ML20099G077
| ML20099G077 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 08/10/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099G080 | List: |
| References | |
| NUDOCS 9208140089 | |
| Download: ML20099G077 (13) | |
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- o-UNITED STATES lt 4E; NUCLEAR REGULATORY COMMISSION o,
. WASHINoTON. D.C. 20%S X
o $g-d ENTERGY OPERATIONS. INC.
SYSTEM ENERGY RESOURCES. IN L SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No NPF-29 1.
The Nuclear Regulatory Commission- (the Commission) has found that:
A.
The application'for amendment by Entergy~0perations. Inc. (the licensee) dated April 30, 1992, complies with the standards and requirements of:the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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;-
I C.-
~ There is reasonable assurance (i) that the activities authorized by-
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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 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 satisfied.
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9208140089:920810
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2.
Ac'cordingly. 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:
(2)- Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection plan contained-in-Appendix B, as revised through Amendment No.101, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility 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 NUCLEAR REGULATORY COMMISSION
-f,,v John T. Larkins,. Director Project Directorate IV-I Division of. Reactor Projects III/IV/V Office-of Nuclear Reactor Regulation
Attachment:
' Changes.to the: Technical Specifications
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' Date of Issuance: ; August' 10,;1992-t 4
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ATTACHMENT TO LICENSE AMEN 9 MENT NO. 101 FACILITY OPERATING Ll([NSE 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.=nd contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 3/4 3-1 3/4 3-1 3/4 3-52 3/4 3-52 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 3/4 3-77 3/4 3-77
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in. Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
APPLICABILITY:
As shown in Table 3.3.1-1.
ACTION:
With the number of OPERABLE channels less than required by the Minimum a.
OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel and/or that trip system in the tripped condition
- within twelve hours, b.
With the number of OPERABLE chaanels less than required by the Minittum OPERABLE Channals per Trip System requirement for both trip systems, place at least one tiip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operationc for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.
4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.
4.3.1.3 The-REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactnr trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at les t once per 18 months.
Each test shall include at least one chan-nel per trip' system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.
4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the
' Channel Functional Test surveillance for the Intermediate Range Monitors for entry into the applicable OPERATIONAL CONDITIONS (as specified in Table 4.3.1.1-1) from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.
- An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these cases, the inoperable channel shall be restored to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or the ACTION required by Table 3.3.1-1-for that Trip Function shall be taken.
- The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.
GRAND GULF-UNIT 1 3/4 3-1 Amendment No. $,101
TABLE 3.3.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLL MINIMUM c)
E OPERATIONAL OPERABLE CHANNELS T
FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (a)
ACTION 1.
a.
Heutron Flux - High 2
3 1
3, 4 3
2 5(b) 3 3
b.
Inoperative 2
3 1
3, 4 3
2 5
3 3
IC}-
2.
Average Power Range Monitor a.
Neutron Flux - High, Setdown 2
3 1
R 3
3 2
ID)
S 3
3 b.
Flow Biased Simulated Thermal Power - High 1
3 4
c.
Neutron Flux - High 1
3 4
d.
Inoperative 1, 2 3
1 3
3 2
5 3
3 3.
Reactor Vessel Steam Dome Pressure - High 1, 2(d) 2 1
4.
Reactor Vessel Water Level - Low, Level 3 1, 2 2
1 5.
Reactor Vessel Water Level-High, I ')
2 4
I-Level 8 6.
Main Steam Line Isolation Valve -
I ")
4 4
I Closure 7.
Main Steam Line Radiation - High 1, 2(d) 7 5
1, 2 ' }
2 1
I 8.
Drywell Pressure - High
4 m
i E-g TABLL'4;3.5.1-1 o
REACTOR' CORE ISOLATION' COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE' REQUIREMENTS
.q ch -
CHANNEL'
- E.
CHANNEL FUNCT10NAL CHANNEL FUNCTIONAL UNITS.
-CHLCK TEST CAllBRATION.
w a.
Reactor Vessel Water' Level -
R ')
I Low Low, level'2 S-M b.
Reactor Vessel Water-S
- M R
'. Level.- High, level 8 c.
Condensate Storage Tank Level - Low S
M R
d.
Suppression Pool' Water Level -
.High S-M R
y e.
Manual Initiation NA-M(b)'
NA
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(a) Calibrate trip unit a2'least once per 31 days.
(b) Manual initiation switches'shall be tested at'least once per _8 months during shutdown. All other 1
circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL 1EST at least once per 31 days as a part of circuitry required.to be tested for' automatic system actuation.
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INSTRUMENTATION 3/4.3.6 CONTROL R0D BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.
The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Satpoint column of Table 3.3.6-2.
APPLICABILITY: As shown in Table 3.3.6-1.
ACTION:
a.
With a control rod block instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.
SURVEILLANCE REQUIREMENTS 4.3.6.1 Each of the above required control rod block trip systems and I
instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.6-1.
4.3.6.2 The provisions of Specification 4.0.4 are not applicable to the Channel Functional tes. surveillances for the Intermediate Range Monitors and Source Range monitors for entry into their applicable OPERATIONAL CONDITIONS (as.specified in Table 4.3.6-1) from 0PERATIONAL CONDITI0h 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.
GRAND GULF-UNIT 1-3/4 3-52 Amendnent No.101
m, TABLE 3.3.6-1 E
o CONTROL ROD BLOCK INSTRUMENTATION E
G; MINIMUM APPLICABLE OPERABLE CHANNELS OPERATIONAL 5
TRIP FUNCTION PER TRIP FUNCTION CONDITIONS ACTION _
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1.
ROD PATTERN CONTROL SYSTEM a.
