LER-1979-006, /01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3021979006R01 - NRC Website |
|
text
-
/
NaC FCRM ',64 U. S. NUCLEAR REGULATO R Y CC'.t'Al*JCN
+
<7 rn LICENSEE EVENT REPORT EXHIBIT A I
.l@
l Contact sLcCie l l l l l 1 mte A$s paint ca tvet ALL accuinto iNeoauaricw i
4 ; 1 1 l ; 1 gl,_ l _ j g [Fl Ll q R) Pj3Jgl0 10l-l01 0l 0 l 0l0 l -l0 ; O ;gg 9 g o
i 7
. 9 LICtsset C;Cg to M
lac &%it % ve64 il 26 Lic4%54 Tvet A 67==f 34 CCN'T 30i 2 glo1 21 Ol1I 719 l@l 012l 0l2l7I 91 @
LLJ@l Oi s! Oi 10 i i
o
.C S
63 6l DOC s E T w'.s g a 3.
49 tvtNTCATI 74
't mE*04f; ATE 4.
EVENT DESCAWTION ANO PRCS ASLE CONSEcutNCES h o
2 IAs a result of Florida Power's review of the Cveln Tun Roln,d Ronnrt-fe J
has been determined'that the present Technical Specification 5.7, figure 4 ITTT1 i or transient limits on Rapid Depressurizations. and hich oressure iniectici f
, tests are in disagreement with that report.
Re-tabulated figures are basedt o
lon " State of the Art."
No effect noon health and safety of the nublic I
o
, as the revised figures have not been exceeded in either case. No previous ;
llDJ ' occurrences, i
su'aEc*cs s$Ne
'E['
"[o'c'e' sLs's$5s covecNENT Ccos 1 xl xi@ L,,xJ@ LzJ@ l 7 I zl z I z l zl z 18 LJJ@ L1) @
a i,
,o a
o i.
o
- o SEQttNflat OCCgnagNc3 agpogy mg.it:0N
@ s(jg' SENT vtan
[,-,-j l o I ol 6 I [f, _j lo !11 LIJ l,.-J Lo.J m EPC A T NO.
C00E fvet No g e no 17 l 9 I a
ai n
u 2
n n
u 2
u
'a O
ON 8L %f T
wou*s 5S i PCs 9
Sup*L E MAN 84 mEm T
4 Lx_j@LxJ@ l2J@
L2JO I ol o I of of l.r_J@
L.N_j@ W@ l z i 9l9 l 9l@
3J
- 4 31 34 37 4W el 42 eJ aa 47 CAuSE cfSCRIPTION AND CCAREC n%i ACTIONS
- As a result of " State of the rt" calculations and data, revised limit
[ figures for Rapid Depressurization and hieh oressure injec*fon en=re %"a 1
i i emerged.
Those areas affected in Tech. Spec's will be revised and submitted to licensing for approval.
I u,,,L,,,j 1
so
's'r'aTs" er-in t rarvs @ oisE:iS v'
%. wn.
- se vaav :ssc=.ar N [D_,j@l Encineerine evaluation I
W @ l Of7 l6l@l NA l
D a[f'u fv CC%? TNT a g t g as g s agLtast AMUNT Os a: Tis sTV Locat.0% 08 mELigt NA l
l u
I
[ z.J L,,zj@l i
a io 0 ;u.5.. EL Es*0scell0l@[zj@l NA l
PimlON%
s
=ri:..r.oN 1
i 7
..s:s,..'J.m'ii.
=is..v,e%@
Nuv,i.
i i T 1 I o I oI nl@l u
.o i.
- - a,c :,:ff;;,q,,o ic~e- @
I w L,z!@l
..,Slj@i;;;..... s @
vc -
[.
l NA f fII!IIiiII II l
- e 4.
3 (904) 795-6436 J. r - o-
,-es, sa..
C.,.E, An a (SEE TTACHED SUPPLEMENTARY INFORMATION S'dEZT)
Lnggg
SUPPLEMENTARY INFORMATION Report No.:
50-302/79-006/0lT-0 Facility:
Crystal River Unit #3 Report Date:
2 February 1979 Occurrence Date:
1 February 1979 Identification of Occurrence:
Revised component cyclic or Transient Limits based on " State of the Art" data and reported under Technical Specification 6.9.1.8.h.
