ML20154S289
| ML20154S289 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/19/1986 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8604010028 | |
| Download: ML20154S289 (26) | |
Text
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UNITED STATES v8' 3.,q/[ 3.
NUCLEAR REGULATORY COMMISSION F// E WASHINGTON, D. C. 20555
..Y MAR 191986 Docket No. 50-416 LICENSEE: Mississippi Power & Light Company (MP&L)
FACILITY: Grand Gulf Nuclear Station, Unit 1
SUBJECT:
SUMMARY
OF FEBRUARY 5, 1986 SITE MEETING REGARDING SPENT FUEL P0OL STORAGE FACILITIES The purpose of the meeting was to observe the high density spent fuel racks and associated shielding walls and pools and to discuss calculations of occupational dose rates. is a list of participants. Enclosure 2 is a handout prepared by the licensee.
The licensee described the high density spent fuel racks in the spent fuel pool in the auxiliary building and in the upper containment pool in the containment building. The upper containment pool is for temporary storage during refueling.
(Enclosure 2, Sheets 3, 4, 5 and 6).
The licensee described the calculations of occupational radiation doses during storage of the spent fuel.
(Enclosure 2, Sheets 7 through 20). Calculated doses are based on placing freshly discharged fuel (with the highest radio-activity) adjacent to the pool walls. Calculated doses on the outside of the spent fuel pool walls are higher than NRC ALARA guideline values. The licensee plans to preclude loading freshly discharged spent fuel adjacent to the walls, as indicated on Sheet 9 Enclosure 2.
The licensee will calculate doses for a specific spent fuel storage pattern which will bring calculated doses outside the pool walls within ALARA guideline values. During refueling and after spent fuel is loaded into the pools, the licensee will measure radiation doses to confirm that calculated values are conservative.
The calculated doses outside the upper containment pool a e highest on the west wall (Sheet 10 of Enclosure 2). This wall is~close to the containment inside wall, however, and the high radiation area is not accessible without placing long ladders or scaffolds in this space. Doses calculated for the south wall, which is easily accessible, are within ALARA valves of 2.5 mR/hr.
(Sheet 10, Enclosure 2).
The NRC staff toured the facility to see the spent fuel pool, the upper contain-ment pool and the areas near the spent fuel transfer tube. Areas that are expected to be the highest radiation areas will be monitored during transfer of spent fuel through the tube to assure doses are ALARA.
8604010028 860319 PDR ADOCK 05000416 P
t 4
2-4 The licensee said it would provide a fuel storage pattern to maintain doses in-easily accessible areas below 2.5 mR/hr, and its plans for surveys and adminis-trative controls during refueling in a letter by March 15, 1986.
1 l
N assedly L. L. Kintner, Project Manager BWR Project Directorate No. 4 i
Division of BWR Licensing
Enclosures:
.As stated i
cc: See next page 1
1 DISTRIBUTION Decket 1ii,e; NRC PDR>"~"
Local PDR 1
PD#4 Reading WButler
]
LKintner MDuncan Young, OELD i
EJordan BGrimes ACRS(10) l NRC Participants 1
i i
4
]
Mb 1
PD# PM PD#4/D LKintner:lb WButler 03/g/86 03/0/86
1 The licensee said it would provide a fuel storage pattern to maintain doses in.
easily accessible areas below 2.5 mR/hr. and its plans for surveys and adminis-trative controls during refueling in a letter by March 15, 1986.
oridsalme etny L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated cc: See next page DISTRIBUTION Docket File f
PD*4 Reading WButler LKintner MDuncan Young, OELD EJordan BGrimes ACRS(10)
NRC Participants I
f PD# PM PD#4/D LKintner:lb WButler 03/g/86 03/ /86
4.
The licensee said it would provide a fuel storage pattern to maintain doses in easily accessible areas below 2.5 mR/hr. and its plans for surveys and adminis-trative controls during refueling in a letter by March 15, 1986.
i
- s..
