IR 05000280/1978031
| ML18113A747 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/15/1978 |
| From: | Robert Lewis, Skolds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18113A746 | List: |
| References | |
| 50-280-78-31, 50-281-78-31, NUDOCS 7901020220 | |
| Download: ML18113A747 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.: 50-280/78-31 and 50-281/78-31 Docket Nos.: 50-280 and 50-281 License Nos.: DPR-32 and DPR-37 Licensee: Virginia Electric and Power Company P. 0. Box 26666 Richmond, Virginia 23261 Facility Name:
Surry Units 1 and 2 Inspection at: Surry Power Station, Surry, Virginia Inspection conducted: October 16-19, 1978 Inspector: J. L. Skolds Approved by: ~.C. ~
R. C. LeJis,ciiief Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on October 16-19, 1978 (Report Nos. 50-280/78-31 and 50-281/78-31)
Areas Inspected:
Routine unannounced inspection of maintenance; followup of licensee event report and followup of previous enforcement matter The inspection involved 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> on site by one NRC inspecto Results:
Of the three areas inspected, no items of noncompliance or devia-tions were identified.
7901 o 2 o 2:; *
RII Report Nos. 50-280/78-31 and 50-281/78-31 I-1 DETAILS I Prepared by,:::;;:2 ~k. J. L. Skolds, Reactor Inspector Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspection: October 16-19, 1978 Reviewed by:
l;.C-. ~
R. C. Lewis, Chief Reactor Projects Section No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted Virginia Electric and Power Company (VEPCO)
- * * * * * * *,'. * Baucom, Station Manager Stewart, Superintenden4 Station Operations Nicholls, Supervisor, Electrical Maintenance Taylor, Supervisor, Mechanical Maintenance Johnson, Supervisor, Engineering Services Rentz, Station Resident Quality Control Engineer Snoberger, Assistant Superviso4 Instrument Maintenance Tower, Supervisor, QA, Operations and Maintenance Wilson, Operating Supervisor Dewandel, Administrative Assistant
- Denotes those present at exit intervie Licensee Action on Previous Inspection Findings 11/;sf7B Date (Closed) Noncompliance (280/281/78-16-06): Failure to follow procedure while performing safety related maintenanc The inspector reviewed completed safety related maintenance procedures and verified that personnel signing the procedure were the same personnel performing the wor Unresolved Items None identified during this inspection.
RII Report Nos. 50-280/78-31 and 50-281/78-31 Exit Interview I-2 The inspector met with licensee representatives as indicated in para-graph 1 at the conclusion of the inspection on October 19, 197 The inspector summarized the scope and findings of the inspection and discussed the open item.
Maintenance The following safety related maintenance documentation was reviewed:
MR N Title S2801291852 Low alarm (CH-358)
S280172670 Replace check valve S1802161316 Change Capacitors & Clean S1802161318 Change Capacitors & Clean (Battery S1804030715 Noise in #1 DG S1804190815 PMS on Static Inverters S1804201207 Install/Remove Primary Manway SI804201307 Body to Bonnet Leak S1804241151 Excessive Leakage during PT 1 SI804242200 Valve Leaks by Seat SI804250400 Valve Leaks through (HOV 1286A)
S1804250401 Valve Leaks through (HOV 1286C)
S1805110724 Body to Bonnet Leak & Repack (HCV-1311)
S1805111430 Repack and Replace Gland Studs (MOV 1700)
S1805151404 Replace Body to Bonnet Gasket SI-91 Char_ger)
- RII Report Nos. 50-280/78-31 and 50-281/78-31 S1805160900 S2805251901 S1806190720 S1806201700 S1806292340 S1807011300 S2807011521 S1807012301 S2807091335 S1807260100 S1808241830 SI0181610 I-3 Replace Valve (MOV-1869B)
Repair circuit on panel ll-4C Leaking Relief valve (RV-1203)
Repack MOV-RH-100 Discharge Flange Leaking Find Block in BIT Recirc Valve Difficult to Operate (2-CH-208)
Repair HT Replace Bonnet (l-CH-94)
Rebuild GAST Vacuum Pump Valve body leaking (BR-203)
Replace Diaphragm (l-CH-309)
The maintenance was reviewed to verify that:
The limiting condition for operation was met while components or systems were removed from service for maintenance The* maintenance activities were accomplished using approved procedure by qualified personnel The maintenance activities were functionally tested or calibrated as necessary prior to returning the component or system to service The required administrative approvals were obtained prior to initiating maintenance activities The maintenance activities were inspected in accordance with the licensee's requirements The inspector used one or more of the following acceptance criteria for the above items:
ANSI 18.7-1972 Technical Specifications
,
RII Report Nos. 50-280/78-31 and 50-281/78-31, I-4 Nuclear Power Station Quality Assurance Manual Topical Report, Quality Assurance Report (VEP-l-3A)
Regulatory Guide 1.33 Findings were acceptable with the exception of the items noted belo Maintenance Procedure MMP-C-V-001.1 (General Valve Maintenance -
Grinnell Valves) was reviewed by the inspector. It waa noted that the procedure utilized Quality Control Inspection sheets to accomplish certain checks in the procedur Examples of these checks included inspecting the valve for cleanliness, checking to insure insulation is not covering the bonnet and that heat tape was removed from the bonne The activities documented on the QC Inspection sheets did not constitute a Quality Control inspection and, therefore, in many cases the same person performing the maintenance also performed the inspection for cleanliness, insula-tion and heat trac The inspector felt that continued use of the QC Inspection sheets to document non-QC activities could lead to a situation where the same person that performs the maintenance would also perform a QC Inspectio This item will remain open (78-31-01) pending inspection of additional safety related mainte-nanc Section 17.2.6 of the Quality Assurance Program Topical Report (VEP-l-3A) states that a copy of the maintenance report for safety related maintenance is sent to the Quality Control staff for notification purpose The QC staff may then initiate an audit program as necessar At present, a computerized system for recording maintenance is in effect and a copy of the maintenance report is not being sent to Q The QC staff is being notified prior to the commencement of all safety related maintenanc This i tern will remain open (78-31-02) pending future inspection of the Topical Quality Assurance Repor Review of Nonroutine Events Reported by the Licensee The inspector reviewed licensee actions with respect to the following listed nonroutine event reports to verify that the events were reviewed and evaluated by the licensee as required by Technical Specifications, that corrective action was taken by the licensee and that safety limits, limiting safety system settings and limiting conditions for operation were not exceeded. The inspector examined selected Operations Committee meetings, licensee investigation reports, logs, records, and interviewed selected personne *
,
RII Report Nos. 50-280/78-31 and 50-281/78-31 I-5 Control Room Emergency Air Supply Leak LER 78-15, Unit 2 No items of noncompliance or deviations were identifie Heat Tracing Circuit Failure LER 78-16, Unit 2 No items of noncompliance or deviations were identifie Accumulator Low Level, LER 78-22, Unit 1 Upon reviewing this LER, the inspector noted that the maintenance report generated due to the faulty relief valve indicated that the relief valve was replaced with a new valv The LER states
"The hydro test pump and relief valve were vented and checked for set point. Subsequent test of the relief and pump was satisfactor_y."
This statement in the LER indicates that the relief valve that originally failed was tested and placed back in the syste Actually, a new valve was placed in the system as the Maintenance Report state The licensee committed to send a revised LER (78-31-03).