ML20245C691
| ML20245C691 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/19/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245C696 | List: |
| References | |
| NUDOCS 8906260254 | |
| Download: ML20245C691 (15) | |
Text
_ _ _ _ _ _
g UNITED STATES g'
g NUCLEAR REGULATORY COMMISSION r,
j WASHING TON, 0. C. 20555 k...../
UR61NIAELECTRICANDPOWERCOMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated March 27,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; C.
The f acility will operate in conformity with the application,
~
the provisions of the Act, and the rules and regulations of the Comission; 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 corp 11ance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission'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 i
amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
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8906260234 890619 fDR ADOCK 05000280 3
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(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b.- -
Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation.
Attachnent:
Changes to the Technical Specifications Date of Issuance: June 19,1989 r
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&p uq.g UNITED STATES
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g NUCLEAR REGULATORY COMMISSION r,
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I VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDEENT TO FACILITY OPERATING LICENSE Amendment No.130 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated March 27, 1989, complies with the l
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (i) that the activities authorized I
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
Tne issuance of this amendment is in accordance with 10 CFR Part l
51 of the Comission's regulations and all applicable requirements j
have been satisfied.
1 I
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
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.i (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.130., are hereby incorporated in the license. The ifcensee.shall: _
J operate the facility in accordance with the Technical Specifications.
l 3.
This. license amendment is effective as of the date of its issuance.
']
FOR THE NUCLEAR REGULATORY COMHISSION h
erbert N. Berkow, Director.
Project. Directorate II-2 Division of Reactor Projects-1/II Office of Auclear: Reactor Regulation _
Attachment:
i Changes to the Technical Specifications Date of Issuance: June 19, 1989 i
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l ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. OPR-32 1
AMENDMENT NO.130 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND S0-281 Revise Appendix A as follows:
. i Removt Pages Insert Pages TS 3.7-9b TS 3.7-9b TS 3.7-16 TS 3..'-16 i
TS 3.7-19 TS 3.7-19 i
TS 3.14-1 TS 3.14-1 TS 3.14-2 TS 3.14-2 TS 3.14-3 TS 3.14-3 TS 3.14-4 TS 3.14 TS 4.1-8a TS 4.1-8a TS 4.1-8aa TS 4.1-8aa TS 4.1-9c TS 4.1-9c l
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control room.
1 The supply lines installed from the containment penetrations to the j
hydrogen analyzers have Category I Class IE heat tracing applied.
The heat tracing system receiees the same transferab'e emergency power as is provided to the containment hydrogen' analyzers. -The heat trace system'is j
de-energized during normal system operation.
Upon receipt of a safety j
injection signal (Train A or Train B), the system is. automatically started, after a preset time delay, to bring the piping process temperature to 250*F 10'F within 20 minutes.
Each heat trace circuit I
is equipped with an RTD to provide ' individual circuit readout,. over f
temperature alarm and cycles the circuit to maintain the process
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temperatures via the solid state control modules.
)
1 The hydrogen analyzer heat trace sy:. tem is equipped' with high temperature, loss of D.C.
power, loss of A.C.
power, loss of control
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power and failure of automatic initiation alarms.
Control Room Chlorine Detection System 1
I The operability of the chlorine detection systera ensures that sufficient' capability is available to promptly detect and automatically initiate protective action in the event of an accidental chlorine release.
This capability is required to protect control room personnel,. and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975.
Non-Essential Service Water Isolation System The operability of this functional system ensures that adequate intake canal inventory can be maintained by the emergency service water pumps.
Adequate intake canal inventory provides design service. water flow to the recirculation spray heat exchangers and other essential loads (e.g.,
control room area chillers, charging pump lube oil ' coolers) following a-t L
design basis loss of coolant accident with a coincident loss of offsite power..Thic system is common to both units in that each of" the two trains will actuate equipment on each unit.
Amendment Nos.130 and. 130
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TS 3.14-1 3.14 CIRCI:tATING AND SERVICE WATER SYSTEMS Acolicability Applies to the operational status of the Circulating and Service Water Systems.
Obiective To define 'those limiting conditions of the Circulating and Service Water Systems.necessary to assure safe station operation.
Specification A.
The Reactor Coolant System temperature or pressure'of a reactor unit shall not exceed 350'F or 450 psig, respectively,. or 'the reactor shall not be critical unless:
1.
The high level intake canal is filled to.at least elevation.+23.0 feet at the high-level intake structure.
2.
Unit subsystems, including piping and valves, shall be operable to the extent of being able to establish the.
following:
a.
Flow to and from one bearing cooling water.- heat exchanger.
b.
. Flow to and from the component' cooling heat exchangers required by Specification 3.13.
.~
Atleasttwocircul$tingwaterpumpsareoperatingorare 3.
4.
Three emergency service water pumps are operable; these pumps will service both units simultaneously.
l Amendment Nos. 130 and 130-
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TS 3.24-2 l
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5.
