IR 05000335/1987005
| ML17219A537 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/07/1987 |
| From: | Blake J, Crowley B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17219A536 | List: |
| References | |
| 50-335-87-05, 50-335-87-5, 50-389-87-05, 50-389-87-5, NUDOCS 8704280642 | |
| Download: ML17219A537 (13) | |
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A W~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-335/87-05 and 50-389/87-05 Licensee:
Florida Power and Light Company 9250 Mest Flagler Street Miami, FL 33102 Oocket Nos.:
50-335 and 50-389 Facility Name:
St.
Lucie 1 and
Inspection Conducted:
March 2-6, 1987 Inspector:
Approved by:
a e, ec
>on ie ngi eering Branch Oiv sion of Reactor Safety License Nos.:
OPR-67 and NPF-16 ae
~ne c7 ate
>gne SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of inservice inspection (ISI) (Unit 1),
augmented inspection of steam and feed systems (Units 1 and 2),
licensee action on previous enforcement matters (Unit 1), and inspector followup items (Units 1 and 2).
Results:
No violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees
"K. N.
- D. A.
- L. M.
~R.
A.
~C.
A.
- F. T.
"N.
G.
"P.
M.
D.
M.
A. T.
Harris, Plant Vice President Sager, Plant Manager Pearce, Operations Supervisor Symes, gA Supervisor Pell, Technical Supervisoi Carr, NDE Supervisor -
PNS Roos, gC Supervisor Heycock, ISI Coordinator Stewart, Test Group Lead Engineer Zielonka, Nuclear Engineer - Power Plant Engineering Other licensee employees contacted included engineers, technicians, mechanics, security force members, and office personnel.
Other Organizations C.
A. Fiallo, Authorized Nuclear Inservice Inspector, Factory Mutual Engineering G.
P,. Alexander, NDE Engineering Consultants, Inc.
NRC Resident Inspector
- H. E. Bibb, Resident Inspector
- Attended exit interview Exit Interview The inspection scope and findings were summarized on March 6, 1987, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspect~on findings.
No dissenting comments were received from the licensee.
The following new item was identified during this inspection.
(OPEN)
Inspector Followup Item 335, 389/87-05-01, Review of ASME Section XI Repair and Replacement Program - paragraph 6.b.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspectio.
Licensee Action on Previous Enforcement Matters 4.
(CLOSED)
Unresolved Item 335/84-27-01, Clarification of Requests for Relief for St.
Lucie Unit 1 IST Program.
This item identified a number of areas where IST relief requests submitted to the NRC by FP8L needed clarification.
Additional information was submitted and the Safety Evaluation Report (SER) issued.
Unresolved Items 5.
Unresolved items were not identified during this inspection.
Independent Inspection Effort (Units 1 and 2)
Because of a number of failures in wet steam piping systems, licensees have an ongoing program for monitoring pipe wall thickness in these systems.
Based on the recent failure of a Surry feedwater pump suction line, FP8L expanded their ongoing monitoring program for wet steam piping to include wall thickness measurements on water systems during the current Unit 1 outage.
The inspector discussed with the licensee their pipe thickness measurement program for steam and water systems for the current outage.
In the Fall of 1986 (prior to the Surry Feedwater Pump Suction line failure),
a 20" diameter 4th point extraction steam pipe on Unit 1 failed due to errosion/corrosion.
As a result of the failure, the licensee developed an inspection program for the current Unit 1 outage to identify for replacement or future inspection degraded piping in two-phase flow wet steam systems.
The program included 32 inspection points (each inspection point consisting of a grid pattern over a portion of the surface of the component chosen for the point) selected from the following systems based on selection criteria given in EPRI report NP3944 dated April 1985.
2nd, 3rd, 4th and 5th Points Extraction Steam Cross Under Piping Main Steam As a result of this portion of the inspection, 13 fittings were identified for replacement - all in the 4th point extraction steam.
The licensee chose 2~4 X Cr-tX Mo alloy steel for the replacement material.
After the Surry feedwater pump suction line failure, the licensee expanded their inspection program to include 15 inspection points (each point consisting of grid pattern over the surface of the component chosen for the point) in the following systems:
Heater Drains Boiler Feed (Feedwater)
Condensate Steam Generator Blowdown MSR Shell'Side Drain
For these systems, in general, the wall thickness was found to be near nominal thickness.
