ML19289G080
| ML19289G080 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1979 |
| From: | Fasano A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 7906260222 | |
| Download: ML19289G080 (8) | |
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Status Report (Maintenance)
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Subject:
Review of maintenance activities and equipment status with j
high probability to have had some input to the March 28, 1979, event.
M The inspection scope is to ascertain maintenance involvement in
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.4 a time period just prior to the event, and a more general condition 4
of plant systems and components that have or suspected to have con-
- 1 cributed to the event.
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The approach to this incpection was the normal inspection of records
=j and discussion with licensee personne1.
i The f ollcwing doc =ents and files were reviewed in the development
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of the content of this report:
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-- The maintenance - Werk Request Log, Unit 2, Starting with 1979
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-- Administrative Procedure 1026, Corrective Maintenance and ah Ma,".inery History, Rev. 8, 11/29/78.
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-- Administrative Procedure 1002, Rules for the Protection of Li
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E=ployees Wcrking on Electrical and Mechanical Apparatus, Rev. 9, 2/23/77.
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-- Adarinistrative Procedure 1021, Plant Modification, Rev. O, 7/22/77.
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-- Staticn Corrective Maintenance Procedure, 1407-1.
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.> i 3i Unit 2 Machine History Files, (selected sections), May 8, 1979.
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-- Unit 2 V Ive List (2075), 2 Volumes
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--- Drawing 2006, Rev. 23, Floor Diagram Makeup Water treatment and
- p Condensate Polishing.
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-- Shift Maintenance Log L.
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-- Instructions for Operating and Repairing Consolidated Electro-
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?:CS matic Relief Valve, B&W Instruction Book No. 620-0006;01-004 00.
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-- QC Surveillance Report No.77-266, 10/26/77 Mechanical Main-X
,y tenance RC-RV2 Inspection Repair and Testing, WR 1467
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-- Machine History Card, Mechanical, RC-RV 2, Electromatic Relief
'i Valve, 10/26/77 w
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-- Machine History Card, (Unit 1), RC-RV 2 and RC-V2 10/26/74,
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'd 9/29/75
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-- Letter BGJ to GPU, Dresser Valve RC-V2, 9/2/75 4
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-- Letter, GPU to UESC, Dresser Valve-RC-V2 d
-- UJG 3079 SR 14 Rev. 13 12a IN
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-- Machine History Card,1/23/79 (see RR-Co '711), Meggard and Bridges em
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Motor Windings due to bellows failure or atmospheric relief valves,.
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(similar documents for emergency feed Pumps 2A and 2B, EF-P-2A, w
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EF-P-23)
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-- Megger test, 1/23/79, Control Building East, EF-P-2A.
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-- UE&C Equipment Data Sheet Mechanical, 7/28/77, Ingersoll Rand, 1
$7 470 gpa at 25 10 and 3560 RPM, discharge pressure 1500 psi, 100*F W
(EF-P-2A)
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-- UE&C Equipment Data Sheet Motors, 7/28/77, EF-P-2A, (CE SN-,
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-- UE6C Equipment Erection Data Sheet Vibration Record, EF-P-2A, 4?
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7f28/77 W
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-- UE6C Motor Bumping Check List, 7/27/77, Discharge pressure
- E 1470 psi, EF-P-23
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. ql UE&C Equipment Data Sheet Motors, 7/27/77, EF-P-2B fh
-- UE&C Erection Data Sheet Vibration Record, 7/27/77, EF-P-2B d
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-- UE6C Motor:Bu= ping Check List, EF-P-2B, 7/27/77 i
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-- Letter, GPU to UE6C, Dresser Valve - RC-V2 T-
-- Dwg 3079 SH 14 Rev. 13 1
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-- Machine History Card, 1/23/79 (see Wr-CO-711), Meggard and Bridged Motor Windings due to bellows failure on atmospheric relief valves, (similar documents for emergency feed Pumps 2A and 2B; EF-P-2A, EF-P-2B)
--UELC Equipment Data Sheet Mechanical, 7/25/77, Ingersoll Rand, 3
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j 470 gpm at 2560 and 3560 RPM, discharge pressure 1500 ps:., 100 F (EF-P-2A) t
-- 'JE6C Equipment Data Sheet Motors, 7/28/77, EF-P-2A, (GE SN-,
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." t 4000 V AC)
-- UELC Equipment Erectiun Data Sheet Vibra tion Record, EF-P-2A,
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7/28/77 f
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-- UE6C Equipment Data Sheet Motors, 7/27/77, EF-P-2B j,5
-- UE&C Motor Bumping Check List, 'T/27/77, discharge pressure J>j 1470 psi, EF-P-2B 1^
UE&C Erection Data Sheet Vibration Record, 7/27/77, EF-P-2B i
-- UE&C Motor Bumping Check List, EF-P-2B, 7/27/77 1,
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-- Manual 31700 Consolidated closed Bonnet Maxiflow Safety Valve, 1
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B6N Instruction Ecok No. 620-0006,01-003-00.
(Dresser Valves)
-- WR No 340, 3/25/77-v/ Procedure, Hot N2 Gas Testing of I
h Pressurizer Code Ralief Valves.
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Persons Contacted 3 }1 W
..,gj James, R. Flcyd, Supv,. Station Operations
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T. H. Hawkins, Maintenance h_ b c4 J. M. McGarry, Supv. Mechanical Maintenance b)
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{!j I. D. Porter, Engineer SRI
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D. M. S'.ovlin, Supt. Maintenance
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R. E. Steglitz, Supv. Unit II Maintenance
. f G. Wolfe, 1/c Maintenance a
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C. Newton, 1/c Maintenance
- 1 4:i J. Eachofer, Maintenance 4
-d The maintenance work request log contained work request related to
- *J the balance of plant. A large number of these requests were in the
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",4 heater drain, condensate and water treatment syste=s.
