IR 05000348/1998300
| ML20217A544 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/06/1998 |
| From: | Aiello R, Peebles T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217A433 | List: |
| References | |
| 50-348-98-300, 50-364-98-300, NUDOCS 9804220279 | |
| Download: ML20217A544 (131) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION II
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Docket Nos.-
50-348, 50-364 License Nos..
NPF-2 NPF-8 Report Nos.-
50-348.364/98-300 Licensee:
Southern Nuclear Power Company Facility:
Farley Nuclear Plant Location:
Columbia. AL Dates:
March 12 -13, 1998 f
Examiners:
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RonaTfF. Aiello. Chief License Examiner
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Approved by:
Thomas A. Peebles. Chief Operator Licensing and Human Performance Branch Division of Reactor Safety I
l 9804220279 980406 PDR ADOCK 05000348 V
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- EXECUTIVE SUMMARY Farley Nuclear Plant NRC Examination Report No. 50-348. 364/98-300 On March 12 and 13. 1998. The NRC conducted an announced operator licensing written and JPM re-take examination in accordance with the guidance of Examiner Standards. NUREG-1021. Interim Revision 8.
These examinations implemented the operator licensing requirements of 10 CFR S55.43 and 55.45.
Doerations One SR0 candidate received a written re-take examination.
This
examination was administered by the facility on March 12. 1998.
One SRO candidate received a JPM re-take examination. The NRC
administered this examination on March 13, 1998.
Candidate Pass / Fail
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SRO R0 Total Percent Pass
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100%
Fail
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0%
i The examiner concluded that the candidates' performance on the written
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and JPM examinations were satisfactory.
(Section 05.3).
Reoort Details
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Summary of Plant Status During the period of the examination, both units were in Mode 1.
I. Ooerations
Operator Training and Qualifications 05.1 General Comments The Licensee developed operator licensing initial written and JPM re-
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take examinations, under the guidance of the NRC, to be administered by
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the facility and the NRC respectively under the requirements of an NRC security agreement, in accordance with the guidelines of the Examiner Standards (ES). NUREG-1021. Interim Revision 8.
One SR0 upgrade re-take applicant received and passed the written examination.
One SR0 upgrade re-take applicant received and passed the JPM operating examination.
05.2 Pre and Post-Examination Activities
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l a. Scope
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The NRC reviewed the licensee's examination submittal using the
criteria specified for examination development contained in NUREG 1021 Interim Rev 8.
b. Observations and Findinas The licensee developed the SRO written and JPM retake examinations.
All materials were submitted to the NRC on time.
The Chief Examiner reviewed, modified and approved the examination prior to administration.
The NRC conducted in-office and onsite preparation prior to examination administration.
The examination met the
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criteria set forth in NUREG 1021 Interim Rev. 8.
The written examination was reviewed and approved in the regional of fice.
Four of the written examination questions contained significant technical errors that resulted in either question deletion or answer modification (See enclosure 3 for details).
These types of errors should have been identified during the facility's technical and managerial reviews.
The NRC conducted the preparation visit for the operating exam on
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- March 12. 1998.
One JPM set was validated.
There were no direct look-up JPM follow-up questions. Most of the JPM follow-up questions were either comprehensive or analytical.
c. Conclusion The NRC concluded that the facility had placed emphasis on ensuring that the examination was technically accurate, with a few exceptions (see Enclosure 3), and discriminating.
05.3 Examination Results and Related Findinas. Observations. and Conclusions a.
General The chief examiner reviewed the results of the written and JPM exr;cinations.
The overall performance of the candidates was satisfactory. The chief examiner identified no discrepancies.
V. Manaaement Meetinos XI. Exit Meeting Summary On March 13. 1998, the chief examiner discussed the examination results with the Operations Training Supervisor.
Dissenting comments were not received from the licensee.
No proprietary information was identified.
