ML20211D664
| ML20211D664 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/16/1986 |
| From: | Frank Akstulewicz Office of Nuclear Reactor Regulation |
| To: | Opeka J CONNECTICUT YANKEE ATOMIC POWER CO. |
| Shared Package | |
| ML20211D669 | List: |
| References | |
| NUDOCS 8610220245 | |
| Download: ML20211D664 (3) | |
Text
.
October 16, 1986 Docket No. 50-213 Mr. John F. Opeka, Vice. President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270 Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
"NUSC0 THERMAL HYDRAULIC MODEL QUALIFICATION, VOLUME II (VIPRE)," TOPICAL REPORT NUSCO 1.40-2 Re:
Haddam Neck Plant By letter dated July 30, 1984, Connecticut Yankee Atomic Power Company (CYAPCO) submitted the subject report to demonstrate the adequacy of the licensee's p! ant modeling techniques using the subject code in support of future plans for in-house reload analysea.
By letter dated September 5, 1986, CYAPC0 responded to questions from the staff and modified the previous submittal to include the development of a one-eighth-core, nineteen channel, fuel-cycle-independent VIPRE model.
The staff has completed its review of the materials submitted and has concluded that the topical report, as modified, is acceptable for referencing for cope thermal-hydraulic licensing calculations for the Haddam Neck Plant.
The staff also requires that the licensee perform an analysis to ensure that the departure from nucleate boiling ratio (DNBR) limit of 1.3 for the W-3 critical heat flux correlation used in VIPRE-01 provides a 95 percent probability at a 95 percent confidence for the DNB limit at the Haddam Neck Plant. A copy of our safety evaluation is enclosed.
Since Millstone Unit 2 has a different fuel design, a separate study is
~
necessary to establish the fuel-dependent inputs and to demonstrate the appropriateness of the DNBR limit for any CHF correlation to be used with the VIPRE-01 code.
Sincerely, Original signed by: F. M. Akstulewicz Francis M. Akstulewicz, Project Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
As Stated cc: See Next Page
,, DISTRIBUTION-CM' "
DJaffe CGrimes ACRS (10)
ISAP' Reading GHsii 0GC-Bethesda JPartlow NRC PDR F stulewicz EJordan AWang Local PDR n
yson BGrimes MBoyle PD#)DP)3 ISAP:DPL-Bh ISAP:DPL-B ISAP:DPL-B
.FAkstulewicf:lt DJa PAnderson g CGrimes
-10/g/86 10/
86 10/G86 10/IL/86 8610220245 861016 PDR ADOCK 05000213 p
~. -..
'9,,
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
g a
wAsmworow, o. c. 2osss October 16, 1986
^
)
Docket No. 50-213 I
Mr. John F. Opeka, Vice President Nuclear Engineering and Operations Connecticut Yankee Atomic Power Company Post Office Box 270.
Hartford, Connecticut 06141-0270
Dear Mr. Opeka:
SUBJECT:
"NUSCO THERMAL HYDRAULIC MODEL QUALIFICATION, YOLUME II (VIPRE)," TOPICAL REPORT NUSCO 140-2 Re:
Haddam Neck Plant By letter dated July 30, 1984, Connecticut Yankee Atomic Power Company (CYAPC0) submitted the subject report to demonstrate the adequacy of the licensee's plant modeling techniques using the subject code in support of future plans for 1
in-house reload analyse's. By letter dated September 5,1986, CYAPC0 responded i
to questions from the staff and modified the previous submittal to include the development of a one-eighth-core, nineteen channel, fuel-cycle-independent VIPRE model.
1 The staff has completed its review of the materials submitted and has concluded that the topical report, as modified, is acceptable for referencing for core thermal-hydraulic licensing calculations for the Haddam Neck Plant.
l The staff also requires that the licensee perform an analysis to ensure that the departure from nucleate boiling ratio (DNBR) limit of 1.3 for the W-3 critical heat flux correlation used in VIPRE-01 provides a 95 percent probability at a 95 percent confidence for the DNB limit at the Haddam Neck Plant. A copy of our safety evaluation is enclosed.
i Since Millstone Unit 2 has a different fuel design, a separate study is necessary to establish the fuel-dependent inputs and to demonstrate the appropriateness of the DNBR limit for any CHF correlation to be used with the l
VIPRE-01 code.
Sincerely, Jancd Y Francis M. Akstulewicz, oject Manager Integrated Safety Assessment Project Directorate Division of PWR Licensing - B
Enclosure:
As Stated cc: See Next Page
Mr. John F. Opeka Connecticut Yankee Atomic Power Company Haddam Neck Plant cc:
Gerald Garfield, Esquire Kevin McCarthy, Director Day, Berry & Howard Radiation Control Unit Counselors at Law Department of Environmental City Place Protection Hartford, Connecticut 06103-3499 State Office Building Hartford, Connecticut 06106 Superintendent Haddam Neck Plant Richard M. Kacich, Supervisor RDF #1 Operating Nuclear Plant Licensing Post Office Box 127E Northeast Utilities Service Company East Hampton, Connecticut 06424 Post Office Box 270 Hartford, Connecticut 06141-0270 Edward J. Mroczka Vice President Nuclear Operations Northeast Utilities Service Company Post Office Box 270 Hartford, Connecticut 06141-0270 Board of Selectmen Town Hall Haddam, Connecticut 06103 State of Connecticut Office of Policy and Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 Resident Inspector Haddam Neck Nuclear Power Station c/o U.S. NRC East Haddam Post Office East Haddam, Connecticut 06423 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
_ - -. _, _,.,