ML20096D316
| ML20096D316 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/28/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20096D319 | List: |
| References | |
| DPR-59-A-083 NUDOCS 8409060023 | |
| Download: ML20096D316 (16) | |
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6 UNITED STAIES.
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s'. g _ n.e j POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET N0. 50-333 JAMES A.' FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. DPR-59 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State of New York (the licensee) dated February 20, 1981, 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; B.
The facility will-operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be-conducted without endangering the health l
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 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 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 amendment and paragraph 2.C(2) of Facility Operating License No.
DPR-59 is hereby amended to read as follows:
8409060023 840828 PDR ADOCK 05000333 P
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. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through-Amendment No. 83, 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 C0FNISSION
.?,':w, l
.c Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 28, 1984
ATTACHMENT TO LICEP!SE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise the Technical Specifications by removing and inserting the
' following pages:
Remove Insert 3
3-
.4 4
30 30 30a 30b 30c 30d 30e 30f 181 181 218 218 219 219 220 220 4
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- +
m
i JRFNPP 1.0 (cont'd) will be started and valves 11.
Sensor,- A sensor is that part-operated.
.of a channel used to detect variations-in a monitored'variabl'e 7.
Protective Action - An action and to provide a' suitable signal.
initiated by the Protection to logic.
System when a limiting safety system setting is reache'd.
A G.
Limiting Conditions for Operat'on (LCO)-
protective action can be at a The limiting conditions for operation channel or system level.
specify the minimum acceptable levels of-system performance necessary to assure
- 8.. Protective Function'- A system safe startup and operation of.the facility.
protective action which results Whenethese conditions are met, the plant from the protective action of can be operated safely and abnormal situations the channels monitoring a can be safely. controlled.
particular plant condition.
9.
Simulated Automatic Actuation -
H.
Limiting Safety System Setting (LSSS) -
Simulated automatic actuation The limiting safety system settings are means applying a simulated settings on instrumentation which initiate-signal to the sensor to actuate the automatic protective action at a level the circuit in question.
such that the-safety limits will not be exceeded. The region between the safety 10.
Trip System - A trip system limit and these settings represent margin means an arrangment of instrument with normal operation lying below these channel trip signals and auxiliary settings. The margin has been established equipment required to initiate so that with proper operation of the instru-action to accomplish a protective mentation safety limits will never be exceeded.
function.
A trip system may require one or more instrument channel trip I.
Modes of Operation (Operational Mode) l signals related to one or more plant parameters in order to initiate trip Mode - The reactor mode is established by the system action.
Initiation of. pro-Mode Selector Switch. The modes include shutdown, tective action may require the trip-refuel,.startup/ hot standby, and run which are ping of a single trip system or the defined as follows:
. coincident tripping of two trip systems.
Amendment lio. 83 3
1.0 Continued 1.
Refuel Mode - The reactor is in system trips and control-rod withdrawal interlocks in service.
the refuel mode when the Mode Swi+:h is in the Refuel Mode J.
Operable - A system, subsystem, train, pos ; ion. When the Mode Switch is in the Refuel position, the component or device shall be OPERABLE or have OPERABILITY when it is capable refueling interlocks are in of performing its specified function (s).
service.
Implicit in this definition shall be the 2.
Run Mode -
In this mode the assumption that all necessary attendant instrumentation, controls, normal and reactor system pressure is at emergency electrical power sources, cooling.
or above 850 psig and the or seal water, lubrication or other auxiliary Reactor Protection System.is equipment that are required for the system, energized with APRM protection (excludin the 15 percent high subsystem, train, component or device to perform its function (s) are also capable of flux trip and the RBM interlocks performing their related support function (s).
in service.
i K.
Operating - Operating means that a system or 3.
Shutdown Mode - The reactor is component is performing its intended functions in the shutdown mode when the in its required manner.
Reactor Mode Switch is in the Shutdown Mode position.
L.
Operating Cycle - Interval between the end f ne refueling outage and the end of the i
a.
Hot shutdown means conditions subsequent refueling outage.
l as above with reactor coolant 0
i temperature > 212 F.
