ML20134N051
| ML20134N051 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/15/1996 |
| From: | Meisner M ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9611260140 | |
| Download: ML20134N051 (5) | |
Text
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== ENTERGY.-
ET"E!*""~""*'
r Port Gbson. MS 39150 Tei 601437 6470 I
d '.
M. J. Meisner Onector l
Nucleat 5d:dv & 1%x3utmory Mws l
' November 15,1996 U.S. Nuclear Regulatory' Commission Mail Station P1-37 Washington, D.C. 20555 Attention:
Document Control Desk -
Subjecti Grand Gulf Nuclear Station Docket No 50-416 i
License No. NPF-29 i
Cycle 9 Reload l
= Response to NRC Request for Additional Information regarding l
Minimum Critical Power Safety Limit
Reference:
11.
NRC L'etter GNRI-96/00177 dated August 22,1996 related to i
the Grand Gulf Nuclear Station Cycle 9 SLMCPR (PCOL-96/008, Revision 1)
I 2.
GNRO-96/0087, Revision to Proposed Amendment to the Operating License (PCOL-96/008, Revision 1) l
- GNRO:
96/00126 I
Gentlemen:
Please find attached Entergy Operations, Inc. response to the NRC request for formal submittal of the comparison plot showing the predicted CPR performance of both GE11 and SPC 9x9-5 limiting bundles throughout Cycle 9 and a description of how the calculations were performed for this plot. The request for this additional information was made during a telephone conference on November 12,1996.
~ This information is being submitted in continuation with GNRO-96/0087, GNRO-
'. 96/00100 and GNRO-96/00119 regarding the proposed amendment to the Grand Gulf Nuclear Station Operating License for the Cycle 9 Minimum Critical Power Ratio Safety Limit (SLMCPR).
The original amendment request had been reviewed and accepted by the Plant Safety Review Committee and the Safety Review Committee. The conclusions of the Significant Hazards Considerations for this response remain unchanged.
9611260140 961115 (fj l !
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GNRO-96/00126 Page 2 of 3 l
Based on the guidelines in 10CFR50.92, Entergy Operations has concluded that the response to the NRC request for additionalinformation involve no additional significant hazards considerations.
- Entergy Operations requests NRC approval and issuance of Technical Specifications changes 4
to allow plant start-up following RF08.
Yo rs truly, i
acg/be attachments:
_1.
Affirmation per 10CFR50.30' 2.
EOl Response to NRC Request for Additional Information I
cc:
Mr. J. E. Tedrow (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. J. W. Yelverton (w/a) i i
j Mr. L. J. Callan (w/a) i Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington,TX 76011 Mr. J. N. Donohew, Project Manager (w/a)
Office of Nuclear Reactor Regulation -
U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 i
~
Dr. E. F. Thompson (w/a)
State Health Officer State Board of Health l
P.O. Box 1700 Jackson, Mississippi 39205 t
i.
-e
Attachm.nt 1 to GNRO-96/00126 Page 1 of 1
~
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET NO. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and SYSTEM ENERGY RESOURCES, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION and ENTERGY OPERATIONS, INC.
AFFIRMATION I, M. J. Meisner, being duly sworn, state that I am Director, Nuclear Safety and Regulatory Affairs GGNS of Entergy Operations, Inc.; that on behalf of Entergy Operations, Inc., System Energy Resources, Inc., and South Mississippi Electric Power Association I am authorized by Entergy Operations, Inc. to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Director, Nuclear Safety and Regulatory Affairs GGNS of Entergy Operations, Inc.; and that the statements made and the mat rs set forth therein are true and correct to the best of my knowledge, information and belie,
~
M. J. Meisner STATE OF MISSISSIPPI COUNTY OF CLAlBORNE 4
SUBSCRIBED AND SWORN TO before me, a Notary Public, in and for the County and State above named, this
// " day of Alownest
.1996.
(SEAL)
CAL ~D LU Notary bublic rNCE$1E My comm,ss. ion expires:
== nsu sismi moTEyb000
- to GNRO-96/00126 Page 1 of 1 Attachment to: GGNS Cycle 9 Minimum CPR Data Summary Figure 1 provides the predicted minimum CPR by fuel design type throughout Cycle 9. This data was calculated by GE using their 3-dimensional nodal simulator (PANACEA). The data is based on expected normal full power operation. GE's CPR correlation, GEXLO7, was applied to GE 11 fuel.
The modified version of the GEXLO2 correlation described in the referenced Cycle 9 MCPR Safety Limit PCOL was applied to the Siemens fuel. The predicted minimum CPR for each fuel design type is presented in Figure 1.
Rnference PCOL-96/008, Rev.1," Cycle 9 Reload Revision to Proposed Amendment to the Operating License,"
C. R. Hutchinson (EOI) to U.S. NRC, July 31,1996.
f I
l Figure 1 - GGNS Cycle 9 Minimum CPR By Fuel Design 1.70 1.65 --
1.60 --
1.55 --
~x D 1.50 --
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y 6
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s.
y~.
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N'
.,N 1.45 --
e s.,
1.40 --
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1.35 --
-e--Siemens Fuel 1.30 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 13.0 GWd/ST m
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