ML18130A622
| ML18130A622 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/11/1979 |
| From: | Herdt A, Vallish E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18130A621 | List: |
| References | |
| 50-280-79-35, NUDOCS 7909200181 | |
| Download: ML18130A622 (3) | |
See also: IR 05000280/1979035
Text
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Report No.
50-280/79-35
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100
ATLANTA, GEORGIA 30303
Licensee:
Virginia Electric & Power Company
P. 0. Box 27777
_ Richmond, Virginia 23261
Facility Name:
Surry Power Station Unit I
Docket No.
50-280
License No.
site near Surry, Virginia
SUMMARY
Inspection on June 20-22, and 28, 1979
Areas Inspected
7-/t) - 7'/
Date Signed
7-11-79
Date Signed
This special, unannounced inspection involved 14 inspector-hours onsite in the
area of concrete expansion anchors in response to IE Bulletin (IEB) 79-02.
Results
No apparent items of noncompliance or deviations were identified.
1.
Persons Contacted
Licensee Employees
- W. L-. Stewart, Station Manager
DETAILS
- R. Berryman, Staff Engineer-Corporate
M. D. Kamarcik, Associate Engineer-Corporate
T. A. Peebles, Superintendent Technical Services
Other licensee employees contacted included 2 technicians.
NRC Resident Inspector
- D. J. Burke
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on June 22, 1979, with
those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Concrete Expansion Anchor Bolts
The licensee's letter Serial No. 146/030879A dated June 4, 1979, was reviewed,
which describes their action in response to IEB 79-02.
A statistical sampling and inspection of 200 anchor bolts in the following
safety related systems was being accomplished at the time of this inspection:
Low Head Safety Injection FP-60 and FP-llA
Spent Fuel Pit Cooling FP-15
Safety Injection System Modification MSK-2 and 3
Residual He~t Removal FP-12
Gaseous Waste Disposal FP-18K
Pressurizer Spray and Relief FP-9E
Containment and Recirculation Spray FP-13H
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Reactor Containment Annulus Piping FP-3B
Fire Protection FP-3C
Main Steam FP-lA and 1B
Auxiliary Steam Generator Feedwater FP-2J
The scope of the inspection program is described in procedure, "Anchor Bolt
Inspection and Test Program for Hanger Baseplates and Anchors in Seismic
Category I Piping Systems Surry Power Station Unit No. 1", dated June 20,
1979.
This procedure was reviewed and includes Special Test Procedures
ST-39, ST-39-P-1 ST-39-P-2, ST-39-P-3 and ST-39-P-4 which describes the
details for inspection and testing of the different kinds of installed
anchor bolts.
The data sheets in Data Package No. 1 and the results of the inspections
were also reviewed. These sheets were from random sampling of anchor bolts
taken from the steam generator feedwater system inside the containment, the
containment recirculation spray system, the low head safety injection
system and the gaseous waste disposal system.
The licensee stated that
these data packages, will be analyized by Engineering to determine which
are "acceptable". He also stated that the results of the sampling program
will determine the future action as required by !EB 79-02.
No items of noncompliance or deviations were identified.
On June 28, 1979, further discussions were held in the VEPCO Richmond
corporate office with the licensee's engineers managing the Surry and North
Anna anchor bolt 'programs. It was pointed out that a description of the
analytical model used to verify the accounting for pipe support base plate
flexibility is required to be submitted with the response to the IE Bulletin
79-02.
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