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PARTIAL LIST OF PERSONS CONTACTED i
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Licensee l
- B. Badham, Supervisor Safety Audit Engineering Review W. Coggins., Performance Modification and Maintenance Support Supervisor
- P. Crone, Engineering Support Performance Review Supervisor
- J. Deavers Senior Plant Instructor
- S. Fulmer Training and Emergency Preparedness Manager D. Grissette, Operations Manager
- D. Hall Operations Instructor
- R. Hill. FNP Plant Manager C. Nisbitt, Assistant Plant manager, Support
- W. Oldfield, Nuclear Operations Training Supervisor
- J. Powell, Senior Plant Instructor
- G. Waymire. Technical Manager
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- B.
Caldwell. Resident Inspector l
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ENCLOSURE 3
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FACILITY RECOMMENDATIONS FOR CHANGES TO EXAMINATION QUESTIONS
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Question Number 1:
Change the correct answer to
"a".
The question stem gives the condition that P, fails high and asked for the initial response of the rod control system.
m During the time frame that impulse pressure is failing, the power mismatch circuit (see attached ) will be causing a maximum rod speed signal based on the large difference in the rate of change of NI-44 and Pm,.
This rate of change signal will be brief and then rod speed will be determined by the difference between median T, and Tre (generated from Pap).
The question o
developer failed to take into account the momentary difference in the rate of change and based the original answer on the T,-T g difference that would e
exist.
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QUESTION No.1:
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Given the following plant conditions:
Loop A Tavg channel is 575 degrees F.
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Loop B Tavg channel is 576 degrees F.
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Loop C Tavg channelis 572 degrees F.
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Rod Control System is in auto with control bank D at 215 steps
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Which one of the following explains how the Rod Control System will initially respond if the selected Pimp pressure failed high?
Rods will step out at 72 steps / minute.
a.
l b. Rods will step out at 48 steps / minute.
c. Rods will step out at 8 steps / minute.
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d. Rods will not move.
ANSWER: c.
KA: 001 A1013.8/4.2 LEVEL:
ANALYSIS
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REFERENCE: OPS-52201E, pg.10-13 LEARNING OBJECTIVE: 052201E13 HISTORY: 052201E05006 was used on one the candidates audit exams The stem and distracters a, b, and c, have been modified.
JUSTIFICATION:
Rods would move out at this speed if the Tref were not high limited.
a.
b. Rods would move out at this speed if average value of Tavg was used instead of the median value.
c. Rods will move out at this speed because the out put of the Rod-Speed Programmer is above 1* but not greater than 3*.
d.
Rods would not move if the Temperature Mismatch Channel out put was from "B" loop Tavg instead of the median Tavg.
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DC Hold Cabinet (Finure 4)
i A failure in a power cabinet may require replacement of a printed circuit card, fuse, or other component. To avoid the possibility ofdropping rods during maintenance and to avoid the need for j
an external power source, each power cabinet contains three switches used to energize any one of the three groups of stationary gripper coils from a separate 125/70-volt DC power source. Placing more than one group in entire system on hold bus may result in overleading of supply.
This power source is the DC hold cabinet. The 125V DC rupply is used to assure latching of the stationary grippers. The 70V DC supply is used to hold the grippers without overheating the coils.
i Control Rod Drive Mechanism
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The CRDM is a three-coil, electromagnetic jack that raises and lowers a 144-inch drive rod,
.which attaches to the control rod assemblies. Tlie three coils, mounted outside the pressure housing, actuate armatures contained within the housing. The movable and stationary gripper armatures operate latches that grip a grooved drive rod. The stationary gripper latches are used to hold the drive rod in position. The movable gripper latches, which are raised and lowered by the lift coil armature, are used to raise and lower the drive rod. Each step of the mechanism moves the drive rod 5/8 inch. Refer to the Reactor Vessel and Core Components lesson for the design and
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construction details of the CRDM I
OPERATIONS histrumentation and Controls Reactor Control Unit (Finure 5)
The reactor control unit consists of two channels: (1) the power mismatch channel and (2)
t the temperature mismatch charmel. The power mismatch channel provides an error signal whenever there is a rate of change between turbine power and reactor power. (During constant
power operation, the error signal will be zero even if turbine power and reactor power are not equal.) The temperature mismatch chann:1 produces an error signal proportional to the deviation l
between median T., and P,,,,, generated Tur. (The error signal will be zero only if the difference between T., and T=ris zero.) This is the normal control channel.
