IR 05000324/1986010
| ML20210N941 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/23/1986 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210N916 | List: |
| References | |
| 50-324-86-10, 50-325-86-09, 50-325-86-9, NUDOCS 8605050329 | |
| Download: ML20210N941 (8) | |
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L UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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AT L ANTA, GEORGI A 30323
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Report Nos.: 50-325/86-09 and 50-324/86-10 Licensee:
Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Docket Nos.:
50-325 and 50-324 License Nos.:
DPR-71 and DPR-62 Facility Name:
Brunswick 1 and 2 Inspection Condu * d:
Ma-ch 17 - 21, 1986 Inspecto :
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oley Date S'igned Approved by.
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1ake, Section Chief Date Signed n neering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection involved 32 inspector-hours on site in the areas of inservice inspection - observation of work activities and data review and evaluation.
Results: One violation was identified - failure to follow ASME Section XI period requirements for the examination of components - paragraph 6.2.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- C. R. Dietz, General Manager, Brunswick Steam Electric Plant (BSEP)
- B. E. Hinkley, Manager, Technical Support
- L.
E. Jones, Director, Quality Assurance
- K. E. Enzor, Director, Regulatory Compliance
- R. M. Poulk, Senior Specialist, Regulatory Compliance
- W. M. Tucker, Engineering Supervisor, Technical Support
- L. W. Wheatley, Project Specialist, Inservice Inspection (ISI) Section Other Organization T. Brinkman - General Electric - Level III Examiner NRC Resident Inspectors
- W. Ruland, Senior Resident Inspector
- L. Garner, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 21, 1986, with those persons indicated in paragraph I above.
The inspector described the areas inspected and discussed in detail the inspection findings listed below. No dissenting comments were received from the licensee.
(0 pen) Violation 324/86-10-01, Failure to Follow ASME Section XI Period Requirements for the Examination of Components paragraph 6.a.
(0 pen) Inspector Follow Item 324/86-10-02; 325/86-09-01, Technical Specification Change for Jet Pump Monitoring paragraph 6.b.
After the completion of the inspection, the licensee notified the inspector that the indication detected in the inconel butter on 28-inch recirculation system Nozzle N-1A had been confirmed as cracked (see paragraph 5.b.).
In addition, the licensee had expanded their inspection to include the other 28-inch recirculation system Nozzel N-1B and had confirmed an axial crack in the inconel butter of this weld. The licensee intends to further expand the scope of ultrasonic examinations to include five additional 12-inch
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recirculation system welds. General Electric (GE) will analyze the crack indications to determine if weld overlay repairs will be necessary.
The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspection.
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3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Unresolved Items Unresolved items were not identified during the inspection.
5.
Inservice Inspection - Observation of Work and Work Activities (73753B)
Unit-2 The inspector observed work activities to ascertain whether the inservice inspection (ISI), repair, and replacement of Class 1, 2, and 3 pressure retaining components are performed in accordance with Technical Specifica-tions (TS), the applicable ASME Code, correspondence between NRR and the licensee concerning relief requests, and requirements imposed by NRC/
industry initiatives.
a.
The inspector reviewed the licensee's ISI plan for the current inspection period of the first ISI 10 year inspection interval to ascertain whether component examination requirements of the TS, ASME Section XI, and the ISI Program accepted by the NRC will be met during the current outage in the areas of:
- Number of items to be inspected Methods of examination
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- Extent of examinations The first 10 year inspection interval for Unit 2 will conclude on July 10, 1986.
Therefore, all inspections required for the first interval are to be completed during the current outage.
See paragraph 6 for details relating to the inspector's review of the entire 1st 10 year inspection interval.
The applicable code for the review of the final 40 month inspection period is the ASME Boiler and pressure Vessel Code,Section XI, 1977
Edition, Summer 1978 Addenda.
In addition to the inspections required to meet the first interval requirements and various other augmented inspections, the outage plan includes the inspection of stainless steel pipe welds relative to intergranular stress corrosion cracking (IGSCC) problems. The proposed inspection program for these welds are specified in Carolina Power and Light Company letters NLS-85-390 dated November 1,1985, and NLS-85-423 dated November 27, 1985.
In general CP&L's proposal specifies 100 percent inspection of the stainless steel welds in the reactor recirculation (RECIRC) and residual heat removal (RHR) systems.
