ML20096C947
| ML20096C947 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/11/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20096C951 | List: |
| References | |
| DPR-44-A-211, DPR-56-A-216 NUDOCS 9601180381 | |
| Download: ML20096C947 (26) | |
Text
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. -a aaat
\\...../
PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.211 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated November 30, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and 4
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
9601180381 960111 PDR ADOCK 05000277 P
l '
l (2) Technical Snecifications 4
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 211, are hereby incorporated in the license.
PECO Energy Company shall operate the facility in accordance j
with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and is to be implemented concurrently with Amendment 210, issued August 30, 1995.
FOR THE NUCLEAR REGULATORY COMISSION
/
Joh
. Stolz, Direct Rr ject Directorate
-2 Division of Reactor Projects - I/II Office of Nuclear Reactor. Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 11, 1996
~
1 o
ATTACHMENT TO LICENSE AMENDMENT NO. 211 FACILITY OPERATING LICENSE NO. OPR-44 I
DOCKET N0. 50-277 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Insert 3.1-16 3.1-16 3.1-17 3.1-17 3.9-8 3.9-8 3.10-23 3.10-23 B3.1-31 B3.1-31 B3.1-32 B3.1-32 B3.1-33 83.1-33 B3.9-14 B3.9-14 B3.9-15 B3.9-15 B3.10-36 B3.10-36 O
i
l Control Rod Scram Accumulators 3.1.5 i
ACTIONS (continued) i CONDITION REQUIRED ACTION COMPLETION TINE l
j 8.
Two or more control B.1 Restore charging 20 minutes from rod scram accumulators water header pressure discovery of j
inoperable with to 2 940 psig.
Condition B l
reactor steam done concurrent with i
pressure 2 900 psig.
j charging water header pressure
< 940 psig l
1 4
i B.2.1
NOTE---------
]
Only applicable if the associated a
3 control rod scram 4
time was within the
{
limits of j
Table 3.1.4-1 during the last scram time j
Surveillance.
Declare the I hour associated control 4
rod scram time
" slow."
QR l
B.2.2 Declare the I hour i
associated control rod inoperable.
i (continued) i i
PBAPS UNIT 2 3.1-16 Amendment No. 210, 211
{
Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable with inoperable charging water reactor steam done accumulators are header pressure pressure < 900 psig.
fully inserted.
< 940 psig 8252 C.2 Declare the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated control rod inoperable.
D.
Required Action B.1 or D.1
NOTE---------
C.1 and associated Not applicable if all Completion Time not inoperable control met.
rod scram accumulators are associated with fully inserted control rods.
Place the reactor Immediately mode switch in the shutdown position.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is ;t 940 psig.
PBAPS UNIT 2 3.1-17 Amendment No. M.
211
Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling 1
)
LCO 3.9.5 Each withdrawn control rod shall be OPERA 8LE.
APPLICABILITY:
MODE 5.
ACTIONS i
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more withdrawn A.1 Initiate action to Immediately control rods fully insert inoperable.
inoperable withdrawn control rods.
4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1
NOTE--------------------
Not required to be performed until 7 days after the control rod is withdrawn.
Insert each withdrawn control rod at least 7 days one notch.
SR 3.9.5.2 Verify each withdrawn control rod scram 7 days i
accumulator pressure is ;t 940 psig.
I PBAPS UNIT 2 3.9-8 Amendment No.210, 211
~..-- -
y a
SDN Test-Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify each withdrawn control rod does not Each time the go to the withdrawn overtravel position.
control rod is withdrawn to
" full out" position 8E Ptior to satisfying LC0 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days 2 940 psig.
PBAPS UNIT 2 3.10-23 Amendment No.H.1 211
Control Rod Scram Accumulators B 3.1.5 BASES ACTIONS A.1 and A.2 (continued) control rod is declared inoperable (Required Action A.2) and LCO 3.1.3 is entered. This would result in requiring the affected control rod to be fully inserted and disarmed, thereby satisfying its intended function, in accordance with ACTIONS of LCO 3.1.3.
The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is reasonable, based on the large number of control rods available to provide the scram function and the ability of the affected control rod to scram only with reactor pressure at high reactor pressures.
B.1. B.2.1. and B.2.2 With two or more control rod scram accumulators inoperable and reactor steam dome pressure ;t 900 psig, adequate pressure must be supplied to the charging water header With inadequate charging water pressure, all of the accumulators could become inoperable, resulting in a potentially severe degradation of the scram performance.
