IR 05000338/1982012
| ML20053D854 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/10/1982 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20053D844 | List: |
| References | |
| 50-338-82-12, 50-339-82-12, NUDOCS 8206070386 | |
| Download: ML20053D854 (6) | |
Text
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o UNITED STATES
'h, NUCLEAR REGULATORY COMMISSION g
ga REGION 11 o
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
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Report No. 50-338/82-12 and 50-339/82-12 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Facility Name:
North Anna Docket Nos. 50-338 and 50-339
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License Nos. NPF-4 and NPF-7 Inspection at No Anna site near Mineral, Virginia
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Date Signed Yr.;?t//f,}f/'V
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Appro ed
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w,vn c A. Herdt,'SkElon Chief
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Engineering Inspection Branch
Division of Engineering and Technical Programs SUMMARY Inspection on April 21-22, 1982 Areas Inspected This routine, unannounced inspection involved 13 inspector-hours on site in the areas of inservice inspection (ISI) data review and evaluation (Unit 2); review of steam generator tube eddy current inspection results (Unit 2); review recent technical specification (TS), submitals affecting ISI inspection requirements (Units 1 and 2).
Results
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Within the areas inspected, no deviations or violations were identified.
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REPORT DETAILS 1.
Persons Contacted -
Licensee Employees
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W. R. Cartwright, Station Manager
- J.' R. Harper, Maintenance Superintendent
- V. L. Lawshe, Sr. Engineering Technician-NDE
- Terry Johnson, Engineer-QA
- Other Organizations Conam Inspection R. H. Lofgren, Level II, ET Data Analyst NRC Resident Inspector D. Johnson M. Shymlock
- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on April 22, 1982, with those persons indicated in paragraph I above. Listed below are findings, identified during the inspection and discussed with the licensee in detail.
a.
(Open) Unresolved Item (339/82-12-01), Inadequate discription of partial ISI weld examination; incomplete weld dimension information (paragraph 6.a).
b.
(0 pen) Inspector Followup Item (339/82-12-02), Calibration block drawings unavailable for review, (paragraph 6.b).
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspectio.
5.
Technical Specification (TS) Submittals Affecting ISI Inspection Require-ments (Units 1 and 2)
The inspector reviewed and discussed with cognizant licensee personnel recent TS submittals affecting-ISI requirements. Affected areas / components included:
a.
Snubbers * 50,000 kips, TS 3/4.7.10 b.
Surveillance Requirements for ISI of ASME Class 1, 2 and Components..., TS 4.0.5 Amendment 19.
c.
Reactor Coolant System (1) Structural Integrity, TS 3/4.4.10 (2) Steam Generators, TS 3.4.5 (3) Steam Generator Supports, TS 3.4.10.2 d.
Quality Assurance Department, TS 6.5.3 The inspector stressed the need to be kept apprised of submittals affecting ISI activities and requested that RII Engineering Inspection Branch be added to their distribution list.
6.
Data Review and Evaluation (Unit 2)
This inspection was performed as a followup to the previous work effort documented in report RII:50-338, 339/82-09. At the time of this inspection all items in the ISI program scheduled for this outage, identified as the first outage /first period interval, had been inspected. Evaluation of eddy.
current inspection results from the three (3) steam generators was almost complete - this phase of the ISI will be discussed in paragraph 7 of this report. The selection and nondestructive examination of items in the Unit 2 ISI program is governed by requirements of the Plant Technical Specifica-tion, section 4.2 and Section XI (74S75) of the ASME Boiler and Pressure Vessel Code.
Components / parts under IWB-2600/IWC-2600 scheduled for examination during
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this outage included reactor vessel studs, nuts, washers and cladding; cer-tain welds in the pressurizer and steam generator "B"; Class 1 and 2 pipe welds; flywheel and other miscellaneous items, e.g., bolts, hangers, etc.
The inspector selected NDE records from the pressurizer; reactor vessel studs, nuts, washers and clad patches; certain pressure boundary pipe welds and steam generator welds. These records were reviewed to ascertain whether they contained information on, or provided reference to:
examination results, examination equipment data, calibration data sheets, evaluations of indications, extent of examination, programmatic deviations, disposition of findings and identi fication of, NDE material, e.g., UT' couplant.