L. L. Kintner, Project Manager BWR Project Directorate No. 4 Division of BWR Licensing
Enclosures:
As stated cc: See next page j
l l
i 4
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Mr. Oliver D. Kingsley, Jr.
Mississippi Power & Light Company Grand Gulf huclear Staiton
.s 2
a cc:
Rcbert B. McGehee, Esquire The Honorable Williaru J. Guste, Jr.
hise, Ccrter, Child, Steen and Caraway Attorney General P.G. Box 651 Department of Justice Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 hicholcs S. Reynolds, Esquire Bishop, Liberraan, Cook, Purcell and Reynolds 1200 17th Street, N.W.
Washington, D. C.
20036 i
Mr. Ralph T. Lally Manager of Quality Assurance Office of the Governor Middle Scuth Services, Inc.
State of Mi!Eissippi P.O. Box 61000 Jackson,liississippi 39201 hew Oricans, Louisiana 70161 Attorney General Mr. Larry F. Dale, Director Gartin Building huclear Licensing and Safety Jacksnn, Mississippi 39205 Mississippi Pcwer & Light Company Jackson, Mississippi 39205 Mr. Jack McMillan, Director P.O. Box 23054 Solid Maste flississippi State Board of Health Mr. R. W. Jackson, Project Engineer 880 Lakeland Bechtel Power Corporation Jackson, Mississippi 39206 15740 Shady Grove Road Gaithersburg, Maryland 28077-1454 Alton B.-Cobb, M.D.
State Health Officer Mr. Ross C. Butcher State Board of Health Senior Resident inspector P.O. Box 1700 U.S. Nuclear Regulatory Comission Jackson, Mississippi 30205 Route 2, Box 399 Fort Gibson, Mississippi 39150 President 1
Claiborne County Board cf Supervisors Regional Adrainistrator, Region 11 Port Gibson, Mississippi 39150
- 4 U.S. Nuclear Regulatory Comission, 1
101 t'arietta Street, N.W., Suite 2900 Mr. Ted H. Cloninger l.
Atlanta, Georgia 30323 Vice President, huclear Engineering and Support Mr. J. E. Cross llississippi Power & Light Corrpary L
Grand Gulf Nuclear Station Site Director Post Office Cox 23054 Mississippi Power & Light Company Jackson, Mississippi 39205 1 a P.O. Box 756 Port Gibson, Mississippi 39150 3
Mr. C. R. Hutchinson GGNS Cer,eral hanager Mississippi Pcwer & Lit;ht Coinpany Post Office Box 756 Port Gibson,liississippi 39150
-Enclosure 1 Attendees February 5, 1986 Meeting with MP&L NRC MP&L L. L. Kintner Rod Elms l
Mike Lamastra L. K. Daughtery i
J. L. Caldwell M. L. Crawford R. C. Butcher S. E. Thomas C. B. Franklin D. L. Marshall J. C. Vincelli F. W. Rosser i
l A. S. McCurdy l
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NRC-MP&L Meeting to Discuss High Density Spent Fuel Racks Installation Date:
February 5, 1986 Time:
9:00 a.m.
Place:
PLS Conference. Room I. Introduction / Purpose M. Crawford II. HDSFR Configuration J. Elms Spent Fuel Pool (SFP)
Upper Containment Pool (UCP)
III. Occupational Dose Rate Calculations B. Franklin Methodology Results i
IV. Proposed Administrative Controls Task Force (ALARA, possible changes, i.e.
ARMS)
S. Thomas H. P. Surveys during refueling outage J. Vince111 Refueling Procedures A. McCurdy r
V. Questions / Answers MP&L/NRC VI. Tour J. Elas b
PCOM NRC-MP&L TENTATIVE AGENDA - 1 I
s
1 HDSFR CONFIGURATION l
Spent Fuel Pool (SFP)
Upper Containment Pool (UCP)
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along the source-detector line.
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FIGURE 2-1 GEOMETRY OF THE UPPER CONTAINMENT POOL X,Y DIMENSIONS H
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