ML20137R951
| ML20137R951 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/21/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20137R955 | List: |
| References | |
| DPR-46-A-095, TAC 55850 NUDOCS 8512060122 | |
| Download: ML20137R951 (11) | |
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UNITED STATES 8
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WASHINGTON, D. C. 20555
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NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUU. EAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District dated May 15, 1985, as supplemented by submittal dated July 11, 1985, 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C(2) cf Facility Operating License No. DPR-46 is hereby amended to read as follows:
8512060122 851121 DR ADOCK 050 8
i
. (2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, 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 its date of issuance.
FOR THE NUCLEA REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of issuance:
November 21, 1985 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 95 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 115 116 117 120 125 165a 193 199 5
D
LIMIIING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
- 3. 5. A' (cont'd.)
4.5.A (cont'd.)
2.
From and after the date that one of 2.
When it is determined that one core the core spray subsystems is made or spray subsystem is inoperable, the found to be inoperable for any reason, operable core spray subsystem and continued reactor operation is per-the LPCI subsystem shall be cemon-missible during the succeeding seven strated to be operable inmediaccly, days provided that during such seven The operable core spray subsystem days all active components of the shall be demonstrated to be oper-other core spray subsystem and active able daily thereafter.
components of the LPCI subsystem and the diesel generators are operable.
3.
Eoch LPCI subsystems shall be opera-3.
LPCI subsystem testing shall be as ble:
follows:
(1) prior to reactor startup from a Item Frequency Cold Condition, except as specified in 3.5.F.7, or a.
Simulated Auto-Once/ Operating matic Actuation Cycle (2) when there is irradiated Test fuel in the vessel and when the reactor vessel pressure b.
Pump Operability once/ month is greater than atmospheric pressure, except as specified c.
Motor Operated Once/ month in 3.5.A.4 and 3.5.A.5 below.
Valve Operability d.
Pump Flow Rate Once/3 months During single pump LPCI, each RHR pump shall deliver at least 7700 GPM but no more than 8400 GPM against a system head equivalent to a reactor vessel pressure of 20 psid above dry-well pressure with water level below the jet pumps. At the same condi-tions, two pump LPCI flow shall be at least 15,000 CPM.
Recirculation pump discharge valves e.
shall be tested each refueling outage to verify full open to full closed in 20 < t < 26 seconds.
4.
From and after the date that one of 4.
When it is determined that one of the the RHR (LPCI) pumps is made or found RHR (LPCI) pumps is inoperable at a to be inoperable for any reason, con-time when it is required to be oper-tinued reactor operation is permissi-ating the remaining active components ble only during the succeeding thirty of the LPCI subsystems, the contain-days provided that during such thirty ment cooling subsystem and both core days the remaining active components spray systems shall be demonstrated of the LPCI subsystem and all active to be operable immediately and the components of both core spray sub-operable LPCI pumps daily thereafter, systems and the diesel generators are operable.
Amendment No. M J,)MI, 95 I
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_ LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.5.A (Cont'd.)
4.5.A. (Cont'd.)
5.
From and after the date that one 5.
When it is determined that the LPCI l
LPCI subsystem is made or found to subsystem is inoperable, both core be inoperable for any reason, contin-spray subsystems and the containment ued reacter operation is permissible cooling subsystem shall be demon-only during the succeeding 7 days, un-strated to be operable immediately less it is sooner made operable, pro-and daily thereafter.
vided that during such 7 days all active components of both core spray subsystems, the containment cooling subsystems (including 2 LPCI pumps) and the diesel generators required for operation of such components shall be operable.
6.
All recirculation pump discharge 6.
All recirculation pump discharge valves and bypass valves shall be operable prior to reactor startup valves shall be tested for oper-(or closed if permitted elsewhere ability during any period of in these specifications).
Raactor cold shutdown exceeding 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if operability tests have not been perfo:ned during the preceding 31 days.
7.
The reactor shall not be started up with the RHR system supplying cooling to the fuel pool.
S.
If the requirements of 3.5.A 1,2,3,4, 5,6 or 7 cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in 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 />.
