ML19256B822
| ML19256B822 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/09/1978 |
| From: | Pletke L, Rise D, Rogers L BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-TF, TASK-TMR 146, PROB-780509, NUDOCS 7909140299 | |
| Download: ML19256B822 (8) | |
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i SITE PROBLEM REPORT TRANSMITTAL
- * *
- CLEAPID * * *
- To:
Change Control For Distribution File:
13-f -/ V4 S. H. Klein - Quality Assurance Contract No.:
620-00o4 Central Engineering Files SPR: /Y/>
_ J.P. Org/')E Y - Task Engineer (s)
Title:
eoss of 44
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L.A.h 27tB - Pro]ect Manager fea 2nj. n+ bo+ co ml: h'e~s Date:
fr-/ 2 - 78 Status Code:
C L. C. Rogers - MET. ED.
P. E. Penooe-/
F. R. Faist - TOLEDO J. R. Bohart - Intl. Support B. A. Karrasch - Plant Integration Attached is one copy of dite Problem Report No.
/ t' 6 which was processed on Contract 620-00 0 6 Future contracts. have been reviewed for the potential of a similar problem. This problem is/is not considered applicable to other contracts PIMARKS:
m NUCLbAR SERVICE SUPPORT ENGINEER
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PDS-?l09t(8-70)
.c SITE PROBLE!.i REPORT BAGCOCK & YlIlCOX
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620-0006 1156 o
Jersey Central P.A.
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PARIh0.[lA5Kh0. GROUP NO.
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,_.s YENDOR Binghan y 7.-
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Ph 9LEH CONT ACT itTLE (MAX 30 CEt.RACTERS)
Loss of PC Pumps & Seal In.jection at Hot Conditions DESCRIPT10N Of PROCLEH:
See Attachment A (Unusual Occurrence Report)
See Attachment B E
2 e-6 S
b STATUS-ACTION 10 DATE, INCLU0thG PERSONS COHTACTED:
U. H. Spangler, L. R. Pletke, R. P. Williamson, J. D. Dempsey Bingham-Willamette Company See Attacicent C FURTHER ACTIOM RECOMMENDED BY SITE PERSONNEL:
Engineering evaluation report to be cubmitted to the site.
O:-
No further action required.
RESOLUTION:
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'EE 11LLE ISLAND STARTUP. TEST ['.,
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9-UNUSUAL OCCURRENCE rep 0RT_
Q*r I '; M7; Attachment A 7
Date of '$ccu'rrence 9-6-77 h
Unit ptt.r.ber 2
Report 13pyber 7
Time of Occurrence 2255 Critique !!inutes Attached: Yes No X Subj ect:
CONDENSATE POLISIIER RESIN MIGRATION
'1.
Description of Occurrence and General Desinnation of Apparent Cause:
(Design Material Personnel Procedurc x Other
)
At about 2255 on 9/6/77, a low nuclear services closed cooling water (NS) suction press. alarm was received in the control room.
Shortly af ter tlic alarm, both NS pumps tripped.
The standby pump then started automatically and immediately tripped. All three US pumps tripped due to the lou motor Inspection of the suction strainers on cooling unter flow interlock.
all three NS pumps revealed gross quantitics of Condensate Polisher Rcsin clogging the strainers.
a 2.'
Operating Conditions at Time of Occu' rence:
Hot Functional Testing in progress (TP 600/28).
Reactor Coolant System at 2155 psig & 532* F.
Four Reactor Coolant Pumps operating and turbine Secondary plant systems operating to support condenser on turning gear.
vacuum.
a Irmediate _ Evaluation, Corrective Action Taken:
3.
Het-Ed personnel in the control roon immediately secured all critical These included all four reactor components supplied by the NS system.
the operating make up pump (MU-P-1A), Instrument Air coolant pumps, Shift Compressors, and Reactor Building Emergency Cooling Pumps.
personnel attempted to supply cooling water to MU-P-1A from the alter-nate supply, Nuclear Services River Uater (NR) System, but MU-P-1A could The Service Air System was aligned to supply instrument not be s tart e.L.
