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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation ML20203B9591997-09-18018 September 1997 Pressure Locking Summary & Evaluations Using Commonwealth Edison Methodology for Sqn ML20210J1761997-07-31031 July 1997 Unit 1,Cycle 9 Alternate Plugging Criteria 90 Day Rept ML20138D1991997-04-0404 April 1997 Special Project97-928S, Sequoyah Nuclear Plant Assessments ML20138C5371997-03-24024 March 1997 Rev 0 to Pressurizer Level Event ML20217G2401997-03-0303 March 1997 Non-proprietary Rev 0 to SE of Reduced Thermal Design Flow ML20117J3611996-08-0101 August 1996 SE of Safety Valve Setpoint Tolerance Relaxation ML20117K9461996-03-0505 March 1996 Reliability Study ML20117K9511996-02-29029 February 1996 Reliability Common Cause Assessment, for Feb 1996 ML20095J1891995-10-0505 October 1995 Design & Analysis of Weld Overlay Repair for Sequoyah Unit 1 CRDM Lower Canopy Seal Welds ML20081D3831995-03-12012 March 1995 Simulator Four Yr Test Rept for 950312 ML20083N9521994-11-16016 November 1994 10CFR50.59 Rept to Nrc ML20024H8491993-07-19019 July 1993 Evaluation of Ultrasonic Test Results from 1993 ISI on Underclad Flaw Indications in Sequoyah,Unit 1 Rv Nozzles. ML20118D1941992-09-21021 September 1992 Technical Rept on Hydrogen Control Measures & Effects of Hydrogen Burns on Safety Equipment ML20114A6641992-08-15015 August 1992 920619 Self-Assessment. Several Hardware & Software Enhancements to Emergency Response Ctrs Completed During Reporting Period ML20141M1341992-03-27027 March 1992 Spent Fuel Pool Mod for Increased Storage Capacity ML20029C2011991-03-12012 March 1991 Initial Simulator Certification. ML20028H8591990-09-0707 September 1990 Nuclear Quality Audit & Evaluation Review Rept, Sequoyah Nuclear Plant Look Back Review of Cable Issues. ML20136J0431990-06-30030 June 1990 Criticality Analysis of Sequoyah Units 1 & 2 Fresh Fuel Racks ML20043B6061990-05-11011 May 1990 Diesel Generator Voltage Response Improvement Rept. ML20006E5771990-02-0505 February 1990 Rev 1 to Sequoyah Units 1 & 2 Spent Fuel Storage Rack Criticality Analysis. ML20246D5351989-02-28028 February 1989 Steam Generator Tubing Insp Results ML20247H1301988-11-30030 November 1988 Rev 0 to Structural Analysis & Evaluation of Sequoyah Reactor Coolant Pump Support Columns ML20236D1951988-11-18018 November 1988 HVAC Damping Values ML20134H6801988-09-0202 September 1988 Technical Evaluation of Procurement of Matls & Svcs ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20151Q2691988-08-0101 August 1988 Final Rept on IE Bulletin 79-14 for Tva,Sequoyah Nuclear Plant Unit 1 & Common Piping ML20155J5721988-07-31031 July 1988 Assessment of Structural Adequacy of Concrete Foundation Cells for Emergency Raw Cooling Water Pumping Station & Access Roadway ML20207F6231988-07-0505 July 1988 Evaluation of Effects of Postulated Pipe Failures Outside of Containment for Sequayah Nuclear Plant,Units 1 & 2 ML20207B6301988-06-27027 June 1988 Engineering Assurance Oversight Review Rept,Sequoyah Nuclear Plant - Unit 1,Design Baseline & Verification Program ML20147G9961988-03-31031 March 1988 Review of Operational Readiness Corrective Actions. Related Documentation Encl ML20147H6331988-02-29029 February 1988 Plant,Diesel Generator Evaluation Rept ML20147G7861988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 1:Design Basis SSE Input ML20147G8041988-02-25025 February 1988 Task Rept on Development of Seismic Acceleration Response Spectra for Diesel Generator Bldg of Sequoyah Nuclear Plant, Part 2:Site-Specific OBE & SSE Inputs ML20234F2111988-01-0505 January 1988 Rept of Sequoyah Readiness Review ML20147F0581987-12-0202 December 1987 Non-linear Time History Seismic Response Analyses for ERCW Cell, Task Rept ML20236B3481987-10-15015 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 207.4(B), Deviation Documentation:Caq Documentation ML20236B3511987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 232.8(B), Piping & Valve Design:Criteria for Min Pipe Wall Thickness ML20236B3541987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 235.2(B), Electrical Safety:Exposed 480 Volt Bus at Panel Top ML20236B3441987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Sequoyah Element Rept 204.9(B), Use of Reverse Prints ML20236B3581987-10-14014 October 1987 Rev 0 to TVA Employee Concerns Special Program Seqouyah Element Rept 241.4(B), Cable Termination & Splices:Amphenol Connector ML20236Q2011987-10-0101 October 1987 Temp Measurement Rept for Long-Term Current Test on Littlefuse,Flas-5,5 Amp Fuses 1999-08-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
Text
.
. TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B)
SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER:
{ 1 TITLE: PIPE SUPPORT DESIGN Observed Bending of Pipe Clamp Ears PAGE 1 0F 8 REASON FOR REVISION:
- 1. To incorporate SRP and TAS comments, to include TVA's corrective action plan information (See Section 10), and to comply with current format.
PREPARATION
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CONCURRENCES 8701120017 870102 .
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- SRP Secretary's signature denotes SRP concurrences are in files.
DATE j ,
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s.((\ 3 W h . 11._ __ i.?l?t lpt . N/A l U ECSP MANAGER DATE '- MANAGER OF NUCLEAR POWER DATE j ( CONCURRENCE (FINAL REPORT ONLY)
1 a
TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 1
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PAGE 2 0F 8 l
- 1. CHARACTERIZATION OF ISSUE (S):
Concern: Issues:
IN-85-305-001 a. Excessive torque on bolts caused l "Over a period of time the bending of clamp ears.
bending of ears on small 8001 support clamps will cause the b. Clamps were modified to A-36 material to yield beyond prevent this bending but l its yield point. Clamps are the clamp manufacturer's installed in both units. (WBNP)." concurrence was not obtained.
- 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES X NO Identified by Quality Technology Company (0TC) l Date 03/25/86 Documentation Identifiers:
Employee Response Team (ERT) Investigation Report for Watts Bar l Nuclear Plant (WBNP) employee concern No. IN-85-305-001.
(
- 3. DOCUENT NOS., TAG NOS., LOCATIONS, OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEMENT.
B001 Support Clamps A-36 Material Both units (WBNP)
- 4. INTERVIEW FILES REVIEWED:
Review of interview files for concern No. IN-85-305-001 shows the following information:
o Generic applicability determination form (Form G-A) o Employee concern assignment request (K-form) o ERT invesitgation report by QTC (03/26/86) o Request for reportability evaluation (ERT Form M) k 0995d - December 09, 1986
l TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 <
l l PAGE 3 0F 8 ;
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
- 6. WHAT REGULATIONS, LICENSING C0PMITMENTS, DESIGN REQUIREMENTS, OR OTHER APPLY OR CONTROL IN THIS AREA?
See Appendix A.
- 7. LI.cf REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER
@CUSSIONSRELATEDTOELEMENT.
See Appendix A.
- 8. , EVALUATION PROCESS:
- a. Investigated toque value specified for SQN for B001 support l clamps.
c' b. Performed calculation te determine if SQN specified toque is l k excessive and could cause bending of ears.
- c. Determined if these clamps were modified by welding l
stiffeners to them to prevent them from bending, d Ascertained if vendor approval was obtained and documented if the clamps were modified. l
- 9. DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
08/12/76: Revision 0 of drawing 47B001-12 issued. Toque values for run line clamps are specified in this document.
l 07/19/77/ Revision 0 of drawings 478001-14 and 47B001-14A 02/07/78: issued. Toque values for branch line clamps are specified in these documents.
l 07/01/77: Civil Engineering Branch (CEB) report No. 75-18, Rev.1 issued.
