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LER-1978-001, Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir |
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| 2801978001R00 - NRC Website |
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Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U. S.
Nuclear ~egulatory Corrnnission Region II - Suite 818 230 Peachtree Street, Northwest Atlanta, Geo.rgia 30303
Dear Mr. O'Reil-ly:
Serial No. 105 PO&M/DLB : das Docket No. so*-280 License No. DPR-32 Pursuant to Surry Power Station Technical Specification 6.6.2b(2), the Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit No~ 1.
LER-78-001/03L-O This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on the agenda for the next meeting of the System Nuclear Safety and Operating Committee.
Enclosures (3 copies) cc:
Dr. Ernst Vo.lgenau, Director (40 copies)
Office of Inspection and Enforcement Mr. William G. McDonald, Director (3 copies)
Office of Management Information and P~ogram Control Very truly yours, zb. J11. &a:/*\\1/
C. M. Stallings Vice President - Power Supply and Production Operations
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NRC FORM 366 (7-77)
U.S. NUCLEAR REGULATORY COMMISSION
- :*CENSEE EVENT REPORT CO,N};ROL BLOCK: I
- - 1 10 1L..---'---'--........L-_._------'6 e
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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I v! Al s I P-1 s I 1 !G)I o I o I,...1 o lo lo lo I o I - Io !'o 101 4 11 I 1 I 1 ! 1101 I 10 7
8 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T [uTI 7
8
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~~~~~~ ~© I o I s I o r*-~
- 101 o I 2 I o I 1 I 1 I s 10 I o I 2 I 2 I 1 I 1 I s I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
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I With Unit #1 at normal full power operation, a hydraulic shock suppressor (Snubber
[)))) I 1-SHP~HSS-18) was found inverted with an empty reservoir.
This event is reportable
--[+/-BJ I per T.S. 6'.6.2b(2).
No significant occurrence took place.. This event had no adverse I [QJ]J affect upon the health and safety of-the public.
7 8 9 SYSTEM
CAUSE
CAUSE CODE CODE SUBCOOE [ill]
1c 1c I@ L.£J@ ~@
s1 7
8 9
10 11 12 13 SEQUENTIAL
@ LER/RO [:VENT YEAR REPORT NO.
REPORT I 7 I 8 I L=.I Io Io 11 I NUMBER 21 22 23 24 26 ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS COMf'.
VALVE COMPONENT CODE SUBCODE SUBCODE u1 P l/1 27 IO IR 1 T J@ l!J@) ~@
18 19 20 OCCURRENCE REPORT CODE TYPE 10 13 I w
L=.l 28 29 30 31 NPRD-4 FORM SUB.
PRIME COMP.
SUPPLIER REVISION NO.
LQJ 32 COMPONENT MANUFACTURER 80
~@LJ@ ~@ ~ 101010 33 34 35 36 37
{22)
ATTACHMENT hf SUBMITTED I I LB@
40 41
~@ ~@ 11 I 2 IO 17 I@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS@
42 43 44 47 j Steady state vibration loosened the lock nut on the snubber support arm, This all owed I
, [JJJJ I the support arm and snubber to roll 180°.
With the snubber inverted, the reservoir I emptied.
The snubber was immediately replaced with a new snubber (Serial i/3073) and ITIII -
OJ}] I the lock nut tightened to prevent reoccurrence.
[III]
7 8
9 FACILITY STATUS
% POWER OTHER STATUS [ill]~@ [l 10 10 1@1-I _N_/A ___ ~
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80 METHOD OF A
DISCOVERY DISCOVERY DESCRIPTION '2_v
~@)LI _O_p:...._e_r_a_t_o_r_O_b_s_e_r_v_a_t_i_o_n _________ _.