!)caineraliced Water uns isolated to all systems to prevent Air, anu further migration.
At approximately 0030, 9 /7 /77, MU-P-1B was started Pump Seal using Cooling Water from the NR system and Reactor Cualant Injection was re-established using the Bingham procedure for loss of scal li.j ection.
O 19i6241 2 or B
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1.6E !!ILE ISLAUD STARTUP AUD TEb.
Report #7 UNUSUAL OCCURREUCE REPORT (Cont 'd.)
TMI Unit 2 O
4.
. In Further Evaluation or Corrective Action Necessary:
Yes, (1) S. Kakarla, UE6C Startup will close out GPU Problem Report #2339 (attached).
(2) Internals Jn DW-V173 will be reinstalled to prevent reoccurrence.
(3) The Dcmineralized Uater System will be completely flushed and all systems supplied by it will be checked for the presence of r esin.
5.
Evaluation:
The cause of the incident is knean.
The internals in check valve DU-V173 were removed to allow transferring water from the Borated Water Storage Tank to the Dcmineralized Water Tank.
This, however, requires closing DW-V172 uhen trans ferring condensate polisher resin for regeneration to prevent back flow of resin into the Dcmineralized Unter system. This code of operation has been 'used on several occasions and had been used Presently for about a veck with no complications.
The temporary water transfer alignment was controlled by a Met-Ed Generated Temporary Procc-dure uhich did not specifically require closing DW-V172 when transfer-(})
ring Condensate Polisher Resin.
Damage from the Resin Migration is limited to potential failure of the Reactor Coolant Pump seals due to loss of seal injection with the Pumps stopped.
The extent or reality of this damage vill not be known until disassembly of the Reactor Coolant Punp Scals for inspection.
The Dcmineralized Water System has been flushed clean of Condensate Polisher Resin and all systems supplied by it have been checked for the presence of resin.
Resin was found only in' Condenser Vactium Pumps, and the Suction Strainers of the US Pumps and Internediate Cooling (IC) Pumps.
All three systems will be flushed clean of resin.
Strainer sizing for the US pumps was such that Rccin Beads could not pass through them.
Therefore, no downstream contamination from Rcsin occurred.
This was verified by Flush Sampics on downstream components.
The ICCU system did have some resin enter into it and it is being taken out in the system filters.
e 1916 2'42 Q
( SE MILE ISLAND STARTUP AND Th.Report #7 s'
UNUSUAL OCCURRENCE REPORT (Cont'd.)
W I Unit 2 5.
Evaluation:
(cont'd.)
The inability of Plant Personnel to restart a makeup pump using Nuclear flow Services River Uater System for cooling was due to inoperative cuitch NS-FS-3102.
The Low Cooling Water Flow Switches on all three in service properly.
This Flow Switch on makeup pumps are not yet HU-P-1B had been mechanically defeated and therefore alloued MU-P-1B
- If these flow switches had been complete and operational at to start.
this tice, MU-P-1A could have becn re-started in ample time to prevent the potential Reactor Coolant Pump Scal Failure based on the ability following this to perform a safe and orderly cooldown of the plant No Technical there are no unresolved Nuclear Safety questions.
- incident, Specifications were violated due to the plant still being in a pre-This incident is classified as an unusual operational test status.
and while not a reportable incident, the NRC was verbally occurr ence, notified on 9/6/77.
6.
Temporary Corrective Action:
- 1) Secure all Critical Components requiring cooling from the US system.
Isolate Domineralized Water System to prevent Further Spread of
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Place Backup systems in service to allcw safe plant shutdoun Rcsin.
(service air to instrument air, UR system supply cooling to MU-P-1B).
Date Complete - 9 /7/77.
- 2) Place Plant in a cold shutdown condition. - Dat'e Compicte - 9 /8/77.
7.
Permanent corrective Action:
Re-install internals Flush the Demineralizc' Uater System clean of resin.
in DW-V173.
