ML15223A737
| ML15223A737 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/02/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8106100049 | |
| Download: ML15223A737 (4) | |
Text
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J 0J 2 1981 mDsT
.T.QnnN TERA-2+1 PWagner NSIC RIngram NRC PDR-3 ORB#4 Rdg OELD L PDRI DEisenhut AEOD JStolz IE-3 Dockets Nds. 50-269, 50-270 ACRS-10 and 50-287 Gray Fil e HOrnstei n/
EBlackwood Mr. William 0. Parker, Jr.
H
/
19O 1 a9 Vice President - Steam Production Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
The staff has completed its review ofNFS-1001, "Reload Design Methodology" for the Oconee Nuclear Station whic was submitted by letter datedjApril 23, 1979 and revised by letters dated May
, 1980 January 28,1981 andApril 22, 1981.
As a result of this review, we find that additional information is required for Us to determine the acce ptafb iItyof the report.
Therefore, we request that you provide the information requested in the enclosure to this letter within 30 days of iis recei pt. If you have any questions on this sjubject, please contact yourN P-ect Manager.
Sincerely, PORIGINAL SIGNED BY jou r. STOLTZ*
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/enclosure:
See next paget 810610 OFFICE)
OB#4:D
- 4:DL SURNAMEO PWagner a DATEO 6/1 /81 NRC FORM 31810/80 NRCM 0240 OFFICIAL RECORD COPY USGPO 1980-329
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 2, 1981 Dockets Nos. 50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.
Vice President - Steam Production Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina. 28242
Dear Mr. Parker:
The staff has completed its review of NFS-1001, "Reload Design Methodology" for the Oconee Nuclear Station which was submitted by letter dated April.23, 1979 and revised by letters dated May 20, 1980, January 28, 1981 and April 22, 1981.
As a result of this review, we find that additional information is required for us to determine the acceptability of the report.
Therefore, we request that you provide the information requested in the enclosure to this letter within 30 days of its receipt. If you have any questions on this subject, please contact your NRC Project Manager.
Sincerely, John F. Stolz, Chief (100rating Reactors Branch #4 ifivision of Licensing Enclosure eq Est fornddto Information cc w/enclosure:
See next page
-07 Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 33189 42? South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West JonesStreet Rale-.gh, 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 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Mr. Robert B.. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420,7735 Old Georgetown Road Bethesda, Maryland 20014 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
Enclosure to ltr.
dtd. 6/02/81 OCONEE RELOAD METHODOLOGY TECHNICAL REPORT NFS-1001 492:0 Core Performance Branch/Thermal-Hydraulics Section 492.1 Provide a more detailed discussion on how the core outlet (6.7) pressure-reactor outlet temperature curves are determined.
492.2 The method used to determine the Maximum Allowable Peaking (6.8.2)
(MAP) factor was to vary the hot channel power until the limiting DNBR was reached. Babcock and Wilcox varies the radial peaking factor rather than the power.
Demonstrate that the Duke method is an acceptable and conservative method when compared to the Babcock and Wilcox method.
492.3 More information is needed on the generic DNBR curves or (6.8.2)
MAP curves.
Supply the following:
- 1.
a detailed discussion of how the curves are developed;
- 2.
what the differences between the RPS DNB offset'curves and the DNB operational offset curves, are;
- 3.
how the MAP curves which have the reference design DNBR as their basis are obtained;
- 4.
how the extremities of the P-T core protection envelope are considered in developing the DNS offset limits.
492.4 In determining the reactor protection system P-T set points, (73.1) the applicant stated that.the RCS 'high pressure trip set point wa' 2355 psig.
,' thi-Technica1 'Spdecifi*tiodsfor Oconee Units 1, 2, and 3, the high pressure trip is at 2300 psig.
Correct this discrepancy..
492.5 Provide the values that are used to error adjust the P-T (7.3.1) set point curve.
How are these numbers obtained?
492.6 On page 7-10 reference is made to the flux/flow ratio (7. 3.2) ratio calculated in Section 6.8.
The flux/flow ratio is.
calculated in Section 6.9.
Correct this discrepancy.
492.7 Provide a'reference o the 6.5 percent full power error
(.3.2) adustnet factor used in setting the RPS power-flow Tm balance.