ML20247B778
| ML20247B778 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/18/1989 |
| From: | Baxter T GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| CON-#389-8927 OLA, NUDOCS 8907240205 | |
| Download: ML20247B778 (9) | |
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DOCKEI C lif M u July 18, 1989; 1:
UNITED STATES OF AMERICA NUCLEAR ~ REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND L JENSING APPEAL BOARD-In the' Matter of-
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-GPU NUCLEAR CORPORATION
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Docket No. 50-320-OLA
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(Disposal of Accident-(Three Mile Island Nuclear
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Generated Water)
Station, Unit 2)-
)
CERTIFICATE OF SERVICE I hereby certify that copies of GPU Nuclear. Corporation l
1 letter-4410-89-L-0067/0469P, June 7, 1989, to the NRC, and GPU 8
Nuclear Corporation letter 4410-89-0035/0474P, June :8, 1989, to.
2 the Pennsylvania Department of Environmental Resources, were served upon the parties identified on the attached Service List by deposit in the U,".
Mail, first class, postage prepaid, this 18th day of July, 1989.
m Thomas A.
Baxter, P.C.
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8907240205 890718 -
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 1
BEFORE THE ATOMIC SAFETY AND LICENSING APPEAL BOARD In the Matter of
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GPU NUCLEAR CORPORATION
)
Docket No. 50-320-OLA 4
)
(Disposal of Accident -
f (Three Mile Island Nuclear
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Generated Water)
Station,-Unit 2)
)
SERVICE "IST
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Thot3s S. Moore, Esquire Dr. Oscar H. Paris Atomic S3fety and Licensing Atomic Safety and Licensing Appeal Panel Board Panel U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C.
20555 Stephen H. Lewis, Esquire Christine N. Kohl, Esquire Colleen P. Woodhead, Esquire Atomic Safety and Licensing Office of the General Counsel
' Appeal Panel U.S. Nuclear Regulatory Commission U.S. Nuclear. Regulatory.
Washington, D.C.
20555 Commission Washington, D.C.
20555 Docketing and Services Branch Secretary of the Commission Mr. Howard A. Wilber U.S. Nuclear Regulatory Commission Atomic Safety and Licensing Washington, D.C.
20555 Appeal Panel U.S. Nuclear Regulatory Adjudicatory File Commission Atomic Safety and Licensing Board Washington, D.C.
20555 Panel Docket U.S. Nuclear Regulatory Commission Peter B. Bloch, Esquire Washington, D.C.
20555 Atomic Safety and Licensing Board Panel Richard P. Mather, Esquire U.S. Nuclear Regulatory Department of Environmental Commission Resources
. Washington, D.C. 20555 Commonwealth of Pennsylvania 505 Executive House Mr. Glenn O. Bright Harrisburg, Pennsylvania 17120 Atomic Safety and Licensing Board Panel Ms. Frances Skolnick L
U.S. Nuclear Regulatory 2079 New Danville Pike Commission Lancaster, Pennsylvania 17603 Washington, D.C.
20555
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Ms. Vera L. Stuchinski 315 Peffer Street Harrisburg, Pennsylvania 17102 Mr. Lee H. Thonus U.S. Nuclear Regulatory Commission P.O.
Box 311 Middletown, Pennsylvania 17057
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GPU Nuclear Corporation duclear m'ar,stx*o a
Middletown, Pennsylvania 17057 0191 717 944-7621 TELEX 64 2386 W'riter's Direct Dial Number:
(71'7-) 948-8400 June 7, 1989 4410-89-L-0067/0469P US Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Dear Sirs:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Processed Water Disposal System Technical Evaluation Report Attached are the GPU Nuclear responses to your reauest for additional Information regarding the Processed Water Disposal System Technical Evaluation Report, as forwarded by your dated May 31, 1989.
