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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20216H8481999-09-23023 September 1999 Safety Evaluation Supporting Amends 190 & 187 to Licenses DPR-29 & DPR-30,respectively ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 ML20210U7831999-08-0404 August 1999 Safety Evaluation Supporting Amends 189 & 186 to Licenses DPR-29 & DPR-30,respectively ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20196F4261999-06-25025 June 1999 Safety Evaluation Supporting Amends 188 & 185 to Licenses DPR-29 & DPR-30,respectively ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205F4791999-03-31031 March 1999 Safety Evaluation Supporting Amends 187 & 184 to Licenses DPR-29 & DPR-30,respectively ML20205D4171999-03-26026 March 1999 Safety Evaluation Supporting Amends 186 & 183 to Licenses DPR-29 & DPR-30,respectively ML20204D9751999-03-17017 March 1999 Safety Evaluation Supporting Amends 185 & 182 to Licenses DPR-29 & DPR-30,respectively ML20198S6841998-12-22022 December 1998 Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition ML20196F8931998-12-0303 December 1998 Safety Evaluation Supporting Amend 182 to License DPR-29 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20216F0221998-03-0606 March 1998 Safety Evaluation Accepting Request Re Temporary Use of Current Procedure for Containment Repair & Replacement Activities at Plant ML20202E2971998-01-0505 January 1998 Safety Evaluation Supporting Amends 164,159,179 & 177 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20211P3151997-10-0707 October 1997 Safety Evaluation Supporting Amends 178 & 176 to Licenses DPR-29 & DPR-30,respectively ML20197B9171997-07-23023 July 1997 Safety Evaluation Re Concrete Expansion Anchor Safety Factors for High Energy Line Break Restraints ML20141E5091997-05-16016 May 1997 Safety Evaluation Supporting TR EMF-96-051(P), Application of Anfb Critical Power Correlation to Coresident GE Fuel for Plant,Unit 2 Cycle 15 ML20138F2881997-05-0101 May 1997 Safety Evaluation Supporting Amends 176 & 172 to Licenses DPR-29 & DPR-30,respectively ML20137F7751997-03-27027 March 1997 Safety Evaluation Supporting Amends 175 & 171 to Licenses DPR-29 & DPR-30,respectively ML20136G7731997-03-14014 March 1997 Safety Evaluation Approving Amends 155,150,174 & 170 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20137G6071997-03-13013 March 1997 Safety Evaluation Supporting Proposed Changes to TS & Bases Ceco ML20135E1551997-02-28028 February 1997 Safety Evaluation Supporting Amends 153,148,172 & 168 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20134H7601997-02-0707 February 1997 Safety Evaluation Approving Rev 65c of Ceco QA TR CE-1-A ML20092M5091995-09-21021 September 1995 Safety Evaluation Supporting Amends 140,134,162 & 158 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20092G9351995-09-11011 September 1995 Safety Evaluation Supporting Amends 159 & 155 to Licenses DPR-29 & DPR-30,respectively ML20086C1941995-06-23023 June 1995 Safety Evaluation Supporting Amends 136,130,157 & 153 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20085L6961995-06-14014 June 1995 Safety Evaluation Supporting Amends 135,129,156 & 152 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20085H0301995-06-13013 June 1995 Safety Evaluation Supporting Amends 134,128,155 & 151 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20085K3391995-06-0808 June 1995 Safety Evaluation Supporting Amends 133,127,154 & 150 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20084R6411995-05-30030 May 1995 Safety Evaluation Supporting Amends 153 & 149 to Licenses DPR-29 & DPR-30,respectively ML20078S8301995-02-16016 February 1995 Safety Evaluation Supporting Amends 131,125,152 & 148 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20149F4151994-08-0404 August 1994 Safety Evaluation Concluding That Unit 1 Can Be Safely Operated During Next Operating Cycle (Cycle 14) ML20070G4541994-07-13013 July 1994 Safety Evaluation Supporting Amends 149 & 145 to Licenses DPR-29 & DPR-30,respectively ML20071G1671994-07-0606 July 1994 Safety Evaluation Supporting Amends 128,122,148 & 144 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively ML20069K6001994-06-10010 June 1994 Safety Evaluation Supporting Amends 146 & 142 to Licenses DPR-29 & DPR-30,respectively ML20029D6911994-05-0303 May 1994 Safety Evaluation Accepting Inservice Testing Program for Relief Requests for Pumps & Valves for Plant ML20067C9411994-03-0202 March 1994 Safety Evaluation Stating Exemptions Granted in 880721 & 910221 SERs Still Valid Re Request for Revs to Exemptions from Fire Protection Requirements of 10CFR50,App R.No Addl Exemptions Required ML20063A6561994-01-19019 January 1994 Safety Evaluation Supporting Amend 139 to License DPR-30 ML20058L2711993-12-0808 December 1993 Safety Evaluation Finding Overlay Repair of Weld 02C-F7 Acceptable & in Conformance W/Gl 88-01.Plant May Be Returned to Safe Operation ML20046D4611993-08-0303 August 1993 Safety Evaluation Supporting Amends 143 & 138 to Licenses DPR-29 & DPR-30,respectively ML20056C4601993-06-17017 June 1993 Safety Evaluation Accepting Proposed Repair of Weld in Recirculation Piping Sys for One Cycle of Operation ML20044H3861993-05-28028 May 1993 Safety Evaluation Supporting Amends 142 & 137 to Licenses DPR-29 & DPR-30,respectively ML20044E1501993-05-13013 May 1993 Safety Evaluation Supporting Amends 141 & 136 to Licenses DPR-29 & DPR-30,respectively ML20128F9731993-02-10010 February 1993 Safety Evaluation Granting Licensee 910930 Request Not to Perform Code Exam on 100% of Attachment Welds on Stabilizer Brackets to Reactor Vessel Under 10CFR50.55(a)(3)(ii) ML20116H1721992-11-0404 November 1992 Safety Evaluation Supporting Amend 139 to License DPR-29 ML20116A8901992-10-19019 October 1992 Safety Evaluation Supporting Amends 119,115,138 & 134 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000254/LER-1999-004-03, :on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-021999-10-12012 October 1999
