Relief Request BV3-IWA-2,Rev 0 to Class 1,2 & 3 Bolting Removal Due to LeakageML20137G479 |
Person / Time |
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Site: |
Beaver Valley |
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Issue date: |
03/12/1997 |
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From: |
DUQUESNE LIGHT CO. |
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To: |
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Shared Package |
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ML20137G377 |
List: |
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References |
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PROC-970312-07, PROC-970312-7, NUDOCS 9704010404 |
Download: ML20137G479 (2) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 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August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements 1999-09-22
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20211K6871998-11-30030 November 1998 Issue 2,Rev 1 to Inservice Testing (IST) Program for Pumps & Valves ML20205F6961998-11-30030 November 1998 Revs to Offsite Dose Calculation Manual ML20154D5241998-08-14014 August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20249A8671998-03-0606 March 1998 Rev 1H to BVPS Unit 1 IST Program for Pumps & Valves ML20217K0591997-12-31031 December 1997 Offsite Dose Calculation Manual for Units 1 & 2 ML20217G7261997-12-15015 December 1997 Relief Request 1-TYP-2-B5.40-1,Rev 0 to Pressurizer Nozzle to Safe End Welds ML20202B2511997-10-0303 October 1997 Pressure Testing Program for Third Ten-Yr Interval at Bvps,Unit 1 & Second Ten-Yr Interval at Bvps,Unit 2,Relief Request BV3-IWA-2,Rev 1, Re Class 1,2 & 3 Bolting Removal Due to Leakage ML20217B2941997-07-0202 July 1997 Rev 0 to 1TYPP-3, ISI Ten Year Plan for Third Interval at Beaver Valley Power Station Unit 1. W/22 Oversize Drawings ML20140C0151997-05-30030 May 1997 Issue 2,Rev 0 to 2nd Ten-Year Interval Update of BVPS-2 IST Program ML20196G3181997-04-17017 April 1997 Rev 16 to IST Program for Pumps & Valves ML20137T2201997-04-0909 April 1997 Rev 8 to 2OM-53C.4.2.6.4(ISS1A), SG Tube Leakage ML20137T2331997-04-0909 April 1997 Rev 8 to 1OM-53C.4.1.6.4(ISS3A), SG Tube Leakage ML20148A9501997-03-21021 March 1997 Rev 0,Issue 3 to IST Program for Pumps & Valves ML20137G4551997-03-12012 March 1997 Relief Request BV2-B3.110-2,Rev 0 to Pressurizer Nozzle-to-Vessel Welds ML20137G4221997-03-12012 March 1997 Relief Request BV1-B3.120-2,Rev 0 to Pressurizer Surge Nozzle Inner Radius Section (RC-TK-1-RADIUS-6) ML20137G4081997-03-12012 March 1997 Relief Request BV1-RV-WELDS,Rev 0 to Reactor Vessel Circumferential Welds (RC-R-1-C-1 & RC-R-1-C-8) ML20137G4351997-03-12012 March 1997 Relief Request BV1-B9.31-2,Rev 0 to Reactor Coolant Sys Branch Connection Welds ML20137G4651997-03-12012 March 1997 Relief Request BV3-IWA-1,Rev 0 to Insulation Removal for Class 1 & 2 Bolted Connections Located Inside Containment ML20137G4591997-03-12012 March 1997 Relief Request BV2-D2.20-1,Rev 0 to Svc Water Sys Welded Attachments ML20137G4791997-03-12012 March 1997 Relief Request BV3-IWA-2,Rev 0 to Class 1,2 & 3 Bolting Removal Due to Leakage ML20137G4441997-03-12012 March 1997 Relief Request BV2-B1.11-1,Rev 0 to Reactor Vessel Lower Circumferential Weld (2RCS-Rev21-C-4) ML20141D2021996-04-26026 April 1996 Rev 14 to Updated IST Program Issue 2 ML20101L7871995-10-11011 October 1995 Unit 2 Offsite Dose Calculation Manual ML20096D3811995-09-26026 September 1995 Issue 1,Rev 15 to Beaver Valley Unit 2 Inservice Testing Program for Pumps & Valves ML20093D6751995-09-19019 September 1995 Rev 0 to BVPS SSFI Technical Assessment Plan for Unit 1 - Safety Injection Sys ML20096D3301995-07-24024 July 1995 Issue 2,Rev 13 to Beaver Valley Unit 1 Inservice Testing Program for Pumps & Valves ML20095B5171995-07-0707 July 1995 Proposed Rev 2E to BVPS Unit 2 IST Program for Pumps & Valves ML20095B5091995-07-0707 July 1995 Proposed Rev 1G to BVPS Unit 1 IST Program for Pumps & Valves ML20085J6021995-04-28028 April 1995 Issue 1,Rev 14a to BVPS Unit 2 IST Program for Pumps & Valves ML20085L0211995-03-24024 March 1995 Rev 12A,Issue 2 to Duquesne Light Co Beaver Valley Power Station Unit 1 IST Program for Pumps & Valves ML20078G9671994-09-30030 September 1994 Rev 13,Issue 1 to Beaver Valley Power Station Unit 2,IST Program for Pump & Valves ML20072Q9281994-07-18018 July 1994 Proposed Rev 2D to BVPS Unit 2 IST Program for Pumps & Valves ML20072Q9191994-07-18018 July 1994 Proposed Rev 1F to BVPS Unit 1 IST Program for Pumps & Valves ML20065S3781994-03-25025 March 1994 Proposed Rev 2C to Beaver Valley Power Station Unit 2 IST Program for Pump & Valves