Sincerely,
/s/ M. B. Roche M. B. Roche Director, TMI-2 JJB/ emf Attachment F. I. Young - Senior Resident Inspector, TMI cc:
W. T. Russell - Regional Administrator, Region I J. F. Stolz - Director, Plant Directorate I-4 L. H. Thonus - Project Manager, TMI Site GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
j 4410-89-L-0067
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NRC QUESTION 1 i
i
'On pages 6 and 10 of your letter, you address the use of differential pressure gauges associated with the K PA filter system and drum enclosure. How often L
eill these pressure gauges be read and logged and how will you assure filter changeout before excessive filter. loading?
i GPU NUCLEAR RESPONSE i
The drum enclosure blower and associated EPA filter system will be operated i
only during processes involving transfer of dried solid waste nsterial. This till entail operation for periods of about two to three (2-3) h)urs at a time
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at a frecuency of no more than twice per day. The operating procedure for j
solids trensfer will recuire blower startup prior to discharge of dried waste
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from the blender / dryer into the packaging system. The procedure also will r:auire that the operator verify filter differential pressure is witnin specifications on initial startup of the blower and that it is checked hourly j
during blower operation..The procedure will reouire a minimum differential
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pressure of 0.5 inches WG and replacement of the filter before the a
differential pressure exceeds 9.0 inches WG.
In addition, the procedure will reouire that drum enclosure differential
. pressure with respect to building ambient pressure is at least 0.1 inches WG negative and that pressure differential is monitored hourly.
NRC QUESTION 2 Periodic monitoring of system parameters and visual inspection for leaks by the operators is mentioned several times in your referenced letter (pages 10, 12, 19). What is the maximum time interval between the operator's surveillance of the system during operation?
GPU NUCLEAR RESPONSE Operating procedures will recuire tnat operating parameters are read and logged hourly.
This activity will reouire a tour of all areas of the evaporator building. Thus, the system will reovire operator surveillance at hourly intervals.
ADDITIONAL INFORMATION In GPU Nuclear letter 4410-89-L-0038, dated April 17, 1989, the response to NRC Question 2 noted that the volume of the transfer tank is 130 gallons with a normal operating level of 40 to 90 gallons. GPU Nuclear was informed by the v:ndor in early May 1989 that the volume of the transfer tank had been increased to 275 gallons. Tne normal operating level of this tank is still expected to be between 40 and 90 gallons. The increased size of the tank provides additional surge volume to preclude an evaporator shutdown if operational problems cause minor delays in blender / dryer cycles. This results in minimal impact on the evaluation of the consequences of potential spills from the system.
T *l 4410-89-L-0067 ATTACHENT.
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In~' addition, GPL1 Nuclear stated in the response to NRC Question 8 that.the drum enclosure erhaust blower had a capacity of 250 SCFM. -On May 31, 1989,.
GPU Nuclear was: informed by the vendor that the exhaust blower is being replaced with ora havirg a capacity of 600 SCFM as originally stated in our; technical evaluation report.
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k OPU Nuclear Corpswation UC Mr Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84-2386 Wnter's Direct Dial Number:
(717) 948-8400 June 28,1989 4410-89-0035/0474P Mr. Hartwin Weiss, Chief Pennsylvania Department of Environmental Resources Bureau of Air Quality One Ararat Blvd.
Harrisburg, PA 17110 Dear Mr. Weiss
Subject:
Three Mile Island Nuclear Station, Unit 2 (THI-2)
TMI-2 Request for Determination of Minor Significance (25 PA Code, Section 127.14(8)) or, Alternatively, Issuance of Plan Approval (25 PA Code 127.11)
The purpose of this letter is to confirm the GPU Nuclear plan to use the proposed evaporator system for disposal of the Accident-Generated Water (AGW) and provide additional information to assist in your review of our subject request. GPU Nuclear reaffirms its present intent to use the evaporator system only for disposal of AGW.
As detailed in our original request, GPU Nuclear committed to operate the ovaporator system'in a mode such that the concentration of contaminants in the cffluent from the evaporator system, with the exception of tritium, will be reduced to a concentration of 1/1000 of the influent (i.e., a DF of 1000 or a 99.9% removal efficiency). GPU Nuclear has committed to the NRC to assure that an acceptable effluent, based on a DF of 1000, is achieved on a quarterly average basis and operation of the system will be in accordance with procedures that have been approved by NRC. In order to assure that che desired removal efficiency is achieved, GPU Nuclear intends to take the following actions.
