ML20207R040
| ML20207R040 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/04/1987 |
| From: | Ainger K COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2811K, NUDOCS 8703110098 | |
| Download: ML20207R040 (3) | |
Text
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2 One FirW Nanonal Plaza Chicago IWnois
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z / Address Reply lo; Post Omco Box 767
,s U-Chca00, Illinois 80000 - 0767.
March 4, 1987 f'
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear-Regulatory Commission Washington,.DC 20555
Subject:
Byron Station Units 1 and 2 Braidwood Station Units 1 and-2 Application for Amendment to Facility Operating Licenses NPF-37_and NPF-66, Appendix A, Technical Specifications NRC Docket Nos. 50-454/455 and 50-456/457 References (a.: January 6, 1987, letter from S. C. Hunsader to H.R. Denton (b): February 11, 1987 letter-from L.N. Olshan to D.L. Farrar
Dear Mr. Denton:
1 Reference (a) transmitted a request for an amendment to the Technical Specifications that would' allow for reconstitution of a fuel assembly. -Reference (b) contained a request for additional information
.regarding this proposed amendment. Attached to.this letter are the responses to the request for additional information.
Please direct any questions regarding this matter to this office.
Very truly yours, I
K. A. Ainger.
{
Nuclear Licensing Administrator
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ATTACISBNT RESPONSE TO RBOURST POR ADDITIONAL'INFORMATION_
RECONSTITUTION OF A FUEL ASSEMBLY.
4 Commonwealth Edison should supply additional information that provides assurance of adequate radiation protection of workers during the
-reconstitution operation. Specific issues to be addressed include:
1.
The qualifications, authority and reporting level of the radiation protection manager..
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Response
The Station Health Physicist, W.A. Bielasco, is the radiation protection manager. He has a Bachelor of Science Degree in Physics and Mathematics from Purdue University.
Mr. Bielasco was an ELT in the U.S.
Navy and has nearly six years of commercial _ nuclear experience.
He-reports to the Radiation / Chemistry Supervisor in direct line organization and meets bi-weekly with the Station Manager to discuss radiation protection items. The Byron Station radiation protection manager meets Regulatory Guide 1.8 qualifications in accordance with the Technical b
~ Specification requirements.
2.
Radiation protection planning and preparations, including utilizing and learning from experience at other plants with similar operations.
Response
i Byron Station contacted Salem, Calvert Cliffs and McGuire Nuclear
_ Stations for fuel reconstitution information.
Information was received-from Salem and Calvert Cliffs Stations and was incorporated into the radiation protection planning meetings.
i' The planned radiation protection coverage. includes continuous health i
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-physics technician job coverage,'shiftly health physics supervision L
review, alarming radiation and contamination equipment, underwater dose rate equipment,-enhanced contamination control measures and minimizing of non-essential observers. Planned video taping of.the job will be performed to allow observation of the process in the non-radiologically controlled area of the plant by interested personnel.
In accordance with Technical Specifications,-the reactor will be subcritical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> before any fuel movement begins.
Before reconstitution starts, the reactor will be subcritical for approximately 30 days.
Criticality calculations performed by Westinghouse Electric Corporation indicate that an effective multiplication factor less than 0.95 will be maintained during the fuel reconstitution process, thereby assuring minimal risk of an inadvertent criticality.
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.. Physical stops (not electrical interlocks) will'be utilized to assure that no fuel rod or fuel assembly component is withdrawn closer to the surface.of the spent fuel pool than 10 feet to maintain adequate shielding for the radiation workers.
3.
The extent of coverage of the operation by trained health physics technicians.
Response
Byron Station will utilize continuous health physics technician coverage for the duration of the operation. A health physics supervisor will. review the area and controls for the job on a shiftly basis.
- 4..Any:special radiation or contamination monitoring equipment that will be utilized.
Response
Eberline equipment will be utilized on the job including an AMS-3 continuous' air monitor, an EC-4~ alarming radiation monitor, a RO ~1 underwater survey probe, hand held G-M and alpha monitors and ion chamber dose rate instruments.
5.
Estimates of worker doses; including both the maximum doses to individuals and the cumulative dose to the group.
Response
1 The reactor coolant system iodine 131 samples obtained at Byron are similar to those obtained at Salem which indicates there should be a comparable ntunber of failed fuel rods. Therefore, based on the Sales data, Byron anticipates total exposure'to be less than 2.0 man-rem and maximum individual exposure to be less than 230 mrem.
6.
Provisions for coping with potential accidents and releases.
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- Response:
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Byron Station will handle any potential accidents and releases in I.
accordance with the Generating Station Emergency Plan procedure for a i
dropped fuel assembly. A potential accident involving release of l
radioactive material during fuel reconstitution activities is bounded by l
'the current FSAR analysis for a dropped fuel assembly accident.
I 2811K l'
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