ML20092J492
| ML20092J492 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley (NPF-073) |
| Issue date: | 09/18/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co |
| Shared Package | |
| ML20092J493 | List: |
| References | |
| NPF-73-A-076 NUDOCS 9509220168 | |
| Download: ML20092J492 (10) | |
Text
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c-44 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20eeH001
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DUOVESNE LIGHT COMPANY l
OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY DOCKET N0. 50-412 BEAVER VALLEY POWER STATION. UNIT Z AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.76 License No. NPF-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated July 24, 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 facilit.y will operate in conformity with the application, i
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 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.
9509220168 950918 PDR ADOCK 05000412 P
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2.
Accordingly, the-license is amended by changes to the Technical-Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-73 is hereby amended to read as follows:
(2)
Technical Snecifications l
The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 76, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated'in the license. DLC0 shall operate the 1
facility in accordance with the Technical Specifications and the 5
Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to 1
be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION 9$14 b i
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J
'F: Stolz, Director P ject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of Issuance: September 18, 1995 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 75 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert i
3/4 4-39 3/4 4-39 3/4 4-39a 3/4 4-39a B 3/4 4-16b B 3/4 4-16b B 3/4 4-16c B 3/4 4-16C B 3/4 4-16d B 3/4 4-16d B 3/4 4-16e B 3/4 4-16e B 3/4 4-16f B 3/4 4-16f r
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NPF-73 REACTOR COOLANT SYSTEM 3/4.4.11 RELIEF VALVES LIMITING CONDITION FOR OPERATION 7
3.4.11 Each Power-Operated Relief Valve (PORV) and associated l
block valve shall be OPERABLE.
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APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
- - - - - - - - - - - - - GENERAL NOTE - - - - - - - - - - - - - -
separate ACTION statement entry is allowed for each PORV and block valve.
a.
With one or more PORVs inoperable and capable of being manually
- cycled, within 1
hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the block valve (s);
otherwise, be in 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 /> and in 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 />.
b.
With one pr two PORV(s) inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the PORV(s) to OPERABLE status or close the associated block i
valves and remove power from the block valve (s);
a minimum of two PORVs are to be OPERABLE within the following 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 hours and in 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 />.
With one PORV inoperable and isolated, power operation may continue until the next refueling outage.
c.
With three PORVs inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and 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 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 />.
I d.
With one block valve inoperable and open, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore the block valve to OPERABLE status or place the associated PORV in manual control.
Restore the block valve to OPERABLE status within the following l
' BEAVER VALLEY - UNIT 2 3/4 4-39 Amendment No. 76
j NPF-73 REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued) i a
i ACTION:
(Continued) i 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 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 />.
With one block valve inoperable, restore the block valve to OPERABLE status within 1
hour or close it, power-operation may continue until the next refueling outage.
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With more than one block valve inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> e.
either restore the block valves to OPERABLE status or place the associated PORVs in manual control.
Restore at least one block valve to OPERABLE status within the
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next hour if three block valves are inoperable; restore a minimum of two block valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; otherwise, 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 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 />.
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i SURVEILLANCE REQUIREMENTS l
3 4.4.11.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by operating the PORV through one complete cycle of full travel.
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4.4.11.2 Each, block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed to meet required ACTIONS b or c.
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BEAVER VALLEY - UNIT 2 3/4 4-39a Amendment No. 76 i
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l NPF-73 REACTOR COOLANT SYSTEM l
BASES (Continued) i
)
3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES (Continued)
[
i APPLICABILITY (Continued) t i
PORV opening setpoint.
The most rapid increases will occur at the i
higher. operating power and pressure conditions of MODES 1 and 2.
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The PORVs are also required to be OPERABLE in MODES 1, 2, and 3 to l
minimize challenges to the pressurizer safety valves.
Pressure increases are less prominent in MODE 3 because the 4
l core input energy is reduced, but the RCS pressure is high.
Therefore, the LCO is applicable in MODES 1, 2, and 3.
The LCO is i
not applicable in MODE.4 when both' pressure and core energy are l
decreased and the pressure surges become much less significant.
i The PORV setpoint is reduced for OPPS in MODES 4 (below the enable temperature),
5, and 6 with the reactor vessel head in place.
LCO 3.4.9.3 addresses the PORV requirements in these MODES.
