ML20041E115
| ML20041E115 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/26/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Toledo Edison Co |
| Shared Package | |
| ML20041E117 | List: |
| References | |
| NPF-03-A-043 NUDOCS 8203100161 | |
| Download: ML20041E115 (9) | |
Text
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b UNITED STATES e
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NUCLEAR REGULATORY COMMISSION y".
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,j WASHINGTON, D. C. 20066 THE TOLEDO EDISON COMPANY N...+#
AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-3 1.
The Nuclear Regulatory Connission (the Comission) has found that:
A.
The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated February 23, 1982, 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Connission'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 CPR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
e203100161 820226 PDR ADOCK 05000346 P
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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:
Revise paragraph 2.C.(2) to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the license. The Toledo Edison Company 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 COMMISSION
)
Jo n F. Stolz, Chief 0 erating Reactors Branch #4 ivision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
Februa ry 26, 1982
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ATTACHMENT TO LICENSE AMENDMENT NO.43 FACILITY OPERATING LICENSE NO. NPF-3
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DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications 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 maintain document completeness.
Pages 3/4 3-7 3/4 3-8 3/4 3-21 3/4 3-30 3/4 6-24 3/4 6-29 3/4 7-5
i TABLE 4.3-1
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v En REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS U
M CHANNEL MODES IN WHICH E
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
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1.
Manual Reactor Trip N.A.
M.A.
S/U(1)
N.A.
2.
High Flux 5
D(2), and Q(7)
M 1, 2 3.
RC High Temperature S
R M
1, 2 4.
Flux - aFlux - Flow S(4)
M(3) and Q(7,8)
M 1, 2 5.
RC Low Pressure S
R***
M 1, 2 6.
RC High Pressure S
R***
M 1, 2 w
7.
RC Pressure-Temperature S
R M
1, 2 8.
High Flux / Number of Reactor "4
Coolant Pumps On S
R M
1, 2 7.
Contalrunent High Pressure.
S R
M 1, 2
- 10. Intennedtate Range, Neutron Flux and Rate S
R(7)
S/U(5)(1) 1, 2 and*
p j
- 11. Source Range, Meutron Flux i
g and Rate 5
R(7)
MandS/U(1)(5) 2, 3, 4 and 5
- 12. Control Rod Drive Trip Breakers M.A.
N.A.
M and S/U(1) 1, 2 and*
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- 13. Reactor Trip Module Logic M.A.
N.A.
M 1, 2 and*
- 14. Shutdown Bypass High Pressure S
R M
2**,3**,4**,5**
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TABLE 4.~-1 (Continued)
NOTATION If not performed in previous 7 days.
(1)
Heat balance only, above 15% of RATED THERMAL POWER.
(2)
WhenTHERMALPOWER[TP]isabove30%ofRATEDTHERMAL (3)
POWER [RTP), compare out-of-core measured AXIAL POWER IMBALANCE [ API ] to incore measured AXIAL POWER IMBALANCE
[APl]. Recalibrate if:
y
[ API,-API]3.3.5%
g AX1AL POWER IMBALANCE and loop flow indications only.
(4)
Verify at least one decade overlap if not verified in previous (5) 7 days.
Each train tested every other month.
(6)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Flow rate measurement sensors may be excluded from CHANNEL (8)
CALIBRATION. However, each flow measurement sensor shall be calibrated at least once per 18 months.'***
With any control rod drive trip breaker closed.
When Shutdown Bypass is actuated.
due in March 1982 delayed
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Eighteen-month surveillance test until March 31, 1982.
DAVIS.-BESSE, UNIT 1 3/4 3-8 Amendment No. 43
Tant.E 4.3-2 c:
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5AFETY FEAltNtES _ACitMil0N SYSTEM INSTRtiMINIATION SHRVEILLANCE RET)lllRIMitiTS EllANNEL MODES IN milch CHANNEL CilAMllEL FilfN.110NAL SilRVilllANCE g
Fl#ICTIONAL_tNIE CHI C F.
cat li;HATl0N TEST R[r)UIRto j
1.
INSTiltMENT STRINGS a.
Containment Radiation - liigh 5
R*
M l.2.3.4,6f I
b.
Containment Pressure - High 5
R M(2) 1, 2, 3 i
c.
