LER-1979-042, T-0:on 791012,during Testing of Pressurizer Code Safety Valves,Lift Setting for Two Valves Were 2,897 & 2,462 Psia,Violating Tech Specs.Caused by Mispositioning of Alignment Pin.Future Testing Will Be Done W/Steam |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2551979042R01 - NRC Website |
|
text
~~*~~- i
~'
PALISADES PLANT NRC FORM366 17-771 U.S. NUCLEAR. REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I
. I I';'\\
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
I 6\\.!)
[il!J IM I r IP I A IL I 1 l@l.b
- Io I o Io I o ID Io I o I DI o I o 1@1 4 11 11 P. 11 1©1. I I@
7 8
9
,5 LICENSE NUMBER
~5
- ie*
UCENSE TYPE. 30 57 CAT 68 CON'T ITIIl 7
8
- ~~~~~ f.!J©1b1 510 I b I 012 I 51 5K?)l 110 1112 17 19 1@1110 1216 1719 I@
60 51 DOCKET NUMBER 58 1111 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I During testing o:f _pressurizer code safety valves, it was determined
([I!) 1 that the lift settings for two of the valves were 2897 psia (RV 1039)
(.Q:TI] I and 2462 j>sia (RV 1040).
T.S. 3.1. 7A requires the lift settings to be
((IT) 1 between 2500. psi~ and 2580 psi a. ( + /- 1%).
The li'ft setting o:f the
[))!] I third code sa:fety valye was within specs.
No similiar :failures have
. f 1I1IJ 1.. occurred in the past; All three pzr code sa:feties were tested this out-I
[)))) I age by using steam as the test fluid.
7 8 9 80 [ill]
7 B
SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE.
I CIJ I@ l!J@ l.Ll@ I VIA IL Iv IE Ix !@ W Lfil 9
. 10 11 12 13 18 19 20 SEQUENTIAL
LEA/RO CEVENTYEAR.
REPORTNO.
CODE TYPE REPORT 17191 I. I I 014121 1011 I L!J I I NUMBER 21 22*
23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN'
(:;:::..
- ATTACHMENT NPRD-4 PRIME COMP.
TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB SUPl'LIER LIJL!J@ ~ ~ fO I 010 I Of L!J@ 12!.J@
l!J@)
33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORREC"rlVE ACTIONS @
REVISION*
NO.
LQJ 32 COMPONENT MANUFACTURER ID 1214 13 I@
44 47 IJ:ill I DisassembJ.y of' RV 1039 revealed that an alignment pin was mispositioned..
ITTIJ I This may have caused the out of' spec.condition of' that valve.
In o:m I addition, info f'rom the vendor reveals that testing wi ~h cold nitrogen
((II) I can :t"esult in up to 10% errors when compared to the li.ft settings with CII!) I steam as the test. medium.
Future testing will be done with steam.
- 7.
B 9
FACILITY.
~
STATUS
"'POWER OTHER STATUS ~
IITIJ L!!..J@ Io I o I o l@)'-1..___:.:;NA;.;,___~
METHOD OF
~
DISCOVERY DISCOVERY DESCRIPTION ~
ULl@)I Test Results 1
a 9 to 12 13 44 ACTIVITY CONTENT IC\\
RELEASED OF RELEASE AMOUNT OF ACTIVITY
[!JI] w @) Lll@I
. NA I
7 B 9 10 11 45.
46 LOCATION OF RELEASE@.
NA 44 45 80 80 BO PERSONNEL EXPOSURES Q
NUMBER
(.;'.;\\TYPE/,;;;\\ DESCRIPTION IIITl I 0 I Of 0 l~l.&J~--....:N;.::;A:__ __________________
___J 7
8 9
12 13 80 PERSONNEL INJURIES I.:':\\
NUMBER DESCRIPTION~
7 cu.
