Text

Amend 109 to License NPF-29,removing Unnecessary Operability Requirements for IRMs & APRMs During Shutdown Operations from TS
	ML20062L020
Person / Time
Site:	Grand Gulf
Issue date:	12/13/1993
From:	Beckner W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20062L022	List: ML20062L020; ML20062L023;
References
	NUDOCS 9312290106
	Download: ML20062L020 (16)
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a nco b

4 UNITED STATES f

Yi E NUCLEAR REGULATORY COMMISSION I

~

E WASHINGTON, D.C. 20555-0001

,,a~...*j ENTERGY OPERATIONS. INC.

SYSTEM ENERGY RESOURCES. INC.

SOUTH MISSISSIPPI ELECTRIC PO ER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. NPF-29.

l.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated May 20, 1993, 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; C.

There is reasonable assurance g ) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such act-Ivities 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.

i

?

9312290106 931213 DR ADOCK 0500 6

l

4 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:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Prstection Plan contained in Appendix B, as revised through Amendment No.109, 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 T

t ly,'gb6< LO* b $

William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 13, 1993 i

2 4

S ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 i

Replace the following pages of the Appendix A Technical Specifications with I

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 3-1 3/4 3-1 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-53 3/4 3-53 3/4 3-54 3/4 3-54 3/4 3-55 3/4 3-55 3/4 3-55a 3/4 3-55a i

3/4 3-56 3/4 3-56 3/4 3-57 3/4 3-57 3/4 10-3 3/4 10-3 3/4 10-4 3/4 10-4 i

-[

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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 channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip 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 CNECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations 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 reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 APPLICABLE MINIMUM OPERATIONAL OPERABLE CHANNELS FUNCTIONAL UNIT CONDITIONS PER TRIP SYSTEM (al ACTION 1.

Intemediate Range Monitors:

a.

Neutron Flux - High 2(,,,,3 b.

Inoperative 2(')

3 1

5 3

3 l

2.

Average Power Range Monitor < bite),

a.

Neutron Flux - High, Setdown 2

3 1

b.

Flow Blased Simulated Thermal Power - High 1

3 4

c.

Neutron Flux - High 1

3 4,

d.

Inoperative 1, 2 3

1 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, il

2 4

Level 8 6.

Main Steam Line Isolation Valve -

il

4 4

Closure j

7.

Main Steam Line Radiation - High 1, 2(d) 2 5

8.

Drywell Pressure - High 1, 2"3 2

1 GRAND GULF-UNIT 1 3/4 3-2 Amendment No. 109

y TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a)

A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

(b)

The " shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn

per Specification 3.9.2 and shutdown margin demonstrations performed per Specification 3.10.3.

(c)

An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.

(d)

This function is not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.

(e)

This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

(f)

This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required.

(g)

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(h)

This function shall be automatically bypassed when operating below the appropriate turbine first stage pressure setpoint of:

(1) s 26.9%** of the value of turbine first-stage pressure at valves wide open (VWO) steam flow when operating with rated feedwater temperature of greater than or equal to 420*F, or (2) s 22.5%** of the value of turbine first-stage pressure at VWO steam flow when operating with rated feedwater temperature between 370*F and 420'F.

(1)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- Allowable setpoint values of turbine first-stage pressure equivalent to THERMAL POWER less than 40% of RATED THERMAL POWER.

GRAND GULF-UNIT 1 3/4 3-5 Amendment No. 6h 109

TABLE 3.3.1-2

[

E g

REACTOR PROTECTION SYSTEM RESPONSE TIMES E

4; 1

4 FUNCTIONAL UNIT RESPONSE TIME 5

(seconds)

-4 1.

L

. Intermediate Range Monitors:

a.

Neutron Flux - High NA b.

Inoperative

' NA 2.

Average Power Range Monitor *:

a.

Neutron Flux - High, Setdown NA b.

