ML20137Q947

Insp Rept 50-354/85-65 on 851223-860103.Violation Noted: Closure of Containment Isolation Valve by Other than Normal Operation

ML20137Q947
Person / Time
Site:	Hope Creek
Issue date:	01/29/1986
From:	Joe Golla, Jerrica Johnson, Kucharski S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20137Q938	List: ML20137Q934 ML20137Q941 ML20137Q947
References
50-354-85-65, NUDOCS 8602070136
Download: ML20137Q947 (7)

See also: IR 05000354/1985065

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No.

50-354/85-65

Docket No.

50-354

License No.

CPPR-120

Licensee:

Public Service Electric & Gas Company

80 Park Plaza - 71C

Newark, New Jersey

07T61

Facility Name:

Hope Creek Generating Station

Inspection At: Hancocks Bridge, New Jersey

Inspection Conducted: December 23, 1935 to January _3,

1986

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Inspectors:

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S. Kucharski, Reactor Engineer

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J. Golla, Reacto/ Engineer

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J .h~ Johnson ,

Approved by:

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Operational Programs Section, 08, DRS

Inspection Summary:

Inspection on December 23, 1985 to January 3, 1986 (Report No. 50-354/85-65)

Areas Inspected:

Routine announced inspection including:

Integrated l eak Rate Test (ILRT) procedure review, ILRT witnessing and results

evaluation, QA/QC involvement, and tours of the facility.

The inspection

involved 115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> onsite by two region-based inspectors.

Results: One violation was identified (closure of a containment isolation

valve by other than normal operation, paragraph 2.5).

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DETAILS

1.0 Persons Contacted

1.1 Public Service Electric & Gas Company (PSE&G)

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• A. Barnabei,

Principal QAE

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• W. Brammeier, QA Engineer

• R. Brandt,

Inspection Services Engineer

• J. Carter,

Startup Manager

• C. Churchman, Site Engineering Manager

• R. Donges,

Lead QAE

• G. Druffner,

Test Engineer

• G. Duncan,

Senior ISI Supervisor

• R. Gri f fith,

Principal QAE

B. Hicks,

Test Engineer

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• R. Johnson,

Site Engineer

• A.

Kao,

Principal Engineer

• S. LaBruna,

Assistant General Manager - HC0

• L. Lake,

ISI Engineer

• P. Landrieu,

Project Manager

• J. Lawrence,

Licensing Engineer

E. Maloney,

ISI Engineer

• M. Metcalf,

Principal QAE

• S. Riggle,

QA Engineer

• R. Salvesen,

General Manager - HC0

• S. Saundra,

Senior Operations Supervisor

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1.2 Bechtel Construction

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K. Wareham,

Engineer

1.3 Stone & Webster Engineering Corporation

H. Thickman,

Test Engineer

1.4 USNRC

• R. Borchardt,

Senior Resident Inspector

• Denotes those present at exit meeting on January 3,1986.

2.0 Containment Integrated Leak Rate Test

2.1 Documents Reviewed

PTP-GP-1,Rev.O, November 8,1985h~"PrimaryContainmentInte-

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grated Leak Rate Test (CILRT)"

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piping and instrumentation diagrams relevant to ILRT valve

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lineup

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calibration records for: 3 pressure gauges, 6 dewpoint hygro-

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meters,17 resistance temperature detectors, and 1 air flow

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meter

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containment volume fraction calculation

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ILRT related Technical Specifications

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instrumentation selection guide

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ILRT log of events

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QA/QC log

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ILRT data center log

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P-1000-1-GP-09, Rev. 0, December 10, 1985, Bechtel work plan /

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procedure record, " Leak Testing of Piping Systems, Test Proce-

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dure and Report"

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2.2 Scope of Review

The inspectors reviewed the above documents to ascertain compliance

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with the regulatory requirements of 10 CFR 50, Appendix J; Hope Creek

draft Technical Specifications; applicable industry standards and

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station administrative guidelines.