Therefore, within 20 minutes from discovery of charging water header pressure < 940 psig concurrent with Condition B, adequate charging water header pressure must be restored. The allowed Completion Time of 20 minutes is reasonable, to place a CRD pump into service to restore the charging water header pressure, if required. This Completion Time is based on the ability of the reactor pressure alone to fully insert all control rods.
The control rod may be declared " slow," since the control rod will still scram using only reactor pressure, but may not satisfy the times in Table 3.1.4-1.
Required Action B.2.1 is modified by a Note indicating that declaring the control rod " slow" only applies if the associated control scram time is within the limits of Table 3.1.4-1 during the last scram time test. Otherwise, the control rod would already be considered " slow" and the further degradation of scram performance with an inoperable accumulator could result in excessive scram times.
In this event, the associated control rod is declared inoperable (Required Action B.2.2) and LCO 3.1.3 entered. This would (continued)
PBAPS UNIT 2 B 3.1-31 Amendment No. 211
. _..~. -.-. -- -
m 1l Control Rod Scram Accumulators I
B 3.1.5 BASES ACTIONS 8.1. B.2.1. and B.2.2 (continued) result in requiring the affected control rod to be fully i
inserted and disarmed, thereby satisfying its intended j
function in accordance with ACTIONS of LC0 3.1.3.
The allowed Completion Time of I hour is reasonable, based on the ability of only the reactor pressure to scram the control rods and the low probability of a DBA or transient occurring while the affected accumulators are inoperable.
C.1 and C.2 i
With one or more control rod scram accumulators inoperable and the reactor steam done pressure < 900 psig, the pressure supplied to the charging water header must be adequate to ensure that accumulators remain charged. With the reactor steam dome pressure < 900 psig, the function of the accumulators in providing the scram force becomes much more important since the scram function could become severely i
degraded during a depressurization event or at low reactor pressures. Therefore, immediately upon discovery of charging water header pressure < 940 psig, concurrent with Condition C, all control rods associated with inoperable accumulators must be verified to be fully inserted.
Withdrawn control rods with inoperable accumulators may fail to scram under these low pressure conditions. The associated control rods must also be declared inoperable within I hour. The allowed Completion Time of I hour is reasonable for Required Action C.2, considering the low probability of a DBA or transient occurring during the time that the accumulator is inoperable.
D.d
~
The reactor mode switch must be immediately placed in the shutdown position if either Required Action and associated Completion Time associated with the loss of the CRD charging pump (Required Actions B.1 and C.1) cannot be met. This ensures that all insertable control rods are inserted and that the reactor is in a condition that does not require the (continued)
PBAPS UNIT 2 B 3.1-32 Amendment No. 211
.-.-----------------------q--
Control Rod Scram Accumulators B 3.1.5 BASES ACTIONS QJ (continued) active function (i.e., scram) of the control rods. This Required Action is modified by a Note stating that the action is not applicable if all control rods associated with the inoperable scram accumulators are fully inserted, since the function of the control rods has been performed.
SURVEILLANCE SR 3.1.5.1 REQUIREMENTS SR 3.1.5.1 requires that the accumulator pressure be checked every 7 days to ensure adequate accumulator pressure exists to provide sufficient scram force. The primary indicator of accumulator OPERA 8ILITY is the accumulator pressure. A minimum accumulator pressure is specified, below which the capability of the accumulator to perform its intended function becomes degraded and the accumulator is considered inoperable. The minimum accumulator pressure of 940 psig is l
well below the expected pressure of approximately 1450 psig (Ref. 1). Declaring the accumulator inoperable when the minimum pressure is not maintained ensures that significant degradation in scram times does not occur. The 7 day Frequency has been shown to be acceptable through operating experience and takes into account indications available in the control room.
REFERENCES 1.
UFSAR, Section 3.4.5.3 and Figure 3.4.10.
2.
UFSAR, Appendix K,Section VI.
3.
UFSAR, Chapter 14.
PBAPS UNIT 2 8 3.1-33 Amendment No. 211
g Control Rod OPERABILITY-Refueling B 3.9.5 i
B 3.9 REFUELING OPERATIONS B 3.9.5 Control Rod OPERABILITY-Refueling BASES BACKGROUND Control rods are components of the Control Rod Drive (CRD)
System, the primary reactivity control system for the,
reactor.
In conjunction with the Reactor Protection System, the CRD System provides the means for the reliable control of reactivity changes during refueling operation.
