LER-1981-056, /01T-0:on 810624,notification Received That 38 Pipe Supports Would Have Failed During Design Basis Seismic Event.Caused by Higher than Normal Slenderness Ratio. Identified Supports Upgraded |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3241981056R01 - NRC Website |
|
text
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSib"1
-(7 77)
LlCENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l lh (PLEASE PRINT OR TYPE ALL REQU4 RED IN50RMATION) lo l 1 l l N l C l B l E ! P l 2 l@l 0 l 0 l-l 0 l 0 l 0 l 0 l 0 l-l0 l 0 l@l 4 l 1 l 1 l 1 l 1 ]@l l
./
8 9 LICENSLE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CA T $8 CON'T 10111 S$gs l L l@l 0 l 5 l 0 l-l013 l 2 l4 @l0 l6 12 l4 l8 l1 l@l 0 ] 710 l 8 ] 8 l 1 l@
7 d
60 61 DOCK ET NUMBER 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h
.l o l 2 l l Notification was received from the Brunswick Engineer ing Support Unit that an analysis l
,i o l 3 l l by United Engineers & Construction (UESC) and EDS Nuclear, Inc., on CRD pipe supports l
- - l 0 l 4 l l indicated that 38 supports (17 on Unit No. 1 and 21 on Unit No. 2) would have f ailed l
- loisi lin their original as-designed /as-installed condition during a Design Basis S ismic l
l0 ls l l Event. This could have caused a failure of the CRD insert and withdrawal lines. This, ll0 l 7 l levent did not affect the health or safety of the public.
l 1 o la l l Technical Specification 6.9.1.81 l
DE CODE SU8CO E COMPONENT CODE SU8 CODE SU E
!!O l 91 lR lB l@ l Bl@ l A l@ l S lU l P l0 lR lT lh lB l@ lZ l@
7 8
9 10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE nEPORT hEVISION LE EVENT YEAR REPORT NO.
CODE TYPE N O.
@ yg,R <ROl8l1l l0l5l6l d
l0l1]
W l-l l0]
RE
_ 21 22 23 24 26 27 28 29 30 31 32 Y
AC ON ON PL NT ME HOURd S8 i FO 4b B.
SUPPLIE "
MANUFACTURER lFl@lFl@
LZ_j@
W@
l0l0l0l0l W@
lNl@
lXl@
l R l 1 l 4 l 0 l@
33 34 35 36 3/
40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l3 lollAll supports identified in the analysis were upgraded such that the stresses would notl g i ii l l exceed structural integrity. The analysis indicated that a higher than rarmal l
,,,,i ; slenderness ratio existed for these supports.
l l i l 31 l l
l i 14 I I l
7 8 9 80 ST 5
% POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION I1 l 5 l l,.,p,,j@ l 0 l 0 l 0 l@l NA l
l l@l A/E Notification l
ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTlvtTY LOCATION OF RELEASE NA l
l NA l
. l1 l6 l
@ lZ l@l 7
8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
li 171 l 0 l 0 l 0 l@l Z l@l NA l
,E RSONNe'L Imu' dies NUM8ER
DESCRIPTION
li 181 l 0 l 0 l 0 l@l NA l
7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
NA l
' U_L9] I Z l@l 8 9
'o 8108030317 810708 80
- I 2 I o l [ Z_J@ DESCRIPTION @
PDR ADOCK 05000324 NRC USE ONLY ISSU E D S
PDR
.4A l
llllll((lllll{
l 7
8 9 10 68 69 80 5 i
R. M. Poulk, Jr.
(919)457-9521 0
gg
~
LER 2-81-56 ATTACHMENT Facility: BSEP Unit No. 2 Date: June 24, 1981 During a review of CRD supports, 60 CRD supports were identified as Potential Short-Term Fixes (STF). These supporcs were immediately epgraded in December 1981 and January 1981 and an analysis performed on the as-found condition. The initial premise for identifying sixty (60) gang frames as Potential Short-Term l
Fixes was that the "Kt/r" ratios of all the frames exceeded the accepted limit of 200. The ratios in excess of 200 were determined in association with a "K" factor of 2.1, which assumes that the structures will act as pure cantilevers.
