ML20086R301
| ML20086R301 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/17/1991 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086R304 | List: |
| References | |
| NUDOCS 9112310226 | |
| Download: ML20086R301 (10) | |
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UNITED $T ATES
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NUCLE AR REGULATORY COMMISSION 4
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l TOLEDO EDISON COMPANY CEP. 0 10R SERVICE COMPANY i
s THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET N0. 50-346 DAVIS.BESSE NUCLEAR POWER STATION, UNIT No. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. NPF-3 1.
The Nuclear Regulatory-Comission (the Commission) has found that:-
A.
The application for amendment by the Toledo Edison Company, Centerior Service Compa"y, and the Cleveland Electric illuminating Company (the licensees)datedAugust 21, 1989, as supplemented September 1, 1989, complies with the standards and requirements-of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regu-lations set forth in 10 CFR Chapter I; B.
-_The facility will operate'in conformity with the application, the provisions of the fct, 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 Cocission'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 i
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; 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:
-9112310226-911217 DR_ ADOCK.0500 6
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W (a) Technical Specifications.
The Technical Spe-ifications contained in Appendix A, as revised through kaendment No,167, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendnent is effective as of its date of issuance and shall be implemented not later than 45 days after issuance.
Y FOR THE NUCLEAR F.'GUL AhW COMMISSION
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IonB.Hopkins,Sr.ProjectManager J
j Project Directorate 111-3 Division of Reactor projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techot<;al Specifications-Date of issuance: Occember 17, 1901 1
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ATTAtliMENT TO LICENSE AMENDMENT NO. 167 4
FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following ') ages of the Appendix "A" Technical Specifications with the attached pr.ges.
T1e revised pages are identified by ainendnent nunber and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert IV IV 3/4 3-46 3/4 3-46
- 3/4 3-47 3/4 3-47
- 3/4 3-48 3/4 3 48 3/4 3-48a i
3/4 3-49 3/4 3-49 3/4 3-50 3/4 3-50 3/4 3-50a 3/4 6-23 3/4 6 23 B 3/8 3-3 B 3/4 3-3 B 3/4 6-4 B 3/4 6-4 E
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 1
3/4.0 AP PL I C AB I L I TY.............................................
3/ 4 0 1 j
3/4.1m REAC1.Vl?Y CONTROL SYSTEMS i
3.4.1.1 BORAT10N CONTROL Shutdown Margin........................................
3/4 1-1 t
B o ro n Di l u t i o n.........................................
3/ 4 1 - 3 i
Moderator Temperature Coef ficient.......................
3/4 1-4 Minimum Temperature for Cri tica11 ty....................
3/4 1-5 3/4.1.2 B0 RATION SYSTEMS Flow Paths - Shutdown..................................
3/4 1-6 Fl ow Pa ths - Opera ti ng.................................
3/4 1-7 Makeup Pump - Shutdown.................................
3/4 1-9 Makeup Pumps - Operating...............................
3/4 1-10 Decay Heat Removal Pump - Shutdown.....................
3/4 1-11 Boric Acid Pump - Shutdown.............................
3/4 1-12 Borid Acid Pumps --Operating...........................
3/4 1-13 Borated Water Sources - Shutdown.......................
3/4 1-14 Borated Water Sources - Operating......................
3/4 1-17 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height - Safety and Regulating Rod Groups........
3/41-19 Group Height - Axial Power Shaping Rod Group...........
3/4 1-21 Position Indicator Channel s............................
3/4 1-22 Rod Dro p T i me..........................................
3/ 4 1 - 2 4 i
Safety Rod Insertion Limit.............................
3/4 1-25 Regulating Rod Inscrtion Limits........................
3/4 1 Ro d P ro g ra m............................................
3 / 4 1 - 3 0 X enon Rea c t i vi ty.......................................
3/ 4 1 - 33 Axial Power Shaping Rod Insertion Limits...............
3/4 1-34 l
DAVIS-BESSE, UNIT L III-Amendment No. 38 l
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INDEX LIMITIN3 C_0NDIT,10NS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3]4.2 POWER DISTRIBUTION LIMITS 3/4. 2.1 AX1 AL POW ER I MBAL ANC E....................................
3/ 4 2-1 3/4.2.2 NUCLEAR HEAT FLUX HOT CHANNEL FACTOR - T................. 3/4 2-5 g
N 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H******* 3/4 2*7 3/4.2.4 QUADRANT POWER TILT......................................
3/4 2-9 3/4.2.5 DNB PARAMET E RS...........................................
3/ 4 2-13 3/4.3 INSTRUMENTATION 3/4. 3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION................
3/4 3-1 3/4.3.2 SAFETY SYSTEM INSTRUMENTATION Safety Features Actuation System.........................
3/4 3-9 Steam and Feedwater Rupture Control System...............
3/4 3 23 Anti ci patory Reac tor Trip Sys tem.........................
3/4 3-30a 3/4.3.3 MONITORING INSTRUMENTATION Radia tion Moni tori ng Instrumenta tion.....................