0 I 0 v
~IOI 0101@1~----~N=A~-----~-~~/~o~g~a~~~'~~~---~
7 8
9 12 BO LOSS OF OR DAMAGE TO FACILITY '4J' TYPE
DESCRIPTION
v:.::J
~
~(§)1~0~~..-~..-..-~~---N~A:.:.-..-..-..-..-..-..-..-..-..-..-..-..-..-~..-..-..-..-~..-..-..-..-~
....J PUBLICITY C\\
BO ISSUEDfu\\DESCRIPTION~
NRC USE ONLY [ffi] W~i..-------___;;N;;;;.A:__ ___________ ___,
I II I II II II 7
B 9
ID 6B 69 I I BO
Attachment to LER 79-042/01-T-O Cons'UI!lers Power Company Palisades Nuclear Plant Docket 50-255 During the 1979 refueling outage, which is currentJ..y.in progress, all three pressurizer code s~ety valves were sent to a test facility in order to have their.lift setpoints checked with steam as the test fluid.
PreviousJ..y, testing of these valves had been performed on site and cold nitrogen had been used as the test fluid.
Two of the three valves tested had lift settings which were outside of the Technical Specifications limits.
SpecificalJ..y, RV 1039 had a lift setting of 2897 psia, and RV 1040 had a lift setting of 2462 psia.
Technical Specification 3.l.7A requires the lift settings for the pressurizer code safety valves to be between 2500 psia and 2580 psia (+/-1%).
The valve data is as follows:
Dresser Industries, Inc.
DI 31739A-l The valves were disassembled, inspected, reflirbished and retested satis-factoriJ..y with steam.
Inspection of RV 1039 revealed that the alignment pin on the upper spring washer was out of its slot, and was bound on the land under the slot (see attached figure). It is probable that the misposition-ing of the alignment pin occurred during the previous rebuilding of the valve in March; 1976.
It is noted; however, that subsequent to the rebuilding of the.valve in March, 1976, it was tested satisfactoriJ..y by checking the lift setting four times with cold nitrogen.
Inspection of RV 1040 revealed no apparent deficiencies.
Information supplied by the valve vendor in August, 1979 indicates that using cold nitrogen to test the lift settings of the valves in question is not ac-ceptable.
The vendor stated that when the data from tests with steam were com-pared With data from cold nitrogen tests, differences of 8% to 10% in lift setting values were noted.
The vendor further stated that correlation of data between steam tests and cold nitrogen tests was not achievable.
Tl:~e vendor stated that this anomaJ..y was applicable specificalJ..y to the Palisades pressurizer code safety valves and did not state whether this phenomenon existed in other s~ety valves manufactured by them.
To avoid future errors in the lift settings of the Palisades pressurizer code safety valves, these valves will continue to be tested with steam as long as there exists no other practical means of testing which will provide accept-able results.
\\
i' I
. : *I I
~
I
1* ~
,*4 I
I *
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000255/LER-1979-001, Forwards LER 79-001/03X-1 | Forwards LER 79-001/03X-1 | | | 05000255/LER-1979-001-03, /03L-0 on 790102:reactor Protection Sys Power Range Channels NI05,06 & 07 Bypassed W/O First Tripping NI08.Caused by Failure to Use Administrative Controls | /03L-0 on 790102:reactor Protection Sys Power Range Channels NI05,06 & 07 Bypassed W/O First Tripping NI08.Caused by Failure to Use Administrative Controls | | | 05000255/LER-1979-002-03, /03L-0 on 790103:steam Generator Specific Conductivity Increased to 7.65 micro-mho Per Cm.Steam Generator Rate Increased & Morpholine/Hydrazine Feed Rate Decreased.Caused by Air in Leakage to Main Condenser | /03L-0 on 790103:steam Generator Specific Conductivity Increased to 7.65 micro-mho Per Cm.Steam Generator Rate Increased & Morpholine/Hydrazine Feed Rate Decreased.Caused by Air in Leakage to Main Condenser | | | 05000255/LER-1979-003-01, /01T-0 on 790117:fitting in Fire Protection Piping for a Cooling