ML15238A648
| ML15238A648 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/24/1982 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| REF-GTECI-A-47, REF-GTECI-SY, TASK-A-47, TASK-OR NUDOCS 8209100010 | |
| Download: ML15238A648 (7) | |
Text
Gray File ORB#4 Rdg Docket No.:
50-269 LB#1 Rdg. (2)
DLBasdekas MRushbrook Szukiewicz SChesnut Rlngram Mr. H. B. Tucker TNovak AOD Vice President SHanauer Nuclear Production Department Atorney DELD Duke Power Company 422 S. Church Street OIE Charlotte, North Carolina 28242 PWagner JStol'z
Dear Mr. Tucker:
DEi senhut ACRS (16)
As you know, we are in the midst of conductin a research program to assess the safety implications of control systems, and have selected the Oconee-1 plant as one of the specific plants in this effort. Although we have substantial as-built design and operation information on Oconee-I, we do not have all the information we will need, particularly on the Integrated Control System, associated support systems, and plant process system parameters.
While our discussions regarding your full participation in this effort have not come to a final conclusion, we have decided that in order to complete this work in a timely manner, wie must continue it on the basis of the best information available to us.
lie have, therefore, decided to proceed, using the information that we have, and where information is missing, using what we believe is representative of Oconee-1.
To date, we have had to nake several assumptions and estimates as described in the attached list. These estimates were made by our contractor, Oak Ridge National Laboratory, based on existing information on Babcock and W.ilcox reactors, and from information received in conjunction with efforts to resolve Unresolved Safety Issue A-49.
This information is provided to you in advance to allow you opportunity for comment.
We will keep you advised as our program proceeds, and, in particular, as we find it necessary to make further assumptions and estimates.
Sincerely, P,
gnnedbl Dearr l
M r. Tuck er:w Darrell G. Eisenhut, Director 8209100010 820824 fie e
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Enclosure:
List of Assumptions and Estimates
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DISTRIBUTION:/
Document Control (50-269)
NRC PDR LPDR NSIC Docket No.: 50-269 TERA LB#1 Reading!'
ACRS (16)
Mr. H. B. Tucker MRushbrook/.
DEisenhut Vice President SChesnut Nuclear Production Department TNo
/
Duke Power Company SHanauer 422 S. Church Street KRGol 16r Charlotte, NC 28242 BE
Dear Mr.-Tucker.,
/
As you know, we are in the midst of conducZtfng a research program to assess the safety implications of control systems/. and have slected the Qconee-1 plant as one of the specific plants in this effort. Although we have substantial as-built design and operation informati n on Oconee-1, we do not have all the information we will need, particularly on the Integrated Control System, associated support systems, and plant process system parameters.
While our discussions regarding your full participation in this effort have not come to a final conclusion, we/'have decided that in order to complete this work in a timely manner, we must continue it on the basis of the best information available to us. We have, there~ore, decided to proceed, using the information that we have, and where inform *fion is missing, using what we believe is representative of Oconee-1.
To date, we have had to make sveral assumptions and estimates as-described in the attached list. Thes estimates were made by our contractor, Oak Ridge National Laboratory, based on existing inforimation on Babcock, and 9Iilcox re~\\tors, and from information recet'ved in conjunction with efforts to resolve USI,A-49,.
This information is prov/ded to you in advance to allow you opportunity for comment. We will keep ou advised as our program proceeds, and, in particular")
as vie find it necessary to make further assumptions and estimates.
Sincerely, Darrell G. Esenhut, Director 7
~Division of Licensing Office of Nuclear Reactor--Regul ati on
Enclosure:
List of Assuri tions and Estimates
- See Deiois yellow.
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL R EGORD COPY USGPO: 198133-96
DISTRIBUTION:
Document Control (50-269)
NRC PDR L PDR NSIC Docket No.:
50-269 TERA LB# 1Reading A torney, OELD Mr. William 0. Parker, Jr.
MRushbrook I&E Vice President SChesnut ACRS (16)
Steam Production TNovak Duke Power Company SHanauer DEisenhut 422 S. Church Street KRGoller Charlotte, NC 28242
Dear Mr. Parker:
As you know, we are in the midst of conductipg a research program to assess the safety implications of control systems,/and have slected the Oconee-1 plant as one of the specific plants in this effp'rt.
