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| (10 CFR), Part 50, Section 50.55a. Section 50.55a(a)(3) states that attematives to te* | | (10 CFR), Part 50, Section 50.55a. Section 50.55a(a)(3) states that attematives to te* |
| requirements of paragraph (f) may be used, when avthorized by the NRC, if (i) the propsed attematives would provide an acceptable level of quality and safety, sr (ii) cc ,liance with the specified requirements would result in hardship or unusual difficuP.y without e compensating | | requirements of paragraph (f) may be used, when avthorized by the NRC, if (i) the propsed attematives would provide an acceptable level of quality and safety, sr (ii) cc ,liance with the specified requirements would result in hardship or unusual difficuP.y without e compensating |
| , increase in the level of quality and safety, The first 10 year inservice testing (IST) interval for Millstone Unit 3 began on April 24,1986, and was scheduled to end on April 23,1996. Because Millstone Unit 3 is currently in an extended outage, the ASME Code allows extensions of the 10 year interval. The licensee has documented its start date in a letter dated October 25,1997, as ' prior to entry into Mode 4." The second 10 year intervallST program for Millstone Unit 3 will be based on the requirements of the 1989 Edition of ASME Section XI that references the OMe.1988, Part 6 for pumps and Part 10 for valves, Northeast Nuclear Energy Company (NNECO/the licensee) submitted Relief Request PR 1 in a letter dated January 8,1998, and proposed a one time altomative to the Code requirements which specifies that prior to the establishment of new pump reference values, an inservice test shall be run at the conditic,s of an existing set of reference values. The staff's evah'ation of Relief Request PR 1 is included in Section 3.0 of this safety evaluation (SE), | | , increase in the level of quality and safety, The first 10 year inservice testing (IST) interval for Millstone Unit 3 began on April 24,1986, and was scheduled to end on April 23,1996. Because Millstone Unit 3 is currently in an extended outage, the ASME Code allows extensions of the 10 year interval. The licensee has documented its start date in a {{letter dated|date=October 25, 1997|text=letter dated October 25,1997}}, as ' prior to entry into Mode 4." The second 10 year intervallST program for Millstone Unit 3 will be based on the requirements of the 1989 Edition of ASME Section XI that references the OMe.1988, Part 6 for pumps and Part 10 for valves, Northeast Nuclear Energy Company (NNECO/the licensee) submitted Relief Request PR 1 in a {{letter dated|date=January 8, 1998|text=letter dated January 8,1998}}, and proposed a one time altomative to the Code requirements which specifies that prior to the establishment of new pump reference values, an inservice test shall be run at the conditic,s of an existing set of reference values. The staff's evah'ation of Relief Request PR 1 is included in Section 3.0 of this safety evaluation (SE), |
| 2.0 DISCUSSION Component identification | | 2.0 DISCUSSION Component identification |
| . Recirculation Spray System pumps 3RSS*P1 A, P1B,- Pic, P1D-- | | . Recirculation Spray System pumps 3RSS*P1 A, P1B,- Pic, P1D-- |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20204H7131999-03-17017 March 1999 Safety Evaluation Concluding That NNECO Provided Adequate Justification for Deviations from RG 1.97,Rev 2, Recommendations,For Instrumentation Monitoring CST Level & Containment Area Radiation at Mnps Unit 2 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys ML20207L2631999-03-0505 March 1999 Safety Evaluation Supporting Amend 104 to License DPR-21 ML20207L5961999-02-22022 February 1999 Safety Evaluation Concluding That Code Requirements,Which Require 100 Percent Volumetric Exam of RPV flange-to-shell, Impractical to Perform to Extent Required & That Alternative Provide Reasonable Assurance of Structural Integrity ML20203D7601999-02-11011 February 1999 Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program ML20196B0501998-11-24024 November 1998 Safety Evaluation Re Licensee 960213 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Unit 2 ML20155K1981998-11-0909 November 1998 Safety Evaluation Re Application of leak-before-break Status to Portions of Safety Injection & Shutdown Cooling Sys ML20195B8711998-11-0909 November 1998 Safety Evaluation Approving Revised Evaluation of Primary Cold Leg Piping