IR 05000272/1979014
| ML18079B007 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/03/1979 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18079B006 | List: |
| References | |
| 50-272-79-14, NUDOCS 7910010397 | |
| Download: ML18079B007 (8) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-272/79-14 Docket No. 50-272 License No. DPR-70 Priority:
Licensee:
Public Service Electric and Gas Company Category:
C Facility Name:
Salem Nuclear Generating Station - Unit 1 Inspection at:
Hancocks Bridge, New Jersey Inspection conducted:
April 16-20 and May 22-25, Inspectors: f.C. ~t ~
R: A. Mc'e~r Inspector Approved by: }, {.,5f,rA.,,.
...,._ ____.;;._ __ +-----------~--....,.---~
L. E. Trip, Chief, Engineering Support Section No. 1, RC&ES Branch Inspection Summary:
1979 date signed 1;3/71 crate signed Inspection on April 16-20, 1979 and May 22-25, 1979 (Report N /79-14)
Areas Inspected:
Routine, unannounced inspection by one regional based inspector of inservice inspection activities including ISI program review, review of NOE procedures, observation of NOE in progress and review of ISI dat The inspection involved 67.5 inspector hours onsite by one NRC inspecto Results:
No items of noncompliance or deviations were identifie DETAILS Persons Conta~ted Public Service Electric and Gas Company G. Duncan, ISI Coordinator
- S. LaBruna, Maintenance Engineer
- L. Lake, Engineer
- B. Leap, Station QA Supervisor
- M. Metcalf, QA Engineer, Resident Group
- Mid~ra~ Station Manager W. Reuther, Resident QA Engineer J. Rogozenski,* Principal Engineer
- D. Sachs, Engineer
- J. Stillman, Station QA Engineer Southwest Research Institute (SwRI)
- W. Clayton, Technical Liaison Group
- W. Flack, Manager Field Services T. Mayces, QA Representative R. Turner, Team Leader Sonic Instruments Incorporated
- D. Lamont, Engineer
- Denote.s those present at exit interview on May 25, 197 **Telephone contac Inservice Inspection ISI Activities I ISI Program The Southwest Research Institute, the licensee ISI contrac-tor, has prepared a long term inservice inspection plan which includes the examinations required by the ASME Code,Section XI, for the first ten-year inspection interval, and has also prepared an examination plan covering the examinations to be completed during the 1979 refueling outag The inspector noted that in addition to the examinations required by Section XI of the ASME Code, welds numbers 34-Ms~2111-2, 14-Bf-2111-3 and 1-SGF-PE~6-56-B were added to the program in order to meet a licensee commitment to the NRC to provide augmented inspection to portions of the Main Steam
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and Steam Generator Feed Systems which were exposed to high heating and cooling rates during post weld heat treatmen The inspector found that the IS1 program meets the require-ments of the facility Technical Specification and the applic-able requirements of the ASME Code,Section XI, 1974 Edition through Summer 1975 Addend No items of noncompliance were identifie Implementing Nondestructive Examination (NOE) Procedures The inspector selected the following NOE procedures for review to ascertain compliance with ASME Code requirements and technical adequacy:
SwRI-NDT-600-3, Revision 46, 11Manual Ultrasonic Examina-tion of Pressure Piping Welds for Piping Welds and Adjacent Base Material in Thickness Range Greater Than 0.4 to 5.0 Inches
SwRI-NDT-600-36, Revision 0, 11Manual Ultrasonic Examina-tions of Studs and Bolts Greater Than One Inch to Less Than Two Inches in Diameter
Procedure Deviation No. 3 to 600-36, Revision 0 SwRI-NDT-200-1, Revision 42, 11 Liquid Penetrant Examina-tion - Color Contrast Method
SwRI-NDT-300-1, Revision 14, 11Dry Powder Magnetic Particle Examinations
SwRI-NDT-900-1, Revision 42, 11Visual Examination of Nuclear Reactor Components by Direct or Remote Viewing
The inspector 1s review for technical adequacy included, but was not limited to, the parameters listed below for the ultrasonic, magnetic particle and liquid penetrant exami-nation techniques~
UJtrasonic Examination (a) The type of apparatus including frequency range is specified (b) The extent of coverage incl~ding bea~ angles and.
scanning surface is specified
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(c) Calibration requirements including frequency and size of transducer and calibration reflectors are specified and consistent with the applicable ASME Code (d) The reference level for monitoring discontinuities is defined and the scanning level is specified and consis-tent with the applicable ASME Code (e)
Acceptanc~ limits are specif1ed or referenced and are consistent with the applicable ASME Code Magnetic Particle Examination (a) The examination is to be done by the continuous method (current on while particles are applied)
(b) The dry particle color provides good contrast with background.
