ML17339B223
| ML17339B223 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/23/1980 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUDOCS 8007310509 | |
| Download: ML17339B223 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 JULY 2 3 580 Leo.&< ~ i~
Docket No. 50-250 50-251 LICENSEE:
FACILITY
'UBJECT:
FLORIDA POWER AND LIGHT COMPANY (FPL)
TURKEY POINT PLANT UNIT NO.
3 AND 4
SUMMARY
OF PHONE CONVERSATION HELD ON JULY 10, 1980 TO DISCUSS QUESTIONS REGARDING THE RADIOLOGICAL ASSESSMENT OF THE STEAf4 GENERATOR REPAIR BACKGROUND The Turkey Point Plant Steam Generator Repair Report was revised (revision
- 7) on March 28, 1980.
This revision included a significant change in the method of cutting the steam generator
- loose, The Radiological Assessment Branch (RAB) review led to some questions concerning the details of the change.
These questions were forwarded in draft form to FPL to enable the FPL staff to begin the preparation of the responses.
The RAB reviewers also requested a site visit in conjunction with the meeting to clarify questions.
Due to budget limitations the site visit was postponed until.
this fall.
In order to expedite the review the questions were discussed by phone to clarify the intent.
Participants are identified in attachment 1.
The draft questions are presented in attachment 2.
SUMMARY
OF PHONE CONVERSATION The questions in attachment 2 were discussed.
The intent of the questions was indicated along with the extent of the response needed for the staff review.
guestions 10, ll, and 12 will be clarified further by the staff on Monday, July 21, 1980.
All other questions were clarified to the extent necessary to permit adequate response.
A meeting is tentatively scheduled for July 21, 1980 in case'urther clarification is necessary.
In addition a site visit will be held this fall.
marshall Grotenhuis, Project Mana Operating Reactors Branch 81, Division of Licensing soovaxo Sop P
Page 2
Meeting Summary for Turkey Point Plant Unit No.
3 and 4
Docket Files NRC PDR Local PDR NSIC TERA ORBI Reading NRR Reading H. Denton E. Case D. Eisenhut R
Purple T. Novak R. Tedesco G. Lainas G. Zech S. Varga T. Ippolito R. Clark R. Reid B. J.
Youngblood A. Schwencer J. Miller-D. Crutchfield J.
Wetmore Project Manager OELD OSD (3)
S.
- Showe, ISE C. Parrish.
R. Fraley, ACRS (16)
Principal Staff Participants Licensee Short Service List cc:
Elizabeth S.
Bowers, Esquire.
Chairman Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Coamission Washington, D. C.
20555 Dr. Emeth A. Luebke Atomic Safety and Licensing Board
~
Panel U. S. Nuclear Regulatory Comnission Washington, D. C.
20555
-Mr ~ Mark P. Oncavage 12200 S.
W. 110th Avenue Miami, Florida 33176 Neil Chonin, Esquire New World Tower Building, 30th Floor 100 N. Biscayne Boulevard Miami, Florida 33132'enry H-Harnage, Esquire Peninsula Federal Building, 10th Floor 200 S. E. First Street Miami, Florida 33131 Dr ~ Oscar H. Paris Atomic Safety and Licensing Board Panel U. S. Nuclear Regulatory Comaission Washington, D. C.
20555
Attachment 1
Participants in the July 10, 1980 Conference call to clarify questions NRC M. Grotenhuis J.
Minns
~h1 1
P. Holton
- 0. Williams FPL R. Kaninsky L. Rodriguez J.
Sheetz H. Story S. Pearl
331-1 Attachment 2
331.
0'31.
1 RADIOLOGICAL ASSESSMENT Describe how you will incorporate the following provisions of Regulatory Guide 8.8, Revision 3, tune 1978, in the steam gener-ator replacement project.
C.2 a.
b.
Co d.
e.f.
go h.
lo J ~
Facility and Equipment Design Features sections all subsections (2), (3), (5). (7), (8).
(1O)
(2), (3)
(1), (2, (4), (6) al 1 subsections (1). (2), (3) all subsections (8)
(>>), (>>)
shielding by maintaining the steam generator water level when pos s ib 1 e.
331. 2 331. 3 331. 4 Revise section
- 3. 3.4. 2 to include a ccmmitment to implement a
bioassay program in accordance with Regulatory Guide 8.9, "Acceptable Concepts,
- Models, Equation, and Assumptions for a Bioassay Program," or equivalent alternative.
Provide a copy of your analysis resulting in person-rem estimates for the mechanical and electro-polishing decontamination, cutting of the divider plate, cutting the steam generator channel head and the steam generator blowdown piping and upper dome.
This should include for each':
I (1) a detailed procedure outline (2) the time and personnel involved in the job (3) dose rate estimated in the area where the job will be perfo rmed (4) total man-rem to complete job.
Provide the basis for the decontamination factor (DF) of 12 on page 3.17.
331. 5 Provide a description of your contamination control program including:
(1) Limits for demarcation of controlled surface contamination
-areas and for release of equipment and facilities for unre-stricted use (acceptable limits are listed in Regulatory Guide 1..86, "Termination of Operating Licenses for Nuclear Reactors,"
or equivalent alternative).
A
331-2 (2) methods of restricting contamination to controlled surface contamination areas.
331-6 331-7 (3) specification of skin dose evaluation criteria including action points for dose evaluation.
Provide a breakdown of the person-rem for the 'project, dividing the doses into four,phases -- preparation; removal, installation and storage.
In the event of a large volatilization accident with the decontamination solution at Turkey Point, what precautions have been taken to assure safe habitability or evacuation of the workers in the steam generator areas:
(1) how will the workers in other areas be notified of such an event; (2) what protection is afforded to the workers; and (3) what procedures will be followed in the event of, such an accident?
Mhat is the estimated dose to workers for such an accident' 331. 8 Provide a description of the radiation protection training program for outside contractor personnel working in restricted areas.
331. 9 Describe your administrative control system to assure that worker dose will be kept within the limits of Part 20 and will be maintained ALARA.
331.10 331. 11 331. 12 Describe the new facilities for the project, including locker
- rooms, shower
- rooms, access control stations, laboratory facili-ties for radioactivity analyses, and decontamination facilities (for equipment and personnel).
Indicate in a table the radiation protection equipment that is provided during this operation to meet the anticipated needs of the operating unit (for normal and accident conditions) and the steam generator repair project.
Include in the table the types of instruments, their numbers, sensitivities, and ranges.
In
- addition, include a table specifying the quantity and types of respiratory. protection equipm nt avail able.
Describe the organization and staffing necessary to provide the radiation protection program for the steam generator replace-
.ment.
Identify by title the individuals, who will be responsible for the program and describe their functional responsibilities, experience and qualifications.
e 331-3 331. 13 331. 14 331. 15 Describe the reasons for the estimated increase from 1301 man-rems/
unit to 2985 per unit.
Your application specifies that a substantial portion of your AlARA program is written in the FPL Health Physics Manual.
Provide a copy of the FPL Health Physics Manual.
1 Describe the cutup and handling for alternatives a,
b and c in Table 3.4-3.
It should include items 1-4 in ques'tion-4.
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