Discussion with licensee persennel indicate that the majority of proble=s have been in
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the balance of plant systems. The apparant initiation of the turbine trip et
{j then reactor trip on March 28, 1979 began by the loss of balance of H
{j plant feedwater associated with the condensate systems.
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,'i The corrective maintenance is administered through the use of work
- j requests.* The work request form allows a plant staff me=ber to report hvg EW that a need for some type of works or change / modification exists.
It 9.h t'[f allows for classifying, level of control, QC or non QC, change, =odification d
kE of corrective, radiation or non radiation.
It provides for assurances of w
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' Job ticket - interchangeable.
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The corrective maintenance responsibilities are discribed for the
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Unit Superintendent, Supervisor of Operations, Supervisor of Maintenance, J
d Maintenance Foreman, Operations Shif t Foreman and Supervisor - QC.
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work request got to the Supervisor of Maintenance.
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'i The operation Shift Foreman approves commencement of work af ter assuring Tech Spec compliance and returning component / system to Service ofter assuring satisfactory retest.
The correct and acceptable retest in_an operations r e s p en s _ib ili ty.
Maintenance initiates log control operations maintains control for use of th= tags the maintenance of tag status in kept by operatien to assure kncwledge of the plant / system status.
The inspector reviewed selected files located in Unit 2 Mechanical Maintenance Office, May 8, 1979. The reviewed material included the Condensate, Emergency Feed, and the Feedwater Machine His ory files.,
The file on the Feedwater had material related to FW-P-1B, WRCO 180,12/13/78, I
stuck shaf t problem and WR 1357, 1/13/78. The files did not appear to con-tain a mechanical history that would have indicated as being contributory to the March 28, 1979 event.
Infor=ation gathered and reviewed on the electromatic relief valve in not complete. The valve is an electrically actuated pressure relief device.
It may be operated by closing a switch or it may be set up in conjunction with a pressure sensitive element to relieve pressure automatically.
'Ihe referenced QC S.:rveillance report,77-266, 10/26/77 documents the 3
witnessing of:
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Electrical test with no pressure applied 7
- Pressure applied to 2300 psig and electrically " popped" three I
consecutive times in five minules.
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- I.eak tested af cer " popping" at 2300 psig and held for 5 minutes.
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The valve was leaking during the hot junctional test and corrective i
maintenance was performed then tested, 10/26/77.
s The wiring was modified, Reference Drawing 3079, SH 14, Rev. 13, _
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h for the indication of power across the solenoid.
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Discussion indicated that the valve had operated during past transients, b$
The more rescent history in that RC-RV-2 has been Icaking and was believed to
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W have been as high as 5 to 6 gpm just prior to March 28, 1979.
p The block valve RC-V2 had work performed on it, 9/22/78 where the ha motor operator was removed and replace, the valve was cycled.
Discussions f
with licensee personnel indicated that concern that the block valve could stick tk S4 g
shut or open if used.
The valve appeared to be operable during the March 29, (F1M 1979 event once it was activated at about 2.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the trip.
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There was discussion about the pressurizer valves, RC-RV2 and RC-V2 M
%i h1 being interchanged with Unit 1.
The early history of these valves have not g
P clarified the actival history.
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The =achine history on the electrical emergency feedwater pu=ps, 3-M EF-P-2A and EF-P-2B does not appear to indicate any major problem. The tN$
most recent history indicated that motor windings and connecting electrical g
YX cables were checked af ter steam leakage, due to bellows failure related to i*db g
the at=ospheric relief valves failed. Dsicussions with licensee personnel M
Q confirm a lack -f problems witt. the emergency feedwater equipment.
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The pressurizer safety valves, RC-R-1A and RC-R-13 history does not in-dicate a problem. Work Request 340 contains test results for lift of these
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valves.
"'hese results indicated that the settings are within the 17. of M
I4 sf 2450 psig. set point.
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o I f The inspector met and spoke to maintenance (mechanical) workers that
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- 4 were assigned the llP to 7A, March 28, 1979 sni.c The discussion indicates 2%
SM that the majority of mechanical maintenance was being performed on Unit 1 in the hd final stages of Unit I refueling outage. They were on their way to the M
[1 warehouse when the turbine trip occurred. They remembered hearing the ij j
relief valves actuate.
They did work on Unit 1 Water treatment system involving 2
1 velves WT-V-62 and V-63.
They were held after their shift completion and 4
b blocked off these two valves, (removed intervals} so that Unit 1 Water could be
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'l made available to Unit 2.
Thi s was done around 7:45 am.
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$1 The inspector learned from other licensee personnel that: The pressurizer
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- j-spray had been elected to be operated in the manual node; there has been a problem
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i with the automatic makeup tank overhead gas centrol system Hydrogen was
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being fed ia an alternate route which required a person to manually feed
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This problem appears to have been there before operatica 4?
took over the system. Control room indication on the makeup tank pressure A
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valve RC-RV2 and possibly one of the two code safety valves on the pressurizer were leading the major leak was being attributed to the electromatic Operations 4
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believed RC-R-13 to be the leaker of much less magnitude. Total known leaks i
were under Tech Spec limits.
Discussions indicat ed that the code safety valves were not tested in place en the pressurizer and as far as can be determined had never lifte/ during a previous transient.
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