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OPS-402041/S2201E
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The enor signals produced by these chnnnels are summed and routed to a bistable and a function generator. The bistable determines the direction of rod motion, esi the function generator determines the rod speed. The resultant output will be sent to the logic cabaus.
Temnerature Afismatch Channel The temperature mismatch channel receives inputs of median T,y, and turbine first stage impulse pressure (P mp). Prior to entering a differential amplifier, the T,y, signal passes through a i
lead / lag card for dynamic conditioning. The lead / lag card provides dynamic compensation by producing an output that anticipates the actual plant T., when T,y, is changing.
On a ramp up in T,ys, the output of the lead / lag card will be the value of actual T., at some future point in time. This compensates for the delay between the time when temperature begins to increase in the reactor and the time when the increase will actually be sensed by the resistance temperature detectors (RTDs) in the loops.
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The Pun, signal, a measure of turbine load, feeds into a function generator. The function generator creates a Tur signal programmed to vary as a function of plant load. Again, for purposes of discussion, the program is 547 F at zero-percent power to 575 F at 100-percent power. The Tur signal passes through a lag circuit for dynamic compensation prior to entering the differential amplifier.
The T,y, and Tar inputs connect to the differential amplifier, which performs the following function:
Tem = (T,er-T )
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The Temsignal will be summed with the P,m signal from the power mismatch channel.
Power Afismatch Channel The power mismatch channel receives inputs from nuclear power (N-44) and P,mp. Pmpis i
conditioned to produce a turbine power signal that may be compared with the nuclear power signal from N-44. When compared in a differential arnplifier, nuclear power and turbine power produce an error output signal equivalent to the difference between turbine and reactor power multiplied by a gain.
OPS-402041/52201E
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The output of the differential amplifier supplies a signal to a derivative card. This card produces an output only when the turbine-reactor power deviation is changing. When the deviation i
is constant, the output of the derivative card, and, therefore, the output of the power mismatch circuit, equals zero.
Any output obtained from the derivative card enters a function generator, which serves as a non-linear gain unit. A small input to the unit will be amplified with a gain of only 0.24, resulting
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in little rod motion. However, if the input is greater in magnitude, the gain becomes 1.2, lending greater weight to the error signal and resulting in increased rod motion.
The output of the non-linear gain unit enters a variable gain unit. The variabic gain unit varies the gain applied to the error signal inversely with turbine power. The variable gain unit compensates for the fact that a step of rod motion produces a greater change in power at high power levels than at low power levels. Therefore, the power enor (Pm ) signal must be reduced as power increases to reduce the rod motion at higher power levels. The variable gain is accomplished by dividing the error signal by the output from the power compensation unit. The power compensation unit generates a function that varies inversely with Pimp.
The output of the variable gain unit, a Pm. signal, inputs to a summing unit to be summed with the T., signal from the temperature mismatch channel. The output of the variable gain unit is provided with a defeat switch, which is located in control cabinet eight of the 7300 cabinets, along with the rest of the reactor control unit. This switch, operated by the I&C department using procedures under their control, allows the power mismatch channel to be isolated from the rest of the reactor control unit for calibration or maintenance purposes. I&C procedures and the PLS document require the rod control system to be in manual control any time this switch is open. If the rod control system were operated in automatic with the mismatch channel defeat switch open, the rod control system would be without the benefit of the anticipatory response provided by this channel, causing a possible improper response of the system.