Tower Broke.Resulting Leakage Could Not Be Isolated;Fire Pumps Placed in Manual.Break Caused by Freezing Weather Conditions | /01T-0 on 790117:fitting in Fire Protection Piping for a Cooling Tower Broke.Resulting Leakage Could Not Be Isolated;Fire Pumps Placed in Manual.Break Caused by Freezing Weather Conditions | | | 05000255/LER-1979-004-01, /01T-0 on 790117:svc Water Pump P-7B Taken out-of- Service W/O Prior Test of Diesel Generator 1-2.Caused by Combination of Poor Judgment & Lack of Awareness of Tech Spec Requirements by Shift Operating Personnel | /01T-0 on 790117:svc Water Pump P-7B Taken out-of- Service W/O Prior Test of Diesel Generator 1-2.Caused by Combination of Poor Judgment & Lack of Awareness of Tech Spec Requirements by Shift Operating Personnel | | | 05000255/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000255/LER-1979-005-03, /03L-0 on 790103:1/4-inch Drain Line in Diesel Generator Fuel Sys Broke,Spraying 100-150 Gal of Fuel Oil Onto Engine.Caused by Vibration | /03L-0 on 790103:1/4-inch Drain Line in Diesel Generator Fuel Sys Broke,Spraying 100-150 Gal of Fuel Oil Onto Engine.Caused by Vibration | | | 05000255/LER-1979-006-01, /01T-0 on 790125:during Preparation for Leak Testing Personnel Air Lock,Found Pressure Gauge Normally Mounted on Outer Door of Air Lock Was Missing.Caused by Procedures Not Specifying Gauge Replacement After Removal | /01T-0 on 790125:during Preparation for Leak Testing Personnel Air Lock,Found Pressure Gauge Normally Mounted on Outer Door of Air Lock Was Missing.Caused by Procedures Not Specifying Gauge Replacement After Removal | | | 05000255/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000255/LER-1979-007-03, /03L-0 on 790115:primary Computer Stopped.Caused by Computer Program Failure.Computer Reprogrammed to Restore Operability | /03L-0 on 790115:primary Computer Stopped.Caused by Computer Program Failure.Computer Reprogrammed to Restore Operability | | | 05000255/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000255/LER-1979-008-03, /03L-0 on 790126: Tank Vent Valve (CV-3051) Opened Simultaneously w/N2 Fill Valve;Tank Pressure Dropped Below Tech Specs Limit. Caused by Electrical Short Between Wires for Fill & Vent Valves | /03L-0 on 790126: Tank Vent Valve (CV-3051) Opened Simultaneously w/N2 Fill Valve;Tank Pressure Dropped Below Tech Specs Limit. Caused by Electrical Short Between Wires for Fill & Vent Valves | | | 05000255/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000255/LER-1979-009-01, /01X-1 on 790220:design Review Indicated Butterfly Valves May Not Close Under Accident Conditions.Caused by Vague Purchase Specs Which Did Not Include Requirements for Closing Against Pressure | /01X-1 on 790220:design Review Indicated Butterfly Valves May Not Close Under Accident Conditions.Caused by Vague Purchase Specs Which Did Not Include Requirements for Closing Against Pressure | | | 05000255/LER-1979-009, Forwards LER 79-009/01X-1 | Forwards LER 79-009/01X-1 | | | 05000255/LER-1979-010-03, /03L-0 on 790207:during Resin Sluicing Operations, Manual Isolation Valve (MV-CVC502) Was Left Open,Resulting in 17 Gpm Leak to Radwaste Sys.Caused by Broken Valve Stop. Valve Stop Will Be Replaced | /03L-0 on 790207:during Resin Sluicing Operations, Manual Isolation Valve (MV-CVC502) Was Left Open,Resulting in 17 Gpm Leak to Radwaste Sys.Caused by Broken Valve Stop. Valve Stop Will Be Replaced | | | 05000255/LER-1979-011-03, /03L-0 on 790227:primary Data Logger Was Inoperable.Caused by Multiplexer Failure at Computer Input/ Output.Faulty Relays Replaced | /03L-0 on 790227:primary Data Logger Was Inoperable.Caused by Multiplexer Failure at Computer Input/ Output.Faulty Relays Replaced | | | 05000255/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000255/LER-1979-012-03, /03L-0 