In addition, the proposal provided for replacement of the isolable portion of the Class 1, 6-inch reactor water cleanup (RWCU) system piping with
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nuclear grade materials, modification of the RWCU containment penetration to eliminate the inaccessible weld of the original flued head penetration design, reinspection by ultrasonic testing (UT) of five weld overlay repairs, and migation of IGSCC using weld overlay and induction heat stress improvement (IHSI).
The proposal also stated that GE examination personnel, performing the IGSCC examinations have been requalified in accordance with the Electric Power Research Institute (EPRI) requirements and that GE's automated SMART UT system would be utilized (where physical clearance allowed) for examinations of the welds.
All examinations proposed above have presently been completed by the licensee and a total of 34 new overlay weld repairs were required.
b.
During the inspections, the licensee notified the irspector that GE had detected an axial indication in the inconel butter on the Unit 2, 28-inch recirculation system nozz.le N-1A.
This examination was performed in accordance with (IAW) the inservice inspection program and NRC Information Notice 84-41.
GE detected the indication using enhanced UT techniques, developed by EPRI and GE and delineated in GE Procedure UT1.51, for automated examination of dissimilar netal welds.
The inspector reviewed the SMART system tape of the examination; observation calibration block reflector comparisons of the indication, and held discussions with the GE Level III concerning GE's methods and plans for further evaluation of the indication. On March 25, 1986, the licensee nctified the inspector by telephone that the indication reported above had been confirmed as an axial crack.
In addition, the licensee had expanded their inspection to include the other 28-inch recirculation system nozzle N-1B and had confirmed an axial crack in the inconel butter of this weld.
The licensee intends to further expand the scope of examinations to include five additional 12-inch recirculation system welds.
GE will analyze the indications to determine whether weld overlays repairs will be required.
Within the areas inspected, no violation or deviation was identified.
6.
Inservice Inspection - Data Review and Evaluation (73755B) (Unit 2)
The inspector reviewed NDE data described below to determine whether the data covers the scope of examinations required by the applicable ASME Codes for the first 10 year inspection interval and to determine whether the inservice inspection files are complete and data within previously established acceptance criteria.
a.
As noted in paragraph 5.a. the first 10 year inspection interval for Unit 2 will conclude on July 10, 1986. Therefore, all examinations of Class 1, 2, and 3 components required by the 10 year requirements of the Technical Specifications and the ISI program accepted by NRC, and meeting the minimum examination percentages specified in the applicable ASME Code,Section XI Edition and Addenda must be complete this outage.
The applicable codes for the review of Brunswick, Unit 2 first 10 year
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interval was ASME 1970 Edition, ASME 1974575 Edition and Addenda and ASME 1977S78 Edition and Addenda.
During the review, the inspector identified the following problems:
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Categories B-G-2 and B-K-2 component examinations were not
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performed in each of the three inspection periods of the first 10 year interval as required by ASME 1970, ASME 74575 and ASME 77578 editions of the code. All examinations in these inspection categories have been scheduled to be performed in the current inspection outage.
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Class 2 components were not examined until the third inspection period.
CP&L's first period inspection started using the 1970 Edition of the ASME Code.
The 1970 Edition of the ASME Code did not have requirements for the examination of Class 2 components.
However, the licensee upgraded their program to the 74575 Edition and Addenda of the ASME Code prior to the second outage in the fi rst inspection period.
The program was further updated to the ASME 77578 for the second and third inspection periods. The 74S75 and 77578 ASME Codes required examination of Class 2 components and require portions of the examinations to be performed during each inspection period.
Failure to perform the examinations delineated above over the entire inspection internal is in violation of ASME,Section XI, and was reported to the licensee as violation Item 50-324/86-10-01, Failure to Meet ASME Section XI Period Requirements for the Examination of Components.
b.
The inspector obtained NDE records for three areas subject to examina-tion, including two areas for Class 1 components such as pumps, valves, supports, and etc., to determine whether the selected records contain or provide reference to the following documents:
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Examination results and data sheets
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Examination equipment data
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Calibration data sheet
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Examination evaluation data
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Records on extent of examination
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Records on disposition of findings
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Identification and certification of materials, equipment, and
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personnel.
