IR 05000263/1975012
| ML20024G607 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/13/1975 |
| From: | Choules N, Jordan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G605 | List: |
| References | |
| 50-263-75-12, IEB-75-03, IEB-75-3, NUDOCS 9102130474 | |
| Download: ML20024G607 (11) | |
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U. S. NUCLEAR REGULATORY C0tStISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION III
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IE Inspection Report No. 050-263/75-12
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Licentce:
Northern States Power Company 414 Nicollet Itall Minneapolis, Minnesota 55201
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Monticello Nuclear Generating Plant License No. DPR-22 Monticello, Minnesota Category:
C Type of Licensee:
Bk'R (CE) 1670 Mwt Type of Inspection: Announced Dates of Inspection:
July 15-18, 1975 h&%.'$b'l47G yg yf
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Principal Inspector:
N. C. Choules
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Accompanying Inc.pectors:
Nonc Other Acconpanying Personnel:
None h.Ar:C ~f" I M 21
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Reviewed By:
E. L. Jordan Senior Inspector
'(Da't e)
Reactor Operations Branch
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9102130474 750015
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DR ADOCK 05000263 l
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$1fMMARY OF_TINDINGS
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Innycetion Summary
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inspection on July 15-18, (75-12):
Records, plant operations, and startup testing vere revieved.
!;o items of nonconpliance were identified.
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Enforecrent Action None.
1.f eentce Action on previous 1v ident ified rnf orecrent !!at t ern l'
1.
Failure of the Operation Comnittee to review operating procedure 11.7.3" :
Review of the Operation Connitt ee necting minut es lio. 547 held on June 25, 1975 indiented that a reviced B.7.3 proerdure hnd been reviewed and approved by the committee.
Thin Attn is considered resolved.
Failure of thgoperation Cort,ittee to review 1;nC identified noncom--
2.
pliance iten:--
Review of the Operat ion Cornittee reetiny, ninutes No. 549 indicated that NnC identifled noncorpliance itern during 1975 had been revieved by the coreittee.
Th l t, item is considered resolved.
O_ther Signsficant Findinqn
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v-S A.
Systens and Components The off-gas radiation level at the air ejectorn continuet to it. Icase indicating additional fuel Icaters.
The licensee is ucing power as required to maintain a nearly constant radiation reI c c't a t the air ejectern r.nd prer.crve fuel integrity.
(Report De. ails, Paragraph 5.f.)
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Tacility, items _(plans and Procedures)
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1..
The licensee plans to shutdown Septenber 12, 1975 for a refueling outage. At that tine the terutining original 7 X 7 fuel anseeblies will be removed and replaced with 8 X S fuel assemblics.
2.
ac 4-inch recirculation bypass linen may be replaced during the 3epten.ber outage depending on the resultn of the inspectiour, of
< % volds in these linen.
If IE Inspection Rpt. No. 030-263/75-09.
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1he licensee plans to remove a drain line which is attached to the reactor cicanup syst?m line connected to the botton of the reactor pressure vecsci during the September outage. The drain
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line acts as a crud trap causing high radiation levels in the areas where control rod drive naintenance work is perforced.
C.
Managerial items
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None.
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D.
Noncompliance Identified and Corrected by Licensee None.
E.
Deviations None.
F.
Status of Previsouly Reported Unresolved Itens Not applicable.
Hannterent Interviev The following persons were present at the inanagenent interview conducted on July 18, 1975:
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C,'F.
Larson, Plant Manager
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H.11. Clarity, Superintendent Plant Engineering and Radiation Protection W. E. Anderson, Superint endent Operations ond Mair.tenance D. D. Antony, Plant Engineer Operations A.
p.ecorde The inspector stated that he had reviewed selected parts of the licensee j
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record storage, system of record retrieval, and' drawing update system and they appear to be adequate.
(Report Details, Paragraph 1)
B.
Plant Operations
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The inspector stated that he had reviewed general plant operations which included a tour of the plant, review of operating records and discussions with operators and no apparent dicerepencies were noted.
(Report Details, Paragraph 2)
C.
' Abnormal Occurrences
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The inspector stated that he had reviewed A0 75-08, 75-09, 75-10 and 75-12 with the licensea's representatives,and it appeared that appropriate ccrrective action had been taken for the occurrences.
(Report Detafin, Paragraph 3)
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Startup Testing he had reviewed startup testing following the The inspector set January-February,1975 outage and no apparent discrepencies vero noted.
(Report Details, Paragraph 4)
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Outstandin,n and Misec11aneous its Subject itett.s including turbine piping thinning, recirculation pump
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seal 1cakage annunciators, augmented of f gas systen, notor opernted valve overload indication, and IP, Bulletin 75-Q3 were dineussed.
