IR 05000309/1987005

Insp Rept 50-309/87-05 on 870427-0501.No Violations or Deviations Noted.Major Areas Inspected:Procedure Review & Test Witnessing of Local Leak Rate Testing

ML20214J861
Person / Time
Site:	Maine Yankee
Issue date:	05/15/1987
From:	Anderson C, Joe Golla NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214J849	List: IR 05000309/1987005 ML20214J846
References
50-309-87-05, 50-309-87-5, NUDOCS 8705280220
Download: ML20214J861 (6)

Text

- . - _ . . . . . . . - . -

.

%

]

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

'

Report N ; Docket N License No. DPR-36 Priority -

. Category C

Licensee: Maine Yankee Atomic Power Company 83 Edison Drive

4 Augusta, Maine'04336 i Facility Name: Maine Yankee Atomic Power Station Inspection At: Wiscasset, Maine t

'

Inspection Conducted: April 27 - May 1, 198 !

Inspectors: Of0 [ ) . I 7 Josdph AY dila, Reactor Engineer date Approved by: b f J 17 Clifford J. Anderson, Chief -date Plant Systems Section, EB

Inspection Summary

Inspection April 27-May 1,1987 (Inspection Report No.

50-309/87-05).

Areas Inspected: Routine unannounced inspection of procedure review and test witnessing of local leak rate testin Results: No violations or deviations were identified.

!

8705280220 870518 7

!

PDR ADOCK 05000309 O PDR

,

-_ _

.

.

<

,

.

DETAILS 1.0 Persons Contacted Maine Yankee Atomic Power Company

• E. Boulette, APM MY L..Cummings, Engineering Assistant PED-

• J. Garrity, Plant. Manager .

T. Gifford, Acting Engineering Section Hea C. Giggey, Performance Engineer

. L.~ Lawson, QA Supervisor

'

• R. Lawton, Jr., Manager QA'

-

S. LeClerc, QC Supervisor

• P. Radsky, Chemical Section Head Nuclear Regulatory Commission

• C. Holden, Senior Resident Inspector-

• L. Myers, Radiation Specialist

• Indicates those present at the exit meeting held May 1, 198 .0 Local Leak Rate Testing (LLRT)

2.1 General The purpose of this inspection was to ascertain that local leak rate

' testing is being administered adequately and conducted in compliance with the requirements and commitments referenced in the following sections. The LLRT procedures were reviewed for technical adequacy to perform the intended activity. Other record keeping and LLRT

related documentation was reviewed to determine adequacy of the overall administrative control of the local leak rate test program, i

2.2 References Technical Specifications Section . Oyster Creek Nuclear Generating Station Technical Specifications Section . 10 CFR; Part 50, Appendix J, Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors

. Final Safety Analysis Report (FSAR)

' ANSI /ANS 56.8-1981, Containment Systems Leakage Testing Requirements

>

_ . - _ _ _ - .

.

. 3 2.3 Documents Reviewed Procedure No. 3.17.4, " Class B & C Leakage Testing",

Revision No. 1 . Procedure No. 3.17.4.11," Component Cooling (in) Leak Test -

Type C", Revision No. 1 Procedure No. 3.17.4.30, " Auxiliary Steam Header Leak Test -

Type C", Revision . Procedure No. 3.17.4.38, " Containment Spray Pump Casing Vent -

Vent C", Revision . QA Evaluation Report No. 87E-028 " Electrical Penetration Leak Test - Type B". QC Independent Inspection Checklist for Independent Inspection No.86-024 " Class B, Containment Airlock Test".

2.4 LLRT Procedure Review The inspector reviewed the LLRT procedures to determine their adequacy of content and adherence to accepted testing methodolog The LLRT program is structured such that every mechanical penetration has a specific procedure covering system lineup and leak testin These penetration specific procedures are governed by a more general procedure which covers test methodology and LLRT record keepin The procedures were found to be technically correct to perform local leak rate testing utilizing the mass flow-in and pressure decay method (where deemed appropriate). These methods are acceptable per 10 CFR 50, Appendix J and current industry practice. The inspector verified that the LLRT procedures contained the following pertinent information: Criteria and response for individual and combined LLRT failure, criterion utilized to determine the maximum pathway leakage through a valve / piping network, instrument system error correction, and test precautions and initial condition No unacceptable conditions were identified within the scope of this revie .5 Test Witnessing and Instrumentation The inspector witnessed the performance of test activities to verify that qualified test equipment and tools were used and that the test technicians followed the procedure. The following mass flow-in tests were witnessed:

Penetration No. 46 Auxiliary Steam Header on April 28, 1987 l

"As-Found" Type C Test of Outside Barrier (Valve No. AS-540)

_

.

.

Penetration No. 93 Containment Spray Pump Casing Vent Header on April 28, 1987 "As-Left" Type C Test of Inside Barrier (Valve No. CS-54)

Penetration No. 3 Primary component cooling water system on April 30, 1987 "As-Left" Type C Test of Inside Barrier (Valve No. PCC-245).

