|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20216E9921997-09-0404 September 1997 Safety Evaluation Accepting 970623 Request for Relief Re Authorization for Use of ASME Code Case N-416-1 & N-532,ISI Program for Listed Plants ML20141H8411997-07-30030 July 1997 Safety Evaluation Accepting Use of Code Case N-508-1 for All Four Plants for Rotation of Serviced Snubbers & Pressure Relief Valves for Purpose of Testing in Lieu of ASME Code ML20138C8501997-04-28028 April 1997 Safety Evaluation Authorizing Proposed Alternative to Vibration Measurement Requirements of OM-6,paragraph 4.6.4 (B),For Standby Svc Water Pumps & Diesel Fuel Oil Transfer Pumps,Per 10CFR50.55a(a)(3)(ii) ML20147H4371997-03-31031 March 1997 Safety Evaluation Accepting Proposed P-T Limits for Heatup, Cooldown,Inservice Leak & Hydrostatic Testing & Core Criticality ML20149M4221996-12-12012 December 1996 Safety Evaluation Supporting Update Insvc Insp Programs to 1992 & Portions of 1993 ASME Boiler & Pressure Vessel Code, Sect XI for Licenses DPR-51,NPF-6,NPF-38,NPF-29 & NPF-47. Technical Ltr Rept Encl ML20107F5611996-04-17017 April 1996 Safety Evaluation Providing Guidance on Submitting plant- Specific Info W/Respect to IST Program Alternatives Request ML20149E8831994-08-0202 August 1994 Safety Evaluation Accepting Interim Relief Request IRR-03 Re Drywell Isolation Check Valves in Equipment Drain Lines & Reactor Equipment Closed Cooling Water Sys ML20058H0221993-11-30030 November 1993 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements in PRR 15,per 10CFR50.55(a)(3)(i). Denies Pump Relief Request 14 ML20059B2771993-10-22022 October 1993 Safety Evaluation Accepting IST Program Relief Requests ML20056G2001993-08-19019 August 1993 Safety Evaluation Denying 930419 Request for Relief from Requirements for Hydrostatic Testing of ASME Class 3 Pressure Retaining Components ML20126A2971992-12-16016 December 1992 Safety Evaluation Accepting Design for Drywell Hydrogen Concentration & Suppression Pool Water Level,W/Respect to Reg Guide 1.97 ML20128D2251992-12-0202 December 1992 Safety Evaluation Accepting Methodology Described in Topical Rept EA-CA-91-0001-M, Steady State Core Physics Methods for BWR Designs & Analysis ML20055F1891990-06-27027 June 1990 Safety Evaluation Supporting Util Tech Spec Change Request Re Scram Accumulator Check Valves ML20245A1051989-06-15015 June 1989 Safety Evaluation Accepting Util 890515 & 19 Submittals Re Results of Augmented IGSCC Insp & Flaw Evaluation of Feedwater Inlet Nozzle N4-A to Safe End Weld ML20247J7411989-05-25025 May 1989 Safety Evaluation Accepting Existing Intervals for on-line Functional Testing for Achieving High Reactor Trip Sys Reliability at All Operating Reactors,Per Generic Ltr 83-28, Item 4.5.3 ML20235N6031989-02-21021 February 1989 Safety Evaluation Approving Alternate Method for Complying w/10CFR50.55a for Main Steam Positive Leakage Control Sys Valve ML20195H1511988-11-23023 November 1988 Safety Evaluation Accepting Responses Re Item 4.5.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability on-line Testing ML20196A6611988-11-18018 November 1988 SER Accepting Util Response to Generic Ltr 83-28,Item 2.1, Part 2 Re Vendor Interface Programs for Reactor Trip Sys Components ML20195G8861988-11-18018 November 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.1, Part 1 Re Reactor Trip Sys Components ML20154M6561988-09-22022 September 1988 Safety Evaluation Supporting Licensee post-trip Review Program & Procedures Per Generic Ltr 83-28,Item 1.1 Re Generic Implications for Salem ATWS Events ML20151Q4701988-08-0101 August 1988 Supplemental Safety Evaluation Re First 10-yr Inservice Insp Program.Nrc Concurs W/Determination Made by Licensee That Section XI of ASME Code Exam Requirements for Category B-A Welds in Reactor Pressure Vessel Are Impractical to Perform ML20150F9501988-07-12012 July 1988 Safety Evaluation Supporting Util 840803 & 870922 Responses to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1 & 3.2.2 Re post-maint Testing of All safety-related Components ML20148D4391988-01-14014 January 1988 Safety Evaluation Supporting Util 870731 & 1030 Submittals on Facility Compliance Re Alternate Rod Injection & Recirculation Pump