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ACTION i
A General Note provides clarification that all pressurizer l
PORVs and block valves are treated as separate entities, each with separate completion times (i.e.,
the completion time 'is on a j
component basis).
a.
With the hCRVs inoperable and capable of being manually i
cycled, either the PORVs must be restored or the flow path isolated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The block valves should be closed but power must be maintained to the associated block valves, since removal of power would render the i
block valve inoperable.
Although a
PORV may be j
designated inoperable, the associated vent path may be 4
manually opened and closed, and the PORV therefore, able l
to perform its function.
PORV inoperability may be due to seat leakage, instrumentation problems related to j
PORV accident monitoring instruments identified in LCO 1
3.3.3.8, or other causes that do not prevent manual use and do not create a possibility for a small break LOCA.
If the position indication is inoperable, then the PORVs i
are inoperable.
For these reasons, the block valve j
'shall be closed but the ACTION requires power be i
maintained to the valve.
Automatic control problems and j
related instrumentation problems would not render the PORVs inoperable.
Accident analyses assume manual d
operation of the PORVs and does not take credit for automatic actuation.
This condition is only intended to i
4 BEAVER VALLEY - UNIT 2 B 3/4 4-16b Amendment No. 76 I
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REACTOR COOLANT SYSTEM BASES (Continued) 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES (Continued)
ACTION (Continued) permit operation of the plant for a limited ' period of time not to exceed the next refueling outage (MODE 6) so that maintenance can be performed on the PORTS to eliminate the seat leakage condition.
Normally, the PORVs should be available for automatic mitigation of overpressure events and shc Id be returned to OPERABLE status prior to entering starcup (MODE 2).
Quick access to the PORV for pressure control can be made when power remains on the closed block valve.
The completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on plant operating experience that has shown that minor problems can be corrected or closure accomplished in this time period, b.
With one or two PORV(s) inoperable and not capable of being manually
- cycled, the PORV(s) must be either restored or isolated by closing the associated block valve and removing the power to the associated block valve.
The completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is reasonable, based on challenges to the PORVs during this time
- period, and provides the operator adequate time to correct the situation.
If the inoperable valve (s) cannot be' restored to OPERABLE status, the PORV(s) must be isolated within the specified time.
Because there is at least one PORV that remains OPERABLE, an additional
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72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is provided to restore a minimum of two PORVs to OPERABLE status.
If a minimum of two PORVs cannot be restored within this additional time, the plant must be i
brought to a MODE in which the LCO does not apply.
Two l
OPERABLE PORVs provide redundancy to allow continued operation until the next refueling outage to perform l
maintenance on the inoperable valve and return it to i
OPERABLE status, l
c.
If three PORVs are inoperable and not capable of being j'
manually cycled, it is necessary to either restore at least one valve within the completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or isolate the flow path by closing and removing the power to the associated block valves.
The completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is reasonable, based on the small potential for challenges to the system during this time and provides the operator time to correct the situation.
If one PORV is restored, then the plant will be in a less limiting 1
BEAVER VALLEY - UNIT 2 B 3/4 4-16c Amendment No. 76 J.
t NPF-73
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REACTOR COOLANT SYSTEM BASES (Continued) t 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES (Continued) i ACTION (Continued)
ACTION statement with the time clock started at the l
original declaration of having three PORVs inoperable.
l If no PORVs are restored within the completion time, i
then the plant must be brought to a MODE in which the i
LCO does not apply.
To achieve this status, the plant i
must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to a
MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed completion times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions i
i in an orderly manner and without challenging plant l
systems.
In MODES 4 and 5, maintaining PORV OPERABILITY i
may be required.
See LCO 3.4.9.3.
I d.
If one block valve is inoperable and open, then it is necessary to either restore the block valve to OPERABLE l
status within the completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or place the i
associated PORV in manual control.
The prime importance for the capability' to close the block valve is to i
4 isolate a stuck open PORV.
Therefore, if the block I
i valve cannot be restored to OPERABLE status within 1 i
hour, the required action is to place the PORV in manual i
control to preclude its automatic opening for an
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overpressdre event and to avoid the potential for a j
stuck open PORV at a time that the block valve is inoperable.
If the block valve is inoperable, it is necessary to restore the block valve to OPERABLE status i.
within 1
hour or close it.