Conditions Prior to Occurrence:
Mode 1 power operation (76%?
Description of Occurrence:
As a result of Florida Power's review of the Cycle Two Reload Report, submitted b; B&W, it was determined that items 11 and 15 in Table 5.7-1 of Technical Specification 5.7 were in disagreement with the report figures.
Item 11, Rapid Depressurizations, according to the Report should now read 40 and the number of test transients for the high pressure injection test, should also read 40.
This information was discussed with NRC Region II and per their request is being reported under Technical Specification 6.9.1.8.h.Through communication with B&W it has been determined that the 80 Rapid Depressurizations (item 11) presently addressed in the Technical Specification was based on the initial Reactor Coolant Stress Analysis and is valid. As a result of the " State of the Art" this figure has now been re-tabulated.
Similarly, the new figures for test transients, involving the high pressure injection test, were derived.
Analysis of Occurrence:
There is no hazard to the health and safety of the plant or general pub-lic.
The number of transients in both cases have not exceeded the revised figures as submitted by B&W.
Corrective Action
Those areas affected within the Technical Specification will be sub-mitted as a Technical Speciffaation change to NRC licensing for ap-proval.
Failure Data:
No previous occurrences.
/rc
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000302/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000302/LER-1979-001-03, /03L-0 on 790101:during Operating Daily Surveillance Log Survey (SP-300),noted That Pressure in B Core Flood Tank Was 630 Psi.Caused by Operator Error During Repressurization | /03L-0 on 790101:during Operating Daily Surveillance Log Survey (SP-300),noted That Pressure in B Core Flood Tank Was 630 Psi.Caused by Operator Error During Repressurization | | | 05000302/LER-1979-002-03, /03L-0 on 790102:33 Ft Wind Direction Monitor Was Inoperable.Caused by Wind Direction Sensor Bearing Being Contaminated W/Coal Dust.Sensor Renewed Thru Normal Maint | /03L-0 on 790102:33 Ft Wind Direction Monitor Was Inoperable.Caused by Wind Direction Sensor Bearing Being Contaminated W/Coal Dust.Sensor Renewed Thru Normal Maint | | | 05000302/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000302/LER-1979-003-03, /03L-0 on 790106:during Rx Runback Following Turbine Trip,Main Feedwater Block Valve FWV-30 Did Not Close.Caused by Valve Sticking on Its Back Seat.Corrective Action:Manual Cycling | /03L-0 on 790106:during Rx Runback Following Turbine Trip,Main Feedwater Block Valve FWV-30 Did Not Close.Caused by Valve Sticking on Its Back Seat.Corrective Action:Manual Cycling | | | 05000302/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000302/LER-1979-004-03, /03L-0 on 790115:cable Tunnel Sump Pump Failed to Start During Operability Verification.Maint Restored Sump Pump Operability.Caused Attributed to Failure of Pump | /03L-0 on 790115:cable Tunnel Sump Pump Failed to Start During Operability Verification.Maint Restored Sump Pump Operability.Caused Attributed to Failure of Pump | | | 05000302/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000302/LER-1979-005-01, Discusses Commitment Stated in LER 79-005-01T-1 Re MSIV Valves Not Closing within Design Time of Five Seconds During Double Ended Pipe Rupture.Util Has Determined That Upgrading Air Circuit to Seismic Class I Will Not Be Nec | Discusses Commitment Stated in LER 79-005-01T-1 Re MSIV Valves Not Closing within Design Time of Five Seconds During Double Ended Pipe Rupture.Util Has Determined That Upgrading Air Circuit to Seismic Class I Will Not Be Necessary | | | 05000302/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000302/LER-1979-006-01, /01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised | /01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised | | | 05000302/LER-1979-007-03, /03L-0 on 790117:reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci.Caused by Expected Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins | /03L-0 on 790117:reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci.Caused by