ML17349A209
| ML17349A209 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 12/15/2017 |
| From: | NRC/RGN-II |
| To: | Florida Power & Light Co |
| References | |
| 50-250/OL-17-01, 50-251/OL-17-01 | |
| Download: ML17349A209 (84) | |
See also: IR 05000250/2017301
Text
Turkey Point 2017-301
Post Exam Comments
1) Applicant Comment (Q89)
2) Supporting Documentation for Applicant
Comment (Q89)
3) Facility Position (Q89)
4) Supporting Documentation for Facility
Position (Q89)
5) Facility Comment (Q34)
6) Supporting Documentation for Facility
Comment (Q34)
7) Facility Comment (Q94)
8) Supporting Documentation for Facility
Comment (Q94)
1) Applicant Comment (Q89)
(
(
!Question Feedback from Applicant
Question 89 Contention:
Question 89 presented the applicants with a situation in which the ICW/CCW Basket Strainer
was being backwashed at the same time as the ICW/TPCW Backwash Strainer. As stated in the
stem of the question, during the subsequent restoration, 4-50-324, ICW/CCW BASKET
STRAINER A INLET ISOLATION, experiences a sheared pin (handwheel spins freely) and
remained closed, and POV-4-4883, ICW/TPCW HEADER B ISOLATION VALVE, failed closed and
would not reopen. The question then asks the student if the limitations of strainer backwashing
per 4-NOP-019 (ARE/ARE NOT) violated; and if the Unit 4 Unit Supervisor (IS/IS NOT) required
to be in HOT SHUTDOWN within the following 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
I chose answer (B) for the Limitations of 4-NOP-019 ARE violated, and the Unit Supervisor IS
NOT required to be in HOT SHUTDOWN within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The keyed answer was (D) in which the
answer stated the Limitations of 4-NOP-019 ARE NOT violated, and Unit Supervisor IS NOT
required to be in HOT SHUTDOWN within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Question 89 is not being contended for the second part of the question. I agree that Unit 4 is
NOT in a Shutdown Action in accordance with Technical Specification 3.0.3. However, I am
contending that the answer for the first part of Question 89 is incorrect.
The limitations of 4-NOP-019 pertaining to the Basket Strainers are found in section 2.2.3.3.
Limitation 2.2.3.3 states as follows: "While isolating an ICW/CCW Strainer, ICW flows below
"Minimum Required ICW/CCW Flowrate" are permitted for up to 5 minutes, without declaring
ICW System inoperable. If flow is below the "Minimum Required ICW/CCW Flowrate" for
greater than 5 minutes, then the ICW system shall be declared inoperable at the time when
flow initially went below the "Minimum Required ICW/CCW Flowrate."
The Initial Conditions/Stem of the question state that valve 4-50-324 has a sheared pin and the
valve remains closed. However, there is no definitive indication about time, which leaves the
applicant to determine if the valve can be opened within 5 minutes to comply with Limitation
2.2.3.3. Indications show that the valve's pin has sheared (handwheel spins freely) and the
valve remains closed. Valve 4-50-324 is a manual operating valve and has no other means to
operate the valve in the open direction. See attached P&ID, isometric drawing, and picture of
valve 4-50-324.
There is no reasonable assumption that the valve can be opened within 5 minutes to comply
with the limitation provided in the procedure. Therefore, I came to the answer that the
limitation to backwash for less than 5 minutes IS violated and thus answer (B) was chosen to
reflect this condition. NUREG 1021-Revision 11 Section D.1 states that "newly discovered
technical information that supports a change in the answer key" can be used as a reason to
support taking two answers for this question or for the removal of this question.
2) Supporting Documentation for Applicant
Comment (Q89)
3) Facility Position (Q89)
Attachment 3
Executive Summary of Challenged Questions and FPL Recommendation
Question 34:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 34 provides the operator with a Loss of CCW scenario in which
one of the RCPs is experiencing High Motor Bearing temperatures. FPL recommends to accept both
A and D distractors as correct for question 34 since two procedures that are applicable during the
conditions described on the stem direct different actions, which are both applicable and correct.
Question 89:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 89 provides the operator with a scenario where one ICW/CCW
strainer and one ICW/TPCW strainer are being backwashed simultaneously. Subsequent failures
prevent restoration from backwashing operations. The question is to determine if a procedural
limitation from 4-NOP-019, Intake Cooling Water System, has been violated and if the Unit Supervisor
is required to apply TS 3.0.3. On question 89 it is unclear if an action statement was initially entered
when the ICW/CCW backwash was started. Due to conflicting answers as a result of a missing piece
of information FPL recommends to delete question 89 from the exam.
Question 94:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 94 is related knowledge of STA responsibilities. At Turkey Point,
our plant administrative procedure 0-ADM-200, Operations Management Manual, is more restrictive
than the Technical Specifications. This question did not specify which reference to use in order to
formulate a response. Due to conflicting answers FPL recommends to delete question 94 from the
exam.
Attachment 3
Applicant Comments on question 89:
Question 89 presented the applicants with a situation in which the ICW/CCW Basket Strainer was
being backwashed at the same time as the ICW/TPCW Backwash Strainer. As stated in the stem of
the question, during the subsequent restoration, 4-50-324, ICW/CCW BASKET STRAINER A INLET
ISOLATION, experiences a sheared pin (handwheel spins freely) and remained closed, and POV-4-
4883, ICW/TPCW HEADER B ISOLATION VALVE, failed closed and would not reopen. The question
then asks the student if the limitations of strainer backwashing per 4-NOP-019 (ARE/ ARE NOT)
violated; and if the Unit 4 Unit Supervisor (IS/IS NOT) required to be in HOT SHUTDOWN within the
following 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
I chose answer (B) for the Limitations of 4-NOP-019 ARE violated, and the Unit Supervisor IS NOT
required to be in HOT SHUTDOWN within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The keyed answer was (D) in which the answer
stated the Limitations of 4-NOP-019 ARE NOT violated, and Unit Supervisor IS NOT required to be in
HOT SHUTDOWN within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Question 89 is not being contended for the second part ofthe qu estion. I agree that Unit 4 is NOT in a
Shutdown Action in accordance with Technical Specification 3.0.3. However, I am contending that the
answer for the first part of Question 89 is incorrect.
The limitations of 4-NOP-019 pertaining to the Basket Strainers are found in section 2.2.3.3.
Limitation 2.2.3.3 states as follows: "While isolating an ICW/CCW Strainer, ICW flows below
"Minimum Required ICW/CCW Flowrate" are permitted for up to 5 minutes, without declaring ICW
System inoperable. If flow is below the "Minimum Required ICW/CCW Flowrate" for greater than 5
minutes, then the ICW system shall be declared inoperable at the time when flow initially went below
the "Minimum Required ICW/CCW Flowrate."
The Initial Conditions/Stem of the question state that valve 4-50-324 has a sheared pin and the valve
remains closed. However, there is no definitive indication about time, which leaves the applicant to
determine if the valve can be opened within 5 minutes to comply with Limitation 2.2.3.3. Indications
show that the valve's pin has sheared (handwheel spins freely) and the valve remains closed. Valve
4-50-324 is a manual operating valve and has no other means to operate the valve in the open
direction. See attached P&ID, isometric drawing, and picture of valve 4-50-324.
There is no reasonable assumption that the valve can be opened within 5 minutes to comply with the
limitation provided in the procedure. Therefore, I came to the answer that the limitation to backwash
for less than 5 minutes IS violated and thus answer (B) was chosen to reflect this condition. NUREG
1021-Revision 11 Section D.1 states that "newly discovered technical information that supports a
change in the answer key" can be used as a reason to support taking two answers for this question or
for the removal of this question.
Attachment 3
Facility Position on Applicant Comment on question 89: FPL concurs with the applicants position
on deletion of question 89.
Facility Comments on question 89:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 89 provides the operator with a scenario where one ICW/CCW
strainer and one ICW/TPCW strainer are being backwashed simultaneously. Subsequent failures
prevent restoration from backwashing operations. The question is to determine if procedural
limitations from 4-NOP-019, Intake Cooling Water System, have been violated and if the Unit
Supervisor is required to apply TS 3.0.3. due to the failures.
