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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required ML20217H5771998-03-27027 March 1998 Safety Evaluation Concluding That No Significant Safety Hazards Introduced at CPS for Net 32% Ampacity Derating Factor for 1 H & 3 H Conduit Fire Barrier Sys & 1 H Cable Tray Fire Barrier Sys.Requests Response Addressing Issue ML20199F6751998-01-26026 January 1998 Safety Evaluation Accepting 971209 Proposed Change to CPS USAR Which Will Impact Commitments Made in CPS QAP Description ML20141K6321997-05-27027 May 1997 Safety Evaluation Accepting Relief Requests for Inservice Testing Program for Plant ML20135D1191996-12-0404 December 1996 Safety Evaluation of First Ten Year Interval Inservice Inspection Program Plan for Illinois Power Co,Clinton Power Station ML20149L7951996-11-12012 November 1996 Safety Evaluation Related to Licensee 960729 Requests for Relief from Requirements of Section XI of ASME Boiler & Pressure Vessel Code,1980 Edition Through Winter 1981 Addenda ML20116G8771992-10-29029 October 1992 Safety Evaluation Supporting Licensee Method of Coping W/Sbo Except W/Respect to Initial Room Temp Used in Control Room heat-up Calculation ML20059H0671990-08-24024 August 1990 SER Accepting Licensee Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austentic Stainless Steel Piping, W/Exception of Licensee Position on Frequency of Leakage Monitoring ML20064A2611990-08-20020 August 1990 Generic SER Re Mark III Containment Hydrogen Control. Hydrogen Injection Rate Strongly Influenced by Background Gas Concentrations ML20246B6311989-08-17017 August 1989 Safety Evaluation Supporting Amend 25 to License NPF-62 ML20245F3471989-08-0404 August 1989 SER Accepting Util 841001,871118 & 880609 Responses to Generic Ltr 83-28,Item 2.1,Parts 1 & 2 Re Evaluation of Reactor Trip Sys Equipment Classification & Vendor Interface,Respectively ML20247B8791989-05-15015 May 1989 Safety Evaluation Concluding That Licensee Combinatory Qualitative Event Analysis Adequately Addresses NRC Concerns Re Loss of Electric Power to nonsafety-related Control Sys ML20246C2301989-05-0303 May 1989 Safety Evaluation Accepting Uitl Response to Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Backup Scram Valves & Commitment to Test Backup Scram Valves Independently During Each Refueling Outage ML20244C5671989-04-10010 April 1989 Safety Evaluation Supporting Amend 21 to License NPF-62 ML20247E8831989-03-27027 March 1989 Safety Evaluation Supporting Amend 20 to License NPF-62 ML20206M5561988-11-21021 November 1988 Evaluation Concluding That Basis Provided by Licensee for Justifying Relief Requests for Replacement Parts Sufficient & Relief Requests 5003 & 5044 Acceptable.Licensee Should Certify Compliance W/Commitments When Replacements Complete ML20151N4701988-07-28028 July 1988 Safety Evaluation Supporting Rev to Position Re Nuclear Sys Protection Sys self-test Sys Failure Detection & Indication for Facility ML20147H7651988-03-0101 March 1988 Safety Evaluation Re First ten-year Interval Inservice Insp Program.Grants Relief from ASME Code Section XI Requirements for Requests 4002,4001 & 4003 & Denies Requests 5001 & 5002. Program Acceptable & in Compliance w/10CFR50.55a(g) ML20214F5641987-05-18018 May 1987 Safety Evaluation Supporting Util Compliance W/Atws Rule 10CFR50.62, Requirements for Reduction of Risk from ATWS Events for Light-Water-Cooled Nuclear Power Plants ML20137L7111986-01-22022 January 1986 Technical Evaluation Re HVAC Duct Work & Support Sys.Overall Structural Design of HVAC Sys Adequate & Provides Sufficient Margin of Safety to Failure Under Normal & DBA Conditions ML20138H1261985-10-18018 October 1985 Supplemental Safety Evaluation Accepting Use of Rev 2 to NCIG-01, Visual Weld Acceptance Criteria for Structural Welding at Nuclear Power Plants. Criteria Appropriate & Meet Requirements of GDC 1 to App a to 10CFR50 1999-02-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARU-603277, Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.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 U-603267, Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With U-603245, Monthly Operating Rept for Jul 1999 for CPS Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for Jul 1999 for CPS Unit 1.