If block valve instrumentation related to accident monitoring instrumentation identified in LCO 3.3.3.8 is determined to be inoperable, then the block valve shall be declared inoperable.
Closing the block valve precludes the need j
to place the PORV in manual control since it is isolated from the system.
The completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is i
reasonable, based on the small potential for challenges to the system during this time period, and provides the operator time to correct the situation.
Because at least one PORV remains
- OPERABLE, the operator is i
permitted a completion time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the inoperable open block valve to OPERABLE status.
If it l
cannot be restored within this additional time, the plant must be brought to a MODE in which the LCO does not apply in order to avoid continuous operation without r
a redundant ability to isolate this PORV flow path.
If 3
BEAVER VALLEY - UNIT 2 B 3/4 4-16d Amendment No.76 4
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i-i NPF.73 REACTOR COOLANT SYSTEM i
j' BASES (Continued) 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES (Continued) l
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ACTION (Continued) i i
the block valve is restored within the' completion time 1
of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the power will be restored and the PORV l
restored to OPERABLE status.
With one block valve inoperable a.nd closed, there still remains two PORV flow l
paths.
This redundancy will allow continued operation l
until the next refueling outage to perform maintenance on the inoperable valve and return it to OPERABLE j
status.
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e.
If more than one block valve is inoperable, it is
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necessary to either restore the block valves within the i
completion time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or place the associated PORVs in manual control and restore at least one block valve within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (and restore a minimum of two block l
valves within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />).
redundancy to allow continued operation until the next refueling outage to perform-maintenance on the
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inoperable valve and return it to OPERABLE status.
The completion times are reasonable, based on the small potential for challenges to the system during this time and provide the operator time to correct the situation.
i If the required actions are not met, then the plant must be brought to a MODE in which the LCO does not apply.
l To achieve this status, the plant must be brought to at j
least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within 12 i
i hours.
The allowed completion times are reasonable, l
based on operating experience, to reach the required.
plant conditions from full power conditions in an i
orderly manner and without challenging plant systems.
In MODES 4 and 5,
maintaining PORV OPERABILITY may be j
required.
See LCO 3.4.9.3.
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SURVEIt.rANCE REOUIREMENTS (SR) i SR 4.4.11.1 j
This surveillance requires a complete cycle of each PORV.
Operating a PORV through one complete cycle ensures that the PORV i
c'an be manually actuated for mitigation of an SGTR.
The frequency i
of 18 months is based on a typical refueling cycle and industry l
accepted practice.
i BEAVER VALLEY - UNIT 2 B 3/4 4-16e Amendment No.76 i
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.s BASES (Continued) i 3/4.4.11 REACTOR COOLANT SYSTEM RELIEF VALVES (Continued) j l
SURVEITLANCE REOUIREMENTS (SR) (Continued) f 1
I Block valve cycling verifies that the valve (s) can be closed if needed.
The basis for the frequency of 92 days is the ASME Code,Section XI.
If the block valve is closed to isolate a PORV that is capable of being manually cycled, the OPERABILITY of the l
block valve is of importance, because opening the block valve is necessary to permit the PORV to be used for manual control of reactor pressure.
If the block valves are closed to isolate inoperable PORVs, the maximum completion time to restore one PORV j
and open the block valve is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, which is well within the i
j allowable limits (25%) to extend the block valve frequency of 92 j
days.
Furthermore, these test requirements would'be completed by the reopening of a recently closed block valve upon restoration of l
the PORV to OPERABLE status (i.e.,
completion of the required i
actions fulfills the SR).
l This SR is not required to be met with the block valve l
closed, in accordance with required ACTIONS b or c of this LCO.
l 3/4.4.12 REACTOR COOLANT SYSTEM HEAD VENTS i
i Reactor Coolant System Vents are provided to exhaust i
l noncondensible gases and/or steam from the primary system that l
could-inhibit natural circulation core cooling.
The OPERABILITY i -
of at least one reactor coolant system vent path from the reactor vessel head or the pressurizer steam space via the PORV's ensures the capability exists to perform this function.
The valve redundancy of the Reactor Coolant System Head vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply or control system does not prevent i
isolation of the vent path.
l The function, capabilities, and testing requirements of the Reactor Coolant System vent systems are consistent with the requirements of Item II.B.1 of NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.
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BEAVER VALLEY - UNIT 2 B 3/4 4-16f Amendment No.76
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