ML20035E851
| ML20035E851 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/07/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035E845 | List: |
| References | |
| NUDOCS 9304190325 | |
| Download: ML20035E851 (15) | |
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UNITED STATES
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j NUCLEAR REGULATORY COMMISSION P
'8 WASHINGTON. D.C. 205564001 l
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f COMMONWEALTH EDISON COMPANY l
l DOCKET NO. 50-295 ZION NUCLEAR POWER STATION. UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE j
l Amendment No. 144 License No. DPR-39 j
1.
The Nuclear Regulatory Commission (the Commission) has found that:
)
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 5, 1992, 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 j
10 CFR Chapter I; j
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 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-39 is hereby amended to read as follows:
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9304190325 930407 PDR ADOCK 05000295 P
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 144
, are hereby incorporated in the license. The licensee shall operate the facility in J
accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$f40L $.
$Y ames E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation 1
Attachmet Changes to the Technical Specifications Date of Issuance: April 7, 1993
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UNITED STATES w
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[.. TT1, j NUCLEAR REGULATORY COMMISSION 7
WASHINGTON. D.C. 20566-0001-
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,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated November 5, 1992, 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 l
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 i
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 j
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-48 is hereby amended to read as follows:
i i
--- -- -...--- - I
. (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 133, are hereby incorporated in the licuse. 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 and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$4KSC {
(A James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 7, 1993 l
l l
ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT N0.144 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO.133 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 151 151 165 165 169a 169a 172 172 176 176 179 179 193 193 194 194 265 265 267 267
o LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6.1 4.6.1.A 2.
The containment spray power operated valves shall be tested pursuant to Specification 4.0.5.
3.
The spray nozzles shall be checked for proper functioning at least every five years.
B.
The three containment spray systems B.
Not Appilcable, shall be operable for pressure reduction and two of three systems for lodine removal whenever the reactor is in hot standby or operating except as specified in 3.6.1C.
C.
From and after the time that one of the C.
Not Appilcable.
three containment spray systems for pressure reduction or two of the three systems for lodine removal are made or found to be inoperable for any reason, reactor operation including recovery from an inadvertent trip is permissible only during the succeeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided that during those 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 1) for pressure reduction the remaining containment spray systems shall be operable and four fan coolers are operable, or 2) for lodine removal the remaining containment spray systems are D.
Not Appilcable, operable.
D.
If these conditions cannot be met, the reactor shall be brought to the 151 Amendment Nos. 144 and 133
~
LIMITING COM0! TION FOR OPERATION SURVEILLANCE REQUIREMENT 3.8.1 4.8.1.A 2.
The centrifugal charging pump system power operated valves shall be tested pursuant to Specification 4.0.5.
B.
Not Applicable.
B.
The two centrifugal charging pump systems shall be operable whenever the reactor is in C.
Not Appilcable.
hot standby or operating except as specified in 3.8.1.C.
C.
From and after the date that one of the two centrifugal charging pump systems is made or found to be inoperable for any reason, reactor operation including recovery from an inadvertent trip is permissible only during the succeeding 7 days provided that during D.
Not Appilcable.
those 7 days the remaining centrifugal charging pump system is operable and both residual heat removal pump systems and both safety injection pump systems are operable.
D.
If these conditions cannot be met the reactor shall be brought to the hot shutdown condition within four hours. After a maximum 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 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
t 1
165 Amendment Nos. 144 and ill
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.8.2 4.8.2.A.4 (Continued)
Valves A0V-SI8870A, A0V-SI88708 and A0V-SI8883 shall be failed in the closed position and have their air supply I
vertfled once per 31 days. Once per 18 months, these valves shall be verlfled to be in their required position.
The
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requirements are appilcable until these valves have been permanently disabled or removed. On completion of modification H22-1-88-21, work package 00132, for Unit 1; and M22-2-88-21, work package 00134, i
for Unit 2; valves A0V-SI8870A and A0V-SI88708 shall be restored to OPERABILITY.
