Event Tracking Sheet of 950123 Event Re Failure of 10 Inch Valve at Weld Joining & Adapter Plate & More Catastrophic Failure to Other Parts Due to Inclusion of Shims Contrary to Drawing| ML20149J435 |
| Person / Time |
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| Site: |
Prairie Island  |
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| Issue date: |
06/30/1997 |
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| From: |
Gray K
NRC |
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| To: |
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| Shared Package |
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| ML20149J390 |
List: |
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| References |
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| FOIA-97-177 NUDOCS 9707280218 |
| Download: ML20149J435 (2) |
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Category:ARCHIVE RECORDS
MONTHYEARML20196F2321998-11-21021 November 1998
Rev 0 to NSP-31Q-302, Evaluation of Limiting Flaws for Structural Adequacy on Lower Full Length CRDM Canopy Seal Weld
ML20236L2781998-07-0606 July 1998
Rev 0 to Calculation ENG-ME-170, Flooding of Unit 2 Loop a Msn Actuation Equipment
ML20217D2451998-03-17017 March 1998
Rev 0 to ENG-ME-355, Intake Canal Available Water Volume Comparison Analysis
ML20202F8931998-02-12012 February 1998
Rev 0 to SIC-98-009, Evaluation of Limiting Flaws for Structural Adequacy in CRDM Repair Adapter Plug Fillet Weld Evaluation at Prairie Island Unit 2
ML20205Q0041998-02-12012 February 1998
Rev 00 to NSP-27Q-301, CRDM Repair Adapter Plug Fillet Weld Evaluation
ML20217D2001998-02-0606 February 1998
Rev 0 to ENG-ME-347, Min Required Intake Bay Volume
ML20199J2281998-01-29029 January 1998
Rev 1 to Calculation NSP-26Q-302, Evaluation of Limiting Flaws for Structural Adequacy in Canopy Seal Repairs at Prairie Island Nuclear Plant
ML20198H3261997-07-29029 July 1997
Rev 0 to FAI/97-88, Verification Experiments for Waterhammer Events in Power Plant Svc Water Sys
ML20198H3771997-07-28028 July 1997
Rev 0 to FAI/97-68, Prairie Island Fan Coil Unit Analysis Using Tremolo 1.01. W/30 Oversize Drawings
ML20149J4871997-06-30030 June 1997
Event Tracking Sheet of 960408 Event Re Crane Valves. Provides Update on Continuing Efforts to Evaluate Whether Erroneous Data to Set Torque Switches for MOVs Supplied to Licensees During mid-1980s.No Contractural Evidence Found
ML20149J4351997-06-30030 June 1997
Event Tracking Sheet of 950123 Event Re Failure of 10 Inch Valve at Weld Joining & Adapter Plate & More Catastrophic Failure to Other Parts Due to Inclusion of Shims Contrary to Drawing
ML20210U3261997-04-23023 April 1997
Rev 0 to FAI/96-107, Experimental Data to Simulate Possible Water-Hammer Loads in Prairie Island Svc Water Sys for DBA Conditions
ML20198H3381996-10-31031 October 1996
Evaluation of Possible Water-Hammer Loads in Prairie Island Svc Water Sys for DBA Conditions
ML20134D2231996-10-17017 October 1996
Press Release III-96-63, Aerial Radiation Measurements Planned for NPPs in Wisconsin & Minnesota
ML20210U3191996-09-0909 September 1996
Rev 0 to FAI/96-77, Assessment of Prairie Island Fan Cooler Piping Loads
ML20112E2801995-10-30030 October 1995
Rev 1 to Calculation PI-NSP-95-002, Conductor Temp in Conduits Wrapped W/One H Darmatt Fire Barrier
ML20059B4181993-10-17017 October 1993
Notation Vote Approving SECY-93-269, Proposed License,Under 10CFR72,for Dry Storage of Spent Fuel at Northern States Power Co Prairie Island Nuclear Generating Plant
ML20059B3331993-10-13013 October 1993