B.
Cpntainment Cooling Subsystem B.
Containment Cooling Subsystem (RNR (RHR Service Water)
Service Water) 1.
Except as specified in 3.5.B.2, 1.
Containment Cooling Subsystem Testing 3.5.B.3, and 3.5.F.3 below both con-shall be as follows:
tainment cooling subsystems loops shall be operable whenever irradiated Item fuel is in the reactor vessel and Frequency reactor coolant temperature is great-a.
Pump & Valve Once/3 months er than 212*F, and prior to reactor Operability startup from a Cold Cendition.
b.
Pump Capacity Test. After punp main-Each RHR service tenance and every water booster pump 93 months shall deliver 4000 gpm.
c.
Air test on dry-Once/5 years well and torus headers and nozzles.
Amendment No. g, g, 95
_i14_
LIMITINC CONDITIONS FOR OPERATION SURifEILLANCE REQUIREMENTS 3.5.B'(Cont'd.)
4.5.B (Cont'd.)
2.
From and after the date that any RHR 2.
When it is determined that any RHR service water booster pump is made service water booster pump is inoper-or found to be inoperable for any able, the remaining active components reason, continued reactor operation of the containment cooling subsystems is permissible only during the suc-shall be demonstrated to be operable ceeding thirty days, unless such immediately and weekly thereafter, pump is sooner made operable pro-vided that during such thirty days all other active components of the containment cooling subsystem are
, operable.
3.
From and after the date that one con-3.
When one containment cooling subsystem tainment cooling subsystem loop is loop becomes inoperable, the operabic made or found to be inoperable for subsystem loop shall be demonstrated any reason, continued reactor oper-to be operable immediately and daily tion is pernissible only during the thereafter.
succeeding seven days unless such subsystem loop is sooner made operable, provided that all active components of the other containment cooling sub-system loop, including its associated diesel generator, are operable.
4.
If the requirements of 3.5.B.1, 3.5.B.2 or 3.5.B.3 cannot be met, an orderly shutdown shall be initiated and the reactor shell be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
C.
HPCI Subsystem C.
HPCI Subsystem 1.
The HPCI Subsystem shall be operable 1.
HPCI subsystem testing shall be per-whenever there is irradiated fuel in formed as follows:
the reactor vessel, reactor pressure is greater than 113 psig, and prior Item Frequency to reactor startup from a Cold Condi-tion, except as specified in 3.5.C.2 a.
Simulated Once/ operating and 3.5.C.3 below.
Automatic Cycle Actuation Test b.
Pump Operability Once/ month c.
Motor Operated Once/ month Valve Operability AmendmentNo.)2F,95
-117-
I
's LIMITING CONDITIONS FOR"0PERATION
~ SURVEILLANCE' REQUIREMEh*IS
~ " ' ~ ~
3.5.E' (cont'd)~ " "
~4~.'5.E - (cont "d) '
2.
From and after the date that one 2.
When ir is determined that one valve in the automatic depressuriza-valve of the ADS is inoperable, the tion subsystem is made or found to be ADS subsystem actuation logic for the s
inoperable for any reason, continued other ADS valves and the HPCI subsys-reactor operation is permissible only tem shall be demonstrated to be oper-during the succeeding seven days un-able inusediately and at least weekly less such valve is sooner made opera-thereafter.
ble, provided that during such seven days the HPCI subsystem is operable.
3.
With the surveillance requireseats of 4.6.D.5 not performed at the required interials due to reactor shutdown, a reactor startup may be conducted pro-vided the appropriate surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of achieving 113 psig reactor steam pressure.
4.
If the requirements of 3.5.E.1 or 3.5.E.2 cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to at least 113 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
F.
Minimum Low Pressure Cooling and F.
Minimum Low Pressure Cooling and Diesel Generator Availability Diesel Generator Availability 1.
During any period when one diesel 1.
When it is determined that one generator is inoperable, continued diesel generator is inoperable, reactor operation is permissible all low pressure core cooling and only during the succeeding seven containment cooling subsystems days unless such diesel generator is shall be demonstrated to be oper-I sooner made operable, provided that able immediately and daily there-all of the low pressure core and con-after.
