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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20202B8571997-11-18018 November 1997 SE Approving Relief Requests for Second 10-Yr Interval for Pumps & Valves Inservice Testing Program for Beaver Valley Power Station,Unit 2 ML20199F4641997-11-13013 November 1997 SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2 ML20212G4961997-10-28028 October 1997 SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20217J5311997-10-0808 October 1997 Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2 ML20217J5891997-10-0707 October 1997 Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1 ML20211D8441997-09-17017 September 1997 SER Approving SG 90-day Rept Submitted by Duquesne Light Co for Beaver Valley Power Station,Unit 1,per GL 95-05 ML20216J5861997-09-0404 September 1997 Safety Evaluation Re Third 10-year IST Program.Approves Valve Relief Requests 1,3 & 4.Valve Relief Request 2 Not Required.Authorizes Pump Relief Requests 1,2,3 & 4 ML20148E1051997-05-28028 May 1997 Safety Evaluation Supporting Amend 204 to License DPR-66 ML20137X1441997-04-0909 April 1997 Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule ML20057B0641993-09-13013 September 1993 Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of Plant ML20056F3561993-08-12012 August 1993 Safety Evaluation Granting Licensee 930607 Request for Relief from Certain ASME Code Requirements for Temporary Repairs to Svc Water Sys ML20126H7601992-12-30030 December 1992 Safety Evaluation Approving Valve Relief Requests VRR-27, VRR-43 & VRR-44 & Will Provide Reasonable Assurance of Operational Readiness of Valves to Perform Intended Functions.Relief Request PRR-11 Cannot Be Approved ML20127P2081992-11-20020 November 1992 SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance ML20248D7681989-09-29029 September 1989 Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys ML20247N3561989-05-30030 May 1989 SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing ML20246M1791989-05-10010 May 1989 Safety Evaluation Re Verification & Validation Plan for Plant Safety Monitoring Sys.Hardware Design of Sys Found Acceptable.Verification & Validation Plan Found Incomplete & Unacceptable.Software Design Process Inadequate ML20246D5501989-04-26026 April 1989 Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for Unit ML20206G0431988-11-17017 November 1988 Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 Closed ML20153C0911988-08-17017 August 1988 Safety Evaluation Re Licensee 870731 Comments on Sser 5, Section 9.5.1.Fire Protection in Cable Rooms & Containment Constitutes Acceptable Deviations from Branch Technical Position Cmeb 9.5-1 ML20205T0021988-08-10010 August 1988 SER Accepting Util 831104,840330 & 870504 Responses to Item 2.2.1 of Generic Ltr 83-28 Re Equipment Classification Programs for All safety-related Components ML20154R4451988-05-31031 May 1988 Safety Evaluation Re Compliance W/Atws Rule 10CFR50.62.Util Proposed Design Acceptable Subj to Final Resolution of Tech Spec Issue ML20154P4341988-05-24024 May 1988 Safety Evaluation Concluding That Proposed Tech Spec Change Acceptable.No Amend Issued Since Conditions Resulting in Need for Amend to License NPF-73 No Longer Exist ML20154F9901988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 880322 Response to Open Issues Identified in 860722 Draft Technical Evaluation Rept of 840330 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20154F9841988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 851114 Response to Open Issues Noted in 851017 Draft Technical Evaluation Rept of 831104 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20153B6291988-04-25025 April 1988 Safety Evaluation Granting Util 870616 & 871110 Requests for Inservice Insp Relief for Welds on Nonregenerative Hxs,Per 10CFR50.55a(g)(6)(i) ML20148K5231988-03-18018 March 1988 Safety Evaluation Supporting Util Inservice Testing Program & Requests for Relief ML20234E0531987-12-0808 December 1987 Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change Unnecessary ML20236X4941987-11-0909 November 1987 Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal Surfaces ML20237B1651987-10-21021 October 1987 Safety Evaluation Supporting Elimination of Primary Component Support Snubbers from Primary Coolant Loops ML20204H7181987-03-18018 March 