Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002ML20206A211 |
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River Bend ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
04/21/1999 |
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From: |
NRC (Affiliation Not Assigned) |
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To: |
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Shared Package |
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ML20206A206 |
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References |
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NUDOCS 9904280101 |
Download: ML20206A211 (6) |
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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
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.p %g\ UNITED STATES -
g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30006 0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR.BEOULATION RELATED TO INSERVICE TESTING PROGRAM RELIEF REQUEST FOR ENTERGY OPERATIONS. INC.
RIVER BEND STATION DOCKET NO. 50-458
1.0 INTRODUCTION
Title 10 of the Code of Federal Reaulations (10 CFR) Section 50.55a, requires that inservice testing (IST) of certain American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 pumps and valves are performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (ASME Code) and applicable addenda, except where altematives 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 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 Commission to approve attematives and to grant relief from ASME Code requirements upon making the necessary findings.
Guidance related to the development and implementation of IST programs is given in Generic Letter (GL) 89-04, " Guidance on Developing Acceptable Inservice Testing Programs," issued l April 3,1989, and its Supplement 1 issued April 4,1995. Also see NUREG-1482, " Guidelines for Inservice Testing at Nuclear Power Plants," and NUREG/CR-6396, " Examples, Clarifications, and Guidance on Preparing Requests for Relief from Pump and Valve Inservice Testing Requirements."
. The 1989 Edition of the ASME Code is the latest edition incorporated by reference in Section 50.55a(b). Subsection IWV of the 1989 Edition, which gives the requirements for IST of valves, references Part 10 of the American National Standards Institute /ASME Operations l and Maintenance Standards (OM-10) as the rules for IST of valves. OM-10 replaces specific i requirements in previous editions of Section XI, Subsection IWV, of the ASME Code.
Subsection IWP of the 1989 Edition, which gives the requirements for IST of pumps, references Part 6 of the American National Standards Institute /ASME OM-6 as the rules for IST of pumps. ,
OM-6 replaces specific requirements in previous editions of Section XI, Subsection IWP, of the i ASME Ccde.
Entergy Operations, Inc.'s (EOl's, the licensee's), IST program submitted in a letter dated I December 2,1997, covers the second 10-year IST interval for the River Bend Station (RBS),
which began on December 1,1997. In a separate letter dated January 6,1998, and i supplemented September 10,1998, EOl submitted one pump relief request and two valve relief requests for its second 10-year IST program. The staff's evaluation of these relief requests are provided herein.
Enclosure '
9904290101 990421
P PDR E
2.0 PUMP RELIEF REQUEST 2.1 Relief Reauest PRR-001 1 The licensee has requested relief from the vibration measurement requirements of OMa-1988,
)
Part 6 (OM-6), Paragraph 4.6.4(b), for the standby service water pumps and the diesel fuel oil i transfer pumps listed below. Paragraph 4.6.4 requires that vertical line shaft pump measurements shall be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction. The licensee has proposed to take vibration measurements in three orthogonal directions in a location that provides valid indication of motor vibratory motion in close proximity to the upper motor bearing housing.
SWP-P2A EGF-P1A SWP-P2B EGF-P1B l
. SWP-P2C EGF PIC I SWP-P2D 2.1.1 Licensee's Basis for Reauestina Relief The licensee states:
The standby service water pump motors are totally enclosed, weather proof induction motors that are equipped with housing covers which completely ens.aroud the upper motor bearing housing. The housing cover precludes vibration measurements from being taken directly on the upper bearing housing.
The diesel fuel oil transfer pumps are also equipped with housing covers that preclude vibration measurements from being taken directly on the upper motor bearing housing.
Removing the upper motor bearing housing covers for routine vibration readings, would compromise the design configuration and the operation of the pump motors. Cooling, thermocouples and other motor sensors would be disabled.
Also, the test configuration would differ greatly from normal configuration which would invalidate the test data obtained to prove operational readiness of the pump. This option is not practical.
Modifying the upper bearing housing cover to include an access port or installing vibration sensors is not preferred since these methods would change component configuration without a compensating inc. ease in safety. The transmission path for the attemate vibration points will not attenuate the vibration response or amplitude, therefore providing equivalent dLta without disturbing the equipment operation or design.
Therefore, the alternative testing proposed would provide adequate indication of component condition to verify operational readiness.
n9 2.1.2 Alternative Testing The licensee proposes:
Vibration measurements will be taken in three orthogonal directions in a location that provides valid indication of motor vibratory motion in close proximity to the upper motor bearing housing.