3/4 3-31 Incore Detectors.........................................
3/4 3-35 Seismic Instrumentation..................................
3/4 3-37 Meteorological Instrumentation...........................
3/4 3-40 Remote Shutdown Ins trumentation.........................
3/4 3 43 Pos t-Accident Moni toring Ins trumentation.................
3/4 3-46 l
Fi re Detection Ins trumentation.,,.........................
3/4 3-52 Radioactive Liquid Effluent Monitoring Instrumentation...
3/4 3-57 Radioactive Gaseous Effluent Monitoring Instrumentation..
3/4 3-62 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 -COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power 0peration..............................
3/ 4 4-1 Shutdown and Hot Standby.................................
3/4.4-2 3/4.4.2 S AF El f V ALVES - SHUTD0WN.................................
3/4 4-3 3/4.4.3 SAFETY VALVES AND PILOT OPERATED RELIEF VALVE -
0 P E RAT I N G..............................................
3 / 4 4 - 4
. DAVIS-BESSE, UNIT 1 IV Amendment No. EB,Ef>,J3A,735,167 l
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1JSTRUMENTAT10N POST-ACCIDENT MONIT0llNG INSTRuf?ENTATION LIM 111NG CONDITION FOR OPERA 110N
- 3. J. 3. 6 The post-accident monitoring instrumentation channel; shown in Table 3.3-10 shall be OPERABLE.
APPLICABILIH: MODES 1. 2 and 3.
ACTION:
a.
With the number of OPERABLE post-accident monitoring instrumentation channels less than the Minimum Channels OPERABLE required by Table 3.3-10. either restore the inoperable channel to OPERABLE status within 30 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 />.
b.
The provisions of Specification 3.0.4 are not applicable.
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i SlJRVEILLANCE REQUIREf1ENTS 4.3.3.6 Each post-accident monitoring instrumentation channel shall be F
demnstrated OPERABLE by performance of the CHANNEL CHECK and CliANNEL CAllBRATION operations at the frequencies shown in Table 4.3-10.
F DAVIS-BESSE. UNIT 1 3/4 3-46 Amendnent No. 167 4
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TABLE 4.3-6 M
M REMOTE SHITEDOVN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS T
E.
e-CHANNEL CHANNEL
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INSTRUMENT CHECK CALIBRATION '
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Reactor Trip Breaker Indication M
N.A.
2.
Reactor Coolant Temperature-Hot Legs M
R 3.
Reactor Coolant System Pressare M
R 4.
Pressurizer Level M
R Y
5.
Steam Generator Outlet Steam Pressure M
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Steam Generator Startup Rang 2 b-rel M
R 7.
Coctrol Rod Position Switches M
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- POST-ACCIDE?iT M0!i1TORIfiG ItiSTRUMEfiTATI0tt G
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IriSTRU5tE?iT OPERABt"
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SG Outlet Steam Pressure 1/ Steam Generator Eq 2.
RC Loop Outlet Temperature 2/ Loop 3.
RC Loop Pressure 2/ Loop 4.
Pressurizer Level 2
5.
SG Startup Range Level 2/ Steam Senarator 6.
Containment Vessel Post-Accident Radiation 2
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High Pressure Injection Flow 1/ Channel y
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Low Pressure Injection (DHR) Flow 1/ Channel 9.
Auxiliary Feedwater Flow Rate 2/ Steam Generator 10.
RC System Subcooling Margin Monitor.
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PORY Position Indicator.
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i PORV Block Valve Position Indicator 1
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Pressurizer Safety Valve Position Indicator 1/ Valve f
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BWST Level 3
- 15. Containment tiormal Sump Level 1
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Containment Wide Range Water Level I
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Containment: Wide Range Pressure 1
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Reac or Coolant Hot Leg Level. (Wide Range) 1 4
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POST-ACCIDEi1T M0ii1 TORII 4G IfiSTRUMETITATIO!i SURVEILLAfiCE REQUIREMEtiTS Ga CHAtifiEL CHAtitiEL G
CHECK CALIBRATION
,M INS 1.UMENT M
R E
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SG Outlet Steam Pressure Z
M R
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RC Loop Outlet Temperature m
M R
3.
RC Loop Pressure M
R 4.
Pressurizer Level M
R S.
SG Startup Range Level b
6.
Containment Vessel Post-Accident Radiation M
R M
R 7.
High Pressure Injection Flow 8.
Low Pressure Injection (DHR) Flow M
R M
R 9.
Auxiliary Feedwater Flow Rate I
M R
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RC System Subcooling Margin Monitor M
R 11.
PORY Positien Indicator E
M R
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PORV Block Valve Position Indicator E
M R
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Pressurizer Safety Valve Position Indicator
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BWST Level
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Containment tiormal Sump Level b
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Containment Wide Range Water Level 5
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POST-ACCIDENT MONITORING INSTRUi4ENTATIO!1 SURVEILLANCE REQUIREMENTS u,
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Containment Wide Range Pressure M
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Incore Thermocouples M
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C0t4TAINMEt4T SYSTEMS 314.6.4 COMBUSTlBLE GAS C0_t4 TROL HYDROGEN At4ALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.