The output of the summing unit, which can either be positive or negative, provides an input to the rods in/out bistable and a function generator. The rods in/out bistable provides the signal to i
direct rod motion (in or out). The polarity of the input signal to the bistable will dictate the
direction the rods are to move. If the input signal exceeds the output setpoint in the positive direction, a rods-out command will be generated. The output setpoints equate to 1.5*F
OPS-402041/52201E j
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temperature error. The rod motion command will reset at * 1"F. This 0.5'F lockup will prevent unnecessary rod motion near the bistable output setpoint.
The function generator determines the rod speed based on the magnitude of the error signal.
The rod speed varies from 8 steps per minute (0 to * 3*F error) to 72 steps per minute ( 5F error). He rod speed varies linearly from eight steps per minute to 72 steps per minute (* 3 to 5'F error).
Rod Control System (Finure 6)
Bank Selector Switch (BSS)
The BSS has eight positions designated as follows:
1.
SBA 2.
SBB 3.
MAN
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AUTO 5.
CBA
6.
CBB 7.
CBC 8.
CBD The position of the BSS is sensed by several components in the logic cabinet, ne BSS position determines the speed input to the pulser, selects the direction input to the master cycler, and provides the bank selection input to the bank overlap unit (BOU). His all takes place in the i
logic cabinet.
A rod speed meter on the MCB indicates calculated rod speed from the reactor control unit.
Since speed signals are always being calculated, even with no rod motion, the meter always indicates some speed. The indicated rod speed depends on the control mode selected by the BSS.
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OPS-402041/52201E
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CONTROL-ROD SPEED AND DIRECTION SIGNAL i
REACTOR CONTROL UNIT FIGURE 3
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REACTOR CONTROL UNIT FIGURE 5 647
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Ouestion Number 5:
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The answer to this question should be "a".
The stem of the question states that the Digital Rod Positioning Indication (DRPI) experiences a loss of power to the Data A cabinet.
The following is an excerpt from DRPI lesson material
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(attached):
Half' Accuracy:
The system will still function with either data bank
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inoperable but with reduced or half accuracy. Table 4 of OPS-52201F, reflects
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the accuracy available with Data A out of service.
The central control cards l
will not receive any information from Data A coils. At three steps, even though a Data A coil has been penetrated, data from the detector encoder card is inhibited, so no knowledge of this is received by the central control card.
It assumes zero coils have been penetrated until a Data B coil is penetrated.
At nine steps, the first Data B coil will be penetrated. The central control cards now have information of one coil being penetrated. When either data bank is inoperative, the information from the' operating data bank is doubled.
L The central control cards now assume that two total coils have been penetrated, and the indication will display 12 steps.
The worst case indication occurs at nine steps where the rod may be plus nine steps or minus three steps.
Plus or minus one (+/-1) must be added to this for manufacturing
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The accuracy for Data (A)
failed is (+10 -4) not +4 -10 as the question indicates (see justification for
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distracter 1).
This accuracy would make answer "a" correct. Answer "b" is j
incorrect because 156 is outside the -4 accuracy for group 1. "c" is incorrect l
because 150 is beyond the -4 accuracy for group 1, and "d" is incorrect l
because 150 is beyond the -4 accuracy for group 2.
This error occurred due to l
the exam developer writing the answer based on data B being failed, when the stem actually specifies data A as the failed channel.
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remain at six steps until a second coil has been penetrated at nine steps. Now, with the rod
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somewhere between nine steps and 15 steps, the indication will show 12 steps. This means that actual rod position can be as much as plus or minus three ( 3) steps from indicated position.
(Table 3 shows this relationship.)
As can be seen from Table 3, when the rod is at three steps, the coil at three steps may or may not have been penetrated enough to make it change state. In either case, the indication will be off by three steps. In addition to the three steps inaccuracy, one additional step must be added
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to the inaccuracy to account for manufacturing tolerance of the coils and tube, the placement of the coils on the tube, and the expansion or contraction of the tube with temperature changes. The
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final full accuracy of the system then becomes plus or minus four ( 4) steps.
