IR 05000272/1990015
| ML18095A389 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/10/1990 |
| From: | Chaudhary S, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18095A388 | List: |
| References | |
| 50-272-90-15, 50-311-90-15, NUDOCS 9008070245 | |
| Download: ML18095A389 (7) | |
Text
Report N Docket No License No DPR-70 DPR-75 U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Licensee:
Public Service Electric & Gas Company P. 0. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name:
Salem Generating Station, Units 1 and 2 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
May 14 - 25, 1990 Inspectors: ~~
S. K. cITTilJCiharYJSr. Reactor Engineer Approved by:
. Strosnider, Chief, MPS, EB, DRS date Inspection Summary:
Routine announced inspection on May 14-25, 1990 (Report Nos. 50-272/90-15, and 50-311/90-15)
Areas Inspected:
The inservice inspection program was reviewed including the ten year plan, steam generator eddy current testing, primary and secondary water chemistry results, and the erosion - corrosion control progra Results:
N~ violations or deviations were identified.
Details Persons Contacted PSE&G
- Robert Brandt, Inspection Services Engineer
- C. J. Conner, Senior ISI - Supervisor, Salem
- R. Donges, Licensing Engineer
- P. J. Kudles, Manager, Site Services
- David Mohler, Rad Protection/Chemistry Manager
- Denotes those attending exit meeting The inspector also contacted other administrative, technical, and management personnel during the inspectio.0 Scope The scope of this inspection included the review and observation of activities and documentation in the following areas:
the ten year inservice inspection (ISI) program, steam generator eddy current examination, the erosion/corrosion (E/C) control program, and primary and secondary water chemistry result.0 Inservice Inspection Program Review The Salem Generating Station, Unit 2 is in the third period of the first ten year interval of the ISI program at the present tim The Salem Generating Station, Unit 2, was built during the 1970s and was placed into commercial service on October 13, 198 In February 1976, the NRC amended Paragraph 55a(g) of 10CFR50 to require nuclear plants to upgrade their Technical Specifications in the areas of ISI requirement By amending Paragraph 55a(g) and by invoking Regulatory Guide 1.26, the NRC required nuclear plants to upgrade their systems to include not only Class 1 systems but also Class 2 systems in their ISI Program Class 1 component and weld identifications were supplied by PSE&G prior to the preservice examination of the plan Vessel drawings and system isometric figures for Class 2 systems and components were compiled from information supplied by PSE&G as part of the upgrading effor *
The identification of the Class 1 systems and components, Appendix 0, is based on a 10-year inspection interval, while the selection and identifica-tion for the Class 2 systems and components, Appendix E, are based on a 40-year lifetime of the plan Identification for Class 3 systems and components will be in the PSE&G pressure testing progra The start of the first 10-year interval for Class 1 and the 40-year interval for the Class 2 system coincides with the date of first commercial operatio The inspector reviewed the ISI Program manual and discussed the status of the program with cognizent licensee personnel, and determined that the majority of the inspections required in the first interval have been completed during previous and the current outages, and the remaining examinations are planned for the next scheduled outag No extension request, as allowed by the ASME Code, has been needed so far, and only ten (10) examinations scheduled this outage have been deferred to the next outage in addition to the ninety five that are scheduled for the next outag Conclusions The licensee has maintained adequate control over the ISI Program, and has completed the required inspections and examinations for the first interval without undue recourse to extension requests and deferrals of tests, inspections, or examinations. NOE Examiner Certification Program In addition to the licensee's staff, contractors are used for various types of NOE associated with ASME Section XI inspections, the E/C program and steam generator eddy current inspection The licensee's staff was technically capable of performing their assigned duties, and the staff size appeared adequate to meet the scheduled work loa The inspector selected a representative sample of qualification - certification records for both licensee personnel and contractors for revie All of the records reviewed were found to be acceptabl.0 Steam Generator Eddy Current Inspection The licensee established an inspection plan prior to the examination to fulfill the requirements of the Technical Specification In addition to the above, due to the concern regarding tube integrity in the area of Anti Vibration Bar (AVR) supports and cold leg thinning, the licensee also examined a substantial number of tubes exceeding Technical Specification requirements in all SG Following is the breakdown of tube inspections in all the Steam Generator *
Salem Unit 2 Steam Generator Eddy Current Inspections Performed Technical Specification Inspection - 23 Steam Generator
12% Random inspection - which included 396 tubes+ 17 tubes with Indications from prior outages Zero (0) pluggable indications during this inspection Additional Eddy Current Inspections Performed. * *
21 Steam Generator 4 previous indications from prior outages post U-bend heat treatment verification of row 2 936 tubes to address AVB wear concerns and/or cold leg thinnin (Following EPRI guidelines and looking in the area of concern for the phenomenon present.)
eight (8) tubes were plugged (heat #NX-6778).