In this regard the analysis concurred that a less conservative "K" factor could be considered for assessing "Short-Term" operability. As it is probable that the lower portions of the f rames, surrounding the CRD bundles, will remain in a nearly vertical attitude when subjected o out-of plane displacement, the structures will act similar to guided cantilevers in most cases. The "K" factor for guided cantilevers is 1.2 as per the AISC Manual's " Recommended Design Value When Ideal Conditions Are Approximated." Thus, a "K"
factor of 1.2 was considered in the reanalysis of the gang frames.
1 Since there were two (2) major generic types.of gang frames identified as
?
Potential Short-Term Fixes, two (2) supports from each type were chosen to be analyzed. The major criteria used for choosing the "best" and " worst" frames l
from each category was the total load imposed on the frames, the overall dimen-i sions of the frame and the end connections used in construction. The frames I
which were not analyzed were grouped according to their similarity to the frames being analyzed.
Support 1-BSEP-7-4 was considered to be representative of the "best" of the large gang frames directly outside of containment.
Reanalysis of the frame indicates that it did not meet the Short-Term Criteria. The support considered to be the " worst" of the large gang frames was not analyzed since the "best" case configuration was found to be deficient. Based on the reanalysis of Support 1-BSEP-7-4, it is projected that all four (4) of the la :ge gang frames in each unit were Short-Term Fixes.
Support 2-BSEP-6-7 was considered to be representative of the '*best" of the smaller gang frames outside containment. Reanalysis of the frame indicates that it meets the Short-Term Criteria.
Based on the Short-Term qualification of 1
Support 2-BSEP-6-7, it is projected that twelve (12) of the Unit No. 1 smaller gang frar.es and ten (10) of the Unit No. 2 smaller gang frames initially identified as Potential Short-Term Fixes are acceptable in association with the Short-Term Criteria.
Support 2-BSEP-7-16 was considered to be representative of the " worst" of the j
smaller gang frames outside containment. Reanalysis of the frame indicates that it did not meet the Short-Term Criteria. Based on the reanalysis of Support 2-BSEP-7-16, it is projected that thirteen (13) of the Unit No. I smaller gang frames and seventeen (17) of Unit No. 2 smaller gang frames initially identified as Potential Short-Term Fixes did not meet the Short-Term Criteria.
I I
i
...m..
~
e In view of the locations of the frames projected to be Short-Term Fixes, it appears that all of the Insert and Withdrawal Lines did not meet the Short-Term Criteria, due to seismic inertial effects.
Note that the number of gang frames identified as Short-Term Fixes is based on the reanalysis of three (3) frames. In this regard, it is conceivable that a detailed analysis of each individual frame may reduce the number of frames identified as Short-Term Fixes. However, since all of the frames initially identified as Potential Short-Term Fixes have subsequently been modified in the field to meet the Short-Term Cri:3ria, we do net consider it beneficial to continue the analysis of structures that no longer exist in the plant.
The design and installation of the CRD System was a turn-key scope project by a subcontractor who performed no other work at the Brunswick site. Therefore, this is considered an isolated case with no generic implications with respect to other plant systems. As explained in letters on December 31, 1981, and February 25, 1981, a detailed line-by-line review of all plant systems is underway to ensure compliance with IE Bulletins 79-02, 79-07, and 79-14. Long-Term Fixes to the CRD lines will be completed by the completion of each unit's next respective refueling outage.
?