B.
The two safety injection pump systems shall B.
Not Applicable, be operable whenever the reactor is in hot standby or operating except as specified in 3.8.2.C.
C.
From and after the date that one of the two C.
Not Appilcable.
safety injection pumps is made or found to be Inoperable for any reason, reactor operation including recovery from an in:dvertent trip is permissible only during the succeeding 7 days provided that during those 7 days the remaining safety injection pump system and both centrifugal charging pump systems and both residual heat removal pump systems are operable.
~l69a Amendment Nos.144 and 133
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l
3.8.3 4.8.3.A 6.
The containment ' Recirculation Sump to RHR Pump Suction Valves' shall be stroked 1
at a containment pressure of 20 psig following each containment leakage rate test to insure operability (MOV-SI8811A, MOV-S!88118).
t 7.
Valves MOV-RH8703, MOV-SI8809A, MOV-l SI88098, MOV-SI8812A and MOV-SI88128 i
shall be placed in the open position and valve MOV-RH9000 shall be placed in the closed position.
Power shall be removed at the respective motor control centers.
1 Once per 31 days, the breakers for these valves shall be verlfled off.
Power may be restored for plant testing, plant evolutions requiring operation of these valves, or in Modes 5 or 6.
Valves i
MOV-RH8703, MOV-SI8812A and H0V-SI88128 shall be stroke tested only during REFUELING OUTAGE.
B.
The two residual heat removal pump systems B.
Not Applicable.
shall be operable whenever the reactor is in hot standby or operating except as specified in 3.8.3.C.
C.
From and after the date that one of the two C.
Not Appilcable.
residual heat removal pump systcms is made or found to be Inoperable for any reason, reactor operation including recovery from an l
l Inadvertent trip is permissible only during i
the succeeding 7 days provided that during
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those 7 days the remaining residual heat removal pump system is operable and both centrifugal charging pump systems and both l
safety injection pump systems are operable.
172 Amendment Nos.144 and 133
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.8.6 8.
Except as specified in Sections 3.8.6C 4.8.6 B.
Not Appilcable.
and 3.8.6D the following numbers of components cooling water pumps and heat exchangers-shall be operable when the reactors are in hot standby or operating:
1.
One unit:
3 pumps and 2 heat exchangers 3
2.
Two units:
4 pumps and 3 heat exchangers C.
From and after the date that two of the C.
Not Appilcable.
component cooling water pumps are found or made Inoperable during 2 unit operation, reactor operation on one unit may proceed indefinitely. Reactor operation is limited to 7 days on the other unit provided that, during those 7.
days, the remaining three pumps and the three heat exchangers are operable.
D.
From and after the date that two of the D.
Not Applicable.
component cooling water pumps and one of the heat exchangers are found or made Inoperable during 2 unit operation, i
reactor operation on one unit may l
proceed indefinitely.
Reactor operation i
is limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on the other unit provided that, during those 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
the remaining three pumps and the I
remaining 2 heat exchangers are operabic.
I 176 Amendment Nos.144 and 133
LIMITING CON 0! TION FOR OPERATION SURVEll. LANCE REQUIREMENT 8.
Three service water pumps
- per unit shall be 4.8.7 B.
Not Appilcable.
' operable whenever the reactor is in hot standby or operating except as specified in 3.8.7.C C.
From and after the date that one of the C.
Not Appilcable.
three service water pumps
- per unit is made or found to be Inoperable for any reason, reactor operation is permissible only during the succeeding 7 days provided that the two remaining service water pumps are operable.
D.
If these conditions cannot be met the D.
Not Appilcable.
reactor shall be brought to the hot shutdown condition within four hours. After a maximum 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 />.
Hith the 48-inch service water discharge headers in the cross-tied mode, one operable service-2 water pump from the other unit with independent standby AC and DC power supplies may be used to fulfill-.the operating requirements of 3.8.7.A, 3.8.7.8, and:3.8.7.C. for both Units 1 and 2.