Date Complete - 9/8/77.
Flush the Condenser Vacuum Pumps, NS System and IC System Clean of Rcsin.
Date Complete - Completion Date Complete CPU Problem Report #2339 Completion Date I
e i916 243 b
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T(ruiE MILE ISLAND STARTUP AND TES.
Report #7 I
TMI Unit 2 UNUSUAL OCCURRICICE REPORT (Cont 'd.)_
0 8,
Similar Unusual Occurrencesj None
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EVALUATORS: /
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S.G. /Po !
Date V-/3V)
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T.M. llawkins Date
%& 9-t s Toole Date 9'I*
\\,6 APPROVED:_
Test Supt.
Date G
O CORRECTIVE ACTION COMPLETE:
GPU Test Supt.
Date DISTRIllUTION:
S. Rakarla J.R. Thorpe (2)
J.J. Earton R.L. Uilliams R.P. Brownewell G.P. Itiller R.F. Fenti M. A. Nelson J.E. Uright Shift Test Engineers L.C. Ro ge rs W.T. Gunn D.E. Iletrick R.W. Ileward, Jr.
R.F. Wilson T.)!. llaukins File S.G. Poje 1916' 244-o -( 9
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z Attachment B The following is a chronology of events specifically concerned with the RC Pumps as a result of the transient described in the Unusual Occurrence
' Report (Ilumber 7).
NOTE:
Intermediate Coo' ling to the RC Pumps was continuously maintained.
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September 6,1977:
22: 55 IIS Cooling Water Pumps Tripped (This system supplies cooling vater to both the RC Pump Motors and the Makeup Pumps. )
22: 58 All 4 BC Pumps are =anually tripped O
23:25 MU Pump 1C trips off line 23: 51 W Pump 1B. trips off line (This pump was not reported as operating by the operating personnel, but the computer log indicates otherwise.) All injection is lost to the RC Pumps September 7, 1977 00:27 MU Pump 1B is started 00:35 Seal Injection is restored at 2 spa O
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Attachment B s -
September 7, 1977 (cont'd) 02:20 Seal Return lines are opened NOTE:
Injection lost for a total of 44 minutes. The RC Pumps were not restarted.
This time log has been compiled from the temperature recordings of Bearing Outlet Temperature and Seal Return Temperature, the Cavity Pressure recordings, the Operator's Log, and the Computer log. Not all of this data agrees, as shown, on all sources but represents the Site's best guess based on limited data of the actual sequence of events.
Cavity pressures were staging properly before the' transient but were very erratic once the seal return lines were reopened. After the transient, G-all four pumps exhibited pressures indicating that only one seal was holding on each pump. Further, temperature data indicates that all four pumps exceeded the 185 F limit via the pump bearing outlet tcmperature or the seal inlet temperature. Maximum temperatures of 300 F vere recorded for two pumps.
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[916 246 n
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Attachment C The decision was made to inspect the seals on all four pumps as a result of all four pumps having exceeded the 185 F limit.
In conjunction with
' this effort, it was decided that the two casing / stuffing box caskets on the 2B pump were to be replaced (see SPR 145).
Bingham representatives, Messrs. Porter, Rogers, and Peterson, plus Mr. Dempsey, B&W Engine' ring, arrived on site;and the seal inspection was begun.
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All four pumps have been examined and new carbides installed on all four pumps. The old carbides vill be relapped and returned to the site as spare parts. The 1A and 2B pumps did not exhibit any excessive heat migration or, consequently, any significant seal damage. The 2A and 1B
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did show heat checking on the seals. Unfortunately, seal leakage was not a recoverable data source at the time; and so no data is available for which pumps were_ leaking and by how much at the time of this transient.
This problem has since been corrected by adding a recorder to the drinking-bird circuits.
The pumps vill be retested upon completion of reassembly of the pumps and reassembly of other equipaent disassembled as a result of this outage. It is not expected that further action vill be required to resolve this probles.
(2) 1916 24?7
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