i i
I
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000325/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000325/LER-1981-001-01, /01T-0:on 810103,feed Pump Tripped on High Vessel Level Due to safety-relief Valve B21-F013G,Model 67F,lift. Caused by High Second Stage & Pilot Leakage in Valve.Pilot Valve Temporarily Replaced Until Next Scheduled Outage | /01T-0:on 810103,feed Pump Tripped on High Vessel Level Due to safety-relief Valve B21-F013G,Model 67F,lift. Caused by High Second Stage & Pilot Leakage in Valve.Pilot Valve Temporarily Replaced Until Next Scheduled Outage | | | 05000324/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000324/LER-1981-001-03, /03L-0:on 810129,during Surveillance Testing, HPCI Sys Initiation Reactor Level Switch Actuated at Simulated Level Above Tech Spec.Caused by Components Slipping Due to Loose Set Screws on Actuator Pointers | /03L-0:on 810129,during Surveillance Testing, HPCI Sys Initiation Reactor Level Switch Actuated at Simulated Level Above Tech Spec.Caused by Components Slipping Due to Loose Set Screws on Actuator Pointers | | | 05000325/LER-1981-002-03, /03L-0:on 810114 & 0212,reactor Protection Sys Logic relays,C71-K3D & K3E,did Not de-energize When MSIV 1-B21-F028B Was Closed.Caused by Sticking Valve Position Limit Switch Actuator Arm Cam.Switch Replaced | /03L-0:on 810114 & 0212,reactor Protection Sys Logic relays,C71-K3D & K3E,did Not de-energize When MSIV 1-B21-F028B Was Closed.Caused by Sticking Valve Position Limit Switch Actuator Arm Cam.Switch Replaced | | | 05000325/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000324/LER-1981-002-03, /03L-0:on 810104,vacuum Breaker X-18A Had Dual open-close Position Indication While in Open Position. Probably Caused by Problem W/Vacuum Breaker Position Limit Switches.Problem Will Be Resolved During Next Outage | /03L-0:on 810104,vacuum Breaker X-18A Had Dual open-close Position Indication While in Open Position. Probably Caused by Problem W/Vacuum Breaker Position Limit Switches.Problem Will Be Resolved During Next Outage | | | 05000324/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000324/LER-1981-003-03, /03L-0:on 810108,suppression Pool Level Exceeded Specs.Caused by Valve Operator Torque Switch Out of Adjustment Allowing Leakage Into Suppression Pool.Switch Repaired | /03L-0:on 810108,suppression Pool Level Exceeded Specs.Caused by Valve Operator Torque Switch Out of Adjustment Allowing Leakage Into Suppression Pool.Switch Repaired | | | 05000324/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000325/LER-1981-003-03, /03L-0:control Rod 26-35 on 810103,18-51 on 810113,38-31 & 22-15 on 810114 Showed Inaccurate Position Indications.Caused by Buffer Card Failure on 26-35;defective Reed Switches in Others.Card Replaced,Switches Repaired | /03L-0:control Rod 26-35 on 810103,18-51 on 810113,38-31 & 22-15 on 810114 Showed Inaccurate Position Indications.Caused by Buffer Card Failure on 26-35;defective Reed Switches in Others.Card Replaced,Switches Repaired | | | 05000325/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000324/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000324/LER-1981-004-03, /03L-0:on 810110,during Startup,Intermediate Range Monitor a Did Not Respond to Changes in Input Signal.Monitor C Indicated Downscale When on Range 7.On 810111 Monitor E Indicated Downscale While Monitor C Still Inoperable | /03L-0:on 810110,during Startup,Intermediate Range Monitor a Did Not Respond to Changes in Input Signal.Monitor C Indicated Downscale When on Range 7.On 810111 Monitor E Indicated Downscale While Monitor C Still Inoperable | | | 05000325/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000325/LER-1981-004-03, /03L-0:on 810118,during Control Rod Operability Check,Pt 14.1,rod 26-07 Would Not Select.Caused by Loose Solder Joint in Rod Select Switch Due to Frequent Use of Switch.New Solder Joint Made | /03L-0:on 810118,during Control Rod Operability Check,Pt 14.1,rod 26-07 Would Not Select.Caused by Loose Solder Joint in Rod Select Switch Due to Frequent Use of Switch.New Solder Joint Made | | | 05000325/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000325/LER-1981-005-03, /03L-0:on 