HalfAccuracy The system will still function with either data bank inoperable but with reduced or half l
accuracy. Table 4 reflects the accuracy available with Data A out of service. The central control
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cards will not receive any information from Data A coils. At three steps, even though a Data A l
coil has been penetrated, data from the detector encoder card is inhibited, so no knowledge of l
this is received by the central control card. It assumes zero coils have been penetrated until a Data B coil is penetrated. At nine steps, the first Data B coil will be penetrated. The central s
control cards now have information of one coil being penetrated. When either data bank is inoperative, the intbrmation from the operating data bank is doubled. The central control cards l
now assume that two total coils have been penetrated, and the indication will display 12 steps.
The worst case indication occurs at nine steps where the rod may be plus nine steps or minus three steps. Plus or minus one ( 1) must be added to this for manufacturing tolerances and temperature changes, providing an accuracy of plus 10 minus four (+10 -4) accuracy when using I
Data B only.
Table 5 illustrates the accuracy received if Data B has had a failure. When the first Data A coil is penetrated, the central control cards double this information. This means that with as low as three steps, the indication can read 12 steps or still read zero steps. After adding the plus
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OPS-S2201F l
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QUESTION No. 005:
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Given the following plant conditions:
Unit 2 is at 50% power.
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Control bank D rods are :
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Group 1 at 161
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Group 2 at 160
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if the Digital Rod Position Indication System (DRPI) experiences a loss of power to the Data "A" cabinet, which one of the following Control Bank D DRPI indications are within the limitations of DRPI-j
Group 1 Group 2 a.
168 162 b.
156 168 c.
150 162 d.
162 150
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ANSWER: d.
KA: 014A202 3.1/3.6 LEVEL:
ANALYSIS REFERENCE: OPS-52201F, pg. 8 LEARNING OBJECTIVE: 052201F09 i
HISTORY: New JUSTIFICATION:
With Data "A" failure accuracy will be +4 and -10,168 on group 1 is outside the accuracy n.
range.
b. Both group 1 and group 2 are outside the accuracy range.
Group 1 is outside the accuracy range of DRPI but is plausible if candidate only remembers i c.
12 steps of tech specs as the accuracy.
d. 162 is within the +4 limit and 150 is within the -10 limit.
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Ouestion Number 13:
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Delete the question due to no correct answer.
Answer
"a" is incorrect because the trip of both main feedwater pumps signal is an auto start signal
for the motor driven auxiliary feedwater (MDAFW) pumps only, it does not start the turbine driven auxiliary feedwater (TDAFW) pump.
Answer "b" a safety injection signal is also an auto start signal for the MDAFW pumps only, it does not start the TDAFW pump.
Answer "c" steam generator low level is an alarm signal only, the actual automatic start signal is steam generator low-low level.
Answer
"d", the AMSAC signal is not active in this case because power has been below 40% for longer than 240 seconds (see attached).
I The validity of the examination outline is not affected by this deletion because there was another question regarding the auxiliary feedwater system and there were 18 other questions in this group to evaluate required knowledge and ability.
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QUESTION No. 013:
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Unit I has been holding at 33% power for the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, which one of the following signals will result in the Auto start of the Turbine Driven AFW pump?
Trip of both main feedwater pumps.
a.
b. Safety injection.
c.
steam generator low level, d. AMSAC signal.
ANSWER: d.
KA: 061K402 4.5/4.6 LEVEL:
MEMORY REFERENCE: OPS-52102H, pg. 9 LEARNING OBJECTIVE: 052102H13 HISTORY: New
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JUSTIFICATION:
Trip of both MFPs will auto start MDAFW Pumps but not the TDAFW Pump.
a.
b. SI signal will auto start MDAFW Pumps but not the TDAFW Pump.
c. This is the only valid signal for these conditions d. The AMSAC signal is not active due to being less than 40% powe l e
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Oneration
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The MDAFW pumps may be controlled from either the MCB or the HSP. The pumps will automatically start on any one of the following:
1.
