ML19318B054
| ML19318B054 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/11/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Crews E SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8006240624 | |
| Download: ML19318B054 (8) | |
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20655 a
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JUN 11 1980 Docket No.:
50-395 Mr. E. H. Crews, Jr.
Vice President and Group Executive Engineering and Construction South Carolina Electric and Gas Company P. O. Box 764 Columbia, South Carolina 29218
Dear Mr. Crews:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (VIRGIL C. SUP91ER NUCLEAR STATION, UNIT NO.1)
To continue our review of your application for a license to operate the Virgil C. Summer Nuclear Station, additional infonnation is required.
The information requested is described in the enclosure and covers the area of radiological assessment.
Please inform us after receipt of this letter the date you anticipate providing an answer.
Sincerely,
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A. Schwencer, Acting Chief Licensing Branch 3 Division of Licensing
Enclosure:
As stated ccs: w/ enclosure See next page 8006240(gLN
cc: Mr. H. T. Babb General Manager - Nuclear Operations
& System Planning South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 G. H. Fischer, Esq.
Vice President & Group Executive South Carolina Electric & Gas Ccmpany P. O. Box 764 Columbia, South Carolina 29218 Mr. William C. Mescher President 8' Chief Executive Officer South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 Mr. William A. Williams, Jr.
Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 Wallace S. Murphy, Esq., General Counsel South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 Troy B. Conner, Jr., Esq.
Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Mr. Mark B. Whitaker, Jr.
Manager - Nuclear Licensing South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 m
cc: Mr. O. W. Dixon, Group Manager Production Engineering 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 /SPS c/o U. S. Nuclear Regulatory Commission P. O. Box 1047 Irmo, South Carolina 29063 4
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6 331.0 RADIOLOGICAL ASSESSMENT BRANCH 331.33 Your description of the " Improved In-Plant Iodine Instrumentation" in NUREG-0578.2.1.8.C is incomplete., Your,FSAR should be amer.sd to describe "in-area capability" of the instrument.
Specify the number and type of sampler,s, sample media, sample flushing methods, sample analysis equipment type and location and procedures and training in the use of the systems.
Sample results must be available within 10 minutes after the sample is taken.
There should be sufficient samplers to sample all vital, areas.
Theisample analysis equipment must be located in a low background area.after Januany 1,.1981&
331. 34 Provide a summary of the shielding design review required by our letter dated November 9,1979, implementing the Lessons Learned item 1#
2.1.6.b of NUREG-0578, and provide a description of the results of this review.
Include in your description:
a.
source terms used in the evaluation (NUREG-0578 specified that source terms in Regulatory Guide 1.3, 1.4 and 1.7 be used).
b.
systems assumed to contain high leve?s of radioactivity in a post-accident situation including, but not limited to, containment 4
residual heat removal, safety injection CVCS, demineralizers, charging systems, reactor coolant filters, seal water filters, sample lines, liquid radwaste systems, and gaseous radwaste systems. If any of these systems or others that could contain high radioactivity were excluded, explain why such systems were excluded from review.
You should verify that direct radiation from1 field.run piping and scattered radiation' (such as shine over shield walls) were included in the analysis.
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c.
specify areas where access is considered necessa.y for vital system operation after. an. accident..Your evaluation of areas to determine the necessary Vital areas should include but 'not be a
limited to, consideration of the control. room Technical Support Center, Operational Support Center, recombiner hookup and control stations, hdrogen purge control stations, containment isolation reset control area, sampling and sample analysis areas, manual ECCS alignment area; motor. control centers, instrument panels, emergency power suppliep, securityicenter and radwaste control panels.
If any of these areas were not considered areas where access was necessary after an accident, explain why they are excluded.
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d.
Designation of the codes used for analysis, such as ORIGEN, IS0 SHIELD, QUAD or others.
The projected doses to individuals for necessary occupancy times e.
in vital areas.
f.
A brief description of the proposed plant modifications resulting from the design r " jew and confirmation that these modifications will be complete by full power operation.
331.35 Provide a description of the two high range containment monitors required by our letter of November 9,1979, implementing the Lessons Learned item 2.1.8.b of NUREG-0572. and specify the location of these monitors
. (inside containment)._ The description of the monitors should include:
e a.
type of radiation measured; b.
the range of ranges of the monitors.
If two.or more. monitors are required.to. span the. range. in Table 2.8.1.b.3 of our November 9,1979 letter (108 7
rad /hr total radiation or 10 R/hr photons only), the ranges of the subsystem monitors must overlap (i.e., upper value/ lower value of overlap) by at least a factor of 10; 10 location of and type.of readout. (continuous ~and. recording).
c.
d.
energy response (sensitive to 60 kev);-
'Ealibration frequency and methods (refueling frequency);
e.
' f.
verification that the monitors are powered separate vital instru-ment buses; g.
verification that the monitors will be operational by full power; h.
Verification that the monitors meet the seismic qualifications of Regulatory Guide 1.100 (5eismic Category I) and are environmentally qualified to survive.in an containment LOCA in accordance with A
The location of the monitors should be shown on plant layout drawings.
The monitors should be located in a manner as to provide a reasonable assessment of radiation levels inside containment. 14onitors should not be placed in areas which are protected by massive shielding.
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4-331.36 Section _13.2.2.3 specifying Shift Crew Composition, does not state that an HP technician will. be onsite:at all times.
" Criteria for Preparation. and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of' Nuclear Power Plants,"
requires that a radiation protection technician be onsite at all times.
Section 13.2.2.3 should be revised accordingly.
331.37 Your F5AR should be amended to provide a description of the radiation protection features incorporated in the system for sampling and analyzing reactor coolant and containment atmosphere in accordance with Lessons Learned requirements.
331.38 Revis6iTable 12.3-3 to include the quantity and types of respiratory protection equipment available during normal operations, accident conditions and major outages requiring supplemental workers.
i 331;39 The plant organization chart in Figure 12.3-1 and 13.1-5 shows the Health Physics Supervisor reporting through the Technical Support
-Supervisor to the. Assistant Plant Manager.
The " Draft Criteria for Utility Management and Technical Competence" specific that the Radiation Protectica Manager (RPM) described in Regulatory Guide 1.8 and equivalent to your HP Supervisor shall report directly to the Assistant Plant Manager.
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Regulatory Guide 8.8. "Infonnation-Relevant to Ensuring Occupational 4
Radiation Exposures.at Nuclear Power Stations be As low As Is Reasonably Achievable",_ states that the RPM should be ' independent of-the technical I
support division. and should have ! direct recourse to the plant manager in order to resolve questions relating to the conduct of the radiation protection program.
It is our position that the HP Supervisor report directly to thd Assistant' Plant Manager.'3 :Your' FSAR and" proposed Technical Specifications.should be. revised accordingly t
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