810101,during Normal Surveillance, Discovered Secondary Containment 20 Ft Elevation Inner Air Lock Door Inoperable Due to Missing Gasket Sealing Matl. Caused by High Personnel Traffic.Gasket Replaced | /03L-0:on 810101,during Normal Surveillance, Discovered Secondary Containment 20 Ft Elevation Inner Air Lock Door Inoperable Due to Missing Gasket Sealing Matl. Caused by High Personnel Traffic.Gasket Replaced | | | 05000324/LER-1981-005-03, /03L-0:on 810113,during Normal Surveillance, Secondary Containment 20-ft Elevation Outer Air Lock Personnel Door Found Not Sealing.Caused by Heavy Personnel Traffic Through Door.Gasket Repaired | /03L-0:on 810113,during Normal Surveillance, Secondary Containment 20-ft Elevation Outer Air Lock Personnel Door Found Not Sealing.Caused by Heavy Personnel Traffic Through Door.Gasket Repaired | | | 05000324/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000324/LER-1981-006-03, /03L-0:on 810115,when Main Steam Line Isolation Valve F028C Reopened During Test P.T.1.3.1P-2,main Steam Line C Indicated Min Flow.Cause Undetermined.Investigation Will Be Performed During Future Outage | /03L-0:on 810115,when Main Steam Line Isolation Valve F028C Reopened During Test P.T.1.3.1P-2,main Steam Line C Indicated Min Flow.Cause Undetermined.Investigation Will Be Performed During Future Outage | | | 05000324/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000325/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000325/LER-1981-006-03, /03L-0:on 810101,containment Atmospheric Monitor, 1-CAC-ATH-1259-2 Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Returned to Svc | /03L-0:on 810101,containment Atmospheric Monitor, 1-CAC-ATH-1259-2 Found Out of Calibr.Caused by Instrument Drift.Monitor Recalibr & Returned to Svc | | | 05000324/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000325/LER-1981-007-03, /03L-0:on 810220,observed 2-inch Discrepancy Between Level Indicators of Suppression Pool Level Transmitters 1-CAC-LT-2601 & 2602.Caused by Insufficient Venting of 2602 Transmitter High Side Sensing Line | /03L-0:on 810220,observed 2-inch Discrepancy Between Level Indicators of Suppression Pool Level Transmitters 1-CAC-LT-2601 & 2602.Caused by Insufficient Venting of 2602 Transmitter High Side Sensing Line | | | 05000325/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000324/LER-1981-007-03, /03L-0:on 810115,Group 1 Isolation Signal Received on Reactor Protection Sys Trip Channel B.Caused by Failure of Relay Coil,Model P/N 12HFAS1A49F Due to Insulation Breakdown.Coil Replaced | /03L-0:on 810115,Group 1 Isolation Signal Received on Reactor Protection Sys Trip Channel B.Caused by Failure of Relay Coil,Model P/N 12HFAS1A49F Due to Insulation Breakdown.Coil Replaced | | | 05000325/LER-1981-008-03, /03L-0:on 810106,while Performing Primary Containment Leak Rate Testing of Personnel Airlock Doors, Discovered That Drywell Exterior Airlock Door Leakage Rate Exceeded Limits.Caused by Tubing Fitting Lodged in Door | /03L-0:on 810106,while Performing Primary Containment Leak Rate Testing of Personnel Airlock Doors, Discovered That Drywell Exterior Airlock Door Leakage Rate Exceeded Limits.Caused by Tubing Fitting Lodged in Door | | | 05000325/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000324/LER-1981-009-04, /04T-0:on 810128,radwaste Sys Liquid Effluent Discharge High Range Indicator/Recorder Found to Have Recorded Release Rate Less than Actual,Causing Tech Spec Limit to Be Exceeded.Caused by Loose Mechanical Linkage | /04T-0:on 810128,radwaste Sys Liquid Effluent Discharge High Range Indicator/Recorder Found to Have Recorded Release Rate Less than Actual,Causing Tech Spec Limit to Be Exceeded.Caused by Loose Mechanical Linkage | | | 05000325/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000325/LER-1981-009-03, /03L-0:on 810115,sys Oil Cooler Inlet Isolation Valve 1-E51-F046 Would Not Open from RTGB Resulting in Reactor Core Isolation Cooling Inoperability.Caused by Incorrect Motor Control Ctr Key Lock Switch Position | /03L-0:on 810115,sys Oil Cooler Inlet Isolation Valve 1-E51-F046 Would Not Open from RTGB Resulting in Reactor Core Isolation Cooling Inoperability.Caused