Records selected for this review were as follows:
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COMPONENT WELD AREA /PART FIGURE OR COMPONENT INSPECTION METHOD Bl.8 Reactor Vessel Closure Studs, UT and Surface Vessel Locations 1-4
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81.8 Closure Nuts, Vessel
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Locations 1-19 i
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Bl.10 Closure Washers, Vessel Visual Locations 1-19
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B1.14 Vessel Cladding C-8, CP-16 PRESSURIZER B2.1 Weld #1 from 0" to 10" UT j
l 82.1 Weld #2 from 0" to 10" UT j
B2.1 Weld #3 from 0" to 10" UT 82.1 Weld #4 from 0" to 10" UT 82.1 Weld #5 from 0" to 10" UT B2.1 Weld #6 from 0" to 10" UT B2.1 Weld #7 from 0" to 10" UT STEAM GENERATORS
B3.3 Disimilar Welds #4 and #5 UT and Surface B4.5 Welds #2, #7, #8, #9,18BC UT and Surface t
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B4.7 Welds #19, #21 and #23 Surface Within these areas the inspector noted the following:
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a.
The records for the welds listed under component figure numbers B2.1
and B3.3 were incomplete in that weld thickness dimensions were not given.
Also the records of partial examinations, as in the case of i
items 83.3 and 84.5, welds 2 and 18BC, did not fully discribe the
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r_ tion of the welds not inspected because of geometric obstructions.
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,nder partial examinations, these records indicated only the side (s)
't the weld that could not be examined.
There was no graphical or serical discription to ' quantify the position of the weld not
inspected. The inspector discussed this matter by telephone with the
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licensee's representative at the corporate office and noted that aside from the fact that Vestinghouse procedure OPS-NSD-101 required this information to be documented, such information was. vital for weld coverage determinations, third party review / evaluation, e.g.,
NRC, and future ISI inspections.
The licensee stated that these records had not been accepted by VEPC0 and agreed to look further into the matter. This item was identified as unresolved item: (339/82-12-01),
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Inadequate Description of Partial ISI Weld Examination; Incomplete Weld Dimension Information.
b.
The inspector requested the licensee to provide drawings / sketches, of basic calibration blocks used for the ultrasonic examination of vessel / pipe welds.
In response to this request the licensee stated that although these drawings existed and have been reviewed in previous inspections by RII staff, they could not be located at this time. The inspector stated that these drawings (sketches) are essential to the review and evaluation of volumetric examinations and should be on hand.
This matter was identified as inspector followup item: (339/82-12-02),
Calibration Block Drawings Unavailable for Review.
7.
Eddy Current Examination - Work Observation, Data Review and Evaluation Eddy current examination of steam generator (SG) tubes was in progress at the time of this inspection.
The examination is being conducted by VEPC0 in accordance with procedure NDE-ET-1, Rev. O, which references Regulatory Guide 1.83 and SNT - TC - 1A, supplement E.
Data interpretation was'per-formed by CONAM's level II data analyst under contract with VEPCO. The inspector reviewed the approved procedure, calibration, calibration stand-ard, equipment and personnel certifications; witnessed instrument calibra-tion with standard #59; and observed examine: ion of steam generator "C" tube R30C46 as performed from the hot leg side om er the "U" bend and down to the 7th support of the cold leg side of the generator.
Discussions with the licensee and the analyst disclosed that denting indica-tions were found throughout S.G. "C".
The condition appeared to be light in severity. and more frequent at the lower four supports.
At the close of the inspection the inspector learned that an effort was underway to locate and quar tify the denting in SG
"C".
Tubes inspected during this outage were as follows:
SG "A"
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All except those in row "1" and less than 50 tubes obstructed by ET inspection gear and other hardware.
SG "B"
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All except those in row "1"and less than 30 tubes obstructed by ET inspection gear, and other hardware.
SG"C"
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All except those in row "1" and less than 168 tubes obstructed by ET inspection gear and other hardware.
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The number of tubes inspected during the outage met and/or exceeded the requirements of North Arna's TS, Table 4.4-1 " Minimum Numt:er of Steam Generators to be Inspected During Inservice Inspection."
Within the areas inspected no violation or deviations were identified.
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