7 45 46 80 8
9 10 12 13 ACTIVITY CONTENT
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RELEASED OF RELEASE AMOUNT OF ACTIVITY ~
ITliJ w @) ll_J(§),__I ---=N/=A,_____ __
7 8
9 10 11 44 44 45
- N/A LOCATION OF RELEASE @
80 PERSONNEL EXPOSURES
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NUMBER r:;:;,. TYPE
DESCRIPTION
[I.El 10 I O I OJLi@L--.:N~/.:..:.A _____________________
7 8
9 11 12 13 BO PERSONNEL INJURIES Q
NUMBER DESCRIPTION~
IT:GJ I O j O I O l@i__ ___
__;N/_A _____________________
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY '43\\
TYPE
DESCRIPTION
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Ll@L N/A 8
9 10 80 1ssu:~~~;;CRIPTION@
NRC USE ONL y ITI9] Li6t---______
N/_A _____________
--J I I I I I I I I I I I I I !
7 8
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10 68 69 80;;;
T. L. Baucom NAME OF PREPAREH (804) 357-3184 PHONE:-------------
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.- '>\\,,;,.. ~-
e I' *tE{ - _Q_ _Q_ _L / 03_ - L - 0 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT #1 DOCKET NO: 050~0280'..
EVENT DATE: 02-01-78 8
. During normal full power operation a snubber (l-SHP-HSS-18) on_Main Steam Line "C" was found* inv-ert'ed*:with an *empty reservoir.
The_ lock nut, which -holds the support
.arm in position, loosened and allowed the support arm and snubber to roll 180°.
The loosening of the lock nut was caused by steady state vibration in the main steam line.
Maintenance and Quality~Control personnel immediately evaluated the situation.
To*
reduce maintenance time, a new snubber, Serial Number 3073, tested in accordance with MMP-P-HSS-020, was substituted for the inverted snubber.. The lock nut was tightened to prevent reoccurrence.
The Maintenance Report was completed at 1630-hours on 02-01-78.
This event did not affect the health and safety of the public.
All other snubbers w~th this configuration were checked and found to be satisfactory.
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| 05000280/LER-1978-001, Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir | Submit Licensee Event Report No. LER-78-001/03L-0 Re Hydraulic Shock Suppressor Found Inverted with Empty Reservoir | | | 05000280/LER-1978-002, Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance | Submit Licensee Event Report No. LER-78-002/01T-0 Re Additional Radial Peaking Factor Surveillance | | | 05000280/LER-1978-003, Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 | Submit Licensee Event Report No. LER-78-003/03L-0 Re Failed Heat Tracing, Panel 8 Circuit 24 | | | 05000280/LER-1978-004-03, /03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be Studied | /03X-1 on 780305:loss of Svc Water Flow Through Charging Pump Intermediate Seal Cooler Was Caused by Corrosion of Stem of Discharge Gate Valve;Corrosion Was Galvanic(Brass Touching Bronze);Problem Will Be Studied | | | 05000280/LER-1978-004, Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler | Submit Licensee Event Report No. LER-78-004/03L-0 Re Loss of Service Water Flow Through Charging Pump Intermediate Seal Cooler | | | 05000280/LER-1978-005, Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouses Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature | Forwarding Licensee Event Report No. LER-78-005/01T-0 Re Westinghouses Error in LOCA-ECCS Evaluation Model, Which Will Result in Higher Calculated Peak Clad Temperature | | | 05000280/LER-1978-006, Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping | Submit Licensee Event Report No. LER-78-006/01T-0 Re Seismically Disqualified Two Pipe Extensions on Fire Protection Yard Piping | | | 05000280/LER-1978-007, Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 | Submit Licensee Event Report No. LER-78-007/03L-0 Re Leak on Body to Bonnet Joint Diaphragm Valve 1-CH-98 | | | 05000280/LER-1978-008, Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 | Submit Licensee Event Report Nos. LER-78-008/03L-0, LER-78-009/03L-0, LER-78-010/03L-0, LER-78-011/03L-0 for Surry Unit No. 1 | | | 05000281/LER-1978-011-03, /03X-1 on 780305:During Normal Full Pwr Oper,There Was No Svc Water Flow Thru Charging Pump Intermediate Seal Cooler 