A steam generator 10-10 level of 25% on Unit 1 (25% on Unit 2) (2/3 level instruments in 1/3 steam generators) and no LOSP
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Both main feed pumps tripped and no LOSP 3.
An engineered safety feature (ESP) sequencer signal 4.
An LOSP sequencer signal 5.
AMSAC (2/3 steam generators < 10% level on Unit 1 (< 10% level on Unit 2];
blocked below C-20) {< 40%}
Turbine-Driven Auxiliary Feedwater Pumo One TDAFW pump provides emergency feedwater flow to the steam generators if off-site power is unavailable. The seven-stage pump is rated at 700 gpm at 1227 psig. Main steam directly from the steam generator provides the power for the turbine. The pump is located on the non-rad side,100 foot elevation.
The condensate storage tank supplies the TDAFW pump through two locked open isolation valves and check valve. An attemate supply may be drawn from the service water system through two motor-operated isolation valves (MOV-3216 and either MOV-3209A or B) and a locked open manual isolation valve located by the TDAFW pump room. The TDAFW pump, like the MDAFW pumps, has a miniflow line containing a locked open isolation valve, check valve, and a flow orifice. A bypass line around the miniflow line provides for system performance and pump flow testing. The bypass line isolation valve is normally locked closed. The miniflow and bypass lines return flow to the condensate storage tank.
Pumn Instrumentation Flow instmment FISL-3218 provides a low flow alarm on the MCB at 80 gpm. A pump suction pressure instrument (PT-3217) provides both local and MCB indication as well as a low suction pressure alarm on the MCB at 22.5 psig. Pressure instrument PT-3222 provides both local and MCB indication of pump discharge pressure. Pump bearing temperatures alarm on the Omniguard panel in the main control room.
OPS-40201D/52102H
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Turbine Or>eration (Firure 3 and 3A)
Connections on the main steam lines from steam generators B and C supply stearn to the TDAFW pump. Steam flows through two parallel lines into a common line, which feeds the TDAFW pump. An air-operated isolation valve (3235A and B) located in each line will admit steam to the TDAFW pump upon receiving a start signal. Each of the valves has an air reservoir associated with it. These valves are in the main steam valve room.
The air reservoir ensures that on a loss-of-instrument air the respective isolation valve can be opened. The reservoir may be supplied from either instrument air or the emergency air compressor. Ifinstrument air pressure falls below 80 psig, the solenoid-operated supply valve to the air reservoir will automatically close. The valve will automatically reopen when pressure retums to 80 psig. A low pressure alarm for instrument air will sound on the MCB at 60 psig.
HV-3235A and B are normally closed. However, a warming line keeps the supply piping at main steam temperature to prevent or minimize the thermal shock during pump starts. The warming line isolation valves (HV-3234A and B) close on a T-signal and can be controlled remotely from the BOP panel. This supply of warming steam condenses in the steam header and as the level of condensate increases, LCV-3608 opens, draining the condensate to the auxiliary steam condensate tank.
During TDAFW pump operation, the steam passes through steam admission valve HV-3226, the trip throttle valve MOV-3406, the govemor valve, and the TDAFW pump turbine.
The steam exhausts to the atmosphere.
The TDAFW pump may be controlled from either the MCB or the HSP. The pump automatically starts on the following:
1.
Steam generator lo-lo level of 25 percent (2/3 level instruments in 2/3 steam generators)
2.
Undervoltage signal of 64.4% on RCP buses (blackout) (1/2 UV relays on 2/3 buses)
3.
AMSAC (2/3 steam generators < 10% level; blecked below C-20 after 260 secs)
Upon receiving a start signal, the steam supply valves (3235A and B) and the steam admission valve (3226) will open.