ML20029D8541994-03-25025 March 1994 Proposed Rev 1E to BVPS Unit 1 IST Program for Pump & Valves. ML20063H2051993-11-19019 November 1993 Rev 11,Issue 2 to Inservice Testing (IST) Program for Pumps & Valves ML20067A3261993-11-18018 November 1993 Rev 12,Issue 1 to Beaver Valley Unit 2 IST Program for Pumps & Valves ML20058P8591993-10-20020 October 1993 Bvps,Units Odcm ML20058P9231993-09-14014 September 1993 IST Program for Pump & Valves, Issue 1,Rev 11 ML20045E2291993-06-17017 June 1993 Odcm. ML20045E1201993-03-25025 March 1993 Issue 2,Rev 9 to Bvps,Unit 1 IST Program for Pump & Valves. ML20045E1191993-01-29029 January 1993 Revised Proposed Rev 1D to Bvps,Unit 1 IST Program for Pump & Valves. ML20116B3271992-08-24024 August 1992 Issue 1,Rev 10 to Inservice Testing Program for Pump & Valves 1999-03-25
[Table view] |
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- 6 PRESSURE TESTING PROGRAM AT BVPS UMIT #1, FOR THE THIRD TEN-YEAR INTERVAL AND BVP2 UNIT #2, FOR THE SECOND TEN-YEAR INTERVAL RELIEF REQUEST BV3-IWA-2, REV. O
SUBJECT:
Class 1,2, and 3 Bolting Removal Due to Leakage Prepared by: U DEd Date: 6fd0f97 Supenisor, Inspection and Standards Resiewed by: # /A Date: 3-ll-h 5 Director, Nuclear Analysis and Inspegan Reviewed by: D -DhC.-b 97 Date: 8/'d /f 7 OSC Meeting No.
Reviewed by: TNAM4 Mo . $I- I Date: d/ % /f7 ORC Meeting No.
Approval by: .s , [~
'_' c- Date: _?-/ 2 O )
Div. VP, Nucle'ar Operations / Plant Manager 9704010404 970325 PDR ADOCK 05000334 G PDR k r
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- . DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit Nos. I and 2 RELIEF REOUEST NO. BV3-lWA-2 Rev. 0 l
COMPONENT ,
i Class I,2, and 3 pressure retaining bolted connections. l ASME CODE SECTION XI REOUIREMENT (1989 Edition) i ASME Section XI,1989 Edition, Subparagraph IWA-5250(a)(2) states, "ifleakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100,"
i BASIS OF RELIEF In accordance with 10CFR50.55a(a)(3)(ii) reliefis requested from the ASME bection XI,1989 Edition, Subparagraph IWA-5250(a)(2) requirement that ifleakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100. Compliance with the Code requirements would result in hardship and unusual difficulty without a compensating increase in the level ;
of quality and safety. Leakage at a bolted connection may be a significant variable in the degradation mechanism of bolted connections. However, leakage is not the only variable and in some cases may not be the degradation mechanism. Bolting materials, leaking medium, duration of the leak, and location of the leak are other variables l to be considered. Removal of bolting at a mechanical connection may not be the most prudent decision to make. l All variables should be considered before disassembling a bolted connection for a sisual VT-3 examination.
Duquesne Light proposes an alternative to the requirements ofIWA-5250(a)(2) that will provide an equivalent level of quality and safety at Class 1,2, and 3 bolted connections.
PROPOSED ALTERNATIVE EXAMINATION Leakage on Code Class I, 2, and 3 bolted connections shall be evaluated to determine the susceptibility of the bolting to corrosion and potential future failure. This review will consider as a minimum, location ofleakage, history ofleakage, bolted connection materials, visual evidence of corrosion with the connection assembled, corrosiveness of the process fluid, history and studies of similar bolted material in a similar emironment, and other components in the vicinity that may be degraded due to the leakage. If the leakage was identified with the bolted connection in senice and the review supports continued senice, the VI' 3 examination may be deferred to the next outage of sufficient duration. If this review warrants further evaluation of the bolted connection, the bolt closest to the leakage source shall be removed, VT-3 examined, and evaluated in accordance with IWA-3100(a). When the removed bolt has rejectable degradation, the remaining bolts will be removed, VT-3 examined and evaluated in accordance with IWA-3100(a). If no degradation is observed on the removed bolt, no further action will be required.
Duquesne Light requests NRC approval of the proposed alternative requirements for Class 1,2, and 3 bolted connections in lieu of those ofIWA-5250(a)(2). NRC approval is requested in a time frame that will support implementation of the alternative requirements for the Unit I twelfth refueling outage currently scheduled to begin in September of 1997 Unit I twelfth refueling outage will be the first outage of the third ten year in crval at Beaver Valley Power Station Unit No.1. The second ten year interval at Beaver Valley Pour Station Unit No. 2 will begin November 17,1997.
,