ML20215G102
| ML20215G102 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 09/30/1986 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 2196K, NUDOCS 8610170071 | |
| Download: ML20215G102 (9) | |
Text
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) Comm:nviealth Edison
_ - 72 West Adams Street, Chicago, Ilhnois Address Reply to: Post Office Box 767 Chicago, lihnois 60690 - 0767 September 30, 1986 Mr. Harold R.~Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulatory Washington, DC. 20555
Subject:
Braidwood Station Unit 1 Interim Technical Specifications to 5% Power - Test Deferrals NRC Docket No. 50-456
Reference:
September 19, 1986 D.H.
Smith letter to H.R.
Denton
Dear Mr. Denton:
Enclosed for your review are interim Technical Specifications that are to be applied to the Final Draft in support of Deferral of Limited Aspects of the Pre-Operational Test Program submittal as referenced.
These interim Technical Specifications are intended to support operation of Braidwcod Station Unit 1 up to 5%
power.
These interim Technical Specifications are closely modeled after those that were-granted for Byron Station Unit 1 for similar reasons.
Should you have any questions concerning this matter please contact this office.
One signed original and fifteen copies of this letter and enclosure are provided for your review.
Very truly yours, h
A. D. Miosi Nuclear Licensing Administrator
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J.
Stevens 2196K 5610170071 560930
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FIN L yg1 INSTRUMENTATION l
3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MG 3 ! SE LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation I
chanriels and interlocks shown in Table 3.3-3 shall be OPERABLE with the % Trip Setpoints set consistent with the values shown in the Trip Setpoint.cogin of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
APPLICABILITY:
As shown in Table 3.3-3.
1 ACTION:
With an ESFAS Instrumentation or Interlock Trip Setpoint less con-a.
3 servative than the value shown in the Trip Setpoint column but more l
conservative than the value shown in the Allowable Value column of Table 3.3-4 adjust the Setpoint consistent with the Trip Setpoint' value.
b.
With an.'E5FAS Instrumentation or Interlock Trip Setpoint less con-servative than the value shown in the Allowable Values column of Table 3.3-4, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4 and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirements of Tabis 3.3-3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
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Equation 2.2-1 Z + RE + SE < TA Where:
Z = The value from Column 2 of Table 3.3-4 for the affected t
- channel, RE = The "as measured" value (in percent span) of rack error for the affected channel, 1
SE = Either the "as measured" value (in percent span) of the sensor errer, or the value for Column SE (Sensor E"rbr) of Table 2.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.2-4 for the affected channel.
With an E5FAS instrumentation channel or interlock inoperable, take the c.
ACTION shown in Table 3.3-3.
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3/4.3.3 MONITORING INSTRUMENTATION AUG 191986 RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1+The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-6 shall be OFERABLE with their Alarm / Trip Setpoints within the specified limits.
APPLICABILITY:
As shown in Table 3.3-6.
ACTION:
a.
With a radiation monitoring channel Alarm / Trip Setpoint for plant operatic.ns exceeding the value shown in Table 3.3-6, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.
b.
With one or more radiation monitoring channels for plant operations inoperable, take the ACTION shown in Table 3.3-6.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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e SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATICN and DIGITAL CHANNEL OPERATICNAL TEST for the MODES and at the frequencies shown in Table 4.3-3.
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FINAL DRAT TABLE NOTATIONS AUG 19ISB6
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"With new fuel or irradiated fuel in the fuel storage areas or fuel building.
- Trip Setpoint is to be established such that the actual submersion dose rate would not exceed 10 mR/hr in the containment building.
For containment purge or vent the Setpoint value may be increased up to twice the maximum concentra-tion activity in the containment determined by the sample analysis performed prior to each release in accordance with Table 4.11-2 provided the value does not exceed 10% of the equivalent limits of Specification 3.ll.2.1.a in accord-ance with the methodology and parameters in the 00CM.
