ML19330B785
| ML19330B785 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/25/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19330B786 | List: |
| References | |
| TAC-43335, NUDOCS 8008050520 | |
| Download: ML19330B785 (13) | |
Text
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j NUCLEAR REGULATORY COMMisslON s
j wasmwaTON, D.C. 20805
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THE TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE j
Amendment No. 28 License No. NPF 3 1.
The Nuclear Regulatory Cosmission (the Conuission) has found that:
A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 20, 1978, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Conmission'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 Connission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities w111 be conducted in compliance with the Consission's regulations; D.
The issuance of this amendment will not be inimical to the connon 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 conmission's regulations and all applicable requirements -
have been satisfied.
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8 00805 0ND
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2.
Accordingly, Facility Operating License No. NPF-3 is hereby amended as indicated below and by changes to the Technical Specifications as indicated in the attachment to this license amendment:
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A.
Revise paragraph 2.C.(2) to read as follows:
j Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 28, are hereby incor-porated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
B.
Replace paragraph 2.C.(3)(d) with the following:
f Prior to operation beyond five Effective Full Power Years, the Toledo Edison l
Company shall provide to the NRC a renalysis and proposed modifications, as necessary, to ensure continued means of protection against low temperature reactor coolant system overpressure events.
C.
Delete paragraph 2.C.(3)(j).
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hkI f.
L/
j ert W. Reid, Chief 1
Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 25, 1980 t
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ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO. NPF-3 i
DOCKET NO. F0-346 Replace the following pages of the Appendix "A" Technical Specifications l
with the enclosed pages as indicated.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to naintain document completeness.
i i
Pages 3/4 3-11 l
3/4 3-12 3/4 3-13 l
l 3/4 3-22 l
3/4 4-2 I
3/4 5-4 i
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TABLE 3.3-3 (Continued)
TABLE NOTATION Trip function may be bypassed in this MODE with RCS pressure below 1800 psig. Bypass shall be automatically removed when RCS pressure exceeds 1800 psig.
Trip function may be bypassed in this MODE with RCS pressure below 600 psig. Bypass shall be automatically removed when RCS pressure exceeds 600 psig.
One must be in SFAS Channels #1 or #3, the other must be in Channels
- 2 or *4 The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS ACTION 9 With the number of OPERABLE functional units one less than the Total Number of Units operation may proceed provided both of the following conditions are satisfied; a.
The inoperable functional unit is placed in the tripped condition within one hour.
b.
The Minimum Units OPERABLE requirement is met; how-ever, one additional functional unit may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 10 -
With any component in the Output Logic inoperable, trip the associated components within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 11 -
With the number of OPERABLE Units one less than the Total Number of Units, restore the inoperable functional unit to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN with-in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 12 -
a.
With less than the Mimimum Units OPERABLE and reactor coolant pressure > 438 psig, both Decay Heat Isola-l tion Valves (DHil-and DH12) shall be verified closed.
b.
With less than the Minimum Units OPERABLE and reactor coolant pressure < 438 psig operation may continue; l
however, the functional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig.
l ACTION 13 -
With less than the Minimum Units OPERABLE and reactor coolant pressure <438 psig, operation may continue; however, the func-tional unit shall be OPERABLE prior to increasing reactor coolant pressure above 438 psig, or the inoperable functional unit shall be placed in the tripped state.
DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No.Z0
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TABLE 3.3-3 E5 SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION
'('
MINIMUM M
TOTAL NO.
UNITS UNITS APPLICABLE
.m FUNCTIONAL UNIT OF UNITS TO TRIP OPERABLE MODES ACTION 3.
MANUAL ACTUATION a.
SFAS (except Containment Spray and Emergency Sump 2
2 2
ALL MODES 11 Recirculation) b.
2 2
1, 2, 3, 4 11 4.
SEQUENCE LOGIC CilANNELS 4
2***
4 1, 2, 3, 4 9#
5.
INTERLOCK CHANNELS b
a.
Decay lleat Isolation Valve 1
1 1
1,2,3,4,5 12#
b b.
Pressurizer lleaters 2
2 2
3,4,5 13#
l g
i 1
h
=
I B~
e l
E.
4
TABLE 3.3-S SAFETY FEATURES SYSTEM RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.
Manual a.
Fans 1.
Emergency Vent Fan NA 2.
Containment Cooler Fan NA b.
ECCS Room NA 2.
Emergency Ventilation NA 3.
Containment Air Sample NA 4
Containment Purge NA S.