Two service water flowpaths to the charging pump service water subsystem are operable.
6.
Two service water flowpaths to the recirculation spray j
subsystems are operable.
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B.
The requirements of Specification 3.14.A.4 may be modified to l
allow one Emergency Service Water-pump.to remain inoperable for a period not to exceed 7 days.
If this pump is not operable in 7 ' days, then place both units-. in Hot Shutdown i
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 i
The requirements of 3.14. A.'4 may be modified to have two Emergency Service Water pumps operable with one unit in Cold Shutdown with combined Spent Fuel pit and shutdown unit ' decay heat loads of 25 million BTV/HR or less.
0ne of the two l
remaining pumps may be inoperable for a period not to exceed 7 days.
If this pump is not operable in 7 days, then place the operating unit in Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and Cold Shutdown within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
l l
C.
There shall be an operating service water flow path'to and from I one operating main control and emergency switchgear' rooms air j
conditioning condenser and at least one operable service water flow path to and from at least one operable main control and emergency switchgear rooms air conditioning condenser wheneyer!
fuel is loaded in reactor core.
Refer to Section 3.23.C for air conditioning system operability requirements above cold shutdown.
The requirements of Speci ications A-5 and A-6 may be modified l D.
to allow unit operation with only one operable flow path to the charging pump service water subsystem and to the rec.irculation spray subsystems.
If the affected systems are not restored to the requirements of Specifications A-5 and A-6 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 1
Amendment Nos. 130 and 130
TS 3.14-3 g..
~
the reactor shall be placed in a hot shutdown condition.
If the requirements of Specifications A-5 and A-6 ace not met within an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be placed in a cold shutdown condition.
Basis The Circulating'and Service Water Systam are designed for the removal of heat resulting from the operation of various systems and components' of either or both of the units.
Untreated water, supplied from the James River and stored in the high level intake canal is circulated by gravity through the recirculation spray coolers and the bearing -cooling water heat exchangers and to the charging pumps lubricating oil cooler service water pumps which supply service water to the charging pump lube oil coolers.
~
In addition, the Circulating and Service Water Systems supply cooling water to the component cooling water heat exchangers and to the main control and emergency switchgear rooms air conditioning condensers.
The Component Cooling heat exchangers are used during normal plant operations to cool various station components and when in shutdown to remove residual heat from the reactor. Component Cooling is not required on the accident unit during a loss-of-coolant accident.
If the loss-of-coolant accident is coincident with a loss of off-site power, the nonaccident unit will be maintained at Hot Shutdown with the ability to reach Cold Shutdown.
The long term Se vice Water requirement for a loss-of-coolant accident in j
one unit with simultaneous loss-of-station power and the second ' unit
'l being brought to Hot Shutdown is greater than 15,000 gpm.
Additional Service Water is necessary to b,rincf' the nonaccident unit to Cold snutdown.
Three diesel driven Emergency Service Water pumps with a design capacity of 15,000 gpm each, are provided to supply water to the High Level Intake canal during a loss-of-station power incident.
- Thus, l
considering the single active failure of.one pump, three Emergency Service Water pumps are required to be operable.
The allowed outage time of 7 days provides operational flexibility to allow for repairs up to and l
i Amendment Mos.130 and 130 9
j i
TS 3.14-4.
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including replacement of an Emergency Service Water pump without forcing dual unit outages, yet limits the amount of operating time without the i
specified number of pumps.
When one Unit is in Cold Shutdown and the heat load from the shutdown
)
unit and spent fuel pool drops to less than 25 million BTU /HR, then one Emergency Service Water pump may be removed from service for the
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subsequent time that the unit remains in Cold Shutdown due to the reduced I
residual heat removal and hence component cooling requirements.
. A minimum level of +17.2 feet in the High Level Intake canal is required to provide design flow of Service Water through the Recirculation Spray heat exchangers during a loss-of-coolant accident for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
}
If the water level falls below +23'6", signals are generated to trip both 1
unit's turbines and to close the nonessential Circulating ari Service I
Water valves.
A High Level ~ Intake canal level of
+23'6" ensures 1
actuation prior to canal level falling to elevation
+23'.
The Circulating Water and Service Water isolation valves which are required I
to close to conserve Intake Canal inventory are periodically verified to limit total leakage flow out of the Intake Canal.
In.-addition, passive vacuum breakers are installed on the Circulating Water pump discharge.
lines to assure that a reverse siphon is not continued for canal levels less than +23 feet when Circulating Water pumps are de-energized.
The remaining six feet of canal level is provided coincident with ESW pump operation as the required source of Service Water for heat loads following the Design Basis Accident.
References:
FSAR Section 9.9 Service Water System FSAR Section 10.3.4 Circulating' Water System FSAR Section 14.5 Loss-of-Coolant Accidents, Including the l
Design Basis Accident 1
Amendment Nos. 130 and 130
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