Trip Sys,Per ATWS Rule 10CFR50.62 ML20236D1851987-10-20020 October 1987 Safety Evaluation Accepting Util 870602 Rev 2 to First 10-yr Interval Inservice Insp Program ML20235K6871987-09-28028 September 1987 Safety Evaluation Accepting Util Monitoring Sys for UHS as Proposed in NUREG-0989, Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue1987-08-26026 August 1987 Safety Evaluation Supporting Proposed Turbine Maint Program. Proposal Satisfies Licensee Commitment Prescribed in Sser 5. Commitment Acceptable Resolution of Turbine Maint Issue ML20209B4291987-04-22022 April 1987 Safety Evaluation Supporting Util Proposed Rev to Tech Specs Re Drywell Leakage Test Interval ML20234E0491987-03-26026 March 1987 SER Accepting Response to Generic Ltr 83-28,Items 3.1.3 & 3.2.3 Re post-maint Testing of Reactor Trip Sys & All Other safety-related Components ML20205M3691987-03-26026 March 1987 Sser Re Mark III Containment Related Issues ML20212L2351987-01-21021 January 1987 Sser Re Util 860512 & 1119 Rev 4 to Preservice Insp Program & Relief Request R 0012 (a to E) from Certain ASME Code Requirements.Relief Granted.Preservice Insp Program in Compliance w/10CFR50.55a(g)(3) ML20203N7061986-10-0909 October 1986 Safety Evaluation Supporting Amend 2 to License NPF-47 ML20214P2061986-09-19019 September 1986 SER Supporting 860917 & 19 Requests for Amend to License NPF-40,changing Tech Spec Table 3.6.4-1 to Allow Inoperability of Inboard Isolation Valve MOVFO76 Through 861004 ML20207H4151986-07-16016 July 1986 Safety Evaluation Supporting Technical Solution to Address Operability & Reliability of Tdi Emergency Diesel Generators ML20133F8241985-08-0505 August 1985 Marked-up Draft Sser 2 Re Application for Ol,Reporting Status of Certain Items Not Resolved at Time of SER Publication 1999-08-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.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 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With 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 RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
[Table view] |
Text
. . .
k# Rf C 7% UNITED STATES h )*d
- I E NUCLEAR REGULATORY COMMISSION
[ WASHINGTON, D.C. 20555-0001 Qg [ u[ /
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIQH BELATED TO THE INSERVICE TESTING PROGRAM RELIEF RE0 VESTS GULF STATES UTILITIES COMPANY RLVER BEND STATION. UNIT 1 DOCKET NO. 50-458
1.0 INTRODUCTION
By letter dated September 14, 1993, Gulf States Utilities Company (GSU) submitted pump relief requests (PRR) 14 and 15 as part of the River Bend Pump and Valve Inservice Testing (IST) Program Plan, Revision 6. The licensee's IST program covers the first ten-year interval from June 16, 1996, to June 16, 1996. The River Bend Station, Unit 1, (RBS) IST program was developed in accordance with the 1980 Edition of ASME Section XI through the Winter 1981 Addenda.
2.0 BACKGROUND
The Code of Federal Regulations,10 CFR 50.55a, requires that inservice testing (IST) of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda, except where relief has been requested and granted or proposed alternatives have been authorized by the Commission pursuant to 10 CFR 50.55a(f)(6)(i), (a)(3)(1), or (a)(3)(ii). In order to obtain authorization or relief, the licensee must demonstrate that (1) conformance is impractical for its facility; (2) the proposed alternative provides an acceptable level of quality and safety; or (3) compliance would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. Section 50.55a(f)(4)(iv) provides that inservice tests of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed, and subject to Commission approval. NRC guidance contained in Generic letter (GL) 89-04,
" Guidance on Developing Acceptable Inservice Testing Programs," provided alternatives to the Code requirements determine) to be aceptable to the staff and authorized the use of the alternatives in Positions 1, 2, 6, 7, 9, and 10 provided the licensee follows the guidance delineated in the applicable position. When an alternative is proposed which is in accordance with GL 89-04 guidance and is documented in the IST program, no further evaluation is required; however, implementation of the alternative is subject to NRC inspection.