Notation Vote Approving SECY-93-269, Proposed License,Under 10CFR72,for Dry Storage of Spent Fuel at Util Plant
ML20059B4151993-10-0808 October 1993
Notation Vote Approving SECY-93-269, Proposed License,Under 10CFR72,for Dry Storage of Spent Fuel at Northern States Power Co Prairie Island Nuclear Generating Plant
ML20059B4121993-10-0707 October 1993
Notation Vote Approving SECY-93-269, Proposed License,Under 10CFR72,for Dry Storage of Spent Fuel at Northern States Power Co Prairie Island Nuclear Generating Plant
ML20058P1301993-07-29029 July 1993
Package Consisting of Attachment to Employee Concerns Programs
ML20079N4161991-11-11011 November 1991
Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Including,Ecological Studies,Water Chemical Analysis,Reproductive study,1987 Progress Rept & 316(a) & (B) Demonstration Study
ML20151P1671988-07-0707 July 1988
Annual Rept of Changes,Tests & Experiments for 1987
ML20151M9601987-07-20020 July 1987
Package of NRC Administered Requalification Exam Results Summary
ML20215F5381986-08-21021 August 1986
Nonproprietary Slide Presentation Entitled, Nrc/Northern States Power/Westinghouse Joint Technical Exchange:Shape Memory Alloy Sleeving, Presented on 860821
ML20203H2851986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
ML20077K7031983-02-23023 February 1983
Nonproprietary Version of Slides Presented at 830223 Meeting Re Fuel Assembly Degradation
ML19305D1471980-03-19019 March 1980
Viewgraphs Presented at 800319 Meeting W/Nrc Re Fuel Pool Mod
ML19305D2151980-02-12012 February 1980
Viewgraphs Presented at 800212 Meeting W/Nrc & Util Re Steam Generator Insp
1998-07-06
[Table view]
Category:PACKAGE OF NONCODED MATERIAL
MONTHYEARML20149J4871997-06-30030 June 1997
Event Tracking Sheet of 960408 Event Re Crane Valves. Provides Update on Continuing Efforts to Evaluate Whether Erroneous Data to Set Torque Switches for MOVs Supplied to Licensees During mid-1980s.No Contractural Evidence Found
ML20149J4351997-06-30030 June 1997
Event Tracking Sheet of 950123 Event Re Failure of 10 Inch Valve at Weld Joining & Adapter Plate & More Catastrophic Failure to Other Parts Due to Inclusion of Shims Contrary to Drawing
ML20058P1301993-07-29029 July 1993
Package Consisting of Attachment to Employee Concerns Programs
ML20079N4161991-11-11011 November 1991
Responds to NUMARC Survey in Support of NRC License Renewal Rulemaking Including,Ecological Studies,Water Chemical Analysis,Reproductive study,1987 Progress Rept & 316(a) & (B) Demonstration Study
ML20151P1671988-07-0707 July 1988
Annual Rept of Changes,Tests & Experiments for 1987
ML20151M9601987-07-20020 July 1987
Package of NRC Administered Requalification Exam Results Summary
IA-86-445, Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 8201311986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
ML20203H2851986-07-28028 July 1986
Package of Documents Re Operating Experience W/Westinghouse PWR Steam Generators Through 820131
1997-06-30
[Table view] |
Text
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-j EVENT FOLLOW-UP ASSIGNMENT SHEET No Sort Specified QUERY > "HUNEMULLER" S Assigned To & Assigned Date >= 01/23/95 & Assigned Date <= 01/23/95 & " CRANE" 5 Plant Name ASSIGNMENT DATE:
01/23/95 ASSIGNED TO:
HUNEMULLER N.
PLANT & UNIT:
CRANE-ALOYCO EVENT DATE:
01/23/95 50.72 REPORT NO:
0 DAILY REPORT DATE:
01/20/95 OTHER REPORT:
ALSO SEE MR H-95-0010 EVENT DESCRIPTION CRANE VALVES / NUCLEAR OPERATIONS REPORTS FAILURE OF 10" VALVE (FIGURE 63174) AT WELD JOINING YOKE AND ADAPTER PLATE AND MORE CATASTROPHIC FAILURE TO OTHER PARTS DUE TO INCLUSION OF SHIMS CONTRARY TO DRAWING. PART OF ORDER FOR WESTINGHOUSE IN EARLY 70s.