- on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-02
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure1999-10-0707 October 1999
- on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20216H8481999-09-23023 September 1999 Safety Evaluation Supporting Amends 190 & 187 to Licenses DPR-29 & DPR-30,respectively 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 ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210U7831999-08-0404 August 1999 Safety Evaluation Supporting Amends 189 & 186 to Licenses DPR-29 & DPR-30,respectively ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With 05000265/LER-1999-002-04, :on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 9907151999-06-25025 June 1999
- on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 990715
ML20196F4261999-06-25025 June 1999 Safety Evaluation Supporting Amends 188 & 185 to Licenses DPR-29 & DPR-30,respectively 05000254/LER-1999-004-02, :on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised1999-06-18018 June 1999
- on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised
ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210H3501999-05-25025 May 1999 Rev 1 to Quad Cities Station IPEEE Submittal Rept ML20207E1621999-05-25025 May 1999 Rev 1 to Quad Cities IPEEE, Consisting of Revised Chapter 4.0 Re Internal Fire Analysis 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 05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance1999-05-12012 May 1999
- on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205F4791999-03-31031 March 1999 Safety Evaluation Supporting Amends 187 & 184 to Licenses DPR-29 & DPR-30,respectively SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205D4171999-03-26026 March 1999 Safety Evaluation Supporting Amends 186 & 183 to Licenses DPR-29 & DPR-30,respectively ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20204D9751999-03-17017 March 1999 Safety Evaluation Supporting Amends 185 & 182 to Licenses DPR-29 & DPR-30,respectively ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20198S6841998-12-22022 December 1998 Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition ML20196F8931998-12-0303 December 1998 Safety Evaluation Supporting Amend 182 to License DPR-29 ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding 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 SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With 05000254/LER-1998-001-01, :on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation1998-10-27027 October 1998
- on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation
05000265/LER-1998-006-04, :on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-061998-10-15015 October 1998
- on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-06
1999-09-30
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p areg'e UNITED STATES
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j-j NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 30666 4 001
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SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO NRC BUI I FTIN 95-02 COMMONWEALTH EDISON COMPANY QUAD CITIES NUCLEAR POWER STATION. UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 1.0
!NTRODUCT!QN 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 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 14, 1995, and September 15,1997, Commonwealth Edison Company (Comed, the licensee) submitted their response to NRC Bulletin 95-02 for Quad Citics Nuclear Power Station, Units 1 md 2 (Quad Cities). In its response, the licensee stated their intent to comply with the requested actions in the bulletin.
2.5 DjlCUSSION The following describes the requested actions in NRC Bulletin 95-02 and the licensee's response to each requested action.
Action i Verify the operability of all pumps which draw suction from the suppression pool when performing their safety functions (e.g., ECCS [ emergency core cooling system), containment 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 licensee evaluated the design of the suction strainers including flow requirements and screen size, the potential sources of material and flow path to the strainers, and torus water conditions during ECCS suction. This evaluation determined that there are relatively few sources of potentially damaging material, the amount of contaminants is small compared to the torus water volume, and it is difficult for contaminants to reach the suction strainers. Therefore, the licensee concluded that the probability of torus contamination creating a safety problem is extremely remote.