M.
Primary Containment Integrity -
Primary containment integrity means that the b.
Cold shutdown means conditions drywell and pressure suppression chamber are as above with reactor coolant intact and all of the following conditions temperature < 212 F. and the are satisfied:
l reactor vessel vented.
1.
All manual containment isolation valves 4.
Startup/ Hot Standby -
In this mode on lines connected to the Reactor Coolant the reactor protection scram trips System or containment which are not initiated by main steam line isolation required to be open during plant accident valve closure is bypassed when reactor conditions are closed.
These valves may be pressure is less than 1,005 psig, the low pressure main steam line isolation valve closure trip is bypassed, the Reactor Protection System is energized with APRM (15 percent) and IRM neutron monitoring i
i 4
J
- 3..
Limiting Conditions for Operation 4.
Surveillanca Requirtments 3.0 General 4.0 General Applicability:
Applicability -
Applies to the general Iro requirements of Section 3.
Applies to the general surveillance requirements of il Section 4.
Objective:
Objective:
To specify the general requirements applicable to
}
each Limiting condition for Operation listed in To specify the general requirements applicable to each 1 Section 3.
surveillance requirement in Section 4.
Specification:
Specifications A.
Limiting Conditions for Operation and ACTION A.
Surveillance Requirements shall be applicable during;.
requirements shall be applicable during the the CPERATIONAL CONDITIONS (modes) specified for OPERATIONAL CONDITIONS (modes) specified for individual Limiting Condition' for Operation un-each specification.
less otherwise stated in the individual Surveillaneq Requirements.
B.
Adherence to the requirements of the Limiting Condition for Operation and associated ACTION B.
Each Surveillance Requirement shall be performed within the specified time interval shall con-within the specified time interval with:
stitute compliance with the specification.
In the event the Limiting Condition for Operation 1.
An allowable variation of +25% of the is restored prior to expiration of the speci-surveillance interval, fled time interval, completion of the ACTION 1,
statement is not required.
2.
A total maximum combined interval time for any.
three (3) consecutive surveillance intervals C.
In the event a Limiting Condition for Opera-not to exceed 3.5 times the specified sur-tion and/or associated ACTION requirements veillance interval.
cannot be satisfied because of circumstances in excess of those addressed in the specifi-C.
Performance of a Surveillance Requirement within j
cation, the unit shall be placed in COLD the sPecified time interval shall constitute com-SHU'IDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> un-pliance with OPERABILITY requirements for a Limit-less corrective measures are completed that ing Condition for Operation and associated ACTION permit operation under the permissible ACTION statements unless otherwise required by the speci-or until the reactor is placed in an OPERA-fication. Surveillance requirements do not have.
TIONAL CONDITION (mode) in which the speci-to be performed on inoperable equipwent.
fication is not applicable.. Exceptions to l
these requirements shall be stated in the individual specifications.
I Amendment No. 83 30
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3 4.0 Continuzd 3.0 ~ Continued D..
Entry into an OPERATIONAL CONDITION D.
Entry into an' OPERATIONAL CONDITION (mode) shall (r ode) shall not be made unless.the not be made unless the conditions of the Limiting
' Surveillance Requirement (s). associated.
Condition for Operation are met without reliance with the Limiting Condition for on provisions contained in the ACTION. statements Operation-have been performed:within.
i unless otherwise excepted. This provision shall the applicable surveillance interval or not prevent passage thru OPERATIONAL CONDITIONS as otherwise specified.
(modes) required to comply with ACTION requirements.
.E.
When a system, subsystem, train, component or device
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4 is determined to be inoperable solely because its emergency power source is inoperable, or solely i
.because its nonnal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:
(1) i ts corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s),
subsystem (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the requirements of i
this specification.
Unless both conditions (1) and (2) are satisfied, the unit shall be placed in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This specification j
is not applicable when in Cold Shutdown or Refuel Mode.
i
?
30a Amendment No. 83 l
3.0 BASES D.
Continued A.
