ML20076E460
| ML20076E460 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/14/1991 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076E461 | List: |
| References | |
| NUDOCS 9108200154 | |
| Download: ML20076E460 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION k
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TOLEDO ED! SON COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPAtlY DOCKET NO 50-346
, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO 1 AMENDMENT TO FACILITY OPERATING L' CENSE Amendment No.159 License No. NPT-3 1.
The Nuclear Regulatory Conunission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric illuminating Company (the licensees) dated June 4, 1991, 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 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 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 NPF-3 is hereby amended to read as follows:
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910B200154 910014 l
PDR ADOCK 0b000346 P
' i (a) Technical Specifications f
The Technical Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporated in the license, The Toledo Edison Company shall operate the :acility in accordance l
with the Technical Specifications.
j 3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 45 days after issuance, j
FOR THE NUCLEAR REGULATORY COMMISSION l
D
, Vf)
Es-s on B. Hopkins, Sr/ Project Manager Project Directorate 111 3 Division of Reactor Projects 111/1V/V i
Office of Nuclear Reactor Reguiation l
Attachment:
Changes to the Technical Specifications Date of issuance: August 14, 1991 I
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~. _ _.. _. _, _..,.... _ _ _ _....., _.., _... _, ~ _..,... _. -
ATTACHMENT TO LICENSE AMENDMENT NO.159 FACILITY OPERATING LICENSE i10. NPF 3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. 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 maintain document completeness.
Remove Insert 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-22 3/4 3-22 t
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wy TABLE 3.3-3 (Continued) i.
Eg SAFETT FEATimES ACTUATION SYSTEM INSTRUMENTATIOft i
T MINIMun E
i TOTAL NO.
IMITS UNITS AFFLICABLE Q
FUNCTIONAL INIIT OF UNITS TO TRIP GPERABLE MODES i
ACTION l
3.
MANUAL ACTUATION i
.i a.
SFAS (except Containment l
Spray and Emergency Susp i
Recirculation) 2 2
2 1,2,3,4,6****
12 i
b.
2 2
1,2,3,4 12 T
l 4.
SEQUENCE LOGIC CHANNELS i
Y j_
g a.
Sequencer 4
2***
3 1,2,3,4 103 i
l b.
Essential Bus Feeder Breaker Trip (90%)
2 1
2*****
1,2,3,4 150
,?
i g
c.
Diesel Generator Start, g
IA,ad Shed on Essential i
l-g Bus (59%)
2 1
2 1,2,3,4 158 1
5 5.
INTERLOCK CHAIEEELS 2
l
?
y a.
Decay Beat Isolation Valve 1
1 1
1,2,3 13 f l e
I, h
b.
Pressurizer Heaters 2
2 2
3******
14 l
.h
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ka0 i
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i TABLE 3.3-3 (Continued)
TABLE NOTATION l
Trip function may be bypassed in this MODE vith RCS pressure belov 1800 psig.
Bypass shall be automatically removed when RCS pressure exceeds 1800 psig.
Trip function may be bypassed in this MODE vith RCS pressure belov 600 psig.
Bypass shall be automatically removed when RCS pressure exceeds 600 psig.
l One must be in SFAS Channels il or #3, the other must be in Channels
$2 or 64.
This instrumentation must be OPERABLE during CORE ALTERATIONS-or movement of irradiated fuel within the containment to meet the requirements of Tech. Spec 3.9.4.
All functional units may be bypassed for up to one minute when starting each Reactor Coolant Pump or Circulating Vater Pump.
When either Decay Heat Isolation Valve is open.
The-provisions of Specification 3.0.4 are not applicable.
l ACTION STATEMENTT ACTION 10 -
Vith the number of OPERABLE functional units one less than the
)
Total Number of Units, STARTUP and/or POVER OPERATION may l
proceed provided both of the following conditions are satisfied:
a.
The inoperable functional unit is placed in the tripped
[
condition within one hour.
For functional unit 4a the i
sequencer channel shall be placed in the tripped condition by physical removal of the sequencer module.-
l b.
The Minimum Units OPERABLE requirement is mets however, one additional functional unit may be bypassed for up to 2 l
hours for surveillance testing per Specification 4.3.2.1.1.
r ACTION 11 -
Vith any component in the Output Logic inoperable, trip the associated components within one hour or be in at least HOT STANDBY vithin 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 SHUTDOVN within the i
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
ACTION 12 -
Vith 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 vithin the i
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTD0VN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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l ACTION 13 -
a.
Vith less than the Minimum Units OPERABLE and reactor coolant pressure 1 438 psig, both Decay Heat Isolation
[
Valves-(DH11 and DR12) shall be verified closed.
.i DAVIS-BESSE, UNIT 1 3/4 3-12 Amendment No. 28, 37, 52, 797./M,159 j
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E TABLE 4.3-2 3
SAFETT FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5
N CHANNEL MODES IN VHICH g
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
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1.
INSTRUMENT STRINGS a.
Containment Radiation - High S
R M
1,2,3,4,65 l
b.
Containment Pressure - High S
R M(2) 1, 2, 3 c.
Containment Pressure - High-High 5
R M(2) 1, 2, 3 d.
RCS Pressure - Low S
R M
1,2,3 e.
RCS Pressure - Low-Lov S
R M
1, 2, 3 f.
'BVST Level - Low-Lov S
R M
1,2,3 c
2.
DUTPUT LOGIC U
a.
Incident Level 51: Containment Isolation S
R M
1,2,3,4,68 b.
Incident Level 52: High Pressure Injection and Starting Diesel Generators S
R M
I,2,3,4 c.
Incident Level 53: Lov Pressure Injection 5
R H
1, 2, 3, 4
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d.
Incident Level 84: Containment g,
Spray S
R M
1, 2, 3, 4 e
e.
Incident Level IS: Containment k
Sump Recirculation Permissive S
R M
1, 2, 3, 4 zo 3.
MANUAL ACTUATION t
w SFAS (Except Containment Spray NA NA M(1) 1,2,3,4,65 y
a.
g and Emergency Sump Recirculation) b.
Containment Spray NA NA M(1) 1, 2, 3
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4.
SEQUENCE LOGIC CHANNELS S
NA M
I,2.3,4 U
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1
o 4
l 0
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E-TABLE 4.3-2 (Continued) i.
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SAFETT FEATURES ACTUATION SYSTEM -INSTRtDfENTATION SURVEILIJW8CE REQUIRENENTS M
N M
1 4
j E
CEAMEL NODES IN WRICH CHANNEL CHANNEL FUNCTIONAL SURVEILIJWICE 1
4 FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED t
5.
INTERLOCK CHANNELS a.
Decay Beat Isolation Valve S
.R 1, 2, 3 b.
Pressurizer Beater S
R 1 -
3 ##
I-i 1
w 1 -
N
- See Specification 4.5.2.d.1 w
4 w
M TABt2 NOTATION 4
g (1) Manual actuation switches shall be tested at least once per 18 months during shutdown. All other l
g circuitry associated with manual safeguards actuation shalt receive a CHANNEL FUNCTIONAL TEST at g
least once per 31 days.
i' j
(2)
The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either vacuum or-
-j z
o, pressure to the appropriate side of the transmitter.
w The surveillance requirements of Section 4.9.4 apply during core alterations or movement of irradiated fuel within the containment.
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Uben either ;ecay Heat 'rciation
? Ivc i _. o mt.
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4.47 a
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