ML20213H107
| ML20213H107 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/12/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20213H110 | List: |
| References | |
| TAC-62789, NUDOCS 8611190099 | |
| Download: ML20213H107 (8) | |
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NUCLEAR REGULATORY COMMISSION 5
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MISSISSIPPI POWER & LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 24 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Mississippi Power & Light Company, Middle South Energy, Inc., and South Mississippi Electric Power Association, (the licensees) dated September 15, 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 provisions 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 endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been sati:fied.
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. 24, are hereby incorporated into this license.
Mississippi Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8611190099 861112 DR ADOCK 0500 6
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. 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
% shned by Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 12, 1986
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3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 12, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 24 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. Overleaf pages provided to maintain document completeness.*
Remove Insert 3/4 6-41 3/4 6-41 3/4 6-42 3/4 6-42*
3/4 6-45 3/4 6-45 3/4 6-46 3/4 6-46*
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.......~.............:;;-.--.....:.a TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES j
SYSTEM AND PENETRATION VALVE NL'MBER NUpeER Containment (Continued)
RHR Pump "B" Test E12-F335 67(0)(C)
Line RHR "B" Test Line E12-F2908-B 67(0)(d) l To Suppr. Pool Inst. Air to ADS P53-F006 70(I) (d)
I LPCS Relief Valve E21-F018 71A(0)
Vent Header RHR Pump "C" E12-F025C 71B(0)(d)
Relief Valve Vent Header RHR "C" Relief E12-F406 71B(I)(c)
Valve Vent Hdr.
to Suppr. Pool
& Post-Acc.
Sample Return RHR Shutdown E12-F036 73(0)
Vent Header RHR Shutdown E12-F005 76B(0)
Suction Relief i
Valve Disch.
RHR Heat Ex. "A" E12-F055A 77(0)(d)
Relief Vent Header RHR Heat Ex. "A" E12-F103A 77(0)(d)
Relief Vent i
Header RHR Heat Ex. "A" E12-F104A 77(0)(d)
Relief Vent l
Header i
SSW "A" Supply P41-F169A 89(I)
SSW "B" Supply P41-F1698 92(I) l Ctat. Leak Rate M61-F015 110A(I)
{
Test Inst, i
Ctat. Leak Rate M61-F014 110A(0) 1 Test Inst.
i Ctat. Leak Rate M61-F019 110C(I)
Test Inst.
Ctat. Leak Rate M61-F018 110C(0) l Test Inst.
Ctat. Leak Rate M61-F017 110F(I)
{
Test Inst.
Ctat. Leak Rate M61-F016 110F(0)
Test Inst.
b.
Drywell LPCI "A" E12-F041A 313(I)
LPCI "8" E12-F041B 314(I)
LPCI "B" E12-F236 314(0)
CRD to Recirc.
833-F013A 326(I)
Pump A Seals GRAND GULF-UNIT 1 3/4 6-41 Amendment No. 24
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TABLE 3.5.4-1 (Continued) i CONTAINMENT ANO DRWELL ISCLATION VALVES SYSTEM AND VALVE NUMBER PENETRATION
_ NUMBER Devwell (Gentinued)
CR0 toitectre.
833-F017A 326(0)
Pump A Seals Instrument Air PS3-F008 335(I)
Staney Liquid C41-F007 328(I)
Control
. Standby Liquid C41-F006 328(0)
Control Cont. Cooling P42-F115 329(!)
Water Supply Drywell Chf11ed P72-F147 332(I)
Water Supply l
Condensate Flush 833-F204 333(I)
Conn.
Condensate Flush 833-F205 333(0)
Conn.
Combustible Gas E61-F002A 339(0)
Control Combustible Gas E61-F0028 338(0)
Control.
Combustible Gas E61-F004A 340(0)
Control Combustible Gas E61-F0048 340(0)
Control
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14per Containment G41-F265 342(0) 1 Pool Orsin CAD to Recire.
833 F0138 346(I)
Pump 8 seals CR0 to Rectre.
