ML19322B591
| ML19322B591 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/16/1975 |
| From: | Parker W DUKE POWER CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912040619 | |
| Download: ML19322B591 (7) | |
Text
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Dunn POWER COMPANY l'owru Iluimswo 402 SouTn Cituncu Srnr.nr, CitAnwrTz, N. C. 20242 WI LLI AM O. PAR M E R, J R.
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REGULAT03 40&
TFILE COPY December 16, 1975 g
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Mr. Benard C. Rusche
' /,,*I Director of Nuclear Reactor Regulation s
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 f.
Attention:
Mr. Robert A. Purple, Chief Operating Reactors Branch #1 Re: Oconce Nuclear Station Docket Nos. 50-269, -270, and -287
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Dear Sir:
Our letter of June 23, 1975 provided a safety analysis report describing the final design of the Oconee Nuclear Station Permanent Wastc Management Facility pursuant to an agreement made in our November 27, 1973 meeting.
Your letter of October 15, 1975 requested additional items of information related to the design of this facility. Attached is our response to your j
request.
Very truly yours, w C' (
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.w WilliamO. Parker,Jh'.,g, EDB:mmb Attachment 14043 o
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7912040
RESPONSE TO MR. R. A. PURPLE'S LETTER OCTOBER 15, 1975 (1)
Item:
Provide a complete set of as-built piping and instrument diagrams (P&ID's) for the liquid, gaseous and solid radwaste systems.
The diagrams should indicate the original, and modified equipment, including instruments, interconnecting piping, and valves.
Response
The requested flow diagrams are listed below and provided as an attachment.
Those drawings marked with an asterisk show the additional equipment incorporated in the Permanent Waste Management Facility.
All other drawings show original station equipment.
PO-106A-1, revision 15 PO-106A-3, revision 12 PO-106B, revision 23 PO-106C, revision 8 PO-106D, revision 12 PO-107B-1, revision 20 PO-107B-3, revision 10 PO-107C-1, revision 20 PO-107C-3, revision 10 PO-107D-1, revision 15 "0-107D-3 revision 11 PO-!O7E, revision 20 PO-107F-1, revision 9 PO-107F-3, revision 7 PO-107G, revision 16
- P0-107H, revision 3
- PO-107J, revision 3
- PO-107K, revision 3
- P0-107L, revision 4
- PO-107M, revision 4 PO-108A-1, revision 19 PO-108A-3, revision 10 PO-108B-1, revision 11 PO-108B-3, revision 10
- PO-108C, revision 4 PO-125C, revision 4 i
(2)
Item:
Provide the process flow diagram for liquid, gaseous, and solid radwaste systems indicating the radwaste process paths used during normal plant power operation with all three units on line.
i The diagrams should show (1) the origin and/or source of radwaste into each receiving tank, (2) the major equipment, instruments, interconnecting piping, and valves, and (3) the following operating data:
(A) Input radwaste flow rates (ga.!1ons/ day) into each of the i
Low Activity Waste Tanks, Higl Activity Waste Tanks, I
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Miscellaneous Waste Holdup Tanks, and Reactor Coolant Bleed Holdup Tanks.
(B) The fraction of liquid radwaste expected to be discharged from the Condensate Monitor Tank and the Condensate Test Tank to the environment after processing.
(C) Detergent (laundry) radwaste input flow rate (gallons / day) into the liquid radwaste system and the fraction of waste discharged to the environment.
Response
The flow diagrams provided in response to Item (1) show the process flow for the liquid, gaseous and solid radwaste systems.
For data requested by (A), (B), and (C), the following information is provided:
(A)
Input radwaste flow rates (in gallons / day) into:
(1) Low Activity Waste Tank (Units 1 and 2) 520
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Low Activity Waste Tank (Unit 3) 200
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(2) High Activity Waste Tank (Units 1 and 2) 210
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High Activity Waste Tank (Unit 3) 280
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(3) Misc. Waste Holdup Tank A (Units 1 and 2) = 1790 Misc. Uaste Holdup Tank B (Units 1 and 2) = 1620 Misc. Waste Holdup Tank A (unit 3) 890
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Fusc. Waste Holdup Tank B (Unit 3) 870
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(4) Reactor Coolant Bleed Holdup Tanks (Average for each unit)
= 2100 The above waste flow values represent average, steady-state conditions gathered in November 1975 and will vary considerably depending upon unit conditions.
For example, the values of flow to the bleed holdup tanks may vary from no flow to several times the value given depending on the time of the cycle.
Beginning of cycle and end of cycle flows would be smallest while near the end of cycle flows would be the greatest.
(B)
Approximately three-fourths of the liquid radwaste processed by evaporation will enter the condensate monitor tanks and condensate test tanks as distillate.
Of that volume, 95-100% is cxpected to be discharged to the environment and 0-5% is expected to be re-used in station systems.
(C) The aierage detergent (laundry) radwaste input flow rate into the liquid radwaste system would be approximately 1,000 gallons / day.
It is expectr i that all of this water would be eventually discharged to the environment.
Please note that this is an estimated quantity and that the laundry is not presently being
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utilized.
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(3)
Item:
In your Waste Management Facility Safety Analysis Report, you have stated that the interim radwaste management system would be acceptable for permanent use with several design modifications.
Itemize the design modifications required and provide the basis for each modification.
Response
The design modifications required to qualify the present facility'for~~
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permanent use are listed below:
A.
Civil 1.
Increase the thickness of the north, west, and south walls of the room housing the evaporator condensate monitor tanks to 24 inches to meet wind and tornado loading design criteria.
2.
Extend the shield wall in the waste evaporator room to the shielding roof slab to meet seismic design criteria.
3.
Provide positive horizontal shear connections between the shielding roof slab and the walls to meet seismic design criteria.
