IR 05000280/1980006
| ML18139A254 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/08/1980 |
| From: | Burke D, Andrea Johnson, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18139A253 | List: |
| References | |
| 50-280-80-06, 50-280-80-6, 50-281-80-08, 50-281-80-8, NUDOCS 8005230399 | |
| Download: ML18139A254 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/80-06 and 50-281/80-08 Licensee: Virginia Electric and Power Company Richmond, VA 23261 Facility Name:
Surry Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Inspection at Inspected Approved SUMMARY Inspection on March 4-7, 1980 Areas Inspected Virginia L/-L-1-~
Date Signed
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Date Signed This special, announced inspection involved 48 inspector-hours on site in the area of small break LOCA, emergency procedures, training and operator knowledg Results Within the areas inspected, no items of noncompliance or deviations were identifie '9 Q
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DETAILS Persons Contacted Licensee Employees
- J. L. Wilson, Superintendent Operations
- R. F. Saunders, Superintendent Maintenance
- G. E. Kane, Operating Supervisor
- F. L. Rentz, Quality Control
- M. R. Kansler, Engineering Supervisor
- H. L. Miller, Supervisor Nuclear Coordinator
- E. P. Dewandel, Staff Assistant Other licensee employees contacted included shift supervisors, assistant shift supervisors and control operator NRC Resident Inspector
- D. J. Burke
- Attended exit interview Exit Interview The inspection scope and findings were summarized on March 7, 1980, with those persons indicated in paragraph 1 abov Inspection findings presented in these details were discussed including licensee commitments in paragraphs 6 and.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Small Break Loss of Coolant-Operator Interviews The inspectors reviewed and discussed, with licensee plant management,
- their emergency procedure EP-2.0 "Loss of Reactor Coolant".
Westinghouse guidelines, procedure development, procedure content, and reactor operator training given to terminate or mitigate the consequences of small break loss of coolant accident (SBLOCA) were also discussed.
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-2-Upon completion of the above plant management interview, the inspectors interviewed five licensed operators, which included one shift supervisor (SRO), one assistant shift supervisor*(SRO), and three reactor operators (SRO's and RO's).
The licensed operator interviews were performed to determine the adequacy of the appropriate procedures from a functional standpoint and the effec-tiveness of the training Progra The following areas were covered: Understanding of small break LOC Differentiation between loss of coolant accidents (LOCA's) and other depressurization event Familiarity with the SBLOCA procedure Operator knowledge of appropriate related procedure Knowledge of transient response characteristics necessary to guide the licensed operator to the correct procedur Evaluation of any individual or generic deficiencie Walk-throughs of the procedures including system-related aspects of the procedures to ensure that the licensed operator actions could be performe Confirmation that appropriate procedure immediate actions were memorize Understanding of procedure subsequent actions and precautions that ensure plant safet Ability to determine break location Recognition of the importance of primary and backup heat sink.
Ability to recognize adequate subcooling and core voiding, importance of subcooled versus saturated conditions, indications of inadequate core cooling and implementation of natural circulatio Recognition of possible instrumentation abnormalities including those encountered during the TMI transient and environmental consideration.
Procedure Adequacy Based on the operator interviews in the above areas, the inspector dete.rmined that the licensee's SBLOCA procedures were adequat However, based on
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,, licensed operator interviews, walk-throughs of the SBLOCA and other reactor coolant depressurization events the following procedure changes should be considered in emergency procedure EP-2.0, Loss of Reactor Coolant: Revise Unit 2 procedures (SBLOCA) to reflect changes _similar to those for completed Unit 1 procedure The licensee agreed to complete the procedure changes prior to the Unit 2 startu Step 4.53, page 9 requires dispatching an operator to restore power at the breaker similar to step 4.51 and needs to be reflected as done in step 4.5 The licensee agreed with this observation and will take appropriate actio Compile a notebook of licensee-collected data of environmental effects on critical instrumentation and place this notebook in or near the control room for operations us The licensee agreed to take this recommendation (c) under advisment as to possibly adding this to the Shift Technical Advisor's packag These items (a through c) will be carried as.an open item, pending future inspections (280/80-06-01 and 281/80-08-01).
Small Break Loss of Coolant and TMI Lessons Training The inspectors reviewed licensee training on the SBLOCA procedures to verify that training included transient analysis and a walk-through of procedures in the control room by each licensed operator and senior opera-to In addition, training.records were reviewed to confirm that all licensed personnel had attended training sessions that had been completed prior to the inspectio Based upon review of the training program, in conjunction with operator interviews, the inspectors determined that the licensee's training program was adequate in the areas inspecte However, the following should be considered for additions to the training program:
The licensee had.completed the majority oftheoperator procedure training and walk-through before this inspectio The licensee stated that the remainder of the training and walk-throughs would be completed by April 30, 1980, which is prior to Unit 1 or Unit 2 startu *This item will be carried as an open item, pending future inspections (280/80-06-02 and 281/80-08-02).
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-4-Small Break Loss of Coolant-System Considerations The inspectors reviewed system-related aspects of procedures to verify that operator actions required subsequent to an SBLOCA could be performe System considerations in the following areas were reviewed: Instrumentation to carry out operator actions i_n the SBLOCA procedur Power operated relief valVe position indicatio Equipment response to safety injection rese Safety injection effects on containment isolatio Real-time consideration of SBLOCA procedure actions, including adequate time to switch over from injection to recirculation mode Protection of high head safety injection pump against deadheading in the recirculation mode No problems were identified with system consideration reviewe,,;.