May 1998 Monthly Operating Repts for May 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 ML20236V7771998-05-31031 May 1998 Rev 1 to 24A5180, Supplemental Reload Licensing Rept for LaSalle County Station Unit 1 Reload 7 Cycle 8 ML20217Q7041998-05-0404 May 1998 Safety Evaluation Accepting Util Request to Leave Leak Chase Channels Plugged During Performance of Containment ILRT ML20247M4491998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for LaSalle County Station ML20216F4941998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for LaSalle County Station,Units 1 & 2 ML20217N6581998-03-30030 March 1998 Special Rept on Fire Detection,Deluge Sys & Fire Rated Assemblies During Period of 980303-25.Established Fire Watches Until Affected Equipment Is Returned to Operable Status ML20216D9511998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for LaSalle County Station,Units 1 & 2 ML20247M4631998-02-28028 February 1998 Rev Monthly Operating Rept for Feb 1998 for LaSalle County Station ML20203D7241998-02-20020 February 1998 Special Rept:On 980118,Fire Detection Zones 1-18 & 2-18 Taken out-of-svc to Prevent False Alarms During Hot Work Activities on Auxiliary Electric Equipment Room Ventilation Sys.Fire Watches Will Remain in Place ML20202G9851998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for LaSalle County Station,Units 1 & 2 ML20199K1651998-01-23023 January 1998 Rev 65h to Topical Rept CE-1-A, Comm Ed QA Tr 1999-09-30
[Table view] |
Text
.
A 42g o* k UNITED STATES j
3 NUCLEAR REGULATORY COMMISSION
's WASHINGTON, D.C. 20606 4001
\...../
SAEEJY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO INSERVICE TESTING PROGRAM REllEF RE00EST RP-01 COMONWEALTH EDIS0N COMFANY LASALLE COUNTY STATION. UNITS 1 AND 2 DOCKET NUMBERS 50-373 AND 50-374
1.0 INTRODUCTION
I The Code of Federal Reaulations,10 CFR 50.55a, requires that inservice testing (IST) of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (the Code) and applicable addenda, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to Sections (a)(3)(1),
(a)(3)(ii), or (f)(6)(1) of 10 CFR 50.55a. In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance is impractical for its facility. Section 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making the necessary !
l findings. NRC guidance contained in Generic Letter (GL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs," provides alternatives to the Code requirements determined acceptable to the staff. Alternatives that l conform with the guidance in GL 89-04 may be implemented without additional !
NRC approval, but are subject to review during inspections. Further guidance was given in Generic Letter 89-04, Supplement 1, and NUREG-1482, " Guidelines l for Inservice Testing at Nuclear Power Plants."
The applicable Code used in the LaSalle Units 1 and 2 third ten-year interval IST program was the 1989 edition of ASME Section XI which specifies that rules for the IST of pumps are stated in ASME/ ANSI Operations and Maintenance Standard, Part 6 (OM-6), " Inservice Testing of Pumps in Light-Water Reactor Power Plants."
2.0 RELIEF RE0 VEST NUMBER RP-01 Relief is requested from the test method requirements of OM-6, Section 5.2(b),
for the Unit I and 2 emergency core cooling system (ECCS) water leg pumps listed below. Relief was granted on an interim basis in an SE dated December 8,1995, in order to investigate installation of flow ENCLOSURE 9612090390 961206 i PDR ADOCK 05000373 P PDR
instrumentation. The licensee has proposed to measure vibration in accordance with OM-6, trend differential pressure and vibration, and use the current monitoring scheme to verify that the ECCS discharge lines are full of water. 1 Flow measurement will not be performed. i 1(2)E22-C003 High Pressure Core Spray Water Leg Pump )
1(2)E21-C002 Low Pressure Core Spray Water Leg Pump 1(2)E12-C003 Residual Heat Removal Water Leg Pump j 2.1 BASIS FOR RELIEF j
The licensee states:
Instrumentation is not installed for measuring flow rates. Pump j flow varies with system operation and system leakage; therefore, ;
- establishing set flow rates for testing purposes is not practical.
The primary purpose of these pumps is to maintain the ECCS pump discharge lines filled to limit the potential for water hammer on ECCS initiation. System modification to provide test measuring locations places undue burden on the utility without demonstrating any increase in the level of plant safety. These pumps are in continuous operation. Pump performance is continuously monitored by a low pressure alarm on each ECCS discharge header.
LaSalle Station monitors the pump for degradation by measuring and j recording pump inlet pressure, discharge pressure, differential
, pressure, and vibration, with the differential pressure and vibration data trended. These measurements are taken quarterly
, and provide satisfactory indication of operational readiness as well as the ability to detect potential degradation. In addition, the main ECCS pumps discharge headers each have a low pressure alarm which continuously monitors the operability of the respective water leg pump. Station Technical Specifications also )
verify operability of the water leg pumps by verifying flow 1 through a high point vent on a monthly basis.
2.2 ALTERNATIVE TEST l The licensee proposes:
Vibration measurement will be obtained under normal operating l conditions and evaluated in accordance with [0M-6]. LaSalle verifies operability of these pumps by pressure maintenance of ECCS discharge lines within allowable limits. In addition, the ,
inlet pressure, discharge pressure, differential pressures are i recorded, with the differential pressure and vibration data trended.
