ML19308D925
| ML19308D925 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/04/1974 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Moore V US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| 5179, NUDOCS 8003200674 | |
| Download: ML19308D925 (5) | |
Text
. __.
AEC DIS TEiITION FOR PART 50 DOCKET MATF"'AL-CONTROL NO:
5179 4
(TEMPORARY FORM) j FILE:
FRCH:
DATE CF DOC DATE REC'D LTR TWX RPT OTHER Florida Pover Corporation St. Petersburg, Fla.
33733 J. T. Rodgers 6-4-74 6-10-74 TO:
SM EE DR X
Hr. Moore 1 sig,ned CIASS UNCLASS PROP INFO INPUT NO CTS REC'D DOCKET NO:
1 50-302
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DESCRIPTION:
ENCLOSURES:
Ltr furnishing info concerning feedvater systems
& Elec, instrumentation & control aspects of the engineered safeguard systems.......
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DIST PER B. BUC!CLEY PLANT NAMb:
Crystal River Unit # 3 FOR ACTION /INFORMATION 6-12-74 AB BUTLER (L)
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c Mr. Voss A. Moore Assistant Director for Light
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Water Reactors, Group 2 Directorate of Licensing Office of Regulation U. S. Atomic Energy Commissiun Washington, D.C.
20545 In Re: Florida Fower Corporation Crystal River Nuclear Generating Plant Docket No. 50-302
Dear Mr. Moore:
Meetings were held between members of your staff and Florida Power Corporation (FPC) representatives in Bethesda on April 23, 24 and 25 and at the Crystal River Unit 3 site on April 29, 30 and May 1,1974. The major topics of discussion at these meetings were the Crystal River Unit 3 feedwater systems and the electrical, instrumentation and control aspects of the engineered safeguards systems and the reactor protection systems.
As a result of these meetings FPC has committed to make various modi-fications in the plant design and to provide additional information in some areas. We are currently performing activities involving system redesign, analytical calculations, design drawings revision and col-lection of information. This information will be transmitted to you and your staff for appropriate review via the submittal of revised drawings and FSAR update. We intend to have an FSAR update submitted by July 1, 1974. The final revised drawings will be submitted in accordance with the Procedure for Submittal of Supplementary Detailed Data contained in Mr. A. Schwencer's letter of May 6, 1974.
We wish to confirm at this time the agreed upon design modifications.
This will allow you and your staff to proceed with activities during this interim period with assurance that we understand your requirements and that FPC is preparing the information required to meet your schedule.
With regard to the feedwater systems, FPC agreed to the following design modifications in general. We realize that your staff must review the revised drawings in order to judge the acceptability of the implementa-tion of these generalized commitments.
517U General Office 3201 Thirty-fourtn street south. P.O Box 14042, St. Petersburg Florida 33733 813-866-5151
. 1)
Main Feedwater System - The main feedwater block valves automatic controls will be upgraded to meet the intent of the appropriate IEEE standards for safety class equipment.
In addition, upgraded automatic controls on two additional valves, one in each train, will be provided to assure an independent backup for tne main block valves. This will yield further assurance that feedwater will be isolated rapidly in the event of secondary steamline failure.
2)
Auxiliary Feedwater System - FPC has agreed to upgrade the auxi-liary feedwater system by means of several design modifications.
Bypass lines will be provided on each auxiliary feedwater train with, safety grade valves, controls and power supplies. The con-trols and power supplies to the bypassed valves also will be upgraded to meet the intent of applicable safety standards. Safety class operators will be provided for the four crossover lines, valves and remote manual safety grade controls with appropriate power supplies will be also provided.
In addition, the mechanical piping cannecting the condensate storage tank to each auxiliary feedwater train and the turbine driven auxiliary feedwater pump steam supply will be upgraded to Seismic Category I standards. To supplement these features, FPC will provide information to assure that sufficient time is available for operator action from the control room in the event that remote manual valve alignment or other action is required, i.e., the reactor system is inherently capable of sustaining loss of feedwater to the unaffected steam generator. during a steamline break accident for a reasonable time interval. These steps will preclude this system from being vul-nerable to single failure and will assure that auxiliary feedwater will be available for interim removal of core decay heat during all accident conditions.
With regard to the electrical, instrumentation and control reviews, the items of importance are listed below in general terms.
It is acknowledged that staff acceptance will depend upon review of the detailed drawings, information and method of implementation.
1)
Diesel Generators - The following items were agreed to with regard to these systems, a)
Interlocks will be provided to prevent paralleling of the diesel generators at any time, b)
Interlocks will be provided to prevent possible paralleling of the diesel generators to the off-site power system during acci-dent conditions.
c)
FPC will provide information to demonstrate capability of the diesels to operate under hurricane induced rain and flooding conditions and during operation of the fire protection system.
d)
FPC will -provide information demonstrating that the particular diesel engines are similar to others already accepted by AEC.
e)
FPC will provide information to demonstrate acceptability of the drain system in the diesel generator rooms.
. 2)
Station Batteries - The following items were agreed to with regard to the stationTatteries, a)
Calculations will be performed to demonstrate that under worst-case conditions, hydrogen generation will not represent an explosion hazard either under normal, recirculation or complete battery room isolation mode conditions. In the highly unlikely event that hydrogen evolution is deemed to make credible a hydrogen explosion postulate, FPC will evaluate the battery room's design and modify if necessary to preclude common mode failure of both battery rooms due to hydrogen explosion.
b)
Information will be provided or referenced to indicate the i
adequacy of the door connecting the rooms to resist fire.
c)
Electrical interconnection of the batteries must be prohibited.
Modifications will be made to eliminate any electrical ties.
3)
Post-Accident Instrumentation - FPC agreed to meet the AEC position that for those instruments used to monitor post-accident conditions within containment, the instrument channels must be redundant with both channels monitored and one channel recorded. This will re-quire some design modifications. Both channels are fed separately from Class 1E distribution systems.
4)
VitalBuses-Designchangeswillbemadetoeliminateanytiies between vital buses.
If an inverter fails during normal operation, the plant will be shut down in eight hours. Transfer will be allowed to a regulated bus.
5)
Fire Prottetion System - FPC will investigate possible flooding of safeguards equipment due to rupture of fire mains. Results will be reported and any required design modifications.;ill be initiated.
6)
Deca:' Heat Removal System - FPC will provide a technical specifica-tion which prohibits use of either RHR train in any mode other than its normal safety standby mode during normal operation of the plant.
7)
Offsite Power - FPC will provide additional separation of cables co'inecting the existing 230 KV substation to the Units 1 and 2 batteries.
In addition, Technical Specification surveillance requirements will be provided to assure proper operability of the sump pumps to prevent flooding of the cable tunnel.
8)
Main Steamlines - FPC will provide drawings of the proposed sleeves to divert steam from the area immediately adjacent to the reactor building to the main aree of the intermediate building in the event of steamline rupture.
s I
o 4-We feel that the meetings were extremely fruitful and hope that you will feel free to contact us for any desired discussion on the above items.
Since the unit is in an advanced stage of construction, we would appre-ciate prompt notification if you or your staff feel that the above itemization has omitted significant activities which are essential for staff acceptance of the unit with regard to the subjects discussed at the meetings.
g truly,/
You
- 'T.%vder
&un/y.w.lj.h~4:.
J. T. Rodgers
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Asst. Vice President JTR/mcm e--
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