In l
addition, the control rods. provide the capability to maintain the reactor subcritical under all conditions and to limit the potential amount and rate of reactivity increase caused by a malfunction in the CR0 System.
UFSAR design criteria require that one of the two required independent reactivity control systems be capable of holding the reactor core suberitical under cold conditions (Ref.1).
The CR0 System is the system capable of maintaining the reactor subcritical in cold conditions.
APPLICABLE Prevention and mitigation of prompt reactivity excursions SAFETY ANALYSES during refueling are provided by refueling interlocks (LCO 3.9.1 and LCO 3.9.2), the SON (LC0 3.1.1, the intermediate range monitor neutron flux scram)(LC0 3.3.1.1),
and the control rod block instrumentation (LC0 3.3.2.1).
The safety analyses for the control rod withdrawal error during refueling (Ref. 2) and the fuel assembly insertion
)
error (Ref. 3) evaluate the consequences of control rod withdrawal during refueling and also fuel assembly insertion with a control rod withdrawn. A prompt reactivity excursion during refueling could potentially result in fuel failure with subsequent release of radioactive material to the environment. Control rod scram provides protection should a prompt reactivity excursion occur.
Control rod OPERABILITY during refueling satisfies Criterion 3 of the NRC Policy Statement.
LCO Each withdrawn control rod must be OPERABLE. The withdrawn control rod is considered OPERABLE if the scram accumulator pressure is 2 940 psig and the control rod is capable of (continued)
PBAPS UNIT 2 8 3.9-14 Amendment No. 211
y Control Rod OPERA 8ILITY-Refueling B 3.9.5 BASES LCO being automatically inserted upon receipt of a scram signal.
(continued)
Inserted control rods have already completed their reactivity control function, and therefore, are not required to be bPERABLE.
APPLICABILITY During MODE 5, withdrawn control rods must be OPERABLE to ensure that in a scram the control rods will insert and provide the required negative reactivity to maintain the l
reactor subcritical.
For MODES 1 and 2, control rod requirements are found in LCO 3.1.2, " Reactivity Anomalies," LC0 3.1.3, " Control Rod OPERABILITY," LCO 3.1.4, " Control Rod Scram Times," and LCO 3.1.5, " Control Rod Scram Accumulators." During MODES 3 and 4, control rods are not able to be withdrawn since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate requirements for control rod OPERABILITY during these conditions.
ACTIONS
&d With one or more withdrawn control rods inoperable, action must be immediately initiated to fully insert the inoperable control rod (s).
Inserting the control rod (s) ensures the shutdown and scram capabilities are not adversely affected.
Actions must continue until the inoperable control rod (s) is fully inserted.
SURVEILLANCE SR 3.9.5.1 and SR 3.9.5.2 REQUIREMENTS During MODE 5, the OPERA 8ILITY of control rods is primarily required to ensure a withdrawn control rod will automatically insert if a signal requiring a reactor shutdown occurs.
Because no explicit analysis exists for automatic shutdown during refueling, the shutdown function is satisfied if the withdrawn control rod is capable of automatic insertion and the associated CRD scram accumulator pressure is 2 940 psig.
l The 7 day Frequency takes into consideration equipment reliability, procedural controls over the scram accumulators, and control room alarms and indicating lights that indicate low accumulator. charge pressures.
(continued)
PBAPS UNIT 2 B 3.9-15 Amendment No. 211
g l
SDM Test--Refueling
~
B 3.10.8 BASES i
l SURVEILLANCE SR 3.10.8.6 i
REQUIREMENTS 1
(continued)
CRD charging water header pressure verification is performed to ensure the motive force is available to scram the control rods in the event of a scram signal. Since the reactor is l
depressurized in MODE 5, there is insufficient reactor pressure to scram the control rods. Verification of charging water header pressure ensures that if a scram;were required, capability for rapid control rod insertion would exist. The minimum pressure of 940 psig is well below the l
expected pressure of approximately 1450 psig while still ensuring sufficient pressure for rapid control rod insertion. The 7 day Frequency has been shown to be acceptable through operating experience and takes into account indications availab' e in the control room.
REFERENCES 1.
NEDE-24011-P-A-US, General Electric Standard Application for Reactor Fuel, Supplement for United States, February 1991.
2.
Letter from T. Pickens (BWROG) to G.C. Lainas, NRC,
" Amendment 17 to General Electric Licensing Topical Report NEDE-240ll-P-A," August 15, 1986.