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept U-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With U-603222, Monthly Operating Rept for May 1999 for Clinton Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Clinton Power Station.With ML20210K8391999-05-11011 May 1999 British Energy Annual Rept & Accounts 1998-99 ML20206H1231999-05-0505 May 1999 Illinois Power Co CPS Main CR Simulator Certification Rept U-603210, Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 U-603192, Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With U-603182, Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue1999-03-12012 March 1999 Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue U-603176, Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With ML20207F2031999-02-10010 February 1999 Rev 1 to CPS COLR for Reload 6 Cycle 7 ML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 U-603144, Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With U-603223, Illinova Corp 1998 Annual Rept. with1998-12-31031 December 1998 Illinova Corp 1998 Annual Rept. with U-603115, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components1998-12-0404 December 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components U-603124, Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With U-603114, Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor1998-11-25025 November 1998 Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor U-603103, Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With U-603101, Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site1998-10-28028 October 1998 Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves U-603091, Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20151U1391998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Clinton Power Station,Unit 1 ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required ML20151Y6591998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Clinton Power Station,Unit 1 U-603033, Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals1998-07-20020 July 1998 Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals U-603041, Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 ML20151U1501998-06-30030 June 1998 Revised Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 U-603023, Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 1 U-603014, Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed1998-05-28028 May 1998 Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed ML20236E7991998-05-26026 May 1998 Final Part 21 Rept Re W Dhp Circuit Breaker Auxillary Switch Operating Assembly Anomalies.Caused by Loss of Breaker Safety Function.Dhp Circuit Will Be Inspected 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 U-603004, Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable1998-05-15015 May 1998 Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable ML20216A9601998-05-0808 May 1998 Part 21 Rept Re Failure of 12 Volt DC Inverter Power Supply. Caused by Inadequately Sized Output Transistor Pair Combined W/Degraded Capacitors.Licensee Plans to Replace All Output Transistors & Degraded Capacitors U-602995, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts1998-05-0505 May 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts U-603006, Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 1 U-602994, Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable1998-04-29029 April 1998 Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable ML20216B1351998-04-21021 April 1998 Rev 0 to Illinois Power Co Clinton Power Station SVC Design Rept U-602979, Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable1998-04-0707 April 1998 Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable U-602976, Monthly Operating Rept for Mar 1998 for Clinton Power Station1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Clinton Power Station ML20217H5771998-03-27027 March 1998 Safety Evaluation Concluding That No Significant Safety Hazards Introduced at CPS for Net 32% Ampacity Derating Factor for 1 H & 3 H Conduit Fire Barrier Sys & 1 H Cable Tray Fire Barrier Sys.Requests Response Addressing Issue U-602968, Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue1998-03-24024 March 1998 Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue U-602960, Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 9804111998-03-12012 March 1998 Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 980411 U-602954, Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 9805131998-03-0909 March 1998 Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 980513 1999-09-30
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p k UNITED STATES 5 y NUCLEAR REGULATORY. COMMISSION WASHINGTON, D.C. speeH001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO NRC Bul i FTIN 95-02 I
ILLINOIS POWER COMPANY l CLINTON POWER STATION DOCKET NO. 50-461 i
1.0 INTRODUCTION
NRC Bulletin 95-02, " Unexpected Clogging of a Residual Heat Removal (RHR) Pump Strainer While Operating in Suppression Pool Cooling Mode," was issued on October 17,1995. It !
requested all holders of boiling-water reactor (BWR) operating licenses or construction permits l
for nuclear power reactors to take five actions to ensure that unacceptable buildup of debris that could clog strainers does not occur during normal operation. By letters dated November 15, 1995, December 21,1995, and October 9,1996, Illinois Power Company (the licensee) submitted their response to NRC Bulletin 95-02 for Clinton Power Station (Clinton). In its response, the licensee stated their intent to comply with the requested actions in the bulletin.