4-NOP-019, Intake Cooling Water System, (Reference 3) allows for ICW/CCW Strainer
backwashing without declaring the ICW header inoperable, during the backwash the ICW
flowrate through the CCW lowers below the Minimum Required, this requires the affected ICW
Header to be declared inoperable if this condition lasts longer than 5 minutes. On the other
hand, at Turkey Point is normal practice to declare the affected ICW header inoperable
preemptively before aligning for backwash. Since question 89 does not specify if an action
statement was initially entered when the ICW/CCW backwash was started the candidates are
required to make an assumption to answer this question, which could lead to two different
answers: B or D.
If assuming that Tech Spec 3.7.3 Action C (Reference 4) was entered before starting the
strainer backwash, the candidate would conclude that no violation of the 4-NOP-019 limitations
have occurred. In this case D distractor is the correct answer.
Attachment 3
If assuming that Tech Spec 3.7.3 Action C was NOT entered before starting the strainer
backwash, the candidate would conclude that a violation of the 4-NOP-019 limitations 2.2.3.3
have occurred due to lowering ICW flowrate through the ICW/CCW heat exchanger for longer
than 5 minutes without declaring the affected ICW header inoperable. 4-NOP-019 allows for
backwashing ICW/TPCW basket strainers for up to 5 minutes without declaring the associated
ICW header inoperable. Under the assumption that a backwash is being attempted to be
performed with both ICW headers operable and inside the 5 minute window, once the isolation
valve (3-50-324) pin shears, the ICW/CCW basket strainer will remain isolated for greater than
5 minutes without declaring the affected ICW header inoperable. This constitutes a violation of
4-NOP-019 limitations 2.2.3.3. In this case B distractor is the correct answer.
FPL recommendation: As the candidates are required to assume that an ICW Header is declared
inoperable or not at the beginning of the backwash, the candidates arrive at conflicting conclusions as
it relates to the violation of the limitations of 4-NOP-019. Due to conflicting answers as a result of a
missing piece of information FPL recommends to delete question 89 from the exam.
References:
3. 4-NOP-019, Intake Cooling Water System.
4. Tech Spec 3.7.3.
4) Supporting Documentation for Facility
Position (Q89)
NRC L-17-1 EXAM SECURE INFORMATION
Page 251
Examination Outline Cross-
reference:
Level
Tier #
2
Group #
1
Topic and K/A #
076
2.1.23
Importance
Rating
4.4
Conduct of Operations: Ability to perform specific system and integrated plant
procedures during all modes of plant operation.
Proposed Question: SRO Question # 89
Given the following conditions:
Unit 4 is operating at 100% power.
Backwashing 4A ICW/CCW and 4B ICW/TPCW strainers, is in progress.
While restoring:
4-50-324, ICW/CCW Basket Strainer A Inlet Isol, experiences a sheared pin
(valve handwheel spins freely) and remains closed.
POV-4-4883, ICW to TPCW Heat Exchangers Isolation Valve, is failed closed
and will not re-open.
Which one of the following completes the statements below?
4-NOP-019, Intake Cooling Water System, limitations for strainer backwashing
(1)
violated.
Unit 4 US
(2)
required to be in at least HOT SHUTDOWN within the
following 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
A.
(1) are
(2) is
B.
(1) are
(2) is NOT
C.
(1) are NOT
(2) is
NRC L-17-1 EXAM SECURE INFORMATION
494
NRC L-17-1 EXAM SECURE INFORMATION
Page 252
D.
(1) are NOT
(2) is NOT
Proposed Answer: D
A.
Incorrect
Both parts incorrect and plausible per discussion below. Both parts are
plausible independently and taken as a whole.
Part 2 incorrect; plausible because POV-4-4883 failure to re-open does not
affect ICW tech specs, since the valve is in its prescribed accident position.
B.
Incorrect.
Part 1 incorrect; plausible since 3-NOP-019 ensures that opposite train (of
the same kind ) strainer is in service before removing any strainer from
service.
C.
Incorrect
Part 2 incorrect; plausible since an ICW header is already OOS and POV-
4-4883 failure would drive actions for TS 3.0.3.
D.
Correct
IAW 4-ONOP-019 and TS 3.7.3/3.0.3
Technical
Reference(s)
4-NOP-019
TS 3.7.3/ 3.0.3
(Attach if not previously
provided)
Proposed Reference to be provided to applicants
during examination:
N
Learning
Objective:
6902277 Objective 4 and 6
(As available)
Question Source:
Bank
PTN 2013
Audit
Modified Bank
X
(Note changes or attach
parent)
New
Question History:
Last NRC
Exam:
NRC L-17-1 EXAM SECURE INFORMATION
495
NRC L-17-1 EXAM SECURE INFORMATION
Page 253
Question Cognitive Level:
Memory or Fundamental
Knowledge
Comprehension or
Analysis
X
10 CFR Part 55 Content:
55.41
55.43
2
Facility operating limitations in the technical specifications and their bases.
Comments:
NRC L-17-1 EXAM SECURE INFORMATION
496
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
6 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2
Limitations
2.2.1
General
1.
When in MODE 1, 2, 3, and 4, the ICW System shall be OPERABLE
with three ICW pumps and two ICW headers.
2.
When in MODE 1, 2, 3, and 4, and there are NOT two OPERABLE
ICW pumps with independent power supplies, then a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO
Action Statement is in effect to restore two pumps from independent
power supplies to OPERABLE status.
3.
When removing an ICW header from service in MODE 1, 2, 3, or 4, a
72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO Action Statement is in effect until header is returned to
service. Because NO flow is being diverted away from the CCW HXs,
as when a strainer is being backwashed, a continuous watch is NOT
required to be posted when the header is out of service.
4.
When the U5 Well Water Injection is in operation, the ICW System
should NOT be operated with three ICW pumps. In this condition,
the injection flow pushes the flow rate through the CCW HXs over
their limit of 10,000 GPM. Momentary flow greater than 10,000 GPM
is allowed.
2.2.2
ICW Pumps
1.
ICW pumps should NOT be operated with water level of the Pump
Well lower than 23 feet 2 inches below the centerline of the pump
discharge which is 20 feet 8 inches below the Intake floor grating.
2.
If ICW pump motor heaters are OOS for more than five days, then
Engineering is required to determine pump OPERABILITY.
3.
The minimum flow for any ICW pump during continuous operation
should be greater than or equal to 3200 gpm.
4.
Maximum ICW flowrate to each CCW HX during normal operation
should NOT exceed 10,000 gpm per HX during normal three HX
operations in order to minimize long term tube side erosion of the
CCW HXs. (ref. 5610-019-DB-002)
A.
The ICW maximum flowrate for each CCW HX may be
increased to 12,850 gpm for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period to accommodate
HX or Basket Strainer cleanings. (ref. 4-NOP-030)
B.
If flow exceeds 10,000 gpm for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then a
condition report shall be initiated.
2.2.1
General
1.
When in MODE 1, 2, 3, and 4, the ICW System shall be OPERABLE
y
with three ICW pumps and two ICW headers.
2.
When in MODE 1, 2, 3, and 4, and there are NOT two OPERABLE
ICW pumps with independent power supplies, then a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO
p
p
p
p
pp
Action Statement is in effect to restore two pumps from independent
power supplies to OPERABLE status.
3.
When removing an ICW header from service in MODE 1, 2, 3, or 4, a
g
72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO Action Statement is in effect until header is returned to
service. Because NO flow is being diverted away from the CCW HXs,
g
y
as when a strainer is being backwashed, a continuous watch is NOT
g
required to be posted when the header is out of service.
4.
When the U5 Well Water Injection is in operation, the ICW System
j
p
y
should NOT be operated with three ICW pumps. In this condition,
p
p
p
the injection flow pushes the flow rate through the CCW HXs over
j
p
g
their limit of 10,000 GPM. Momentary flow greater than 10,000 GPM
is allowed.
2.2.2
ICW Pumps
1.
ICW pumps should NOT be operated with water level of the Pump
p
p
p
p
Well lower than 23 feet 2 inches below the centerline of the pump
p
p
discharge which is 20 feet 8 inches below the Intake floor grating.
2.
If ICW pump motor heaters are OOS for more than five days, then
p
p
y
Engineering is required to determine pump OPERABILITY.
3.
The minimum flow for any ICW pump during continuous operation
y
p
p
g
should be greater than or equal to 3200 gpm.
4.
Maximum ICW flowrate to each CCW HX during normal operation
g
p
should NOT exceed 10,000 gpm per HX during normal three HX
gp
p
g
operations in order to minimize long term tube side erosion of the
p
g
CCW HXs. (ref. 5610-019-DB-002)
A.