Some degradation was identified in the MSR shell side drain piping, which may require further inspections next outage.
A team has been designated to develop a program for future inspections for both Units 1 and 2.
The program will incorporate the lessons learned during the current program.
6.
Inservice Inspection - Review of Program (73051) (Unit 1)
The inspector reviewed the licensee's ISI program for the current outage (last outage, 3rd period, 1st 10 yr. interval) in the areas indicated below.
In accordance with the provisions of Florida Power and Light Company (FP8L) submittals (L-77-203 dated, July 1, 1977 and L-77-291, dated September 16, 1977) to the NRC, the applicable code for ISI is the ASME Boiler and Pressure Vessel (B8PV) Code,Section XI, 1974 Edition, 1975 Addenda.
a 0 The inspector reviewed the ISI program documents listed below.
Many of these documents were reviewed during previous inspections (see Region II reports 50-389/84-32 and 50-389/86-09).
For documents previously reviewed, only changes since the last review were reviewed.
C8P-PSL-87-100-2, Revision 0, FC-l, 1987, Inservice Examination Plan For FPLL Company St.
Lucie Nuclear Power Plant Unit No. 1.
PNS-CIS-QI 2.14, Revision 1, Nuclear Energy Manual For ASME Section XI, Inservice Inspection of Nuclear Power Plant Components.
'P8L, Topical Quality Assurance Report FP&L TQAR 1-76A, Revision
QI 1-PR/PSL-7, Revision 6, Quality Control Organization QI 10-PR/PSL-4, Revision 5, Plant Inservice Inspection QI 16-PR/PSL-l, Revision 17, Corrective Action QI 17-PR/PSL-l, Revision 10, Quality Assurance Records QI 18-PR/PSL-2, Revision 14, Quality Control Surveillances QI 18-QAD-3, Revision 8,
Scheduling of QA Department Audit Activities
4.
QP 2.4, Revision 6, Preparation and Revision of Quality Instructions I
QP 2.5, Revision 8,
Quality Assurance Indoctrination and Training QP 2.9, Revision 6, Qualification of QA Audit, QC Inspection and Construction Test Personnel QP 2. 14, Revision 0, Implementation of ASME XI QP 16. 1, Revision 8, Corrective Action QP 17. 1, Revision 13, The Collection and Storage of Quality Assurance Records for Nuclear Power Plants QP 18. 1, Revision 13, Conduct of Quality Assurance Department Audits QAD Quarterly Audit Schedule (1986)
QAD Quarterly Audit Schedule (1987)
QAD Annual Audit Program Plan (1986)
QAD Annual Audit Program Plan (1987)
QA Audit QSL-OPS-87-497 (In Progress)
NDE Procedure TR-1, Revision 0, ISI/NDE Manual Orientation For PNS Personnel NDE Procedure TR-2, Revision 0, Orientation Program for Contractor NDE Personnel NDE Procedure CAL-1, Revision 1, Ultrasonic Instrument Linearity Verification NDE Procedure CAL-2, Revision 1, Calibration of Magnetic Particle Equipment NDE Procedure CAL-5, Revision 0, Eddy Current Equipment Calibration and Certification ADM-CIS-4.1, Revision 0, Inservice Inspection (ISI) Services Vendor Performance Requirements ADM-CIS-5.2, Re'vision 0, Field Changes to Section XI Programs/Plans/Schedules
AOM-CIS-5.3, Revision 0, Field Changes to Nondestructive Examination Procedures AOM-CIS-6. 1, Revision 0, Guidelines for Controlled Documents ADM-CIS-7.1, Revision 0, Procedure for the Receipt Inspection of Nondestructive Examination Equipment and Materials AOM-CIS-9. 1, Revision 0, Procedure for the Qualification of NDE Procedures and Calibration Block Standards ADM-CIS-10.2, Revision 0, Control of Final Issued Document Data Packages ADM-CIS-10.3, Revision 0, The Administrative Review of the
.Document Data/Record Packages For Program Compliance ADM-CIS-17.1, Revision 0, Quality Assurance Records QI PNS-NDE-QI-9.2, Revision 0, Control of Nondestructive Examination (NDE) Activities -
NDE Manual QI PNS-NDE-QI-9.3, Revision 2, Nondestructive Examination Personnel Qualifi'cation and Certification e
QI PNS-NDE-QI-9.4, Revision 0, Visual Examination Personnel Qualification and Certification The documents were reviewed in the areas of:
Conformance with ASME 88PV, Code,Section XI and applicable code cases Approval of code cases Use of an authorized nuclear inservice inspector (ANII) and approval of plan and procedures by the ANII Review and approval of the ISI plan and procedures Identification of commitments and regulatory requirements Procedures for preparing plans and schedules and filing with enforcement and regulatory authorities Sufficient organizational staff to ensure performance of acceptable ISI work Site administrative procedures to define authorities and responsibilities for final evaluation and acceptance of ISI results
Haintenance and retention of appropriate ISI records gA review including assurance that plans and procedures have been reviewed by appropriate personnel and meet regulatory requirements Establishment of procedures for corrective action Procedures for auditing ISI activities by qualified gA personnel Corrective action of conditions adverse to quality Audits or surveillance of ISI activities Oversee contractor activities concerned with ISI Personnel qualification requirements Reporting requirements per ASHE code and Technical Specifications Identification and process of rel.ief requests b.