On the standby service water pumps the upper measurements will be taken on a lifting lug that is integral to the motor stator housing. The lifting lug is structurally rigid and provides transmissibility of the motor vibratory motion. The vibration j measurements will be taken in three orthogonal directions on the lifting lug. l On the diesel fuel oil transfer pumps the upper measurements will be taken on the motor stator housing which is rigidly connected to the motor bearing housing. 4 The vibration measurements will be taken in three directions on the motor stator I in close proximity to the motor bearing housing.
2.1.3 Evaluation The Code requires that quarterly vibration measurements be taken on vertical line shaft pumps during their regular inservice test. Since the actual pumps are submerged in water or oil, the Code requires that vibration measurements be taken on the upper motor bearing housing in three orthogonal directions, one of which is the axial direction. The licensee states that accat .
to the upper motor bearing housing for both the standby service water and diesel fue,I oil j transfer pumps is impeded by housing covers on all seven pumps. It would be a hardship without a compensating increase in safety for the licensee to modify the pump to perform the vibratic,n measurements if there were comparable locations on the pumps to collect vibration data.
The licensee has proposed to take vibration measurements from attemative locations that would provide vibration data, which was not attenuated from the upper motor bearing housing.
For the standby service water pumps, the licensee will take vibration measurements from a lifting lug that is integral to the motor stator housing. The vibration measurements for the diesel fuel oil transfer pumps would be taken from the motor stator housing, which is rigidly connected to the motor bearing housing. The licensee states that measurements will be taken in three orthogonal directions on all pumps as required by the Code.
The licensee's alternative locations for taking vibration measurements provide rigid structural contact to the motor bearing housing. The locations should not be subject to dampening effects that could mask potential degradation. Therefore, the licensee's proposed attemative testing will provide assurance of pump operability. In addition, the licensee should ensure that the new test locations are properly marked in accordance with OM-6, Paragraph 4.6.4(d), to ensure the validity of the vibration measurements upon implementation of the attemative testing.
F-2.1.4 Conclusion The proposed alternative to the vibration measurement requirements of OM-6, Paragraph 4.6.4(b), for the standby service water pumps and the diesel fuel oil transfer pumps ,
is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) based on the determination that compliance j with the specified requirements results in a hardship without a compensating intcrease in the level of quality and safety. A similar alternative was authorized for RBS in an NRC safety evaluation dated April 28,1997.
3.0 VALVE RELIEF REQUEST 3.1 Relief Reauest VRR-001 VRR-001 requests relief from the stroke time measurement requirements of ASME Code.
OM-10, Paragraph 4.2.1.4, for the affected main steam line safety / relief valves (SRVs) and automatic depressurization system (ADS) relief valves. These valves are located on the main steam lines between the reactor vessel and the first isolation valve inside the drywell.
3.1.1 Licensee's Basis for Heauestino Relief The licensee states: 1 The Safety Relief Valves are not equipped with direct position indicating devices.
Additionally, the actual valve stroke times are on the order of 100 mS. Use of other -
indicators of valve position (i.e. acoustic monitors, tailpipe temperature, vessel pressure) da not provide the accuracy required to use the stroke times, which would be obtained, for any meaningful use (i.e., degradation trending). The proper valve stem movement during actuation is verified during periodic shop testing.
Modification of the valves to provide direct position indication would be costly and would not provide a compensating increase in the level of safety gained by the availability of stroke time measurements.
3.1.2 Alternative Testina The licensee proposes:
No stroke time measurements will be performed. The valves will be full stroke exercise tested in accordance with ASME/ ANSI OMa-1988, Part 10. SRV tailpipe staam flow, reactor vessel pressure drop, or indication on the SRV tailpipe acoustic monitor will be used to provide positive indication of valve stroke.
3.1.3 Evaluation and Conclusion The Code requires that power-operated valves be stroked-timed in order to determine the I extent of any valve degradation. However, the affected SRVs and ADS valves are not equipped with direct position indicating devices, and additionally, the actual valve stroke times are on the order of 100 ms. Although the installation of direct positioning indicators may be physically possible, there are no feasible means to accurately measure the stroke time. To I
l I
O 5-require the installation of a device to directly measure stroke time would constitute z. hardship without a compensating increase in the level of quality and safety. The proposed means of using acoustic monitors, tailpipe temperature, and vessel pressure drop do not provide the accuracy for the required stroke time, but it would provide reasonable assurance of valve stroking and operational readiness of the affected valves.
