ML17319B493
| ML17319B493 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/19/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Dolan J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| Shared Package | |
| ML17319B494 | List: |
| References | |
| NUDOCS 8209020089 | |
| Download: ML17319B493 (9) | |
Text
AU6 1S 1982 Docket No. 50-316 Nr. John Dolan, Vice President
.Indiana and Michigan Electrfc Company Post Office Box 18 Bowling Green Station New York, New York 10004 0
DISTRIBUTION Docket NRC PDR L PDR NSIC>t ORB¹l Rgg DEisenhut OELD IE ACRS-10 "
CParrish RCil imber g Gray
Dear Mr. Dolan:
SUBJECT:
D. C.
COOK UNIT 2 CYCLE 4 RELOAD - QUESTIONS ON XN-NF-621, REVC 1
This letter confirms the August 18, 1982 telecopied request for additional information on the subject Exxon topical report.
Please respond thethe questions in Enclosur e 1 at the earliest possible date to expedite our review of your application.
Your response is also needed to the information requested in the enclosed summary of the August 5, 1982 meeting (Enclosure
- 2) held at NRC between NRR, Exxon and members of your staff, The reporting and/or r ecordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OIIB clearance is not required under P.L.96-511.
Enclosures:
As stated Sincerely,
.Og iginal sign94 baal
- s. A. varga Steven A. Varga, Chief Operating Reactors Branch
¹1 Division of Licensing cc w/enclosures:
See next page 8209020089 8208 i9 PDR ADOCK 00000316
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Docket No>. 50-6 Ih. John Dolan, Vice President Indiana and Michigan ectr ic Company Post Office Box 18 Bowling Green Station New York, New York 10004 DISTRIBUTION Docket NRC PDR L PDR NSIC ORB¹1 Rdg DEisenhut OELD IE ACRS-10 CParrish RCilimberg Gray
Dear tir. Dolan:
SUBJECT:
D. C.
COOK UNIT 2 CYCL 4 RELOAD - QUESTIONS OH XH-HF-621, REV.
1 This letter confirms the August 18, 982 telecopied request for additional information on the subject Exxon topi 1 report.
Please respond to the enclosed questions at the earliest pos ble date to expedite our review of your application.
Your response is also needed to the informa ion requested during the August 5, 1982 meeting held at NRC between t
R, Exxon and members of your staff.
The reporting and/or recordkeeping requirements ontained in this letter affect fewer than ten respondents; therefore, Ot)B clearance is not required under P.L.96-511.
S incer ely,
Enclosure:
As stated cc w/enclosure:
See next page Steven A. Varga, Ch ef Operating Reactors B anch
¹1 Division of Licensing OFFICE 0 SURNAME/
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Mr. John Dolan Indiana and Michigan Electric Company cc:
Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.
- 0. C.
20036
'aude Preston Palenske Memorial Library 500 Market Street St. Joseph, Michigan 49085 W.
G. Smith, Jr., Plant Manager Donald C. Cook Nuclear Plant P. 0.
Box 458 Bridgman, Michigan 49106.
U. S. Nuclear Regulatory Commission Resident Inspectors Office 7700 Red Arrow Highway Stevensville, Michigan 49127 William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.
20515 James G. Keppler Regional Administrator - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen El lyn, Illinois 60137
ENCLOSURE 1
THEfNAL-HYORAULICS SECTION Core Performance Branch
~uestion I Provide a complete description of hbw the local conditions for the XNB correlation were calculated in developing the correlation.
The description should include a discussion of:
the subchannel code used; the subchannel modeling; axial nodalization; and input assumptions (such as mixing factors, friction factors, spacer grid loss coefficients).
>Ihat uncertainties are associated with this analytical technique?
uestion 2
Provide the range of condi tions over which the XNB correlation is applicable.
In particular, provide the following;
- pressure, local mass velocity, local quality, heated lenght, grid spacing, equivalent hydraulic diameter, equivalent heated hydraulic diameter, fuel designs, inlet subcooling.
uestion 3
There are a number of correction factors, such as FAXIAL, SPC, HVF, KLOSS, and CC, which are designed to make the correlation fit a number of different geometries.
Provide a detailed discussion, including calculations and test
- results, on the development and calculation of these empirical functions.
Also, provide a discussion of how these parameters will be determined in licensing applications.
What uncertainties are associated with these parameters.
uestion 4
What type of fuel design does the ROSAL test data represent?
Justify your response.
~uestion 5 Perform F tests for each of the geometry types and the total population to support the hypothesis that all the data belong to the same population.
In addition, provide an analysis of @cans and a comparison of variance analysis to account for variances due to the different geometry types.
If it is determined that the data is not part of the same population, provide justifi-cation for using all the data in determining the DNBR limit.
!)
uestion 6
In determining the DNBR limit, Exxon statistically characterized the ratio of predicted to measured critical heat flux data.
Provide the same statistical analysis for the ratio of measured to predicted CHF and the resultant DNBR limit. Justify using the method you selected.
uestion 7
What was the rate of power increase for the CHF tests?
Were duplicate runs made during a series of tests to establish continued integrity of the test bundle?
Were any post-test inspections made to determine if there were indications of hot spots at locations other than where thermocouples were located.
~uestion 8
For the uniform heat flux tests, Exxon has stated that the end of the heated length was used as the location of CHF.
- However, many of the data reported in XN-NF-81-80, "DNB Test Data Report",
show that CHF occurred at the thermo-couple upstream of the end of the heated length.
Justify your technique of using the calculated minimum DNBR elevation to locate the CHF elevation.
Also provide all of the heated lengths used in the DNB tests.
Question 9
The XNB correlation appears to be based on local conditions obtained from a bundle-wide calculation as opposed to using a four rod subchannel which includes the rod that indicated CHF.
Using a bundle-wide technique may result in higher local conditions and powers than those obtained experimentally.
This would result in the correlation being based on local conditions that are non-conservative with respect to the test results.
Justify your technique of using bundle-wide calculations as dpposed to using subchannel calculations.
uestion 10 Which thermocouples indicated CHF for the ENC-5 tests?
When the ring type CHF indicators were used, what subchannel was used as the CHF location?
Ouestion 11 Provide an errata skeet or corrected pages to XN-NF-621, Revision 1.
Why were some of the test data reported in XN-NF-81-80 eliminated from the data reported in XN-NF-621, Revision 1.
uestion 12 For the uniform heat flux tests, the highest quality location should occur at the end of the heated length; therefore, CHF should also occur at the end of the heated length.
Some of the ENC-I thru V test'data show that CHF occurs at the thermocouple upstream of the end of the heated
- length, (guestion 8).
Provide an explanation of why CHF occured at the upstream thermocouple and not at the end of the heated length.