LR-N04-0369, Notification of Revised Application of Westinghouse Dynamic Rod Worth Measurement Technique
| ML042440637 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/19/2004 |
| From: | Mannion M Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LR-N04-0369 | |
| Download: ML042440637 (3) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG ANuclearLLC LR-N04-0369 AUG199 04 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 NOTIFICATION OF REVISED APPLICATION OF WESTINGHOUSE DYNAMIC ROD WORTH MEASUREMENT TECHNIQUE SALEM GENERATING STATION, UNIT NO. 2 FACILITY OPERATING LICENSE DPR-75 DOCKET NO. 50-311 PSEG Nuclear, LLC (PSEG) currently employs the Westinghouse Dynamic Rod Worth Measurement (DRWM) technique, which is a state-of-the-art method of measuring the reactivity worth of the control and shutdown banks. As a result of the planned new vessel head installation on Unit 2 in April 2005, the RCCA pattern for shutdown bank "A" will be modified (see attached figure) to increase total plant shutdown margin. This modified RCCA pattern was not specifically analyzed in the DRWM topical report, therefore the sensitivity to prediction errors has not been demonstrated.
As a result, Westinghouse has been consulted in regard to the new pattern and the subsequent effect oh DRWM accuracy. Westinghouse indicates that the new Unit 2 shutdown bank "A" pattern will have little effect on the sensitivity.
Therefore, Westinghouse has indicated that use of DRWM with the new RCCA pattern in April 2005 is appropriate.
The following is the summary of the assessment:
- 1. The movement of the four Shutdown Bank A (SA) control rods will reduce the exaggeration of a potential error in the SA prediction, and it is unlikely to cause a masking of any such error.
95-2168 REV. 7/99
Document Control Desk LR-N04-0369 Page 2 of 3
- 2. The impact of this change to the overall sensitivity to a prediction error is expected to be negligible. All conclusions drawn of the original work in NRC approved (TAC M83235, dated January 5, 1996) WCAP-13360 remain valid.
Since the current Salem Unit 2 pattern is presented on Figure 82, page D-22 of WCAP-13360, PSEG is notifying the NRC staff of this pattern change and that Westinghouse will confirm the validity of the original sensitivity study in WCAP-13360 utilizing the data acquired in April 2005. This will provide further evidence that continued use of DRWM with the new Salem Unit 2 RCCA pattern remains appropriate.
PSEG staff has reviewed this assessment in light of the information presented by Westinghouse and agree with the content of this assessment.
If you have any questions or require additional information, please contact Mr.
Kent Halac at (856) 339-1280.
Sincerely, Michael Mannion Fuel/RX Engineering Manager C:
Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager - Salem & Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555 USNRC Senior Resident Inspector - Salem Units 1 and 2 Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625
pocument Control Desk LR-N04-0369 Page 3 of 3 SALEM UNIT 2 REVISED RCCA PATTERN (Effective April 2005)
R P
N M
L K
J H
G F
E D
C B
A i
1 2
+ T KF
I I
I I
]I I
D B
D 3
+
D I
S B I I ISD jISBI I SBI
.SC I I I
C A
- SA C
SA 5
6 7
8 9
10 11 SC SD I
D SA B
C B
D SB SB B
A C
D
~
C A
B C
B SA D
__I__-SC 12 13 14 SA C
- SA
A C
D B
D SA
- 15 RCCA Removed -1 RCCA Added
+
B-12 D-02 M-14 P-04 D-10 IF-04 K-12 M-06