The licensee noted that Clinton uses a continuous suppression pool cleanup system to maintain pool cleanliness and that visual observation indicates that overall pool cleanliness is good. In addition, pump suction pressure data for the systems which draw suction most frequently from the suppression pool have not indicated that any buildup of material has occurred.
2.0 DISCUSSION The following describes the requested actions in NRC Bulletin 95-02 and the licensee's response to each requested action.
i Action i Verify the operability of all pumps which draw suction from the suppression pool when j performing their safety functions (e.g., ECCS (emergency core cooling system), containment l spray, etc.), based on an evaluation of suppression pool and suction strainer cleanliness ;
conditions. This evaluation should be based on the pool and strainer conditions during the last inspection or cleaning and an assessment of the potential for the introduction of debris or other !
materials that could clog the strainers since the pool was last cleaned.
- . Response The Clinton suppression pool was last cleaned in April of 1994, by vacuuming the bottom.
l However, Clinton has a continuously operating suppression pool cleanup system. In normal ,
operation this system processes the suppression pool water volume once very 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />. The 9808310260 980827 l" l PDR ADOCK 05000461>
G PDR ,
l o 2 in-line strainers on this system have not experienced excessive fouling and have had only seven cleanings in 9 years of operation. The suppression pool cleanup system processes the water through filter /demineralizers, which remove fibrous material and sediment before retuming the water to the pool.
The suction pressure date for the RHR A and B pumps, which have the most frequent operation with the suppression pool as a source, did not indicate any clogging taking place. There have also been no abnormal suction pressures identified by the inservice inspection program for any other ECCS or the reactor core isolation cooling system (RCIC) pumps.
l The existing programs to prevent the inadvertent introduction of material in the suppression L pool were reviewed and no further actions were required. Details on the programs were l provided in the response to requested action 4.
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Action 2 Confirm the operability evaluation in requested action 1 above through appropriate test (s) and strainer inspection (s) within 120 days of the date of this bulletin.
i
Response
The RHR A, B, C, and low-pressure core spray (LPCS) pumps have operability tests performed l quarterly, taking suction from the suppression pool. An examination of the pump suction history for these pumps showed no adverse trends, so the licensee determined that no further testing was required. The high-pressure core spray (HPCS) and RCIC pumps are also tested quarterly, although they take suction from the RCIC storage tank. An inspection and cleaning of the ECCS and RCIC suction strainers was completed on December 12,1995. The as-found condition of the strainers did not require cleaning as there was insufficient debris to negatively affect ECCS and RCIC operation. However, cleaning was performed tc., establish a baseline condition for future examinations.
In addition, in an April 1996 event, the licensee operated various safety relief valves to control reactor pressure. Subsequently, RHR B was operated for over 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> to remove the decay heat from the suppression pool. During this event there were no indications of inadequate j suction pressure for any of the pumps taking suction from the suppression pool. A visual !
inspection of the RHR B suction strainer following the event identified some debris accumulation but it was an insufficient amount to affect operability.
Action 3 Schedule a suppression pool (torus) cleaning. The schedule for cleaning the suppression pool i should be consistent with the operability evaluation in requested action 1 above. In addition, a l program for periodic cleaning of the suppression pool should be established, including _
procedures for the cleaning of the pool, criteria for determining the appropriate cleaning
. frequency, and criteria for evaluating the adequacy of the pool cleanliness. ;
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l
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}
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3
Response
!- As previously stated, the suppression pool was last cleaned in April of 1994; however. the suppression pool cleanup system provides continuous filtering and demineralizing of the pool.