Expected Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins | | | 05000302/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000302/LER-1979-008-03, /03L-0 on 790119:RC3-GP3-BL4 Light Did Not Extinguish When Test Switch Returned to Off Position.Caused by Dirty Contacts in Relay | /03L-0 on 790119:RC3-GP3-BL4 Light Did Not Extinguish When Test Switch Returned to Off Position.Caused by Dirty Contacts in Relay | | | 05000302/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000302/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000302/LER-1979-009-03, /03L-0 on 790124:while Performing Reactor Protection Sys Functional Testing,Rod Group 6 Dropped Into Core,Rod Group Overlap Was Exceeded.Caused by a AC Power Breaker Being Left Open | /03L-0 on 790124:while Performing Reactor Protection Sys Functional Testing,Rod Group 6 Dropped Into Core,Rod Group Overlap Was Exceeded.Caused by a AC Power Breaker Being Left Open | | | 05000302/LER-1979-010-03, /03L-0 on 790125:during Routine Operations,Air Handling Fan Failed to Start.Caused by Faulty Overcurrent Timing Relay | /03L-0 on 790125:during Routine Operations,Air Handling Fan Failed to Start.Caused by Faulty Overcurrent Timing Relay | | | 05000302/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000302/LER-1979-011-03, /03L-0 on 790210:reactor Coolant Dose Equivalent I-131 Exceeded Tech Spec Limits.Caused by Expected Spike Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Sys Cleanup Returned to Acceptable Limits | /03L-0 on 790210:reactor Coolant Dose Equivalent I-131 Exceeded Tech Spec Limits.Caused by Expected Spike Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Sys Cleanup Returned to Acceptable Limits | | | 05000302/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000302/LER-1979-012-03, /03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed | /03L-0 on 790214:during Safeguards Test, RB-3GP-2 Light Did Not Illuminate.Caused by Burr on Relay Shaft.Relay Cleaned & Burr Removed | | | 05000302/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000302/LER-1979-014-03, /03L-0 on 790220:decay Heat Cooler 3A Outlet Remote Shutdown Temp Indicator Inaccurate & Rendered Inoperable.Caused by Failed Resistance Temp Detector (Rtd). RTD Replaced & Sys Recalibr | /03L-0 on 790220:decay Heat Cooler 3A Outlet Remote Shutdown Temp Indicator Inaccurate & Rendered Inoperable.Caused by Failed Resistance Temp Detector (Rtd). RTD Replaced & Sys Recalibr | | | 05000302/LER-1979-015-03, /03L-0 on 790221:fire Svc Tanks 1-B & 1-A Contained Less than Min Volume Required by Tech Specs. Caused by Improper Design.Engineering Evaluation Initiated | /03L-0 on 790221:fire Svc Tanks 1-B & 1-A Contained Less than Min Volume Required by Tech Specs. Caused by Improper Design.Engineering Evaluation Initiated | | | 05000302/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000302/LER-1979-016, Forwards Supplementary Info Re LER 79-016/04X-0 | Forwards Supplementary Info Re LER 79-016/04X-0 | | | 05000302/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000302/LER-1979-017-03, /03L-0 on 790223:heat Trace Recorder for Concentrated Boric Acid Flowpath Was Malfunctioning & Rendered Inoperable.Caused by Failed Recorder Drive Wheel. Drive Wheel Replaced & Heat Trace Recorder Returned to Svc | /03L-0 on 790223:heat Trace Recorder for Concentrated Boric Acid Flowpath Was Malfunctioning & Rendered Inoperable.Caused by Failed Recorder Drive Wheel. Drive Wheel Replaced & Heat Trace Recorder Returned to Svc | | | 05000302/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000302/LER-1979-018-03, /03L-0 on 790301:inner Airlock Door Found Unlatched.Caused by Inadequate Latching Design.Corrective Action Will Be Determined Upon Results of Engineering Info Request | /03L-0 on 790301:inner Airlock Door Found Unlatched.Caused by Inadequate Latching Design.Corrective Action Will Be Determined Upon Results of Engineering Info Request | | | 05000302/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000302/LER-1979-019-03, /03L-0 on 790223:motor Driven Emergency Feedwater Pump Discharge Pressure Gauge EF-2-PI Was Out of Calibr. Caused by Inoperable Dampening Snubber Located in Sensing Line.Snubber Was