leak-before-break Analysis for Plant ML20155C3781998-10-30030 October 1998 SER Denying Amend to Allow Changes to Fsar.Nrc Found That NNECO Had Not Considered Diversity Provided by Switch in Control Room That Removes Power to 1 of 2 MOV in SDC Sys Flow Path in Evaluation of High Low Pressure Design ML20155C8441998-10-29029 October 1998 Safety Evaluation Accepting Licensee Proposal to Withdraw ATWS Test Commitment ML20238F2781998-08-27027 August 1998 SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 ML20236U7051998-07-22022 July 1998 Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation ML20236K6971998-07-0101 July 1998 SER Accepting Third 10-year Interval Inservice Insp Program Plan,Rev 2 & Associated Request for Relief & Proposed Alternatives for Plant,Unit 2 ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20249C2541998-06-24024 June 1998 Safety Evaluation Accepting Proposed Rev 19 to NNECO QAP Topical Rept & Amended Through 980609.Informs That NNECO Exception to Provisions in Paragraph 10.3.5 of Constitutes Temporary & Acceptable Alternative ML20248J0031998-06-0404 June 1998 Safety Evaluation Accepting Millstone Nuclear Power Station Emergency Plan ML20248M2991998-06-0202 June 1998 Safety Evaluation Approving Application Re Restructuring of Central Maine Power Co by Establishment of Holding Company ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20217M4181998-04-30030 April 1998 Suppl Safety Evaluation Accepting Licensee RCS Pressure & Heat Removal by Containment Heat Removal Sys post-accident Monitoring Instrumentation ML20216G7921998-03-13013 March 1998 Safety Evaluation Authorizing Proposed Alternative to Check Valve Obturator Movement Requirements of OM-10 for SIL Accumulator Outlet for Listed Check Valves ML20203E8521998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(f) for Performing Required Inservice Testing of Certain Class 2 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E9341998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E2441998-02-0909 February 1998 Safety Evaluation Accepting Re Approval of Realistic,Median Centered Spectra Generated for Resolution of USI-A-46 ML20198R9941998-01-13013 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Millstone Nuclear Power Station,Unit 3 ML20202H7461997-12-10010 December 1997 Safety Evaluation Accepting Licensee Position That Correction of AC-11 Single Failure Vulnerability Unncessary ML20202J0911997-12-0202 December 1997 Safety Evaluation Accepting Proposed Exemption,Which Meets Special Circumstance Given in 10CFR50.12(a)(2)(ii) ML20198S2411997-10-31031 October 1997 SE Accepting Licensee Request for Deviations from Recommendations in Reg Guide 1.97,Rev 2 for Temp & Flow Monitoring Instrumentation for Cooling Water to ESF Sys Components & Containment Isolation Valve Position ML20212G5991997-10-27027 October 1997 Safety Evaluation Supporting Amend 103 to License DPR-21 ML20217K8801997-10-27027 October 1997 Correction to Safety Evaluation Supporting Amend 103 to License DPR-21.Phrase or Rod Block Protection Has Been Deleted from Listed Sentence in Staff Associated SE ML20212F1381997-10-22022 October 1997 Safety Evaluation Supporting Amend 102 to License DPR-21 ML20217M9301997-08-19019 August 1997 Safety Evaluation Accepting Continued Operation W/O High Startup Rate Trip by Nene for Millstone,Unit 2 ML20149J2661997-07-23023 July 1997 Safety Evaluation Accepting Changes & Reanalyses in ECCS Evaluation Models & Application of Models for Plant,Unit 2 ML20141L8821997-05-28028 May 1997 Safety Evaluation Supporting Amend 101 to License DPR-21 ML20138A0111997-04-23023 April 1997 Safety Evaluation Accepting Licensee Proposal,Not to Perform Type C Leakage Rate Testing on 14 Subject CIVs ML20137V5931997-04-15015 April 1997 Safety Evaluation Supporting Amend 100 to License DPR-21 ML20137U3121997-04-10010 April 1997 Safety Evaluation Supporting Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20134A0331997-01-23023 January 1997 Safety Evaluation Accepting Util Proposed Alternatives to ASME Code Requirements ML20133N3401997-01-14014 January 1997 Safety Evaluation Supporting Amend 98 to License DPR-21 ML20135C4221996-12-0202 December 1996 Safety Evaluation Accepting Proposed Alternative Described in Relief Request R-1 Re Valve Inservice Testing Program at Facility ML20128P4381996-10-0909 October 1996 Safety Evaluation Accepting Review of Cracked Weld Operability Calculations & Staff Response to NRC Task Interference