ML20127P032
| ML20127P032 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/09/1985 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127P019 | List: |
| References | |
| NUDOCS 8505230678 | |
| Download: ML20127P032 (13) | |
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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by the Omaha Public Power District (the licensee) dated July 22, 1981, as supplemented by letters dated June 15 and October 27, 1982, September 20, 1983, and April 6,1984, 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 CFR Chapter I; B.
The facility will operate in confomity 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 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 Commission's regulations and all applicable requirements have been satisfied.
8505230678 850509 PDR ADOCK 05000285 P
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-40 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No.
, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 9, 1985 l
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET N0. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised
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pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 2-65 2-65 2-65a 2-66 2-66 i
2-66a 2-67 2-67 2-67a 2-68 2-68 2-68a 2-68a l
2-68b 2-69 2-69 2-69a l
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2.0 LIMITING CONDITIONS FOR OPERATION 2.15 Instrumentation and Control Systems Applicability Applies to plant instrumentation systems.
Objective To delineate the conditions of the plant instrumentation and control systems necessary to assure reactor safety.
Specifications The operability of the plant instrument and control systems shall be in accordance with Tables 2-2 through 2-5.
(1)
In the event the number of channels of a particular system in service falls one below the total number of installed channels, the inoperable channel shall be placed in either the bypassed or tripped condition within one hour if the channel is equipped with a key operated bypass switch, and eight hours if jumpers or blocks must be installed in the control circuitry. The inoperable channel may be bypassed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovering loss of operability; however, if the inoperability is determined to be the result of malfunctioning RTDs or nuclear detectors supplying signals to the high power level, 4
thermal margin /lcw pressurizer pressure, and axial power distribution channels, these channels may be bypassed for up to 7 days from time of discovering loss of operability. If the inoperable channel is not restored to operable status after the allowable time for bypass, it shall be placed in the tripped position or, in the case of malfunc-tioning RTDs or linear power nuclear detectors, the reactor shall be placed in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If active maintenance and/or surveillance testing is being perfomed to return a channel to active service or to establish operability, the channel may be bypassed during the period of active maintenance and/or surveillance testing.
Thisspecificationappliestothehighragetrip-widerangelog channel when the plant is at or above 10- % power and is operating below 15% of rated power.
(2) In the event the number of channels of a particular system in service falls to the limits given in the column entitled " Minimum Operable Channels", one of the inoperable channels must be placed in the tripped position or low level actuation permissive position for the auxiliary feedwater system within one hour, if the channel is equipped with a bypass switch, and within eight hours if jumpers or blocks are required.
If the channel has not been restored to operable status after 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovering loss of operability, the reactor shall be placed in a hot shutdown condition within the follow-ing 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, operation can continue without containment 2-65 Amendment No. 8, 29, 54, 65, 88
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2.0 LIMITING CONDITIONS FOR OPERATION 2.15 Instrumentation and Control Systems (Continued) ventilation isolation signals available if the containment ventila-tion isolation valves are closed.
If after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of initiating a hot shutdown procedure the inoperable engineered safety features or isolation functions channel has not been restored to operable status, the reactor shall be placed in a cold shutdown condition 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 applies to the high rate trip-wide range log channel when the plant is at or above 10-9% power and is operating below 15% of rated power.
(3)
In the event the number of channels of a particular system in service falls below the limit; given in the columns entitled " Minimum Operable Channels" or " Minimum Degree of Redundancy", except as conditioned by the column entitled "Pennissible Bypass Conditions", the reactor shall be placed in a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; however, opera-tion can continue without containment ventilation isolation signals available if the ventilation isolation valves are closed.
If minimum conditions for engineered safety features or isolation functions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from time of discovering loss of operability, the reactor shall be placed in a cold shutdown condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the number of operable high rate trip-wide range log channels falls below that given in the column entitled
" Minimum Operable Channels" in Table 2-2 and the reactor is at or above 10-4% power and at or below 15% of rated power, reactor critical operation shall be discontinued and the plant placed in an operational mode allowing repair of the inoperable channels before startup or reactor critical operation may proceed.
j If, during power operation, the rod block function of the secondary CEA position indication system and rod block circuit are inoperable for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the plant computer PDIL alarm, CEA group deviation alarm and the CEA sequencing function are inoperable for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the CEAs shall be withdrawn and maintained at fully withdrawn and the control rod drive system mode switch shall be maintained in the off position except when manual motion of CEA Group 4 is required to control axial power distribution.