' Flow Biased Simulated Thermal Power - High

< 0.09**

c.

Neutron Flux - High I 0.09 d.

Inoperative NA 3.

Reactor Vessel Steam Dome Pressure - High s

4.

Reactor Vessel Water Level - Low, level 3

- < 0.35 5.

Reactor Vessel Water Level - High, level 8 5 1.05 u,

a 6.

Main Steam Line Isolation Valve - Closure 5 1.05

< 0.06 7.

Main Steam Line Radiation - High RA 8.

Drywell Pressure - High NA 9.

Scram Discharge Volume Water level - High NA 10.

Turbine Stop Valve - Closure

< 0.10 11.

Turbine Control Valve Fast Closure, Valve Trip System

~

i Oil Pressure - Low

< 0.10, 12.

Reactor Mode Switch Shutdown Position HA 13.

Manual Scram NA

Neutron detectors are exempt from response time testing.

Response time shall be measured l

f rom the detector' output or from the input of the first electronic component in the. channel.

- Not including simulated thermal power time constant.

Measured from start'of turbine control valve fast' closure.

t 5

4

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-mm

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i--e--o---,---

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TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVElllANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CAllBRATION SURVEILLANCE REQUIRED 1.

Intermediate Range Monitors:

a.

Neutron Flux - High S/U. S,(6)

S/U, W R

2 S

W R

5(*'

b.

Inoperative NA W

NA 2, 5(*)

2.

Average Power Range Monitor:"'

a.

Neutron Flux - High, S/U, S,(6)

S/U, W SA 2

Setdown l

b.

Flow Biased Simulated Thermal Power - High S,

Q W(d"*',

SA, R"'

1 c.

Neutron Flux - High S

Q W(d', SA 1

d.

Inoperative NA Q

NA 1, 2 l

3.

Reactor Vessel Steam Dome 0

Pressure - High S

Q R(

1, 2 '

4.

Reactor Vessel Water level -

Low, level 3 S

Q R(

1, 2 5.

Reactor Vessel Water Level -

High, level 8 S

Q R(')

1 6.

Main Steam Line Isolation Valve - Closure NA Q

R 1

7.

Main Steam Line Radiation -

0 High S

Q R

1, 2 '

8.

Drywell Pressure - High S

Q R(

1, 2(*'

GRAND GULF-UNIT 1 3/4 3-7 Amendment No. 6h91 109 T

TABLE 4.3.1.1-1 (cmticmn REAC70R PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT

- CHECK __

TEST CALIBRATION SURVEILLANCE REQUIRED 9.

Scram Dischag e Volume Water Level - High a.

Transmitter / Trip Unit S

Q R")

1, 2, 5"'

b.

Float Switch HA Q

R 1, 2, 5")

10. Turbine Stop Valve - Closure S

Q R")

1

11. Turbine Control Valve Fast Closure Valve Trip System 011

"-essure - Low S

Q R")

1

12. Reactor Mode Switch Shutdown Position NA R

NA 1,2,3,4,5

13. Hanual Scram NA W

NA 1, 2, 3, 4,'5 (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the previous 7 days.

(c'l With any control rod withdrawn from a core cell containing one or more fuel assemblies.

l (d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER 25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

I; ;l The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.

I 1 Calibrate trip unit at least once per 92 days.

I i Deleted.

/ l This calibration shall consist of verifying the 6 i I second simulated thermal power time constant.

/

l Not applicable when the reactor pressure vessel head is unbolted or removed per Specification 3.10.1.

i fll1)lNotapplicablewhenDRYWELLINTEGRITYisnotrequired.Not applicable to control rods removed per Specifica-Applicable with any control rod withdrawn.

tion 3.9.10.1 or 3.9.10.2.

GRAND GULF-UNIT 1 3/4 3-8 Amendment No. 67 91T109 T

TABLE 3.3.6-1 CONTROL ROD BLOCK INSTRUMENTATION MINIMUM APPLICABLE OPERABLE 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

If 60 2.