Agreement ML20128L7541996-10-0404 October 1996 Safety Evaluation Supporting Amend 97 to License DPR-21 ML20248C5451995-05-0202 May 1995 SER on Millstone Unit 3 Individual Plant Exam of External Events to Identify plant-specific Vulnerabilities,If Any,To Severe Accidents & Rept Results Together W/Any licensee-determined Improvements & C/A to Commission ML20248C5731994-07-19019 July 1994 SER Step 1 Review of Individual Plant Exam of External Fire Events for Millstone Unit 3 ML20059H4991994-01-24024 January 1994 Safety Evaluation Accepting Revised Responses to IEB-80-04 Re MSLB Reanalysis 1999-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20206T3991999-03-31031 March 1999 First Quarter 1999 Performance Rept, Dtd May 1999 B17747, Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Millstone Nuclear Power Station,Unit 1.With 1999-09-30
[Table view] |
Text
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8(# ~ UNITED STATES
{ t NUCLf1AR REQULATORY COMMISSION wASHINeToN, D.C. asseHoot BAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO A REQUEST FOR RELIEF FROM ASME_ CODE SECTION XI REQUIREMENTS NORTHEAST MUCL EAR ENERGY COMPANY. ET AL, MILLSTONE NUCLEAR POWER STATION UNIT No. 3 QQCKET No. 50-423
1.0 INTRODUCTION
The Technical Specifications for Millstone Unit 3, state that the inservice inspection and testing of the American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 components shall be performed in accordance with Sectl0n XI of the ASME Boller and Pressure Vessel Cede (ASME Code) and applicable Addenda as required by Title 10 of the Code of Federal Raoulations -
(10 CFR), Part 50, Section 50.55a. Section 50.55a(a)(3) states that attematives to te*
requirements of paragraph (f) may be used, when avthorized by the NRC, if (i) the propsed attematives would provide an acceptable level of quality and safety, sr (ii) cc ,liance with the specified requirements would result in hardship or unusual difficuP.y without e compensating
, increase in the level of quality and safety, The first 10 year inservice testing (IST) interval for Millstone Unit 3 began on April 24,1986, and was scheduled to end on April 23,1996. Because Millstone Unit 3 is currently in an extended outage, the ASME Code allows extensions of the 10 year interval. The licensee has documented its start date in a letter dated October 25,1997, as ' prior to entry into Mode 4." The second 10 year intervallST program for Millstone Unit 3 will be based on the requirements of the 1989 Edition of ASME Section XI that references the OMe.1988, Part 6 for pumps and Part 10 for valves, Northeast Nuclear Energy Company (NNECO/the licensee) submitted Relief Request PR 1 in a for Millstone Unit 3.Approval Requested to Support Mode 4 Operations Scheduled for Jan 1998|letter dated January 8,1998]], and proposed a one time altomative to the Code requirements which specifies that prior to the establishment of new pump reference values, an inservice test shall be run at the conditic,s of an existing set of reference values. The staff's evah'ation of Relief Request PR 1 is included in Section 3.0 of this safety evaluation (SE),
2.0 DISCUSSION Component identification
. Recirculation Spray System pumps 3RSS*P1 A, P1B,- Pic, P1D--
' Code Class 2-9002270146 990217 PDR ADOCK 05000423 I Enclosure
l l
2 Code Requiremat OM 6, paragraph 4.5, "To establish an additional set of reference values?
Licensee's Code Rollef Request The licensee requested the following:
[P)ursuant to 10 CFR 50.55a(f)(5)(lii), NNECO hereby requests one time relief from the IST requiremen' of the OM S code (paragraph 4.5). This requires that a pump test be performed at ti existing reference values pnor to system modifications when establishing an udditional set of reference values for future evaluation of pump performance and determination of pump operability, Licensee's Basis for Requesting Relief The licensee provided the following basis for the relief request:
The Recirculation Spray system [RSS) was modined during the extended shutdown which began in May 1996. Due to changes in the design basis of the RSS system, orifice plates were installed in t.w pump discharge piping for *rch line to reduce maximum flow capacity. Dunng the initial design enange review, a pump test at the existing reference -
values, prior to system modifications, was not identified as a requirement of the OM 6 code. Concurrent to the modification, it has been determined that a t# fun at the .
