ML20134M689
| ML20134M689 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/21/1996 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134M691 | List: |
| References | |
| NUDOCS 9611260004 | |
| Download: ML20134M689 (6) | |
Text
.
p@ un 4
UNITED STATES p
g j
NUCLEAR REGULATORY COMMISSION S
WASHINGTON. D.C. 20066 4 001 o%...../
ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION ENTERGY MISSISSIPPI. INC.
DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE i
i Amendment No. 131 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found thai:
A.
The applications for amendment by Entergy Operations, Inc. (the licensee) dated May 9 and July 31, 1996, as supplemented by the i
letters dated September 5, October 22, and November 15, 20, and 21, 1996, comply with the standards and requirements of the Atomic j
Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
Comission; l
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; I
D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
V 9611260004 961121 I
PDR ADOCK b5000416 P
l i 2.
Accordingly, the license is amended by changes to the Technical i
Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-29 is hereby
^
amended to read as follows:
1 (2) Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 131, are hereby incorporated into this 1
license. Entergy Operations, Inc. shalf operate the facility in accordance with the Technical Specifications and the Environmental j
Protection Plan.
3.
This license amendment is' effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
L
{JackN.Donohew,SeniorProjectManager J
l Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 21, 1996
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 131 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT 2.0-1 2.0-1 5.0-20 5.0-20 5.0-21 9
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core $ls 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
l l
THERMAL POWER shall be s 25% RTP.
- 2.1.1.2 With the reactor steam dome pressure a: 785 psig and core flow a: 10% rated core flow:
MCPR shall be a 1.12 for two recirculation loop operation or a: 1.14 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.
l 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the corporate l
executive responsible for overall plant nuclear safety.
l
- MCPR values in T.S. 2.1.1.2 are applicable only for cycle 9 operation.
I
)
(continued) 4 GRAND GULF 2.0-1 Amendment No. 440, 131
Reporting Requirements 5.6
?
5.6 Reporting Requirements 5.6.5 Core Operatino Limits Report (COLR) (continued)
- 10. XN-NF-85-74(P)(A), "R00EX2A (BWR): Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA.
j
- 11. XN-CC-33(P)(A), "HUXY: A Generalized Multirod Heatup Code with 10CFR50 Appendix K Heatup Option," Exxon Nuclear Company, Inc., Richland, WA.
- 12. XN-NF-825(P)(A), "BWR/6 Generic Roif Withdrawal Error Analysis, MCPR, for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, Inc., Richland, WA.
- 13. XN-NF-81-51(P)(A), "LOCA-Seismic Structural Response of an Exxon Nuclear Company BWR Jet Pump Fuel Assembly,"
Exxon Nuclear Company, Inc., Richland, WA.
- 14. XN-NF-84-97(P)(A), "LOCA-Seismic Structural Response of an ENC 9x9 BWR Jet Pump Fuel Assembly," Advanced Nuclear Fuels Corporation, Richland, WA.
15, XN-NF-86-37(P), " Generic LOCA Break Spectrum Analysis for BWR/6 Plants," Exxon Nuclear Company, Inc., Richland, WA.
- 16. XN-NF-82-07(P)(A), " Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model," Exxon Nuclear Company, Inc.,
Richland, WA.
- 17. XN-NF-80-19(A), Volumes 2, 2A, 2B, & 2C, " Exxon Nuclear Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," Exxon Nuclear Company, Inc., Richland, WA.
- 18. XN-NF-79-59(P)(A), " Methodology for Calculation for Pressure Drop in BWR Fuel Assemblies," Exxon Nuclear Company, Inc., Richland, WA.
- 19. NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II) with exception to the misplaced fuel bundle analyses as discussed in GNR0-96/00087 and the generic MCPR Safety Limit analysis as discussed in GNR0-96/00100, letters from C. R. Hutchinson to USNRC.
' 20. J11-02863SLMCPR, Revision 1, "GGNS Cycle 9 Safety Limit MCPR Analysis."
(continued)
- Items 19 and 20 of TS 5.6.5.b are applicable only for Cycle 9 operation.
GRAND GULF 5.0-20 Amendment N,0. 430, 131
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core Operatina Limits Report (COLR) (continued)
I c.
The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
GRAND GULF 5.0-21 Amendment No. 430, 131