10/25/77: CEB Report No. 77-42 for static pipe support tests and development for Sequoyah (SQN) Units 1 and 2 issued.
l 0995d - December 09, 1986 l-
TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 ,
(~-
PAGE 4 0F 8 05/15/78: Current revision (Revision 5) of 478001-12 issued.
06/16/78 Current revisions (Revision 4) of 478001-14 and 06/78: (Revision 1) of 478001-14A issued.
05/22/84: Current revision (Revision 3) of CEB-75-18 issued.
05/31/85: TVA receives the employee concern.
03/25/86: ERT investigation report of this concern.
04/01/86: WBNP preliminary perception of the employee concern (memo from J. C. Standifer to R. G. Domer).
Discussion:
The concern as stated is that over a long period of time the ears on small 8001 support clamps will bend because of excessive torguing and that this bending will result in stressing A-36 i material beyond its yield point.
to B001 Seismic Category I type supports are used to support drain lines, instrument sensing lines, sampling lines, radiation monitoring lines, and test and process lines containing isolation valves. These lines are called branch lines. The supports consist of a stanchion pipe welded directly to the run line or to the clamp which is fastened to the run line. Similarly the branch line is welded or clamped to the stanchion. Adequacy of the branch line and run line clamp when over-torqued is the concern which will be addressed in this discussion, Drawings 478001-14,14A & -12 specify a tonaue value of 5 to 10 f t-lb (depending on the size of the bolt) for branch line clamps and 100 ft-lb for run line clamps (regardless of clamp and bolt size). The 100 ft-lb value may have arisen from a test program (App. A, 5.a and 5.e) that specified this value for Bergen-Patterson clamp #298 for all pipe sizes.
Drawing No. 478001-12, Rev. 5 and CEB Report No. 77-42 specify tonaue values for the bolts, whereas CEB Report No. 75-18, under the tabulation of parameterc for anchor clamp, specifies preload values for the bolts. To establish a relationship between preload and tonaue values, the evaluation team calculated tongue values for
(
i 0995d - December 09, 1986 I -
\
TVA EMPLOYEE CONCERNS REPORT NUM8ER: 221.6 (B) l SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 5 0F 8 clamp sizes for 2-1/2-inch to 30-inch-diameter pipe. For comparison purposes, preload and toque values for a 3/4-inch-diameter bolt of a 2-1/2-inch-diameter pipe clamp are listed below:
Reference Preload (1b) Toque (f t-lb)
App. A, 5.d & 5.a --
100 App. A, 5.b 2,800 --
App. A, 5.c 2,800 42 (Bechtel calc.) 6,667*
- Bolt load corresponding to 100 f t-lb toque value.
The above tabulation shows that a toque value of 100 f t-lb will produce a preload almost 2-1/2 times the value indicated in App. A, 5.b or, alternately, the actual toque required is about 40 percent of what was specified for installation of these clamps. Therefore, it is evident that the 8001 support clamps were over-stressed by over-toq uing of the bolts and the ears could have been bent, especially for smaller size pipe clamps. Instead of reducing the toque value to a value compatible to the bolt preload, WBNP welded stiffeners to these clamps to prevent them from bending. This is discussed in the ERT investigation report referenced in section 2.0. SQN did not weld stiffeners to the clamps.
Welding stiffeners to the clamps is likely to prevent bending of I clamp ears, but it causes the specified preload in the bolts to be exceeded. The excessive toque value for installation of these clamps should be reduced to be compatible with the capacity of the clamps and bolts. The clamps, if damaged or determined to be ineffective for their intended function, should be replaced and installed at the lower toque value equivalent to the specified bolt preload.
Findings:
- a. There could be no bending of ears for the small bore pipe l branch line clamps because the toque values specified for their installation were reasonable.
- k. .
0995d - December 09, 1986
TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B) l SPECIAL PROGRAM REVISION NUMBER: 1 I PAGE 6 0F 8 There would be bending of ears for the run line clamps because excessive torque value was specified for their i installation. This excessive torque could also cause !