previous reference values should be performed whenever reference ym,cs art .'1anJed, however the arrent system modification limits flow to less than the previous reference flow (flow limited to approximately 3000 gpm [ gallons per minute) and previous reference flow was 4150 gpm).
To allow testing at the previous reference values, system hardware changes, installed during the current outage, would have to be dismantled, This would involve removing the orifice plates, manufacture and installation of dum tly plates, and re Installing the original orifice plates after testing was complete. Implementing these changes just to run a test at the previous reference values will not provide any additional value to the determination of pump operability than the scheduled post modification testing. The post modification testing is a more comprehensive test which will compare each pump's performance against the original pump performance curves (testing at 5 points up to approximately 3000 gpm). This post modification test, as an attemative to the code test, would allow clear determination of the pumps operating status and provida an acceptable level of quality and safety with regard to RSS pump testing.
The preposed attemative testing will verify the original pump curve, up to approximately 3000 gpm, as compared to a one point verification as required by ne code. This testing provides sufficient verification of each pump's operating stasus such that new reference
- values can be established from which deviations in pump performance, relative to original performance, can be readily detected. An evaluation of past RSS pump test results has identified that there are no signs of performance degradation and all four pumps continue to run as new, consistent with low cumulative run times, i.e. less than 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. The pumps have been idle for approximately 22 months during the current extended shutdown and thus should not have experienced any degradation.
e 3-Licensee's Proposed Alternative Examination The licensee proposed the following:
All four RSS pumps will be tested at flowrotes of approximately 3000,2500,2000,1500 and 1000 gpm as part of the post modification testing to support determ'.iation of pump operability. Pump performance at each test point will be compared to the original factory performance curve, the RSS system design criteria and pump manufacturer acceptance criteria. Any discrepancies in pump performance will be dispositioned in accordance with ASME OM-6 corrective actions. Additionally each pump will be tested it the minimum recirculation flow to establish new reference values.
3.0 EVALUATION The four RSS pumps have a safety function to provide flow to the recirculation spray headers during the injection phase of the accident and provide long term cooling during the recirculation .
phase of the accident. The previous inservice test for these pumps was performed at a reference flow rate of 4150 gpm. During the current extended outage, the RSS system was modified to reduce the maximum flow rate to approximately 3000 gpm by installing orifice plates on the discharge of each pump.
The Code requires for safety related pumps that prior to establishing an additional set of reference values, an inservice test shall first be run at the conditions of an existing set of reference values and the results analyzed. To meet the Code requirements, the licensee would be required to remove the installed orifice plates for each pump, perform the Code required test to reconfirm the previous reference values, and reinstrll the plates. This would result in a hardship for the licensee without a compensating increase in safety if there are other means to demonstrate acceptable pump operation.
The licensee has proposed to perform a post modification test which consists of collecting performance data for each pump at five points and then comparing this data to the original factory performance curve, the RSS system design criteria, ano the pump manufacturer acceptance criteri3. In addition, the ASME corrective action requirements will be adhered to in this post modifie.ation test. The NRC staff has concluded that the proposed testing provides seasonable assurance of operational readiness because the attemative test of taking five data points across virtually the entire range of pump operation (500 gpm to 3000 gpm) is more stringent than the Code-required test.
4.0 CONCLUSION
The staff conclude that pursuant to 10 CFR 50.55a(a)(3)(ii), the proposed attemative described in the enclosed SE may be authorized in that compliancc with the specif,ed requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Principle Contributors: Jim Andersen Joseph Colaccino Date: February 17, 1998
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