An additional cleaning of the suppression pool was conducted in refueling outage 6, which began in 1996. A program addressing future inspection frequency, inspection crite;ia, and additional cleanings will be included in the response to NRC Bulletin 96-03, "Poter,tial Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling Water Reactors."
Action 4 Review foreign material exclusion (FME) procedures and their implementation to determine whether adequate control of materials in the drywell, suppression pool, and ' systems that interface with the suppression pool exists. This review should determine if comprehensive FME controls have been established to prevent materials that could potentially impact ECCS
, operation from being introduced into the suppression pool, and if workert are sufficiently aware of their responsibilities regarding FME. Any identified weaknesses shov2d be corrected in addition, the effectiveness of the FME controls since the last time the suppression pool was cleaned and the ECCS strainers inspected, and the impact that any w9aknesses noted may have on the operability of the ECCS should be assessed.
Response
l In response to requested action number 4, the licensee has revie wed their FME practices and concluded that they are adequate. This conclusion is based on 'axtensive procedural controls l for FME and a review of condition reports which indicated no aaverse trend in the area of FME for the suppression pool. f j Action 5 Consider additional measures such as suppression pool water sampling and trending of pump j suction pressure to detect clogging of ECCS suction strainers. !
l Resoonse
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l The licensee currently conducts a suppression pool sampling program with required actions if a 9 parameter falls into an abnormal range. In addition, ECCS and RCIC pump suction pressure is recorded and trended as part of the ISI program. The licensee concluded that the sampling and testing programs are adequate and no further actions are required.
3.0 EVALUATION The purpose of the requested actions in the bulletin is to ensure that ECCS and other pumps
- drawing suction from the suppression pool do not experience unacceptable buildup of debris that could clog strainers during normal operation and would prevent them from performing their safety function. Requested action 1 requested licensees to evaluate the operability of their
- pumps based on the cleanliness of the suppression pool and strainers. Requested action 2
i l O.
4 l then requested a verification of the licensee's assessment through a pump test and strainer
( inspection. These two actions serve to ensure that the pumps are currently operable and not i experiencing unacceptable debris buildup. Requested actions 3,4 and 5 serve to ensure that I
appropriate measures, such as cleaning of suppression pools and strengthening of FME L practices, are taken in the long term to prevent debris accumulation in the pool.
L The staff has concluded that the licensee's assessment of the ability of all pumps drawing
! suction from the suppression pool to perform their safety function has a reasonable basis for concluding that all of the pumps evaluated are operable, in addition, the licensee conducted an inspection to confirm that the RCIC and ECCS systems were not affected by an unacceptable l buildup of debris that could clog the pump strainers. Initial strainer cleanliness was considered l
good. Each strainer had a uniform covering of iron oxide dust that was easily removed by slight agitation. Although no cleaning was necessary, the strainers were cleaned to provide a l baseline for future examinations.
The staff has concluded that the licensee's response meets the intent of requested actions 1 and 2 and is acceptable. The staff has also concluded that the licensee's evaluation of their FME program and suppression pool cleaning program meets the intent of requested actions 3 and 4, and is acceptable. The licensee's existing programs such as trending of pump suction pressure data, sampling of torus water / sediment, and periodic inspections of the strainers and torus provide additional opportunity for early identification of potential strainer fouling. The staff has concluded that these additional actions meet the intent of requested action 5 and are acceptable. The staff has also concluded that the schedule forimplementation of the actions proposed by the licensee is appropriate given the actions already taken.
4.0 CONCLUS!QN Based on the staff's evaluation of the licensee's submittal (s), the staff finds the licensee's response to NRC Bulletin 95-02 to be acceptable.
Principal Contributors: John B. Hickman R. Elliott (by precedent)
Date! August 27, 1998 l
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