ML19339C068
| ML19339C068 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/28/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8011170439 | |
| Download: ML19339C068 (5) | |
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Docket No. 50-395 007 2 8 1930 Mr. T. C. Nichols, Jr.
Vice President & Group Executive Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281
Dear Mr. Nichols:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION 1
In our review of your responses to TMI matters, we have determined that additional information is required to enable us to complete our review.
Enclosed are requests 321.14 thru 321.16 from the Effluent Treatment Systems Branch.
We request that you provide this additional information not later than November 7, 1980.
If you cannot meet this schedule, or if you require clarification of the requests, please contact the staff's assigned project manager.
Sincerely,
$%w Robert L. Tedesco Assistant Dire: tor for Licensing Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page l
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Mr. T. C. Nichols, Jr.
Vice President & Group Executive ODI 2 6 1980 Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281 cc: Mr. William A. Williams, Jr.
Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 J. B. Knotts, Jr., Esq.
Debevoise & Liberman 1200 17th Street, N. W.
Washington, D. C.
20036 Mr. Mark B. Whitaker, Jr.
Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1. Box 93C Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o V. S. NRC Route 1, Box 64 Jenkinsville, South Carolina 29065
O REQUESTS FOR ADDITIONAL INFORMATI0t' 321.14 Additional Accident Monitoring Instrumentation (Effluent) Action Plan II.F.1 Your response regarding the above action plan is incomplete.
At this time we require clarifications and additional infonnation on the following items:
1.
Will the Hydrogen Purge exhaust be also monitored by RM-A14?
2.
In your FSAR, you have stated that, based on the process monitor RM-A9 reading, operator action will be undertaken to divert condenser air ejector releases via the main plant vent if needed. How soon will this manual diversion be completed when needed?
3.
Will the area radiation monitors RM-Gl9A, B and C that you propose to install to monitor steam dump / safety valve releases provide a dose rate range equivalent to Xe-133 equivalent concentration range of 10-l to 103 u::i/ c in the discharge? How will you correct the readings of these external monitors for low energy gammas?
4.
Describe the procedures and calculational methods you will employ to convert instrument readings to concentrations or/and release rates.
5.
Describe how you will initially calibrate these monitors and also at what frequency, you will calibrate them periodically.
6.
The additional information you are required to provide should include (a) the energy dependence of these monitors (b) the background correction to the' instrument readings, if applicable (c) how these readings will be
-._a-displayed and disseminated (d) assurance that readings can be obtained at least every.15 minutes during and following an accident.
7.
You should provide infomation on iodine and particulate effluent sampling for the main plant vent and reactor building purge releases.
321.15 Primary Coolent Sources Outside Containment - III.D.1.1 -
Your response regarding the above action is inadequate.
1.
Provide a list of the systems that you propose to test for leakage in the immediate future.
2.
Provide infomation on the continuing leak reduction program you plan to implement. The infomation should include (a) frequency of the integrated leak tests (b) method and summary of procedures
)
for testing each system or subsystem (c) steps that will be taken for minimizing occupational exposures and (d) details on the preventive maintenance steps to reduce leakage to as-low-as practical levels.
321.16 Post Accident Sampling - Action Plant II.B.3 Your response regarding the above action plan is incomplete.
1.
You should provide information on (a) time for completion of sample i
analysi: (this should not exceed 2_ hours) (b) isotopes that will be detected (c) concentration range for reactor coolant that can be sampled (d) quantification of dissolved gases in unpressurized reactor coolant samples.
. 2.
Your information should include assurance that backup sampling through grab samples will be provided for systems using in-line monitoring for samples. You should also give the frequency of such grab sampling.
3.
You should commit to (a) sampling containment atmosphere under both positive and negative containment atmosphere (b) not having to place in operation, to use the sampling systems, any system that may be isolated during an accident and (c) returning residues of sample collection to containment or a closed system.
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