The trip throttle valve and governor valve, integral with the turbine, control the steam flow to the TDAFW pump. The trip throttle valve automatically trips shut on a turbine overspeed of
OPS-402010/52102H L
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- Question Number 87:
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Delete the question.
The stem of the question states that the date 1/10/98 is the issue date of TCN 3C.
FNP-0-AP-1 paragraph 7.1.1.1 (attached) requires that the dates for which the change is to be effective be listed in the lower right hand corner and a one time change shall be valid for the indicated dates only and this period shall not exceed 90 days. The information provided in the stem regarding the effective dates was incomplete in that it only provided the date issued.
Additionally, the candidate requested clarification (Facility recommendations enclosure 3) about counting the issue date and was told yes it counts by the proctor. The incomplete stem information and the answer provided prevented the candidate from having to evaluate when the time requirement actually began and could have also misled him in the correct counting of the 90 day period.
The deletion of this question does not affect the validity of the examination outline because there were four questions remaining in this category to sample the required knowledge and ability.
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QUESTION No. 087:
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You are about to use a System Operating Procedure that has the following markings:
- The applicable portion of the procedure has been changed by TCN 3C.
- In the lower right-hand corner of the page is the statement "One Time Only."
- In the lower right-hand comer of the page is written " Issued on 1/10/98."
Which one of the following is the latest date this TCN could be valid?
a.
1/30/98 b.
3/10/98
c.
3/30/98 l
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4/10/98 l
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ANSWER: d.
KA: G1213.1/3.2 LEVEL:
MEMORY REFERENCE: FNP-0-AP-1, pg.15 LEARNING OBJECTIVE: OS2303A01
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HISTORY: New JUSTIFICATION:
When a TCN is within 20 days of the end duration the responsible individual is notified.
a.
b. A TCN shall be approved or denied within 60 days ofimplementation.
c. An outstanding TCN over 80 days old will be referred to an Assistant General Manager for disposition or extension.
d. A one time only TCN will not exceed 90 days.
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06/19/97 13:28:50
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ENP-0-AP-1
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Temporary changes shall be documented using the Procedure Request Form (Figure 1). The individual assigned to prepare the temporary change will fill out items I through 3 of the Procedure Request Form and verify that the procedure or manual has been screened for 10 CFR 50.59 applicability per paragraph 5.1.
7.1.1 One time only changes In addition to the TCN, the lower right hand comer of the replacement l
and/or additional page(s) shall show:
7.1.1.1 The dates for which the change is to be effective.
7.1.1.1.1 The one time only temporary change shall be valid for the indicated date(s) only and this period shall not exceed 90 days.
7.1.1.2 That this is a one time only change.
7.1.2 Temporary changes Rquired By Plant Conditions in addition to the TCN, the lower right-hand comer of the replacement and/or additional page(s) shall show (1) the plant condition for which the l
change is to be effective, and (2) that this is a one time only change.
7.2 Review ofTemporary Changes
The temporary change will be reviewed by a qualified reviewer as stated in Section 4 of this procedure. The qualified reviewer will complete Item 4 of the Procedure Request Form and designate:
7.2.1 Any required cross-disciplinary review or PORC review in Item 5 of the Procedure Request Form.
7.2.2 The temporary change approval authority in Item 6 of the Procedure Request Form.
7.2.3 The Final appmval authority in Item 7 of the Procedure Request Form.
7.3 Approval Requirements for Temporary Changes Temporary changes shall be approved as specified in this paragraph prior to implementation.
7.3.1 The approval authority shall ensure that:
-15 Revision 35
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ENCLOSURE 4 o
NRC RESOLUTION OF COMMENTS 1. SRO Question # 1 Comment accepted. The answer key was changed to accept choice "a" as the correct answer.
2. SR0 Question # 5 Comment accepted. The answer key was changed to accept choice "a" is the correct answer.
3. SRO Question # 13 Comment accepted. The question was deleted.
4. SRO Question # 87 Comment accepted. The question was deleted.
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