Pentration Room Purge NA c.
Control Room HV & AC Units NA d.
High Pressure Injection 1.
High Pressure Injection Pumps NA 2.
High Pressure Injection Valves NA e.
Component Cooling Water 1.
Component Cooling Water Pumps NA 2.
Component Cooling Aux. Equip. Inlet Valves NA 3.
Ccmponent Cooling to Air Compressor Valves NA f.
Service Water System 1.
Service Water Pumps NA 2.
Service Water From Component Cooling Heat Exchanger Isolation Valves NA 1
g.
Containment Spray Isolation Valves NA h.
Emergency Diesel Generator NA 1.
Containment Isolation Valves 1.
Vacuum Relief NA 2.
Normal Sump NA 3.
RCS Letdown Delay Coil Outlet NA 4.
RCS Letdown High Temperature NA DAVIS-BESSE, UNIT I 3/4 3-14
g TABLE 3.3-4 SAFETY FEATURE _S ACTUAT_ ION SYSTEM INSTRUMENTATION TRIP SETPOINTS G
u, FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES C*
INSTRUMENT STRINGS
~
a.
Containment Radiation
< 2 x Background at RATED
< 2 x Sackground at RATED THERMAL POWER, TllERMAL POWER
-b.
Containment Pressure - High
< 18.4 psia
< 18.52 psla#
c.
Containment Pressure - High-High
< 38.4 psia
< 38.52 psia #
d.
RCS Pressure - Low 1 1620.75 psig 1 1615.75 psig#
e.
RCS Pressure - Low-Low 1 420.75 psig 1 415.75 psig#
f.
BWST Level
-> 49.5 and < 55.0 in. H 0
-> 48.3 and
< 56.7 in. H 0 p
SEQUENCE LOGIC CHANNELS e.
Essential Bus Feeder Breaker Trip (90%)
> 3744 volts for
> 3558 volts
- 7 + 1.5 sec
- for 7 + 1.5 sec#
b.
Diesel Generator Start, load Shed on g
Essential Bus (59%)
> 2071 and < 2450 volts
> 2071 and < 2450 5
for 0.5 + 0.1 sec volts for 0.5 + 0.1 sec#
z P
INTERLOCK CHANNELS k
rc a.
Decay Heat Isolation Valve
< 438 psig
< 443 psigf*
l and Pressurizer Heater Allowable Value for CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION.
- Referenced to the centerline of Dilli and DH12 l.
TABLE 4.3-2 5
SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS T'
CHANNEL MODES IN WHICH E5 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE
((
FUNCTIONAL UNIT glECK CALIBRATION TEST REQUIRED g
5.
INTERLOCK CHANNELS
((
a.
Decay Heat Isolation Valve S
R 1,2,3,4,5 3,4,5 l
b.
Pressurizer Heater S
R
- See Speci fication 4.5.2.d.1 TABLE NOTAT!0ri
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R$
(1) Manual actuation switches shall be tested at least once per 18 months.during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.
Y (2) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or m
E[
pressure to the appropriate side of the transmitter.
$n 42, 4
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TABLE 4.3-2 g"
SAFETY FEATURES ACTUATION SYSTEM INSTRUMfNTATION SURVEILLANCE REQUIREMENTS U
viF CIIANNEL MODES IN WHICH CilANNEL CHANNEL FUflCTIONAL SURVEILLANCE
]
g FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED
[
1.
INSTRUMENT STRINGS j
a.
Containnent Radiation - liigh S
R H
All MODES
)
b.
Containment Pressure - High S
R M(2) 1, 2, 3 f
c.
Containment Pressure - liigh-liigh S
R M(2) 1, 2, 3 l
d.
RCS Pressure - Low S
R M
1,2,3 e.
RCS Pressure - Low-Low S
R M
1, 2, 3 f.
BWST Level - Low S
R M
1, 2, 3 i
2.
OUTPUT LOGIC a.
Incident Level #1: Containment Isolation S
R M
All MODES b.
Incident Level #2: liigh Pressure
[
Injection and Starting Diesel Generators S
R M
1, 2, 3, 4 c.
Incident Level #3: Low Pressure Injection S
R M
1, 2, 3, 4 d.
Incident Level #4: Containment e
Spray S
R M
1, 2, 3, 4 e.
Incident Level #5: Containment Sump Recirculation S
R M
1, 2, 3, 4 3.
MANUAL ACTUATION SFAS (Except Containment Spray NA NA M(1)
All MODES a.
and Emergency Sump Recirculation) b.