This specification states the applicability of each specification in terms of defined The intent of this provision is to insure
-OPERATIONAL CONDITION (mode) and is provided that facility operation is not initiated to delineate specifically when each specifica-with either required equipment or systems tion is applicable.
inoperable or other limits being exceeded.
B.
This ' specification defines those conditions Exceptions to this provision may be made necessary to constitute compliance with the for a limited number of specifications when terms of an individual Limitin'g Condition for startup with inoperable equipment would not Operation and associated ACTION requirement.
affect plant safety.
These exceptions are stated in the ACTION statements of the -
C.
This specification delineates the ACT, ION to be appropriate specifications.
taken for circumstances not directly provided for in the ACTION statements and whose occurrence E.'
This specification delineates what additional would violate the intent of the specification.
conditions must be satisfied to permit operation l Under the terms of Specification 3.0, the to continue, consis tent wi th the _ ACTION s tatemenG facility is to be placed in COLD SHUTOOWN within for power sources, when a normal or emergency the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
it is assumed that the-power source is not OPERABLE.
It specifically unit is brought to the required OPERATIONAL prohibits operation when one division is inoperal CONDITION (mode) within the required times by because its normal or emergency power source is promptly initiating and carrying out the inoperable and a system, subsystem, train, appropriate ACTION s tatement.
component or device in another division is inoperable for another reason.
D.
This specification provides that e:1try into an OPERABLE CONDITION (mode) must be made with (a)
The provisions of this specification permit the the full complement of required systems, equipment ACTION statements associated with individual or components OPERABLE and (b) all other systems, subsys tems, trains, components or parameters as specified in the Limiting Conditions devices to be consistent with the ACTION statemen:
for Operation being met without regard for allow-of the associated electrical power source.
It
- able deviations and out of service provisions allows operation to be governed by the time contained in the ACTION statements.
30b Amc.1dment No. 83 t
3.0 BASES - Continued E.
Continued E.
Continued As a further example, Specification 3.9.A.
requires in part that two 115KV lines and limits of the ACTION statement associated with reserve station transformers be available.
the Limiting Condition for Operation for the The ACTION statement provides a 7 day out-normal or emergency power source, and not by the of-service time when both required offsite individual ACTION statements for each system, sub-circuits are not OPERABLE.
If the definition system, train, component or device that is of OPERABLE were applied without consideration determined to be inoperable solely because of the of Specification 3.0.E., all systems, subsystems inoperability of its normal or emergency power trains, components and devices supplied by the source.
inoperable normal power sources, both of the offsite circuits, would also be inoperable.
c This would dictate invoking the applicable For example, Specification 3.9.A. requires in 1
part that both emergency diesel generator systems ACTION statements for each of the applicable be OfERABLE.
The ACTION statement provides for a LCOs.
However, the-provisions of Specification 7 day out-of-service time when emergency diesel 3.0.E. permit the time limits for continued generator system A or B is not OPERABLE.
If operation to be consistent with the ACTION sta the definition of OPERABLE were applied without ment for the inoperable normal power sources instead, provided the other specified conditio consideration of Specification 3.0.E., all systems, are satisfied.
In this case, this would mean subsystems, trains, components and devices supplied by the inoperable emergency power source, diesel that for one division the emergency power sourcG generator system A or B, would also be inoperable, must be OPERABLE (as must be the components This would dictate invoking the applicable ACTION supplied by the emergency power source) and all statements for each of the applicable Limiting redundant systems, subsystems, trains, compon-Conditions for Operation. However, the provisions ents and devices in the other division must be of Specification 3.0.E. permit the time limits for OPERABLE, or likewise satisfy Specification continued operation to be consistent with the 3.0.E. (i.e., be capable of performing their ACTION statement for the inoperable emergency diesel design functions and have an emergency power generator system instead, provided the other specified source OPERABLE).
In other words, both conditions are satisfied.
If they are not satisfied, emergency power sources A and B must be shutdown is required in accordance with this OPERABLE and all redundant systems, subsystems, specification.
trains, components and devices in both division %
30c Amendment No. 83
9
- 3. 0 BASES - Continued E.
Continued must also be OPERABLE.