Only one of the six service water pumps may be used to fulfill the operability requirements for both Units I and 2.
1 J
179 Amendment Mos. 144 and 133 4
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3.8 The normal procedure for starting a reactor is to condition to provide for reduction of the decay heat the reactor coolant to near operating heat from the fuel, and consequent reduction of temperature by running the reactor coolant pumps.
cooling requirements after a postulated A reactor is then made critical by wtthdrawing loss-of-coolant accident.
This will also permit control rods and/or diluting boron in the Improved access for repairs in some cases. After a coolant.(1) Hith this mode of startup, the energy limited time in hot shutdown condition, if the stored in the reactor coolant during the approach malfunction (s) are not corrected, the reactor will to criticality is substantially equal to that be placed in the cold shutdown condition, utilizing during power operation, and therefore the minimum normal shutdown and cooldown procedures.
In the required engineered safeguards and auxillary cold shutdown condition there is no possibility of cooling system are required to be operable, an accident that would release fission products or During low temperature physics tests there is a damage the fuel elements, negIlgible amount of stored energy in the reactor coolant; therefore, an accident comparable in The plant operating procedures require 1 mediate severity to the Design Basis Accident is not action to effect repairs of an Inoperable possible, and the engineered safeguards systems component, and therefore in most cases repairs will are not required.
be completed in less than the specifled allowable repair times.
Furthermore, the specified repair The operable status of the various systems and times do not apply to regularly scheduled components is to be demonstrated by periodic tests maintenance of the engineered safeguards systems, as specified. A large fraction of these tests which is normally to be performed during refueling will be performed while a reactor is operating in shutdowns. The limiting times to repair and test the power range.
If a component is found to be Intervals are based on two considerations:
Inoperable, it will be possible in most cases to e'fect repairs and restore the system to full 1)
Assuring with high reliability that the operability within a relatively short time.
For a safeguard system will function properly if single component to be Inoperable does not negate required to do so.
the ability of the system to perform its function, (2) but it reduces the redundancy provided in a 2)
Allowances of sufficients time to effect reactor design and thereby limits the ability to repairs using safe and proper procedures, tolerate additional equipment failures.
If it develops that the specification cannot be met, the A repair period of 7 days has been developed based reactor will Initially be put in the hot shutdown upon the above considerations and based upon a l
degree of functional redundancy between systems over the range of break sizes (3). Testing of the alternate train when one train has become inoperable is not required provided periodic surveillance testing of the alternate train is current and there is no reason to suggest the alternate train is inoperable.
193 Amandment Nos. 144 and 133
1 Base d R_and 4.8_(Continued 1 1
Assuming a reactor has been OPERATING at full ated The pressure and volume limits for the accumulators i
power for at least 100 days, the magnitude of the decay assure that the required amount of water is injected 3
heat decreases after Initiating MODE 3.
Thus, the with the required boric acid concentration following a requirement for core cooling in case of a postulated loss-of-coolant accident.
The limits are based on the loss-of-coolant accident while in the MODE 3 condition values used for the accident analyses.
(4) is significantly reduced below the requirements for a postulated loss-of-coolant accident during P0HER The RMST supplies borated water to the Emergency Core OPERATION.
Putting a reactor in the MODE 3 condition Cooling System (ECCS) during the injection phase.
In significantly reduces the potential consequences of a the recirculation phase of operation, the two Residual i
loss-of-coolant accident, and also allows more free Heat Removal (RHR) pumps are realigned to take suction access to some of the engineered safeguards components from the containment recirculation sump.
The RHR pumps i
in order to effect repairs, may then be aligned to supply recirculation water to the Containment Spray Recirculation Phase Systems, and to j
Failure to complete repairs within the allowable time the Safety Injection (SI) pumps and Centrifugal Charging 4
after going to the MODE 3 condition is considered pumps for cold leg recirculation.