Containment Spray NA NA M(1) 1, 2, 3 4.
SEQUENCE LOGIC CHANNELS S
NA M
1, 2, 3, 4 4
REACTOR C001 ANT SYSTEM LIMITING C'ONDITION FOR OPERATION (Continued)
MODES 3, 4 and 5:
a.
Operation may proceed provided at least one reactor ecolant loop is in operation with an associated reactor coolant pump or decay heat removal pump.*
b.
Not more than one decay heat removal pump may be operated with the sole suction path through DH-ll and DH-12 unless the control power has been removed from the DH-ll and DH-12 valve operators, or manual valves DH-21 and DH-23 are opened.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
- All reactor coolant pumps and decay heat removal train pumps may be de-energized for up to l hour to acconnodate surveillance testing
& pre-operational testing, provided no operations are permitted which could cause dilution of the reactor coolant system boron concentration.
SURVEILLANCE REQUIREMENTS 4.4.1 The Reactor Protective Instrumentation channels specified in the applicable ACTION statement above shall be verified to have had their trip setpoints changed to the values specified in Specification 2.2.1 for the applicable number of reactor coolant pumps operating either:
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after switching to a different pump combination a.
if the switch is made while operating, or b.
Prior to reactor criticality if the switch is made while shutdown.
DAVIS-BESSE, UNIT 1 3/4 4-2 knendment No. 7. )( 2 8 y
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3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION h
3.4.1 Both reactor coolant loops and both reactor coolant pumps in each loop shall be in operation, j
APPLICABILITY: As noted below, but excluding MODE 6.*
ACTION:
MODES I and 2:
a.
With one reactor coolant pump not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 78.3% of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1 for operation with three reactor coolant pumps operating:
1.
High Flux t
2.
Flux-aFlux-Flow b.
With one reactor coolant pump in each loop not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 50.6'4 of RATED THERMAL POWER and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the setpoints for the following trips have been reduced to the values specified in i
Specification 2.2.1 for operation with one reactor coolant pump operating in each loop:
1.
High Flux
~
2.
Flux-aFlux-Flow
- See Special Test Exception 3.10.3.
iI DAVIS-BESSE, UNIT 1 3/4 4-1 AmendmentFNo.16 e.
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O EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS b.
At least once per 31 days by verifying that the ECCS piping is full of water by venting the ECCS pump casings and discharge piping high points.
By a visual inspection which verifies that no loose debris c.
(rags, trash, clothing, etc.) is cresent in the containment which could be transported to tr.s containment amergency sump and cause restriction of the pump suction during LOCA con-ditions. This visual inspection shall be perfomed:
1.
For all accessible areas of the contaiment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within contaiment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
Verifying that the interlocks:
a) Close DH-ll and DH-12 and deenergize the pressurizer i
heaters, if either DH-ll or DH-12 is open and a simulated reactor coolant system pressure which is i
greater than the trip setpoint(<438 psig) is applied.
b) Prevent the opening of DH-ll and DH-12 when a simulated or actual reactor coolant system pressure which is greater than the trip setpoint (<438 psig) is applied.
2.
A visual inspection of the containment emergency sump which verifies that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
3.
Verifying a total leak rate < 20 gallons per hour for the LPI system at:
a)
Nomal operating pressure or hydrostatic test pressure of,> 150 psig for those parts of the system dawnstream of the pump suction isolation valve, and b)
> 45 psig for the piping from the containment mergtncy sump isolation valve to the pump suction isolation valve.
4.
Verifying that a minimum of 72 cubic feat of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the TSP storage baskets.
DAVIS-BESSE, UNIT l 3/4 5-4 Amendment No. / 2 8
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I EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T;yg > 280*F LIMITING CONDITION FOR OPERATION i
3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprisec of:
a.
One OPERABLE high pressure injection (HPI) pump, b.
One OPERABLE low pressure injection (LPI) pump, c.
One OPERABLE decay heat cooler, and d.
An OPERABLE flow path capable of taking suction from the borated water storage tank (BWST) on a safety injection signal and automatically transferring suction to the containment sump on a borated water storage tank low level signal during the j
recirculation phase of operation.
I APPLICA5!'ITY: MODES 1, 2 and 3.
i ACTION:
I a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 witnin 90 days describing the circumstances of the actuation and the total accumulated actuation cycles te date.
i SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
l DAVIS-BESSE, UNIT 1 3/45-3 Y