I PBAPS UNIT 2 B 3.10-36 Amendment flo. 211 i
. -m-
l c uru p
4 UNITED STATES i
s j
NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 200sM001 gs,...../
l PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 216 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by PECO Energy Company, et al. (the licensee) dated November 30, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-56 is hereby amended to read as follows:
A
. (2) Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.216, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and is to be implemented concurrently with Amendment 214, issued August 30, 1995.
FOR THE NUCLEAR REGULATORY COMISSION l
l Jo F. Stolz, Direct Pr ject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance:
January 11, 1996
A ATTACHMENT TO LICENSE AMENDMENT N0. 216 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Enanza Insert 3.1-16 3.1-16 3.1-17 3.1-17 3.9-8 3.9-8 3.10-23 3.10-23 83.1-31 B3.1-31 B3.1-32 B3.1-32 B3.1-33 B3.1-33 B3.9-14 B3.9-14 B3.9-15 83.9-15 B3.10-36 B3.10-36 m...
NF Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TINE B.
Two or more control B.1 Restore charging 20 minutes from rod scram accumulators water header pressure discovery of reactor steam done Condition B inoperable with to 2 940 psig.
1 concurrent with pressure 2 900 psig.
charging water header pressure
< 940 psig I
8til B.2.1
NOTE---------
Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.
Declare the I hour associated control rod scram time
" slow."
4 0.!!
B.2.2 Declare the I hour associated control rod inoperable.
(continued)
PBAPS UNIT 3 3.1-16 Amendment No UJ.
216
1 Control Rod Scran Accumulators 3.1.5 l
ACTIONS (continued) l l
CONDITION REQUIRED ACTION COMPLETION TINE i.
C.
One or more control C.1 Verify all control Immediately upon rod scram accumulators rods associated with discovery of inoperable rt *h inoperable charging water i
reactor steam done accumulators are header pressure pressure < 900 psig.
fully inserted.
< 940 psig -
l 8110 1
l C.2 Declare the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated control rod inoperable.
l' i
i i
D.
Required Action B.1 or D.1
NOTE---------
C.1 and associated Not applicable if all Completion Time not inoperable control met.
rod scram accumulators are associated with fully inserted control rods.
Place the reactor Immediately l
mode switch in the shutdown position, j
i SURVEILLANCE REQUIRENENTS SURVEILLANCE FREQUENCY.
SR 3.1.5.1 Verify each control rod scram accumulator 7 days pressure is it 940 psig.
{
Agpnt No.2N-PBAPS UNIT 3 3.1-17
q Control Rod OPERABILITY-Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY-Refueling LC0 3.9.5 Each withdrawn control rod shall be OPERA 8LE.
APPLICA8ILITY:
NODE 5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TINE A.
One or more withdrawn A.1 Initiate action to Ismediately control rods fully insert inoperable.
inoperable withdrawn control rods.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1
NOTE--------------------
Not required to be performed until 7 days after the control rod is withdrawn.
Insert each withdrawn control rod at least 7 days one notch.
SR 3.9.5.2 Verify each withdrawn control rod scram 7 days
[
accumulator pressure is 2 940 psig.
PBAPS UNIT 3 3.9-8 Amendment No. 214, 216
y 4
SDM Test-Refualing l
3.10.8 4
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.10.8.5 Verify ear.h withdrawn control rod does not Each time the go to the withdrawn overtravel position.
control rod is withdrawn to
" full out" j
position 8tEl 4
3 Prior to satisfying LCO 3.10.8.c requirement i
after work on 4
control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days 2 940 psig.
l l
PBAPS UNIT 3 3.10-23 Amendment No.21J.
216
Control Rod Scram Accumulators 8 3.1.5 i
BASES i
ACTIONS A.1 and A.2 (continued) control rod is declared inoperable (Required Action A.2) and LC0 3.1.3 is entered. This would result in requiring the affected control rod to be fully inserted and disarmed, thereby satisfying its intended function, in accordance with ACTIONS of LCO 3.1.3.
The allowed Completion Time of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is reasonable, based on the large number of control rods available to provide the scram function and the ability of the affected control rod to scram only with reactor pressure at high reactor 3
a pressures.
B.1. B.2.1. and B.2.2 With two or.more control rod scram accumulators inoperable and reactor steam done pressure ;t 900 psig, adequate pressure must be supplied to the charging water header.
With inadequate charging water pressure, all of the accumulators could become inoperable, resulting in a potentially severe degradation of the scram performance.
