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LER-1978-034, /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 |
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NRC FORM 366 (7-77)
LICENSEE EVENT REPORT CONTROL BLOCK: I I f1\\
(PLEASE PRINT O.PE ALL REQUIRED INFORMATION) 1L.. _
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I v I A I s I PI s I 1 101 o I o I - I o I o I o Io Io I-Io I a 1014 I 1 I 1 I 1 I 1 101 I 10 7
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LICENSEE COOE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T [TIJJ 7
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- ~~~~~ L!J© I o I s I o I o I o I 2 I s I o 101 1 I 1 I o I 1 I 1 I s IG) I 1 I 2 I 1 I 1 I 2 I a I G) 60 61 DOCKET NUMBER
. 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During a routine inspection an lQ-27 78 it was noted tbat 17 spare process pipivg penetrations on Unit 1 and 23 on Unit 2 were not_ capped in the Anxj Jj ary Bui 1 ding,
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although the inside ends are sealed.
A s11hseq11eot ved fi cation inspect inn reveal-
[III]
ed that 21 penetrations on Unit 1 and 22 penetrations on Unit 2 are affected.
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I This condition is less conservative than described in ESAR Section 5 2 This coo-
@ID I dition is reportable in accordance with T.S. 6,6,2,a,(9),
[)))) I of the public were not affected.
7 8 9
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SYSTEM CODE Isl Al@
9 10 Q
LEA/RO CVENT YEAR
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REPoRr 17 18 I NUMBER 21 22
CAUSE
CAUSE CODE SUB CODE COMPONENT CODE w@w@ I P! El NI El Tl RI@
11 12 13 l=J 23 SEQUENTIAL REPORT NO.
I o I 3l 41 24 26 18 OCCURRENCE CODE I o I 1 I 27 28 29 The health and safety COMP.
SUBCODE w@
19 REPORT TYPE w
30 VALVE SUBCODE w@
20 REVISION NO.
L!J 32 80
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ATTACHMENT NPRD-4
~ SUBMITTED FORM SUB.
ACTION FUTURE EFFECT SHUTDOWN TAKEN ACTION ON PLANT METHOD HOURS 31 PRIME C.OMP.
SUPPLIER COMPONENT MANUFACTURER LU@~@ ~@ LU 10 10 10 33 34 35 36 37 10 I L!J@ 1.2!.l 40 41 42 L!J@
43 I s I 41 21 o!@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
44 47 III]J !The outside end of the penetrations were left uncapped at completion of construe-OJJJ jtion.
External welded caps will be installed on these penetrations to provide OJ)) jdouble barrier containment isolation as described in the FSAR.
9 FACILITY STATUS
% POWER OTHER STATUS METHOD OF A
I 80 DE L!J@ 11 IO IO l@I...._ __
N_A __
OISCOVERY DISCOVERY DESCRIPTION (3.,
~@I..__A_d_H_o_c_R_e_v_i_e_w ____________ _.
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10 12 11 ACTIVITY CONTENT
(;';;.,
RELEASED OF RELEASE AMOUNT OF ACTIVITY
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NA _____
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9 10 11 44 45 46 80 7
44 NA LOCATION OF RELEASE @
45 80 PERSONNEL EXPOSURES r::;:;,,
NUMBER A
TYPE t:;;\\ DESCRIPTION~
[DTI I o I o I oJe~,.____..;.;.NA _______________________ __,
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9 11 12 13 80 PERSONNEL INJURIES Q
NUMBER DESCRIPTION~
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! 0 ! 0 IO l@L--_----=..::NA~-------------------------'
7 8
9 11 12 LOSS OF OR DAMAGE TO FACILITY '43' TYPE
DESCRIPTION
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~{§)L--_NA ____________________________ __,
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9 10 80 PUBLICITY Q
NRC USE ONL y ISSUEDr,;;\\ DESCRIPTION~
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7 8 'TB! 2'""0=2"""'0:c---c-o-2~0=-=7:r---------------------,.'.6B 69 80;;;
T. L. Baucom (804)357-3184 o
NAME OF PREPARER------------------
PHONE:-------------
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Surry Power Docket No:
Report No:
Stat ion, Unit 1 50-280.
78-034/~lX-1
,_-=---"'-----
Containment Spare.Process Piping Penetrations
- 1.
Description of Event
During a routine inspection on 10-27-78 it was noted that 17 spare process piping containment penetrations on Unit 1 and 23 on Unit*2 had never been capped on the Auxiliary Building end.
A subsequent verifica-tion inspection revealed that 21 penetrations on Unit 1 and Z2.penetra-tions on Unit 2 are affected.
Containment ends are capped.
The condition has existed since the construction period and is less conservative than described in Section 5.2 of the FSAR (not updated).
Upon review, on 11-1-78, of the documentation identifying the condition, it was determined that the condition was reportable in accordance with Technical specifica-tion 6.6.2.a(9).
This report is applicable to Surry Unit 1 (Docket No.
50-280) and Unit 2 (Docket 50-281).
- 2.
Probable Consequences/Status of Redundant Systems:
All spare penetrations are sealed on the inside (containment) ends of the penetrations.
There has been no compromise of containment integrity as evidenced by the fact that the containment has experienced two ILRT tests and five years of operation with no indication of degradation of the integrity of the inside caps, Therefore, the health and safety of
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the public have not been affected.
- 3.
Cause
It appears that the outside end of the penetrations were left uncapped at the completion of construction.
- 4.
- Immediate Corrective Action:
An immediate inventory was conducted to verify the condition initially reported.
The architect-engineer was requested to advise a method and procedures for correcting the condition.
- 5.
Subsequent Corrective Action:
The Surry FSAR, Section 5.2-10.states that pipe penetrations that are spares are to be capped at both ends.
In order to resolve this apparent discrepancy, external welded caps will be installed as per the architect-engineers design and thereby providing the double barrier utilized in the original design for containment isolation.
This modification will be implemented on Unit 1 by Mid April, 1979, and on Unit 2 by the end of the upcoming Steam Generator Outage, scheduled to commence in January, 1979.
- 6.
Actions Taken to Prevent Recurrence:
The situation described is a result of the construction process.
The procedural controls now applicable to changes' in.fac~lity configuration would preclude a recurr.ence.
e (Attachment, page 2 of 2)
Surry Power Docket No:
Report No:
Station, Unit 1 50-280 78-034/0lX-l Containment Spare Process Piping Penetrations
- 7.
Generic Implications:
North Anna Power Station Unit 1 has the same spare p1p1ng penetration arrangement.
We have informed our architect-engineer of this event.
They are reviewing their records to determine if other facilities are affect.
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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. 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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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