IR 05000219/1974011

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RO Insp Rept 50-219/74-11 on 740609-10.No Violations Noted. Major Areas Inspected:Ipclrt
ML20107D128
Person / Time
Site: Oyster Creek
Issue date: 07/02/1974
From: Mccabe E, Rebelowski T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18039A986 List: ... further results
References
FOIA-95-258 50-219-74-11, NUDOCS 9604180138
Download: ML20107D128 (8)


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U.S. AT0!!IC ENERGY C0d&!ISSION

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.; 'f1 DIRECTORATE OF REGULATORY OPERATIONS

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REGION I

RO Inspection Report No:

50-219/74-11 50-219 Docket No:

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Licensee:

Jersey Centfal Power and Liglit Company DPR-16 Madison Avenue and Punch Bowl Road p

Morristown, New Jersey 07960 C

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Category:

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Locat' ion:

Oyster Creek, Forked River, New Jersey

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Type of Licensee:

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Ann unced Typ. of Inspection:

June 9-10, 1974 -

Dates of Inspection:

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Dates of Previous Inspection:

R porting Inspector f[//7/

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f T. Rebel [ ski,ReactorIpspector Date Accompanying Inspectors:

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k Other Accompanying Personnel:

Q Date EcViewed By:

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E. C. McCabO, Senior Reactor Inspector Date Nuclear Support Section Reactor Operations Branch

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9604180138 960213 PDR FOIA DEKOK95-258 PDR

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' SUMMARY OF FINDINGS

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l'pj Enforcement Action None Licensee Action on Previously Identified Enforcement Items Not Inspected Design Changes None

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Unusual Occurrences None Other Significant Findings A.

' Current 1.

The Integrated Primary Containment Leak Rate Test.as conducted by the licensee indicated a satisfactory. leakage rate of 0.301 NU4 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (criteria 0.627) at a pressure of 20 paig (P ).

(Detail 3b)

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The inspector's review of IPCLRT prerequisites found licensee actions adequate.

(Detail 3d)

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The problems encounted by the licensee during testing included

. partial loss of instrumentation, high drywell alarms and valve abnormalities.

(Detail 3c)

B.

Status of Previously Reported Unresolved Items 1.

The licensee's containment temperature stabilization criterion has been defined.

(Detail 3dl)

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The licensee has reviewed containment air mass inventory.

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(Detail 3d2)

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The licensee's Quality Assurance staff monitored the conduct of IPCLRT. -(Detail 3d3)

4.

The licensee's method of access control did not limit all work in secondary containment areas.

(Detail 3d4)

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Management Interview

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i 4-A management interview was conducted at the site at the conclusion of

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the inspection on June 10, 1974, with Mr. J. Carroll, Plant Superin-

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tendent and Nk. K. O. E. Fickeissen, Jr., Technical Supervisor.

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The following summarizes the items discussed:

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A.

Integrated Primary Containment Leak Rate Test E

The inspector stated that the purpose of the inspection was to witness the conduct of portions of the Integrated Primary Con-

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1.

The inspector stated that the licensee's prerequisites to

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IPCLRT were satisfactory accomplished.

(Detail 3d)-

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The inspector stated that preliminary data appeared to-in-dicate that IPCLRT would meet acceptance criteria.

(Detail

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3b)

3.

The inspector discussed with licensee instrumentation failure, I

drywell sump alarms and valve abnormalities.

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EdM The licensee's representative stated that a retest of valves

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i in areas where extension of test boundaries were made, the leakage values would be added to final summary report leakage

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calculations.

(Detail 3c)

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Resolution of the following unresolved items was accomplished.

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DETAILS

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Persons Contacted

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Mr. J. Behm, Quality Assurance.

, Mr. lR. Bright, Associate Engineer -

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Mr.1 H.c Ca11ahan, Control Room Operator Mr.. J. Carroll,' Station Superintendent

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Mr.-B.1 Cooper,. Shift Foreman

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Mr. K.. Pickeissen, Jr., Technica1' Supervisor -

Mr. E. Growney, Technical Engineerf

Mr. D. Reeves, Jr., Chief Engineer l

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Mr. E. Rosenfeld, Associate Engineer

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2.

General-The inspector was notified by the licensee on. June 9,1974, that

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preparations for the Integrated Primary Containment Leak Rate

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Test (IPCLRT) were complete.

32 Integrated Primary Containment Leak _ Rate Test (IPCLRT)

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The licensee's periodic Integrated Primary Containment Leak Rate j

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Test was performed during June ' 9-13,1974.

The inspector was WFM -

on site ;during initial pressurization, temperature stabilization and a. portion of the leakage test.

Included in this report is additional data transmitted to the inspector by 'the licensee upon completion of the IPCLRT.

a.

Prerequisites.

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(1) Examination of Containment Structural Integrity j

The licensee performed an inspection of containment to determine the -extent (if any) of the structural deterio-ration of containment since the previous integrated. leak rate t'est (June, 1972). The following areas were examined.

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(a) Bolting of bolting flanges.