The ICW maximum flowrate for each CCW HX may be
y
increased to 12,850 gpm for a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period to accommodate
gp
p
HX or Basket Strainer cleanings. (ref. 4-NOP-030)
B.
If flow exceeds 10,000 gpm for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, then a
gp
condition report shall be initiated.
NRC L-17-1 EXAM SECURE INFORMATION
497
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
7 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.2
ICW Pumps (continued)
4.
(continued)
C.
ICW flow should be throttled to maintain flow less than
10,000 gpm unless elevated flows are required (it is
acceptable to run three ICW pumps with CCW HX flows
greater than 10,000 gpm during periods of elevated canal
temperature) ref. CR 1987062
5.
Maximum ICW Pump flowrate is permitted up to 18,500 gpm. If an
ICW Pump is operated in excess of 18,500 gpm, then flow should be
reduced to less than 18,500 gpm as soon as possible. If an ICW
pump has operated at flows greater than 18,500 gpm for more than
twenty (20) minutes, then once pump flow has been reduced to
18,500 gpm or less, the IST Coordinator should be notified to perform
vibration and pump DP testing per 4-OSP-019.1, Intake Cooling
Water Pump Inservice Test to ensure integrity of the affected pump.
6.
Concurrent operation of both the ICW and CW pumps in a single
Intake Bay with a Stationary Screen installed is permitted only when
determined necessary by Shift Manager or Unit Supervisor to
accommodate pump shifting during emergent operating conditions.
Such periods of operation shall be limited to as short a duration as
possible, and an operator shall be stationed to continuously monitor
the intake bay.
7.
Operation of either the ICW or the CW pump in a single intake bay
with a stationary screen installed is permitted when subject to the
following restrictions:
A.
Prior to placing the ICW pump in service, pump well water
levels shall be verified greater than 20 feet 8 inches below the
Intake floor grating.
B.
Fouling of the stationary screen shall be monitored periodically
to ensure that minimum required water levels are present. The
frequency of the surveillance shall be determined by Shift
Manager or Unit Supervisor based on current grass influx rate.
C.
Any collected debris shall be removed from the stationary
screen prior to reaching the minimum required water level.
D.
If diving activities are being performed on the west side of the
stationary screens, then the affected ICW and CW pumps
shall be secured and declared out of service during the time
the diver remains in the well.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
7 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.2
ICW Pumps (continued)
4.
(continued)
C.
ICW flow should be throttled to maintain flow less than
10,000 gpm unless elevated flows are required (it is
gp
q
(
acceptable to run three ICW pumps with CCW HX flows
p
p
p
greater than 10,000 gpm during periods of elevated canal
g
gp
temperature) ref. CR 1987062
5.
Maximum ICW Pump flowrate is permitted up to 18,500 gpm. If an
p
p
p
gp
ICW Pump is operated in excess of 18,500 gpm, then flow should be
p p
gp
reduced to less than 18,500 gpm as soon as possible. If an ICW
gp
p
pump has operated at flows greater than 18,500 gpm for more than
r
p
p
p
g
gp
twenty (20) minutes, then once pump flow has been reduced to
y (
)
p
p
18,500 gpm or less, the IST Coordinator should be notified to perform
gp
p
vibration and pump DP testing per 4-OSP-019.1, Intake Cooling
r
p
p
g p
g
Water Pump Inservice Test to ensure integrity of the affected pump.
6.
Concurrent operation of both the ICW and CW pumps in a single
p
p
p
g
Intake Bay with a Stationary Screen installed is permitted only when
y
y
p
y
determined necessary by Shift Manager or Unit Supervisor to
y y
g
p
accommodate pump shifting during emergent operating conditions.
p
p
g
g
g
p
g
Such periods of operation shall be limited to as short a duration as
p
p
possible, and an operator shall be stationed to continuously monitor
p
the intake bay.
7.
Operation of either the ICW or the CW pump in a single intake bay
p
p
p
g
with a stationary screen installed is permitted when subject to the
y
following restrictions:
A.
Prior to placing the ICW pump in service, pump well water
p
g
p
p
p
p
levels shall be verified greater than 20 feet 8 inches below the
Intake floor grating.
B.
Fouling of the stationary screen shall be monitored periodically
g
y
p
y
to ensure that minimum required water levels are present. The
q
p
frequency of the surveillance shall be determined by Shift
q
y
y
Manager or Unit Supervisor based on current grass influx rate.
C.
Any collected debris shall be removed from the stationary
y
y
screen prior to reaching the minimum required water level.
D.
If diving activities are being performed on the west side of the
g
g p
stationary screens, then the affected ICW and CW pumps
y
p
p
shall be secured and declared out of service during the time
the diver remains in the well.
NRC L-17-1 EXAM SECURE INFORMATION
498
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
8 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.2
ICW Pumps (continued)
7.
(continued)
E.
If diving activities are being performed on the east side of the
stationary screens, the affected CW pumps shall be secured
during the time the diver remains in the well. There are NO
specific limitations on ICW pump usage when diving activities
are performed on the east side of the stationary screens.
8.
When starting ICW Pumps, the maximum flow rates for the in-service
HXs may be exceeded. The high flow rate is acceptable provided the
duration of high flow is minimized.
9.
If time permits following the raking of an Intake Well, the respective
Intake Well CW Pump should operate for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to
starting the associated ICW Pump.
2.2.3
Basket Strainers
1.
DP across the ICW Basket Strainers at the CCW HXs should NOT
exceed 1.5 psid and at the TPCW HXs should NOT exceed
2.25 psid.
2.
The maximum allowable ICW / CCW Basket Strainer element
(screening) differential pressure is 10.0 psid per
Section 7.1.2, Developmental Reference 6.P. Operation with
differential pressures near or at 10.0 psid may challenge the
structural integrity of the Basket Strainer element (screening).
3.
While isolating an ICW/CCW Strainer, ICW flows below Minimum
Required ICW/CCW Flowrate are permitted for up to 5 minutes,
without declaring ICW System inoperable. If flow is below the
Minimum Required ICW/CCW Flowrate for greater than 5 minutes,
then the ICW System shall be declared inoperable at the time when
flow initially went below the Minimum Required ICW/CCW Flowrate.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
8 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.2
ICW Pumps (continued)
7.
(continued)
E.
If diving activities are being performed on the east side of the
g
g p
stationary screens, the affected CW pumps shall be secured
y
,
p
p
during the time the diver remains in the well. There are NO
g
specific limitations on ICW pump usage when diving activities
p
p
p
g
g
are performed on the east side of the stationary screens.
8.
When starting ICW Pumps, the maximum flow rates for the in-service
g
p
HXs may be exceeded. The high flow rate is acceptable provided the
y
g
duration of high flow is minimized.
9.
If time permits following the raking of an Intake Well, the respective
f
p
g
g
p
Intake Well CW Pump should operate for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to
p
p
starting the associated ICW Pump.
2.2.3
Basket Strainers
1.
DP across the ICW Basket Strainers at the CCW HXs should NOT
exceed 1.5 psid and at the TPCW HXs should NOT exceed
2.25 psid.
2.
The maximum allowable ICW / CCW Basket Strainer element
(screening) differential pressure is 10.0 psid per
(
g)
p
p
p
Section 7.1.2, Developmental Reference 6.P. Operation with
p
p
differential pressures near or at 10.0 psid may challenge the
p
p
y
g
structural integrity of the Basket Strainer element (screening).
3.
While isolating an ICW/CCW Strainer, ICW flows below Minimum
g
Required ICW/CCW Flowrate are permitted for up to 5 minutes,
q
p
p
without declaring ICW System inoperable. If flow is below the
g
y
p
Minimum Required ICW/CCW Flowrate for greater than 5 minutes,
q
g
then the ICW System shall be declared inoperable at the time when
y
p
flow initially went below the Minimum Required ICW/CCW Flowrate.
NRC L-17-1 EXAM SECURE INFORMATION
499
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
9 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.4
CCW Heat Exchangers
1.
ICW outlet temperature from CCW HXs should NOT exceed 120qF.
2.
Maximum ICW flowrate to each CCW HX during normal operation
should NOT exceed 10,000 gpm in order to minimize long term tube
side erosion of the CCW HXs. The ICW flowrate for each CCW HX
may be increased to 12,850 gpm for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period to
accommodate HX or Basket Strainer cleanings.
3.