ENCLOSURE 98o909033o 9eo904 PDR ADOCK 0500o254 G
PDR
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2-i The licensee's assessment of operability for the Unit 1 pumps considered the following. During the Quad Cities, Unit 1, refueling outage in 1994, and the Quad Cities, Unit 2, refueling outage in 1995, the suppression pools' strainers were inspected and the suppression pools were drained, the walls and floor hydrolyzed, surfaces sandblasted, and new protective coatings applied. The pools were refilled with fresh domineralized water. A cleaning of the Unit i drywell was also performed. Inservice testing data for the ECCS pump surveillances were reviewed and no 4
degradation of suction pressure was identified. Foreign material exclusion (FME) controls, enhanced in response to NRC Bulletins 92-02 and 93-02, Supplement 1, were also eviewed.
Based on the above, the licensee concluded that all pumps which draw suction from the suppression pools while performing their safety function for Quad Cities, Units 1 and 2, were operable.
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.
Response
in October of 1995, multiple pump tests were performed to confirm operability of the ECCS suction strainers. Suction pressure on each pump was measured at the beginning and end of the test and no decrease in suction pressure was observed. Subsequently, a diver performed an inspection of the Unit 1 suppression pool. inspected strainers had no indication of any buildup of fiber or debris after the pump test. The observed sludge film thickness after 14 months of
)
operation was approximately 1/32 of an inch. The FME program is intended to minimize the
)
possibility of material being ! eft in the pool. Pump suction pressures are recorded and trended during in-service quarter 1y ECCS pump surveillances which would provide indications of strainer blockage. Additionally, fullinspections of the suppression pools and strainers are scheduled for future outages. Based on the above, the licensee concluded that the ECCS stdion strainers -
were cperable.
Action 3 Schedule a suppression pool (torus) cleaning. The schedule for cleaning tne suppression pool -
should be consistent with tne operability evaluation in requested action 1 above. In addition, a 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.
ResDonse Based on the Unit 1 cleaning in 1994, the Unit 2 cleaning in 1995, and the current satisfactory condition of the torus, the licensee did.not identify an'immediate need for an additional cleaning.
The licensee state J that appropriate commitments regarding torus pool inspections, tests, and cleaning will be inade based on the results of future inspections and tests and subsequent NRC guidance on strtiner performance.
i l
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3 e
65ili2fL4 i
Review 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 3
?
exists. This review should determine if comprehensive FME controls have been established to j
l
- prevent materials that could potentially impact ECCS operation from being introduced into the suppression pool, and that workers are sufficiently aware of their responsibilities regarding FME.
i Any identified weaknesses should be corrected. In addition, the effectiveness of the FME controls since the last time the suppressien pool was cleaned and the ECCS strainers inspected, and the impact that any weaknesses noted may have on the operability of the ECCS should be assessed.
Response
The licensee reviewed existing procedures and training for FME and recent Problem Identification Forms for FME issues. The licensee concluded that modifications to the FME programs were not currently needed.
Action 5 Consider additional measure:: such as suppression pool water sampling and trending of pump suction pressure to detect clogging of ECCS suction strainers.
Response
Quad Cities currently samples suppression pool water weekly and analyzes for conductivity weekly and for pH, Chloride, Silica, Sulfate, and total organic carbon monthly. The licensee also trends the ECCS pump suction pressures as part of the inservice testing program. No further measures were proposed.
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 cxperience unacceptable buildup of debris that could clog strainers during normal operation which 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 then j
requested a verification of the licensee's assessment through a pump test and strainer j
inspection. These two actions serve to ensure that the pumps are currently operable and not experiencing unacceptable debris buildup. Requested actions 3,4 and 5 serve to ensure that appropriate measures, such as cleaning of suppression pools and strengthening of FME practices, are taken in the long term to prevent debris accumulation in the pool.
I The staff has concluded that the licensee's assessment of the ability of all pumps drawing I
suction from the suppression pool to perform their safety function has a reasonable basis for i
concluding that all o;,he pumps evaluated are operable. The licensee conducted an inspection i
to confirm that the ECCS systems were not affected by an unacceptable buildup of debris that could clog the pump strainers. Initial strainer cleanliness was considered good. The staff has concluded that the licensee's response meets the intent of requested actions 1 and 2 and is l
i l
~
a I
4 i i I
acceptable. The staff has also concluded that the licensee's evaluation of their FME program and suppression pool cleaning program meet the intent of requested actions 3 and 4, and are 1-acceptable. The licensee's programs for trending pump suction pressure data, sampling torus
{
water / sediment, and periodically inspecting the strainers and torus provide additional opportunity 3
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 for implementation of the actions proposed by the licensee is appropriate given 3-
]
the actions already taken.
]
4.0 CONCLUSION
e Based on the staff's evaluation of the licensee's submittal (s), the staff finds the licensee's 3
response to NRC Bulletin 95-02 to be acceptable.
Principal Contributors:
J. B. Hickman R. Elliot (by precedent)
Dated: September 4, 1998 i
t