The inspectors witnessed activi-

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ties related to the ILRT and subsequent ILRT verification test. Also

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witnessed were structural integrity test (SIT) completion and drywell

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to torus bypass test.

The inspectors performed an independent calcu-

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lation of ILRT leak rate using PSE&G test data.

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2.3 Procedure Review

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The inspectors reviewed the ILRT procedure PTP-GP-1 for technical

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adequacy and consistency with regulatory requirements.

Review of

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the procedure's acceptance criteria, test methods and references

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indicate adequate conformance with 10 CFR 50, Appendix J.

The

inspectors reviewed the procedural valve line-ups for containment

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piping penetrations.

This review was performed to ensure that

systems were properly vented and drained to expose the containment

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isolation valves to test pressure with no artificial boundaries.

No unacceptable conditions were identified.

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2.4

ILRT Instrumentation Calibration

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Prior to performance of the test the inspectors reviewed the cali-

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bration records for the resistance temperature detectors (RTD's), dew

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point instruments, precision pressure gauges, and the verification

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test flow meter.

This review determined that Precision Pressure

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Gauge No. 2686 was not within the required 6 month calibration fre-

quency for ILRT instrumentation. Also, no records on the calibration

of the ILRT verification test flow meter were available.

The in-

spectors informed the licensee of these deficiencies which were then

promptly corrected before performance of the test.

The precision

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pressure gauge was recalibrated by PSE&G Nuclear Service Personnel

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and another air flow meter with current calibration was ootained.

The rest of the ILRT instrumentation was found to meet calibration

accuracy and frequency requirements.

Calibration standards used were

traceable to the National Bureau of Standards.

2.5 Test Performance & Control

The SIT, and drywell-to-torus bypass tests were performed within the

guidelines of the procedure. SIT completion involved pumping the

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containment to specific pressures to permit visual (soap bubble)

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examinations required to complete the primary containment ASME Code

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Section III acceptance pressure testing.

The purpose of the

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drywell-to-torus bypass test was to verify that the leakage from the

drywell to the suppression chamber which bypasses the downcomer vents

is within the acceptance criteria.

The ILRT of the containment is designed to test its leak tight

integrity. A problem with this test arose when a post test inspec-

tion by QA personnel of CIV's inside containment revealed a CIV with

it's clutch lever down.

This indicated that the clutch was engaged

and that the valve, instrument air valve No. KL-001 (HV-5148), was

closed by it's handwheel. Normal operation for this valve is accom-

plished by its motor operator.

Hand tightening of valves which are

normally motor operated may result in a tighter closure which can in-

hibit leakage through the valve and may cause a test result which

does not reflect the actual leak tight integrity of the containment

under accident conditions.

Although licensee QA personnel identified this problem it is consider-

ed a repetitive type of event; QA personnel had identified similar

findings prior to the initiation of the ILRT for which the appropriate

operations and test personnel had been made aware of and reportedly

corrected.

Therefore, it appears that additional corrective actions

are warranted in the area of procedural control of valve operations.

Closure of a CIV for an ILRT by other than normal means is a violation

of 10 CFR 50, Appendix J, Section III.A.I.(b) (50-354/85-65-01).

2.6 Test Chronology

See Attachment 1 to this report.

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2.7 Test Results Reviewed

2.7.1

ILRT

The licensee evaluated the test results for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period

0421 December 31, 1985 to 0435 January 1, 1986.

The calculated

leakage rate at the upper confidence limit (UCL) was 0.181 WT.

%/ day. This was done using the mass point method.

The test

acceptance criteria based on 0.75 La is 0.375 WT %/ day.

The inspectors performed an independent calculation of the test

results using test data to compare with the licensee's leak rate

calculation. A comparison of licensee to NRC results is given

below. The units are WT %/ day, allowable is 0.375.

Licensee

Mass point method - 0.176, Calculated UCL - 0.181

ERC

Mass point method - 0.175, Calculated UCL - 0.179

The above values are subject to add-on local leakages from

valves that will be reworked after the ILRT.