1987 Interim Safety Evaluation Re Pump & Valve Operability Assurance (SER Confirmatory Issue 13).Pages from Pvort Audit Encl ML20206G2231987-03-12012 March 1987 SER Accepting Licensee Request to Use Damping Values from ASME Code Case N-411 Per Conditions Outlined in Util ML20207P6551987-01-0202 January 1987 SER Accepting Licensee Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing ML20212B0111986-11-30030 November 1986 Safety Evaluation Granting Util Request for Exemptions from App R Requirements Re Separation of Cables & Equipment & Associated Circuits ML20205G4491986-08-31031 August 1986 Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20204G9281986-07-31031 July 1986 Safety Evaluation Supporting Util 860502 Submittal of Westinghouse Reload Safety Evaluation,Beaver Valley Nuclear Plant,Unit 1 Cycle 6 ML20203G2371986-07-28028 July 1986 Interim SER Re Dcrdr Summary Rept & Preimplementation Audit on 860211 & 12.Requirements of Suppl 1 to NUREG-0737 Generally Satisfied.Several Items Remain to Be Completed ML20206H4931986-06-19019 June 1986 Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable ML20205N1151986-04-22022 April 1986 Interim Rept Re Review of Util Response to Generic Ltr 85-12 on Reactor Coolant Pump Trip Criteria.Addl Info Required ML20202C5721986-04-0303 April 1986 Sser Accepting Util 860304 Response to Generic Ltr 83-28, Item 4.3, Seismic Qualification of Shunt Trip Components ML20214E3631986-03-17017 March 1986 Safety Evaluation Supporting Amend 2 to CPPR-105 ML20154N7451986-03-10010 March 1986 Safety Evaluation Supporting Util 850819 Request to Withdraw Original Commitment to Provide Steam Leakage Collection Sys Around Certain Steam Valves 1999-04-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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Text
. . _ -
O ter p- 4 UNITED STATES 4
g ,j
't NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
. . . . . ,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE TESTING PROGRAM DUQUESNE L CHT COMPANY OHIO EDISON COMPANY PENNSYLVANLg POWER COMPANY BEAVER VALLEY POVJR STATION. UNIT NO.1 DOCKET NO. 50-334
1.0 INTRODUCTION
The Code of Federal Regulations,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 BoilerandPressure VesselCode (the Code) l and applicable addenda, except where attematives have been authorized, or relief has been requested by the licensee and granted by the Commission, pursuant to Sections (a)(3)(i), (a)(3)(ii),
or (f)(6)(i) of 10 CFR 50.55a. In proposing attematives or requesting relief, the licensee must 3
demonstrate that: (1) the proposed attematives 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 Director of the Office of Nuclear Reactor Regulation to approve altematives and to grant relief from ASME Code requirements upon making the necessary findings. Guidance related to the development and implementation of inservice testing (IST) programs is given in Generic Letter (GL) 89-04, " Guidance on Developing Acceptable inservice Testing Programs," issued April 3,1989, and its Supplement 1 issued April 4,1995. Additional guidance can be found in NUREG-1482,
" Guidelines for Inservice Testing at Nuclear Power Plants," NUREG/CR-6396," Examples, Clarifications, and Guidance on Preparing Requests for Relief from Pump and Valve inservice i
Testing Requirements," and " Summary of Public Workshops Held in NRC Regions on Inspection Procedure 73756,' Inservice Testing of Pumps and Valves,' and Answers to Panel Questions on inservice Testing issues."
j The 1989 Edition of the ASME Code is the lates' mn incorporated by reference in paragraph (b) of Section 50.55a. Subsection lWP or the 1989 Edition, which gives the requirements ;
for IST of pumps, references Part 6 of the American National Standards institute /ASME Operations !
and Maintenance Standards (OM-6) as the rules for IST of pumps. OM-6 replaces specific requirements in previous ed:tions of Section XI, Subsection lWP of the ASME Code.
2.0 BACKGROUND
By letter dated June 11,1998, Duquesne Light Company (DLC), the licensee, submitted a new pump relief request PRR-5 for the third 10-year interval for the Beaver Valley Power Station, Unit No.1 (BVPS-1) IST Program. PRR-5 requested relief to use expanded acceptance ranges for flow and discharge pressure for the emergency diesel generator (EDG) fuel oil transfer pumps at BVPS-1.