Replaced | /03L-0 on 790223:motor Driven Emergency Feedwater Pump Discharge Pressure Gauge EF-2-PI Was Out of Calibr. Caused by Inoperable Dampening Snubber Located in Sensing Line.Snubber Was Replaced | | | 05000302/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000302/LER-1979-020-03, /03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins | /03L-0 on 790228:following Reactor Trip,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci Per Gram,Contrary to Tech Specs.Caused by Spike Following Reactor Trip & Leaking Fuel Pins | | | 05000302/LER-1979-021-04, /04L-0 During 1978:difference of More than Two Std Deviations Existed Between Preoperational Study & Operational Study in Metabolic Functions of Discharge Salt Marshes Adjacent to Facility.Cause Natural or Seasonal | /04L-0 During 1978:difference of More than Two Std Deviations Existed Between Preoperational Study & Operational Study in Metabolic Functions of Discharge Salt Marshes Adjacent to Facility.Cause Natural or Seasonal | | | 05000302/LER-1979-021, Forwards LER 79-021/04L-0 | Forwards LER 79-021/04L-0 | | | 05000302/LER-1979-023, Forwards LER 79-023/03L-0 | Forwards LER 79-023/03L-0 | | | 05000302/LER-1979-023-03, /03L-0 on 790308:discovered RCS C1 Concentration Was .17ppm,contrary to Tech Specs.Caused by Appearance of Suspended Solids During Cooldown When Boron Concentration Increased.Purification Sys Reduced Concentration | /03L-0 on 790308:discovered RCS C1 Concentration Was .17ppm,contrary to Tech Specs.Caused by Appearance of Suspended Solids During Cooldown When Boron Concentration Increased.Purification Sys Reduced Concentration | | | 05000302/LER-1979-024-03, /03L-0 on 790315:during Plant Heatup,Discovered That Temp Device at 175 Ft Elevation of Meteorological Monitoring Tower Was Inoperable.Cause Unknown.Temp Device Tested Satisfactorily & Returned to Svc | /03L-0 on 790315:during Plant Heatup,Discovered That Temp Device at 175 Ft Elevation of Meteorological Monitoring Tower Was Inoperable.Cause Unknown.Temp Device Tested Satisfactorily & Returned to Svc | | | 05000302/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000302/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000302/LER-1979-026-03, /03L-0 on 790318:during Reactor Startup,Discovered Absolute Position Indication for Rod 8 Was Inoperable.Caused by Sticking Reed Switch.Variable Ac Frequency,Applied to Reed Switch Circuit,Eliminated Sticking | /03L-0 on 790318:during Reactor Startup,Discovered Absolute Position Indication for Rod 8 Was Inoperable.Caused by Sticking Reed Switch.Variable Ac Frequency,Applied to Reed Switch Circuit,Eliminated Sticking | | | 05000302/LER-1979-027, Forwards Supplemental Info for LER 79-027/04X-0 | Forwards Supplemental Info for LER 79-027/04X-0 | | | 05000302/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000302/LER-1979-028-03, /03L-0 on 790321:while Performing Emergency Feedwater Sys Demonstration,Discovered Pump Discharge Pressure Gauge EF-2-PI Inoperable.Caused by Failed Pressure Gauge.Gauge Replaced | /03L-0 on 790321:while Performing Emergency Feedwater Sys Demonstration,Discovered Pump Discharge Pressure Gauge EF-2-PI Inoperable.Caused by Failed Pressure Gauge.Gauge Replaced | | | 05000302/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000302/LER-1979-029-03, /03L-0 on 790321:discovered Makeup Pump 3-C Discharge Stopcheck Valve MUV-2 Was Improperly Positioned. Cause unknown.MUV-2 Reset to Proper Throttle Setting & Returned to Svc | /03L-0 on 790321:discovered Makeup Pump 3-C Discharge Stopcheck Valve MUV-2 Was Improperly Positioned. Cause unknown.MUV-2 Reset to Proper Throttle Setting & Returned to Svc | | | 05000302/LER-1979-031-01, /01T-0 on 790412:during Routine Radwaste Release, Release Monitor Went Into High Alarm Because Radwaste Isolation Valves WDV-320 & 321 Failed to Close.Caused by Sticking Contacts in Monitor Bypass Switch | /01T-0 on 790412:during Routine Radwaste Release, Release Monitor Went Into High Alarm Because Radwaste Isolation Valves WDV-320 & 321 Failed to Close.Caused by Sticking Contacts in Monitor Bypass Switch | | | 05000302/LER-1979-031, Forwards LER 79-031/01T-0 | Forwards LER 79-031/01T-0 | |
|