Therefore, within 20 minutes from discovery of charging water header pressure < 940 psig concurrent with Condition B, adequate charging water header pressure must be restored. The allowed Completion Time of 20 minutes is reasonable, to place a CRD pump into service to restore the charging water header pressure, if required. This Completion Time is based on the ability of the reactor pressure alone to fully insert all control rods.
The control rod may be declared " slow," since the control rod will still scram using only reactor pressure, but may not satisfy the times in Table 3.1.4-1.
Required Action B.2.1 is modified by a Note indicating that declaring the control rod " slow" only applies if the associated control scram time is within the limits of Table 3.1.4-1 during the last scram time test. Otherwise, the control rod would already be considered " slow" and the further degradation of scram performance with an inoperable accumulator could result in excessive scram times.
In this event, the associated control rod is declared inoperable (Required Action B.2.2) and LCO 3.1.3 entered. This would (continued)
PBAPS UNIT 3 8 3.1-31 Amendment No. 216
Control Rod Scran Accumulators B 3.1.5 BASES ACTIONS B.1. B.2.1. and B.2.2 (continued) result'in requiring the affected control rod to be fully inserted and disarmed, thereby satisfying its intended function in accordance with ACTIONS of LC0 3.1.3.
The allowed Completion Time of I hour is reasonable, based on the ability of only the reactor pressure to scram the control rods and the low probability of a DBA or transient occurring while the affected accumulators are, inoperable.
C.1 and C.2 With one or more control rod scram accumulators inoperable and the reactor steam done pressure < 900 psig, the pressure supplied to the charging water header must be adequate to ensure that accumulators remain charged. With the reactor steam dome pressure < 900 psig, the function of the accumulators in providing the scram force becomes much more important since the scram function could become severely degraded during a depressurization event or at low reactor pressures. Therefore, immediately upon discovery of charging water header pressure < 940 psig, concurrent with condition C, all control rods associated with inoperable accumulators must be verified to be fully inserted.
Withdrawn control rods with inoperable accumulators may fail to scram under these low pressure conditions. The associated control rods must also be declared inoperable within I hour. The allowed Completion Time of I hour is reasonable for Required Action C.2, considering the low probability of a DBA or transient occurring during the time that the accumulator is inoperable.
D.d The reactor mode switch must be immediately placed in the shutdown position if either Required Action and associated Completion Time associated with the loss of the CRD charging pump (Required Actions B.1 and C.1) cannot be met. This ensures that all insertable control rods are inserted and that the reactor is in a condition that does not require the (continued)
PBAPS UNIT 3 8 3.1-32 Amendment No. 216
Control Rod Scram Accumulators j
B 3.1.5 i.
s BASES
}
ACTIONS D.J (continued) j active function (i.e., scram) of the control rods. This Required Action is modified by a Note stating that the i
action is not applicable if all control rods associated with j
the inoperable scram accumulators are fully inserted, since j
the function of the control rods has been performed.
I I
SURVEILLANCE SR 3.1.5.1 l
REQUIREMENTS SR 3.1.5.1 requires that the accumulator pressure be checked i
every 7 days to ensure adequate accumulator pressure exists to provide sufficient scram force. The primary indicator of accumulator OPERABILITY is the accumulator 1ressure. A minimum accumulator pressure is specified, miow which the i
capability of the accumulator to perform its intended l
function becomes degraded and the accumulator is considered J
inoperable. The minimum accumulator pressure of 940 psig is
{
i
}
well below the expected pressure of approximately 1450 psig (Ref. 1). Declaring the accumulator inoperable when the minimum pressure is not maintained ensures that significant j
degradation in scram times does not occur.
The 7 day i
Frequency has been shown to be acceptable through operating i
j experience and takes into account indications available in the control room.
REFERENCES 1.
UFSAR, Section 3.4.5.3 and Figure 3.4.10.
j 2.
UFSAR, Appendix K,Section VI.
j 3.
UFSAR, Chapter 14.
i l
i i
)
l 1
l i
i PBAPS UNIT 3 B 3.1-33 Amendment No. 216 4
4
Control Rod OPERABILITY-Refueling 8 3.9.5 4
8 3.9 REFUELING OPERATIONS 8 3.9.5 Control Rod OPERABILITY-Refueling BASES BACKGROUND Control rods are components of the Control Rod Drive (CRD)
System, the primary reactivity control system for the reactor.
In conjunction with the Reactor Protection System, the CR0 System provides the means for the reliable control of reactivity changes during refueling operation.