(neport Details, Paracraph 5)
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REPORT DETAILS
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Persons Contacted _
grthern States Power Company
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C. E. Larson, Plant Manager H.11. Clarity, Superintendent, Pl c.nt Engineering and Radiation Protection U. E. Anderson, Superintendt nt, Operation and Maintenance D. D. Antony, Plant Engineer Operations V. A. Shania, Plant Engineer Technical S. L. Pearr.on, Shift Supervisor 11. Seibel, Shi'
Supervi or R. A. Ynitch, 5 ift Supervisor R. R. Rodger, L.
4 Plant Equiprent Operational teactor operator J. M. Carsten, t-d Plant Equiprent Operational Reactor Operator 11. E. Nir.o, Maintenance Supervisor J. P. Heneage, Engineer E. D. Day, Engineer W. J.11111, Engineer, Instrument s H. M. Y.cndall, Plant Office Supervisor F. L. Fey, Arcistant Radiation Prot ection Engineer C.11. lintrwen, Supervising Engineer, Plant Engineering t:nd Construction Depart r.cnt 1.
Records
s The int.pector reviewed the licensec pregran of control, st orage and retrieval of records to detere11ne if the Technical fpecifications requirencnts of section 6.6 were being conplied with.
'Ibe inspector celected and verified that the following records are retrievable.
a.
Reactor coolant flow recorder charts for February 1974.
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Average power range monitor recorder charts for December 1974, b.
Fuel records for 1973, c.
d.
Abnormal Occurrence 74-19 records.
0064, Radiation Monitor Reactor Building c.
Surveillance test, Vent Test for Decenber 1973.
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f.
Maintenance records for r.aintenances perforr.ed on the 250 volt battery a,ystem listed on Page III-3 of Semi Annual Operating
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Report No. 8.
Emergency diesel generator preventive maintenance records since g.
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April 1914.
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Records of reviews made by the Operation Cornittee of changes h.
made te operating procedure B.8.1.13 and surveillance tests 0/05, 0/06 and 0/07.
These chacces were indicated in Section I.D.4 of Seni Annual Operating Report No. 8.
The inspector verified that as built drawings f or changes in plant design, listed in section 1.D.4 and 5 of Seni Annual Operating Report No. 8, vere revised to reficct these changes.
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The licensee has prepared and naintainn equipment hiutory cardn en safety Maintenance and preventative maintenance perforrted on related equipnent.
the equiprent is recorded on the cards. Maintainin'g equipment history cards has been in effect for about r.ix nonths.
Pron those cards long tern equipnent degradation or adverce trends can be deterrained.
Also, the to the licensee is in the process of r.etting up a progran to provide input pdison Electric Institute's plant Ecliability progran. The input to this, progran vill also provide the license with equipnent history and degradation information.
2.
plant Operations a.
Plant Tour _
licenece's The inspector' toured the plant accompanied by the representative. llouscheeping practices vero generally acceptabic.
.During the tour, two equipment,dECURE and two 110LD tags were
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selected and reviewed for proper approval and the status log No reviewed to det~rine if the tags were cecounted for.
dicerepencies s te noted.
The inspector reviewed the status of various annunicators which vere lit in the control reon with a control room operntor.
Adequate explanationsvere given as to why thesc ennunicc. toro vere lit.
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b.
Log Books ihe inspector reviewed the Recetcr and Control Roen tog and Shif t Supervisur's log f or selected days during the period of April 1 to and confirced that entries are filled out and initialed July 15, 1975 and that the Operations Supervis,or is reviewing and initialing the log sheets indicating his review.
The inspector noted in his review of the logs that the entries are nade with good details.
The inspector also reviewed Control Rocc and Meactor Euilding hourly and daily log sheets for July 1 to 15,1975 and no dis-
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crepencies were noted.
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TheJunperBypasslogvanreviewedbacktoMarch15,ig75.
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No discrepancies were noted.
As van previously noted-. / the licensechas initiated the use of Bypass /Junper forms and it
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appears to be a bin inprovenent over his previous method of
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keeping track of bypasses and jumpers.
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The inspector reviewed SOE Reports 75-04 and 75-05 which were c.
prepared and approved by the Operations Commit'tce during April
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to July 1975.
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SOE 75-04 - The event involved oil leakane from two hydraulic suppreer. ors on the HPCI synten ubich vere still operable and hence not an obnormal occurrence.