Although we have substantial as-built design and operation informatio on Oconne-1, we do not have all the information we will need, particularly n the Integrated Control System, associated support systems, and plant process system parameters.
hile our discussions regarding yoyr full participation in this effort have not come to a final conclusion, w have decided that in order to complete this work in a timely manner, we must continue it on the basis of the best information available to us. We have, therefore, decided to proceed, using the information that we have, and where info ation is missing, using what we believe is representative of Oconee-1.
To date, we have had to R
ke several assumptions and estimates as described in the attached list. W will keep you advised as our program proceeds, and, in particular, as e find it necessary to make further assumptions and estimates.
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Regulatory Reactor
Enclosure:
List of Assumptions and Estimates OR:PDLLBM O
DL:AD/L DL:DIR OFFICE SURNAME SChes n t PWa'ager JStolz TMNovak SHanauer KRGoller DEisenhut DATE9/
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NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD CO PY USGPO: 1981-3i5-960
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orrison Duke Power Company
. Wenzinger 422 S. Church Street D. Basdekas Charlotte,. NC 28242
Dear Mr. Parker:
As you know, we are in the midst of conducting a earch program to assess the safety implications of control syst
, and that we want to use the Oconee-1 plant as one of the specific ants in this effort.
Although we have substantial as-built desig and operation information on Oconee-1, we do not have all the info tion we will need, particu larly on the Integrated Control System, ssociated support systems, and plant process system parameters.
While our discussions regarding y r full participation in this effort have not come to a final conclu on, we have decided that in order to complete this work in a tim y manner, we must continue this work on the basis of the best inf mation available to us. We have, there fore, decided to proceed, ing the information that we have, and, where information is miss g, what we believe is "representative" of Oconee-].
To date, we have had o make the attached list of assumptions and estimates. We woul like to request that you review this list and let us know if the are correct for Oconee-1. If not, would you please provide u with the correct information on Oconee-1, so that our analyses an conclusions will more accurately reflect reality for Oconee-1.
Your assis -ce in this matter is appreciated.
Sincerely, Karl R. Goller, Director Division of Facility Operations Office of Nuclear Regulatory Research nclosure: List of Assumptions and Estimates B RB 3/82 ICB:DFO:RES IC S.IQ.
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Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 33189 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Oconee County Library 501 West Southbroad Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Regional Radiation Representative EPA Region IV 345 Courtland Street, N.E.
Atlanta, Georgia 30308 William T. Orders Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock &.Wilcox Nuclear Power Generation Divisi-on Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 1200 17th Street, N.W.
Washington, D. C. 20036
ESTIMATES/ASSUMPTIONS FOR PARAMETERS USED IN ORNL MODEL OF OCONEE UNIT 1 Core and Vessel Avg. flow area per pin
.1774 in2 Hydraulic diam of flow area
.2388 in Hydraulic diam of downcomer 1 ft Hydraulic diam of lower plenum 1 ft Hydraulic diam of upper plenum 4 ft Pressure losses (drag and form)
Vessel 20 psi Steam generator 40 psi Total primary loop 80 psi Main feedwater pump 2
Moment of inertia 60- lb-ft Rated head 2260 ft Rated torque 7350 lb-ft 3
Rated density 62.3 lb/ft Control system BTU limit:
The BTU limit is determined by a weighted sum of reactor outlet
-2 temperature (TH), feedwater temperature (TF), and steam generator pressure (PSG) times normalized reactor coolant flow (WRC) as shown by, BTU limit =
(THL +
TFL +
PSGL 200) (WRCL/100)
- where, THL% 3.44(TH-5750F),
TFL (TF-100 0 F)/9 +
60, 105 PSG = 1000 psi, PSGL
=
105
- l1(PSG-1000)/25; 1000<PSGS1125 psi, 50 PSG 1125
- psi, and WRCL
=
105 WRC Feedwater demand:
The feedwater demand (WD) is altered by the value of feedwater temperature in order to reduce effects on plant state by changing water temperature. The following relations are used to obtain a correction factor (FC) for the feedwater demand based on feedwater temperature (TF):
=
f(WD)
AT
=
TF -
TIC FC
=
1 + AT/1000.
Where the desired feedwater temperature TIC is determined by the following conditional equation, 200 + 53 x 10 6 (WD) 06.0 $1.83 x 10 lbs/hr WD 297 +
32.7 X 106 (WD -
1.83 x 106):
1.83 x 106.< WD 2.92 x 106 326 + 17.1 X 106 (WD - 2.92 X 106):
2.92 X 106< WD-e 5.14 X 106 400 +
9.78 X 106 (WD -
5.14 X 106):
5.14 X 106.< WD