SPECIFIC FOLLOW-UP ASSIGNMENT DETERMINE DETAILS, EVALUATE SAFETY SIGNIFICANCE AND GENERIC IMPLICATIONS. IN ADDITION, ADDRESS THE FOLLOWING SPECIFIC CONCERNS: DETERMINE IF THIS IS RELATED TO CRANE VALVE YOKE ISSUE AT PEACH BOTTOM THAT HAD PREVIOUS FOLLOWUP AS QUICKLY AS POSSIBLE DETERMINE IF USED IN A SAFETY-SIGNIFICANT APPLICATION. COORDINATE WITH EMEB.
3AFETY SIGNIFICANCE:
SIGEVENT AO OTHER OR CRIEFING:
EVENT FOLLOW-UP REPORT: INFORMAL CLOSEOUT DESCRIPTION CLOSEQUT: A Containment Isolation Valve at the Prairie Island Nuclear Plant was damaged as a result of operctional problems involving maintenance procedures. The valve in question was a Crane 10", Figure 63174.
An cv:luation of the original valve order retrieved from Crane archive records identified many of the utilities to whom valves, purchased by Westinghouse Electric, were shipped. This enabled Crane Valves Nuclear Operat bns (CVNO) to send a special letter to these utilities discussing the incident, providing a technical discussion, and effering analytical engineering support. Analysis of the as-built valve configurations brought to CVN0's cttention indicates there is adequate thrust capacity with respect to design basis. Based on its evaluation of this matter, and given the relevant f acts and circunstances, CVNO concluded that the valve design of Figure 63174, when instatted and operated properly does not constitute a reportable item under 10 CFR Part 21.
Tha Mechanical Engineering Branch (EMEB) reviewed the vendor's Part 21 Final Report. EMEB initially believed th;t this issue was related to en ongoing review of Crane's weak link analysis (Part 21 #95024), but upon further review has determined this yoke / adapter plate weld issue has been adequately addressed.
The Generic Issues and Events Assessment Panel screened this issue on February 14, 1995. The Panel classified its slenificance as "Other," and determined that there was no need for a generic consnunication.
R3f:rences:
- 1. January 12, 1995, Crane letter, " Final Report on 10 CFR Part 21 Evaluations," (Accession No. 9501200336)
SUBMITTED BY: HUNEMULLER N.
DATE: 08/15/96 APPROVED BY:
R. DENNIG DATE: 08/16/96 CLOSEOUT NARRATIVE ENTERED:
K. Gray DATE: 08/19/96 ETM*
Page:1 06/30/97 9707200218 970722 PDR FOIA FOWLER 97-177 PDR
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EVENT FOLLOW-UP ASSIGNMENT SHEET No Sort Specified QUERY) "HUNEMULLER" $ Assigned To & Assigned Date >= 01/23/95 & Assigned Date <= 01/23/95 & " CRANE" $ Plant Name CLOSEOUT DESCRIPTION (Continued)
(P rt 21 #95024).
- 2. January 27, 1995, Crane letter, " Final Report on 10 CFR Part 21 Evaluation of Crane Valves Installed with Shim Between Yoke and Adapter Plate," (A; cession No. 9504110027) (Part 21 #95035).
- 3. August 30, 1994, Crane letter, " Potential 10CFR21 Condition," (Accession No. 9409140324) (Part 21 #95006).
- 4. April 14,1994, Northern States Power Company letter, " Reply to a Notice of Violation NRC Inspection Report Nos. 282/94002(DRP) and 306/94002(DRP) Procedural Deficiency Allowing Damage to a Safety related Valve,"
(Acceshion No. 9404220188).
- 5. Daenber 28, 1994, Crane letter, " Interim Report #2 of 10CFR Part 21 Evaluation," (Accession No. 9501040170)
(P rt 21 #95007).
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