ML20009B397
| ML20009B397 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 07/08/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8107150365 | |
| Download: ML20009B397 (7) | |
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DISTRIBUTION:
JUL 8 1981 Docket File -
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LB#1 Rdg TERA DEisenhut PDR JYoungblood LPDR KKiper NSIC Docket Nos.: STN'50-45LSTN50-455 MRushbrook TIC RTedesco ACRS (16) and STN 50-456, STN 50-457'.
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TMurley Mr. J. S. Abel RMattson G
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Director of Huclear Licensing' RHartfi' eld, MPA p3 Comonwealth Edison Company
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Chicago, Illinois 60690
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Dear Mr. Abel:
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Subject:
Request for Additiona.1,Infomation, fpr,,t.he Byron /Braidwood Sai.dts%%
Review In the course of our review of. the. Byron /Brai,dwood FSAR, we have identified the need for addiMonal information regarding your radiation protection program. This request for information is, included, as, Enclo.sure 1, items 331.24 through 331.35.
In order to maintain our present, review sc.hedu,le,.we request that you respond to the enclosed items within six weeks of. receipt.of. this letter.
If you require clarification or discussion.of..the enclosed request, please. contact the Project Manager for Byron /B' aidwood, Kenne,th.L. Kiper,. (301). 492-7318.
r Sincerely, original *isn.d by R.abert L. Tode Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosure:
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Mr. J. S. Liei Oircctsr of Lcic r Liccr,str.;
Comonwealtn Edison Company
- Post Office sex 767 Chicago, Illinois-60690
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Mr. William Kortier Mr. Edward R. Crass Atomic Power Distribution Nuclear Safeguards and Licensing Division-Westinghouse Electric Corporation Sarger.t & Lundy Engineers P. O. Box 355 55 East Monroe Street Pittsburgh, Pennsylvania 15230 Chicago, Illinois 60603
. Paul M. Murphy, Esa' Nuclear Regulatory Commission, Region III -
Isham, Lincoln & Beale-Office of Inspection and Enforcement One First National Plaza 799 Roosevelt Road 42nd Floor-Glen Ellyn, Illinois 60137 Chicago, Illinois 60603 Myron Cherry, Esq.
Mrs. Phillip B. Johnson Cherry, Flynn and Kanter 1907 Stratford Lane 1 IBM Plaza, Suite 4501 Rockford, Illinois 61107 Chicago, Illinois 60611 Professor Axel Meyer Department of Physics Northern Illinois University DeKalb, Illinois 60115 C. Allen Bock, Esq.
P. O. Box 342 Urbanan, Illinois 61801 Thomas J. Gordon, Esq.
Waaler, Evans & Gordon
'2503 S. Neil Champaign, Illinois 61820 Ms. Bridget Little Rorem 4
Appleseed Coo'rdinator 117 North Linden Street Essex, Illinois 60935 Kenneth F. Levin, Esq.
Beatty, Levin, Holland, Basofin & Sarsany 11 Sout.h LaSalle Street Suite 2200 Chicago, Illinois 60603 m
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331.0 Radiological Assessment Branch 331.24 Based on information contained in fiUREG-0731 " Criteria fer Utility (13.1)-
Management and Technical Competence,"'it is our position that the radiation protection group should oe a separate organization from the chemistry group.
Your station organization chart (Figure 6.1-2) shows the radiation protection and chemistry technicians combined.
Additionally, in accordance with Regulatory Guide 8.8, it is our position that the Rad-Chem Supervisor (RPM) should have access to the Station Superintendent in all radiation protection matters.
In matters related to radiological health and safety, the RPM has direct responsibility to both employees and management that can best be fulfilled if he is independent of station divisions, such as operations, maintenance or technical support, whose prime respon-sibility is continuity or improvement of station operability.
Your FSAR should be revised to outlira how your plannt i radiation protection program reflects this position.
Concurrent to the changes requested above, Figure 6.1-2 should show that on radiation protection matters, the Rad-Chem Supervisor has access to the Station Superintendent and the radiation protection technicians and chemistry technicians become separate groups.
In addition the technicians should be qualified separately as chemistry and radiation protection technicians, and each ranort directly to their respected group supervisor.
