ML18101B315
| ML18101B315 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/08/1996 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-96-001, IEB-96-1, LR-N96093, NUDOCS 9604150211 | |
| Download: ML18101B315 (9) | |
Text
Public Service Electric and Gas Company Louis F. Storz Senior Vice President - Nuclear Operations Public Service Electric andJtl'ff'(f~19g&'*O. Box 236, Hancocks Bridge, NJ 08038 LR-N96093 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Gentlemen:
NRC BULLETIN 96-01: CONTROL ROD INSERTION PROBLEMS SALEM GENERATING STATION UNIT NOS l AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 609-339-5700 Public Service Electric & Gas Company (PSE&G) has received Bulletin 96_.0l.
The Salem units are in a shutdown and defueled condition which prevents the prompt completion of all of the Bulletin-requested actions.
This letter provides as complete a response as possible under the given plant conditions and will be supplemented as described herein.
REQUIRED RESPONSE (1) With the reactors defueled, PSE&G cannot promptly certify the control rods operable.
Our response to Requested Action 2, below, provides the basis for our determination that the control rods were operable for *the past five years for both Salem Units.
As a normal part of restart testing, Requested Action 3 will be implemented.
A supplement to this response will be made within 30 days of completing Requested Action 3 that certifies initial control rod operability for the subsequent cycle.
Requested Action 1 The Salem Operations Department was cognizant of the recent industry events outlined in NRC Bulletin 96-01, and initiated actions, in early March 1996, to incorporate training on those events into the restart training program.
During restart training, operators will be briefed on the recent industry events and will receive training, including simulator drills, responding to an event in which the control rods do not fully insert on a reactor~trip. Additionally,*
prior to restart, an information directive on recent industry rod insertion events will be provided to operations department personnel.
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Document Control Desk LR-N96093 APR 0 8 1996 Requested Action 2
- 0 0
Based upon a historical review of all reactor trip data for the past five years and rod drop testing for the last fuel cycle, all control rods were operable up to the current plant shutdowns for both Salem units.
Any new data obtained during plant restart testing per Requested Action 3 for the current outages, in conjunction with the data already available from Wolf Creek, South Texas, North Anna, and other industry experience, will be considered in making a supplemental determination of control rod operability prior to returning each Salem unit to power operation.
A supplement to this letter will be provided within 30 days of completing Requested Action 3 that summarizes the data and verifies control rod operability.
Requested Action 3
° Control rod drop times and recoil data will be measured and evaluated during the current restart effort and also any subsequent outage during calendar year 1996 which is expected to extend for at least ten days, prior to entering Mode 2.
° Control rod drag forces for all rodded fuel assemblies will also be measured and evaluated during the current restart effort prior to entering Mode 5.
Requested Action 4
° For any reactor trip during calendar year 1996, PSE&G will verify that all control rods have promptly fully inserted.
The verification will be performed through the formal Post-Trip Review process.
The Post-Trip Review will also include the Sequence-of-Events as provided by the plant computer.
This information will be used to assess the operability and performance trend of the rods.
REQUIRED RESPONSE (2) Based upon the preliminary loading pattern for Salem Unit 2, Cycle 10:
Table 1 of this letter provides the fuel design type, materials in fuel rods, guide tubes, grids, spacers (sleeves), and the guide tube inner dimensions (above and below the dashpot). shows the control rod locations.
Attachments 2 and 3 depict the core map of rodded fuel assemblies indicating beginning and end of cycle assembly average burnup distributions respectively.
Quarter-core control rod locations are circled for reference.
95-4933
9**.
Document Control Desk LR-N96093,APR 0 8 1996 Since this loading information is preliminary, supplied burnup distributions and fuel inventory may change as the design is finalized.
Should the final Salem Unit 2, Cycle 10 loading differ from the data provided herein, PSE&G will provide a supplemental response containing the new fuel inventory and corresponding burnup distributions prior to restart.
Due to the extended outage of Salem Unit 1, no loading pattern has been developed for Cycle 13.
Similar information to that provided herein for Unit 2 will be submitted following confirmation of restart details for Salem Unit 1.
REQUIRED RESPONSE (3) PSE&G will comply with the reporting requirements of this item for Requested Actions 3 and 4 as applicable.
Should you have any questions regarding this response, we will be pleased to discuss them with you.
Sincerely, Attachments (4) 95-4933
Document Control Desk LR-N96093 c Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 APR 0 8 1996 Mr. L. Olshan, Licensing Project Manager -
Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. c. Marschall (X24)
USNRC Senior Resident Inspector -
Salem Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
STATE OF NEW JERSEY COUNTY OF SALEM
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)
)
REF:
LR-N96093 SS.
L. F. Storz, being duly sworn according to law, deposes and says:
I am Senior Vice President - Nuclear Operations of Public Servic~
Electric and Gas Company, and as such, I find the matters set forth in the above referenced letter, concerning the Salem Generating Station, Unit Nos. 1 and 2, are true to the best of my knowledge, information and belief.
