IR 05000311/1978053

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IE Insp Rept 50-311/78-53 on 781226-29.No Noncompliance Noted.Major Areas Inspected:Containment Integrated Leak Rate Test & Licensee Action on Previous Insp Findings
ML18078A956
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/17/1979
From: Caphton D, Graham P, Tanya Smith
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18078A955 List:
References
50-311-78-53, NUDOCS 7903090325
Download: ML18078A956 (6)


Text

u.s~ NUCLEAR REGULATORY COMMISSlON OFFICE OF INSPECTION AND ENFORCEMENT Region I P-~ - - **--

NOTICE port N /78-53 Ji _I C3TA:.. J :1J Docket N ~5....,,0._-....... 3........ 11..._ __ _

' *-**.... -..-;~..:. 11*~,*\\.:CORDANC:= ~,1fri 1:..,, r(.::.;90 License No. CPPR-53 Priority -------

Category Bl

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Licensee:

Public Service Electric.and Gas Company

Park Place Newark. New Jersev 0701 Facility Name:

Salem Nuclear Generatina Station, Unit 2 Ir.spection at: Hancocks Bridge, New Jersey Inspection conducted: December 26-29, 1978 Inspec-:ors:

Approved by:

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T. H. Smith, Reactor Inspector fJ&.xLL P. D. Graham, Reacttir Jnspector h/12~/-- _G

&: L. Ca~~clear Support Section l, RO&NS Branch Inspection Summary:

Inspection on December 26-29, 1978 (Report No. 50-311/78-45)

date signed

~/;7/79

.

dat~ signed date signed 1 /;7/79

'da tG i gned Areas Inspected:

Routine, unannounced inspection by regional based inspectors of the Containment _Integrated Leak Rate Test and licensee action on previous inspection finding The inspection involved 39 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> on site by two NRC regional based inspector Results:

No items of noncompliance or deviations were identifie "1o?,<>'f't:>J2. 5

~aian I Form 12 (R~v. April 77)

  • DETAILS Persons Contacted Public Service Electric and Gas Company K. Kieper, Materials Test Engineer
  • H. Lowe, QA Engineer J. McAdams, Materials Test Engineer
  • E. Meyer, Project QA Engineer F. Twogood, Lead Shift Test Engineer United Engineers and Constructors M. Juister, Mechanical Test Engineer S. Page, Lead Test Engineer
  • D. Snyder, Project Manager
  • E. Walsh, Assistant Field Superintendent, QC
  • denotes those present at the exit intervie The inspe_ctor also talked with and interviewed several other members of the engineering and technical staff.

Licensee Action on Previous*Inspection Findings (Closed) Unresolved Item (311/78-29-01):

The licensee has estab-1 ished a system which will ensure that Type C retests are perfonned after maintenance on containment isolation valve (Closed) Unresolved Items (311/78-29-03 and 311/78-29-08):

Due to the nature of their operation and system location, it has been determined that valves SJ49, RH26, RHl, 21SJ44 and 22SJ44 do not require Type C testing. These items are considered resolve (Closed) Unresolved Item (311/78-29-07):

Written documentation from the vendor has b~en received and reviewe The vendor has confirmed earlier discussions of the readability and calibration accuracy of Leak Rate Monitors which have no low range scale (0-20 SCCM).

This item is resolved.

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(Closed) Unresolved Item (311/78-45-01): The procedure was revised to require the CILRT be run for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Leak rate calculations will be made using uncorrected raw dat An instrument error analysis will be performed with the results being added to the Leak rate calculation prior to comparison with the acceptance criteri.

The procedure was corrected to require that dewcels be operable throughout the tes.

Sump level. and RCS level changes were monitored before and after the test. Corrections to the leak rate will be made if require.

Errors in valve lineups were correcte.

The correct acceptance criteria was added to the procedur.

Proper venting and draining of required systems was accomp-1 ished during the test. *

(Closed) Inspection Follow Item (311/78-45-02):

No data rejection criteria was in the test procedure, however, during the test no data was rejecte Containment Integrated Leak Rate Test (CILRT) General On December 26-29, 1978, the Salem Nuclear Generating Station Unit 2 performed its preoperational CILRT at a pressure of Pa (47 PSIG).

The test was performed in accordance with proce-*

dure DTP 30-LRT-3, Revision 0, "Reactor Containment Type A Integrated Leakage Rate Test 11 dated December 12, 197 The inspectors reviewed the test procedure, witnessed various portions of the test, and independently verified many of the test calculations. Details of the test are discussed belo The inspector had no further questions or corrments other than those which follow.

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  • Chronology 12/26 12/27 12/28 12/29 Plant Tour 1300

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I

Containment structural inspection and closeou Commenced containment pressurizatio Containment pressurization secured at approximately 47.5 PSI Commenced stabilization perio Stabilization satisfactor Commenced CILR Initial data sets indicate leak rate within acceptance criteri Completed CILRT with 1 ea k rate at the 95;&

upper confidence level of approximately 0.029%/day which is below the acceptance criteria of 0.75 La or 0.075%/day.

Attempted verification test using pump back metho Attempt was unsuccessful due to error in reading pump back gas mete Second attempt at pump back unsuccessfu Gas meter faile Corrmenced verification by superimposed leak metho Completed successful verification tes The inspectors accompanied licensee personnP-1 on an inspection of the containment prior to the CILR Structural and other conditions inside the containment were satisfactor At the

completion of the tour the inspectors witnessed the Type B test on the 130 1 personnel airlock door Several attempts to complete the Type B test failed. - Repairs were made to the inner door seal and a successful test was conducte Instrumentation The inspector reviewed the calibration information for the test resistance temperature detectors (RTD 1s), dewcels, pressure*

instruments and the verification test flowmeter to verify traceability to nationally recognized standards and to deter-mine calibration error All instrumentation was suitably traceabl Computer Program During the CILRT, the inspector performed independent leak rate calculations using raw data~ The inspector noted that the licensee's computer program was calculating the contain-ment leak rate incorrectl The computer program was immediately corrected by licensee representative CILRT Results On December 29, 1978, the CILRT was successfully complete The inspector's calculated results are summarized belo Item Acceptance Criteria Results (1)

CILRT Leak Rate by Mass Point Technique 0.0257%/day (2)

Upper 95% Confidence 0.075%/day 0.0294%/day Level of Leak Rate (Mass Point)

(3)

Supplemental Verification Test Difference 25% La 19.7%La

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  • 6 Exit Interview At the inspection's end the inspectors held a meeting (see Detail 1 for Attendees) to discuss the inspection scope and finding No items of noncompliance were identified and there were no un-resolved items.