ML20086H065
| ML20086H065 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/13/1995 |
| From: | Hagan R WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ET-95-0067, ET-95-67, NUDOCS 9507170407 | |
| Download: ML20086H065 (5) | |
Text
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W@sLF CREEK NUCLEAR OPERATING CORPORATION Robert C. Hagan Vce Presdent Engineer ng July 13, 1995 ET 95-0067 U.
S.
Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-137 Washington, D.
C.
20555
Reference:
Letter ET 95-0051, dated June 14, 1995, from R. C. Hagan, WCNOC, to the NRC
Subject:
Docket No. 50-482:
Correction to Request for Revision to Technical Specifications to Implement Cycle 9 Nuclear and Core Thermal-Hydraulic Design Methodologies Gentlemen:
Attachment I to the Reference provided a detailed safety evaluation / analysis, including a description of the proposed changes, for the application for amendment to Facility Operating License No. NPF-42 for Wolf Creek Generating Station (WCGS) transmitted by the Reference.
This license amendment request proposes revising Technical Specification 3.2.2,
" Heat Flux Hot Channel Factor," Technical Specification 3.2.3,
" Nuclear Enthalpy Rise Hot Channel Factor," Technical Specification
- 6. 9.1. 9,
" Core Operating Limits Report," and associated Bases sections.
The requested revision is needed to incorporate changes associated with the planned implementation of advanced nuclear and core thermal-hydraulic design methodologies purchased from Westinghouse Electric Corporation for the Cycle 9 reload design.
Pages 15 and 16 of Attachment I to the Reference incorrectly indicated these pages contained confidential commercial information which Westinghouse considers to be proprietary information.
This information is marked in brackets throughout Attachment I,
including pages 15 and 16.
The Reference requested that all bracketed information in Attachment I be regarded as proprietary information, and withheld from public disclosure, in accordance with the provisions of 10 CFR 2.790.
The purpose of this letter is to provide corrected copies of pages 15 and 16 of Attachment I of the Reference.
The attached pages do not contain proprietary information, and replace the corresponding pages in our original submittal, 9507170407 950713 PDR ADOCK 05000482
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P PDR
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P O Box 411/ Burhngton. KS 66839 / Phone- (316) 364-8831 An Equal Opportunity Ernployer MTHC' VET
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ET 95-0067 Page 2.of 2 A copy of this submittal, with attachments, is being provided to the designated Kansas State official.
If you have any questions concerning this matter, please contact. me at (316) 364-8831, extension 4553, or Mr. Richard D. Flannigan, at extension 4500.
Very truly yours,
/
obert C. Hagan RCH/jra Attachments Corrected Pages 15 and 16 to Attachment I of Letter ET 95-0051, dated June 14, 1995 cc:
G. W. Allen (KDHE), w/a L. J. Callan (NRC), w/a D. F. Kirsch (NRC), w/a J. F. Ringwald (NRC), w/a J. C. Stone (NRC), w/a 4-
STATE OF KANSAS
)
)
SS COUNTY OF COFFEY
)
Robert C. Hagan, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By
.s Rob rE C. Hagan
/
/
Vi e President
[
En ineering l
SUBSCRIBED and sworn to before me this
//O day of p, 1995.
!&A>A YslisuL Ig Notary Public. State of Kansas ANGELA E.WESSEL sotary public l
_u Appt. Expires
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Expiration Date a h,- d /999 g
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I 2.1.2 Benchrsiarks 2.1.2.1 Startup Benchmarks 2.1.2.1.1 Rod Worths Rod worth measurements at startup of Cycles 6,7 and 8, using the Rod Exchange method, are compared to results from calculations with ANC in Table 2-1. The data in this table clearly shows that the WCNOC acceptance criteria for control rod bank worths, listed below, were met with substantial margin in all cases.
Accentance Criteria for Control Rod Bank Worth Uncertainty
- 1. Absolute value of the percent difference between measured and predicted integral bank worth for the reference bank (maximum worth bank) is less than or equal to 10%. For each test bank, absolute value of the percent ditTerence between the measured (inferred) test bank I
worth and the predicted worth is less than or equal to 15% or less than or equal to 100 pcm whichever is greater.
- 2. The sum of the measured (inferred) bank worths for all banks must be less than or equel to 110% of the sum of all the predicted bank worths.
2.1.2.1.2 HZP Critical Boron Concentration Critical boron concentration measurements at startup are compared to results from calculations with ANC in Table 2-2. WCNOC acceptance criterion requires that the measured boron concentration and predicted boron concentration at startup differ by no more than +/- 100 ppm.
The results in Table 2-2 indicate acceptable agreement between measured and predicted values.
2.1.2.1.3 HZP Moderator Temperature Coefficient (MTC)
MTC values inferred from Isothermal Temperature Coefficient (ITC) measurements at startup are compared to results from calculations with ANC in Table 2-3. The WCNOC acceptance criterion requires that the measured / inferred MTC values differ from predicted values by no more than 2.0 pcm/ F. As shown in Table 2-3, this standard was adequately met for each cycle; significantly, the ANC-calculated MTC is more positive than the measured / inferred MTC.
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2.1.2.2 Cycle Depletion Benchmarks 2.1.2.2.1 Boron Letdown Curve The measured and ANC-calculated baron letdown curves are compared for Cycles 6,7 and 8 in Figure 2-2, Figure 2-3, and Figure 2-4. respectively. The WCNOC Measurement and Acceptance Criteria are, for critical boron concentration predictions, a difference of no more than 50 ppm, plus a difTerence of no more than 1000 pcm-equivalent of the predicted boron concentration. These Figures show that the agreement is good and the criteria are met.
2.1.2.2.2 Power Distribution WCNOC has an ANC-based model to monitor the power distribution in Cycle 8. A " measured" Fj, is inferred from flux maps obtained during monthly surveillances. The " measured" FJ, is based on the measured in-core detector signal at the thimble location in the fuel assembly. This signal is modified by assembly power-to-thimble flux and pin-to-assembly power factors from ANC to convert it to FJ,.
The first several Cycle 8 comparisons between the " measured" and calculated FJ, are shown in Figure 2-5 through Figure 2-8. The results show good agreement. The largest difference between measurement and prediction occurs in peripheral. Iow power assembly locations in the core. The uncertainty factor of 5% used by WCNOC is satisfied.
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