ACTION STATEMENTS ACTION 26 With less than the Minimum Channels OPERARLE requirement, operation may continue provided the containment purge valves are maintained closed.
ACTION 27 With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, within I hour isolate the Control Room Ventilation System and initiate operation of the Control Room Make-up System.
ACTION 28 Must satisfy the ACTION requirement for Specification 3.4.6.1.
ACTION 29 With the number of OPERABLE channels one less than the Minimum 4
Channels OPERABLE requirement, ACTION a. of Specification 3.9.12 must be satisfied. With both channels inopereble, provide an appropriate portable continuous monitor with the same Alarm Set-point in the fuel' pool area with one Fuel Handling Buf1 ding Exhaust filter plenum in o of Specification 3.9.12.* peration.
Otherwise satisfy ACTION b.
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INSTRUMENTATION CHLORINE DETECTION INSTRUMENTATION AUG 19 $$g LIMITING CONDITION FOR OPERATION 3.3.3.11+ Two independent chlorine detection instrumentation channel,s, with their Alarm / Trip setpoints adjusted to actuata at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE.
APPLICABILITY:
All MODES.
ACTION:
a.
With one chlorine detection instrumentation channel inoperable, re-store.the inoperable instrumentation channel to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation.
b.
With both chlorine detection instrumentation channels inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation.
c.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RECUIREMENTS 4.3.3.11 Each chlorine detection instrumentation channel shall be demonstrated OPERABLE by performance of a functional test in accordance with the manufac-turer's recommendations at least once per 31 days and a CHANNEL CALIBRATION at laast once per 12 months.
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SRAICWOOD - UNITS 1 & 2 3/4 3-79
FK DiMFT PLANT SYSTEMS AUG 191996 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM LIMITING CONDITICN FOR OPERATION 3.7.6 Two independent Control Room Ventilation Systems shall be OPERABLE.
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APPLICABILITY:
All MODES.
ACTION:
MODE 5 1, 2, 3 and 4:
With one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANOBY 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 />.
MODES 5 and 6:
a.
With one Control Room Ventilation System inoperable, restore the inoperable system to OPERABLE status within 7 days or initiate and maintain operation of the remaining OPERABLE Control Room Ventilation System in the makeup mode, b.
With both Control Room Ventilation Systems inoperable, or with the OPERABLE Control Room Ventilation System, required to be in the makeup mode by ACTION a. not capable.of being powered by an OPERABLE emer-gency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.
SURVEILLANCE REOUIREMENTS
- 4. 7. 6 Each Control Room Ventilation System shall be demonstrated OPERABLE:
a.
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 that the control rocm air tamperature is less than or equal to 90*F; b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the Emergency Makeup System HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; anc flow through the recirculation charcoal adsorber for 15 minutes, c.
At least once per 18 months or (1) af ter any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the Emergency Makeup System filter plenum by:
1)
Verifying that the cleanup system satisfies the in place penetra-tion testing acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a C.S.e. and C.S.d of Regulatery Geide 1.52. Revision 2, Mar:h 1978, and the system fl o rate is 6000 cfm : 10% for tne Emergency Maxeue System; 9p he.,, l le, pe b in %) uNeul% en gc k d..
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BRAICWOOD - UNI 5 1 & 2 3/4 7-14
HNAL UMH PLANT SYSTEFS g igtges SURVEILLANCE REQUIREMENTS (Continued) 2)
Verifying, within 31 days af ter removal, that a laboratory analysis of a representative carbon sample from the Emergency Makeup System obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175% when tested at a tempera-ture of 30*C and a relative humidity of 70%; and 3) verifying a system flow rate of 6000 cfm + 10% for the Emergency Makeup System and 49,500 cfm 110% for the Recirculation System when tested in accordance with ANSI N510-1980, d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of Emergency Makeup System operation by verify-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 2, March 1978,
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meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175% when tested at a temperature of 30*C and a relative humidity of 70%;
e.
