ML20041G526
| ML20041G526 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/09/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8203220467 | |
| Download: ML20041G526 (12) | |
Text
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MAR 0 1982 Docket FileV NRC PDR Docket Nos. 50-295 Local PDR g
50-304 ORB #1 Rdg O
D. Eisenhut 9
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Mr. Louis 0. De1 George DWigginton g
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Director of Nuclear Licensing C. Parrish Commonwealth Edison Company JKohler, RI h
Post Office Box 767 es, RIII g
Dear Mr. DelGeorge:
The Zion Station Unit Nos.1 and 2 Technical Specifications on auxiliary feedwater pumps and flow paths have been under review for some time. He have had a number of discussions with your staff on the appropriate actions to be taken and the allowable out of service times before taking these actions. The enclosed draft Technical Specifications are proposed for the Zion Station. They were developed specifically for the Zion Station and after our review of infonaation from the Zion Probabilistic Safety Study.
It is requested that Commonwealth Edison Company review these proposed Technical Specifications and provide your comments and revisions to this office within 30 days of receipt of this letter. If you have any questions, please let us know.
Sincerely, Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing cc: See next page t
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Mr. Louis 0. De1 George Commonwealth Edison Company cc: Robert J. Vollen, Esquire 109 North Dearborn Street Chicago, Illinois 60602 Dr. Cecil Lue-Hing Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611 Zion-Benton Public Library District 2600 Emmaus Avenue Zion, Illinois 60099 Mr. Phillip P. Steptoe
!shan, Lincoln and Beale Counselors at Law One First National Plaza 42nd Floo-Chicago, Illinois 60603 Susan N. Sekuler, Esquire Assistant Attorney General Environmental Control Division 188 West Randolph Street, Suite 2315 Chicago, Illinois 60601 U. S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shiloh Blvd.
Zion, Illinois 60099 James P. Keppler Regional Administrator - Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Street Glen Ellyn, Illinois 60137
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O LIMITINd CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.7 STEAM GENERATOR EMERGENCY IIEAT REMOVAL 4.7 STEAM GENERATOR EMERGENCY llEAT REMOVAL Applicability:
Applicability:
Applies to auxiliary feedwater pump system, Applies to surveillance of auxiliary auxiliary feedwater supply system, and steam feedwater pump system, auxiliary feedwater generator safety valves.
supply system and steam caerator safety valves.
Objective:
Objective:
i To insu"e adequate plant cooldown capabili-To insure availability of the above system r
ties upon loss *of normal feedwater flow and and valves.
loss of main condenser vacuum.
Specification:
Specification:
1.
Steam Line Safety and Relief Valves, 1.
Steam Line Safety an'd Relief Valves l
per unit
- l per unit.
A.
Twenty ASMC code safety valves A.
Ten steam generator safety valves (5 per steam generator) shall be per unit shall be tested for set operable whenever the reactor is pressure at each refueling ontage.
Testing shall be done by a calibrated heated above 350 Or except as
'specified in 3.7.1.C, 3.7.1.D, auxiliary lifting device or b'y bench and 3.7.1.E testing on compressed gas. 'At least i two of the valves tested shall be from each orifice size
("Q" or "R").
All
. valves on a unit shall have been tested at the end of each second re-i fueling outage.
The valves and the corresponding set pressures and orifice sizes are identified in Table 4.7-1.
B.
Deleted B.
Deleted I
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SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION 3.7.1 E.
When the reactor is operating on 3 loops, 4.7.1 E. Not applicable-at least two code safety valves associated wtih the remaining steam generator must be OPERABLE.
F.
Not applicable.
F.
If these co,nditions cannot be met, the reactor shall be brought to the HOT SHUTDOWN condition within four hours.
After a maxinnmi of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> in the HOT SHUTDOWN condition, if the system is. not OPERABLE, the reactor shall be brought to the COLD SHUTDOWN condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Auxiliary Feedwater Pump System, per unit 2.
Auxiliary Feedwater Pump System, per unit A.
Three independent steam generator A.
Each feedwater pump shall be demonstrated OPERABLE:
auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:
1.
At least once per month by:
1.
Two motor-driven auxiliary feedwater a.
Verifying the pump starts pumps, each capable of being powered from separate emergency busses, and upon actuation from the control room, operates j
for at least ten minutes 2.