on 790201:during Normal Plant Operation, Primary Coolant Pump Inadvertantly Stopped.Reactor Immediately Tripped.Shutdown Margin Was Less than Specified in Tech Specs.Power Conversion Sys Was Emergency Borated | /03L-0 on 790201:during Normal Plant Operation, Primary Coolant Pump Inadvertantly Stopped.Reactor Immediately Tripped.Shutdown Margin Was Less than Specified in Tech Specs.Power Conversion Sys Was Emergency Borated | | | 05000255/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000255/LER-1979-013-01, /01X-1 on 790327:level in T-82C Safety Injection Tank Decreased While Draining D Tank to Permit Increase in Boron Concentration.Caused by Seal Leakage.Cv 3004 Drain Valve Will Be Repaired During Next Refueling Outage | /01X-1 on 790327:level in T-82C Safety Injection Tank Decreased While Draining D Tank to Permit Increase in Boron Concentration.Caused by Seal Leakage.Cv 3004 Drain Valve Will Be Repaired During Next Refueling Outage | | | 05000255/LER-1979-013, Forwards LER 79-013/01X-1 | Forwards LER 79-013/01X-1 | | | 05000255/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000255/LER-1979-014-03, /03L-0 on 790315:during Normal Plant Operation, Primary Computer Stopped,Due to Computer Program Failure. Computer Reprogrammed & Restored to Operability | /03L-0 on 790315:during Normal Plant Operation, Primary Computer Stopped,Due to Computer Program Failure. Computer Reprogrammed & Restored to Operability | | | 05000255/LER-1979-015-01, /01T-0 on 790409:refer to from Dp Hoffman to Dl Ziemann Re Pipe Supports | /01T-0 on 790409:refer to from Dp Hoffman to Dl Ziemann Re Pipe Supports | | | 05000255/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000255/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000255/LER-1979-016-03, /03L-0 on 790406:diesel Generator Output Breaker Has Potential to Lockout Open.Caused by Failure of Contact on Shutdown Sequencer to Operate.Sequencer Repaired | /03L-0 on 790406:diesel Generator Output Breaker Has Potential to Lockout Open.Caused by Failure of Contact on Shutdown Sequencer to Operate.Sequencer Repaired | | | 05000255/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000255/LER-1979-017-03, /03L-0 on 790404:while Taking Battery Voltage Readings,Two Cells in Station Battery 2 Burst Due to Explosion of Hydrogen Inside Cells.Battery Taken Out of Svc. Two Replacement Cells Ordered | /03L-0 on 790404:while Taking Battery Voltage Readings,Two Cells in Station Battery 2 Burst Due to Explosion of Hydrogen Inside Cells.Battery Taken Out of Svc. Two Replacement Cells Ordered | | | 05000255/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000255/LER-1979-018-03, /03L-0 on 790409:reactor Made Critical W/O Conducting Flow Test of Lines.Caused by Misinterpretation of Tech Specs.Personnel Instructed to Exercise Care When Reviewing Operability Requirements | /03L-0 on 790409:reactor Made Critical W/O Conducting Flow Test of Lines.Caused by Misinterpretation of Tech Specs.Personnel Instructed to Exercise Care When Reviewing Operability Requirements | | | 05000255/LER-1979-019-03, /03L-0 on 790331:sump Drained to Auxiliary Bldg Floor Drains Through Test Connection Located Between Containment Bldg Isolation Valves.Caused by Communication Failure.Corrective Action Still Being Evaluated | /03L-0 on 790331:sump Drained to Auxiliary Bldg Floor Drains Through Test Connection Located Between Containment Bldg Isolation Valves.Caused by Communication Failure.Corrective Action Still Being Evaluated | | | 05000255/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000255/LER-1979-020-01, /01T-0 on 790501:restraints for Piping Between Power Conversion Sys Safety Injection Tanks B & D Not Adequate.Caused by Program Error Used by Consultant to Determine Hanger Placement | /01T-0 on 790501:restraints