22 Steam Generator 7 previous indications from prior outages post U-bend heat treatment verification of row 2 888 tubes to address AVB wear concerns and/or cold leg thinnin (Following EPRI guidelines and looking in the area of concern for the phenomenon present.)
four (4) tubes plugged (heat #NX-6778).
23 Steam Generator 2388 tests to obtain steam generator tube history and to address AVB wear concern and/or cold leg thinnin (Following EPRI guidelines and looking in the area of concern for the phenomenon present.)
post U-bend heat treatment verification of row 2 fifteen (15) tubes plugged (heat #NX-6778).
24 Steam Generator 28 previous indications from prior outages post U-bend heat treatment verification of row 2 330 tubesheet inspections to address concerns regarding expansion of the tubes above the top of the tubeshee tubes to address ABV wear concerns and/or cold leg th~nning. (Following EPRI guidelines and looking in the area of concern for the phenomenon present.)
Eleven (11) tubes plugged (heat #NX-6778).
The eddy current inspection was done with the motorized rotating pancake coil (MRPC), using the Zetec Digital Data Acquisition System, and Westinghouse Intelligent Eddy Current Data Analysis System.at
frequencies 400, 200, 100, and 25 KHZ operated in both differential and absolute mode The examination was performed using standard 0.740 or 0.720 0.0 bobbin coil probe Ten percent (10%) of SG-24 tubes (approximately 330) were examined for concerns regarding the tube rolling proces This examination did not disclose any over-expansion of tube out of the tube shee In row-1 of the hot leg side of all the steam generators, 336 tubes were inspected for plug-in-plug (PIP) installation to address the heats of plugs believed susceptible to ISC The licensee had established the acceptance limit for tube degradation as 35% or more through-wall crack in any tub Conclusions The licensee has performed inspections in excess of the Technical Specification requirements in all steam generators to determine the operat-ing condition of the generators and to assure safety and reliability of the NSSS syste Also, recognizing the importance of 11ALARA 11 concept, the licensee provided adequate training, controls, and maximum effective automation for these inspections and examinations. Data Analysis Data analysis was performed using the Zetec Computer Screening (CDS) system and Westinghouse Intelligent Eddy Current Data Analysis syste During the inspection, Westinghouse system was being use The results of these analyses were then reviewed by one or more Level III analyst Any questionable finding was reviewed by a supervisory analyst for final resolutio Conclusions The inspector did not identify any deficiencies in the methods of analysi No violation was identifie.0 Steam Generator Secondary Side In-Bundle Inspection The 11 CECIL 11 inspection is performed in each SG in every schedule outage to determine the state of sludging at the base of SG, and the effectiveness of sludge lancing operation The system is an automated video inspection procedur Erosion-Corrosion Control Program The licensee has initiated an erosion/corrosion control program in response to the NRC Information Notice 86-10 The responsibility for the development and administration of the program has been assigned to
- the engineering department of the license The actual measurements and testing as directed by engineering are performed by or contracted out by the ISI departmen The engineering department issued a procedure on 3/7/90 detailing the requirements and list of items covered by the program for the current outag However, due to time and resource constraints, the ISI department requested a prioritized listing of items which must be covered this outag The engineering department then prioritized the lis The data was being evaluated at the time of this*
inspectio The inspector had no further questions in this regard at this tim.0 Water Chemistry - Primary and Secondary (Unit-1 and Unit-2)
Water Chemistry data were reviewed as part of the inspectio The methods of collecting and verifying the accuracy of data were not included in the scope of this inspectio Reactor Coolant System Results (Primary)
The Reactor Coolant System water chemistry as reported by the licensee for the last operating cycle has been stabl Normal variations occur during plant transient The specifications and typical values reported are as follows:
Parameter Lithium Sp. Conductivity Boron pH Oxygen Fluorine Chloride Specification based on boron
<40.0 microSiemens none 4.2 - 1 <100 ppb
<150 ppb
<150 ppb Secondary Water Chemistry Results Range 0.4-0.8 ppb 5.06 - 5.6 mSiemens 1-4 ppm 6.5 - ppb 19 ppb 5-22 ppb The secondary water chemistry results obtained from the steam generator blow down were also stabl The Typical values reported are as follows:
Parameter Sp. Conductivity Chloride Sulfate Sodium Specification
>1.0 microSeimen
<20 ppb
<20 ppb
<20 ppb No unusual trends or deficiencies were identifie Range 2 mSeimens 1 - 2.5 ppb 2 - 5 ppb 0. 3 - 1. 9 ppb
l
10.0 Management Meeting The findings of the inspection were discussed with licensee representatives during the course of inspection, and presented the licensee management at the close of inspection on May 25, 1990 at the exit meetin (See paragraph 1.0 for attendees)
At no time during the inspection was written material provided to the licensee by the inspecto The licensee did not indicate that proprietary information was involved within the scope of this inspection.