331.25 In accordance with tha criteria contained in NUREG-0731, it is our position (13.1) that your organization chain should contain a qualified individual to provide backup in'the event of the absence of the Radiation Protection Manager (RPM).
The December 1979 revision of ANSI 3.1 specifies that individuals temporarily filling the RPM position should have a B.S. degree in science or engineering, two years experience in radiation protection, one year of which should be
. nuclear power plant experience, six months of which should be on-site.
It is our position that such experience should be professional experi-Identify and provide an outline of the qualification of the ence.
individual who will act as the backup for the RPM in his absence.
331.26 Table 13.1-2 of your FSAR states that you will fill the position of (13.1)"
Rad-Chem Supervisor 45 months prior to core loading.
Your Technical Specifications will require your Rad-Chem Supervisor to meet the criteria for Radiation Protection Manager as specified in Regulatory Guide 1.8.
You should provide a resume of the education, training, and experience of the individual selected to fill this position as soon as it is available.
331.27 Section 13.1.3.1 of the FSAR states that "an individual will be (13.1) considered qualified as a radiation-chemistry technician in a respon-sible position after completion of the onsite radiation-chemistry technician training program, and a total of one year of general power plant, chemistry, or. radiation protection experience or equiv-alent training." Your Technical Specifications will require that your plant staff meet the qualification of ANSI 18.1.
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standard requires two years experience in radiation protection before an individual is considered qualified as a radiation protection technician. 'If you wish to propose an alternative qualification program for your radiation technicians, you should provide a detailed description of the qualification program.
Otherwise, your FSAR should be amended to show radiation technician qualification per ANSI 18.1.
331.28Property "ANSI code" (as page type) with input value "ANSI 18.1.</br></br>331.28" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. Your portable radiation monitoring instrument list in Table 17. 5-2 (12.5) show no instrument capable of measuring dose rates greater than
-100 R/hr.
Instruments capable of measuring 10,000 R/hr are neces-sary to determine radiation levels following a THI-type accident.
Regulatory Guide 1.97 (Revision 2) specifies that portable survey meters and the area radiation monitors in areas requiring access after an accident should have a range up to 10,000 R/hr.
Provide a commitment in your FSAR to have such portable radiation monitoring instruments and specify locations of area radiation monitors in accessible post-accident areas.
These monitors should be capable of measuring dose rate up to 10,000 R/hr.
331.29 Provide information on the quantity and types of respirators (12.5) provided for Byron /Braidwood Station in accordance with the guidelines of Regulatory Guide 1.70, Section 12.5.2.
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a 331.30 Verify that your program for internal radiation exposure assessment (12.5.
-(whole body counting, and bioassay programs) meets the criteria of 5.3)
Regulatory Guide 8.26, " Applications of Bioassay of Fission and Activation Products" or outline equivalent alternatives.
331.31 Verify.that your air sample calibration program meets Regulatory (12.5)
Guide 8.25 or outline an equivalent alternative.
331.32 Provide additional information on how your exposure tracking and (12.5) exposure reduction program, includes the elements of Regulatory Guide 1.70, Section 12.1.3 and 12.5.3, and Regulatory Guide 8.8, Section C.3.9(8)(j), C.3.8(2), and C.3.c(2)(5), including rem-tracking, self-reading pocket dosimeter use, post-maintenance, actual exposure, and how these results are used to make changes in future work.
Verify that annual exposure reviews are performed by plant management and that these are used to identify groups with the highest exposure in order to assure that doses are ALARA.
331.33 Provide additional information regarding the sensitivity of (12.3.
airborne radioactivity monitors in accordance with Section 1.3 of 4.2)
Verify that the airborne radioactivity monitors described in Section 12.3.4 of the FSAR are capable of detecting 10 MPC-hours of particulate and iodine radioactivity in compartments which may be occupied and may contain airborne radio-activity (the acceptance criteria in Standard Review Plan Section 12.3).
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331.34 Explain how the Byron /Braidwood Station will implement a chemistry
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. (12.3):
control program to reduce radiocobalt production and crud buildup in normally radioactive systems.
(See~ Regulatory Guide 8.8,
.Section C.2.e(3)).
331.35 Provide the information requested in II.B.2, II.F.1(3), and II.D.3 of NUREG-0737, " Clarification of TMI Action Plan Requirements."
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