(c) The examination is conducted with sufficient overlap to achieve 100 percent coverage (d) Magnetic yoke lifting power is consistent with ASME Code requirements (e) Acceptance criteria are specified or referenced and are consistent with the applicable ASME Code Section Liquid Penetrant Examination (a) The examination method is consistent with ASME Code requirements (b)
Penetrant materials used for nickel base alloys and austenitic stainless steel are ~equired to be analyzed for compliance with allowable residual sulfur and halogen content (c)
Examination surface requirements, including temperature limitations, are specified and consistent with ASME Code requirements (d) Methods for removal of solvent removable penetrant are specified and consistent with the applicable ASME Code (e) A technique for evaluation of indications is specified, acceptance standards are referenced, and are*~onsistent with the applicable ASME Cod *
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No items of noncompliance were identifie Observation of NOE in Progress (1)
Ultra~onic Examination The inspector observed the ultrasonic exmination of the following:
Number 11 RHR Heat Exchanger Studs numbers 1, 18, 19 and 36 Weld number 6MS-2111-20, valve to 6-inch diameter pipe in the Main Steam System The insgector's observations included the longitudinal beam, 0 examination of the heat exchanger studs, and the o0, longitudinal beam and 45° shear wave examination of the steam system wel The calibration*and examina-tion of the studs was governed by procedure SwRI-NDT-600-36, Revision 0, and procedure SwRI-NDT-600-3, Revision 46, governed the main steam weld examination.
The inspector noted that the technique used for th~ stud examination incorporated a 7.5 MH transducer connected to a Sonic MARK I Flaw Detector wMose frequency selector switch was set at 5.0 MH. 'The inspector requested SwRI to identify the examinatton frequency resulting from the techniqu During discussions with SwRI NOE personnel at the site, and in a telephone conversation with SwRI personnel at San Antonio, Texas, the inspector was informed that the frequency selector switch tunes the received signal, but does not affect the frequency of the transmitted signal which is determined by the transducer frequenc The inspector then contacted Sonic Instruments, Inc., the instrument manufacturer, and was informed that originally the instrument functioned as described by SwRI personnel, but that a design change was incorporated in the instru-ment which changed the function of the frequency selector switc The serial number of the Sonic MARK.I instruments on site indicated they represented both design features according to the manufacturer's informatio In a subsequent telephone conversation on June 11, 1979, the inspector informed the licensee of a telephone call from SwRI to the inspector advising the inspector that,
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based on a SwRI conversation with Sonic Instruments, Inc., the information given the inspector by SwRI repre-sentatives and the Sonic Instruments, Inc. representative was incorrec This item is considered unresolved pending clarification of instrument function regarding use of the frequency selector switch on the Sonic MARK I instrumen (272/79-14-01)
(2) Visual Examination The inspector witnessed the visual examination of number 11 RHR Heat Exchanger upper and lower flange nuts which was governed by procedure SwRI-NDT-900-1, Revision 4 The flange nuts were examined in place using a flash-light as a visual ai No items of noncompliance were identifie (3)
NOE Personnel Qualification Records The inspector reviewed personnel qualification and certification records for the individuals performing the examinations listed abov The inspector found that the certifications were in accordance with the applicable requirements of SNT-TC-lA, the governing documen No items of noncompliance were identifie !SI.Data Review The inspector reviewed a selected sample of available !SI data in order to ascertain that the data are complete and that the licensee 1 s disposition of adverse findings and subsequent reexamination is consistent with ASME Code and Regulatory requirement Records associated with the following were included in the inspector 1 s review:
Steam Generator Feed System elbow to pipe weld number 14-BF-2111-3 Steam Generator Feed System penetration weld number l-SGF-PEN-6-56-B
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Main Steam System pipe to valve weld number 34-MS-2111-2 Safety Injection System tee to cap weld number 8-SJ-1162-17 Safety Injection System pipe support weld number 8-SJ-1152-16-PS RHR Heat Exchanger vessel support weld number 12-RHR-HEX-2VS Safety Injection System valve bonnet studs number 12-SJ-44BS-7, -8 Main Steam Header upper studs number 12-MS-167-USS Main Steam Header lower studs number ll-MS-167-LSS-l, -2 The inspector noted that the ultrasonic examination procedure referenced on calibration sheet number 190038 for main steam header upper studs and on calibration sheet number 190073 for lower studs did not agree with the data provided in the ISI program.
The licensee advised the !SI contractor of the apparent dis-crepancy and agreed that a review of all data sheets would be done and necessary corrections made to the final data which would be submitted to the license The inspector.stated that this item is considered unresolved pending licensee review of the final data and subsequent NRC inspectio (272/79-14-02)
The inspector noted that weld 8-SJ-1162-17, weld 8-SJ-1152-16-PS and weld 12-RHR-HEX-2VS displayed linear liquid pene-trant indications as documented on penetrant examination record sheet number 110003, number 110026, number 110028 and number 11005 The inspector examined SwRI Custom~r Notification Form (CNF)
No. 1, CNF No. 2 and CNF No. 7 and licensee Testing Deficiency Report (TOR) No. 160, TOR No. 161 and TOR No. 17 The inspector found that the linear indications were considered nonrelevant and were accepted as ts by the licensee, but that no reexamination was done to verify that relevant indications were not present.
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At the exit meeting on May 25, 1979, the licensee stated that the indications would be reexamined and the results of the reexamination would be documente The inspector stated that this was considered an item of noncompliance for failure to properly disposition penetrant indication In a subsequent telephone conversation on July 2, 1979, the inspector informed the licensee that the item would be considered unresolved pending the reexamination and NRC review of the reexamination result (272/79-14-03) Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviation Unresolved items disclosed during the inspection are discussed in Paragraph 2.c.(l) and.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) at the conclusion of the inspection on May 25, 197 The inspector summarized the purpose and scope of the inspection and the findings.