2-SW-E-1B,due to Failure of the Coolers Discharge Gate Valve | /03X-1 on 780305:During Normal Full Pwr Oper,There Was No Svc Water Flow Thru Charging Pump Intermediate Seal Cooler 2-SW-E-1B,due to Failure of the Coolers Discharge Gate Valve | | | 05000281/LER-1978-011, Forwards LER 78-011/03X-1 | Forwards LER 78-011/03X-1 | | | 05000280/LER-1978-012, Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand | Submit Licensee Event Report No. LER-78-012/03L-0 Re Inside Recirculation Spray Pump 1-RS-P-1A, Failure to Rotate by Hand | | | 05000280/LER-1978-013, Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | Submit Licensee Event Report Nos. LER 78-013/03L-0 Re Six Snubbers Not Meeting Test Criteria, & 78-014/03L-0 Re Mount Plate Was Warped, & 3 of 8 Bolts Were Insufficiently Embedded | | | 05000280/LER-1978-015, Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | Submit Licensee Event Report No. LER-78-015/03L-0 Re Valve Cleanliness Inspection Found Foreign Material on Valve Seating Surfaces | | | 05000280/LER-1978-016, Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | Submit Licensee Event Report No. LER 78-016/03L-0 Re Valve MOV-RH-100 Was Not Opening | | | 05000280/LER-1978-017, Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | Submit Licensee Event Report Nos. LER 78-017/03L-0 Re Not Documenting Four Electric Maintenance Procedures & Two Periodic Tests, & 78-020/03L-0 Re Suspended Air Bubbles in Reservoir Fluid | | | 05000280/LER-1978-018, Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | Sutmit Licensee Event Report No. LER 78-018/03L-0 Re Two Main Steam Safety Valves Were Not within Plus or Minus 3% of Setpoint as Required | | | 05000280/LER-1978-022-03, /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | /03X-1 on 780726:Hydro Test Pump Failed to Build Up Pressure During Attempt to Fill Safety Injection Accumulators Due to Lifting of Its Relief Valve.Valve Replaced & Checked.Accumulator Refilled | | | 05000280/LER-1978-022, Forwards LER 78-022/03X-1 | Forwards LER 78-022/03X-1 | | | 05000280/LER-1978-024, Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | Submit Licensee Event Report No. LER 78-024/03L-0 Re No Alarm During a Planned Release of Liquid Radioactive Waste | | | 05000280/LER-1978-027, Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | Submit LER 78-027/03L-0 Re Seven Snubbers Not Meeting Inspection Criteria | | | 05000280/LER-1978-028-03, /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | /03L-0 on 780916:snubber Not Meeting Inspec Criteria Caused by Low Oil Level Due to Leakage at Mating Surface Between Body & End Plate.Holding Bolts Were Tightened & Snubber Was Refilled | | | 05000280/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000280/LER-1978-029-03, X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | X-1, LER 78-029-03L-0, & LER 78-031-03L-0 for Surry 2 Re Critical Below Minimum Insertion Limit on D Control Bank | | | 05000280/LER-1978-029, Forwards LER 78-029/03L-0 | Forwards LER 78-029/03L-0 | | | 05000280/LER-1978-030, Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | Forwards LER 78-030/03L-0, 78-031/03L-0, 78-032/03L-0, 78-033/03L-0 | | | 05000280/LER-1978-030-03, /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | /03L-0 on 781009:w/unit at Rated Pwr,Charging Pump Component Cooling Water Pump Btripped.Pump Tripped on Overcurrent.Caused by Corrosion Damage to Motor Bearings. Pump & Motor Rebuilt & Reinstalled | | | 05000280/LER-1978-031-03, /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | /03X-1 on 781001:during Normal Operation,Channel I Pressurizer Level (Protection) L-I-459 Drifted High.Caused by Drift of Electronic Zero Adjustment,In Conjunction W/ Leakage Thru Transmitter Bypass/Equalizing Valve | | | 05000280/LER-1978-031, Forwards LER 78-031/03X-1 & 78-038/03X-1 | Forwards LER 78-031/03X-1 & 78-038/03X-1 | | | 05000281/LER-1978-032, Forwards LER 78-032/03L-0 | Forwards LER 78-032/03L-0 | | | 05000280/LER-1978-032-03, /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | /03L-0 on 781011:heat Tracing Circuit Faults Had Occurred as a Result of Boric Acid Incursion.Faults Repaired & Circuit Current Verified | | | 