If these conditions are not satisfied, shutdown is required in accordance with this specification.
In Cold Shutdown and Refuel Modes, Speci-
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fication 3.0.E. is not applicable, and thus the individual ACTION statement for each applicable Limiting Condition for Operation in these OPERATIONAL CONDITIONS (modes) must be adhered to.
o i
i Amendment No. 83 30d i
?
e e
4.0 BASES C.
Continued A.
This specification provides that surveillance equipment, systems or components are asstuned activities necessary to insure.the Limiting to be OPERABLE if the associated surveillance conditions for Operation are met and will be activities have been satisfactorily performed performed during the OPERATIONAL CONDITIONS within the specified time interval.
Nothing (modes) for which the Limiting Conditions in this provision is to be construed as for Operation are applicable.
Provisions defining equipment, systems or components for additional surveillance activities to OPERABLE, when such items are found or known be performed without regard to the appli-to be inoperable although still meeting the cable OPERATIONAL CONDITIONS (modes) are Surveillance Requirements.
provided in the individual Surveillance Requirements.
D.
This specificationi ensure =.that surveillance--
activities associated with a Limiting Condi-B.
The provisions of this specification pro-tion for Operation have been performed within vide allowable tolerances for performing the specified time interval prior to entry surveillance activities beyond those speci-into an applicable OPERATIONAL Col 0ITION (mode).
fled in the normal surveillance interval.
The intent of this provision is to ensure that These tolerances are necessary to provide surveillance activities have been satis-operational flexibility because of factorily demonstrated on a current basis as scheduling and performance considerations.
required to meet the OPERABILITY requirements 1
of the Limiting Condition for Operation.
C.
The provisions of this specification set forth the criteria for determination of Under the terms of this specification, for compliance with the OPERABILITY require-example, during initial plant start-up or I
ments of the Limiting Conditions for following extended plant outage, the appli-Operation. Under this criteria, cable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.
z i
a Amendment No. 83 30e
JAFNPr 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Applicability:
Applicability:
Applies to the instrumentation and associated Applies to the surveillance of the instrumentation devices which initiate the reactor scram.
and associated devices which initiate reactor scram.
Objective:
Objective:
To assure the operability of the Reactor To specify the type of frequency of surveillance to Protection System, be applied to the protection instrumentation.
Specification:
Specification:
A.
The setpoints, minimum number of trip systems, A.
Instrumentation systems shall be functionally minimum number of instrument channels that must tested and calibrated as indicated in Tables be operable for each position of the reactor 4.1-1 and 4.1-2 respectively.
mode switch shall be as shown on Table 3.1-1.
The design system response time from the opening of the sensor contact to and including the opening of the trip actuator contacts shall not exceed 50 msec.
B.
Minimum Critical Power Ratio (MCPR)
B.
Maximum Fraction of Limiting Power Density (MFLPD)
During reactor power operation at rated power The MFLPD shall be determined daily during and flow, the MCPS operating limits shall reactor power operation at 125"/ orated not be less than those shown below:
thermal power and the APRM high flux scram and Rod Block trip settings adjusted if necessary as required by Specifications 2.1.A.l.c and 2.1.A.l.d, respectively.
1.
When surveillance requirement (Tg h t 4.1.E is met.
Amendment No. jpdI p/(, 83 30f
JAFNPP 3.7 (cont'd) 4.7 (cont'd) t 9.
Primary containment atmosphere shall be 9.
Primary Containment Atmosphere continuously monitored for hydrogen and Monitoring Instruments.
oxygen when containment integrity is required. The monitoring system shall a.
Instrumentation shall be. functionally be considered operable if at least one tested and calibrated as specified in.
monitor is operable.
Table 4.7-1.
a)
From and after the time the primary containment atmosphere monitoring instruments are found or made to be inoperable for any reason, continued reactor operation is permissible for the succeeding thirty (30) days unless one instrument monitoring each parameter is sooner made operable, provided an appropriate a
grab sample is obtained and analyzed at least once each twenty-four (24) hour period.
b)
If specification 3.7.A.9.a cannot be met, the reactor shall be placed in the cold condition within twenty-four (24) hours.