Minimum ICW flowrate to CCW HXs during normal operation should
be determined as follows:
If three CCW HXs are in service, then the minimum required
ICW flow rate is 11,000 gpm TOTAL, and at least 3500 gpm
If less than three CCW HXs are in service, or flow through any
HX is less than 3500 gpm, the Minimum Required ICW/CCW
Flowrate will be determined by the STA or Shift Manager per
Attachment 5, Instructions for Determining Minimum Flow
Using Flow Rate Curves or Manual Calculation.
To decrease the Minimum Required ICW/CCW Flowrate, the
CCW HX with highest tube resistance may be declared OOS
at the discretion of the Shift Manager while the basket strainer
is OOS. If a CCW HX is declared OOS, then the ICW flow
through that CCW HX can NOT be used to calculate the
Minimum Required ICW/CCW Flowrate.
2.2.5
TPCW Heat Exchangers
1.
ICW outlet temperature from TPCW HXs should NOT exceed 105qF.
2.
Maximum ICW flowrate to a TPCW HX during normal operation is
12,000 gpm.
3.
Minimum ICW flowrate to each in service TPCW HX is 8000 gpm. If
flowrate decreases to less than this value, then the System Engineer
should be notified.
4.
Attachment 8, Alternate Method to Determine ICW Flow Through the
TPCW Heat Exchangers, may be used to determine ICW flow
through a TPCW HX in the event the normal flow device is
unavailable.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
9 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.4
CCW Heat Exchangers
1.
ICW outlet temperature from CCW HXs should NOT exceed 120
0qF.
2.
Maximum ICW flowrate to each CCW HX during normal operation
g
p
should NOT exceed 10,000 gpm in order to minimize long term tube
gp
g
side erosion of the CCW HXs. The ICW flowrate for each CCW HX
may be increased to 12,850 gpm for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period to
y
gp
p
accommodate HX or Basket Strainer cleanings.
3.
Minimum ICW flowrate to CCW HXs during normal operation should
be determined as follows:
If three CCW HXs are in service, then the minimum required
q
ICW flow rate is 11,000 gpm TOTAL, and at least 3500 gpm
If less than three CCW HXs are in service, or flow through any
,
g
HX is less than 3500 gpm, the Minimum Required ICW/CCW
gp
q
Flowrate will be determined by the STA or Shift Manager per
y
g
p
Attachment 5, Instructions for Determining Minimum Flow
g
Using Flow Rate Curves or Manual Calculation.
To decrease the Minimum Required ICW/CCW Flowrate, the
q
,
CCW HX with highest tube resistance may be declared OOS
g
y
at the discretion of the Shift Manager while the basket strainer
g
is OOS. If a CCW HX is declared OOS, then the ICW flow
through that CCW HX can NOT be used to calculate the
g
Minimum Required ICW/CCW Flowrate.
NRC L-17-1 EXAM SECURE INFORMATION
500
TURKEY POINT - UNITS 3 & 4
3/4 0-1
AMENDMENT NOS. 235 AND 230
3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS
3/4.0 APPLICABILITY
LIMITING CONDITIONS FOR OPERATION
3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is
required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet
the Limiting Conditions for Operation, the associated ACTION requirements shall be met, except as provided in
Specification 3.0.6.
3.0.2
Noncompliance with a specification shall exist when the requirements of the Limiting Condition for
Operation and associated ACTION requirements are not met within the specified time intervals, except as
provided in Specification 3.0.6. If the Limiting Condition for Operation is restored prior to expiration of the
specified time intervals, completion of the ACTION requirements is not required.
3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION
requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action shall be initiated to place the unit, as applicable, in:
a.
At least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
b.
At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
c.
At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may
be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting
Condition for Operation. Exceptions to these requirements are stated in the individual specifications.
This specification is not applicable in MODES 5 or 6.
3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for
the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not
met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in
accordance with ACTION requirements when conformance to them permits continued operation of the facility for
an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL MODES as
required to comply with ACTION requirements. Exceptions to these requirements are stated in the individual
specifications.
NRC L-17-1 EXAM SECURE INFORMATION
501
TURKEY POINT - UNITS 3 & 4
3/4 7-17
AMENDMENT NOS. 263 AND 258
PLANT SYSTEMS
3/4.7.4 ULTIMATE HEAT SINK
LIMITING CONDITION FOR OPERATION
3.7.4 The ultimate heat sink shall be OPERABLE with an average supply water temperature less than or equal to
104F.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the requirements of the above specification not satisfied, be in at least HOT STANDBY within 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 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This ACTION shall be applicable to both units
simultaneously.
SURVEILLANCE REQUIREMENTS 4.7.4
The ultimate heat sink shall be determined OPERABLE:
a.
In accordance with the Surveillance Frequency Control Program by verifying the average supply
water temperature* is less than or equal to 104F.
b.
At least once per hour by verifying the average supply water temperature* is less than or equal to
104F, when water temperature exceeds 100F.
- Portable monitors may be used to measure the temperature.
NRC L-17-1 EXAM SECURE INFORMATION
502
Exam: Turkey Point 2017 NRC Exam - Question Worksheets
Examination Outline Cross-reference:
Level
Tier #
2
Group #
1
Topic and K/A #
076
2.1.23
Importance Rating
4.4
Conduct of Operations: Ability to perform specific system and integrated plant
procedures during all modes of plant operation.
Proposed Question: SRO Question # 88
Given the following conditions:
Unit 4 is operating at 25% power.
TPCW/ICW Isolation Valves, POV-4-4882 and 4883 have failed CLOSED.
The crew has entered 4-ONOP-019, Intake Cooling Malfunction.
POV-4-4882 has been opened manually using the local handwheel.
POV-4-4883 will NOT open.
Which one of the following identifies the status of TPCW cooling, and identifies the
technical specification implications of this event, if any?
A.
TPCW Cooling has been restored; Declare the 4A ICW header inoperable ONLY,
enter the action statement for LCO 3.7.3, Intake Cooling Water System, and
restore the inoperable header within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
B.
TPCW Cooling has been restored; Declare the 4A ICW header AND 4A train of
Safety Injection Automatic Actuation Logic inoperable and enter action for LCO 3.3.2, Engineered Safety Feature Actuation System, and restore the inoperable
train within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
C.
TPCW Cooling has NOT been restored; Declare the 4A ICW header AND 4A train
of Safety Injection Automatic Actuation Logic inoperable and enter action for LCO 3.3.2, Engineered Safety Feature Actuation System, and restore the inoperable
train within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D
TPCW Cooling has NOT been restored; Declare the 4A ICW header inoperable,
enter the action statement for LCO 3.7.3, Intake Cooling Water System, and
restore the inoperable header within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Proposed Answer: A
Page 8
NRC L-17-1 EXAM SECURE INFORMATION
503
ES-401, Page 21 of 52
5
Attachment 2
Figure 2-1 Screening for SRO-Only Linked to 10 CFR 55.43(b)(2)
(Technical Specifications)
Can the question be answered solely by knowing
-hour TS/TRM Action?
RO question
Yes
No
Can the question be answered solely by knowing
the LCO/TRM information listed above the line?
Yes
RO question
No
Can the question be answered solely by knowing
the TS safety limits?
Yes
RO question
No
Does the question involve one or more of the following for the
TS, TRM, or ODCM:
application of required actions (TS Section 3) and SRs (TS
Section 4) in accordance with rules of application
requirements (TS Section 1)
application of generic LCO requirements (LCO 3.0.1 through
3.0.7 and SR 4.0.1 through 4.0.4)
knowledge of TS bases that is required to analyze
TS-required actions and terminology
SRO-only
question
Yes
No
Question might not be linked to
10 CFR 55.43(b)(2) for SRO-only
application of required actions (TS Section 3) and SRs (TS
pp
q
(
)
Section 4) in accordance with rules of application
)
requirements (TS Section 1)
application of generic LCO requirements (LCO 3.0.1 through
pp
g
q
3.0.7 and SR 4.0.1 through 4.0.4)
NRC L-17-1 EXAM SECURE INFORMATION
504
REVISION NO.:
PROCEDURE TITLE:
PAGE:
24
INTAKE COOLING WATER SYSTEM
8 of 158
PROCEDURE NO.:
4-NOP-019
TURKEY POINT UNIT 4
2.2.2
ICW Pumps (continued)
7.
(continued)
E.
If diving activities are being performed on the east side of the
stationary screens, the affected CW pumps shall be secured
during the time the diver remains in the well. There are NO
specific limitations on ICW pump usage when diving activities
are performed on the east side of the stationary screens.
8.