Initially, upon installation of the evaporator on-site, GPU Nuclear will perform a testing program using a non-radioactive surrogate to ensure the system operates as designed. After surrogate testing, the initial startup and processing of AGW will be in a decoupled mode with no release to the cnvironmcht through the vaporizer until GPU Nuclear ensures the evaporator is l
operating satisfactorily.
GPU Nucleat Corporation is a subsidiary of the General Public Utilities Corporation L_______
w at-C 1Mr. C iss' ' Ane 28,1989 -
4410-89-0035 l
- During processing of AGW, the specific batch of water to be' processed will be risolated. The source tank, normally one of the 500,000 gallon Processed Water
' Storage Tanks (PWSTs),Lwill pe recirculated to assure homogeniety and
- sampled. A chemical and radiochemical analysis'of the sample for the
. principal constituents will.be performed. The analyses to be performed will include a gamma scan; gross alpha count; determination.of Strontium-90,-
Carbon-14, and Tritim concentrations; pH; conductivity; and baron and sodim
. concentrations.
Once processing from a PWST has begun, a sample of the water will be collected-from that. tank after every 100,000 gallons of processing. The tank will be recirculated periodically to ensure representative samples are obtained. If processing AGW from a' smaller source tank, samples will be drawn at intervals cquivalent to-20% of tank volume, but not more often than daily. Analyses to be performed on these samples include a gamma scan; gross alpha count; d; termination of Strontium-90 concentration; pH; conductivity; and boron and sodium concentrations. The analytical results will generally be availaale to the operations staff in 4 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after sample collection.
During processing, the system effluent will be sampled and analyzed for boron
- at 12-hour intervals. The sample results will generally be available within about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and will be used to calculate the overall system 0F. 'The boron cnalysis can detect baron concentration down to a level of 1 ppm. In addition, a sample of the effluent will be collected every 2 days and analyzed for Strontim-90 (LLD(1.1 E-7 uCi/ml), Carbon-14 (LLD<1.0 E-7 uCi/ml), and Cesium-137 (LLDC3.7 E-8 uCi/ml). The analytical results will generally be available within about 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Due to the natural volatility of boric acid, baron will be used as a conservative indicator of the removal efficiency of the evaporation process.
Subsequent;to the surrogate testing program and initation of the normal AGW processing, the 12-hour boron samples will be used to calculate a 96-hour rolling average of. removal efficiency exclusive of non-representative system operation (e.g., startup, shutdown, or malfunction). If the system average
' perfomance drops below a DF of 1000 (99.9% removal efficiency) or if a
- condition should exist which,'in the judgement of GPU Nuclear, is such that a Shour. average DF of 1000 cannot be re-established, releases to the environment through the vaporizer will be terminated, the system will be placed in a decoupled or shutdown mode and the Commonwealth will be notified telephonically, Releases to the environment through the vaporizer will not recommence until the cause of the lower mmoval efficiency can be determined and appropriate corrective action has been taken.
' GPU Nuclear will provide the Commonwealth with a detailed report of the
-ovaporator system operability as demonstrated by the surrogate testing L
program.
In addition, GPU Nuclear will provide the Commonwealth a monthly report on evaporator system operations based on an agreed upon femat. A detailed description of the radiation monitor to be installed to monitor vaporizer influent will be provided as part of the surrogate test program
- r port.
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Mr. Weiss June 28, 1989 l ;-
4410-89-0035 On the basis of the information previously submitted and the additional operating conditions defined above, GPU Nuclear requests a favorable determination that the proposed evaporator system is a source of minor significance.
Sincerely,
/s/ M. B. P.oche M. B. Roche Director, THI-2 J.JB/ emf cc:
T. Gerusky - Director, PA Department of Environmental Resources - BRP s - g J. Proctor - Legal Consultant - Bishop, Cook, Russell and Reynolds
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