Containment Pressure - liigh-Illqh 5
R M(2) 1, 2, 3 i
d.
RCS Pressure - Low 5
R H
1, 2, 3 e.
RCS Pressure - Low-tow 5
R H
1, 2, 3 f.
BWST Level - Low -Low 5
R M
1, 2, 3 l
2.
OUTMlf LOGIC a.
Incident level #I: Containment
{
Isolation 5
R M
1,2,3,4,67 b.
Incident Level 82: High Pressure
{
Injection and Starting Diesel Generators 5
a M
1, 2, 3, 4 c.
Incident Level #3: Law Pressiere Injection 5
R H
1, 2, 3, 4 y
d..
Incident Level #4: Containment Spray 5
R H
1, 2, 3, 4 g
e.
Incident Level #5: Containment i
Sunp Recirculation Permissive 5
R H
1, 2, 3, 4 g
3.
MAIIUAL ACTUATION g.
a.
5FAS (Except Containment Spray NR NA M(1) 1,2,3,4,6#
aM Emergency Sung Recirculation) b.
Containment Spray N4 M
M(1) 1, 2, 3 4.
SEQUENCE LOGIC CllANNELS 5
114 M
1,2,3,4 g
- Eighteen-month surveillance test due in March 1982 delayed until March 31, 1982.
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- 5 Y'
8:
f5 4
a IABLE 4. 3-2 SAFETY FEAftlRES ACTilAil0lt SYSTEM INSTRUMENTAil0N SINtVEILLANCE _RglR[ MINTS i
CilANNIL MODES IN WICil CilANNEL CilANNFL FUNLil0NAL SURVEILLANCE N.Tl0RAL Wii
{!H ((,,
CAL _IMHAil0N, iEST REQUIRED a
5.
Initat0CK CnAmEts 4
y l
g a.
secar eat isolation valve 5
m a
n i, 2, 3, e, 5 b.
presserfrer Heater 5
N 3,4,5
' **5ee Specification 4.5.2.d.1 TA8tC IIOTATIfMI o
(1) Manual actuettua switches sivell be tested at least once per 10 months.during shutdown. All other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCil0NAL r+
g 1[5T at least once per 31 days.
N (2) The CH4fgqEL FUNCTIONAL TEST shall faclude esercising the transmitter by applying either vacuum or 7
pressure to the appropriate side of the transmitter.
The prowlsions of Section 3.0.3 are not appilcable for the.first test of each channel following the first refueling outage.
i The survelliance requirements of Section 4.9.4 apply during core alterations or movement of m
1rradiated fuel within the containment.
TABLE 3.3-13 STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM RESPONSE TIMES ACTUATED EQUIPMENT _
RESPONSE TIME IN SECONDS 4
1.
Auxiliary Feed Pump 10 2.
Main Steam Isolation Valves 1 6 3.
Main Feedwater Valves a.
Main Control
<8 b.
Startup Control 5 13 c.
Stop Valve 1 16 4.
Turbine Stop Valves 1 6 DAVIS-BESSE, UNIT 1 3/4 3-29
g TABLE 4.3-11
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STEAM AND FEEDWATER RUPTURE CONTROL SYSTEM
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INSTRUMENTATION SURVEILLANCE REQUIREMENTS GM
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c CHANNEL CHANNEL CHANNEL FUNCTIONAL FUNCTIONAL UNIT CHECK CALIBRATION TEST
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1.
Instrument Channel a.
Steam Line Pressure - Low S
R M
b.
Steam Generator Level - Low S
R*
M
]
c.
R M
Differential Pressure-High d.
Reactor Coolant Pumps-Loss of S
R M
2.
Manual Actuation NA NA R*
i 3"
to y
- Eighteen-month surveillance test due in March 1982 delayed until g
March 31,1982.
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CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDR 0 GEN ANALYZERS i
LIMITING CONDITION FOR OPERATION j
3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTION:
With one hydrogen ana.yzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days 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 />.
SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once cer 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:
a.
Zero volume percent hydrogen, balance nitrogen, and b.
2.5 + 0.5 volume percent hydrogen, balance nitrogen.
