IR 05000280/1989015
| ML18153B765 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/31/1989 |
| From: | Belisle G, Julian C, Mellen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153B764 | List: |
| References | |
| 50-280-89-15, 50-281-89-15, NUDOCS 8906200214 | |
| Download: ML18153B765 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323 Report Nos.:
50-280/89-15 and 50-281/89-15 Licensee:
Virginia Electric and Power Company Richmond, VA 23261 Docket Nos.:
50-280 and 50-281 Faci]ity Name:
Surry 1 and 2 Inspection Conducted:
May 1-5, 1989 License Nos.: DPR-32 and DPR-37
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Approved by:
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Caudle A. Julian, Chief(;
Engineering Branch Division of Reactor Safety SUMMARY Scope
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.;,. / 0 I Date Signed This special, announced SSFI follow-up was performed to assess corrective actions taken by the licensee pursuant to Unit 1 restar Results The calculation for computing the upper intake canal inventory (ME-166) will be satisfactory providing completion of special testing to verify some assumptions used in ME-16 This special testing was scheduled for mid Ma Most hardware problems \\'/ere evaluated and either calculations or equipment installations were essentially complet Some recalculation will be required once ME-166 data is fully finalize Discussions between engineering and site personnel identified that clear lines of communication had not been fully established for incorporating engineering data into site procedures; however, updated site procedures had not been issued at the time of this inspection. Training of site personnel had not been fully established to assure that the operating staff were fully cognizant of the new operating parameter No violations or deviations were identified.
8906200214 890606 PDR ADOCK '05000280 Q
PNU
- Persons Contacted Licensee Employees REPORT DETAILS
- W. Benthall, Licensing Supervisor
- D. Christian, Assistant Station Manager, Operations and Maintenance
- W. Corbin, Project Engineer
- J. Fisher, Procedures Group
- E. Grecheck, Assistant Station Manager, Nuclear Safety and Licensing
- A. Hall, Engineering
- W. Henry, Operations
- G. Miller, Licensing Coordinator J. Price, QA Manager
- T. Sowers, Power Engineering Services Other licensee employees contacted included engineers, operators, technicians, maintenance personnel, and office personne NRC Resident Inspectors
- L. Nicholson, Resident Inspector
- J. York, Resident Inspector
- Attended Exit Interview Acronyms used throughout this report are contained in the last paragrap.
Followup On Corrective Actions (92702) SWHX Operability (1) Modifications EWR 88-538, MCR Chiller SW Differential Pressure and Temperature Instrumentation, involved installing MCR chiller SW differential pressure and temperature instrumentation for performance monitorin The work was completed in accordance with the instructions in the work package, with few deviation At the time of this inspection, the modification package had not been completed and the post modification testing had not starte EWR 89-152, CCHX SW Flow Differential Pressure Instrumentation,
- involved installing SW flow measurement instrumentation for the CCHX This EWR had not been implemented at the time of this inspectio The developed procedures appeared adequate.
(2)
Special Tests ST-235, MCR Chiller SW Flow Calibration, had not been started at the time of this inspectio The purpose of this special test is to provide baseline data on control room chiller equipment and to determine condenser performance and cleaning require-ment The test is scheduled to be run in mid-Ma Upper Intake Canal Inventory Issues (1)
Modifications EWR 89-161, CW Discharge Tunnel Vacuum Breaker Valves, evaluates CW valves for -CW discharge tunnel venting, has not been implemented at the time of this inspectio The developed procedures appeared adequat ERW 89-152 is discussed in section 2.A of this repor DC 88-33-3, Intake Canal Level Modifications, for both Units 1 and 2, completes all component installation associated with re-powering eight CW MOVs, level sensors, remote electronic enclosures, level channel relay panels, level isolation actuation logic train panels, and the associated conduit, cables, and annunciator input The modification implementation progress was hampered by the large number of field changes (66 at the time of this inspection).
The inspectors -discussed the final EWR goal with the licensee staff; however, due to the extensive revisions that have been incorporated into the modification package, no conclusion of the effectiveness of the modification was reache From the discussions with the licensee's engineering staff, the inspectors determined that the methodology used in this' modification package was accurat DC 88-34, CW Condenser Waterbox and Low Level Discharge Pipe Vacuum Breakers, involves installing vacuum breaker The CW condenser waterbox vacuum breaker va 1 ves are designed to minimize canal inventory loss by using pneumatically actuated valves that interrupt the siphon action in the main condense The CW discharge pipe vacuum breakers are passive breakers which prevent the back flow of upper intake canal water to the river by breaking the siphoning effect through the CW 1 ines at approximately the 25 foot leve (2)
Special tests ST-243~ CCHX SW Flow with Vacuum Priming Isolated, haa not been started at the time of this inspectio The purpose of this special test is to obtain data for evaluating the upper CCHX cooling capability by monitoring the differential pressure and
the water level in the heat exchanger without vacuum pr1m1ng and with the upper intake canal level at the 20 foot leve The test is scheduled to be run in mid-Ma l-ST-246, CW/SW Isolation Valve Leakage, had not been started at the time of this inspectio The purpose of this special test is to determine the leakage through service water valves 1-SW-MOV-lOIA and 1-SW-MOV-101 The test is scheduled to be run in mid-Ma ST-247, CW/SW Isolation Valve Leakage, had not been started at the time of this inspectio The purpose of this special test is to determine the leakage through service water valves 2-SW-MOV-201A and 2-SW-MOV-201 The test is scheduled to be run in mid-Ma ST-249, CW/SW Isolation Valve Leakage, had not been started at the time of this inspectio The purpose of this special test is to determine the leakage through service water valves 2-SW-MOV-202A and 2-SW-MOV-202 The test is scheduled to be run in mid-Ma ST-251, Leak Test of Condenser Inlet and Outlet Motor Operated Valves, had not been started at the time of the inspectio The purpose of this special test is to measure the leakage through each of the condenser inlet and outlet MOV The leakage from these valves will be combined with SW system valve leakage to quantify the tota1 leakage flow for the statio The test is scheduled to be run in mid-Ma ST-252, CW/SW Isolation Valve Leakage, had not been started at the time of this inspectio The purpose of this special test is to determine the leakage through each CCHX service water inlet and outlet valv The test is scheduled to be run in mid-Ma ST-255, CCHX SW Flow Instrumentation Calibration, had not been started at the time of this inspectio The purpose of this special test is to obtain base line data to determine the service water flow through each CCHX and to obtain the necessary data to calibrate the inlet service water annuba The test is scheduled to be run in mid-Ma ESW Pump Operability Issues (1) Modifications EWR 88-357, ESW Pumphouse Equipment Seismic Supports, addressed multiple concerns relating to; verifying seismic qualification documentation for pump supports, verifying seismic qualification documentation for diesel supports, verifying seismic
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qualification documentation for diesel starting batteries, verifying seismic qualification documentation for diesel starting battery supports, verifying seismic qualification documentation for diesel starting battery charger supports, verifying seismic qualification documentation for pressure indication support stands, verifying seismic qualifications for diesel exhaust piping and supports, performing walkdowns to verify small piping supports, and performing walkdowns to assure nonsafety-rel ated equipment would not impact safety-related equipment during a seismic even Associated with this EWR were multiple calculations including:
SE0-474, Revision 0, Seismically Qualified Supports for Batteries to Start Diesel Motors for Emergency Service Water Pumps; SE0-475, Revision 0, Battery Charger Support for Batteries for Diesel Motor Starter for Emergency Service Water Pumps; SE0-1180, Revision 0, Qualification of Pressure Gauge Supports - PI-SW-107A, B, and C; CE-0577, Revision 0, Pipe Stress Analysis of Emergency Service Water Pump Exhaust Line; and SE0-1182, Revision 0, ESW Exhaust Supports S88357-1-C-001, 002, 004, 005, 007, and 008 (lower level).
Most of this work had been completed an_d the calculations were adequat EWR 88-467, ESW Pump Electrical Modifications, addressed concerns relating to diesel starting battery problems, battery charger classification (nonsafety-related) and seismic qualification (not seismically qualified), preventive maintenance and battery testing not being conducted in accordance with vendor instructions, wiring of diesel controls, and EWS pump control room indication and control In order to reso 1 ve these issues severa 1 ca lcul ati ans were performed including: CE-0593, Revision 0, Seismic Qualification of Emergency Service Water Starting Batteries; CE-0602, Revision 0, Seismic Qualification of Emergency Service Water Diesel Starting Battery, Exide COM-8D-P and Battery Rack; and EE-0044, Revision 0, Electrical Equipment Qualification, Emergency Service Water System SSFI Concern The corrective action for EWR 88-467 was essentially complete and the calculations were adequat EWR 88-474, ESW Pump Strainer Modifications, addressed removing the inlet screens for the ESW pumps, adding a strainer on the 3-inch cooling line to each pump's diesel cooler to prevent diesel cooler fouling, and rerouting the 1-inch cooling line to the 90 degree gear cooler into the 3-inch line downstream of the strainer. This will prevent cloggin *
This work was essentially complete El~R 88-495, ESW Pump Instrumentation, addressed changing the existing pressure gauge line on each of the emergency service water pumps to provide venting and draining so that more accurate readings could be obtained and adding a 1-inch weld inlet with an annubar for obtaining flow measurement This work is essentially complete EWR 88-585, ESW Pumphouse Ventilation Dampers, addressed upgrading documentation for the qualification records on the damper assemblies, providing damper covers to prevent water penetration into the ESW pumphouse during a maximum postulated hurricane, provides tools and procedures for station operators to take appropriate actions in the event of postulated actuator failure (short term), and modifies the dampers for local and manual actuation (long term).
Associated with the EWR were multiple calculations including NUS-66; Revised July 8, 1968, Notes on Ventilation for Secondary Plant; NUS-144, Revision 2, Screen Wash and Emergency Service Water Pumps; and CE-0621, Revision 0, Seismic Qualification for Low Level Intake Structure HVAC Damper This work is ongoin (2)
Special Tests ST-228, ESW Pump Battery Electrical Load Verification, had not been started at the time of this inspectio The purpose of this test is to obtain starting and running amperage and voltage data. on the ESW pump diesels.The test is scheduled to be run in mid-Ma ST-231, 48 Hour Run of the ESW Pumps, was completed on February 1, 1989, and witnessed by the inspector The purpose of this test was to gather various data to determine performance characteristics for the ESW pumps, ESW diesels, ESW diesel batteries, and ESW room temperature The inspectors discussed the analysis of the test data with the licensees'
design engineering staff. The licensee concluded the ESW diesel batteries received negligible amounts of radiant heat from the operating diesel engines, and would operate in a maximum average temperature of approximately 125 degree Additionally, the test demonstrated that the 11A 11 ESW pump could not deliver 15,000 gpm, which was the basis for design calculations that were in effect at the time of the tes The licensee later discovered that the pump had an improperly sized impelle The impeller was replace There have been no subsequent tests to
- demonstrate 11A
ESW pump capacit The design required flow rate for the ESW pumps has been revised, based on additional engineering calculations and is currently approximately 16,500 gpm (reference design calculation ME-166).
This will be demonstrated by performance tests prior to unit restar ST-256, Emergency Service Water Flow Uprating Test, had not been approved or started at the time of this inspectio The purpose of this test is to obtain baseline performance data subsequent to pump refurbishmen This data wil 1 be used to develop performance curves for the ESW pumps and determine the adequacy of the design minimum submergence of 5 fee Within these areas, no violations or deviations were identifie.
Design Calculations ME-220, Structural Analysis of the Lifting Lugs on the CW Discharge Tunnel Manhole Pit Missile Shield and Its Access Cove The purpose of this calculation was to analyze the lifting lugs and access cover on the CW discharge tunnel manhole pit to determine; the actual stress, allowable stress, and the margin of safet The calculation concluded that the lifting lugs on the missile shield and access cover have a demonstrable safety factor for tension and plug tear out stres The inspectors verified the accuracy of the basic assumptions and the analytical methodolog The results appear both conservative and accurat ME-166, Intake Canal Inventory The purpose of this calculation was to evaluate and develop a minimum TS water level for the upper intake canal and to determine the maximum time allowed for operator action The results of this calculation indicated that a 23 foot upper intake canal level would be sufficient for all postulated accident scenario The calculation relied on operator actions that, at the time of the inspection, had not been incorporated into site procedure The calculation requires 3 ESW pumps to be available with a flow rate of approximately 16,500 gpm each to support the 23 foot upper intake canal leve Additionally, the calculation has additional restraints that have operational impac These have not been incorporated into other calculation The basic assumptions appeared valid; however, without performing special testing to verify the assumptions being used and incorporating the required activities into the appropriate procedures and other engineering calculations, it was not possible to determine if the conclusions reached in this calculation are valid.
- 7 ME-214, CCHX Operability with 2 Units at Power The purpose of this calculation was to define the operability parameters of the CCHXs and the upper intake canal when 2 units are initially operatin The results of this calculation indicated that operation with 2 ESW pumps is marginal if the outflow seepage and evaporation is considered and adequate if the actual ESW pump flows are use The assumption that outflow from seepage and evaporation was insignificant is invalid based on calculation ME-16 With the addition of errant assumptions and the inherent conservatism in the ca lcul a ti on, the operation with 2 ESW pumps is not adequately addresse The licensee's ability to operate with 3 ESW pumps was demonstrate Additionally, the licensee stated that a single failure is not ass urned for accidents that occur during LCO condition The calculation is preliminary and will be corrected prior to 2 Unit operatio ME-207, Operability Parameters of the CCHXs The purpose of this calculation was to define the operability parameters for the CCHX As was noted in the discussion of calculation ME-214, some of the basic assumptions for this calculation are not accurat Although this calculation references ME-166, Revision 2, as the basis for the calculation, the assumptions of out flow seepage and evaporation, along with the ESW flow rates are not consistent with the assumptions of ME-166. * The licensee's engineering staff stated the calculation would be revised to be consistent with ME-16 The calculation is preliminary and will be corrected prior to unit restar ME-0222, Component Cooling Water Heat Exchanger Operability The purpose of this.calculation was to develop a set of curves to identify the operability of CCHXs as a function of blockage percent, flow, delta pressure across the tubes, and heat transfer capacit This calculation references the assumptions in ME-207, Revision Oas the basis for the calculatio As was noted in the discussion of calculation ME-214, some of the basic assumptions for this calcula-tion are not accurat The results of this calculation defines the operational parameters for the CCHXs; however, the calculation assumptions of ESW flow rates are incorrect and when corrected, will affect the result The calculation is preliminary and will be corrected prior to unit restar ME-187, Pressure Drop Due to Marine Growth in the RSHX Inlet SW Piping Upstream of Valves SW-MOV-203.
The purpose of this calculation was to determine the potential impact to the SW flow of the RSHXs due to marine growth, The results show that a drop of approximately 3.7 percent in the RSHX flow rate is expected in both the 30 and 48 inch line These results appear to be within the capacity of the sys tern, provided there are no significant losses uncovered in other calculation CE-0577, Pipe Stress Analysis of Emergency Service Water Pump Diesel Exhaust Line With Addition of Support The purpose of this calculation was to perform a stress analysis of the ESW pump exhaust line for thermal, dead weight, seismic conditions, and check the stress against the allowables stated in USAS B31.l-1967 Cod All the stresses are within allowable stresses given in the reference cod Conclusions:
The inspectors discussed the current assumptions in the engineering calculations with the design engineering group personnel, the system engineer, the Procedure Revision Coordinator and a representative of plant managemen The discussion focused primarily on assumption discrepancies noted between interrelated design calculations and the translation of those engineering assumptions into site procedural requirement The inspectors were told that some effort would be made to coordinate the translation of engineering assumptions into station procedures; however, there would be no formal training for all of the changes with the plant operations staf Some of the changes would be formally discussed, some of the changes would be handled informally and some df the changes would be addressed by procedural changes onl The inspector expressed the concern that procedures that govern the plant operational configuration in the event of a Design Basis Accident need to reflect the envelope of conditions that are the basis of the assumption used to mitigate the accident conditio The inspector was assured by a station management representative that this would occur; additionally, all of the engineering
. calculations would use the same set of assumption Within these areas, no violations or deviations were identifie.
Proposed TS Changes The inspectors reviewed the proposed TS changes submitted to NRR on March, 27, 198 Specifically the TS changes address:
A change in the minimum circulating and service water intake canal level from eighteen feet to twenty-three fee An increase in the required number of operable ESW pumps from two to three..
- Provide operability and surveillance requirements for the new safety-related canal level actuation syste The changes requested _are consistent with Design Calculation ME-166 requirement Within this area, no violations or deviations were identifie.
Followup (92701) (Closed) Inspector Followup Item (280, 281/88-32-14):
Clarify Procedure SUADM-LR-12 Relative to Performing Safety Evaluation The initial concern was a misapplication in performing 10 CFR 50.59 reviews for changing PCT temperatures stated in 10 CFR 50, Appendix This concern was clarified in a subsequent revision to SUADM-LR-12, Safety Analyses 10 CFR 50.59/10 CFR 72.48 Reviews, dated February 26, 198 (Closed) Inspector Followup Item (280,281/88-32-24):
Incorporate MOVATS Testing for SW and CW Valve The initial concern was that not all SW and CW valves were being MOVATS teste Numerous deficiencies were previously identified, with MOVs as discussed in NRC Inspection Report Nos. 50-280,281/
89-0 Based on these deficiencies, the licensee developed an MOV Action Plan and documented this plan in a memorandum to the NRC dated April 19, 1989, Serial Nos. 89-27 T_he SW and CW valves discussed in NRC Inspection Report Nos. 50-280,281/88-32 are included in the MOV Action Pla Problems and testing associated with these valves are scheduled to be corrected prior to the respective unit startu.
Exit Interview The inspection scope and findings were summarized on May 5, 1989, with those persons indicated in paragraph 1 abov The inspectors described the areas inspected and discussed in detail the inspection finding Proprietary information is not contained in this repor Dissenting comments were not received from the license.
Acronyms cc CCHX CW ESW EWR gpm HVAC Component Cooling Water Component Cooling Water Heat Exchanger Circulating Water Emergency Service Water Engineering Work Request Gallons Per Minute Heating, Ventilating and Air Conditioning
MCR MOV MOVATS NRR PCT QA RS RSHX SW SWHX TS VB voe VP vs
Main Control Room Motor Operated Valve Motor Operator Valve Actuator Training Nuclear Reactor Regulation Peak Clad Temperature Quality Assurance Recirculation Spray Recirculation Spray Heat Exchanger Service Water Service Water Heat Exchanger Technical Specification Vacuum Breaking Volts Direct Current Vacuum Priming Ventilation System