Basis During plant operation, the complete instrumentation systems will normally be in service.
Reactor safety is provided by the reactor protection system, which automatically initiates appropriate action to prevent exceed-ing established limits.
Safety is not compromised, however, by continuing operation with certain instrumentation channels out of service since provisions were made for this in the plant design. This specification outlines limiting conditions for operation necessary to preserve the effectiveness of the reactor control and protection system when any one or more of the channels are out of service.
All reactor protection and almost all engineered safety feature channels are supplied with sufficient redundancy to provide the capability for channel test at power, except for backup channels such as derived circuits in engineered safeguards control system.
I 2-66 Amendment No. 8, 29, 54, 65,88
2.0 LIMITING CONDITIONS FOR OPERATION 2.15 Instrumentation and Control Systems (Continued)
Basis (Continued)
When one of the four channels is taken out of service for maintenance, the protective system logic can be changed to a two-out-of-three coincidence for a reactor trip by bypassing the removed channel.
If the bypass is not effected, the out-of-service channel (Power Re7uved) assumes a tripped
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condition (except high((qte-of-change of power, high power level and high i
pressurizer pressure), 81 which results in a one-out-of-three channel logic.
If in the 2 of 4 logic system of the reactor protective system one channel is bypassed and a second channel a nually placed in a tripped condition, the resulting logic is 1 of 2.
At rated power, the minimum operable high-power level channels is 3 in order to provide adequate power tilt detection.
If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts and from exceeding dropped CEA peaking factors.
All engineered safety features are initiated by 2-out-of-4 logic matrices except containment high radiation which operates on a 1-out-of-5 basis.
The engineered. safety features system provides a 2 of 4 logic on the signals used to actuate the equipment connected to each of the two emergency diesel generator units.
The rod block system automatically inhibits all CEA motion in the event a Limiting Condition for Operation (LCO) on CEA insertion, CEA deviation, CEA overlap or CEA sequencing is approached. The installation of the rod block system ensures that no single failure in the control element drive control system (other than a dropped CEA) can cause the CEAs to move such that the CEA insertion, deviation, sequencing or overlap limits are exceeded.
Accordingly, with the rod block system installed, only the dropped CEA event is considered an A00 and factored into the derivation of the Limiting Safety System Settings and Limiting Conditions for Operation. With the rod block function out-of-service several additional CEA deviation events must be considered as A00s. Analysis of these incidents indicates that the single CEA withdrawal incident is the most limiting of these events. An analysis of the at-power single CEA withdrawal incident was performed for Fort Calhoun for.various initial Group 4 insertions, and it has been concluded that the Limiting Conditions for Operation (LCO) and Limiting Safety System Settings (LSSS) are valid for a Group 4 insertion of less than or equal to 15%.
References (1) FSAR, Section 7.2.7.1 2-66a Amendment No. 8, 20, 25, 32, 73,88 l
TABLE 2-2 Instrument Operating Requirements for Reactor Protective System
- Test, Maintenance Minimum Minimum Permissible and Operable Degree of Bypass Inoperable No. Functional Unit Channels Redundancy Condition Bypass-1 Manual (Trip Buttons) 1 None None N/A 2
High Power Level 2(b)(c) j(c)
Thermal Power (e)(f)
Input Bypgssed below 10-*%
Rated Power (ofa)(d) 3 Thermal Margin / Low 2(b) 1 Below 10-4%
(e)(f)
Pressurizer Pressure RatedPower(
(d) 4 High Pressurizer 2(b) 1 None (e)
Pressure 5
Low R.C. Flow 2(b) 1 Below 10-4% of (e)
Rated Power (a)(d) 6 Low Steam Generator 2/Stegm 1/ Steam None-(e)
Water Level Gentb1 Gen 7
Low Steam Generator 2/Stegm 1/ Steam Beloy 550)
(e) psiala)(d Pressure Gentbl Gen 8
Containment High 2(b) 1 During Leak Test (e)
Pressure 9
Axial Power 2(b)(c) j(c)
Below 15% of (e)(f)
Distribution Rated PowerL9) 10 High Rate Trip-Wide 2(b) 1 Below 10-4% and (e)
Range Log Channels above 15% o'f RatedPowerta)(g) 11 Loss of Load 2(b) 1 Below 15% of (e)
Rated Power (9) 12 Steam Generator 2(b) 1 None (e)
Differential Pressure a
Bypass automatically removed.