for Piping Between Power Conversion Sys Safety Injection Tanks B & D Not Adequate.Caused by Program Error Used by Consultant to Determine Hanger Placement | | | 05000255/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000255/LER-1979-021-03, /03L-0 on 790427:during Routine Surveillance of safety-related snubbers,S-44 (LPIS Pump Discharge) Had No Visible Oil Level.Oil Leakage from Snubber Caused by Failed O-ring,attributed to Ald Age.Ring Replaced | /03L-0 on 790427:during Routine Surveillance of safety-related snubbers,S-44 (LPIS Pump Discharge) Had No Visible Oil Level.Oil Leakage from Snubber Caused by Failed O-ring,attributed to Ald Age.Ring Replaced | | | 05000255/LER-1979-022-03, /03L-0 on 790426:during Routine Surveillance of safety-related snubber,S-9 (Main Steam Line) Had No Visible Oil Level.Oil Leakage from Snubber Caused by Failed O-ring,attributed to Old Age.Ring Replaced | /03L-0 on 790426:during Routine Surveillance of safety-related snubber,S-9 (Main Steam Line) Had No Visible Oil Level.Oil Leakage from Snubber Caused by Failed O-ring,attributed to Old Age.Ring Replaced | | | 05000255/LER-1979-023, Forwards LER 79-023/03L-0 | Forwards LER 79-023/03L-0 | | | 05000255/LER-1979-023-03, /03L-0 on 790518:leak in Regenerative Heat Exchanger (E-56) Shell Side Vent Line Resulted in Degradation of Chemical & Vol Control Sys.Caused by High Porosity in Weld.Weld Ground Out & Repaired | /03L-0 on 790518:leak in Regenerative Heat Exchanger (E-56) Shell Side Vent Line Resulted in Degradation of Chemical & Vol Control Sys.Caused by High Porosity in Weld.Weld Ground Out & Repaired | | | 05000255/LER-1979-024-03, /03L-0 on 790608:level in Safety Injection Tank Fell Below Tech Spec Limit.Caused by Annunciation of Independent Level Switch.Switch Adjusted | /03L-0 on 790608:level in Safety Injection Tank Fell Below Tech Spec Limit.Caused by Annunciation of Independent Level Switch.Switch Adjusted | | | 05000255/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000255/LER-1979-025-01, /01X-1 on 790619:heat Transfer Coefficients of Component Cooling Water Heat Exchanger Were Less than Required.Caused by Fouled Tube Sides.Tubes Will Be Cleaned More Frequently | /01X-1 on 790619:heat Transfer Coefficients of Component Cooling Water Heat Exchanger Were Less than Required.Caused by Fouled Tube Sides.Tubes Will Be Cleaned More Frequently | | | 05000255/LER-1979-025, Forwards LER 79-025/01T-0 | Forwards LER 79-025/01T-0 | | | 05000255/LER-1979-026-03, /03L-0 on 790604:steam Generator Chemistry Ph Dropped Below Tech Spec Min When Condensate Polishers Placed in Svc.Caused by Resin Leakage from Polishers Due to Defective Septums.Resin Mixture Changed;Chemical Feed Ended | /03L-0 on 790604:steam Generator Chemistry Ph Dropped Below Tech Spec Min When Condensate Polishers Placed in Svc.Caused by Resin Leakage from Polishers Due to Defective Septums.Resin Mixture Changed;Chemical Feed Ended | | | 05000255/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000255/LER-1979-027-03, /03L-0 on 790614:during Normal Power Operation, Conductivity of B Steam Generator Increased to 7.65 Micro/Mhos Per Cm Beyond Tech Spec Limit.Caused by Condenser in Leakage | /03L-0 on 790614:during Normal Power Operation, Conductivity of B Steam Generator Increased to 7.65 Micro/Mhos Per Cm Beyond Tech Spec Limit.Caused by Condenser in Leakage | | | 05000255/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000255/LER-1979-028-03, /03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction | /03L-0 on 790623:conductivity & Sodium Concentration in Steam Generator a Exceeded Tech Spec Limits.Caused by Combination of Condenser Tube in Leakage & Chemical Hideout Return as Result of Power Reduction | | | 05000255/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | |
|