Deleted 3.

SOURCE RANGE MONITORS a.

Detector not full in

4 2ff 61 2**

5 62 b.

Upscale (*)

4 2ff 61 2**

5 62 Inoperative

4 2ff 61 c.

2**

5 62 '

d.

Downscale"3 4

2ff 61 2**

5 62 4.

Deleted l

5.

SCRAM DISCHARGE VOLUME a.

Water Level High 2

1, 2, 5*

64 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.

Upscale 3

1 64 7.

REACTOR MODE SWITCH SHUTDOWN POSITION 2

3, 4 63 GRAND GULF-UNIT I 3/4 3-53 Amendment No. 59,101,105, 109

INSTRUMENTATION TABLE 3.3.6-1 (Continu:d)

CONTROL ROD BLOCK INSTRUMENTATION

' ACTION Declare the RPCS inoperable and take the ACTION required by ACTION 60 Specification 3.1.4.2.

With the number of OPERABLE Channels:

ACTION 61 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.

r ACTION 63 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, initiate a rod block.

With the number of OPERABLE channels less than required by the ACTION 64 Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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.

Whenever the related function is not bypassed as specified in notes (a) through (c).

(a) This function shall be automatically by; issed if detector count rate is

> 100 cps or the IRH 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 'igher.

(d) Deleted l

GRAND GULF-UNIT 1 3/4 3-54 Amendment No. 69,101,105, 109

TABLE 3.3.6-2

[

CONTROL R0D BLOCK INSTRUMENTATION SETPOINTS TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE 1.

ROD PATTERN CONTROL SYSTEM a.

Low Power Setpoint 20 + 15, -0% of RATED THERMAL 20 + 15. -0% of RATED THERMAL POWER POWER b.

High Power Setpoint

$70% of RATED THERMAL POWER 570% of RATED THERMAL POWER 2.

Deleted 3.

SOURCE RANGE MONITORS a.

Detector not full in NA NA b.

Upscale s 1 x 10 cpss 1.5 x 10 cps, 5

5 c.

Inoperative NA

- NA d.

Downscale 2 0.7 cps 2 0.5 cps 4.

Deleted 5.

SCRAM DISCHARGE VOLUME a.

Water Level-High s 32 inches s 33.5 inches 6.

