IR 05000280/1979059
| ML19253C488 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/25/1979 |
| From: | Burke D, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A260 | List: |
| References | |
| 50-280-79-59, 50-281-79-78, NUDOCS 7912050624 | |
| Download: ML19253C488 (4) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 M ARIETTA ST N.W., SUITE 3100 p,
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ATLANTA, GEORGIA 30303 s
Report Nos. 50-280/79-59 and 50-281/79-78 Licensee: Virginia Elcctric and Power Company Richmond, Virginia 23261 Facility Name: Surry, Units 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Inspection at Surry Si e ar ur, Virginia Inspector:
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Date Si'gned Approved by:
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P. J /Kel gS Chief, RONS Branch Da'te Si'gned j
SUMMARY Inspection in September 10-28, 1979 Areas Inspected This routine inspection by the resident inspector involved 60 inspector-hours onsite in the areas of plant operations and maintenance, including the Unit 2 steam generator replacement outage work, followup on previously identified items, and plant security.
Results Of the four areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees Virginia Electric and Power Company (VEPCO)
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- W. L. Stewart, Station Manager
- J. L. Wilson, Superintendent, Operations
- T. A. Peebles, Superintendent, Technical Services
- R. F. Saunders, Superintendent, Maintenance R. M. Smith, Supervisor, Health Physics G. Kane, Operating Supervisor
- F. L. Rentz, Resident QC Engineer
- D. A. Christian, Engineering Superviaor Other licensee employees contacted during this inspection included control room operators, shift supervisor, QC, engineering, HP, plant maintenance, security, engineering, and administrative personnel.
- Attended exit interview 2.
Management Interviews The scope and findings were summarized on a weekly basis 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 daring this inspection.
5.
Unit 2 Steam Generator Replacement Activities The inspector reviewed certain U-2 SG replacement and associated activities to verify that the activities were performed in accordance with the Steam Generator Repair Program (SGRP) and applicable procedures.
The review included the following activities:
a.
Inspection tours of the Unit 2 containment for cleanliness and radiation control; appropriate work and radiation controls were being implemented.
b.
Observation of inspections and work being performed on the Unit 2 pipe supports to satidy IE Bulletin 79-14.
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-2-t Within the areas inspected, no items of noncompliance or deviations were identified.
6.
Unit I and 2 Operations and Maintenance Unit I remains shutdown pending resolution of NRC questions regarding IE Bulletin 79-14 (As-built piping systems verification). The inspector toured the Unit I and 2 control rooms and certain plant areas to verify
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that the shutdown operations were in accordance with the Technical Speci-fications and facility procedures.
Plant logs, maintenance and records were also reviewed. Within the areas inspected, no items of noncompliance were identified. Specific areas of inpsection included:
In addition to verifying that a qualified ASCO solenoid operated pilot a.
valve (NP Series) was installed on Unit I containment sump isolation valve (TV-DA-100A), the inspector reviewed Design Change 79-522 testing which verified sump isolation upon initiation of safety injection.
b.
Followup on LER 280/78-04, which addressed the temporary loss of service water (SW) flow through charging pump intermediate seal cooler 1-SW-E-1B due to failure of the discharge gate valve.
Corrosion of the valve stem permitted the valve disc to drop and obstruct one train of SW flow. Following an engineering study (78-08), the licensee replaced all 1 1/2 and 2 inch valves in the Unit 2 system with bronze ball valves; Unit I valve replacement is scheduled to be completed during the next major outage. A successful hydrotest was performed on the Unit 2 system following maintenance; however, on September 27, 1979, the inspector noted some leakage from valve 2-SW-129 flange.
The licensee is taking corrective action on the apparent leak.
Ler's 280/78-04 and 281/78-11 are closed.
A walkdown of the plant high and low level liquid waste drain tank c.
went piping from the tanks to the process vent system, utilizing FM-80A and 90B prints. No discrepancies were identified. The inspec-tor noted that the tanks lead open overflow piping to the local floor drains in the auxiliary building tank rooms. Licensee evaluation determined that the systems which deliver liquids to the tanks would be off gassed and would not vent gases through the overflow lines.
d.
Review of the Unit 1 inside recirculation spray (IRS) pump and motor testing following maintenance which included replacement of the lower motor bearing. After rebuilding, the IRS (1-RS-P-1A and IB) pump motors were successfully tested at the North Anna facility for 8 and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> respectively before reinstallation at Surry.
GE motors EHJ524018 (IA) and EHJ524019 (IB) were installed in Unit I and periodic test 17.2 was performed to verify pump operability.
LER 280/79-09 remains open pending conrrective action on Unit 2.
e.
Review of emergency procedures to verify that the reactor coolant pumps are tripped upon initiation of high head safety injection caused by low reactor coolant system pressure; the procedures have been revised in accordance with IE Bulletin 79-05C and 79-06C.
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Review of Unit 1 Periodic Tests 17.1, Containment Spray System, PT 17.3, Containment Outside Recirculation Spray Pumps PT 18.1, Low Head SI Test and Flushing of SS Piping and PT 38.8, Chemical Additon Tank Sampling, performed between May and September, 1979, in accordance with TS 4.5, 4.11, and 4.1.
No discrepancies were identified. The chemical additon tank sodium hydroxide concentration was between 19 and 22%, as required by PT 38.8 (TS 18%).
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Observation of certain anchor bolt inspections performed in Unit 1 containment in accordance with IE Bulletin 79-02.
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7.
Plant Physical Protection The inspector verified the following by observation:
a.
Gates and doors in protected and viatal area barriers were closed and locked when not attended.
b.
Isolation zones described in the physical security plans were not compromised or obstructed.
Personnel were properly identified, searched, authorized, badged and c.
escorted as necessary for plant access control.
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