ML20070T989
| ML20070T989 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/18/1983 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070T991 | List: |
| References | |
| NUDOCS 8302100097 | |
| Download: ML20070T989 (9) | |
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4 BALTIM0RE GAS AND ELECTRIC COMPANY DOCKE T NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR.
1.
The Nuclear Regulatory Commission (the Commis'sion) has found that:
A.
The. application for amendment by Baltimore Gas & Electric Company (the licensee) dated November 5,1982, as supple-mented November 17, 1982, 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 CFD. Chapter I; B~.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Co. mission; a
C.
There is reasonabTe assurance (1) that the activities authorized by this amendment can be conducted without 1 -
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 l
common -defense and security or to the health and safety of the public; and.
e E.
The. issuance of this amendment is in accordance w.ith 10 CFR Part 51 of the Commission's regulations and all applicable
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requirements have been satisfied.
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2.
According'y, the license is amended by cha'nges to the Technical Specifications as indiccted in the attachment to this license amendment, and paragraph E.C.2 of Facility Operr. ting License.
No. DPR-69 is hereby amended to read as follows:
2 Technical Spedifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, 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.
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FOR THE NUCLEAR REGULATCPi COMMISSION k
Gus C. Lainas, Assistant Director for Operating Reactors Divisi6n of Licensing At tachre n'_ :
Changes to the Technical Specifications _
' Date oof Issuance: January 18, 1982 t
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G ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318
. 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 contains vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain
.docur.ent completeness.
Paaes 3/4 7-5 3/4 7-5s 3/4 7-5b (deleted) 3/4'74 (overleaf to 3/4 7-5b)
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PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The No. 12 condensate storage tank (CST) shall bc OPERABLE with a minimum contained water volume of 150,000 gallons per unit.
AP.0LICABILITY: MODES 1, 2 and 3.
ACTION:
With the No.12 condensate storage tank inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the CST to OPERABLE status or be ir. HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or b.
Demonstrste the OPERABILITY of the No. 21 condensate storage tank as a backup supply to the auxiliary feedwater pumps and restore the No.12 condensate storage tank to OPERABLE status within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
o SURVEILLANCE REQUIREMENTS 4.7.1.3.1 The No.12 condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume is wit,hin its limits when the tank is the supply source for the auxiliary feedwater pumps.
I 4.7.1.3.2 The No. 21 condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the tank contains a minimum of 150,000 gallons of water and by verifying that the flow path for taking suction from this tank is OPERA 5LE with the manusi valves in this flow path.open whenever the No. 21 condensate storage tank is the supply source for the auxiliary feedwater pumps.
CALVERT CLIFFS,-UNIT 2 3/4 7-6 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 62 FACILITY OPERATING LICENSE N0. DPR-69 4
DOCKET NO. 50-318 Replace the following hages of the Appendix A *echnical Specifications; 2
with the enclosed pages as indicated..The revised pages are identified by Amendment number and contains vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain
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document-~ completeness.
Pages 3/4 7-5 3/4 7-5s 5/4. 7-5b' (deleted) 3/4'7-6 (overleaf to 3/4 7-Sb)
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o PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two auxiliary feedwater trains consisting of one steam driven and.one motor driven pump and associated flow paths capable of automatically initiating flow shall be OPERABLE.*
(An OPERABLE steam driven train shall consist of one pump aligned for automatic flow initiation and one pump aligned in standby.)**
APPLICABILITY: MODES 1, 2 and 3.
i ACTION:
a.
With one motor driven pump inoperable:
l' Restore the inoperable motor driven pump 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, b.
With one steam driven pump inoperable:
1.
Align the OPERABLE steam driven pump to automatic initiating 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 SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and 2.
Restore the inoperable steam driven pump to standby status (or auto-matic initiating status if the other steam driven pump is to be' e
placed in standby) within the next 30 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c.
Whenever a subsystem (consisting of one pump, piping, valves and l'.
controls in the direct flow path) required for operability is inoperable for the performance of periodic testing (e.g. manual discharge valve closed for pump Total Dynamic Head test) a dedicated operator will be stationed at the local station with direct communication to the Control Room. Upon completion of any testing, the subsystem required for operability will be returned to its proper status and verified in its proper status by an independent operator check.
d.
The requirements of Specification 3.0.4 are not applicable whenever any combination of two (motor or steam driven) pumps are aligned for automatic flow initiation.
For a period of up to 30 days following the e'ntering into Mode 2 from Cycle 5 startup, at power. levels not to exceed 55% of rated thermal power, the auxiliary feedwater system may be inoperable except with regard to the
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capability for manually. initiating and manually controlling flow to either
. steam generator with the two steam driven auxiliary feedwater trains.
