ML20205Q641
| ML20205Q641 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 03/31/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205Q646 | List: |
| References | |
| TAC-63175, NUDOCS 8704060004 | |
| Download: ML20205Q641 (10) | |
Text
.
/pa agg
'o UNITED STATES E {, m [,,g NUCLEAR REGULATORY COMMISSION
-E W ASHINGTON, D. C. 20555
,k~Q,i t
MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSIS 5IPPI ELEGIRIC F0WER ASSOCIATION DOCKET hD. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMEhDMENT TO FACILITY OF'EPATING LICENSE Amendment No. 29 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amendment by Mississippi Power & Light Company, System Energy Resources Inc. (formerly Middle South Energy, Inc.)
and South Mississippi Electric Power Association, (the licensees) dated October 17, 1986, 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 provisiens of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endanaerino the health and safety of the public, and (11) 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.
2.
Accordingly, the license is amended by changes to the Technical 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:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 29, are hereby incorporated into this license.
System Energy Resources, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8704060004 870331 DR ADOCK 0500 6
. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION orsalmi ss..d by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
flarch 31, 1987 i
4 4
>]
PDL4 h
OGC PD#4/D Md'p en LKintner:ca Ap)/Mi WButler e
87 3 /Ju/87 3 / D/87 }/jp87
-2 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION-L Walter R. Butler. Director BKR Project Directorate Ko. 4 Division of BWR Licensing Attachttent:
Changes to the Technical Specifications Date of Issuance: 11 arch 31, 1987 3
-p-
ATTACHMENT TO LICENSE AMENDMENT NO. 29 FACILITY OPERA' NG LICENSE NC. NPF-29 DOCKF NO. 50-416 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Arendment number and contain vertical lines indicating the area of change. Overleaf page(s) provided to maintain document completeness.*
Retrove Insert 3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6*
3/4 6-53 3/4 6-53*
3/4 6-54 3/4 6-54 3/4 8-47 3/4 8-47 3/4 8-48 3/4 8-48*
l i
REACTOR COOLANT SYSTEM 3/4.4.2 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, and b.
The safety / relief tail pipe pressure switches for each safety / relief valve shall be OPERABLE.
Number of Valves Function Setpoint* (psig) 8 Safety 1165 + 11.6 psi 6
Safety 1180 7 11.8 psi 6
Safety 1190 7 11.9 psi 1
Relief 1103 7 15 psi 10, Relief 1113 7 15 psi 9
Relief 1123115 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 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 />.
b.
With one or more safety / relief valves stuck open, provided that suppres-sion pool average water temperature is less than 110 F, take action to 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.
With one or more safety / relief tail p'pe pressure switches inoperable, restore the inoperable switch (es) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 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 />.
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 The tail pipe pressure switch for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be 30 i 5 psig by performance cf a.
- The lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
- nitial opening of 1821-F051B is 1103 + 15 psig due to low-low set function.
I i
GRAND GULF-UNIT 1 3/4 4-5 AmendmentNo.29l 4
I
i REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) a.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and a
!~
b.
CHANNEL CALIBRATION at least once per 18 months.*
4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:
CHANNEL FUNCTIONAL TEST, including calibration of the trip unit, at a.
least once per 31 days.
b.
CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation of the entire system at least once per 18_ months.
a l
i I
i i
l 1
l t
i i
l i
)
- The provisions of Specification 4.0.4 are not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is
{
adequate to perform the test.
i i
i.
- i?AND GULF-UNIT 1 3/4 4-6 1
e **
gr m-yw--<-ry-w e9m a-mt vw---
w,w y-mm-,
4 um p-9
,r wemwwm,,wy
l l
TABLE 3.6.6.2-1 (Continued)
SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS / VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION (Seconds)
Valves (Continued)
Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F064)-(A) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F066)-(A) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F047)-(A) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F063)-(B) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F065)-(B) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F067)-(B) 4 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F061)-(B) 4 Floor'and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F158)-(A) 9 Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F160)-(A) 9 Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F163)-(A&B) 9 Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F159)-(B) 9 Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F161)-(B) 9 Makeup Water Treatment Sys. Aux. Bldg. Isol. Valve (P21-F024)-(A) 30 Domestic Water System Aux. Bldg. Isol. Valve (P66-F029A)-(A&B) 4 PSW Aux. Bldg. Isol. Valve (P44-F121)-(A) 100 GRAND GULF-UNIT 1 3/4 6-53
TABLE 3.6.6.2-1 (Continued)
SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS / VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION (Seconds)
Valves (Continued)
PSW Aux. Bldg. Icol. Valve (P44-F122)-(A) 100 PSW Aux. Bldg. Isol. Vclve (P44-F117)-(A) 100 PSW Aux. Bldg. Isol. Valve (P44-F118)-(A) 100 PSW Aux. Bldg. Isol. Valve (P44-F120)-(B) 100 PSW Aux. Bldg. Isol. Valve (P44-F123)-(B) 100 PSW Aux. Bldg. Isol. Valve (P44-F116)-(B) 100 PSW Aux. Bldg. Isol. Valve (P44-F119)-(B) 100 RHR Discharge To Liquid Radwaste Valve (E12-F203)-(A&B) 30 i
GRAND GULF-UNIT 1 3/4 6-54 Amendment No. 29 l
T
,.*,e
r
TABLE 3.8.4.2-1 MOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE (CON-TINUOUS) (ACCIDENT SYSTEM (S)
VALVE NUMBER CONDITIONS) (NO)
.AFFECTED Q1E51F010 Continuous RCIC System Q1E51F013 Continuous RCIC System Q1E51F019 Continuous RCIC System Q1E51F022 Continuous RCIC System Q1E51F031 Continuous RCIC System Q1E51F045 Continuous RCIC System Q1E51F046 Continuous RCIC System Q1E51F059 Continuous RCIC System Q1E51F068 Continuous RCIC System RCIC Trip and Throttle Continuous RCIC System Valve on Turbine Q1E51C002 Q1E51F095 Continuous RCIC System l
Q1821F065A No Reactor Coolant System Q1B21F065B No Reactor Coolant System Q1B21F098A No Reactor Coolant System Q1B21F098B No Reactor Coolant System Q1821F098C No Reactor Coolant System Q1821F098D No Reactor Coolant System Q1821F019 Continuous Reactor Coolant System Q1821F067A Continuous Reactor Coolant System Q1821F067B Continuous Reactor Coolant System Q1821F067C Continuous Reactor Coolant System Q1821F0670 Continuous Reactor Coolant System Q1B21F016 Continuous Reactor Coolant System Q1B21F147A Continuous MSL Drain Post LOCA Leak-age Control Q1821F1478 Continuous MSL Drain Post LOCA Leak-age Control Q1B33F019 Continuous Recirculation System Q1833F020 Continuous Recirculat. ion System Q1B33F125 Continuous Recirculation System Q1833F126 Continuous Recirculation System Q1833F127 Continuous Recirculation System Q1833F128 Continuous Recirculation System Q1D23F591 Drywell Monitoring System Q1D23F592 Drywell Monitoring System Q1D23F593 Drywell Monitoring System Q1023F594 Drywell Monitoring System Q1E12F040 Continuous RHR System Q1E12F023 Continuous RHR System Q1E12F006A Continuous RHR System Q1E12F052A Continuous RHR System Q1E12F008 Continuous RHR System Q1E12F394 Continuous RHR System GRAND GULF-UNIT 1 3/4 8-47 Amendment No.
2C l
4
l TABLE 3.8.4.2-1 (Continued)
HOTOR OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICE (CON-TINUOUS) (ACCIDENT SYSTEM (S)
VALVE NUMBER CONDITIONS) (NO)
AFFECTED Q1E12F014A Continuous RHR System Q1E12F026A
- Continuous RHR System Q1E12F082A No RHR System Q1E12F082B No RHR System Q1E12F290A Continuous RHR System Q1E12F047A Continuous RHR System 4
Q1E12F027A Continuous RHR System Q1E12F073A Continuous RHR System Q1E12F346 Continuous RHR System Q1E12F024A Continuous RHR System i
Q1E12F087A Continuous RHR System Continuous RHR System Q1E12F048A Q1E12F042A Continuous RHR System 5
Q1E12F004A Continuous RHR System Q1E12F003A Continuous RHR System Q1E12F011A Continuous RHR System Q1E12F053A Continuous RHR System Q1E12F037A Continuous RHR System Q1E12F028A Continuous RHR System Q1E12F064A Continuous RHR System Q1E12F2908 Continuous RHR System Q1E12F004C Continuous RHR System l
QlE12F021 Continuous RHR System Q1E12F064C Continuous RHR System Q1E12F042C Continuous RHR System I
Q1E12F048B Continuous RHR System Q1E12F049 Continuous RHR System Q1E12F037B Continuous RHR System Q1E12F053B Continuous RHR System i'
Q1E12F0748 Continuous RHR System Q1E12F042B Continuous RHR System Q1E12F064B Continuous RHR System Q1E12F096 Continuous RHR System Q1E12F094 Continuous RHR System Q1E12F006B Continuous RHR System Q1E12F0118 Continuous RHR System Q1E12F052B Continuous RHR System Q1E12F0478 Continuous RHR System Q1E12F027B Continuous RHR System Q1E12F0048 Continuous RHR System Q1E12F0878 Continuous RHR System Q1E12F003B Continuous RHR System Q1E12F026B Continuous RHR System Q1E12F024B Continuous RHR System Q1E12F028B Continuous RHR System Q1E12F009 Continuous RHR Systec Q1E12F073B Continuous RHR System CRAND GULF-UNIT 1 3/4 8-48 i
e
,n,
- ~ - - -
e, aw-
,-.--m, ~,, -,,- - -. - -
>-,