05000281/LER-1978-032-03, /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | /03L-0:on 780921,heat Tracing Circuit Manual Boration/Boric acid-to-blender Failed.Caused by Boric Acid Penetration of Heat Tracing Tape Circuits.Heat Tracing Tape Replaced | | | 05000281/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000281/LER-1978-033-03, /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | /03X-1 on 780926:circulating Water Outlet Valve MOV-CW-200D Failed to Close When Operated Electrically. Caused When Actuator Cam for Shut Torque Switch Became Wedged Against Torque Switch Hold Down Screw | | | 05000280/LER-1978-033-03, /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | /03L-0 on 781015:heat Tracing Circuit Failed. Caused by Old Boric Acid Buildup & Penetration of Heat Leakage | | | 05000281/LER-1978-034-03, /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | /03L-0:on 781006,w/unit at Cold Shutdown,Snubbers 2-RH-HSS-20 & 2-WFPD-HSS-9 Inoperable.Caused by Low Fluid Level.Defective Snubbers Dry Because of Leaking Rod Seals & Mechanical Damage to Seals.Snubbers Replaced | | | 05000280/LER-1978-034-01, /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | /01X-1 on 781101:noted That 17 Spare Process Piping Penetrations on Unit 1 & 23 on Unit 2 Were Not Capped in Auxiliary Bldg.Caused by Failure to Properly Complete Capping at End of Constr | | | 05000280/LER-1978-034, Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | Update to LER 78-034/01X-2 on 781101:17 Spare Process Piping Containment Penetrations Were Not Capped.Condition Has Been Overlooked Since Const.Design Change Approved to Weld Caps on Open Ends | | | 05000280/LER-1978-035, Forwards LER 78-035/01T-0 | Forwards LER 78-035/01T-0 | | | 05000281/LER-1978-035-03, /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | /03L-0:on 781007,during Cold Shutdown,Valve Pit Flooded While Draining Circulating Water Box D.Caused by Damage of Valve from Flooding | | | 05000280/LER-1978-035-01, /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | /01T-0 on 781109:study of Calibr Techniques Showed That SI Accumulators Indicated Level Would Be Lower than Actual Level.Discovered After Rigorous Review of Factors Affecting Instru | | | 05000280/LER-1978-036, Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | Forwards LER 78-036/03L-0, 70-037/03L-0 & 78-038/03L-0 | | | 05000280/LER-1978-036-03, /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | /03L-0 on 781107:failure of Heat Tracing Circuit 24D,Unit 1,due to Boric Acid Damage.Heat Tracing Tape Replaced | | | 05000281/LER-1978-036-03, /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | /03L-0 on 781015:compensatory Surveillance on RCP Cstator & Hearing Temp Had Not Been Performed.Caused by Failure of Operating Personnel to Restore Process Computer Trend Block Following Computer Reinitialization | | | 05000281/LER-1978-036, Forwards LER 78-036/03L-0 | Forwards LER 78-036/03L-0 | | | 05000281/LER-1978-037, Forwards LER 78-037/03L-0 | Forwards LER 78-037/03L-0 | | | 05000280/LER-1978-037-03, /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | /03L-0 on 781107:procedure Deviation Found Re Filling & Venting Reactor Coolant Sys on 770105.Procedure Deviation Was Misrouted to Records Vault W/O Review by Snsoc.Deviation Has Now Been Submitted to Snsoc for Review | | | 05000281/LER-1978-037-03, /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | /03L-0 on 781022:with Unit at Rated Pwr,Panel Indicator for Radiat Monitor RM-213 Monitoring a Steam Generator Blowdown Read 0.Caused by Loose Connector Joining Detector Cable to Electronic Chassis | | | 05000281/LER-1978-038-03, /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | /03X-1 on 781030:boric Acid Flow from Boric Acid Tank to Blender Was Interrupted.Caused by Blockage of Crystallized Boron at Elbow in Line 1-CH-356-152 | | | 05000280/LER-1978-038-03, /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | /03X-1 on 781108:review of Operational Data Showed That Quarterly Calibr of Nuclear Power Range Instrumentation Had Not Been Performed Per Schedule,Due to Scheduling Error | |
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