Later in the Indicative of a requirement for major maintenance and accident, ECCS flow from the RHR and SI pumps may be i
therefore in such a case, the reactor in general is to realigned to hot leg recirculation.
These evolutions be put into the MODE 5 condition, are done in accordance with Emergency Operating Procedures.
(8) l The limits for the accumulators and Refueling Water l
Storage Tank (RNST), insure the required amount of The five component cooling system pumps and three heat water with the required boron concentration is exchangers are located in the Auxiliary Building and are available for injection into the primary coolant system a shared system between Units I and 2.
The components t
following a loss-of-coolant accident and are based on are accessible for repair af ter a loss-of-coolant values used for the accident analysis (4).
accident.
During the recirculatlon phase following a loss-of-coolant accident on a unit, only one component cooling pump and heat exchanger is required for alntmum safeguards of that unit.
Therefore, a minimum requirement of four component cooling pumps and three heat exchangers for two OPERATING units provides i
sufficient redundancy.
(5)
A total of six service water pumps are installed, only i
one service water pump is required immediately following a postulated loss-of-coolant accident.
(6) (See p. 195) 1 i
)
i l
194 Amendment Nos. 144 and 133
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT 3.15.2.8 4.15.2.B.
If off-site power cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching the hot shutdown condttion, the reactor of that untt shall be placed in the cold shutdown condition.
i C.
From and after the date that one of the C.
When one diesel generator is diesel generators for a unit (IA, IB or inoperable, the other two diesel 0 for Unit 1 - 2A, 28 or 0 for Unit 2) generators shall be demonstrated to is made or found inoperable reactor be operable by conducting the l
operation on that unit is permissible testing specified in Section i
only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- 4.15.1.B.2 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The provided that the two remaining diesel availability of the two sources of 4
generators are operable and the two off-site power shall be demonstrated sources of off-site power in Sections by performing Surveillance 3.15.1.A and 3.15.1.C are available.
Requirement 4.15.1.A within I hour The ava11ab111ty of two sources of and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off-site power shall be demonstrated thereafter.
within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
The operability of the two remaining diesels shall be demonstrated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
From and after the date that one of the D.
Not Applicable.
Engineered Safeguards 4160-volt buses of t
i a unit (147, 148 or 149 for Unit 1 -
l 247, 248, or 249 for Unit 2) is made or i
found to be Inoperable for any reason, the reactor of that unit will be placed in the hot shutdown condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
i The reactor may be maintained in this condition for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, provided the major components listed in Table 3.15-1 are operable.
If 1
LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.15.2 G.
From and after the date that one 4.15.2.
G.
Not Appilcable.
instrument inverter of a unit (111, 112, 113 or 114 for Unit 1 - 211, 212, 213 i
and 214 for Unit 2) is not operable, i
reactor operation of that unit is permissible only during the succeeding 14 days.
If the inverter is not restored to service within the 14 days, or if a second Inverter becomes Inoperable, the reactor of the unit shall be brought to the cold shutdown condition.
3 l
H.
If more than one of the conditions specified in 3.15.2.A, 3.15.2.B.
3.15.2.C 3.15.2.D. 3.15.2.E, 3.15.2.F 5
and 3.15.2.G occur concurrently, the i
reactor of the affected unit shall be t
brought to the hot shutdown condition Imediately.
If a specified limiting condition for operation has not been restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor of that unit shall be placed in the cold l
shutdown condition.
l 3.
Diesel Fuel 3.
Diesel Fuel l
A.
There shall be a minimum of 40,000 A.
The quantity of diesel fuel j
gallons of diesel fuel in the storage available in the storage and tanks and 350 gallons in the day tanks day tanks shall be checked once 1
for each diesel.
a month or on a daily basis when the diesel generators are dsed.
i f
j 267 Amendment Mos. 144 and 133-E
.