The licensee described the event in the cover letter f or A0 75-07 dated Tebruary 27, 1975.
and was previously reported.4,7ondensate demineralizer prob
SOE 75-05 - This event vau a
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There were no itens of noncorapliance noted in the rcvicu of these events.
d.
Iemporary Hemo's Tenpurary Meno's are temporary changes to the Operation's Manual.
The subject netwo chich vere in ef f ect at the tino of the increc-tion vere revicued.
Four Orders were in effect and no discrepencies
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' Abnortral Occurrencen n.
AO 763/75-08 The licensee informed the inspector on May 5,1975 by telephone
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that the control circuit for the RCIC turbir.: r.tenn supply valve MO 2078 was determined to be dcenergized due to an open undervoltsp occurrence is as described in licensco's report.g for this relay coil.
The details and the corrective acti
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The licensee representative stated that there has been no f urther f ailurce of the relay coil and that the f ailed coil had b.cen sent to their c3ectrical laboratory in Minneapolis for analysis.
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3/ IE Inspection Rpt. No. 050-263/75-05.
T/ Ibid.
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NSP to DL 5/15/75.
l/ A0 Rpt. No. 050-263/75-08,
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A0 75-09 The licensec inf ormed the inspector on Ny 27, 1975 by telephone that during surveillance testing the core spray injection valve No. 1751 closed but vould not reopen on sirnal from the control The valve was opened by hand and subsequently operated room.
properly during testing.
The details for thic occurrence are described in the licentee's report.5/'
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The intpector inquired if the licenace had determined why the valve did not open.
The licensen's r<presentative stated that they had corpletely checked out the valve and control circuits
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and could find no reason uhy the valve did not open and it has opetated properly r.ince the occurrence.
c.
A0 75-10
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The licensee reported to the inspector on July 3,1975 by telephone that reactor high pressure scrc.n ovi tch PS 2-3-55A was f ound inoperabic due to the bourdon tube httting th stop plate.
The detailt, and corrective cct$on for this u currence are given in the licensee's report.b rhe licent ee's represent ative indicated that the evitch should operate prior to the Lourdon tube striking the otop.
It appeared that two problers were involved in this occurrence.
The r. top van set so close to the bourdon tube that it did not allow for any drift and the adjustnent screw had a busitup collar under the
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head of the ccree rhich allo.ced the adjustint rechanisn to slip over the collar and the tube to hit the stop.
The collar was apparently forr.ed during the et.nufacture and is not present on all adjustment screws.
The licensec's is inspection adjustnent s.crerr, in other switch to det c rr.ine if ritular collars exirt,
d.
A0 75-12 The licencee reported to the inspectot on July 14, 1975 that a small Icak developed in a local reactor pressure guage.
The Icak lowered the cater Icvel in the ref erence leg f or the rernn and LCCS initiating Yaruay instrunents causing then to indicate high water 1cvel and preventing then f rem tripping within the limiting safety cynteu setting.
The redundant Yaruays vere not affected.
The leak was caused by a cracked bourdon tube, 1hc licensee isolated the local guage and returned the reference legs to normal vithout interruption of teattor power. The licensee's report had not been prepared at the time of this inspection.
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I/ A0 Rpt. No. 050-263/75-09, NSP to DL 6/6/75.
6/ A0 Upt. No. 050-263/75-10,1:SP to DL 7/11/75.
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4.
Startup Testing The inspector reviewed testing perforrned during startup following the January-rebruary, 1975 outege.
Tes. ting perf orned and reviewed were as follows.
Cont rol rod drive insertion tirne por s'urveill'a6cc test 0081 was a.
performed on all rods on which naintenance was performed during the outage.
Insertion tines of rods tested met the Technical Specification requircraents, b.
Shutdown margin testing eith the most reactive rod uithdrawn was perforned por curve 111ance ter.t 0073.
This testing verified the reac tor van shutdoun by greater than 1.22% SK vith the nost reactive rod fully eithdrawn and net the requirenents of Technical Specification 3.3. A.1 and 4.4. A.J.
power t o flow maps and core.tP data were obtained, c.
d.
Core power distribution rneasurer.ents vere obtained at 5 3?;, 6 27.,
84% and 96?. power using the traversing in-core power detectors, Heat balances were perf orned at 2 2*., 50*, 5 97., 7 2%, 93% and 1007;.
c.
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Critical rod position in the A cnd B rod sequence configurations
. were obtained and were within 1% of the estimated critical position as tequired by the technical specifications.
5.
Outstanding,and Misec11pneous_lter4.
The follering iter s vere reviewed.