When starting ICW Pumps, the maximum flow rates for the in-service
HXs may be exceeded. The high flow rate is acceptable provided the
duration of high flow is minimized.
9.
If time permits following the raking of an Intake Well, the respective
Intake Well CW Pump should operate for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to
starting the associated ICW Pump.
2.2.3
Basket Strainers
1.
DP across the ICW Basket Strainers at the CCW HXs should NOT
exceed 1.5 psid and at the TPCW HXs should NOT exceed
2.25 psid.
2.
The maximum allowable ICW / CCW Basket Strainer element
(screening) differential pressure is 10.0 psid per
Section 7.1.2, Developmental Reference 6.P. Operation with
differential pressures near or at 10.0 psid may challenge the
structural integrity of the Basket Strainer element (screening).
3.
While isolating an ICW/CCW Strainer, ICW flows below Minimum
Required ICW/CCW Flowrate are permitted for up to 5 minutes,
without declaring ICW System inoperable. If flow is below the
Minimum Required ICW/CCW Flowrate for greater than 5 minutes,
then the ICW System shall be declared inoperable at the time when
flow initially went below the Minimum Required ICW/CCW Flowrate.
TURKEY POINT - UNITS 3 & 4
3/4 7-16
AMENDMENT NOS. 263 AND 258
PLANT SYSTEMS
3/4.7.3 INTAKE COOLING WATER SYSTEM
LIMITING CONDITION FOR OPERATION
3.7.3
The Intake Cooling Water System (ICW) shall be OPERABLE with:
a.
Three ICW pumps, and
b.
Two ICW headers.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
a.
With only two ICW pumps with independent power supplies OPERABLE, restore the inoperable
ICW pump to OPERABLE status within 14 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The provisions of Specification 3.0.4 are
not applicable.
b.
With only one ICW pump OPERABLE or with two ICW pumps OPERABLE but not from
independent power supplies, restore two pumps from independent power supplies to OPERABLE
status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With only one ICW header OPERABLE, restore two headers to OPERABLE status within
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.3
The Intake Cooling Water System (ICW) shall be demonstrated OPERABLE:
a.
In accordance with the Surveillance Frequency Control Program by verifying that each valve
(manual, power-operated, or automatic) servicing safety-related equipment that is not locked,
sealed, or otherwise secured in position is in its correct position; and
b.
In accordance with the Surveillance Frequency Control Program during shutdown, by verifying
that:
1)
Each automatic valve servicing safety-related equipment actuates to its correct position
on a SI test signal, and
2)
Each Intake Cooling Water System pump starts automatically on a SI test signal.
3)
Interlocks required for system operability are OPERABLE.
5) Facility Comment (Q34)
Attachment 3
Executive Summary of Challenged Questions and FPL Recommendation
Question 34:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 34 provides the operator with a Loss of CCW scenario in which
one of the RCPs is experiencing High Motor Bearing temperatures. FPL recommends to accept both
A and D distractors as correct for question 34 since two procedures that are applicable during the
conditions described on the stem direct different actions, which are both applicable and correct.
Question 89:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 89 provides the operator with a scenario where one ICW/CCW
strainer and one ICW/TPCW strainer are being backwashed simultaneously. Subsequent failures
prevent restoration from backwashing operations. The question is to determine if a procedural
limitation from 4-NOP-019, Intake Cooling Water System, has been violated and if the Unit Supervisor
is required to apply TS 3.0.3. On question 89 it is unclear if an action statement was initially entered
when the ICW/CCW backwash was started. Due to conflicting answers as a result of a missing piece
of information FPL recommends to delete question 89 from the exam.
Question 94:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 94 is related knowledge of STA responsibilities. At Turkey Point,
our plant administrative procedure 0-ADM-200, Operations Management Manual, is more restrictive
than the Technical Specifications. This question did not specify which reference to use in order to
formulate a response. Due to conflicting answers FPL recommends to delete question 94 from the
exam.
Attachment 3
Facility Comments on question 34:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 34 provides the operator with a Loss of CCW scenario in which one
of the RCPs is experiencing High Motor Bearing temperatures. The way question 34 is presented to
the candidates, does not specifically ask about procedure hierarchy or the minimum required actions
for the given conditions; it only asks what are the RCP trip requirements in accordance with each
procedure In this case, A and D distractors both constitute correct answers:
A distractor is correct based on the 3-ONOP-030, Component Cooling Water Malfunction,
foldout page (Reference 1).
D distractor is correct based on the 3-ONOP-041.1, Reactor Coolant Pump Off-Normal, foldout
page (Reference 2).
Attachment 3
FPL recommendation: Entry conditions exist for both 3-ONOP-041.1 and 3-ONOP-030. A distractor
is correct because on a loss of CCW, 3-ONOP-030 requires to trip all RCPs. D distractor is correct
because 3-ONOP-041.1 RCP STOPPING CRITERIA for RCP motor bearing temperature is met,
requiring 3B RCP to be tripped. FPL recommends to accept both A and D distractors as correct for
question 34 since two procedures that are applicable during the conditions described on the stem
direct different actions, which are both applicable and correct.
References:
1. 3-ONOP-030, Component Cooling Water Malfunction, foldout page.
2. 3-ONOP-041.1, Reactor Coolant Pump Off-Normal, foldout page
6) Supporting Documentation for Facility
Comment (Q34)
NRC L-17-1 EXAM SECURE INFORMATION
Page 96
Examination Outline Cross-
reference:
Level
Tier #
2
Group #
1
Topic and K/A #
008
K3.03
Importance
Rating
4.1
Knowledge of the effect that a loss or malfunction of the CCWS will have on the
following: RCP
Proposed Question:
RO Question # 34
Given the following conditions:
Unit 3 experiences a total loss of CCW.
3B RCP Motor bearing temperature is 200°F and rising.
Which one of the following completes the statement below?
The RO is required to trip
(1)
as directed by
(2)
foldout page.
A.
(1) all the RCPs
(2) 3-ONOP-030, Component Cooling Water Malfunction
B.
(1) all the RCPs
(2) 3-ONOP-041.1, RCP Malfunction
C.
(1) ONLY 3B RCP
(2) 3-ONOP-030, Component Cooling Water Malfunction
D.
(1) ONLY 3B RCP
(2) 3-ONOP-041.1, RCP Malfunction
NRC L-17-1 EXAM SECURE INFORMATION
183
NRC L-17-1 EXAM SECURE INFORMATION
Page 97
Proposed Answer:
A
A.
Correct
IAW 3-ONOP-030 Foldout page.
B.
Incorrect
Part 2 is incorrect, but plausible since this is the appropriate procedure
entered for RCP motor bearing high temperature.
C.
Incorrect
Part 1 is incorrect but plausible since the criteria for stopping 3B RCP is
met based on high motor bearing temperature.
D.
Incorrect
Both parts are incorrect, but plausible per discussion above. Question parts
are independent and plausible as a whole.
Technical
Reference(s)
3-ONOP-030
3-ONOP-041.1
(Attach if not previously
provided)
Proposed Reference to be provided to applicants
during examination:
N
Learning
Objective:
LP 6902229 Obj 6
(As available)
Question Source:
Bank
Modified Bank
(Note changes or attach
parent)
New
X
Question History:
Last NRC
Exam:
Question Cognitive Level:
Memory or Fundamental
Knowledge
Comprehension or
Analysis
X
10 CFR Part 55 Content:
55.41
10
55.43
NRC L-17-1 EXAM SECURE INFORMATION
184
NRC L-17-1 EXAM SECURE INFORMATION
Page 98
Administrative, normal, abnormal, and emergency operating procedures for the
facility.
Comments:
NRC L-17-1 EXAM SECURE INFORMATION
185
REVISION NO.:
PROCEDURE TITLE:
PAGE:
8A
COMPONENT COOLING WATER MALFUNCTION
FOLDOUT
PROCEDURE NO.:
3-ONOP-030
TURKEY POINT UNIT 3
FOLDOUT PAGE
For Procedure 3-ONOP-030
TOTAL LOSS OF CCW FLOW
1) Manually TRIP the reactor.
2) CONFIRM reactor trip using the EOP network.
3) STOP all RCPs.
4) ISOLATE Letdown and Excess Letdown.
5) ESTABLISH one Charging Pump running at maximum speed, and DISPATCH
operator to establish emergency cooling water to one of the remaining two
Charging Pumps per Attachment 1.
6) MONITOR RCS pressure closely while running Charging Pump at maximum speed.
