ML20206D086
| ML20206D086 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/14/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206D091 | List: |
| References | |
| NUDOCS 8811160532 | |
| Download: ML20206D086 (7) | |
Text
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k UNITED STATES NUCLEAR REGULATORY COMMISSION o
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WASHING TON, D. C. 20666
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MISSISSIPPI POWER & LIGHT COMPANY SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Commissicn) has found that A.
The application for ar,endment by System Energy Rescurces, Inc.,
(the licensee), dated June 21, 1908, 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 (1) 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 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.
831116053? G81114 DR ADOCK 0000 6
1
. 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 fio. NPF-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment lio. 49, are hereby incorporated into this license. System Energy Resources, Inc. shall operate the f acility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE tiUCLEAR REGULATORY C0PMISSION Original signed by D. Verrelli for Elinor G. Adensam, Director Project Directorate !!-1 Division of Reactor Projects 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance: November 14, 1988 DT[:
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ATTACHMENT TO LICENSE AMENDMENT NO. 49 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 An.endment number and contain vertical li.ies indicating the area of change.
Remove Insert 3/4 3-53 3/4 3-53 3/4 3-54 3/4 3-54 3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57
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TABLE 3.3.6-1 x
CONTROL R00 BLOCK INSTRUNENTATION E
G MINIMUM APPLICABLE l-OPERA 8LE CHANNELS OPERATIONAL TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION 1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpoint 2
1, 2 60 b.
High Power Setpoint 2
1#
60 l
2.
APRM a.
Flow Biased Neutron Flux-Upscale 6
1 61 b.
Inoperative 6
1, 2, 5 61 c.
Downscale 6
1 61
{
d.
Neutron Flux - Upscale, Startup 6
2, 5 61 Y
3.
SOURCE RANGE MONITORS Detector not full in("'*)
4 2
61 a.
2**
5 62 b.
Upscale (b) 4 2
61 2**
5 62 Inoperative (b) 4 2
61 c.
2**
5 62 d.
Downscale(C) 4 2
61 2**
5 62 4.
9 a.
Detector not full in 6
2, 5 61 E
b.
Upscale 6
2, 5 61 G
c.
Inoperati 6
2, 5 61-Downscale{g) l d.
6 2, 5 61 l
5 5.
a.
Water Level-High 2
1, 2, 5*
62 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale 3
1 62 7.
REACTOR MODE SWITCH SHUTDOWN POSITION 2
3, 4 63
INSTRUMENTATION TABLE 3.3.6-1 (Continued)
CONTROL R00 BLOCK INSTRUMENTATION ACTION ACTION 60 Declare the RPCS inoperable and take the ACTION required by Specification 3.1.4.2.
ACTION 61 With the numb c of CPERABLE Channels:
a.
One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour.
b.
Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour.
'With the number of OPERABLE channels less than required by the ACTION 62 Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.
ACTION 63 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.
NOTES With more than one control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
OPERABLE channels must be associated with SRMs required OPERABLE per Specification 3.9.2.
With THERMAL POWER greater than the Low Power Setpoint.
j (a) This function shall be automatically bypassed if detector count rate is t
> 100 cps or the IRM channels are on range 3 or higher.
(b) This function shall be automatically bypassed when the associated IRM channels are on range 8 or higher.
(c) This function shall be automatically bypassed when the IRM channels are on range 3 or higher.
(d) This function shall be automatically bypassed when the IRM channels are on range 1.
(e) The provisions of Specification 3.0.4 are not applicable for entering OPERATIONAL CONDITION 5.
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GRAND GULF-UNIT 1 3/4 3 54 Amendment No.
49
y TABLE 4.3.6-1 z
CONTROL R00 BLOCK INSTRJMENTATION SURVEILLANCE REQUIREMENTS C
U CHANNEL OPERATIONAL E
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION (a3 SUP.'.'EILLANCE REQUIRED 1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpo.~it NA S/U(b),M Q
1, 2 I) b.
High Power Setpoint NA S/U
,M Q
1**
2.
APRM a.
Flow Biased Neutron Flux-II)(9' s
Upscale NA W
W SA 1
b.
Inoperative NA 3/U,W Wg) 1, 2, 5 N
c.
Downscale NA W
, SA 1
{
d.
Neutroa Flux - Upscale, Startup NA S/U(b) M Q
2, 5 y
3.
SOURCE RANGE MONITORS E
a.
Detector not full in NA S/U,W NA 2, 5 b.
Upscale NA S/U,W Q
2, 5 c.
Inoperative NA S/U,W NA 2, 5 d.
Downscale NA S/U,W Q
2, 5 4.
INTERMEDIATE RANGE MONITORS a.
Detector not full in NA S/U,W NA 2, 5 b.
Upscale NA S/U,W Q
2, 5 c.
Inoperative NA S/U,W NA 2, 5 d.
Downscale NA S/U,W Q
2, 5 g
5.
a.
Water Level-High NA M
R 1, 2, 5*
j 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW
]
a.
Upscale NA M
Q 1
o 7.
REACTOR MODE SWITCH SHUTDOWN POSITION NA R
NA 3, 4 i
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INSTRUMENTATION TABLE 4.3.6-1 (Continued)
CON 1ROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:
a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
b.
Within 7 days prior to startup, c.
[ Deleted) d.
[ Deleted]
e.
[ Deleted]
f.
This calibration shall consist of t'.e adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater than or equal to 4
25% of RATED THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.
g.
This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.
h.
This calibration shall consist of verifying the trip setpoint only.
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
With THERHAL POWER greater than the Low Power Setpoint.
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GRAND GULF-UNIT 1 3/4 3-57 Amendment No. Ah, 49 i
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