b.
If minimum operable channel conditions are reached, one inoperable channel must be placed in the tripped condition within one hour-from the time of discovery of loss of operability. The remaining channel may be bypassed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and, if an inoperable channel is not returned to operable status
-within this time frame, a unit shutdown must be initiated. (See Specification (2) and exception associated with the high rate trip-wide range log channel.)
2-67 Amendment No. 60, 77, 88
TABLE 2-2 (Continued) c If two channels are inoperable, load shall be reduced to 70% or less of rated power.
d For low power physics testing this trip may be bypassed up to 10-l% of rated power.
e If one channel becomes inoperable, that channel may be bypassed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovery of loss of operability.
If not returned to operable status within this time frame, the channel must be placed in the tripped condition.
(SeeSpecification(1)andassociatedexceptions.)
f If the inoperable channel is determined to be caused by malfunctioning RTDs or nuclear detectors, the channel may be bypassed for up to 7 days from time of discovery of loss of operability.
If not returned to operable status within this time frame, the unit must be placed in tot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
g.
For each channel, the same bistable automatically activates the Loss of Load and Axial Power Distribution (APD) trips and automatically bypasses the high rate trip at 15% of rated power. Only the APD trip is a Limiting Safety System Setting. Therefore, the bistable is set to actuate within the APD tolerance band.
i 2-67a Amendment No.69, 77, 88
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TABLE 2-3 Instrument 0perating Requirements for Engineered Safety Features
- Test, Maintenance Minimum Minimum Permissible-and Operable Degree of Bypass Inoperable No.
Functional Unit Channels Redundancy Condition Bypass 1
Safety Injection A
Manual 1
None None N/A B
High Containment Pressure A 2(a)(d)'
1 During Leak (f)
B 2(a)(d) j Test C
Pressurizer Low / Low
-(a)(d)
Pressure A 2
1 Reactor Coolant-(f)
B 2(a)(d) j Than1700 psia (b)
Pressure Less 2
Manual 1
None None N/A B
High Containment Pressure A 2(a)(c)(d)1 During Leak (f)
B 2(a)(c)(d)j Test C
Pressurizer Low / Low A
2(a)(c)(d)1 Reactor Coolant (f)
B 2(a)(c)(d)j Than 1700 psia (b)
Pressure Less 3
Recirculation A
Manual 1
None None N/A' B
SIRW Tank Low Level A 2(a)(d) 1 None (f)
B 2(a)(d).
1 4-Emergency Off-Site Power Trip A
Manual 1(*)
None None N/A B
Emergency Bus Low Voltage (Each Bus)
Id) 1 Reactor Coolant (f)
-Loss of Voltage 2
-Degraded Voltage 2(a)(d) j greLess e
2-68 Amendment No. U, 65,88 u-
TABLE 2-3 (Continued)
- Test, Maintenance Minimum Minimum Permissible and Operable Degree of Bypass Inoperable No.
Functional Unit Channels Redundancy Condition Bypass i
Manual 1
None None N/A B
Auto. Initiation A Operating Modes B
3, 4, and 5
- Steam Generator 2(a)(d) 1 (h) i Low Level a)(g)
- Steam Generator 3
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(4)
Low Pressure
- Steam Generator 3(a)(g) j
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Differential Pressure a
A and B actuation circuits each have 4 channels.
b Auto removal of bypass above 1700 psia.