7) WHEN Attachment 1 is COMPLETE, THEN OPERATE Charging Pump supplied with
emergency cooling to maintain RCP seal cooling.
LOSS OF CCW TO ANY COMPONENT
IF Component Cooling Water flow to any component cooled by CCW is lost, THEN SHUT
DOWN the affected component.
CHARGING PUMP EMERGENCY COOLING CRITERIA
IF Cooling Water is NOT available to Charging Pumps, THEN OPERATE Charging Pump at
maximum speed until cooling is restored from CCW System or per Attachment 1.
CCW PUMP STOPPING CRITERIA
IF any Component Cooling Water Pump is cavitating, THEN STOP the affected Component
Cooling Water Pumps, and PLACE in PULL-TO-LOCK.
REACTOR TRIP CRITERIA
IF tripping a RCP is required, THEN manually TRIP the reactor prior to STOPPING the RCP.
RCP STOPPING CRITERIA
IF any RCP bearing temperature annunciator alarm actuates AND its associated motor
bearing temperature is greater than 195qF, THEN TRIP reactor and STOP the affected RCPs.
CCW PUMPS, HEAT EXCHANGERS, AND FLOWS/LOADS
CCW System operation once CCW System Header has been restored shall be within the
operating restrictions of 3-NOP-030 summarized as follows:
N-1 CCW Pumps (where N = number of CCW HXs aligned to CCW)
All CCW HXs in service when RHR in service
With only two CCW HXs in service AND both RHR HXs aligned to CCW, PLACE two
CCW Pumps in PULL-TO-LOCK.
Maximum five out of six CCW Heat Loads.
TOTAL LOSS OF CCW FLOW
1) Manually TRIP the reactor.
)
y
2) CONFIRM reactor trip using the EOP network.
)
3) STOP all RCPs.
NRC L-17-1 EXAM SECURE INFORMATION
186
Procedure No.:
3-ONOP-041.1
Procedure Title:
Reactor Coolant Pump Off-Normal
Page:
Foldout
Approval Date:
5/3/16
W2010:/ab/cls/cls
FOLDOUT PAGE FOR PROCEDURE 3-ONOP-041.1
1. RCP STOPPING CRITERIA
IF any of the following RCP limits are reached, THEN manually Trip the Reactor, and verify Reactor Trip using
the EOP network, and then stop the affected RCP, and close PCV-3-455A, PZR Spray Valve Loop C, or
PCV-3-455B, PZR Spray Valve Loop B, if applicable.
RCP pump bearing temperature on DCS - GREATER THAN OR EQUAL TO 225F.
RCP motor bearing temperature on DCS - GREATER THAN OR EQUAL TO 195F.
RCP stator winding temperature on DCS - GREATER THAN OR EQUAL TO 248F.
Note exception in Foldout Page Item 4.
Motor frame vibration, R-3-369 (Points 1, 2, 5, 6, 9, 10) - GREATER THAN OR EQUAL TO 5 MILS.
Note exception in Foldout Page Item 4.
RCP shaft vibration, R-3-369 (Points 3, 4, 7, 8, 11, 12) - GREATER THAN OR EQUAL TO 20 MILS.
Note exception in Foldout Page Item 4.
2. RCP SEAL CRITERIA FOR STOPPING RCP
IF any of the following RCP limits are reached, THEN manually Trip the Reactor, and verify the Reactor
Tripped using the EOP network, and stop the affected RCP, Close the applicable RCP CBO Isolation Valve
303A, 303B, or 303C, and Close PCV-3-455A, PZR Spray Valve Loop C, or PCV-3-455B, PZR Spray Valve
Loop B, if applicable.
RCP CBO temperatures on DCS - GREATER THAN OR EQUAL TO 260F.
RCP CBO flow exceeds 4.1 gpm
Any Seal Stage differential pressure exceeds 2000 psid AND respective CBO Isolation valve
(CV-3-303A, 303B or 303C) is Open
3. FAST LOAD REDUCTION CRITERIA
IF any of the following RCP limits are reached, THEN perform 3-GOP-100, Fast Load Reduction.
RCP CBO Flow - GREATER THAN 3.7 gpm AND increasing
DP across any Seal Stage - GREATER THAN 1700 psid AND respective CBO Isolation valve
(CV-3-303A, 303B or 303C) is Open
ALL of the following indications exist on the same RCP indicating a failed #3 Seal
RCP CBO Flow - LESS THAN 0.5 gpm
RCP CBO isolation vale - OPEN
P3 pressure - LESS THAN 100 psig
P2 pressure - GREATER THAN 1000 psig
4. EXCEEDING VIBRATION OR STATOR TEMPERATURE LIMITS
For the basis of obtaining data for startup, for balancing an RCP, or for shutdown operations; the
Electrical Maintenance Supervisor or Component Engineering Supervisor may authorize continued
RCP operations with vibration level or stator winding temperature above stopping criteria noted in
Foldout Page Item 2. This authorization is required to be obtained prior to starting the RCP.
When in EOP network, RCP stator winding temperature on DCS -
GREATER THAN OR EQUAL TO 300F.
5. RCP VIBRATION ASSESSMENT CRITERIA
IF motor frame vibration, R-3-369 (Points 1, 2, 5, 6, 9, 10), is greater than or equal to 3 mils, but less than
5 mils, THEN contact Engineering to evaluate the condition.
NRC L-17-1 EXAM SECURE INFORMATION
187
REVISION NO.:
PROCEDURE TITLE:
PAGE:
8A
COMPONENT COOLING WATER MALFUNCTION
FOLDOUT
PROCEDURE NO.:
3-ONOP-030
TURKEY POINT UNIT 3
FOLDOUT PAGE
For Procedure 3-ONOP-030
TOTAL LOSS OF CCW FLOW
1) Manually TRIP the reactor.
2) CONFIRM reactor trip using the EOP network.
3) STOP all RCPs.
4) ISOLATE Letdown and Excess Letdown.
5) ESTABLISH one Charging Pump running at maximum speed, and DISPATCH
operator to establish emergency cooling water to one of the remaining two
Charging Pumps per Attachment 1.
6) MONITOR RCS pressure closely while running Charging Pump at maximum speed.
7) WHEN Attachment 1 is COMPLETE, THEN OPERATE Charging Pump supplied with
emergency cooling to maintain RCP seal cooling.
LOSS OF CCW TO ANY COMPONENT
IF Component Cooling Water flow to any component cooled by CCW is lost, THEN SHUT
DOWN the affected component.
CHARGING PUMP EMERGENCY COOLING CRITERIA
IF Cooling Water is NOT available to Charging Pumps, THEN OPERATE Charging Pump at
maximum speed until cooling is restored from CCW System or per Attachment 1.
CCW PUMP STOPPING CRITERIA
IF any Component Cooling Water Pump is cavitating, THEN STOP the affected Component
Cooling Water Pumps, and PLACE in PULL-TO-LOCK.
REACTOR TRIP CRITERIA
IF tripping a RCP is required, THEN manually TRIP the reactor prior to STOPPING the RCP.
RCP STOPPING CRITERIA
IF any RCP bearing temperature annunciator alarm actuates AND its associated motor
bearing temperature is greater than 195F, THEN TRIP reactor and STOP the affected RCPs.
CCW PUMPS, HEAT EXCHANGERS, AND FLOWS/LOADS
CCW System operation once CCW System Header has been restored shall be within the
operating restrictions of 3-NOP-030 summarized as follows:
N-1 CCW Pumps (where N = number of CCW HXs aligned to CCW)
All CCW HXs in service when RHR in service
With only two CCW HXs in service AND both RHR HXs aligned to CCW, PLACE two
CCW Pumps in PULL-TO-LOCK.
Maximum five out of six CCW Heat Loads.
Procedure No.:
3-ONOP-041.1
Procedure Title:
Reactor Coolant Pump Off-Normal
Page:
Foldout
Approval Date:
5/3/16
W2010:/ab/cls/cls
FOLDOUT PAGE FOR PROCEDURE 3-ONOP-041.1
1. RCP STOPPING CRITERIA
IF any of the following RCP limits are reached, THEN manually Trip the Reactor, and verify Reactor Trip using
the EOP network, and then stop the affected RCP, and close PCV-3-455A, PZR Spray Valve Loop C, or
PCV-3-455B, PZR Spray Valve Loop B, if applicable.
RCP pump bearing temperature on DCS - GREATER THAN OR EQUAL TO 225F.
RCP motor bearing temperature on DCS - GREATER THAN OR EQUAL TO 195F.