4.
Add 12 inches of reinforced concrete to the shielding roof slab for missile protection.
5.
Tie the north wall of the valve gallery to the interior shielding walls to meet seismic design criteria.
6.
Tie the east wall of the pipe chase to the interior shielding walls to meet wind and tornado loading design criteria.
B.
Electrical l
The redundant 480 VAC circuit consisting of MCC RWJ and the 600 VAC/480 VAC auto traasformer, with associated cables and cable trays, will be added.
In addition, MCC RWH will be modified to receive power from redundant 480 VAC sources.
The modified 480 VAC system is shown on Figure 3.3-1 of the Waste Management Facility Safety Analysis Report. These modifications will be made to bring the system into conformance with Duke Power Company standards.
C.
Mechanical 1.
A portion of the piping and valves on the hot skid of the liquid waste solidification system will require replacement to meet NRC Regulatory Guide 1.26 Quality Group D standards.
2.
The following valves do not meet Duke Power Company specifications for Class G piping systems and will be replaced.
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Interim evaporator condensate return valves, a.
b.
Recirculating Cooling Water System butterfly valves RCW-299, -300, -301, -305, -306, -307.
3.
The following valves do not meet NRC Regulatory Guide Quality Group D standards (Duke pipir.g class E) and will be eplaced.
i a.
Interim evaporator condensate demineralizer chemical additional valve.
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Combination vacuum / relief valves.
c.
Miscellaneous diaphragm valves FS/1/70A/24, 25, 26, 27, 28, 30.
4.
The following valves serve as isolation valves upstream and downstream of the interim waste gas decay taaks and will be seismically qualified or replaced.
Valve Type Valve Operating Number Diaphragm GWD-196 GWD-197 N-222 GWD-227 GWD-204 6
GWD-191 GWD-199 GWD-200 GWD-205 GWD-228 N-224 GWD-194 GWD-223 GWD-211 N-226 GWD-229 GWD-214 GWD-220 Safety Relief GWD-225 GWD-226 GWD-218 Check GWD-192 GWD-195 GWD-219 Discharge Control GWD-206 GWD-207 GWD-215 5.
Piping between the interim waste gas decay tanks and the valves listed in 4 above must be seismically qualified or replaced.
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6.
The interim waste gas decay tanks will be seismically qualified.
(4)
Item: Provide complete system descriptions, process flow diagrams and P&lD's for the Liquid Waste Solidification System.
Response
Flow diagrams for the Liquid Waste Solidification System are included in the response to item 1.
A written description of the system is included in Appendix A of the Waste Management Facility Safety Analysia Report.
(5) Item: Justify that the system components and structures housing the modified liquid, gaseous and solid radioactive waste treatment systems satisfy the design guidance defined in the attached Branch Technical Position ETSB No. 11-1 " Design Guidance for Radioactive Waste Management Systems lustalled in Light-Water-Cooled Nuclear Power Reactor Plants".
Response
The system components and structures housing the modified liquid, gaseous and solid radioactive waste treatment systems will satisfy the design guidance defined in Branch Technical Position ETSB No. 11-1 with the exception that piping systems were tested in accordance with ANSI B31.1 code requirements only. The minimum test pressure of 75 psig and minimum test time of 30 minutes called for in section IVC of ETSB No. 11-1 were not implemented.
(6)
Item: Provide test data obtained and process parameters established for the Liquid Waste Solidification System to assure that there is no free liquid (uncombined water bound in the solid matrix) within the solid waste containers prior to shipment offsite.
Response
Specific test data have not been accumulated relative to free liquid within the solid waste containers. Visual inspections, however, have been made of containers prior to shipment and free liquid on the surface of the solid has not been observe <' to be a problem. Careful management of chemicals and the solidification process serves to assure proper solidification.
(7) Item: Provide a complete description of radiation monitors for the waste management facility building ventilation exhaust system.
Regulatory Guide 1.21 recommends continuous monitoring of fission and activation gases, iodine, and particulates along principle gaseous waste effluent pathways.
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Response
The radiation monitor in the radwaste facility ventilation exhaust system monitors total gaseous activity primarily for the detection of activity leakage within the facility. This system is not a principle liquid or gaseous waste effluent pathway since liquid and gaseous waste is returned to the Auxiliary Building and utilizes existing release points.
Therefore, the radwaste ventilation exhaust does not monitor iodine separately nor does it monitor particulates as mentioned in Regulatory Guide 1.21.
A sample line from the final building ventilation exhaust duct brings the air sample to a Victorcen Model 840-3 off-line effluent monitor system.
This system is made up of a Victorcen Model 841-35 sampler and a Model 843-20 beta scintillation detector. The readout for the unit is located near the waste disposal control panel in the radwaste facility, and it initiates a high radiation alarm signal to a local annunciator on the control panel. This annunciator panel initiates an annunciator alarm in the Unit 3 Control Room.
-7 133 The sensitivity of this system is 8 x 10 pCi/cc for Xe (0.34 MeV 7
Beta), and 3 x 10 pCi/cc for 85 Kr (0.670 MeV Beta).
A particulate filter is used in this gas detector to prevent contamination of the detector.
The unit also alarms on loss of sample flow as it is a continuous sample monitor.
(8)
Item:
Provide any proposed Oconee Technical Specifications considered necessary to reflect the final system design.
1
Response
in Section 7 of the safety analysis report submitted, the rupture of the facility's gaseous decay tanks is discussed. The consequences of this postulated accident is no worse than that evaluated in FSAR Section 12.
Therefore, the maximum activities to be contained in one of these tanks will be limited to 17,200/E curies, as specified in Oconee Technical Specification 3.10.5.b.
No new technical specifications are considered necessary to reflect the final design of the Permanent Waste Management Facility.
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