9312100235 931130 '
PDR ADOCK 0500 8
m ~
Section 50.55a authorizes the Commission to grant relief from ASME Code requirements or to approve proposed alternatives upon making the necessary findings. The NRC staff's findings with respect to granting or not granting '
the relief requested or authorizing the proposed alternative as part of the licensee's IST program are contained in this safety evaluation (SE).
In rulemaking to 10 CFR 50.55a, effective September 8,1992, (see 57 TR ;
34666), the 1989 Edition of ASME Section XI was incorporated in '
10 CFR 50.55a(b). The 1989 Edition provides that the rules for IST of pumps and valves shall meet the requirements set forth in ASME Operations and Maintenance Standards Part 6 (OM-6), " Inservice Testing of Pumps in Light-Water Reactor Power Plants," and Part 10 (OM-10), " Inservice Testing of Valves in Light-Water Reactor Power Plants." Pursuant to 10 CFR 50.55a(f)(4)(iv),
portions of editions or addenda may be used provided that all related '
requirements of the respective editions or addenda are met, and subject to Commission approval. Because the alternatives meet later editions of the Code, relief is not required for those inservice tests that are conducted in accordance with OH-6 and OM-10, or portions thereof, provided all related requirements cre met. Whether all related requirements are met is subject to NRC inspection.
3.0 RELIEF RE0 VESTS Pumo Relief Reouest Number 14 The licensee has requested relief from the inservice test procedure requirements specified in ASME Section XI, Table IWP-3100-1, for line fill pumps in the following systems: high pressure core spray, IE22*PC003; residual heat removal - low pressure coolant injection, IE12*PC003; low pressure core spray, IE21*PC002; and reactor core isolation cooling, IE51*PC003. The licensee has proposed to measure all test quantities listed in Table IWP-3100-1 with the exception of differential pressure. (Note: Pump Relief Request Number 10 already grants relief from the requirement to take pump bearing temperature for these pumps.)
Licensee's Basis for Reouestina Relief: The licensee states that the line fill pumps' function is to keep the main emergency core cooling systems (ECCS) and reactor core isolation cooling (RCIC) pump discharge piping full of water.
These line fill pumps operate continuously whenever their respective main pump and system is in an operable condition; therefore, testing for operational readiness of these pumps is not required. Adequate verification of their intended function is provided by the control room switch panels with annunciator signals and panel lights if the pressure were to drop to a preset value. In addition, RBS technical specifications require a verification every 31 days that the main ECCS and RCIC pump discharge piping is filled with water 1 by venting the piping at the high point vents.
1
Licensee's Proposed Alternative Testino: The licensee proposes that since the pumps are continuously running while the systems are operable, no additional quarterly testing will be performed. The pumps performance will be monitored on a quarterly frequency by obtaining operating performance parameters (i.e.,
suction pressure, flow rate, oil levels, and visual inspection for leaks) and vibration monitoring, and recording the results in the record of tests. These parameters will have acceptance, alert, and required ranges to establish proper trending for component degradation.
Evaluation The ASME Code,Section XI, Subsection IWP, requires that safety-related pumps be tested quarterly to verify their operational readiness. Routine testing gives an indication of current pump condition and identifies any trends in pump degradation so timely corrective action can be taken on a degraded pump prior to a catastrophic failure. The Code, IWP-3400(b), does not require a special inservice test for pumps that operate more often than the required testing frequency provided the plant log shows each such pump was operated at least once every 3 months at the reference conditions, and the quantities specified by the Code are measured, observed, recorded, and analyzed.
The line fill pumps are continuously running when the ECCS and the RCIC are operable. These pumps function to maintain a positive pressure in the associated ECCS and PCIC piping. The ECCS and RCIC line pressures are monitored in the contrel room and will alarm if any line pressure falls below the set pressure. The licensee has proposed to monitor all pump parameters specified in Table IWP-3I00-1 quarterly, with the exception of differential pressure. The licensee did not provide any justification in their relief request as to why differential pressure could not be measured. In the Updated Safety Analysis Report (USAR), the ECCS and RCIC piping and instrument schematics show differential pressure taps across each of the line fill pumps.
However, the USAR schematics do not show any differential pressure measurement instrumentation installer at any of these locations.
