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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 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 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) ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively 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 ML20236S4081998-07-0101 July 1998 Safety Evaluation Supporting Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively ML20248L1961998-06-0808 June 1998 Safety Evaluation Supporting Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively 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 ML20216E4701998-03-0909 March 1998 Safety Evaluation Approving Exemption from Updated FSAR Requirements of 10CFR50.71(e)(4) for Sequoyah Nuclear Plant,Units 1 & 2 ML20203K6811998-02-20020 February 1998 Safety Evaluation Supporting Amends 231 & 221 to Licenses DPR-77 & DPR-79,respectively ML20198P9171998-01-13013 January 1998 Safety Evaluation Supporting Amend 230 to License DPR-77 ML20217D7881997-09-29029 September 1997 Safety Evaluation Supporting Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively ML20211G2061997-09-23023 September 1997 Safety Evaluation Supporting Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively ML20210J5951997-08-12012 August 1997 Safety Evaluation Supporting Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively ML20151L7981997-07-14014 July 1997 Safety Evaluation Supporting Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively ML20148S0581997-07-0101 July 1997 Safety Evaluation Supporting Amends 225 & 216 to Licenses DPR-77 & DPR-79,respectively ML20140F0311997-06-10010 June 1997 Safety Evaluation Supporting Amends 224 & 215 to Licenses DPR-77 & DPR-79,respectively ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20137Y8911997-04-21021 April 1997 Safety Evaluation Supporting Amends 223 & 214 to Licenses DPR-77 & DPR-79,respectively ML20101M5761996-04-0303 April 1996 Safety Evaluation Supporting Amend 211 to License DPR-79 ML20100N5711996-03-0404 March 1996 Safety Evaluation Supporting Amends 220 & 210 to Licenses DPR-77 & DPR-79,respectively ML20097D4191996-02-0707 February 1996 Safety Evaluation Supporting Amends 218 & 208 to Licenses NPF-77 & NPF-79,respectively ML20095F9891995-12-11011 December 1995 Safety Evaluation Supporting Amends 216 & 206 to Licenses DPR-77 & DPR-79,respectively ML20094N5341995-11-21021 November 1995 Safety Evaluation Supporting Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively ML20094D2451995-10-30030 October 1995 Safety Evaluation Supporting Amend 204 to License DPR-79 ML20093E1191995-10-11011 October 1995 Safety Evaluation Supporting Amend 214 to License DPR-77 ML20093B9471995-10-0404 October 1995 Safety Evaluation Supporting Amends 213 & 203 to Licenses DPR-77 & DPR-79,respectively ML20092N0711995-10-0202 October 1995 Safety Evaluation Supporting Amends 212 & 202 to Licenses DPR-77 & DPR-79,respectively ML20092H0811995-09-15015 September 1995 Safety Evaluation Supporting Amends 211 & 201 to Licenses DPR-77 & DPR-79,respectively ML20092G7071995-09-13013 September 1995 Safety Evaluation Supporting Amends 210 & 200 to Licenses DPR-77 & DPR-79 ML20087L4671995-08-22022 August 1995 Safety Evaluation Supporting Amends 207 & 197 to Licenses DPR-77 & DPR-79,respectively ML20086C2861995-06-29029 June 1995 Safety Evaluation Supporting Amends 205 & 195 to Licenses DPR-77 & DPR-79,respectively ML20085G5811995-06-13013 June 1995 Safety Evaluation Supporting Amends 203 & 193 to Licenses DPR-77 & DPR-79,respectively ML20085G5091995-06-13013 June 1995 Safety Evaluation Supporting Amends 202 & 192 to Licenses DPR-77 & DPR-79,respectively ML20083L1931995-05-10010 May 1995 Safety Evaluation Supporting Amends 198 & 189 to Licenses DPR-77 & DPR-79,respectively ML20087J3291995-04-28028 April 1995 Safety Evaluation Supporting Amends 197 & 188 to Licenses DPR-77 & DPR-79,respectively ML20082E4291995-04-0404 April 1995 Safety Evaluation Supporting Amends 196 & 187 to Licenses DPR-77 & DPR-79,respectively ML20078M8441995-02-0909 February 1995 Safety Evaluation Supporting Amends 195 & 186 to Licenses DPR-77 & DPR-79,respectively 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 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 ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively 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 ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program 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 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively 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 ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
ML20198C0211998-12-16016 December 1998 Safety Evaluation Supporting Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively 05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
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 ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively ML20195G3271998-11-17017 November 1998 Safety Evaluation Supporting Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
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 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
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 ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively 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 05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
1999-09-30
[Table view] |
Text
_ _ _ _ _ _ - _ _ _ - _ _ _ _ _
@ It09 UNITED STATES S
er i
NUCLEAR REGULATORY COMMISSION j
WASHINGTON, O. C. 20555
...../
SAFETY EVALUATION BY THE OFFICE OF SPECIAL PROJECTS EMPLOYEE CONCERN ELEMENT REPORT 223.1(B)
"INSTRUMENT LINE SUPPORT CONNECTIONS" TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR POWER PLAF UNITS 1 AND 2 I.