One steam turbine-driven auxiliary feedwtaer pump capable for being on recircul'ation flow,-
powered from an OPERABLE steam
.and the di,scharge pressure
'and flow are within + 10%
supply system.
of a point on the puip head APPLICABILITY:
Modes 1, 2, an'd 3
- curve, and b.
Verifying the pump provides at least 105 gpm flow to each steam generator.
G 158
lit 1ITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.7.2 4.7.2.A.2 ACTION:
a.
With one motor-driven auxiliary feedwater The surveillance and testing.6f the turbine pump inoperable, restore the pump to driven auxiliary feedwater pump as specified OPERABLE status within seven days, or be in 4.7.2. A.1 need only be performed whenever in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
the reactor is in modes 1 or 2.
Whenever the reactor is taken from mode 3 into mode 2 b.
With two motor-driven auxiliary feedwater without the required surveillance and testing pumps inoperable, restore at least one have been performed within the required 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 so _illance period, the surveillance and be in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
.4 ting shall be performed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering mode 2 or within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after With a turbine-driven auxiliary feedwater completing low power physics tests after a c.
pump inoperable, and the conditions of refueling outage.
3.7.2 action step (d) not met, restore the turbine-driven auxiliary feedwater 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 Mode within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The discharge flow paths of the motor-driven auxiliary feedwater pumps shall be realigned to provide two OPERABLE flow paths to the steam generators within the initial 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
)
d.
With a turbine driven auxiliary feed-water pump inoperable and the following conditions met or in effect:
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- repairs are begun immediately and every reasonable effort is made to continue the repairs uninterrupted,.
- the two motor driven auxiliary feedwater pumps and all their required i
and emergency power supplies OPERABLE,
- it has been determine ~d that the repairs can be made within 7 days, then l
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1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.7.2 4.7.2 restore the turbine driven auxiliary feed-water pump to OPERABLE status within 7 days or be in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The discharge flow paths of the motor driven auxiliary feedwater pumps shall be realigned to provide two OPERABLE flow paths to the steam generator within the initial 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- e. With a turbine-driven auxiliary feedwater pump and one motor-driven auxiliary feedwater pump inoperable, restore one pump to operabic status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- f. With three auxiliary feedwater pumps inoperable, make every effort to restore.
at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
- g. With either auxiliary feedwater pump discharge flow paths inoperable, restore j
the flow path 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 Mode 4 within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- h. With both auxiliary feedwater pump discharge flow paths inoperable, make every effort to restore at least one flow path to OPERABLE status as soon as possible.
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIRD(L RT 3.7.3 Auxiliary feedwater supply system 4.7.3 Auxiliary feedwater supply system (Table 4.7-3)
A.
The condensate st orage tank (s) shall be operable with a minimum contained A.
Surveillance and testing of the volume of 170,000 gallons of water auxiliary feedwater supply system shall lined up to each unit with its be'as follows:
reactor above 350 OF, except as specified in 3.7.3.B and 3.7.3.C.
~
1)
The contained water volume shall bei verified to be within its limits at least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2)
The manual valves for the lined-up tank (s) for*cach unit shall be verified locked open each month.
B.
From and after the time that the B.
When the service water system'is the conditions in 3.7.3.A cannot be required supply system, the system met, continued reactor operation is per' shall be demonstrated operable at least" missib,le provided that at least one o.f daily by stroking the power-operated the t'ro following criteria are met:
service water. supply valves to at least two operable auxiliary feedwater pumps 1)
Within the next four hours the from the control room.
Performance will conditions of 3.7.3.A are restored, be acceptable if valve motion l's or indicated upon actuation.
2)
Within the next four hours the operability of the service water system as a backup supply to the l
auxiliary feedwater pumps is demonstrated, and that the conden-sate storage tank's (s ) are restored-to operable status within the next 7 days.
C.
If thc conditions in 3.7.3.A.and C.