The staff concludes that relief from the stroke time measurement requirements of OM-10, Paragraph 4.2.1.4, for the main steam SRVs and ADS valves is granted pursuant to 10 CFR 50.55a(a)(3)(ii) based on the determination thct compliance with the Code requirements results in a hardship without a compensating increase in the level of quality and safety and that the proposed attemative provides reasonable assurance of valve operability.
A similar alternative for the same valves was authorized for River Bend in an NRC safety evaluation dated November 24,1997.
3.2 Relief Reauest VRR-002 VRR-002 requests relief from the requirements of valve obturator movement of Paragraph 4.3.2.4(b) of OM-10 when a mechanical exerciser is used for the following check valves:
E22-AOVF005; E12-AOVF041 A; E12-AOVF041B; E12-AOVF041C; E21-AOVF006; E51-AOVF065; E51 AOVF066 3.2.1 Licensee's Basis for Reauestina Relief The licensee states:
Demonstration of valve obturator movement in accordance with Part 10, Paragraph 4.3.2.4(b) may not provide adequate assurance of valve operational readiness for check valves other than vacuum breakers. Measurement of the force or torque required to initiate movement (breakaway) may not be sufficient to verify that the listed valves are capable of stroking to their open safety position. Valve binding in excess of acceptable limits may occur at the obturator positions beyond the point of initial movement. This mode of valve degradation would not be identified by the procedure specified in Part 10, Paragraph 4.3.2.4(b).
The listed valves no longer have air actuators connected to the valves. Therefore, the valve actuators cannot be used to perform the Code required exercise testing.
Exercising the listed valves with flow would require using the Emergency Core Cooling System (ECCS) pumps to inject water into the reactor due to relatively high accident flow rates required for full stroke exercising of the valves. Additionally, the injection line nozzles associated with the Residual Heat Reinoval System are not equipped with internal spargers. General Electric Service Information Letter 401 identifies problems with injecting water through this flow path and potential damage to nuclear instrumentation or fuel assemblies which could occur if this flow path were used for other than emergency conditions. For these reasons performing the Code required check valve testing with flow creates a hardship without providing a compensating increase in the level of quality and safety.
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Part 10 also allows check valve disassembly at refuehg outages as an alternative to the valve obturator movement described in Paragraphs 4.3.2.4(a) or (b). However, check valve disassemoly is not a preferred attemative.
The proposed alternate testing is in accordance with a previously approved edition of the ASME Boiler and Pressure Vessel Code and will provide an acceptable level of quality and safety.
3.2.2 Alternative Testina The licensee proposes:
Obturator movement for the listed valves will be demonstrated in accordance with the 1980 Edition of the ASME Boiler and Pressure Vessel Code,Section XI,
. Paragraph IWV-3522(b), as follow:
A mechanical exerciser shall be used to move the disk. The force or torque delivered to tne disk by the exerciser will be limited to less than 10% of the equivalent force or torque represented by the minimum emergency condition pressure differential acting on the disk, or to 200% of the actual observed force or torque required to perform the exercise on the valve when the valve is new a.2d in good operating condition, whichever is less.
The force or torque required to full-stroke exercise the listed valves to the open position will be measured.
3.2.3 Evaluation and Conclusion Use of a mechanical exerciser to demonstrate valve obturator movement is permitted by OM-10, Paragraph 4.3.2.4(b), and Code relief is not required. However, Paragraph 4.3.2.4(b)
. requires specifically that the force or torque of initial movement (breakaway) be measured and
, compared to a reference value. Measuring the force or torque of the initial movement provides important information for determining how the valve would initially break away from its seat.
The proposed test, performed in accordance with Section XI, Paragraph IWV-3522, and previously allowed by the Code, does not require the measurement of, and comparison to a reference value, the breakaway force or torque. Therefore, the proposed test would not provide equivalent information required by OM-10, Paragraph 4.3.2.4(b). Also, the licensee has not demonstrated, at this time, that there is any hardship, burden or impracticality to performing the Code-required measurement of breakaway force or torque using the mechanical exerciser. ;
Therefore, relief request VRR-002 is denied. I It should be noted that the licens)e's proposed alternative of performing the test in accordance with Section XI, Paragraph IWV-3522 was previously allowed by the Code and would provide i useful information about a check va!ve. The staff considers use of Section XI, !
Paragraph IWV-3522 to be acceptable, and its use would not require relief if the force or torque of initial obturator movement is measured and compared to a reference value in accordance ;
. with Paragraph 4.3.2.4(b) of OM-10.
Principal Contributor: Y. S. Huang l
Date: April 21, 1999 L-