-over-stressing and failure of clamp bolts.
- b. SQN did not modify pipe clamps to prevent them from bending.
Conclusion:
The concern is valid for the run line clamps but not for the branch line clamps. The torque value specified in drawing 47B001-12, Rev. 5, for installation of B001 type support, is excessive. This excessive torque could cause bending of ears of clamps on the run line or overstress the bolts.
- 10. CORRECTIVE ACTION:
In its corrective action plan (CAP) (App. A, 5.g), TVA will revise drawing 478001-12 to provide appropriate bolt torque values for the clamps listed. A plant survey will be performed to identify and
(-' evaluate B001 type supports that may have been installed with excessive torque applied to the clamp bolts. The evaluation team concurs with this CAP.
(.
0995d - December 09, 1986
TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B) l SPECIAL PROGRAM l REVISION NUMBER: 1
?
f' PAGE 7 0F 8 I
APPENDIX A
- 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
- a. CEB Report No. 77-42, " Static Pipe Support Tests and Development - SQN 1 & 2," (10/25/77)
- b. CEB Report No. 75-18, Rev. 3, "Small Line Attachment Details to Class 2 and 3 Piping Equal to or Larger Than 2-1/2 Inch Diameter," (05/22/84), Rev.1 (07/01/77)
- c. Bechtel Calculation No. PD-221-14, (09/04/86)
- d. Drawings 478001-1 through -17, titled " Mechanical Branch Valve Connection Seismic Support. Seismic Class I Structures"
- e. Memo from J. C. Standifer to R. G. Domer, "WBNP - Employee Concern IN-85-305-001," (04/01/86)
- f. Nuclear Performance Plan (NPP), Volume II, Rev. 1,(07/14/86) l
(":,: TCAB002, Corrective Action Plan (CAP), (11/05/86) g.
- 6. WHAT REGULATIONS, LICENSING C0pmITMENTS, DESIGN REQUIREMENTS, OR OTHER APPLY OR CONTROL IN THIS AREA?
- a. Drawing 478001-12, Rev. 5, (05/15/78)
- b. Drawing 478001-14, Rev. 4, (06/16/78)
- c. Drawing 478001-14A, Rev.1, (06/78)
- d. CEB Report No. 75-18, Rev. 3, (05/22/84)
- 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER
- DISCUSSIONS RELATED TO ELEMENT.
- a. TVA Transmittal #077, (07/17/86)
- b. RFI #SQN-519, (08/28/86)
- c. WBNP RFI #088, (05/29/86)
_ d. WBNP RFI #031, (04/17/86)
L 0995d - December 09, 1986 i
? -
TVA EMPLOYEE CONCERNS REPORT NUMBER: 221.6 (B)
SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 8 0F 8 CATD LIST The following CATD identifies and provides corrective action for the findings included in this report:
221.06 SQN 01 (10/21/86)
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l 0996d - December 09, 1986
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REFERENCE - ECPS120J-ECPS121C TENNESSEE VALLEY AUTHORITY PAGE -
97 FREQUENCY - REQUEST OFFICE OF NUCLEAR POWER RUN TIME - 12:57:19 l ONP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM (ECPS) RUN DATE - 12/02/86 LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 22106 OBSERVED BENDING OF SMALL-BORE PIPE CLAMP EARS
) S GENERIC KEYHORD A H APPL QTC/NSRS P KEYHORD B CONCERN SUB R PLT BBSH INVESTIGATION S CONCERN KEYHORD C g NUMBER CAT CAT D LOC FLQB REPORT R DESCRIPTION KEYHORD D IN 305-001 EN 22106 N HSil YYYY SR OVER A PERIOD OF TIME THE BENDING OF PROCEDURES T50021 REPORT EARS ON SMALL B001 SUPPORT CLAMPS H INSTALLATION ILL CAUSE THE A-36 MATERIAL TO YIELD HANGERS 3- BEYOND ITS YIELD POINT. CLAMPS ARE PIPE INSTALLED IN BOTH UNITS CHBNP5 1 CONCERNS FOR CAT 5 .EGORY 22106
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