In addition to review of the above documents pertaining to ISI, the inspector discussed with the licensee administrative procedures for ascertaining that requirements of Articles IMA-4000 and IWA-7000 of ASME Section XI for repair and replacements are covered.
Procedure gP 2.14 refers to IMA-4000 and IMA-7000 for repairs and replacements without giving any details.
Although it appears that the various elements of a repair and replacement program exist, there is not a
document to tie the various elements together and specify responsibilities.
When questioned by the inspector, the licensee pointed out that a guality Instruction (gI) for this, purpose had been drafted and was in the review cycle.
Pending further review of the program after issue of the gI, Inspector Followup
'tem 335, 389/87-05-01, Review of ASME Section XI Repair and Replacement Program, was identified.
Within the areas inspected, no violations or deviations were identified.
7.
Inservice Inspection - Review of Procedures (73052) (Unit 1)
The inspector reviewed the ISI procedures indicated below to determine whether the procedures adequately covered required aspects of the approved ISI program.
See paragraph 6 above for the applicable cod a.
The following procedures were reviewed in the areas indicated below:
PNS"CIS-gI 2. 14, Revision 1, Nuclear Energy Manual For ASME Section
>(I, Inservice Inspection of Nuclear Power Plant Components.
NDE Procedure TR-2, Revision 0, Orientation Program for Contractor NDE Personnel F
NDE Procedure CAL-1, Revision 1, Ultrasonic Instrument Linearity
,Verification NDE Procedure CAL-2, Revision 1, Calibration of Magnetic Particle Equipment PNS-NDE-(I-9.3, Revision 2, Nondestructive Examination Personnel qualification and Certification NDE-2. 1, Revision 3, Magnetic Particle Examination (St.
Lucie - Unit 1)
NDE-3. 1, Revision 4, Liquid Penetrant Examination Solvent Removable Visible Dye Technique (St.
Lucie - Unit 1)
NDE-. 4. 1, Revision 1, Visual Examination VT-l, For Melds/Bolting/Bushings/Mashers NDE-4.2, Revision 0, Field Change A, Visual Examination VT-2 Conducted During System Pressure Tests NDE-4.3, Revision 0, Visual Examination VT-3/VI-4 NDE-4.5, Revision 1, Visual Examination NDE-5.3, Revision 1, Field Change A, Ultrasonic Examination of Clad Carbon Steel Piping NDE-5.7, Revision 1, Ultrasonic Examination of Reactor Pressure Vessel Studs and Reactor Coolant Pump Studs NDE-5. 14, Revision 0, Manual Ultrasonic Examination of Reactor Pressure Vessel Melds The procedures were reviewed in the areas of:
Compliance with licensee commitments Approval of procedures by the ANII qualification of NDE personnel
Recording, evaluating, and dispositioning of findings Records Retention b.
Specification of responsibilities of licensee and contractor personnel Procedure NDE 2. 1 was reviewed for technical content relative to:
examination method, surface preparation, use of color contrast particles, surface temperature, light intensity, coverage, prod spacing, magnetizing current, yoke pole spacing, and acceptance criteria.
C.
d.
e.
