ML19341C726
| ML19341C726 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Callaway  |
| Issue date: | 02/09/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Bryan J, Koester G KANSAS GAS & ELECTRIC CO., UNION ELECTRIC CO. |
| References | |
| NUDOCS 8103040023 | |
| Download: ML19341C726 (5) | |
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BJYoungblood ADromerick bcc: TERA MRushbrook NRC/PDR RTedesco L/PDR Docket Nos.: M RVollmer NSIC and 50-483 TMurley TIC Dross ACRS (16)
RHartfield, MPA Mr. Joh'n X. Bryan Mr. Glenn L. Koester Vice President Vice President - Nuclear i
Union Electric Company Kansas Gas and Electric Company i
1901 Gratiot Street 201 North Market Street Post Office Box 149 Post Office Box 208 St. Louis, Missouri 63166 Wichita, Kansas 76201
Dear Gentlemen:
Subject:
SNUPPS FSAR - Request for Additional Infonnation As a result of our review of your application for operating licenses we find that we need additional information regarding the SNUPPS FSAR. The specific infonnation required is as a result of the Radiological Assessment Branch's review and is listed in the Enclosure.
To maintain our licensing review schedule for the SNUPPS FSAR, we will need responses to the enclosed request by March 22, 1981.
If you cannot eet this date, please inform us within seven days after receipt of this letter of the date you plan to submit your responses so that we may review our schedule for any necessary changes.
Please contact Mr. Dromerick, SNLP PS Licensing Project Manager, if you desire any discussion or clarification of the enclosed request.
Sincerely, i
p, Robert L. Tedesco, Assistant Director for Licensing s'
Division of Licensing g\\
S 3-y Q Enclosure-g T
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Mr. J. K. Bryan Mr. Glenn L. Koester Vice President - Nuclear Vice President - Ooerations Union Electric Company Kansas Gas & Electric Company P. O. Box 149 201 North Market Street St. Louis, Missouri 63166 Wichita, Kansas 67201 cc: Gerald Charnoff, Esq.
William H. Ward, Esq.
Shaw, Pittman, Potts, MACEA Trowbridge & Madden 5130 Mission Road 1800 M Street, N.W.
Shawnee, Kansas 66205 Washington, D.C.
20036 Mr. John M. '4ylie II 4
Mr. William H. Griffin Energy Reporter Assistant Attorney General Kansas City Star State of Kansas 1729 Grand State House Kansas City, Missouri 64108 Topeka, Kansas 66612 Ms. Treva Hearn, Assistant General Counsel Kansas City Power & Light Company Missouri Public Service Commission ATTN: Mr. D. T. McPhee P. O. Box 360 Vice President Jefferson City, Missouri 65102 1330 Baltimore Avenue Kansas City, Missouri 66141 Mr. Gary Haden Wichita Eagle & Beacon Mr. Nicholas A. Petrick Box A-20 Executive Director, SMUPPS Wichita, Kansas 67201 5 Choke Cherry Road Rockville, Maryland 20850 Resident Inspector U. S. Nuclear Regulatory Commission Mr. James T. Wiglesworth, Esq.
P. O. Box 1748 9800 Metcalf Jefferson City, Missouri 65101 Suite 400 General Square Center Mr. Jay Silberg, Esquire Overland Park, Kansas 66212 Shaw, Pittman, Potts & Trowbridge 1800 M Street, N..W.
Mr. J. E. Birk Washington, D. C.
20036 Assistant to the General Counsel Union Electric Company Mr. Joe Mulholland St. Louis, Missouri 63166 Manager of Powe.- Suoply and Engineering Kansas Electric Power Cooperative, Inc.
Dr. Vern Starks P. O. Box 4627, Gage Center Station Route 1, Box 863 Topeka, Kansas 66604 Ketchikan, Alaska 99901 Mr. D. F. Schnell Ralph Foster, Esq.
Manager - Nuclear Engineering Kansas Gas & Electric Building Union Electric Comoany P. O. Box 208 P. O. Box 149 Wichita, Kansas 67201 St. Louis, Missouri 63166 1
1
REQUEST FOR ADDIT 10NAL TWFORMATION i
SNUPPS FSAR 331.0 Radiological Assessment Branch 331.1 Section 12.1.2.5.b addresses a neutron shield design at the RPV in (12.1.2.5b)econtainment. Please specify the neutron and gamma dose equivalent rates that will exist at specific locations within the various levels of containment prior to shield installation and after the shield is installed. A figure or table showing respective dose rates would be a suitable format. Describe your plan for neutron personnel dosimetry whenever an entry is made while the reactor is at power, the frequencies at which entries are made, and the number of people making these entries.
331.2 Radiation levels in excess of 100 R/hr can occur in.the vicinity of (12.2.1.3) spent fuel transfer tubes ~ therefore, all accessible portions of the trans-fer tubes must be shielded during fuel transfer. Please address the manner in which shielding, access control and radiation monitoring will be incor-porated into the radiation protection program to prevent either occupants or transient workers from receiving very high exposures during transfer of spent fuel from the reactor to the spent fuel pool through the fuel transfer tubes. Use of removeable shielding for this purpose is acceptable.
4 Provide appropriate figures (e.g. plan and elevation) that shows the shielding arrays for all direct gamma' radiation and streaming pathways from the spent fuel during the transfer. On the same figure show the location of any administrative controls by barriers, signs, audible and visual alarms, locked doors, etc. All accessible portions of the transfer
/ tubes that cannot be adequately shielded shall be clearly marked with a sign stating that potentially lethal fields are possible during fuel transfer. These markings should be clearly stated on portable shielding.
m
331.3 Describe the procedure for extracting a sample from the Nuclear Sampling (12.2.1.2.3) System of RCS, RHR and CVCS with as low as is reasonably achieveable exposures to personnel withdrawing the sample.
In your response include use of shielding, area monitoring, portable survey meters, hand contact with sample containers, dose rate levels in sampling area, dose rate level of sample container, etc. Consider sample taken during normal operations, anticipated operational occurrances and accidents. The response to this question should satisfy the requirements of NUREG-0578 item 2.1.8.a, Post Accident Sampling, with regard to Radiation Protection.
331.4 Table 12.2-7 indicates the radionuclide concentration in the spent fuel (TABLE 12.2-7) pool (SFP) water. Relevent reactor operating experience shows that the 60Co activity, from crud transferred to the SFP from the interchange of the primary Coolent water during refueling, is several orders of magni-tude greater than that shown in the table even after purification by the SFP clean-up system. Please justify the values given in the table for 60Co, 58Co I34Cs, and Co and shcw that these values will be retained 137 after several years of reactor operation. Provide an estimate of the dose rate above the SFP during a refueling operation and for the period thereafter.
Include in the estimate the effect on the dose rate of any radioactive equipment that might be stored therein.
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l 331.5 Please clarify how iodine radioactivity levels can be " inferred from the (12.3.4.2.2.2.2) particulate and noble gas radioactivity levels" when monitoring the exhaust from the radwaste and auxiliary buildings as addressed in section 12.3.4.2.2.2.2 and 12.3.4.2.2.2.4.