(b)

Cable penetrations.

l (c)- Pipe expansion joints.-

(d)' Evidence of leakage from torus.

-(e)' Torus' support members..

(f)

Liner plates bulging.

.(g) Liner-plate cracks.

l (h). Structural beam deformation.

j-(i) Pitting,' corrosion or rusting.

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-4-No deterioration was noted by the licensee.

Minor rusting was noted on a number of penetration welds.

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(2)

Instrumentation Calibration The inspector reviewed the licensee's documentation of containment leak rate instrumentation calibration for the following.

(a) Ten resistance temperature probes.

(b) Six deweells.

(c) Pneumatic piston pressure gauge.

(d) Absolute manometer.

(e)

U-tube water manometer.

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(f)

Air flow meter.

(8 to 100 cfm)

The instruments were calibrated with traceability to the National Bureau of Standards, and within frequency criteria established by the licensee.

b.

Sequence of IPCLRT Events 6/9/74 - 0800 Final Preparations in progress.

1500 Airlock Leak Rate in progress.

1625 Pressurization of containment started.

pyy 1705 Pressurization stopped - Torus pressure gauge not functioning - Replaced.

1715 Pressurization of containment continued.

6/10/74 -0055 Drywell pressure at 21.00 psig.

0400 Temperature Stabilization period started.

0600 Temperature Stabilized at %860F.

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1400 Power Supply to Dewcells inadvertently dis-connected.

Data accumulation restarted.

(Preliminary IPCLRT.,541% wt/ day).

6/11/74 Test in progress.

6/12/74 -0700 Integrated Leak Rate Test terminated.

Sensitivity leakage verification test temperature stabilization period started.

6/13/74 -1200 Final set of data reading on system sensitivity check taken.

6/13/74 -1310 Commenced depressurization of containment.

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-5-The calculated containment integrated leak rate of 0.301 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (88.5 scfh) was determined.

The criteria

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of 0.627 weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was not exceeded.

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c.

Problems During Containment Testing (1)

Dewcell Failure The licensee experienced the failure of one of six in-stalled dewcells. Number 3 dewcell temperature indica-tor, located in the drywell below the reactor vessel, failed.

The criterion of two thirds of the installed instrumentation being operable was not violated.

The volume fraction value associated with this dewcell~was distributed between the functioning dewcells.

This revision was entered into the licensee computer program.

The inspector hau no further questions (o this item.

(2)

Drywell Sump Alarm During the initial pressurization of the containment volume a high level drywell sump alarm was experienced.

A change to the Integrated Primary Containment Leak Rate Test procedure was written to allow pump down of the W%h drywell sump during the test.

The licensee established that a leak rate of one half gal / min from all sources was contributing to the level increases in the sump.

The water levels of the reactor vessel and torus were monitored and an equilibrium volume of water was main-tained in containment to compensate for the drainage.

(3)

Valve Abnormalities i

(a) During a survey of secondary containment the licensee noted air leakage from an improperly secured manual isolation valve on piping supplying the high pressure trip and alarm functions.

The manual valve was found unseated and was rescated properly.

(b) The main steam line drain valves V-1-106 and V-1-107 were found to be leaking.

The boundaries were

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extended and the licensee stated that this exception will be noted in the final summary report.

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d.

Previously Reported Unresolved Items on CILRT

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(1) Temperature Stabilization s

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The temperature stabilization criteria established by the licensee calls for a rate of change of average temperature J

of less than 1.0 F/Hr averaged over the last two hours.*

I A table of actual readouts is listed below:

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Date Time Avg. Temp Rate of Change 6/10 0400 86.75 6/10-0500 86.30-0.550/hr.

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86.00-0.300/hr.

'T 6/10 0700 86.05

+0.050/hr.

6/10 0800 86.20

+0.15 /hr.

Temperature stabilization was established at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on 6/10/74.

This item resolves the items documented in Report 50-219/74-09, details 2d and Report 50-219/74-10, details

3c.

(2)

Containment Air Mass Inventory The licensee had revised the IPCLRT procedure to include blanking and venting of systems. _One area of concern lLn the supply air to containment pressurization was resolved.

(R0 Report 50-219/74-09, Detail 2e)

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(3) Quality Assurance Audits

aj The licensee maintained a quality assurance surveillance

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3/4 of procedural items during the conduct of test. This d'

resolves the item documented in R0 Report 50-219/74-09, Detail 3j.

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(4) Access Control The licensce's review of administrative restrictions to

entry to secondary containment concluded that no further restrictions to limit access to secondary buildings were required during the conduct of IPCLRT.

During the in-spector's time on site, the licensee experienced an in-advertent loss of power.to monitoring instruments due to removal of power source through personnel error.

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  • . Note: The temperature stabilization criterion was verified-acceptable by

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. telephone conversation with RO:HQ (Seyfrit/Brunner, 6/26/74).

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test data points were restarted and test time loss of

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approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> was incurred. The inspector had

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no further comments in this area.. This resolves the

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.W item documented in RO Report 50-219/74-09, Detail 2f.

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