Subscri~~d and Sw~ore me
- this '(+ti.
day o
, 1996 My Commission expires on KIMBERLY JO BROWN NOTARY PUBLIC OF NEW JERSEY M*t GemmissiaH Ex~ires Ap1 ii 21, 1!l98
Region 7A 9A IOA IOB llA 12 15XA TABLE 1 DESIGN FEATURES FOR PRELIMINARY SALEM UNIT 2CYCLE10 LOADING PATTERN Design Materials Grids Spacers RCCA Fuel/
(Sleeves)
Guide Tubes I
Westinghouse Zircaloy-4/
Inconel Stainless Standard Zircaloy-4 Steel (SS) 8 Westinghouse Zircaloy-4/
top/ bottom: Inconel top/bottom: SS Vantage 5H Zircaloy-4 Mid: Zircaloy-4 Mid: Zircaloy-4 16 Westinghouse Zircaloy-4/
top/ bottom: Inconel top/bottom: SS Vantage 5H Zircaloy-4 Mid: Zircaloy-4 Mid: Zircaloy-4 12 Westinghouse Zircaloy-4/
top/ bottom: Inconel top/bottom: SS Vantage 5H Zircaloy-4 Mid: Zircaloy-4 Mid: Zircaloy-4 8
Westinghouse Zirlo/
top/ bottom: lnconel top/bottom: SS Vantage+
Zirlo Mid: Zirlo Mid: Zirlo 4
Westinghouse Zircaloy-4/
top/ bottom: Inconel top/bottom: SS Vantage 5H Zircaloy-4 Mid: Zircaloy-4 Mid: Zircaloy-4 4
Westinghouse Zirlo/
top/ bottom: Inconel top/bottom: SS Vantage+
Zirlo Mid: Zirlo Mid: Zirlo Guide Tube I.D. (in.)
Above Dash pot/
Below Dashpot
.450/.397
.442/.397
.442/.397
.442/.397
.442/.397
.442/.397
.442/.397
R F'
I I I
I I
\\
I I
i I
i I
' i I
SA 0
B D
SA N
SA c
SC SB A
SA BANK IDENTIFIER A a c 0
L 0
so a
c a
ATTACHMENT 1 SALEMUNIT2 J
H G
F E
B 0
c a
D c
c a
NUfl8ER OF' LOCATIONS 4
I I
9 a
D BANK IDENTIF'IER SA SB SC SD Control an* lhutclown lank Location*
D c
I I I
SA c
SI SC c
SA NlMIER OF' LOCATIONS a a 4
4 B
2 SA I
I 4
5 D
6 7
a 8
--*g D
10 11 SA 12 13 14 15
R p
9A 29.747 10A 21.764 108 15XA 21.448 0
108 11A 21.143 3.889 11A 11A 3.764 3.88 118 15XA 2.853 0
11A 11A 3.758 3.88 108 11A 20.999 3.885 108 15XA 21.466 0
10A 21.775 9A 29.78 ATTACHMENT 2 PRELIMINARY SALEM UNIT 2 CYCLE 10 Beginning of Cycle 10 (BOC) Assembly Average Burn ups (GWO/MTU)
N M
L K
J H
G F
E D
c B
A 108 108 11A 118 11A 108 108 21.448 20.986 3.767 2.862 3.778 21.041 21.419 9A 10A 15XA 11A 11A 15XA 11A 11A 15XA 10A 9A 29.767 21.75 0
3.906 3.871 0
3.868 3.903 0
21.715 29.775 108 118 108 15X8 9A 10A 9A 15X8 108 118 108 9A 19.446 3.431 21.568 0
25.649 16.827 25.714 0
21.584 3.418 19.384 29.856 118 108 11A 12 11A 10A 11A 12 11A 108 118 10A 3.419 19.62 4.078 27.678 2.789 22.202 2.789 27.822 4.077 19.717 3.42 21.738 108 11A 15XA 12 12 11A 12 12 15XA 11A 108 15XA 108 21.566 4.081 0
23.155 27.092 3.736 26.759 23.099 0
4.08 21.477 0
21.419 15X8 12 12 12 11A 10A 11A 12 12 12 15X8 11A 108 0
27.964 23.231 25.95 3.585 21.89 3.587 25.983 23.127 27.879 0
3.887 20.949 9A 11A 12 11A 10A 15XA 10A 11A 10A 11A 9A 11A 11A 25:734 2.789 26.884 3.606 20.571 0
20.545 3.59 27.092 2.792 25.715 3.879 3.765 10A 10A 11A 10A 15XA 15XA ~
11A @ 10A ~
118 16.84 22.241 3.717 21.934 0
( 35.324 0
1.983 3.718 22.236 16.794 0
2.852 9A 11A 12 11A 10A 15XA 10A 11A 12 11A @11A 11A 25.778 2.8 26.824 3.594 20.567 0
20.603 3.591 27.051 2.79 25.676 3.882 3.771 15X8 12 12 12 11A@ 11A ~
12 12 15X8 ~
108 0
27.677 23.284 25.847 3.59 21.875 3.592 25.877 23.059 27.815 0
3.895 21.019 108 11A 15XA 12 10A 11A 10A 12 15XA 11A@15XA 108 21.506 4.077 0
23.186 27.055 3.738 26.998 23.258 0
4.091 21.508 0
21.465 118 108 11A 12 11A @ 11A 12*
11A ~118@
3.423 19.643 4.075 27.75 2.793 2.222 2.789 27.837 4.077 3.424 21.77 108 118 108 15X8 9A 10A @15X8@118 108 9A 19.414 3.417 21.568 0
25.738 16.763 25.742 0
1.524 3.422 19.388 29.602 9A 10A 15XA 11A 11A 11A 15XA@ 9A 29.729 21.681 0
3.913 3.868 3.871
.897 -
0 21.74 29.701 108 108 11A 118 11A 108 108 21.466 20.952 3.768. 2.862 3.774 21.157 21.465 2
3 4
5 6
7 8
9 10 11 12 13 14 15
p *.
