IR 05000412/1986026

Insp Rept 50-412/86-26 on 860908-12.No Violations Identified.Major Areas Inspected:Preservice Insp (PSI) Program & Review of PSI Data

ML20215H081
Person / Time
Site:	Beaver Valley
Issue date:	10/03/1986
From:	Mcbrearty R, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215H076	List: IR 05000412/1986026 ML20215H075
References
50-412-86-26, NUDOCS 8610210438
Download: ML20215H081 (5)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-26 Docket N License N CPPR-105 Category B Licensee: Duquesne Light Company

'P.O. Box 4 Shippingport, Pennsylvania- 15077 Facility Name: Beaver Valley Power Station, Unit 2 Inspection At: Shippingport, Pennsylvania

. Inspection Conducted: September 8 - 12, 1986 Inspectors- / ^#

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R. A. McBrearty,' Reactor Engineer - date Approved by: b MNd 6 J. T. Wiggins( Chief, Materials and date

& Processes Section, EB, DRS Inspection Summary: Inspection on September 8-12, 1986(Report No.50-412/86-26)

Areas Inspected: Routine, unannounced inspection by.one regional based inspector of the PSI program and review of PSI dat Results: No violations were identifie '

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DETAILS Persons Contacted Duquesne Light Company R. Coupland, Director - QC

• J. Godleski, Senior Test Engineer

• T. Heimel, NDE Specialist

• A. Mosso, NDE Coordinator

• R. Perry, Supervisor - NDE Services

• L. Rabenau, Compliance Engineer D. Rakas, Data Controller R. Reba, Construction Engineering

• C. Schulte, RRC Chairman

• Sikorski, Director - Inservice Inspection U.S. Nuclear Regulatory Commission

• J. Beall, Senior Resident Inspector

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• Denotes those present at the exit meetin . Preservice Inspection (PSI) Program The inspector reviewed the PSI program with respect to compliance with 10 CFR 50.55a, and the adequacy of the admir istrative controls contained therein. The applicable edition and addenda of ASME Section XI is man-dated by 10 CFR 50.55a based on the date of issuance of the construction permit. At Beaver Valley Unit 2, the effective code is the 1971 Edition through Winter 1972 Addenda. So that PSI will more closely relate to inservice inspection, the licensee has elected to comply with the 1980 Edition of Section XI through Winter 1980 Addenda. The licensee is not

, required to obtain NRC approval to use a code edition which is referenced by 10 CFR 50.55a, and which is later than the mandated edition. The selection of Class 2 piping for PSI was based on guidance provided by Subarticle IWC-1200, Table IWC-2500-1, Categories C-F-1 and C-F-2 of the 1983 Addenda. Boundaries of Code Class 1, 2 and 3 systems subject to inspection per Section XI are defined in accordance with the Unit 2 FSA Additionally the PSI program defines the requirements for NDE personnel qualification / certification and for the fabrication of NDE calibration standard No violations were identifie . . -

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3 s 3. PSI Data Review t &

The inspector selected data for revie'w to ascertain compliance with applicable ASME Code and regulatory requirements, and with' licensee commitments. Additionally the review was done to ascertain that the examinations were performed by properly qualified personnel, and that flaw indications were evaluated by individuals qualified to perform that function. Data representing the following welds were includedsin the inspector's review:

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Ultrasonic Examination  ;

2 RHS-006-F02, 12" dia. pipe to pipe weld '

2 RHS-006 F03, 12" dia. elbow to pipe weld

2 RHS-006-F04,'12" dia, elbow to pipe weld 2 SIS-018-1A-B, 6" dia, pipe .to reducer weld

2 SIS-018-F01, 6" dia, pipe to elbow weld

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2 SIS-018-28, 6" dia, pipe to elbow weld 2 SIS-018-2D, 6" dia'. pipe to elbow weld

2 SIS-098-F04, 4" dia pipe to elbow weld

2 SIS-066-F01, 12" dia. pipe to valve weld 2 SIS-069-1B,.12" dia. pipe to elbow weld

2 SIS-069-1A, 12" dia. pipe to elbow weld

2 SIS-069-F01, 12" dia, pipe to valve weld

2 SIS-069-F02, 12" dia. pipe to valve weld Magnetic Particle Examination

2 MSS-107-1B, 36" dia, pioe to cap weld 2 MSS-107-F500, 36" dia, pipe to cap weld Liquid Penetrant Examination 2 RCS-080-5A, 4" dia, elbow to pipe weld

2 RCS-080-58, 4" dia. pipe to elbow weld

2 RCS-080-5C, 4" dia. elbow to pioe weld

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2 RCS-080-6A, 4" dia. pipe to tee weld 2 RCS-080-8A, 4" dia. pipe to elbow weld The inspector found that the examinations were performed in accordance with applicable NCE implementing procedures, and complied with Code and regulatory requirements. Examination results were documented, evaluated and properly dispositioned with one exception. Report number LP 101-132, dated 1/25/86, of the liquid penetrant examination of 4" diameter reactor coolant system weld number 2 RCS-080-8A, which was reviewed by the ANII and by the NES Level III, noted that 6 indications were detected.out of the area of interest in base material adjacent to the wel Five of the indications were listed as being linear, and the sixth was noted as a rounded indication. The inspector found that the length of each of the linear indications exceeded the acceptance limits defined by ASME Section XI, 1980 Edition through Winter 1980 Addenda, but no evaluation or dis-position was provided. The inspector advised the licensee representative regarding th: NRC position on the need for the evaluation and disposition of indications regardless of their location and method of detectio While the inspector was at the site the weld and adjacent base material was subjected to re-examination by the liquid penetrant method. The results showed that one of the original five linear indications was non-relevant, and a second could not be detected. The remaining three in-dications exceeded the Section XI acceptance standards as delineated in Table IWB-3514-3. The re-examination results are documented by liquid penetrant report LP-101-603 dated 9/10/86 and are being evaluated by the licensee. Disposition will be based on the licensee's evaluatio The inspector's review of remaining data involving recorded indications identified no other instances where recordable indications were not eval-uated. Further, the inspector found no evidence of similar instances which were identified during previous NRC inspections. Based on this the item appears to be an isolated case, and therefore, is considered un-resolved pending licensee disposition of the indications, and subsequent NRC review of the licensee's action (412/86-26-01).

The data were found to include calibration information, examination limitations, UT couplant and penetrant material identification, and the results were recorded so that evaluation could be mad No violations were identifie . Unresolved Items A unresolved items are matters about which more information is required in order to ascertain whether they are. acceptable, violations or deviations. An unresolved item is discussed in paragraph 3 of this repor . . _ . . - - --

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5. Exit Meeting The inspector met with licensee representatives, listed in paragraph 1, at the conclusion.of the-inspection on September 12, 1986. The inspector summarized the purpose and the scope of_the inspection and the finding At no time during this inspection was written material provided by.the inspector to the license .-

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