The inspector reviewed the system lineups.for the tests witnessed and determined that they were in an effective test configuratio The test technicians followed approved procedures, utilized qualified test equipment, and were competent to perform the test The inspector reviewed calibration records for the Leak Rate Monitor (LRM)-used to conduct the tests described above. The standards used to calibrate the instruments contained within the LRM (Pressure Gage, Temperature Gage, Flow Meier) were certified to be traceable to the

National Bureau of Standards (NBS). Per Procedure'No. 3.17.4 " Class

, B & C Leakage Testing" the flow meters within the LRM are to receive a " functional" calibration check at least once every three weeks during the testing period and upon completion of the Type B & C test program. The inspector noted that the licensee had identified that the functional check for the LRM flowmeters was several days overdu The inspector questioned the licensee about the validity of any LLRT's done with the instrument since the three week period had elapse The licensee stated that the flow meters would receive their functional check before any further tests were performed and that if the flow meters were found to be out of calibration all' tests performed since the last functional calibration check would be repeated. The inspector discussed this situation with licensee management. It was concluded that measures would be taken to ensure that the LRM flowmeters receive their functional calibration checks in a timely manner. Until licensee action to ensure adherence to the proper leak rate monitor functional calibration check frecuency has been verified, this will remain an unresolved item (50-309/87-05-01).

2.6 Administrative Control The inspector reviewed documentation relevant to the overall admin-istrative control of the local leak rate test program. Information which documented the following status / activities was reviewed:

recording of test results, acceptance and failure criteria for individual penetrations and/or valves, failed surveillanc evaluations, test instrument calibration and test record sheet, an test instrument degraded condition report. These documents provide for thorough administrative control of the overall LLRT progra One deficiency was noted and brought to the attention of licensee management by the inspector. The status index for containment penetration surveillance tests " Running Total" was not being

.

_ _ . _ _ _ _ _ . _ . - - _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ _ _ . _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ . . _ . . . _ _ _ . _ _ - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ - . _ - _ _ _ - _ _ _ _ . _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ . _ _ .

-

. ..

.

. 5 maintained. -The licensee stated that the index would be updated and that measures would be taken to ensure proper administrative control in this area. The inspector had no further question ;

The inspector verified, through an audit of LLRT results records, that LLRTs were conducted at required intervals since the last containment Integrated Leak Rate Test.

+

2.7 Reverse Direction Testing e

10 CFR 50, Appendix J, Section III.C.1 states in part: " Type C tests shall be performed by local pressurization. The pressure shall be applied in the same direction as that when the valve would be required to perform its safety function, unless it can be determined that the results from the tests for a pressure applied in

'

a different direction will provide equivalent or more conservative results." The inspector questioned the licensee about the status of reverse direction testing at Maine Yankee. The licensee stated

'

that in several cases local leak rate testing of containment isola-tion valves is performed in reverse direction. Of these cases, three have in the past been tested in the reverse direction without technical justification.~ These are: The RCS Primary Vent System Valve No. PV-8 (Penetration No. 42), and Post Accident Purge System Valve Nos. PAP-1 and PAP-49 (Penetration No. 84). The licensee further stated that hardware modifications were being made to the above systems this outage to permit testing in the proper direction. The inspector reviewed modification drawings on the affected penetrations. The inspector verified'that the proposed modifications would permit an effective test configuration with pressure applied in the proper direction. The licensee stated that the modifications would be completed this outage before LLRT is performed on the subject valves. The inspector had no further question .0 Personnel Training and Qualifications

'

The Qualification and training of selected test personnel were discussed with a licensee representative. In addition.the inspector evaluated the performance of test technicians during the test witnessin The inspector determined that the test technicians qualifications met the requirements specified in ANSI N 18.1-1971 " Selection and training of nuclear power plant personnel". They were knowledgeable of their respon-sibilities and technical aspects of leak testin No unacceptable conditions were identified.

,

, . _ - --- .- _ . .,_ _ .m . . _ . . -_, ,

.

.

.

4.0 QA/QC The inspector discussed coverage of local leak rate testing with QA representatives and reviewed QA surveillance reports. It was determined that QA provides coverage of a small sample of LLRT's and that QA findings and evaluations are well documented. However, it was determined that QA does not evaluate overall LLRT program adequacy. The inspector i

.

discussed with the licensee the safety significance of the containment isolation boundary and the need for increased QA attention to the overall effectiveness of the LLRT program. The licensee agreed with the inspectors observation and committed to increase QA/QC involvement in the

overall local Leak Rate Test Program. The inspector bed no further question .0 Exit Meeting Licensee management was informed of the purpose and scope of the 1 inspection at the entrance interview. The findings of the inspection I were periodically discussed and were summarized at the exit meeting on May 1, 1987.

]

J Attendees at the exit meeting are listed in section 1.0 of this repor At no time during the inspection was written material provided to the j licensee by the inspectors.

I

,

, -- - . . - , -. .,