ML20078S759
| ML20078S759 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 02/16/1995 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078S762 | List: |
| References | |
| NUDOCS 9502270115 | |
| Download: ML20078S759 (8) | |
Text
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UNITED STATES o
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20856
- s.,...../
ENTERGY OPERATIONS. INC.
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SYSTEM ENERGY RESOURCES. INC.
t SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION j
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MISSISSIPPI POWER AND LIGHT COMPANY h
DQCKET NO. 50-416 GRAND CULF NUCLEAR STATION. UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.118 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated August 11, 1993, complies with the standards and requirements of the Atomic 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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common 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.
9502270115 950216 PDR ADOCK 05000416 P
e i l 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:
L (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environments 1 Protection Plan contained in Appendix B, as revised through Ar.,endment No.118, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Envircnmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION j
Paul W. O'Connor, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation
Attachment:
Changes ',o the Techrscal Specifications Date of Issuance:
February 16, 1995 i
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a e
ATTACHMENT TO LICENSE AMENDMENT NO. 11a 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. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 3-74 3/4 3-74 3/4 3-76 3/4 3-76 3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6
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]NSTRUMENTATION I
-ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.5 'The accident monitoring instrumentation channels shown in Table 3.3.7.5-1 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3.7.5-1.
ACTION:
With one or more accident monitoring instrumentation channels inoperable, take the ACTION required by Table 3.3.7.5-1.
1 SURVEILLANCE REQUIREMENTS 4
C 3. 7. 5 Each of the above required accident monitoring instrumentation channels shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.5-1.
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GRAND GULF UNIT 1 3/4 3-73 i
u IABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION APPLICABLE MINIMUM j
OPERATIONAL REQUIRED NUMBER CHANNELS INSTRUMENT CONDIT10N1.
OF CHANNELS OPERABLE EI1Q l.
Reactor Vessel Pressure 1, 2, 3 2
1 80 2.
Reactor Vessel Water Level 1,2,3,4,5 2
1 82-j 3.
Suppression Pool Water Level 1, 2, 3 2
1 80-4.
Suppression Pool Water Temperature 1, 2, 3 6,1/ sector 6,1/ sector 80 5.
Deleted g
6.
Drywell Pressure 1, 2, 3 2
1 80 7.
Drywell and Control Rod Drive Cavity Temperature 1, 2, 3 2 (each)
I (each) 80 8.
Containment Hydrogen Concentration Analyzer and Monitor 1, 2, 3 2
1 83 9.
Drywell Hydrogen Concentration Analyzer and Monitor 1, 2, 3 2
1 83 i
- 10. Containment Pressure (wide and narrow range) 1, 2, 3 2 (each).
1 (each) 80
- 11. Containment Air Temperature 1, 2, 3 2
1 80
- 12. Deleted l
- 13. Containment /Drywell Area Radiation Monitors I,2,3,4,5 2'
2' 81
- 14. Deleted
- 15. Deleted t
- 16. Deleted
- 17. Deleted
- 18. Deleted
- Each for containment and drywell.
408 118 GRAND GULF-UNIT 1 3/4 3-74 Amendment No.
T
TABLE 4.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIP.EMENTS t
CHANNEL CHANNEL I
INSTRUMENT CHECK CALIBRATION l
i 1.
Reactor Vessel Pressure M
R 2.
R l
t 3.
Suppression Pool Water Level M
R s
4.
Suppression Pool Water Temperature M
R 5-Deleted l
6.
Drywell Pressure M
R 7.
Drywell and Control Rod Cavity Temperature M
R 8.
Containment Hydrogen Concentr: tion Analyzer and Monitor NA M*
i 9.
Drywell Hydrogen Concentration Analyzer
[
and Monitor NA M*
- 10. Containment Pressure M
R t
- 11. Containment Air Temperature M
R i
- 12. Deleted l
- 13. Containment /Drywell Area Radiation Monitors M
R**
l
- 14. Deleted
- 15. Deleted
- 16. Deleted
- 17. Deleted i
- 18. Deleted i
- Using sample gas containing:
a.
One volume percent hydregen, remainder nitrogen.
b.' Four volume percent hydrogen, remainder nitrogen.
- The CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr with an installed i
or portable gamma source.
l GRAND GULF-UNIT 1-3/4 3-76 Amendment No.118
e-t REACTOR COOLANT SYSTEM 314.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2.1 For the following safety / relief valves:
- a. The safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than those satisfying the safety valve function requirement shall be OPERABLE with the specified lift settings
- b. Deleted Number of Valves Function Setooint* (osia) 8 Safety 1165 i 11.6 psi 6
Safety 1180 i 11.8 psi 6
Safety 1190 i 11.9 psi I
Relief 1103 i 15 psi 10' Relief 1113 i 15 psi 9
Relief 1123 i 15 psi APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
- a. With the safety and/or relief valve function of one or more of the above i
required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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- b. With one or more safety / relief valves stuck open, provided that suppression pool average water temperature is less than 110*F, take action close the stuck open relief valve (s); if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position.
- c. Deleted l
- d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.2.1.1 Deleted The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
- Initial opening of IB21-F051B is 1103 i 15 psig due to low-low set l
GRAND GULF-UNIT 1 3/4 4-5 Amendment No. 29,105, 118
4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE ** by performance of a:
- a. CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at -
least once per 92 days.
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- b. CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated j
automatic operation of the entire system at least once per 18 months.
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- A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillance without placing the trip system in the tripped condition.
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GRAND GULF-UNIT 1 3/4 4-6 Amendment No. M5d18
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