REACTOR COOLANT SYSTEM RECIRCULATION FLOW

a.. Upscale s 111% of rated flow s 114% of rated flow 7..
REACTOR MODE SWITCH SHUTDOWN POSITION NANA l
' GRAND GULF-UNIT 1
3/4 3-55 Amendment No. Mr 109 l
.m..-
m.
m..m.
m m.
ma.
m
-m..
, ~.... - - -
..,s.
.s--
~.. _ -., _ _,,,,.
.,_,,m
~
INSTRUMENTATION TABLE 4.3'.6-1 (Continued)
CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REOUIREMENTS NOTES:
i a.
Neutron detectors may be excluded from CRANNEL CALIBRATION.
b.
Within 7 days prior to startup.
c.
[ Deleted]
d.
[ Deleted) e.
[ Deleted) f.
[ Deleted) g.
[ Deleted)
I h.
[ Deleted]
With any control rod withdrawn. Not applicable to control rods removed 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 b
i i
GRAND GULF-UNIT 13/4 3-57 Amendment No. 15,49,101, 109
TABLE 4.3.6-1 CONTROL R00 BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION (*)
SURVEILLANCE REQUIRED 1.
R00 PATTERN CONTROL SYSTEM a.
Low Power Setpoint NA S/U*), Q Q
1, 2
b. High Power Setpoint NA S/U*), Q Q
1**
2.
Deleted 3.
SOURCE RANGE MONITORS a.
Detector not full in NA S/U,W NA 2ff, 5 b.
Upscale NA S/U,W Q
2ff, 5 i
c.
Inoperative NA S/U,W NA 2ff, 5,
d.
Downscale NA S/U,W Q
2ff, 5-i 4.
Deleted 5.
SCRAM DISCHARGE VOLUME-a.
Water Level-High NA Q
R 1, 2, 5*
6. ' REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.. Upscale NA Q
Q l
7.
REACTOR MODE SWITCH SHUTDOWN POSITION NA R
NA 3, 4 I
t GRAND GULF-UNIT 1 3/4 3-56 Amendment No. 10,07,101,109
. t
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n,
-e,n.,,E.,,..,<.w.-+
,,w..,-
.e,,;ew,-+,-~~--,.
,,~s,w-
,~~.-r--,
,,,,~,a
~w,,,.v.
.n.c Se,,r.-,w..,-,s.
n
,,~e.---
-,-,,--,---+-.<rew'
SPECIAL TEST EXCEPTIONS 3/4.10.3 SHUTDOWN KARGIN DEMONSTRATIONS LIMITING CONDITION FOR OPERATION 3.10.3 The provisions of Specification 3.9.1, Specification 3.9.3 and Table 1.2 may be suspended to permit the reactor mode switch to be in the Startup position and to allow more than one control rod to be withdrawn for shutdown margin demonstration, provided that at least the following requirements are satisfied.
a.
The source range monitors are OPERABLE per Specification 3.9.2 with the RPS circuitry " shorting links" removed.
b.
The rod pattern control system is OPERABLE per Specification 3.1.4.2, or conformance with the shutdown margin demonstration procedure is verified by a second licensed operator or other technically qualified member of the unit technical staff.
c.
The " continuous withdrawal" control shall not be used during out-of-sequence movement of the control rods.
d.
No other CORE ALTERATIONS are in progress.
e.
The Average Power Range Monitors are OPERABLE per the requirements of Specification 3.3.1 for OPERATIONAL CONDITION 2.
APPLICABILITY: OPERATIONAL CONDITION 5, during shutdown margin demonstrations.
ACTION:
With the requirements of the above specification not satisfied, immediately place the reactor mode switch in the Shutdown or Refuel position.
SURVEILLANCE REQUIREMENTS 4.10.3 Within 30 minutes prior to and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during the performance of a shutdown margin demonstration, verify that; a.
The source range monitors are OPERABLE per Specification 3.9.2 l
with the RPS circuitry " shorting links' removed.
b.
The rod pattern control system OPERABLE, or a second licensed operator or other technically qualified member of the unit technical staff is present and verifies compliance with the j
shutdown demonstration procedures, and c.
No other CORE ALTERATIONS are in progress.
Grand Gulf-Unit 1 3/4 10-3 Amendment No.109 4
I SPECIAL TEST EXCEPTIONS i
3/4.10.4 RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION i.
3.10.4 The requirements of Specifications 3.4.1.1 and 3.4.1.3 that recirculation loops be in operation may be suspended for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the performance of:
a.
PHYSICS TESTS, provided that THERMAL POWER does not exceed 5% of RATED THERMAL POWER, or b.
The Startup Test Program.
APPLICABILITY:
OPERATIONAL CONDITIONS 1 and 2, during PHYSICS TESTS and the Startup Test Program.
ACTION:
a.
With the above specified time limit exceeded, insert all control rods.
b.
With the above specified THERMAL POWER limit exceeded during PHYSICS TESTS, immediately place the reactor mode switch in the Shutdown position.
SURVEILLANCE REQUIREMENTS 4.10.4.1 The time during which the above specified requirement has been. suspended shall be verified to be less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at least once per hour during PHYSICS TESTS and the Startup Test Program.
4.10.4.2 THERMAL POWER shall be determined to be less than 5% of RATED THERMAL POWER at least once per hour during PHYSICS TESTS.
o GRAND GULF-UNIT 1 3/4 10-4 i

ML20062L020

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