The NRC staff issued a request for additionalinformation (RAI) related to pump relief request PRR-5 on August 11,1998. DLC responded to the RAl in a letter dated October 15,1998. DLC's response concluded that "the fuel oil transfer pumps should remain in the BVPS-1 IST Program and continue to be tested in accordance with OM-6 and the approved relief requests. Proposed pump relief request PRR-5 is still considered necessary due to the design and application of the pumps.'
3gO O 34 ENCLOSURE p PDR
l 2
The BVPS-1 IST program for the third 10-year interval began on September 20,1997, and is scheduled to expire on September 20,2007. The BVPS-1 IST program was developed to the 1989 Edition of the ASME Boiler and Pressure Vessel Code,Section XI. The 1989 Edition of the Code specifies that the rules for the inservice testing of pumps and valves are stated in the ASME/ ANSI Operations and Maintenance (OM) Standards, Part 6, " Inservice Testing of Pumps in Light-Water Reactor Power Plants," Part 10, " Inservice Testing of Valves in Light-Water Reactor Power Plants," and OMa-1988 Addenda to the OM 1987 Edition. (Reference DLC third 10-year IST program submittal for BVPS-1 dated April 30,1997; NRC SE dated September 4, 1997; and Revision 1 to the third 10-year IST program for BVPS-1 dated June 2,1998.)
3.0 EDG FUEL OIL TRANSFER PUMP RELIEF REQUEST PRR-5 PRR 5 pertains to the four EDG fuel oil transfer pumps for BVPS-1 (1EE-P 1 A,1EE-P-1B,1EE-P-1C, and 1EE-P-1D). These ASME Code Class 3 screw-type positive displacement pumps transfer fuel oil from the underground EDG fuel oil storage tank to the auxiliary fuel oil day tank in order to provide continuous operation of the diesel at rated load for up to 7 days during an emergency. (The auxiliary fuel oil day tank and engine mounted tank together contain approximately 900 gallons of fuel oil which is only sufficient to supply EDG operation for approximately 4-5 hours at rated load.)
DLC requested relief from Section 5.2(d) of OM-6 for the four EDG fuel oil transfer pumps. This section of the ASME Code requires that " Pressure, flow rate, and vibration (displacement or velocity) shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the limits given in Table 3 and corrective action taken as specified in para. 6.1."
3.1 DLC's Basis for Reauest DLC provided the following basis for the relief request:
In accordance with 10CFR50.55a (f)(5)(iii), relief is requested on the basis that compliance with the code requirement is impractical for BVPS-1.
The limits given in Table 3 for positive displacement pumps for discharge pressure are 0.93 to 1.10P, for the Acceptable Range and 0.90 to <0.93P, for the Alert Range Low, and for flow 0.95 to 1.10Q, for the Acceptable Range and 0.93 to <0.95Q, for the Alert Range Low. These limits are too restrictive for the Fuel Oil Transfer Pumps at BVPS-1. The baseline discharge pressures for these four pumps range between 7 psig and 11 psig. Applying the OM-6 limits for these values, the average allowable degradation from the reference value is only 0.8 psig. The discharge pressure indicators have graduations every 0.2 psig, however, a review of the previous data for discharge pressure since 1985 reveals that the discharge pressure has historically varied as much as 1 psig from one test to the next and between 1-3 psig over the course of a year. In addition, the allowable inaccuracy of the discharge p. essure gauges would allow variations of l
1
. = - - --
0.48 psig, equal to more than half of the Acceptable Ranges. The baseline flows for these four pumps range from 9 to 12 gpm. The average allowable degradation for flow is therefore only 0.7 gpm. The flow values also vary from test to test and between 1-3 gpm over the course of the year.
The OM-6 limits are, therefore, too restrictive. Normal historic variation in discharge pressure and flow would require the pumps to enter the Alert or Required Action Ranges. Trends would not be observed because the pumps would have to be declared inoperable before enough data could be obtained to determine if the data obtained is a true indication of a degrading condition or data scatter, in addition, the ASME trending would also pick-up variations caused by fouling of the suction strainer or discharge filter or by chattering of the relief valve.
An allowable variation larger than 0.8 psig or 0.7 gpm, therefore, is needed to trend pump performance.
NUREG 1482, Paragraph 5.6 " Operability Limits of Pumps," states that it expanded renges are needed, relief must be obtained. "The request for relief must include the licensee's basis for the expanded ranges and the basis for finding that the pump performance does not demonstrate degrading conditions.