Also, the total local leakage from instrument Air Valve No.

KL-001 (HV-5148) is planned to be added to the ILRT result as

previously detailed in paragraph 2.5.

This is the CIV which was

found to be manually closed.

This add on leakage will compen-

sate for any difference in leakagc through the valve which may

have occurred due to it being hand tightened instead of being

closed by its motor operator.

2.7.2

ILRT Verification Test

The ILRT was followed by a successful superimposed leak veri-

fication test.

The licensee imposed a leak of 0.470 WT %/ day on

the existing overall containment leakage.

This number repre-

sents approximately 1.0 La.

The test results were within the

acceptance criteria band.

The inspectors also verified these results by independert calcu-

lations. A comparison is given below. Again, units are con-

tainment air WT t/ day.

Licensee

Mass Point Band -

0.520 s 0.571 s 0.770

NRC - Mass Point Band - 0.520 s 0.591 s 0.770

These preliminary results indicate a successful ILRT.

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2.7.3

Drywell-To-Torus Bypass Test

The bypass leakage rate satisfied the acceptance criteria of a

drywell-to-torus differential pressure change of less than 0.25

inches of water per minute for 10 minutes.

2.7.4

SIT Completion

This test was performed by the licensee in conjunction with con-

tractor personnel (Becthel Construction) and was fully successful.

All weld joints within the test boundary were examined for leak

tightness and found to be acceptable.

No unacceptable conditions were noted.

3.0 Facility Tours

The inspectors conducted inspection tours independently both before and

during ILRT.

Examined during these tours were containment system bound-

aries, component tagging, and instrumentation to support the ILRT. During

these tours the inspectors observed licensee personnel checking for

evidence of leakage and inspecting containment boundaries.

No unacceptable conditions were noted.

4.0 Independent Calculations

The inspectors performed independent calculations of the containment

leakage and subsequent ILRT verification test. Details are included in

Section 2.7 of this report.

5.0 QA/QC Involvement

The inspectors observed QA/QC personnel monitoring the activities con-

cerning the SIT, ILRT, ILRT Verification Test, and Drywell-to-torus bypass

test. QA/QC personnel performed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surveillance of these activities

and were knowledgeable of test sequences and their responsibilities.

No unacceptable conditions were noted.

6.0 Exit Meeting

A meeting was held on January 3, 1986 with PSE&G/ Hope Creek management to

discuss the scope and findings of the ir spection as dalineated in this

report. At no time during this inspection was written information pro-

vided to the licensee.

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Attachment 1 to Report 50-354/85-65

Test Chronology

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DATE

TIME

ACTIVITY

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12/27/85

1315

Commenced final drywell walkdown

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12/23/85

0555

Commenced pressurizing w/ incremental hold

points for SIT completion

12/29/85

0045

SIT completed and results acceptable

12/30/85

2330

Commenced pressurizing for ILRT

2355

Commenced 4 hr. stabilization period

12/31/85

0421

Commenced ILRT

01/01/86

0435

Ccmpleted ILRT, realigning computer program

for the ILRT verification.

0800

Commenced verification test

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1200

Completed verification test

1245

Reviewed verification test data and found

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satisf actory results.

1335

Commenced depressurization

2310

Completed post test inspection of torus

exterior shell & supports. No deficient

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conditions noted.

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01/02/86

0114

Completed torus interior structural

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inspection.

No deficient conditions noted.

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0205

Commenced inspection of 17 motor operator

CIV's in drywell.

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0310

Inspection of 17 CIV's completed. One

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valve KL-001, HV-5148 was found to have

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manual operator clutch engaged.

0350

Commenced post ILRT drywell inspection

0607

Completed post ILRT drywell inspection.

No

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structural or equipment deficiencies noted.

2343

Commenced drywell-to-torus bypass test

stabilization.

01/03/86

0050

Commenced bypass test

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0112

Completed bypass test

0210

Orywell depressurized.

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