SUBJECT Category:
Engineering (20000)
Subcategory:
Instrument Support Design (22300)
Element:
Instrur.ent Line Support Connections (22301)
The basis for Element Report 223.1(B) Revision 1, dated January 14, 1987 is employee concerns PH-85-054-001, IN-85-398-002 and IN-85-398-003 which state:
PH-85-054-001:
}
"The notes on the 47A050 series drawings were really confusing to the Quality Control inspection personnel.
Much confusion existed between the size, number and type of instrumentation support clamps which were acceptable by the 050 series note and what type clamp was called for on the typical support drawing..."
IN-85-398-002:
"Inconsistent hanger torquing: until June 1,1985 no instrumentation hanger bolts were torqued.
From that date, bolts were required to be torqued to 6 ft-lb.
This amount of torque flattens half moon clamps and damages clamp noses.
Three to four months ago, hanger inspectors randomly inspected an unknown [ number] of bolts and 40% failed (possibly 80 tested.)
Concerned individual (CI) questions corrective action for the 10-20 thousand not tested.
New 050 notes (early July 1985) permit hand tightening and then turning 1/2 turn with wrench, but this can leave the tubing loose.
(Bothunits)..."
IN-85=398-003:
"Bolts for clamps manufactured by Unistrut were not required to be torqued prior to June 1, 1985 for Unit 1.
Unit 2 bolts have an option to be torqued to 6 ft-lbs.
Haif moon clamps flatten during a 6 ft-lb torque.
If torquing is an option on unit 2, why wasn't it an option on unit 1, and when should the option be applied? CI knows that this was not a procedural requirement on units..."
These concerns were evaluated by the licensee as potentially nuclear safety-related and potentially applicable to Sequoyah (generic).
8803220330 090311
'DR ADOCK 05000328 P
PDR
e II.
SUMMARY
OF ISSUES Six issues were defined by the licensee as applicable to this evaluation:
1.
The notes on the 47A050 series drawings for typical supports describing sizes, numbers, and types of instrument line support connections were confusing to Quality Control inspection personnel.
2.
Bolts for instrument line clamps were not torqued before June 1,1985.
3.
The bolts were over-torqued to 6 ft-lb af ter June 1,1985 cousing damage to the clamps.
4 Forty percent of the clamps failed random inspection (possibly 80 visually examined.)
5.
The new requirement is for bolts to be hand-tightened followed by a half-turn with a wrench.
This may be inadequate.
6.
The torque requirements for Unit 1 are different from those for Unit 2.
III. EVALUATION 1
T'tA Employee Concerns Special Program Report No. C017303-SON, Revision 3 dated January 28, 1987, "Instrument Line Clamps" covers similar issues and was used in the evaluation.
DRAWING NOTES The licensee's evaluation team restated this issue to mean that confusing information in the 47A050 series drawings caused construction to use unquali-fied clamps to support Category I and I(L) instrument lines.
The licensee admitted that clamps were used to support the instrument lines at Watts Bar Nuclear Plant without authorization from the engineering department and 17 types of unauthorized clamps were found in their warehouse.
The Sequoyah drawings did not specify the types found at Watts Bar, but two types of unauthorized clamps were found in the Sequoyah warehouse.
These instrument connt:ctions were sampled in April 1986 in response to a civil engineering branch significant condition report no. SCR SQN CEB 8612, "Specific Bolt Tightening Instructions" to determine the torque on installed bolts.
A total of 302 mechanical piping, electrical conduit and instrument tubinn clamps were examined.