- A standby pump shall be available for operation-but aligned so that auto-matic flow initiation is defeated upon AFAS actuation.
CALVERT CLIFFS - UNIT 2 3/4 7-5 Amendment No. 37, F3, 57, 62
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater flowpath shall b,e demonstrated OPERABLE:
a.
At least once per 31 days by:
l.
Verifying that each steam driven pump develops a Total Dynamic Head of > 2800 ft. on recirculation flow.
(If verification must be demonstrated during startup, surveillance testing shall be performed upon achieving an RCS temperature 3,300*F and-prior to entering MODE 1).
2.
Verifying that the motor driven pump develops a Total Dynamic Head of 3,3100 ft. on recirculation flow.
3.
Cycling each testable, remote operated valve that is not in -
its operating position through' at least one complete cycle.
4.
Verifying that each valve Qpanua-1, power operated or automat'ic) in the direct flow path is in its correct position. The AFW flow control valves may be verified by observing a 160 gpm setpoint on the flow indicator controller in Control Room.
l b.
Before entering MODE 3 after a COLD SHUTDOWN of at least 14 days by completing a flow test that verifies the flow path from the conden-l sate storage tank to the steam generators.
i c.
At least once per 18 months by verifying that each automatic valve in the flow path actuates to its correct position and each auxiliary feedwater pump automatically starts and delivers a modulated flow of l
160 gpm + 10 GPM to each flow leg upon receipt of each auxiliary feedwater actuation system (AFAS) test signal.
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o CALVERT CLIFFS - UNIT 2 3/4 7-Sa Amendment No. 49, 62'
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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam line code safety valves ensures.
that the secondary system pressure will be limited to within its design pressure of 1000 psig during the most severe anticipated system opera-tional transient..The maximum relieving capacity is associated with a turbine trip from 100% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink (i.e., ro steam bypass to the condenser).
The specified valve lift settings and relievingLcapacities are in accordance with the requirements of Section III of the ASME Boiler and.
Pressure Code,1971 Edition.
The total relieving capacity for all valves on all of the steam lines is 12.18 x 106 lbs/hr which is 108 percent of the total secondary steam flow of 11.23 x 106 lbs/hr at 100% RATED THERMAL POWER. A minimum of 2 OPERABLE safety valves per steam generator ensures that sufficient relieving capacity,is available for removing decay heat.
STARTUP and/or POWER OPERATION is allowable with safety valves-inoperable within the limitations of the ACTION requirements on the basisi 9
of the reduction 'in secondary system steam flow and THERMAL' POWER' required by the reduced reactor trip settings of the Power Level-High-channels.
The reactor trip setpoint reductions are derived on the follo' wing bases:
For two loop operation SP = (X) - (Y)(V) x 106.5 i
y For single loop operation (two reactor coolant pumps operating in the same loop)
SP = (X) - (Y)(U) x 46.8 where:
reduced reactor trip setpoint in. percent of RATED SR
=
THERMAL POWER maximum number of inoperable safe'ty valves per steam V
=
line s
CALVERT CLIFFS-UNIT 2 B 3/4 7-1 9
PLANT SYSTEMS BASES i
U maximum number of inoperable safety valves per
=
I operating steam line 106.5 =
Power Level-High Trip Setpoint for two loop operation 1
46.8 =
Power Level-High Trip Setpoint for single loop opera. tion with two reactor coolant pumps operating in the same loop X
Total ~ relieving capacity of all_ safety valves per
=
steam line in lbs/ hour Y
Maximum relieving capacity of any one~ safety valve
=
in 1bs/ hour 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the, auxiliary-feedwater system ensures that the Reactor l
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-Coolant System can be cooled down to less than 300 F from normal operating _
conditions in the event of a total loss of offsite power. A capacity of.400 gpm is sufficient to ensure that adequate feedwater. flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than u
0 300 F when the shutdown cooling system may be placed into operation.-
Flow control valves, installed in each leg supplying the_ steam generators,-
maintain a nominal flow setpoint of 160 gpm plus or minus 10 gpm for operator setting band. The nominal flow setpoint of 160 gpm incorporates _a total instru--
ment loop error band of plus 47 gpm (217'gpm total flow per leg) and minus 60 gpm (90 gpm total flow per leg).
In the spectrum of events analyzed in which automatic initiation of auxiliary 1 feedwater occurs the nominal setting of 160 gpm allows a minimum of 10 ~ minutes before operator action is required. At 10 minutes after automatic initiation of flow the operator is assumed to be available to increase or decrease auxiliary feedwater flow to that required for existing-plant conditions.
CALVE J CLIFFS - UNIT 2 B 3/4 7-2 Amendment No. 47,4 7, 62e c,
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