833-F0178 344(0)
Pamp B Seals Service Air PS2-F196 363(I)
Cont. Leak Rate M61-F021 434A(I)
Test Inst.
s l
Cont. Leak Rate M61-F020 438A(0) sys.
-8 LINO FLANGES Cont. Leak Rate NA 40(!)(0)
Sys.
Cont. Leak Rate NA.
Sys.
82(I)(0) i Containment NA 343(I)(0)
Leak Rate System GRAND GULF-UNIT 1 3/4 6-42 Ameneent No.21l
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m y-y, y
_ TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER Containment (Continued)
RHR "B" Test Line E12-F350 67(0)(c)
T/C RHR "B" Test Line E12-F312 67(0)(c)
T/C RHR "B" Test Line E12-F305 67(0)(c)
T/C Refueling Water P11-F425 69(0)IC)
Transf. Pump Suction T/C Refueling Water P11-F132 69(0)(c)
Transf. Pump Suction T/C Inst. Air to AOS PS3-F043 70(0)
T/C Post Acc. Sample E12-F409 71B(I)(c)
Return and RHR "C" Relief Valve Vent Ndr. to Suppr.
Pool T/C Post Acc. Sample E12-F408 71B(0)(c)
Return and RHR "C" Relief Valve Vent Hdr. to Suppr.
Pool T/C Cont. Leak Rate M61-F010 82(I)
T/C RWCU To Feedwater G33-F055 83(0)
T/C Suppr. Pool P60-F011 85(0)
Cleanup T/C Suppr. Pool P60-F034 85(0)
Cleanup T/C RWCU Pump Suction G33-F002 87(0)
T/C RWCU Pump G33-F061 88(0)
Discharge T/C SSW T/C P41-F163A 89(0)(c)
SSW T/C P41-F163B 92(0)(c) b.
Orwell LPCI "A" T/C E12-F056A 313(0) l LPCI *B" T/C E12-F056B 314(0)
Instrument Air T/C P53-F493 335(0) i SLCS T/C C41-F026 328(0)
Service Air T/C P52-F476 363(0)
RWCU T/C G33-F120 366(I)
Reactor Sample 833-F021 465(0)
T/C GRAND GULF-UNIT 1 3/4 6-45 Amendment No. 24 l
CONTAINMENT SYSTEMS 3/4.6.5 DRYWELL VACUUN RELIEF
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i LIMITING CONDITION FOR OPERATION 3.6.5 Bott1 drywell post-LOCA vacuum relief subsystems and both drywell purge s
vacuum relief subsystems shall be OPERA 8LE with associated vacuum breakers and i
isolation valves closed.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
i AFTE:
T 1
With one of the drywell post-LOCA vacuu? relief subsystems and/or one of a.
the drywell purge vacuum relief subsysta.4 inoperable for opening but.
known to be closed, restore the inoperable subsystem (s) to OPEAA81.E status within 30 days or be in at least HOT SHUTD0WN 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 C0.'D SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
but known to be closed, provided that both of the drywell pu relief subsystems are OPERA 8LE, restore the inoperable subsystems to OPERA 8LE status within 30 days or be in a 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 />.
With two of the post-LOCA vacuum relief subsystems and one of the drywell c.
purge vacuum relief subsystems inoperable for opening but known to be closed, restore one inoperable subsystem to OPERA 8LE status within 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 />.72 hours or be in at
)
i
)
d.
With one of the drywell isolation vacuum breakers open, restore the open 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 SHUTDOW l
ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i l
e.
With the position indicator of an OPERA 8LE drywell vacuum breaker or l
associated feelation valve of the drywell vacuum relief subsystems
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least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by local indication. inoperable, verify the vacuum
$NUTDOWN 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 t following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
$URVEILLANCE REQUIREMENTS 4.6.5 valve shall be:Each post-LOCA and purge system vacuum breaker and asscciated isolation i
s.
Verified closed at least once per 7 days.
i GRAND OULF-UNIT'1 3/4 6-44 AmenhentNo.21l Effective Date:
OCT 2 01986
+