In addition, the control rods provide the capability to maintain the reactor subcritical under all conditions and to limit the potential amount and rate of reactivity increase caused by a malfunction in the CRD System.
UFSAR design criteria require that one of the two required independent reactivity control systems be capable of holding the reactor core subcritical under cold conditions (Ref.1).
The CRD System is the system capable of maintaining the reactor suberitical in cold conditions.
APPLICA8LE Prevention and mitigation of prompt reactivity excursions SAFETY ANALYSES during refueling are provided by refueling interlocks (LCO 3.9.1 and LCO 3.9.2), the SOM (LC0 3.1.1, the intermediate range monitor neutron. flux scram)(LC0 3.3.1.1),
and the control rod block instrumentation (LCO 3.3.2.1).
The safety analyses for the control rod withdrawal error i
during refueling (Ref. 2) and the fuel assembly insertion error (Ref. 3) evaluate the consequences of control rod' withdrawal during refueling and also fuel assembly insertion with a control rod withdrawn. A prompt reactivity excursion during refueling could poi.entially result in fuel failure with subsequent release of radioactive material to the environment. Control rod scram provides protection should a prompt reactivity excursion occur.
Control rod OPERABILITY during refueling satisfies Criterion 3 of the NRC Policy Statement.
LCO Each withdrawn control rod must be OPERABLE. The withdrawn control rod is considered OPERABLE if the scram accumulator pressure is ;t 940 psig and the control rod is capable of (continued)
PBAPS UNIT 3 B 3.9-14 Amendment No. 216
Control Rod OPERABILITY-Refueling B 3.9.5 BASES LCO being automatically inserted upon receipt of a scram signal.
(continued)
Inserted control rods have already completed their reactivity control function, and therefore, are not required to be OPERA 8LE.
APPLICABILITY During MODE 5, withdrawn control rods must be OPERA 8LE to ensure that in a scram the control rods will insert and provide the required negative reactivity to maintain the reactor suberitical.
For MODES 1 and 2, control rod requirements are found in LCO 3.1.2, " Reactivity Anomalies," LCO 3.1.3, " Control Rod OPERABILITY," LCO 3.1.4, " Control Rod Scram Times," and LCO 3.1.5, " Control Rod Scram Accumulators." During MODES 3 and 4, control rods are not able to be withdrawn since the reactor mode switch is in shutdown and a control rod block is applied. This provides adequate requirements for control rod OPERABILITY during these conditions.
ACTIONS Ad With one or more withdrawn control rods inoperable, action must be immediately initiated to fully insert the inoperable control rod (s).
Inserting the control rod (s) ensures the shutdown and scram capabilities are not adversely affected.
Actions must continue until the inoperable control rod (s) is fully inserted.
SURVEILLANCE SR 3.9.5.1 and SR 3.9.5.2 REQUIREMENTS During MODE 5, the OPERABILITY of control rods is primarily required to ensure a withdrawn control rod will automatically insert if a signal requirinq a reactor shutdown occurs.
Because no explicit ana'ysis exists for automatic shutdown during refueling, the shutdown function is satisfied if the withdrawn control rod is capable of automatic insertion and the associated CRD scram accumulator pressure is 2 940 psig.
The 7 day Frequency takes into consideration equipment reliability, procedural controls over the scram accumulators, and control room alarms and indicating lights that indicate low accumulator charge pressures.
(continued) l PBAPS UNIT 3 B 3.9-15 Amendment No. 216 l
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SDM Test-Refueling B 3.10.8 BASES SURVEILLANCE SR 3.10.8.6 REQUIREMENTS (continued)
CRD charging water header pressure verification is perfomed to ensure the motive force is available to scram the control rods in the event of a scram signal. Since the reactor is depressurized in MODE 5, there is insufficient reactor pressure to scram the control rods. Verification of.
charging water header pressure ensures that if a scram were required, capability for rapid control rod insertion would i
exist. The minimum pressure of 940 psig is well below the expected pressure of approximately 1450 psig while still ensuring sufficient pressure for rapid control rod insertion. The 7 day Frequency has been shown to be acceptable through operating experience and takes into account indications available in the control room.
REFERENCES 1.
NEDE-24011-P-A-US, General Electric Standard Application for Reatb r Fuel, Supplement for United States, February 1991.
2.
Letter from T. Pickens (BWROG) to G.C. Lainas. NRC,
" Amendment 17 to General Electric Licensing Topical Report NEDE-24011-P-A," August 15, 1986.
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Amendment No. 216 PBAPS UNIT 3 8 3.10-36
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