In addition, the operable
,tainment cooling subsystems and the diesel generator shall be demon-remaining diesel generator shall be strated to be operable immediately operable and the requirements of and every three days thereafter.
l 3.9.A.1 are met. If this require-ment cannot be met, the require-ments of 3.5.F.2 shall be met.
I 2.
During any period when both diesel i
generators are inoperable, continued j
reactor operation is permissibic'_only j
during the succeeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless one diesel generator is sooner made operable, provided that all the low l
pressure core and containment cooling subsystems are operable and the reactor power level is reduc'dd to 25%
of rated power and the requirements of 3.9.A.1 are met. If this requirement cannot be met, either the requirements shall be met or an orderly shutdown shall be initiated and the reactor 1
placed in 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 />.
l AmendmentNo.)tf,95
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i 3.5.i BASES (cont 'd.)
core spray subsystems and LPCI constitute a 1 out of 3 system; however, the combined effect of the two systems to limit excessive clad temperatures must also be considered.
The test interval specified in Specification 4.5 is 1 month.
Should a subsystem fail, a daily test is called for on the remaining systems to ensure that they will function.
Should one core spray subsystem become inoperable, the remaining core spray and the LPCI system are available should the need for core cooling arise. To assure that the remaining core spray and LPCI subsystems are available, they are demon-l strated to be operable immediately. This demonstration includes a manual initi-ation of the pumps and associated valves.
l Should the loss of one LPCI pump occur, a nearly full complement of core and containment cooling equipment is available. Three LPCI pumps in conjunction with the core spray subsystem will perform the core cooling function.
Because of the ' availability of the majority of the core cooling equipment, which will be demonstrated to,be operable, a thirty day repair period is justified.
If the LPCI subsystem is not available, at least 1 LPCI pump must be available to fulfill the containment cooling function.
The 7 day repair period is set on this basis.
B.
Containment Cooling Subsystem The containment cooling subsystem for CNS consists of two loops each with 2 RHR (LPCI) pumps serving one side of the RHR heat, exchanger and two RHR Service Water Booster Pumps serving the other side.
The design of the loops is predicted upon the use of one RHR Service Water Booster Pump and one RHR he'at exchanger, for heat removal after a design basis accident. Thus, there are ample spares for margin above design conditions. Loss of margin should be avoided and the equipment maintained in a state of operation.
So a 30 day out-of-service time is choscn for this equipment.
If one loop is out-of-service reactor operation is permissible for seven days with daily testing of the operable loop.
h With components or subsystems cut-of-service, overall core and containment.
cooling reliability is maintained by demonstrating the operability of the re-maining cooling equipment. The degree of operability to be demonstrated depends on the nature of the reason for the out-of-service equipment.
For routine out-of-service periods caused by preventive maintenance, etc., the pump and valve operability checks will be performed to demonstrate operability of,the remaining components. However, if a failure, design deficiency, etc., caused the out-of-service period, then the demonstration of operability a ould be thorough enough to assure that a similar problem does not exist on the remaining com-ponents.
For example, if an out-of-service period were caused by failure of a pump to deliver rated capacity, the other pumps of this type might be sub-jected to a capacity test.
In any event, surveillance procedures, as required by Section 6 of these specifications, detail the required extent of testing.
The pump capac.ity test is a comparison of measured pump performance parameters i
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1 AmendmentNo.p(,95
-125-i
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LIMITING CONDITIOHS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.B.ft>nt'd) 4.7.B (cont'd) 4.
If these conditions cannot be met, 4.a. At least once per operating cycle procedures shall be initiated automatic initiation of each branch of immediately to establish reactor the standby gas treatment system shall conditions for which the standby be demonstrated.
gas treatment system is not required.
b.
At least once per operating cycle manual operability of the bypass valve for filter cooling shall be demonstrated.
c.
When one standby gas treatment system i becomes inoperable the other standby gas treatment system shall be demon-strated to be operable immediately and daily thereafter. A demonstra-tion of diesel generator operability is not required by this specification.