- iot applicable 3.7.3.9 cannot be met the reactor (s) shall be brought to hot shutdown and below 350 Or within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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Component',Name Component Number FWOO4 Auxiliary Feedwater Pump-1A (2A)
(turbine driven) i Auxiliary Feedwater Pump-1B (2B)
FW005 (motor driven) l Auxiliary Feedwater Pump-lC (2C)
FWOO6 1;
(motor driven) i t
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. Auxiliary Feedwater Pump System i
TABLE 4.7-2 1
161
r Component Nanee "omponent Numbar condensate Storage Tank SC001 Auxiliary Feedwater Pump -1A (2A)
MOV.SWO102 service water supply valve Auxiliary Feedwater Pump -1B (2B)
. service water supply valve Auxilia;y Feedwater Pump - 1B (2B)
MOV -SW O 10 4 service water supply valve Auxiliary Feedwater Pump - IC (2C)
MOV-SWO103 service water supply valve Auxiliary Feedwater Pump - IC (2C)
MOVv SW O 105 service water supply valve
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Auxiliary Feedwater Supply System TABLE 4.7-3 161a
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Bases:
3.7 The twenty code steam safety valves During 3 loop operation, at least two safety per unit have a total combined capa-valves are retained in service for any.unlikely city to relieve the total steam pressurization on the non-operating steam flow of one unit.
These valves generator, assure code overpressure protection is provided (1).
In the event Although not required for safe operation of the that one or more of the safety valves unit, the four atmospheric steam relief valves are inoperable, the loop steam flows per unit, provide additional decay heat removal are restricted to the maximum re-capability.
These valves, which are air or lieving capacity of the most restric-electric motor operated, are also manual'ly tive, operating loop.
This is controllable from the control room, and are accomplished by reduction of the installed to prevent unnecessary operation of Power Range Neutron Flux High Set-the steam generator safety valves.
(1) point Trip such that reactor power is limited to be less than the thermal The auxiliary feedwater pump systems provide a power required to produce steam flow very reliabic source of flow to the steam gener-in excess of the relieving capacity ators for decay heat removal.
Either the steam The of the most restrictive loop.,
driven auxiliary feedwater pump or one of the reactor trip setpoints are derived two motor driven auxiliary feedwater pumps can on the following basis:
supply the required flow of a unit.
(2)
Por 4 loop operation:
Suction to the auxiliary feedwater pumps is TSVC-ISVC SP =
x 109%
provided by the condensate storage tank or, TSVC as a backup, the service water system.
A minimum of 170,000 gallons are required to Por 3 loop operation:
provide fdr 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at hot standby followed TSVC-ISVC by 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cooldown at 50'r per hour with SP =
x 75%
steam discha'ge to the atmosphere concurrent r
.TSVC with total loss of offsite power.
(3)
This is sufficient to reduce the reactor coolant where:
system temperature to below 350'r when the Residual Heat Removal System may be placed SP = Reactor Trip setpoint P"'"'I TSVC = Total safety valve relieving capacity per steam generator ISVC= Inoperable safety valve (1)
PSAR, Section 10.3 relieving capacity per steam generator.
(2)
PSAR, Section 14.1.9 (3)
PSAR, Section 6.7.2 162 l
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P.anually operated valves are av'allable which will allow the condensate storage t'anks to be cross connected.
Therefore, water for the auxiliary feedwater pumps may be supplied from either tank.
Ilowever, when operated in a cross-connected mode, the supply lines will be lined up such that the minimum of 170,000 gallons of water will be drawn upon immediately without additional actions.
When a condensate st'orage tank is shared O
by both units operating above 350 F,
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minimum volume of 340,000 gallons shall be ava,ilable.
In 3.7.2, item d, the 7 day outage time for the turbine driven auxiliary feedwater pump is to allow time to mpair in place the most limiting part or component. The term "every reasonable effort" means that repairs are to begin immediately and are to continue uninterrupted until the turbine driven auxiliary feedater pump is declared operable or the unit is shutdown according to Section 3.7.2.d.
Time is pennitted in;this definition to obtain parts on an expedited basis.
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11ases :
4.7 The testing.of at least two safety -
valves of each orifice size assures that representative sample of valves is a
tested at each refueling.
The testing interval assures the availability of the safety valves and of the auxiliary feedwater pump system.
The four hour delay in the surveillance and testing of the turbine driven auxiliary feed-water pump until the reactor has reached the hot stpndby condition is to prevent unnecessary cooldown of the reactor coolant system during periods when the reactor is not available as a heat source.
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