The basis for acceptable pump performance pertains to the pump and not the system, though pump performance must meet system requirements to remain in an analyzed condition."
Therefore, BVPS-1 requests relief to use expanded ranges for discharge pressure and flow for the Fuel Oil Transfer Pumps. The ranges proposed for discharge pressure would be 0.80 to 1.20P, for the acceptable range and 0.70 to <0.80P, for the Alert Range. The function of these pumps is to be able to deliver fuel to the day tank to supply the Diesel Generator under fullload. The amount of fuel that is required to be delivered is 3.6 gpm, significantly lower than the reference values for all of the pumps, in addition, due to the nature of positive displacement pumps, flow should be the more consistent parameter. Therefore, the proposed range for flow is 0.90 to 1.150, for the Acceptable Range and 0.80 to <0.900,, for the Alert Range. The proposed range for the flow value is more restrictive because the flow rate is the more critical parameter for the system. The high flow limit is based on approximately half of the allowable variation expected in pumps with this rated flow rate, from the Hydraulic Institute Test Standard for Rotary Pumps,14th edition.
These ranges would only result in an average allowed variation of-2.5 psig and
+1.7 psig for pressure and -2.1 gpm and +1.5 gpm for flow. In addition, during discussions with Ingersoll-Dresser Pumps, the pump manufacturer, when questioned about a limiting value for pump performance, the pump manufacturer has stated that as the pump wears and the clearances open, the performance will gradually change. No limiting value for either flow or discharge pressure was provided and sudden performance degradation is not expected. The proposed expanded ranges will allow degrading conditions to be identified and provide assurance that the Fuel Oil Transfer Pumps will be capable of fulfilling their safety function.
1 i
i 4 >
2 3.2 Proposed Altemate Testina The licensee proposed the following:
. i Test per 10ST-36.1 and 2, " Diesel Generator Monthly Tests" using expanded ;
- ranges for flow and discharge pressure. '
1 .
3.3 Evaluation The NRC staff issued a request for additional information (RAl) related to pump relief request i PRR-5 on August 11,1998, that suggested that the BVPS-1 fuel oil transfer pumps need not be !
included within the scope of the licensee's IST program. DLC's October 15,1998, response stated that " these pumps are considered class 3 components that are supplied with emergency ;
power, that perform a function in shutting down a reactor to cold shutdown and mitigate the j consequences of an accident, and in accordance with 10 CFR 50.55a, should remain in the BV-1 -
lST Program." In addition, the licensee stated that "in order to ensure these pumps are capable of performing their safety function, they should continue to be tested as separate components, !
not as subassembly components of the Diesel Generator."
DLC requested relief from the Code specified acceptance criteria for pressure and flow rate on the basis that conformance with these requirements is impractical for BVPS-1. The licensee proposed to test the D/G fuel oil transfer pumps (i.e., per 10ST-36.1 and 10ST-36.2, " Diesel
, Generator Monthly Tests") using expanded ranges for flow and discharge pressure as summarized in the following table.
[('Qyliggy] Acceptable Range Alert Range Required Action
, .u e J d V: 1'%
Range OM-6, Table 3b 0.93 to 1.10 P, 0.90 to <0.93 P, <0.90 P, >1.10 P ,
0.95 to 1.10 Q, 0.93 to <0.95 Q, <0.93 Q , > 1.10 Q ,
Proposed in PRR-05 0.80 to 1.20 P, 0.70 to <0.80 P, <0.70 P, >1.20 P, for the four Fuel Oil 0.90 to 1.15 Q, 0.80 to <0.90 Q, <0.80 Q , >1.15 Q ,
Transfer Pumps DLC stated that the discharge pressure range for these pumps is 7 to 11 psig and that discharge pressure varies as much as 1 psig from one test to the next and as much as 1-3 psig over the course of a year. Flow rate for these pumps range between 9 gpm and 12 gpm and varies as much as 1-3 gpm over the course of a year. DLC suggested that in situations where pump discharge pressure and flow rate vary significantly (e.g., approximately 10 to 40% of the reference pressure and flow rate), as they apparently do with the BVPS-1 fuel oil transfer pumps, it is impractical to meet the restrictive hydraulic acceptance criteria as specified by the Code.