Trending of pump hydraulic performance data requires at least one established reference value for either pump differential pressure or flow rate. With the reference value set, the other parameter is measured to determine the extent of any degradation of pump hydraulic performance. Since the licensee's proposed testing does not include provisions to monitor differential pressure during any test, adequate trending data to predict pump hydraulic condition will not be taken. In addition, the licensee's relief request does not address why the line fill pumps cannot be tested during cold shutdowns. It may be possible to install temporary instrumentation quarterly or during cold shutdowns to measure differential pressure.
The licensee's submittal of PRR I4 does not provide justification for not measuring pump differential pressure. In addition, the licensee did not provide information on how the pump hydraulic condition will be evaluated after each test without measuring pump differential pressure. Finhily, the
,~
licensee did not address testing these pumps during cold shutdowns.
Therefore, relief cannot be granted as requested.
Conclusion The licensee's relief request is denied. The licensee should either test the i line fill pr.ps in accordance with the Code requirements or investigate testing the pumps during cold shutdowns. In addition, this relief request should be revised, if resubmitted, to include adequate justification for nut measuring p1mp differential pressure quarterly.
Pump Relief Recuest Number 15 The licensee has requested interim relief from the flow measurement .
requirements of ASME Section XI, Paragraph IWP-4600, for the emergency diesel generator fuel oil transfer pumps, IEGF* PIA, IEGF*PIB, and IEGF*PIC. The licensee stated in their September 14, 1993, letter, that relief was requested to be granted on an interim basis pending the approval of a Code Case. The licensee has proposed to calculate an average flow rate by using the day tank level instrumentation.
Licensee's Basis for Reauestino Relief: The licensee states that the purpose !
of the emergency diesel generator fuel oil transfer pump is to pump fuel from !
the storage tank to the emergency diesel generator fuel oil day tank. There are no flow instruments installed in the fuel oil system. The inservice test requirement is to obtain a flow rate which is achieved by a measurement of level of the storage tank and a volume change versus time to indicate a flow .
rate.
Licensee's Proposed Alternative Testino: The licensee proposes that to obtain the required flow rate, the use of level instrumentation over a specific time period will be used to calculate the flow rate. This calculation will be .
documented in the record of test on a quarterly basis. The level instrument will meet the accuracy and range specified in IWP-4100.
Evaluation l The Code, IWP-4600, requires that the pump flow rate shall be measured using a rate or quantity meter installed in the system. The emergency diesel generator fuel oil transfer pumps do not have flow meters currently installed in the system. The licensee has proposed to calculate the pump flow rate by determining the time to fill a predetermined volume of the day tank. The licensee's proposed method of testing results in the calculation of an average flow rate as compared with an instantaneous flow rate that would be measured with flow instrumentation in the piping circuit. The Code does not make a distinction between average and instantaneous flow rates but does require that the instrument measuring the flow rate be accurate to f2 percent of the full-scale range of the instrument. The licensee stated in their relief request that the level instrument used will meet the Code accuracy requirements of.
Table IWP-4110-1. The accuracy of the level instrument is subject to i i
verification by inspection. Therefore, the licensee's proposed alternate !
method of testing provides an acceptable level of safety.
1 i
a o .
9' In the September 14, 1993, letter the licensee requested that PRR 15 De granted on an interim basis pending the outcome of a Code Case. The staff I contacted the ASME staff to check on the status of the aforementioned Code Case and determined that no action is currently underway in the Code on this subject. However, since the licensee's proposed alternate method of testing provides an acceptable level of safety, the staff has determined that the proposed alternative is acceptable for long-term relief. Depending on the action of the ASME Code Committee, this method may be determined to meet the Code at some future date. At that time, the licensee may withdraw this relief request and note the basis for the withdrawal in their IST program.
Conclusion The proposed alternative to the Code requirements to mea.yrt he flow rate by i determining the change in tank level over a period of time ; authorized pursuant to 10 CFR 50.55a(a)(3)(1) based on the alternative providing an acceptable level of quality and safety. j
4.0 CONCLUSION
The staff has determined that the proposed alternative to the ASME Code requirements in PRR 15 provides an acceptable level of quality and safety and therefore authorizes its use pursuant to 10 CFR 50.55a(a)(3)(1). Pump Relief Request Number 14 is denied. The licensee should either submit a response to the evaluation in this relief request within 3 months of the date of this SE or perform testing of the line fill pumps in accordance with the Code requirements.
Principal Contributor: Joseph Colaccino Date: November 30, 1993
- __ _ - - _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _