ML14192A375
| ML14192A375 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/18/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Howe P Carolina Power & Light Co |
| References | |
| REF-GTECI-A-47, REF-GTECI-A-49, REF-GTECI-RV, REF-GTECI-SY, TASK-A-47, TASK-A-49, TASK-OR NUDOCS 8205280560 | |
| Download: ML14192A375 (8) | |
Text
Distribution:
<Docket File JHeltemes Docket No. 50-261 MAY 18 1982
\\ORB #3 Rdg DEisenhut Mr. Patrick W. Howe OELD CEIyo 0I&E (1)
Carolina Power & Light Company E5a 336 Fayetteville St.
equa Raleigh, North Carolina 27602
. SVarga CParri sh,
,7
Dear Mr. Howe :
CRS I C/
ACRS (10)
During recent conversations with CP&L we have discussed the NRC's ongoing studies to achieve resolution of UnresolvedSafety Issues (USI) A-47 ("Safety Implications of Control Systems") and A-49 ("Pressurized Thermal Shock").
As one of the eight plants involved in providing information related to A-49 (Information Request August 1981) you are an appropriate candidate for further participation in our ongoing studies.
A list of the information (Enclosure 1) about your Robinson 2 plajnt that the staff would need in pursuing these studies was telecopied to you May 13, 1982.
We also indicated that a meeting of our staff with your technical people to discuss in some detail these information needs should be held. Since your proposed date of August 1, 1982 is too late to meet our schedular needs, we request a meeting with your staff on June 3, 1982 at your Corporate offices in Raleigh, N. C. to discuss these identified information needs. It will be the purpose of this meeting to provide you with details of our information requirements.
We trust that the discussion during our meeting will provide you with the information needed for you to conclude that CP&L should participate in this program to resolve A-47 and A-49, by providing the information identified in Enclosure 1.
Detailed arrangements for the meeting will be made by Mr. G. Requa, Robinson 2 Project Manager. Thank you for your cooperation.
Sincerely, ORIGINAL SIGNED no Thomas M. Novak, Assistant Director r00' for Operating Reactors Division of Licensing 0
Enclosure:
As stated rd<C cc w/encl:
See next page D
DL:ORB#1 VDL:R n
OFFICE Aark:ms Gequg TMoa DGE s-'
SURNAME DATEI 5/ 1YI82 5/85/82
- 5.
NRCFORM31(10-80)NRCM024o OFFICIAL RECO D COPY USGPO:1981-335-960
Mr. J. A. Jones Carolina Power and Light Company cc: G. F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
Washington, D. C. 20036 Hartsville Memorial Library Home and Fifth Avenues Hartsville, South Carolina 29550 U. S. Nuclear Regulatory Commission Resident Inspector's Office H. B. Robinson Steam Electric Plant Route 5, Box 266-lA Hartsville, South Carolina 29550 Alan S. Rosenthal, Chairman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Richard S. Salzman Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dr. W. Reed Johnson Atomic Safety and Licensing Appeal Board Panel U. S. Nuclear Regulatory Commission Washington, D. C. 20555 James P. O'Reilly Regional Administrator - Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
tnciosure i ENCLOSURE 1 Information Needed i-r A-47 The following information will be needed to perform the work we have initiated at ORNL and EG&G, Idaho Falls (as defined in Task Action Plan A-47) for resolution of USI A-47, "Safety Implications of Control Systems."
Design Descriptions and/or Specifications of the automatic and manual control systems used for normal plant operation (that are not relied upon to perform any safety furctions) and the control systems that dynamically interact with the primary reactor fluid system, the secondary steam system, and the feedwater system. This information should include:
Piping and Instrumentation Diagrams (If these drawings already exist in the FSAR, then only a verification will be needed to assure that these drawings represent the final as-built design.
Function (analog and digital) Logic and Schematic Wiring Diagrams of the non-safety-grade control systems.
These drawings should include those systems supplied by the NSS vendor (or supplied by.others), that interact with the primary reactor fluid system, the secondary steam system, and the feedwater system, and also, those systems that provide support to-the plant protection systems.
Information-should include set point settings on controllers (i.e., gain, reset, alarm and trip settings).
One Line Electrical. Diagrams for on-site power systems including electrical AC and DC power systems as well as hydraulic and pneumatic power systems) that supply power to valves, pumps, motors, and to the control and the display system instrumentation. Sufficient detail should be provided to show protective relay devices (if any).
(If these diagrams already exist in the FSAR, then only verification will be needed to assure that those drawings represent the final as built design.)
Neutronic and Thermal Hydraulic 'Parameters will be needed for the computer simtulation.
This information should include (a) *selective up-to-date drawings of the core that show the.
principal dimens'ons, for example, the core length and diameter, the vessel 00's and ID's the core barrel, the thermal shield reflector thickness, and fluid inventory (in the vessel, through the core and the plena), and the effective heat transfer areas, (b) isotopic composition of equilibrium cycle core, including fuel, fission products, control poisons, and rod worth, (c) *selective major component data for (1) the turbine generator (i.e., rated steam, PT and flow rates and efficiency for each stage, rated power, and general construction of the turbines, such as, the number -of blades, nozzels, - area and angles; (2) the feedwater heater, including reheaters and moisture separators (i.e., inlet and outlet P, T and flow, capacity and efficiency; (3) pump characteristics for TCP, HPI, LPI, FEP and AFWP (i.e., curves for (a) the driven turbines, (b) HP vs flow, (c) efficiency vs. flow, pump volume and moments of inertia).
-3 In addition to the above, we anticipate the need for selected operator manuals and procedures for, (a) normal operation, such as start-up, power, and shutdown procedures that identify safety limits and pre cautions, and *(b) emergency procedures, for the loss of major components (such as turbine, reactor trip, instrument air, or service water), and procedures for remote shutdown. The specific document requests will be defined and generated (for-each plant) after initial discussions are held with the utility to determine where and how the desired information may best be found.
ENCLOSURE 2 Plant Information Needs For PTS Study A-49 The following information will be needed to perform the work we have.
initiated at ORNL/SAI.
Primary Coolant System
- 1. Any large system simulator code input decks (this gives primary system -geometry, masses) i.e..,.
RELAP 3, 4, 5 or RETRAN or CEFLASH; i.e., vendor codes or TRAC (No proprietary information is desired)
Or, if code input deck not available, need data to construct deck; i.e.:
Complete set of P&IDs for primary system
- - All sectional areas and volumes of primary coolant systems (particularly SG & RV)
- - P&IDs for HPI, LPI, and charging systems and accumulators
- 2..
Process and Operation data (pressures, temperatures, flow rates) to check code
- 3. For 3-D vessel downcomer studies, need:
Assembly drawings for core internals.(to get-detailed flow areas and component masses), vessel itself, downcomer region Cold leg nozzle geometry Details of HPI porting
-2 Secondary System
- 1. P&IDs for condensate system, FW system, steam and power production system, including turbine and condenser.
- 2. Process and operating data on secondary system (pressures, temperatures, flow rates).
- 3. Flow areas and volumes. for secondary coolant system.
Control Systems
- 1. Digital and analog logic for control systems.
- 2. Setpoints for control systems;.trip points on secondary system pumps.
- 3. If available, event trees/fault 'trees on relevant equipment.
Vessel Material Properties Pedigree on vessel and weld materials; location of welds; capsule surveillance data (probably NRC already has in 60 days reports and other documents).
- Support Systems P&IDs for the.following systems located in the auxiliary building, turbine building, and containment building:
- instrument air
- ac power dc power vital power supplies
- Emergency Procedures Abnornal transient and/or emergency operating procedures (covers SBLOCA, loss-of-FW, MSLB, etc.)
ENCLOSURE 3 Schedule for Informatfon Needs USI A-49 B&W In hand -
Oconee
- 1.
These programs are on hold pending receipt of this information. Work can begin on either plant as soon as the information is obtained. The CE evaluations for the.second plant can begin 60 days later. Unless these data are obtained in the near future, the schedules for USI A-49 will be impacted.
W July 1, 1982*
CE September 1, 1982*
GE July 1, 1982*
- The proposed schedule for USI A-47 will be impacted if these dates are not met.