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.S-l During the second ten-year interval, expanded ranges were used for these pumps, as permitted by Section IWP-3210 of the 1983 edition of the ASME Section XI Code which stated:
The allowable ranges of inservice test quantities in relation to the reference values are tabulated in Table IWP-3100-2. If these ranges cannot be met, the Owner shall )
I specify in the record of tests (IWP-6000) the reduced range limits to allow the pump !
to fulfill its function, and those limits shall be used in lieu of the ranges given in Table IWP-3100-2.
i For this third ten-year interval (which began on 9/20/97), the 1989 edition of the Code is used, which references OM-6. OM-6 does not contain a paragraph similar to IWP-3210 which would allow the use of expanded ranges. Section 5.6,' Operability Limits for Pumps," of NUREG-1482 states that I the OM-6 Working Group could not endorse the IWP philosophy of letting the owner specify any acceptance criteria deemed appropriate when the limits of the applicable table could not be met.
' Because OM-6 is incorporated by reference in Paragraph (b) of 10 CFR 50.55a, licensees that use OM-6 must obtain relief if expanded ranges are needed. l The licensee stated that without expanded acceptance ranges, normal historic variation in discharge pressure and flow rate would require the pumps to enter the alert or required action ranges. Trends would not be observed because tha pumps would have to be declared inoperable before enough data could be obtained to determine if the data obtained is a true indication of a degrading condition or data scatter. DLC has investigated possible causes for the variations in pump discharge pressure and flow rate (e.g., fouling of the suction s' vainer or discharge filter or possible chattering of the downstream relief valve) and has been unable to either correlate the variation to an adverse pump (or system) condition or to limit the magnitude of the variation such that the OM-6 acceptance criteria could reasonably be used. During a telephone conference callwith DLC on November 12,1998, DLC representatives stated that pump discharge pressure and flow rate variations could not be reduced without expending significant additional time and resources (e.g., on pump replacement and/or system redesign). Based on this information, the staff concludes that compliance with the Code is impractical because of design limitations. Imposition of the Code requirements would require significant system redesign and modification.
1 Ingersoll-Dresser Pumps, the fuel oil transfer pump manufacturer, stated that as the pump wears and the clearances open, the pump's performance will gradually change. No sudden pump performance degradation is expected.
i While quarterly testing of the fuel oil transfer pumps is required to satisfy inservice test l
requirements, DLC representatives indicated that these pumps will be tested monthly in '
conjunction with the EDG technical specifications surveillance requirement. While some of the j
monthly tests may not meet all of the IST requirements, they will provide added confidence in ;
the operational readir,ess of these pumps. During a telephone conference call with DLC ,
representatives on November 12,1998, DLC representatives stated that it would take corrective l actions if any IST parameters on a fuel oil transfer pump falls outside the acceptance criteria I
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1 during any of the monthly tests. The NRC staff considered imposing monthly inservice testing of the 1 fuel oil transfer pumps on DLC (with the expanded acceptance criteria for discharge pressure and l
flow rate) but decided not to reauire the monthly tasting because monthly EDG testing may not consume sufficient fuel oil to support inservice testing of both associated fuel oil transfer pumps (i.e., I without having to possibly drain fuel oil from the auxiliary day tank to a 55 gallon drum).
DLC's proposed expanded ranges for discharge pressure and flow are consistent with the licensing l
basis assumptions in the plant's safety analysis. The reference flow rate for gagh pump is '
significantly higher than the 3.6 gpm required, even at the lower required action flow rate proposed i by DLC. These proposed ranges will allow pump degradation to be identified in a timely manner.
On this basis, the DLC's proposal to use altamate, less-restrictive acceptance criteria for fuel oil l
transfer pump discharge pressure and flow rate is acceptable to the NRC staff. Testing as proposed ;
by DLC will provide reasonable assurance that the fuel oil transfer pumps will be capable of fulfilling l their safety function.
3.4 Conclusion Relief is granted and the attemative imposed pursuant to 10 CFR 50.55a(f)(6)(i) based on the impracticality of testing the fuel oil transfer pumps in accordance with the Code-specified acceptance criteria. The relief granted is authorized by law and will not endanger the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon the licensee if the Code requirement were imposed on the facility.
Principal Contributor: D. Fischer Date: December 21, 1998