by Incorrect Motor Control Ctr Key Lock Switch Position | | | 05000324/LER-1981-009, Forwards LER 81-009/04T-0 | Forwards LER 81-009/04T-0 | | | 05000325/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000325/LER-1981-010-03, /03L-0:on 810120,upon Auto Initiation After Reactor Scram,Rcic Turbine Failed to Accelerate to Idle Speed,Making RCIC Inoperable.Caused by Dirty Contacts in Turbine Steam Inlet Supply Valve 1-E51-F045.Contacts Cleaned | /03L-0:on 810120,upon Auto Initiation After Reactor Scram,Rcic Turbine Failed to Accelerate to Idle Speed,Making RCIC Inoperable.Caused by Dirty Contacts in Turbine Steam Inlet Supply Valve 1-E51-F045.Contacts Cleaned | | | 05000324/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000324/LER-1981-010-03, /03L-0:on 810120,RHR Svc Water Subsys a Suction valve,2-SW-V101,would Not Open Fully.Caused by Two Hex Nuts on Input Shaft of Valve Motor Operator,Model H3BC-SMB-00, Freezing to Shaft.Nuts & Shaft Reworked & Lubricated | /03L-0:on 810120,RHR Svc Water Subsys a Suction valve,2-SW-V101,would Not Open Fully.Caused by Two Hex Nuts on Input Shaft of Valve Motor Operator,Model H3BC-SMB-00, Freezing to Shaft.Nuts & Shaft Reworked & Lubricated | | | 05000324/LER-1981-011-03, /03L-0:on 810120 & 0123,actual Pool Level Determined in Excess of Upper Tech Spec Limit.Caused by Improper Calibr Data & Calibr Procedure Inadequacy.Procedure Revision Underway & Indicators Correctly Calibr | /03L-0:on 810120 & 0123,actual Pool Level Determined in Excess of Upper Tech Spec Limit.Caused by Improper Calibr Data & Calibr Procedure Inadequacy.Procedure Revision Underway & Indicators Correctly Calibr | | | 05000324/LER-1981-011, Forewards LER 81-011/03L-0 | Forewards LER 81-011/03L-0 | | | 05000325/LER-1981-011-03, /03L-0:on 810121,during Routine Shutdown Operation,Seat Leakage Discovered on Reactor Recirculation Sample Inboard Isolation Valve 1-B32-F019.Cause Unknown. Valve Will Be Inspected & Repaired During Next Outage | /03L-0:on 810121,during Routine Shutdown Operation,Seat Leakage Discovered on Reactor Recirculation Sample Inboard Isolation Valve 1-B32-F019.Cause Unknown. Valve Will Be Inspected & Repaired During Next Outage | | | 05000325/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000324/LER-1981-012-03, /03L-0:on 810320,wiring Deficiency Associated W/ Actuation Switch Discovered That Prevented Switch Operation. Caused by Improper Writing of Field Revision to Plant Mods Requiring Installation of Switches | /03L-0:on 810320,wiring Deficiency Associated W/ Actuation Switch Discovered That Prevented Switch Operation. Caused by Improper Writing of Field Revision to Plant Mods Requiring Installation of Switches | | | 05000325/LER-1981-012-03, /03L-0:on 810122,rod 26-35 Did Not Have Position Indication at Position 03 & Rod 34-35 Did Not Have Position Indication at Position 02.Caused by Defective Rod Position Indication Reed Switches.Corrective Maint Will Be Comple | /03L-0:on 810122,rod 26-35 Did Not Have Position Indication at Position 03 & Rod 34-35 Did Not Have Position Indication at Position 02.Caused by Defective Rod Position Indication Reed Switches.Corrective Maint Will Be Completed | | | 05000325/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000324/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000324/LER-1981-013-03, /03L-0:on 810119,HPCI Sys Component Test Tp 9.3.a Could Not Be Completed.Caused by Failed Motor on CST Suction Valve F004.Motor Sent to Svc Contractor to Be Repaired | /03L-0:on 810119,HPCI Sys Component Test Tp 9.3.a Could Not Be Completed.Caused by Failed Motor on CST Suction Valve F004.Motor Sent to Svc Contractor to Be Repaired | | | 05000324/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000325/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000325/LER-1981-013-03, /03L-0:on 810122,rod Worth Minimizer Sys Rod Blocks Were Received W/Proper Adherence to Control Rod Pattern Pull Sheet.Caused by Inadequate Procedures.Rods Pulled to Correct Position | /03L-0:on 810122,rod Worth Minimizer Sys Rod Blocks Were Received W/Proper Adherence to Control Rod Pattern Pull Sheet.Caused by Inadequate Procedures.Rods Pulled to Correct Position | |
|