I i
i 2.3 { VALUATION The Code requires that each water leg pump be tested by establishing a fixed and repeatable hydraulic reference value of either differential pressure or pump flow, establishing the reference value during quarterly testing, and recording the variable reference value and bearing vibration for comparison with Code acceptance criteria. The design of the water leg pumps and their associated ECCS do not enable inservice testing to be readily performed in accordance with the Code. The necessary instrumentation is not installed in the system and a modification would be required for measuring flow and differential pressure. The licensee proposes to monitor the pumps for mechanical degradation only (i.e., vibration monitoring) without monitoring for hydraulic degradation.
The evaluation of this relief request in the December 8,1995, SE stated that i the licensee did not indicate whether portable flow instrumentation had been considered for flow measurement of the ECCS water leg pumps. At least one other plant (Perry) performs inservice testing in accordance with the Code requirements using ultrasonic flow instrumentation. Although the licensee stated in its initial submittal that there is no flow criterion on these pumps that could be used to determine whether the pumps are satisfactorily performing their safety function, IST scceptance criteria does not require testing at the design condition. Therefore, if ultrasonic flow instrumentation could be utilized, acceptance criteria in accordance with the Code requirements could be established.
The NRC has stated that the installation of instrumentation to meet a later edition of the Code is not considered a backfit (see Minutes of the Public Meetings on GL 89-04, Question 105 and Response). However, for the water leg pumps, which are continuously operating pumps, the function is merely to keep the ECCS pump discharge header piping in a filled condition to prevent water hammer upon pump start. The actual output and hydraulic performance of the water leg pumps are not critical to the safety function, as long as the pumps ,
are capable of maintaining the piping full. Alarms alert plant operators to ;
the condition when the water leg pumps do not maintain the piping full to a i set alarm level. In addition, vibration data will be indicative of levels !
trending toward unacceptable values and should allow time for the licensee to )
take corrective actions before the pumps fail. While the inservice testing would not be as complete as it would be if the Code requirements were imposed, Section 50.55a does include provisions for impracticalities due to design limitations, as the initial imposition of the Code requirements was subsequent to the design and construction of a number of nuclear plants. The proposed alternative provides a reasonable assurance of operational readiness because i differential pressure and bearing vibration are measured and trended. In 1 addition, alarm indications are present which indicate a degradation in the pressure of the ECCS discharge lines.
The licensee did not discuss whether the pumps are included in a preventative maintenance program because of the impracticalities of full compliance with the inservice testing requirements. If the pumps are not already included in l
l l
such a program, it is recommended that an assessment of the past operating history of the pumps be performed and a determination be made as to whether or not periodic maintenance is warranted. The granting of the relief is not, however, dependent on the licensee's prior performance of such an assessment.
The monitoring during continuous operation via the level alarms and vibration ;
measurements will provide adequate assurance of the operational readiness for i operation in an accident mitigation condition.
2.4 CONCLUSION
l The proposed relief request to not perform flow rate testing in accordance l with OM-6, Section 5.2(b), for the ECCS water leg pumps is granted and the '
alternative testing imposed pursuant to 10 CFR 50.55a(f)(6)(1) based on the ,
impracticality of performing the required testing and in consideration of the ;
burden on the licensee if the Code requirements were imposed. The alternative t testing will provide adequate assurance of the operational readiness of these !
pumps for performing their safety function of maintaining the ECCS piping full of water to prevent water hammer in the event the ECCS is actuated. 1 Principal Reviewer: J. Colaccino, DE/EMEB l Date: December 6, 1996 l l
l l
N h i
.y December 6, 1996 Ms. Irene Johnson, Acting Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III l
.1400 Opus Place, Suite 500 Downers Grove, IL 60515
SUBJECT:
EVALUATION OF REQUEST FOR RELIEF R0-01 FOR THE PUMP AND VALVE INSERVICE TESTING PROGRAM - LASALLE COUNTY STATION, UNITS 1 AND 2 (TAC NOS. M96955 AND M96956) 1
Dear Ms. Johnson:
i l
By letter dated October 24, 1996, Commonwealth Edison Company submitted Relief Request RP-01 proposing an alternate testing method for the emergency core cooling system water leg pumps at LaSalle County Station Units 1 and 2. This relief request was previously granted on an interim basis in a safety evaluation (SE) dated December 8, 1995. The staff has reviewed the proposed alternative referenced above against the requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code pursuant to paragraph 50.55a of Part 50 to Title 10 of the Code of Federal Reaulations. The basis for the staff's conclusions are contained in l the enclosed safety evaluation. The staff has concluded that relief request ,
RP-01 is granted and the alternative testing imposed pursuant to 10 CFR l 50.55a(f)(6)(1) based on the impracticality of performing the required testing !
and in consideration of the burden on the licensee if the Code requirements l were imposed. The alternative testing will provide adequate assurance of operational readiness of these pumps. i Sincerely, Original signed by:
Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV i Office of Nuclear Reactor Regulation '
Do:ket Nos. 50-373, 50-374
Enclosure:
Safety Evaluation cc w/ encl: see next page Distribution:
' Docket: File: PDIII-2 R/F J. Roe JWR E. Adensam EGA1 PUBLIC R. Capra D. Skay C. Moore OGC 015B18 ACRS 52E26 M. Dapas, RIII G. Hill (4)
DOCUMENT NAME: LA96955.LTR *See previous concurrence To receive a copy of this document, Indicat Q the box: "C" = Copy without enclosures *E' = Copy with enclosures *N' = No copy 0FFICE PM:PDIII-2 < LAW I.I-2 l D EMEB l D:PDIII-2 lG OCG l NAME DSKAY// wd M TMQJRC W *TSCARBROUGH RCAPRA Roc. *MYOUNG DATE 12/Y/96 17/6/96 11/27/96 12/co/96 12/03/96 0FFICIAL RECORD COPY