B.
Standby Gas Treatment System B.
Standby Gas Treatment System 1.
Except as specified in 3.7.B.2 below 1.
Standby Gas Treatment System both circuits of the Standby Gas Treatment surveillance shall be performed as System shall be operable at all times when indicated below:
secondary containment integrity is required.
a.
At least once per operating cycle, it shall be demonstrated that:
(1) Pressure drop across th'e combined high-efficiency and charcoal filters is less than 5.7 in. of water at-6,000 scfm and (2) Each 39kW heater shall dissipate greater than 29kW of electric power as calculated by the following expression:
P="Y3' EI where P= Dissipated Electrical Power; E= Measured line-to-line voltage in volts (RMS);
I= Average measured phase current in amperes (RMS).
Amendment No. M J#, M g,
, 83 181
3.9 Continued 4.9 Continued 6.
Once within one hour and at least once per eight hours thereafter, while the reactor.is being operated in accordance with Specifications 3.9.B.1, 3.9.B.3..and 3.9.B.4, the availability of th'e operable off-site sources shall be verified by the correct breaker alignment indicating power availability.
C.
Diesel Fuel C.
Diesel Fuel There will be a minimum of 64,000 gal.
Once a month the quantity of diesel fuel of diesel fuel on site for each available in each storage tank shall be manually measured and compared to the reading operable pair of diesel generators.
of the local level indicators to ensure the proper operation thereof.
1.
From and af ter the time that the 1.
Once each month a sample of the fuel oil storage tank level diesel fuel in each storage tank instrumentation is made or shall be checked for quality as found to be inoperable for any per the following:
reason continued reactor operation is permissible indefinitely, provided Flash Point g F 125 F min.
that the level in the affected storage Pour Point - F 10 F max.
tank is manually measured at least Water & Sediment 0.50% max.
once/ day.
Ash 0.5% max.
I Distillation 90% Point 540 min.
Viscosity (SSU) at 100 F 40 max.
I U
Sulfur 1% max.
Copper Strip Corrosion No. 3 max.
Cetane #
35 min.
218 l
Amendment No. Jf, 83
3.9 Continued 4.9 Continued 2.
The Diesel Fuel Oil Transfer System 2.
During the monthly. diesel generatori shall be operable whenever'the diesel testing..the diesel fuel oil transfer generator it supplies is required to systems shall be checked for? proper) be operable, except as specified' operation.
below:
4 a.
From and after the time that fuel oil transfer pump.per Diesel Generator System is made or found to be inoperable for any reason, continued reactor operation is permissible for a period not to exceed 60 days; provided that the remaining fuel oil transfer pumps be demonstrated to be a
operable inmediately and weekly thereafter.
b.
From and after the time that only. two fuel oil transfer pumps per Diesel Generator System are 2
operable, continued reactor operation is permissible for a period not to exceed 30 days total per pair of diesels, provided that i
the remaining fuel oil transfer l
pumps are demonstrated to be operable immediately and daily thereafter.
219 ll l
Amendment No. 83 l
f 1
3.9 Centinued 4.9 continu:d c.
From and after the time 'that only one fuel oil transfer pump in a Diesel Generator System is found to be operable, that Diesel Generator System shall be considered inoperable and continued reactor operation shall be in accordance with Specification 3.9.B.3 above.
3.
Whenever the diesel fuel on site for each operable pair of Diesel Generators decreases to less than 64,000 gallons as I
a result of operation of the Diesel Genera-tors "to meet Technical Specification requirements," Specification 3.0.C does not apply.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> are allowed to restore fuel oil storage i
tank quantity to a minimum of 64,000 gallons.
D.
Diesel Generator Operability D.
Not Applicable Whenever the' reactor is in the cold shutdown or refueling modes, a minimum of one of the pairs of Emergency Diesel Generators, and all its j
associated emergency equipment shall be operable whenever any work is being done which has the potential for draining the vessel, secondary containment is required, or a core or containment cooling system is required.
220 l.
Amendment No. 83
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