Turbine 1:oist ure Senerator l'o, 3 Inlet Stean Piping a.
it was previously repor ed that the licensee had observed thinning in the subject piping.1
"Ihe inspector inquired ac to that action the licensee uns taking :,n' regard to this item.
The licensee's represent ative stated that a recting van held with General Electric regarding the piping. General Electric requested a section of piping to perforn burst testing on.
The licensee vill cut out a
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six foot sect ion of piping with t hinning during the Sept er.ber
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outage to send to General Electric.
After the burst testing is conpleted and eveluated, General Electric believes they will be j
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in a position to make reconmendations concerning repIncenent of piping.
7/ IE inspection Rpt. No. 050-263/75-05-9-t
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b.
Recirculation pug heakare Annunefators
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During the tour of the plant the inspector noted that one of four subjn t annunciators was lit continuously. A similar situatica was observed previout,1y.8./ The inspector inquired as to the status of corrective action regarding these annunciators.
The licenoec's representative stated that a de' sign change was being processed which vill delete this system of Icakage detection because the pico switches for'the switches are unreliabic.
The licensee vill rely on pump seal pressures and temperaturet.,
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and dryvell sump levels to detect leakage.
Autyented Off Ca9 Syp t en c.
The incpector reviewed the perfernance of the subject systen with the licen:,ee's representative for the past two months.
On May 29, 1975, the Train t reconbiner was shutdwn due to a reconhiner condenser high level. Investigation revealed that catalyst (palladium) pelletn had clogged the condenser Icvel control valve.
Further investipation revealed that the upper catalyut retention screen in the recorhiner had failed.
The vesue) designer inspecto3 the vessel and calculated that the screen had failed as a result of bed fluidization subsequent to a differ-ential pressure (d/p) in excess of the 0.8 paid f or vhich it was designed.
This d/p was attributed to the rapid _cqualization of the partial vacuum created by condensation of entrapped steam in a
shutdoun train rhen the train is returned to service.
Further invectigation revealed that catalyst particles had flushed int o the 42 inch delay line.
The systen vcs nodified and repaired and the licem.c c han changed the operating procedure to require that a shutdown t rain be gradually equalized with the operating train.
Also, because of
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the presence of palladium particles in the 42 inch delay line the licensee is not pernitting operatica of the plcnt without a recombiner train in operation due to the potential hydrogen detonation problen.
Following the repair of the B train, the A reconbiner train was shutdwn and the upper catalyst retention screen inspected.
The catalyst loading door trap had opened, allowing catalyst pellets to go dwnstrean during cysten transiente. The systen van modified and repaired in the sar:e tunner as the D reconbiner train.
Both the units were operabic at the time of the inspection.
8_/ RO Inspection Ept. 050-263/74-10
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Motor Operated Valve Overload Indicatten The Itcensee had previously connited to review nethods to provide nur.orrance of power to the subject valves.2/
The licensee'c representative inforned the incpector that a design change was being prn essed which vill modify the indication circuitry such that if the thernal overload 'ic actuated, the valve indicating lights in the control room vill go out, indicating a prob'em to the operater.
c.
1R Bulletin 75-03, MCO B300 and 8302 Solenoid Yalves
'Ibe inspector rcviewed the licenbee'c response
/ to the subject lO bulletin vith the lic(nsee's representative.
The licennec stated in his response that they had ci;hi alenoid valves of the type described in the bulletin but they have ectal seats and resilent seats vhich is not the type which have problens.
The licensee representative indicated they h. 'e had no failures of the ci;;ht valves they have installed nnd further action is planned for this bulletin.
f.
Off-Gas ptdiat!on Leveln and Ken or Pover level 1'or a previous inspection on May 14-16, 197511/
it wa; reported
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that the licensec had reduced pover irom 100% to 93% due to in-creasing radiation icycle at the ait ejectors apparently due to increased fuel lenkers.
Since that tinc the licensee has gradually
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decrent.ed }a.er to abnut 8 3 t.
to lirit t he radicticn lev ( 2n, lhc licencee ins chinist rat ively set c linit of I? R/hr at the air ejectors.
On July 12, 1975, the licensee reduced power to tbout 45% for a rod pattern exchange.
Uhen power level was increased.
04: rac the t-
-fr.un inver t h: t c ru3 d l e ob t.s ined eithout t ne'
12 R/hr at the air ejector.
1;y July 18, IM5, the licensee had been abic to increase power to 70% and stay below 12 R/hr at the air ejector.
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9/ RO Inspection Ept. No. 050-263/74-10, 10/ Letter, 1;Sp to Region III dtd 4/lb/74.
jl/ IE Inspection Ept. No. 050-263/75-09.
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