- ~, II R
p N
9A 34.866 9A 108 34.845 33.081 10A 118 32.868 23.841 108 15XA 108 29.365 19.155 41.873 108 11A 15X8 32.444 25.49 22.843 11A 11A 9A 19.369 25.88 44.14~
118 15XA 10A 20.229 23.291 37.212 11A 11A 9A 19.376 25.894 44.201 108 11A 15X8 32.331 25.515 22.889 108 15XA 108 29.397 19.186 41.862 10A 118 32.902 23.878 9A 108 34.882 33.068 9A 34.836 ATTACHMENT 3
. PRELIMINARY SALEM UNIT 2 CYCLE 10
. End of Cycle 10 (EOC) Assembly Average Burnups *
(GWDIMTU)
M L
K J
H G
F E
D c
8 A
108 108 11A 118 11A 108 108 29.378 32.316 19.381 20.237 19.384
~2.359 29.343 10A 15XA 11A 11A 15XA 11A 11A 15XA 10A 9A 32.871 19.174 25.525. 25.89 23.296 25.877 25.51 19.16 32.826 34.871 118 108 15X8 9A 10A 9A 15X8 108 118 108 9A 23.867 41.899 22.886 44.105 37.216 44.145 22.86 41.891 23.838 33.027 34.948 108 11A 12 11A 10A 11A 12 11A 108 118 10A 40.903 26.713 44.828 24.277 41.45 24.273 44.932 26.691 40.974 23.86 32.863 11A 15XA 12 12 11A 12 12 15XA 11A 108 15XA 108 26.689 21.988 40.996 44.773 25.404 44.503 40.936 21.997 26.703 41.828 19.181 29.354 12 12 12 11A 10A 11A 12 12 12 15X8 11A 108 45.025 41.015 43.317 24.95 41.363 24.944 43.352 40.964 44.977 22.873 25.51 32.288 11A 12 11A 10A 15XA 10A 11A 10A 11A 9A 11A 11A 24.245 44.582 24.944 40.106 21.161 40.086 24.944 44.759 24.253 44.148 25.892 19.381 10A 11A 10A 15XA @15XA @ 11A ~
10A @118 41.473 25.387 41.397 21.155 1.269 21.143 1.417 25.354 41.462 37.187 23.296 20.23 11A
.12 11A 10A 15XA 10A 11A 12 11A 11A 11A 24.29 44.57 24.979 40.106 21.154 40.124 24.919 44.713 24.255 44.117 25.893 19.382 12 12 12 11A @,11A @"
12 15X8@108 44.831 41.116 43.247 24.934 41.348 4.961 43.266 0.895 44.93 22.875 25.513 32.346 11A 15XA 12 10A 11A 10A 12 15XA 11A 15XA 108 26.725 22.004 40.997 44.719 25.389 44.693 41.075 22.. 001 26.7 41.849 19.173 29.389 108 11A 12 11A @ 11A 12 11A@118@
40.937 26.708 44.877 24.263
- 41.
24.263 44.946 26.712 40.922 23,867 32.886 118 108 15X8 9A 10A @ 15X8@ 118 108 9A 23.86 41.895 22.875 44.168 37.163 44.171 22.872 41.86Z 23.873. 33.049 34.716 10A 15XA 11A 11A @ 11A @ 15XA ~
9A 32.81 19.176 25.532 25.884° 23.299 25.882 25.511 19.174 2.874 34.81 108 108 11A 118 11A 108 108 29.395 32.292 19.385 20.238 19.381 32.461 29.387 2
3 4
5 6
7 8
9 10 11 12 13
. 14 15