Coincident high containment pressure and pressurizer pressure low signals c
required for initiation of containment spray.
d If minimum operable channel conditions are reached, one inoperable channel
- must be placed in the tripped condition or low level actuation position for auxiliary feedwater system within eight hours from the time of discovery of
- loss of operability. The remaining inoperable channel may be bypassed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and, if an inoperable channel-is not returned to operable status within this time frame, a unit shutdown must be initiated (see Specifica-tion (2)).
e Control switch on incoming breaker.
f If one channel becomes inoperable, that channel must be placed in the tripped or bypassed condition within eight hours from time of discovery of loss of operability.
If bypassed and that channel is not returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovery of loss of operability, that channel must be placed in the tripped condition within the following eight hours.
(See Specification (1) and exception associated with maintenance.)
g Three channels required because bypass or failure results in auxiliary feed-water actuation block in the affected channel.
h If one channel becomes inoperable, that channel must be placed in the actuation
. condition within eight hours or bypassed condition within one hour from time of-discovery of loss of operability.
If bypassed and that channel is not returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovery of loss of operabil-ity, the channel must be placed in the low level actuation permissive condition within the following eight hours.
(See Specification (1) and exception associated with maintenance.)
2-68a Amendment No. 65, 88
TABLE 2-3 (Continued)
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If the channel becomes inoperable, that channel must be placed in the bypassed condition within eight hours from time of discovery of loss of operability.
If the channel is not returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from time of discovery of loss of operability, one of the~ eight channels may continue to be'placed in the bypassed condition provided the Plant Review Committee has reviewed and documented the judgment concerning prolonged operation in bypass of the defective channel. The channel shall be returned to operable status no later than during the next cold shutdown.
If one of the four channels on one steam generator is in prolonged bypass and a channel on the other steam generator becomes inoperable, the second inoperable channel must be placed.in bypass within eight hours from time of discovery of loss of operability.
If one of the inoperable channels is not returned to operable status within seven days from the time of discovery of the second loss of
- operability, the unit must be placed in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4 2-68b Amendment No.88
TABLE 2-4
- Test, Maintenance Minimum
' Minimum Permissible and Operable Degree of Bypass Inoperable No.
Functional Unit Channels Redundancy Condition Bypass 1
-Containment Isolation A
Manual 1
None None N/A B
Containment High Pressure A-2(a)(e) 1 During Leak (f)
B 2(a)(c) j Test C
Pressurizer Low /
Low A 2(a)(e) 1 Reactor Coolant (f)
B 2(a)(e) j Pressure Less Than1700 psia (b) 2 Steam Line Isolation A
Manual 1
None None N/A B
Steam Generator Low Pressure A 2/S';egm 1/ Steam Steam Generator (f)
Gensei Gen Pressure Less B
2/ Steam 1/ Steam Than 650 psia (c)
Gen (e)
Gen 3
Ventilation Isolation A
Manual 1
None None N/A B
Containment High Radiation A 2(d)
None If Containment G)
B 2(d)
Ventilation Isola-tion Valves Are Closed a
A and B circuits each have 4 channels, b
Auto removal of bypass above 1700 psia, c
Auto removal of bypass above 550 psia.
d A.and B circuits are both actuated'by any one of the five VIAS initiating channels; RM-050, RM-051, RM-060, RM-061, or RM-0C2; however, only RM-050 and RM-051 are required for containment ventilation isolation.
e If minimum operable channel conditions are reached, one inoperable channel must be placed in the tripped condition within eight hours from the time of discovery of loss of operability. The remaining inoperable channel may be by-passed for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from the time of discovery of loss of operability and, if an inoperable channel is not returned to operable status within this time frame, a unit shutdown must be initiated (see Specification (2)).
2-69 Amendment No. 88 i
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i TABLE 2-4 (Continued) f;
.If one channel becomes, inoperable, that channel must be placed in the tripped
- or bypassed. condition within eight hours from the time of discovery of loss of operability.
If bypassed and that channel is not returned to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> from the time of discovery of loss of operability, that channel must be placed in the tripped condition within the following eight hours.
(See Specification (1) and exception associated with mainte-c nance.)
a 2-69a Amendment NoJB8
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