APPL,1CABILITY: MODES 1 and 2.
ACTION:
With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STAT 4DBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLAt4CE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 31 days by performance of a CHANNEL CHECK.
4.6.4.2 Each hydrogen analyzer shall be demonstrated OPERABLE at least i'
once per 92 days on a STAGGERED TEST BASIS by performing a CHAT 4NEL CALIBRATION using sample gases containing:
a.
Zero volume percent hydrogen, balance nitrogen, and b.
2.5 + 0.5 volume percent hydrogen, balance nitrogen.
2 DAVIS-BESSE, UNIT 1 3/4 6-23 Amendment No.167
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. DELETED DAVIS-BESSE, UNIT 1 3/4 6-24 Amendment No. 43, 66
3/4.3 INST _RUMENTATION BASES REMOTE SHUTDEN INSTRUMENTATION (Continued)
HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost.
. 31 4. 3. 3._6 POST-ACCIDENT HONITORINC INSTRUMENTATION l
The OPERABILITY of the post-accident monitoring instrumentation ensures j
that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.
The containment Hydrogen Analyzers, although they are considered part of the plant post-accident monitoring instrumentation, have their OPERABILITY requirements located in Specification 3/4.6.4.1, Hydrogen Analyzers.
3/4.3.3.7 CHLORINE DETECTION SYSTEMS - Deleted 3/4.3.3.8 FIRE DETECTION INSTRUMENTATION Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
Prompt detection of fires will ieduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. With the fire detector (s),
local panel alarms, and connecting circuitry OPERABLE, the establishment of frequent file patrols to inspect local fire panel (s) will provide the required fire detection capability.
DAVIS-BESSE, UNIT 1 B 3/4 3-3 Amendment No. 9,ED EE JM,154,167
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CONTAINMENT SYSTEMS 3
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irumage rate are consistent with ti;e issumptions used in the safety analyses.
ik rate surveillance requiremects assure that the leakage assumed for the during the recirculation phase will not be exceeded, n
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.ti.6.2.2 CONTAINMENT COOLING SYSTEM N
le The OPERABILITY of the containment cooling system ensures that 1) the containment air tenperature will be maintained within limits during normal c?ar6 tion, and 2) adequate heat removal crvacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
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3/4.6.3 CONTAINMENT ISOLATION VAL _V_E_S_
The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the eveat of a release of radioactive material to the containment atmospt".re or pressurization of the ;ont_
ment.
Containment isolation within the regttired time limits i
specified end as that the release of radioactive material to the environment
,jwill be consistent with the assumptions used in the analyses for a LOCA.
I Containment isolation valves and their required isolation times are addressed in the USAR. The opening of a closed inoperable containment isolation valve on i
I an intermittent basis during plant operation is permitted under administrative control.
Opcrating procedures identify those valves which may be opened under administrative control as weil as the safety precautions which must be taken when opening valves u '
such controls.
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l DAVIS-BESSE, IINIT 1 8 3/4 6-3 Amendment No. 13E, 147 hyf
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4 CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the Hydrogen Analyzers, Containment Hydro.wn Dilution System. and Hydrogen Purge System ensures that this equipe nt will be available to maintain the maximum hydrogen concentration *..ithin the containment vessel at or below three volume percent following a LOCA.
The two redundant Hydrogen Analyzers determine the content of hydro-g.
within the containment vessel.
The Hydrogen Analyzers, although they J
na, their OPERABILITY requirements in this Specification, are considered part of the post-accident monitoring instrumentation of 5pecification 3/4.3.3.6, Post-Accident Monitoring Instrumentation.
1 The Containment Hydrogen Dilution (CHD) System consists of two full capacity, redundant, rotary, positive displacement type blowers to supply L
air to the containment.
The CHD System controls the hydrogen concentra-tion by-the addition of air to the containment vessel, resulting in a pressurization of the containment and suppression of the hydrogen volure fraction.
The Containment Hydrogen Purge System Filter Unit functions ar. a backup to the CHD System and is designed to release air from the con-tainment atmosphere through a HEPA filter and charcoal filter prior to discharge to the station vent.
3/4.6.5 SHIELD BUILDING 3/4. 6. 5.1 EMERGENCY VL1T!LATION SYSTEM
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The OPERAB!LITY of the eTergency ventilation syst.
ensures that containmcnt vessel leakage occurring during LOCA conditions into the annulus will be filtend through the HEPA filters and charcoal adsorber trains prior to dis'.Nrge to the atmosphere. This requirement is neces-scry to meet the assumptions used in the safety analyres and limit the sit. boundary ridiation doses to within the limits of 10 CFR 100 during LOCA conditions.
T DAVIS-BESSE, boIT 1 B 3/4 6-4 Amendment No. 46,167