C.
Secondary containment integrity shall 1.
Secondary containment surveillance be maintained during all modes of shall be performed as indicated plant operation except when all of below:
the following conditions are met.
D I
Amendment No.[ 95
-165a-
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM Applicability:
Applicability.
Applies to the auxiliary electrical Applies to the periodic testing pcuer system.
requirements of the auxiliary electrical systems.
Objective:
Objective:
To assure an adequate supply of elec-Verify the operability of the auxiliary trical power for operation of those electrical system.
systems required for safety.
Specification:
Specification:
A.
Auxiliary Electrical Equipment A.
Auxiliary Electrical Equipment 1.
The reactor shall not be made criti-1.
Emergency Buses Undervoltage cal from a Cold Shutdown Condition Relays unless all of the following condi-tions are satisfied:
a.
Loss of voltage relays a.
Both off-site sources (345 KV and once every 18.aonths, loss 69 KV) and the startup transformer of voltage on emergency and emergency transformer are avail-buses is simulated to able and capable of automatically demenstrate the load shed-supplying power to the 4180 Volt ding from emergency buses emergency buses IF and 1G.
and the automatic start of diesel generators.
b.
Both diesel generators shall be operable and there shall be a mini-b.
Undervoltage relays mum of 45,000 gal. of diesel fuel in the fuel oil storage tanks.
Once every 18 months, low voltage on emergency buses c.
The 4160V critical buses IF and 1G is simulated to demonstrate and the 480V critical buses IF and IG disconnection of the emer-are energized.
gency buses from the offsite power source. The under-1.
The loss of voltage relays and voltage relays shall be their auxiliary relays are calibrated once every 18
- operable, menths.
2.
The undervoltage relays and 2.
Diesel Generators their auxiliary relays are
- operable, a.
Each diesel-generator shall be started manually and loaded to d.
The four unit 125V/250V batteries and not less than 50% of rated load l
their chargers shall be operable.
for no less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> once each month to demonstrate oper-c.
The power monitoring syste'n for the ational readiness.
inservice RPS MG set or alternate source shall be operable.
AmendmentNo.(Mf,F/,)d,95
-193-
4.9 BASES The monthly test of the diesel generator is conducted to check for equipment failures and deterioration. Testing is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions. The diesel Senerator will be manually started, synchronized and connected to the bus and load picked up.
The diesel generator should be. loaded to at least 50%
of rated load to prevent fouling of the engine.
It is expected that the diesel generator will be run for at least two hours. Diesel generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.
Each diesel generator has two air compressors and two air receivers for starting.
It is expected that the air compressors will run only infrequently.
During the monthly check of the diesel generator, each receiver in each set of receivers will be drawn down below the point at which the corresponding compressor automatically starts to check operation and the ability of the compressors to recharge the receivers.
The diesel generator fuel consumption rate at full load is approximately 275 gallons per hour.
Thus, the monthly load test of the diesel generators will test the operation and the ability of the fuel oil transfer pumps to refill the day tank and will check the operation of these pumps from the emergency source.
The test of the diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system; i.e it will check diesel generator starting and closure of diesel generator breaker and sequencing of load on the diesel generator. The diesel generator will be started by simulation of a loss-of-coolant accident.
In additiou, an undervoltage condition will be imposed to simulate a loss of off-site power.
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pumps to deliver full flow. Periodic testing of the various components, plus a func-tional test once-a-cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure. The type,
of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
In addition, the checks described also provide adequate indication that the batteries have the speci-fled ampere-hour capability.
The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine.
I When it is determined that some auxiliary electrical equipment is out of service, the increased surveillance required in Section 4.5.F is deemed adequate to provide assurance that the remaining equipment will be operable.
The Reactor Protection System (RPS) is equipped with a seismically qualified.
Class 1E power monitoring system. This system consists of eight Electrical Protection Assemblies (EPA) which isolate the power sources from the RPS if the input voltage and frequency are not within limits specified for safe system operation.
Isolation of RPS power causes that RPS division to fail safe.
Amendment No. #, ff, M,J/, 95
-199-