RCP stator winding temperature on DCS - GREATER THAN OR EQUAL TO 248F.
Note exception in Foldout Page Item 4.
Motor frame vibration, R-3-369 (Points 1, 2, 5, 6, 9, 10) - GREATER THAN OR EQUAL TO 5 MILS.
Note exception in Foldout Page Item 4.
RCP shaft vibration, R-3-369 (Points 3, 4, 7, 8, 11, 12) - GREATER THAN OR EQUAL TO 20 MILS.
Note exception in Foldout Page Item 4.
2. RCP SEAL CRITERIA FOR STOPPING RCP
IF any of the following RCP limits are reached, THEN manually Trip the Reactor, and verify the Reactor
Tripped using the EOP network, and stop the affected RCP, Close the applicable RCP CBO Isolation Valve
303A, 303B, or 303C, and Close PCV-3-455A, PZR Spray Valve Loop C, or PCV-3-455B, PZR Spray Valve
Loop B, if applicable.
RCP CBO temperatures on DCS - GREATER THAN OR EQUAL TO 260F.
RCP CBO flow exceeds 4.1 gpm
Any Seal Stage differential pressure exceeds 2000 psid AND respective CBO Isolation valve
(CV-3-303A, 303B or 303C) is Open
3. FAST LOAD REDUCTION CRITERIA
IF any of the following RCP limits are reached, THEN perform 3-GOP-100, Fast Load Reduction.
RCP CBO Flow - GREATER THAN 3.7 gpm AND increasing
DP across any Seal Stage - GREATER THAN 1700 psid AND respective CBO Isolation valve
(CV-3-303A, 303B or 303C) is Open
ALL of the following indications exist on the same RCP indicating a failed #3 Seal
RCP CBO Flow - LESS THAN 0.5 gpm
RCP CBO isolation vale - OPEN
P3 pressure - LESS THAN 100 psig
P2 pressure - GREATER THAN 1000 psig
4. EXCEEDING VIBRATION OR STATOR TEMPERATURE LIMITS
For the basis of obtaining data for startup, for balancing an RCP, or for shutdown operations; the
Electrical Maintenance Supervisor or Component Engineering Supervisor may authorize continued
RCP operations with vibration level or stator winding temperature above stopping criteria noted in
Foldout Page Item 2. This authorization is required to be obtained prior to starting the RCP.
When in EOP network, RCP stator winding temperature on DCS -
GREATER THAN OR EQUAL TO 300F.
5. RCP VIBRATION ASSESSMENT CRITERIA
IF motor frame vibration, R-3-369 (Points 1, 2, 5, 6, 9, 10), is greater than or equal to 3 mils, but less than
5 mils, THEN contact Engineering to evaluate the condition.
7) Facility Comment (Q94)
Attachment 3
Executive Summary of Challenged Questions and FPL Recommendation
Question 34:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 34 provides the operator with a Loss of CCW scenario in which
one of the RCPs is experiencing High Motor Bearing temperatures. FPL recommends to accept both
A and D distractors as correct for question 34 since two procedures that are applicable during the
conditions described on the stem direct different actions, which are both applicable and correct.
Question 89:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 89 provides the operator with a scenario where one ICW/CCW
strainer and one ICW/TPCW strainer are being backwashed simultaneously. Subsequent failures
prevent restoration from backwashing operations. The question is to determine if a procedural
limitation from 4-NOP-019, Intake Cooling Water System, has been violated and if the Unit Supervisor
is required to apply TS 3.0.3. On question 89 it is unclear if an action statement was initially entered
when the ICW/CCW backwash was started. Due to conflicting answers as a result of a missing piece
of information FPL recommends to delete question 89 from the exam.
Question 94:
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 94 is related knowledge of STA responsibilities. At Turkey Point,
our plant administrative procedure 0-ADM-200, Operations Management Manual, is more restrictive
than the Technical Specifications. This question did not specify which reference to use in order to
formulate a response. Due to conflicting answers FPL recommends to delete question 94 from the
exam.
Attachment 3
Facility Comments on question 94 :
This question is being challenged in accordance with NUREG 1021 REV 11, ES-403 for the following
reason: a question with an unclear stem that confused the applicants or did not provide all the
necessary information. Question 94 is related to operators knowledge on STA responsibilities.
Attachment 3
At Turkey Point our plant administrative procedure 0-ADM-200, Operations Management
Manual, is more restrictive than the Technical Specification requirement. Technical
Specifications Administrative Controls Section allows for a NPS (Shift Manager) to assume the
STA position. From the Tech Spec Administrative Controls (Reference 5) stand point the STA
is allowed to assume the command and control responsibilities and C is the correct answer:
Attachment 3
Procedural limitations present in 0-ADM-200, Operations Management Manual,
(Reference 6) prevent the STA to assume command and control functions. In this case D
distractor is the correct answer.
FPL recommendation: Question 94 did not specify to answer in accordance with Tech Specs or
0-ADM-200. If answering from the Tech Specs point of view, the STA is allowed to assume
Command and Control functions as Tech Specs allows dual role to be assumed for the STA and Shift
Manager positions (at Turkey Point all STAs are SRO licensed). 0-ADM-200 does not allow the STA
to assume Command and Control functions. Based on the standard used to answer this question the
candidates will arrive at conflicting answers as it refers to the ability of the STA to assume Command
and Control functions. Due to conflicting answers FPL recommends to delete question 94 from the
exam.
Reference:
5. Tech Spec Table 6.2-1. (Reference 5).
6. 0-ADM-200, Operations Management Manual (Reference 6)
8) Supporting Documentation for Facility
Comment (Q94)
NRC L-17-1 EXAM SECURE INFORMATION
Page 265
Examination Outline Cross-
reference:
Level
Tier #
3
Group #
1
Topic and K/A #
G1
2.1.1
Importance
Rating
4.2
Conduct of Operations: Knowledge of conduct of operations requirements.
Proposed Question: SRO Question # 94
Given the following conditions:
Unit 3 is in MODE 5.
Unit 4 is in MODE 4.
Which one of the following identifies the responsibilities of the SRO assigned to
the STA position?
(1)
required to remain within 10 minutes of
the control room and
(2)
allowed to assume command and control
responsibilities.
A.
(1) is NOT
(2) is
B.
(1) is NOT
(2) is NOT
C.
(1) is
(2) is
D.
(1) is
(2) is NOT
Proposed Answer: D
A.
Incorrect
Both parts incorrect; Plausible because the US with STA responsibilities is
not required to be in the control room per ADM-200,but because Unit 4 is
in Mode 1, they must be within 10 minutes of the control room
NRC L-17-1 EXAM SECURE INFORMATION
529
NRC L-17-1 EXAM SECURE INFORMATION
Page 266
B.
Incorrect
Wrong for same reason as Option A part 1. Part 2 Plausible because the
applicant may consider that unit 3 is in Mode 5 and STA duties are not
required.
C.
Incorrect
2nd part is incorrect; plausible because Unit 3 is in MODE 5 and an STA is
not required in MODE 5 IAW Tech spec Table 6.2-1.
D.
Correct
IAW 0-ADM-200.
Technical
Reference(s)
0-ADM-200
(Attach if not previously
provided)
Proposed Reference to be provided to applicants
during examination:
N
Learning
Objective:
6902025 Obj. 5
(As available)
Question Source:
Bank
Modified Bank
(Note changes or attach
parent)
New
X
Question History:
Last NRC
Exam:
Question Cognitive Level:
Memory or Fundamental
Knowledge
X
Comprehension or
Analysis
10 CFR Part 55 Content:
55.41
55.43
1
Conditions and limitations in the facility license
Comments:
NRC L-17-1 EXAM SECURE INFORMATION
530
REVISION NO.:
PROCEDURE TITLE:
PAGE:
31
OPERATIONS MANAGEMENT MANUAL
13 of 72
PROCEDURE NO.:
0-ADM-200
TURKEY POINT PLANT
3.0
RESPONSIBILITIES (continued)
4.
Control Room Supervisor (CRS) - The CRS reports to the SM. If assigned to
the Work Control Center, the CRS reports to the Work Control Center
Supervisor (WCCS) during an outage and the SM during non-outage times.
The CRS is responsible for:
A.
Reviewing and approving Plant Work Orders electronically via NAMS for
Pre-reviews and eWP.
B.
Maintaining the equipment out-of-service book in accordance with
0-ADM-213, Technical Specification Related Equipment and Risk
Significant SSC Out-Of-Service Logbook.