Low Power Setpoint 2
1, 2 60 b.
High Power Setpoint 2
1#
60 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 g
1 3.
SOURCE RANGE MONITORS Detector not full in(a) 4 2##
61 l
m J,
a.
w 2**
5 62 b.
Upscale (b) 4 2##
61 l
2**
5 62 Inoperative (b) 4 2##
61 c.
2" 5
62 d.
Downscale(c) 4 2##
61 l
2**
5 62
[
4.
a.
Detector not full in 6
2, 5 61 S
b.
Upscale 6
- 2. 5 61 A
Inoperati 6
2, 5 61 c.
Downscale{g) g d.
6 2, 5 61 5.
Water Level-High 2
1, 2, 5*
62 5
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 number of OPERABLE 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.
ACTION 62 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within one hour.
ACU ON G3 -
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 withe' wn.
Not appiicable to control rods
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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 greator than the Low Power Setpoint.
Whenever the related function is not bypassed as specified in notes (a) through (c).
l (a) This function shall be automatically bypassed if detector count rate is
> 100 :ps or the IRM channels are on range 3 or higher.
f (b) This function shall be automatically bypassed when the associatec 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.
GRAND GULF-UNIT 1 3/4 3-54 Amendment No. $9,101
n TABLE-4.3.6-1 5
g, CONTROL R0D BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS-oc:
CHANNEL OPERATIONAL:
E
-CHANNEL FUNCTIONAL
-CHANNEL CONDITIONS'FOR WHICH' j
TRIP FUNCTION-CHECK TEST CALIBRATION (a)-
. SURVEILLANCE REQUIRED:
x]
1.
ROD PATTERN CONTROL SYSTEM' a.
Low Power Setpoint-NA S/U(b) 9 9
1, 2
[
S/U( ), Q
-Q 1**
b.
High Power Setpoir.t NA.
2.
APRM a.
Flow Biased Neutron Flux-II)(9)
Upscale N.9 Q
W
, SA 1
b.
- Inoperative -
NA
'S/U,Q-Ng) 1, 2, 5 c.
Downscale NA Q
W
, SA 1
S/U(b) Q Q
2, 5 g
d.
Neutron Flux - Upscale, Startup NA
[
3.
SOURCE RANGE MONITORS i
E a.
Detector not full in NA S/U,W NA 2,## 5 b.
Upscale NA 5/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 t
k 5.
a_
Water Level-High NA Q
R 1, 2, 5*
5 6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW I
a.
Upscale NA Q
Q 1
7.
REACTOR MODE SWITCH SHUTDOWN
-POSITION NA R
NA 3, 4 e_.
t a
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INSTRUMENTATION TABLE 4.3.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS NOTES:
a.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
b.
Within 7 days price to startup.
c.
[Celeted]
d.
[ Deleted]
e.
[ Deleted]
f.
This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a beat 031ance during OPERATIONAL CONDITION 1 when THERMAL POWER is greater tnan or equal to 25% of RATED THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL F0WER.
g.
This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal, b.
This calibration shall censist of verifying the trip setpoint only.
With any control rod withdrawn.
Not applicable to control rods re,r.oved per Specification 3.9.10.1 or 3.9.10.2.
With THERMAL POWER greater than the Low Power Setpoint.
Whenever the related function is not bypassed as specified in Table 3.4.6-1 notes (a) through (c).
I GRAND GULF-UNIT 1 3/4 3-57 Amendment No. I6, H,101
INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPERATION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE.
a.
In OPERATIONAL CONDITION 2*, four.
b.
In OPERATIONAL CONDITION 3 or 4, two.
A_PPLICABILITY:
OPERATIONAL CONDITIONS 2*, 3 and 4.
ACTION:
In OPERATIONAL CONDITION 2* with one of the above required source a.
range monitor channels inoperable, restore at least 4 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 />.
b.
In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable con-trol rods to be fully inserted in the core and le d the reactor mode switch in the Shutdown position within ore hour.
SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:
a.
Performance of a:
1.
CHANNEL CHECK at least once per:
a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in OPERATIONAL CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION-3 or 4.
2.
CHANNEL CALIBRATION ** at least once per 18 months.
b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 7 days prior to moving the reactor mode switch from the Shutdown position, and 2.
At least once per 31 days #.
c.
Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps with the detector fully inserted.
- With IRM's on range 2 or below.
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
- The provisions of Specification 4.0.4 are not applicable to the Source Range Monitor Channel Functional test surveillances for entry into OPERATIONAL CONDITIONS 2*, 3 or 4 from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.
GRAND GULF-UNIT 1 3/4 3-77 Amendment No. 101
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~ 1NSTRUMENTA110N TRAVERSIN3 IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7.
The traversing in-core probe system shall be OPERABLE with:
Five movable detectors, drives and readout equipment to map the core, a.
and b.
Indexing equipment to allow all five detectors to be calibrated in a common location.
APPLICABILITY:
When the traversing in-core probe is used for:
Recalibration of the LPRM detectors, and a.
b.*
Monitoring the APLHGR, LHCR, MCPR, or'MFLPD.
ACTION:
With the traversing in-core probe system inoperable, do not use the system for the above applicable monitoring or calibration functions. The provisions of Specification 3.0.3 are not applicable.
l SURVEltLANCE RE'dIREMENTS a
4.3.7.7 The traversing in-core probe system shall oe demonstrated.0PERABLE by normalizing each of the'above required detector outputs within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to use when required for the LPRM calibration function.
"Only tne detector (s) inL the location (s) of interest are required to be.0PERABLE.
1 GRAND GutF-UNIT 1-3/4 3-78 Amendment No. 69 l h
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