Procedure NDE 3. 1 was reviewed for technical content relative to:
method consistent with ASNE Code, specification of brand names of penetrant materials, specification of limits for sulfur and total halogens for materials, pre-examination surface preparation, minimum drying time following surface cleaning, penetrant application and penetration time, temperature requirements, method of removing penetrant, method of surface drying prior to developer application, type of developer and method of application, examination technique and conditions, technique for evaluation, and acceptance criteria.
Procedure NDE 4. 1 was reviewed for technical content relative to:
method direct visual.,
remote. visual or translucent visual; how visual examination is to be performed; type of surface condition available; surface preparation, if any; whether direct or remote viewing is used; special illumination, instruments, or equipment to be used, if any; sequence of performing examination, when applicable; data to be tabulated, if any; acceptenance criteria is specified and consistent with the applicable code section or controlling specification; and report form completion.
Procedures NDE 5.3, NDE 5.7 and NDE 5. 14 were reviewed for technical content in the areas of:
type of apparatus, extent of coverage including beam angles and scanning techinques, calibration requirements, search units, Distance Amplitude Curves (DAC),
reference level for monitoring discontinuities, method of demonstrating penetration, levels of evaluation and recording indications, and acceptance standards.
Within the areas inspected, no violations or deviations were identified.
8.
Inservice Inspection - Observation of Work and Work Activities (73753)
(Unit 1):
The inspector observed the ISI activities described below to determine whether these activities were being performed, in accordance with regulatory requirements and licensee procedures.
See paragraph 6 above for the applicable cod a.
The inspector reviewed the examination plan for the current inspection to determine if changes were being properly documented.
b.
qualification and certification records for the following NDE examiners involved in the examinations identified in paragraph c.
and d.
below were reviewed:
-
Two Level II Examiners One Level I Examiner UT
-
Five Level II Examiners One Level I Examiner General
-
One Level III Examiner c.
In-process magnetic particle inspection was observed for reactor pressure vessel (RPV) nuts 44, 47, 49, and 51.
The inspections were compared with applicable procedures in the following areas:
Specification of procedure to be used and availability of procedure at inspection area Use of knowledgeable NDE personnel qualified to the proper level Specific areas, locations and extent of examination clearly defined Type and color of ferromagnetic particles r
Material surface preparation/cleanliness Material surface temperature Examination technique/coverage Magnetizing current Prod or pole spacing Yoke lifting power Evaluation of indications d.
In-process ultrasonic (UT) inspection was observed for the following welds/components:
RPV Nuts 44, 47, and
RPV Studs 36, 38, 39, 40, and 42 RPV Closure Head to Flange Meld RPV-CH-209-02
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The inspections were compared with applicable procedures in the following areas:
Specification of procedure to be used and availability of procedure at inspection area Required equipment and materials available Specific areas, locations and extent of examination clearly defined Test attributes as specified in applicable test procedure Evaluation of indications e.
The inspector discussed with the licensee the eddy current (ET)
inspection program for steam generator tubes.
The program for the current outage included approximately 100K of the tubes in both generators.
At the time of the NRC inspection, the ET inspection had been completed.
Forty-seven (47) tubes in generator A and 30 tubes in generator B had been identified for plugging.
The licensee was still in the process of correlating the inspection results with past results and defining the nature of defects causing the indications.
The inspection results will be reported to the NRC in accordance with applicable requirements.
Within the areas inspected, no violations or deviations were identified.
9.
Inspector Followup Items (IFI) (92701B) (Units 1 and 2)
(OPEN)
IFI 335/86-25-01, 389/86-24-01, Review of Revised Welding Program.
This item pertained to weaknesses identified in the licensee welding program.
As identified in the previous inspection report, the licensee has initiated steps to formulate a
new welding program suitable for all FP8L entities.
Since issuance of the new welding program is a long term process, the licensee has revisions to Procedure M 0400 and the Welding Manual in process to correct the known weaknesses for the interim.
(OPEN)
IFI 389/86-24-02, Revision to Valve Stroke Testing Frequency Requirements.
This item pertained to the need to revise valve testing procedures to ensure procedurally that surveillance intervals are not exceeded.
At the times of the NRC inspection, a
revision to Procedure 0010125 to ensure that surveillance intervals are not exceeded was in the plant review cycle.