All of the 120 instrument line clamps examined were authorized connections.
Although the 47A050 drawings at Sequoyah were generally confus-ing, the licensee's inspectnrs told the licensee's evaluation team that drawing interpretation problems relating to instrument line clamps were resolved satisfactorily.
This concern was not substantiated.
U l
4 BOLTS NOT TORQUED Sequoyah construction procedures SNP Inspection Instruction No. 1 dated August 8, 1973, "Inspection of Bolted Ccnnections" and SNP Inspection Instruction No. 66 dated January 7, 1977, "Inspection of Supports", gave bolt tightening instructions for hangers, supports and miscellaneous steel that were undefined,
'.e., "show no slack and hand tight." The sampling progran identified above showed that about one-half of the 302 clamps examined were loose and the employee concern is substantiated.
Special Maintenance Instruc-tion SMI-0-317-25 was initiated on March 27, 1986 to walk-down instrument lines and tighten items found to be loose.
This instruction was first applied to lines outside of containment.
The licensee has cemitted to tightening bolts for instrument line clamps under the program described in engineering change notices 6690 and 6791.
Since then, the Sequoyah Plant Manager has directed that all instrument line clamps be tightered.
BOLTS OVER-TORQUED An inspection at Watts Bar Unit 1 shewed instrument lines and supports damaged because of high torque.
Sequoyah drawings 47A050-17 Revision 0, dated May 19, 1986, specifies 5-7 f t-lbs torque for some 1/4 in, diameter bolts, cne-half turn past hand tight for other 1/4 in, bolts and 17-19 ft-lbs for the 3/8 in, bolts.
These numerical values are in accordance with the manufacturer's recomendations, i.e., Unistrut Corporation Ceneral Engineering Catalog No.
10R, page 35.
The 302 clamps examined in the Sequoyah sampling program were not damaged by over-torquing.
This concern is substantiated for Watts Bar, but not for Sequoyah.
CLAMPS FAILED INSPECTION About one-half of the 302 clamps examined in the sampling inspection were loose and the concern is substantiated.
The corrective actions are found in the special maintenance instruction and plant manager's directions mentioned above.
HAND TIGHTEN AND HALF TURN INADEQUATE Sequoyah drawing 47A050-17 Revision 0 dated May 19, 1986 specifies one-half turn past hand tight for the Unistrut single-hole clamps that are used to attach 1/4 in, through 1 in, diameter tubing to panel supports.
The manufac-turer's literature shows that round head screwdriver slot screws should be used.
The licensee reported in memo no. B46-860612-001, "SQH Unistrut One-and Two-piece Tubing Clarps with Stainless Steel Tubing," that it took about 35 lbs to pull the tubes out of the clamps, regardless of diameter and tne torque on the clamps could be as little as 1.2 ft-lbs.
The licensee felt that this amount of tightening met the design requirements.
The NRC staff did not accept this conclusion because of the low values for the large tubing sizes and the lack of confidence in achieving proper tightening with a screw driver.
The staff and the licensee perforred additional tests at Sequoyah on 1/4 in. tubing with screworiver-tightened screws.
It took little
. effort to rotate the tube within the clamp and moderate manual effort was required to pull the tube out of the clamp.
However, the staff found that the large size clamps for the 3/4 in, and 1 in, tubing are not in stock at Sequoyah and the smaller clamps are used with hex head bolts, which are wrench-tightened.
The staff performed a walk-down in the Power Block and the 1/4 in, clamps observed were tight and hex heao bolts were used.
Since only 1/4, 3/8 and 1/2 in, clamps are involved and bolts are used, the tightening is sufficient and this employee concern is not substantiated for Sequoyah.
UNIT 1 AND UNIT 2 REQUIREMENTS Units 1 and 2 of Watts Bar had different bolt torquing requirements, while both Sequoyah units always had the same requirements.
This concern is substantiated for Watts Bar, but not for Sequoyah.
IV.
CONCLUSION The NRC staff believes that the licensee's investigation and resolution of the issues in TVA Employee Concerns Special Program no. 223.1(B) Revision 1, dated January 14, 1987, "Instrument Line Support Connections" was adequate.
For Sequoyah, two issues concerning loose instrument line clamps were substantiated and corrective actions are almost complete and four issues were not substantiated, v
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