C.
Reviewing and approving clearances.
D.
Coordinating the activities from the Work Control Center, when assigned
to the Work Control Center.
NOTE
The STA position shall be manned when one or both units are in
MODES 1, 2, 3, or 4.
The STA position may be vacant for a period of time NOT to exceed
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for emergency reasons provided immediate action is taken to fill
the STA position to meet or exceed the minimum requirements. This
provision does NOT permit any STA position to be unmanned upon shift
change due to an oncoming STA being late or absent.
E.
When assigned Shift Technical Advisor responsibilities, the Unit
Supervisor:
Monitors Ultimate Heat Sink performance by trending ICW/CCW
Heat Exchanger performance in accordance with 3/4-OSP-019.4,
CCW Heat Exchanger Performance Monitoring.
Reviews Temporary System Alterations (TSA) in accordance with
EN-AA-205-1102, Temporary Configuration Changes
Supports Post Trip Reviews (PTR) in accordance with
0-ADM-511, Post Trip Review (PTR).
Maintains Continuing Training Requirements per TPD-E05, STA
Initial and Continuing Training Program, and 0-EPIP-20201,
Maintaining Emergency Preparedness Radiological Emergency
Plan Training.
E.
When assigned Shift Technical Advisor responsibilities, the Unit
g
Supervisor:
NRC L-17-1 EXAM SECURE INFORMATION
531
REVISION NO.:
PROCEDURE TITLE:
PAGE:
31
OPERATIONS MANAGEMENT MANUAL
14 of 72
PROCEDURE NO.:
0-ADM-200
TURKEY POINT PLANT
3.0
RESPONSIBILITIES (continued)
4.
E.
(continued)
Remains within 10 minutes of the Control Room.
When directed in the EOP network, monitors Critical Safety
Function Status Trees in accordance with 3/4-EOP-F-0.
Provides an independent, dedicated concern for the safety of the
Turkey Point Nuclear Plant by advising the Shift Manager on
actions to terminate or mitigate the consequences of such events.
Serves in an advisory capacity only and does NOT assume
command or control functions.
During an accident situation, the STA remains in the Control
Room and assesses plant conditions. Upon entry into the EOP
network, the STA ceases collateral duties and gives full attention
to the primary duty of independent assessment of core safety. In
performing this assessment, the STA does the following:
a.
Independently evaluates plant response, diagnoses the
event, and verifies maintenance of plant safety functions.
b.
Maintains a broad, big-picture perspective of the event.
c.
Based on assessment of the relevant facts and data,
makes recommendations concerning maintenance of
safety functions to the Shift Manager.
Is relieved of accident assessment responsibilities only by another
STA.
Remains within 10 minutes of the Control Room.
Serves in an advisory capacity only and does NOT assume
y
p
y
command or control functions.
NRC L-17-1 EXAM SECURE INFORMATION
532
ES-401, Page 24 of 52
8
Attachment 2
Figure 2-2 Screening for SRO-Only Linked to 10 CFR 55.43(b)(5)
(Assessment and Selection of Procedures)
Can the question be answered solely by knowing
systems knowledge (i.e., how the system works,
flowpath, logic, component location)?
RO question
Yes
No
Can the question be answered solely by knowing
immediate operator actions?
Yes
Can the question be answered solely by knowing
entry conditions for AOPs or plant parameters
that require direct entry into major EOPs?
Yes
No
Does the question require one or more of the following:
assessment of plant conditions (normal, abnormal, or
emergency) and then selection of a procedure or section of
a procedure to mitigate or recover, or with which to
proceed
knowledge of when to implement attachments and
appendices, including how to coordinate these items with
procedure steps
knowledge of diagnostic steps and decision points in the
EOPs that involve transitions to event-specific
sub-procedures or emergency contingency procedures
knowledge of administrative procedures that specify
hierarchy, implementation, and/or coordination of plant
normal, abnormal, and emergency procedures
SRO-only
question
Yes
Can the question be answered solely by knowing
the purpose, overall sequence of events, or
overall mitigative strategy of a procedure?
No
No
Yes
Question might not be linked to
10 CFR 55.43(b)(5) for SRO-only
No
RO question
RO question
RO question
g
y
g
y
knowledge of administrative procedures that specify
g
p
p
y
hierarchy, implementation, and/or coordination of plant
y
p
normal, abnormal, and emergency procedures
NRC L-17-1 EXAM SECURE INFORMATION
533
TURKEY POINT - UNITS 3 & 4
6-2
AMENDMENT NOS. 229 AND 225
ADMINISTRATIVE CONTROLS
PLANT STAFF
6.2.2
The plant organization shall be subject to the following:
a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in
Table 6.2-1;
b.
DELETED
c.
At least two licensed Operators shall be present in the control room during reactor startup,
scheduled reactor shutdown and during recovery from reactor trips. In addition, while either unit
is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room;
d.
A Health Physics Technician* shall be on site when fuel is in the reactor;
e.
All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior
Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent
responsibilities during this operation; and
f.
DELETED
h.
The Operations Supervisor shall hold a Senior Reactor Operator License.
i.
The Operations Manager shall either:
1.
hold or have held a Senior Reactor Operator License on the Turkey Point Plant; or,
2.
have held a Senior Reactor Operator License on a similar plant (i.e., another pressurized
water reactor); or
3.
have completed the Turkey Point Plant Senior Management Operations Training Course.
(i.e., certified at an appropriate simulator for equivalent senior operator knowledge level.)
- The Health Physics Technician composition may be less than the minimum requirements for a period of time
not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill
the required positions.
TURKEY POINT - UNITS 3 & 4
6-3
AMENDMENT NOS. 260 AND 255
ADMINISTRATIVE CONTROLS
TABLE 6.2-1
MINIMUM SHIFT CREW COMPOSITION
POSITION
NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION
BOTH UNITS IN
MODE 1, 2, 3, or 4
BOTH UNITS IN
MODE 5 or 6
OR DEFUELED
ONE UNIT IN MODE 1, 2, 3, or 4
AND
ONE UNIT IN MODE 5 or 6 or DEFUELED
1
1
1
1
none**
1
3*
2*
3*
3*
3*
3*
1***
none
1***
NPS - Nuclear Plant Supervisor with a Senior Operator license
SRO - Individual with a Senior Operator license
- Individual with an Operator license
- Auxiliary Operator
The shift crew composition may be one less than the minimum requirements of Table 6.2-1 for a period of time
not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided
immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift
crewman being late or absent.
During any absence of the Nuclear Plant Supervisor from the control room while a unit is in MODE 1, 2, 3, or 4,
an individual (other than the Shift Technical Advisor) with a valid Senior Operator license shall be designated to
assume the control room command function. During any absence of the Nuclear Plant Supervisor from the control
room while both units are in MODE 5 or 6, an individual with a valid Senior Operator license or Operator license
shall be designated to assume the control room command function.
- At least one of the required individuals must be assigned to the designated position for each unit.
- At least one licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling must be present
during CORE ALTERATIONS on either unit, who has no other concurrent responsibilities.
- The STA position may be filled by the Nuclear Plant Supervisor or an individual with a Senior Operator license
who meets the 1985 NRC Policy Statement on Engineering Expertise on Shift.
REVISION NO.:
PROCEDURE TITLE:
PAGE:
31
OPERATIONS MANAGEMENT MANUAL
14 of 72
PROCEDURE NO.:
0-ADM-200
TURKEY POINT PLANT
3.0
RESPONSIBILITIES (continued)
4.
E.
(continued)
Remains within 10 minutes of the Control Room.
When directed in the EOP network, monitors Critical Safety
Function Status Trees in accordance with 3/4-EOP-F-0.
Provides an independent, dedicated concern for the safety of the
Turkey Point Nuclear Plant by advising the Shift Manager on
actions to terminate or mitigate the consequences of such events.
Serves in an advisory capacity only and does NOT assume
command or control functions.
During an accident situation, the STA remains in the Control
Room and assesses plant conditions. Upon entry into the EOP
network, the STA ceases collateral duties and gives full attention
to the primary duty of independent assessment of core safety. In
performing this assessment, the STA does the following:
a.
Independently evaluates plant response, diagnoses the
event, and verifies maintenance of plant safety functions.
b.
Maintains a broad, big-picture perspective of the event.
c.
Based on assessment of the relevant facts and data,
makes recommendations concerning maintenance of
safety functions to the Shift Manager.
Is relieved of accident assessment responsibilities only by another
STA.