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DAVIS-BESSE, UNIT 1 3/4 6 23 l
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CONTAINMENT SYSTEMS CONTAINMENT RECIRCULATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment recirculation systems shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
With one containment recirculation system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at ieast 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 />.
SURVEILLANCE REQUIREMENTS 4.6.4.2 Each containment recirculation system shall be demonstrated OPERABLE:
a.
At least once per 92 days on a STAGGERED TEST BASIS by:
1.
Verifying that the system can be started on operator action in the control room, and 2.
Verifying that the system operates for at least 15 minutes.
b.
At least once per 18 months by verifying a system flow rate of at least 7,200 cfm.*
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- Eighteen-month surveillance test due in March 1982 delayed until March 31,1982.
i DAVIS-BESSE, UNIT 1 3/4 6-24 Amendment No. 43
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
Verifying that the system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.5.c and C.S.d of Regula-tory Guide 1.52, Revision 1. July 1976, and the system flow rate is 8,000 cfm 110%.
3.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1. July 1976, meets the laboratory testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52, Revision 1. July 1976.*
4.
Verifying a system flow rate of 8,000 cfm 110% during system operation when tested in accoNance with ANSI M510-1975.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verify-c.
ing within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory testing criteria of Regula-tory Position C.6.a of Regulatory Guide 1.52, Revision 1, July 1976.*
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the system at a flow rate of 8,000 cfm i 10%.
2.
Verifying that the system starts automatically on any containment isolation test signal.**
1 3.
Verifying that the filter cooling bypass valves can be manually opened. **
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- Representative samples of used activated carbon from the EVS shall pass the laboratory test given in Table 3 for an activated carbon bed depth of 2 inches (i.e., the two 2 inch filter beds in series shall be tested per Test 5.b in Table 2 at a relative humidity of 70% for a methyl iodide penetration of less than 1%). The pre-and post-loading sweep medium temperature shall be 80'C for Test 5.b of Table 2. Regulatory Guide 1.52, Revision 1. July 1976.
- Eighteen-month surveillanca test due in March 1982 delayed until March 31,1982.
DAVIS-BESSE,im T 1 3/4 6,29 Amendment No. 43
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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i 4.
Verifying that each system produces a negative pressure 1
of > 0.25 inches W.G. in the annulus within 4 seconds after the fan attains a flow rate of 8000 cfm + 10%.
This test is to be performed with the flow patE established prior to starting the EVS far., and the other dampers associated with the negative pressure boundary closed.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove > 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 8000 cfm i 10%.
f.
After each complete. or partial replacement of a charcoal adsorber bank by serifying that the charcoal adsorbers remove
> 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 8000 cfm 110%.
DAVIS-BESSE, UNIT 1 3/4 6-30 Amendment No. 3 1
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
The Auxiliary Feed Pump Turbine Steam Generator Level Control System shall be demonstrated OPERABLE by perfomance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.
d.
The Auxiliary Feed Pump Turbine Speed Switch, Auxiliary Feed Pump Suction Pressure Interlocks, and Auxiliary Feed Pump Turbine Inlet Steam Pressure Interlocks shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.*
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- Eighteen-month surveillance test for AF Pump Speed Switch due in llarch 1982 delayed until March 31, 1982.
DAVIS-BESSE, UNIT 1 3/4 7-5 Amendment No. 43
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage facilities (condensate Morage tank and deaerator storage tank) shall be OPERABLE with a minimum contained volume of 250,000 gallons of water.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
With the condensate storage facilities inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:
a.
Restore the condensate storage facilities to OPERABLE status 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 />, or b.
Demonstrate the OPERABILITY of the service water system as a backup supply to the auxiliary feedwater system and restore the condensate storage facilities to OPERABLE status within 7 days 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 />.
SURVEILLANCE REQUIREMENTS i
i 4.7.1.3.1 The condensate storage facilities shall be demonstrated
(
OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the contained water volume to be within its limits when the facilities are the supply source for the auxiliary feedwater pumps.
4.7.1.3.2 The service water system shall be demonstrated OPERABLE at l
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that at least one service water loop is operating and that the service water loop-auxiliary feedwater system isolation valves are either open or OPERABLE whenever the service water system is the supply source for the auxiliary feedwater pumps.
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DAVIS-BESSE, UNIT 1 3/4 7-6 l