The following components were verified:
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Component Examined Examination Method (20) Jet Pumps Hold-Down Beams Ultrasonic Examination (UT)
CP&L Periodic Test:
PT-90.6 Examinations Performed by GE (64) Reactor Vessel Studs Magnetic Particle Examination Studs 15-19 removed and (MT) and UT Performed by examined with MT and UT Southwest Research Institute (SwRI)
Studs 1-14 and 20-64 MT Procedure No. 300-2 Rev. 36 Examined in place with UT and UT Procedure No. 600-18 Rev. 24 Used in Examinations Feedwater Nozzle Inter-radius Work performed IAW Examination of Nozzles CP&L Plant Modification N-4A 945 82-022, UT and Liquid N-4B @l35 Penetrant Examinations (PT)
N-4C @225 were performed by GE N-4D @315
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During the inspector's review of ISI data for the jet pumps hold down beams the inspector inquired as to the status of other recommendations made in the GE Service Information Letter (SIL) No. 330.
These recommendations included the following:
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Jet Pump Beam Crack Surveillance Initiate daily surveillance and evaluation of jet pump performance.
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Jet Pump Operability Technical Specifications Review the Technical Specifications to determine if they should be revised.
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Jet Pump Performance Monitoring Establish a jet pump performance monitoring program.
The licensee had reviewed this issue and had written a draft Technical Specification Change (No. 84TSB32).
This Technical Specification change however, has been in the draft form since 1984.
Brunswick Unit 2 has now achieved the ten years service GE predicted would be needed for crack initiation in a BWR-4 reactor jet pump hold-down beam.
In addition, a Region II licensee operating a BWR-4 reactor of the same vinage as Brunswick Unit 2 has already reported a crack in one of the jet pump hold down beams.
The inspector held discussions with cognizant licensee personnel concerning this matter and the licensee agreed to review this issue in light of the 10 year service presently achieved on Unit 2.
Licensee action in this area will be tracked as Inspector Followup Items 324/86-10-02, 325/86-09-01, Technical Specification Change for Jet Pump Monitorin '
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c.
The inspector obtained NDE records of pressure retaining welds in the reactor pressure vessel to determine whether the following requirements were met:
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The method, extent and technique of examination comply with licensee's ISI program and applicable NDE procedure.
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The recording, evaluation, and disposition of findings are in compliance with the applicable NDE procedure and applicable code requirements.
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Inservice nondestructive examination results compared with recorded results of prior Section XI examinations.
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The method usea for NDE was sufficient to determine the full extent of indication or acceptance.
Identification and certification of materials, equipment and
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personnel.
Records for the following welds were reviewed by the inspector:
Welds Examined Vendor and Procedure Used Top circumferential weld No. B Vendor: SwRI (Dollar Plate Weld) 382-inch SwRI UT Procedure 600-15 Category No. B-A, Item Revision 55 No. B. 1.21 (Code Case 1.150 had been Invoked)
Reactor Vessel to Feedwater Nozzle Vendor:
SwRI Welds for Nozzles N-4A SwRI UT Procedure N-48, N-4C and N-4D 700-6 Revision 17 d.
The inspector also reviewed NDE data for two pressure retaining pipe weld in each of three piping systems to determine if the following requirements were met:
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The examination unit calibration data sheets show no major deviations between initial and final calibrations.
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Collected examination data and any recordable indications are properly recorded to permit accurate evaluation and documentation.
Evaluation of examination data performed by a Level II or
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Level II examiner.
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Evaluation of examination data complies with the procedure.
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Materials, equipment, and personnel were certifie '
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Records for the following welds were reviewed:
System / Weld Identification Calibration Sheet Numbers Reactor Core Isolation Cooling (RCIC)
(1) 2E51-RCIC-4" DISCH-5 190034 (2) 2E51-RCIC-4" DISCH-6 190034 and 190033 High Pressure Core Injection (HPIC)
(1) E41-HPIC 14"-DISCH-3 190112 (2) E41-HPIC 14"-DISCH-10 190017 Core Spray (CS)
(1) ?E 21-CS-10"-A-DISCH-4 190039 and 190040 (2) 2E 21-CS-10"-A-DISCH-12A 190035 and 190036
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Within the areas inspected, no violations except as noted in paragraph 6.a or deviations were identified.
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