At least once per 18 months by:
1)
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6.0 inches Water Gauge while operating the Emergency Makeup System at a flow rata of 6000 cfm 10%,
2)
Verifying that on a Safety Injection or High Radiation-Control Room Outside Air Intake test signal, the system aut:matically switches into a makaup mode of contYol room ventilation with flow *.hrough the Emergency Makeup System HEPA filters and charcoal adsorber banks and the recirculation charcoal adsorber; 3)v* Verifying that the Emergency Makeup System maintains the control room at a positive nominal pressure of greater than or equal to 1/8 inch Water Gauge relative to ambient pressure in areas adjacant to the control room area when operating an Emergency Makeup System at a flowrate of 6,000 cfm 110% and the recircula-tion charcoal adsorber at a flowrate of 49,500 cfm 10%.
4)
Verifying that the heaters dissipate 27.2 2 2.7 kW when tested in accorcance witn ANSI N510-1980.
5)# Verifying that the Emergency Makeup System maintains the Upcer Cable Spreading Area at a positive nominal pressure of greater than or equal to 0.02 inches Water Gauge relative to the ambient pressure in areas adjacent to the upper cable spreading ares (except for adjacent control roem areas pressurized as seccifie::
above) when operating an Emergency Makeup Systra at a ficw rata of 6,000 cfm : IC*. and the recirculation charcoal acscreer at a flowrate of 49,500 cfm t 10%.
BRAIDw000 - UNITS 1 & 2 3/4 7-15
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w PLANT SYSTEMS AUG 191805 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST F'ILTER PLENUM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7 Three independent non-accessible area exharst filter plenums (50%
capacity each) shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With one non-accessible area exhaust filter plenum inoperable, restore the inoperable plenum to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hcurs and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS a.7.7 Each non-accessible area exhaust filter plenum shall be demonstrated OPERA 8LE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that operation occurs for at least 15 minutes; b.
At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communi-cating with the exhaust filter plenum by:
1)
Verifying that the exhaust filter plenum satisfies the in placa penetration and bypass leakage tasting acceptance criteria of less than 1% when using the test procedure guidanca in Regulatory Positions C.5.s, C.5.c and C.5.d of Regulatory Guide 1.52, Revi-sion 2, March 1978, and the flow rate is 66,900 cfm 10% for the train and 22,300 cfm 11C% per bank; 2)
Verifying, within 31 days after removal, that a laborstery analysis of a representative carbon sample from each bank of adsorbers of the train obtained in accordance with Regulatery Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1975, meets the, laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1975, for methyl icacice penetration of iess than 1% when tested at the temperature of 30*C and a relative humioity of 70%;
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BRA:0WCCO - UNITS 1 & 2 3/4 7-17
REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS AUE 19 4
!IMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:
The personnel hatch should have a minimum of one door closed at any a.
one time and the equipment hatch shall be in place and held by a minimum of four bolts or the equipment hatch removed pursuant to Surveillance Requirement 4.9.4.2, b.
A minimum of one door in the personnel emergency exit hatch is closed, and Each penetration providing direct access from the containment c.
atmosphere to the outside atmosphere shall be either:
1)
Closed by an isolation valve, blind flange, or manual valve, or 2)
Capable of being closed by an OPERABLE automatic corytainment purge isolation valve.
APPL.ICABILITY:
Ouring CORE ALTERATIONS or movement of irradiated fual within the containment.
ACTION':
With the requirements of the above specification not satisfied, immediataly suspend all operations involving CORE ALTERATICNS or movement of irradiatad fuel in the containment building.
SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment building penetrations shall be deternined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge isolation valve within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CDP.E ALTERATIONS or movement of irradiated fuel in the containment bulleing by:
Verifying the penetraticns are in their closed / isolated condition, a.
or b.
Testing the containment purge isolation valves per the applicsole portions of Specification 4.6.3.2.
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