ML20064K794
| ML20064K794 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/15/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064K796 | List: |
| References | |
| NUDOCS 9403230286 | |
| Download: ML20064K794 (24) | |
Text
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S UNI' LED STATES 5'
'i NUCLEAR REGULATORY COMMISSION k..... jf WA$HINGTON, D.C. 20555 4 001 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY QELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR-44 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated November 1,1993 as supplemented on January 26, 1994 and February 18, 1994, 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 (1) that the activities authorized by 1
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 or safety of the public; and 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. DPR-44 is hereby amended to read as follows:
9403230286 940315 e
PDR ADOCK 05000277R P
....(2) Iechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.184, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented upon completion of modification 5281.
FOR THE NUCLEAR REGULATORY COMMISSION (br o Y YCl DG Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 15, 1994 1
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ATTACHMENT TO LICENSE AMENDMENT N0'.184' a
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FACILITY' OPERATING-LICENSE NO.-DPR--44
. DOCKET NO. 50-277 o
Replace the'following pages of the Appendix A Technical Specifications with-the' enclosed pages. The revised areas are indicated by marginal lines ~
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Remove
' Insert
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59 59 75 75 84 84 93 93 97.
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233a 233a 234 234 235-235 l
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Unit 2 PBAPS LIMITING COEDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.2.D.
Radiation Monitorina 4.2.D.
Radiation Monitorina Systems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions 1.
Reactor Buildina Isolation 1.
Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-t Table 3.2.D.
brated and checked as indi-cated in Table 4.2.D.
2.
Main Control Room System logic shall be The limiting conditions for functionally tested as operation are given in indicated in Table 4.2.D.
Table 3.2.D.
2.
Main Control Room E.
Drvwell Leak DetectioD Instrumentation shall be The limiting conditions of functionally tested, operation for the instru-calibrated and checked as mentation that monitors indicated in Table 4.2.0.
drywell leak detection are given in Section 3.6.C, E.
Drvwell Leak Detection
" Coolant Leakage".
Instrumentation shall be calibrated and checked as indicated in table 4.2.E.
t Amendment ho. 102, 160.184
s.
- ~
Unit 2 PBAPS TABLE 3.2.D RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No.
of Operable Instrument No. of Instrument Channels per Channels Provided Action Trip System Trip Function Trip Level Setting by Design (2)
(1)
~~ 2 Refuel Area Exhaust Upscale, <16 mr/hr 4 Inst. C.innels A or B Monitor 2
Reactor Building Upscale, <16 mr/hr 4 Inst. Channels B
Exhaust Monitors 1
(3)
Main Stack Monitor Upscale, $10' cps 2 Inst. Channels C
s, l 2
(4)
Main Control Room Upscale, <400 cpm 4 Inst. Channels D
u.
Notes for Table 3.2.D
- 1. Whenever the systems are required to be operable, the specified number of instrument channels shall be operable or placed in the tripped condition.
If this cannot be met, the indicated action shall be taken.
- 2. Action 8g A.
Cease operation of the refueling equipment.
g B.
Isolate secondary containment and start the standby gas treatment system.
=
C. Cease purging of primary containment, and close vent and purge valves greater than 2 inches in diameter.
?l D. As described in LCO 3.11.A.5 z
- 3. The trip function is required to be operable only when the containment is purging through the SGTS and containment integrity is required.
If both radiation monitors are out of service, g
action shall be taken as indicated in Note 2, (C)..
m
- 4. The trip function is required to be operable whenever secondary containment -is required on T
either unit.
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Unit 2 ^
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TABLE 4.2.D MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS Instrument Functional
. Instrument Instrument Channels Test Calibration Check '(2) 1)
Refuel Area Exhaust (1)
Once/3 months Once/ day Monitors'- Upscale 2)-
Reactor Building Area (1)
_Once/3 months Once/ day.
3).
Main ~ Stack Monitor Once/3 months once/12 months Once/ day.
53 as described in f
4.8.C.4.a 4)
Main Control Room Once/3 months Once/18 months once/ day as described in-4.11.A.5 Loaic System Functional Test (4)
'(6)
'Frecuency
~E 1)
Reactor. Building Isolation-Once/ Operating Cycle 5.5 2)
Standby Gas Treatment Once/ Operating Cycle System Actuation-z E:."
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Unit 2 PBAPS 1.
3.2 kb1EE (Cont'd)
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatmer.t system.
Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refuelir', floor.
Each set of instrument channels is arranged in a 1 out oi 2 twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack.
Trip signals from these monitors are required only when purging the containment through the SGTS and containment integrity is required.
The trip signals isolate pri-mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open.
This signal is added to fulfill the requirements of item II.E.4.2(7) of NUREG-0737.
Four channels of in-duct radiation monitors are provided which initiate the Main Control Room Emergency Ventilation System.
Each set of instrument channels are arranged in a one (1) out of two (2) twice trip logic.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The integrated flow is indica-tive of reactor coolant leakage.
A Drywell Atmosphere Radioactivity j
Monitor is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system.
(See Bases for 3.6.C and 4.6.C)
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.
This instrumentation and the applicable NUREG-0737 requirements are:
1.
Wide range drywell pressure (II.F.1.4) 2.
Subatmospheric drywell pressure (II.F.1.4) 3.
Wide range suppression chamber water level (II.F.1.5) 4.
Main stack high range radiation monitor (II.F.1.1) 5.
Reactor building roof vent high range radiation monitor (II.F.1.1) 6.
Drywell hydrogen concentration analyzer and monitor (II.F.1.6) 7.
Drywell high range radiation monitors (II.F.1.3) 8.
Reactor Water Level - wide and fuel range (II.F.2) 9.
Safety-Relief Valve position indication (II.D.3) Amendment No. 102, 112, ZI3, 156,184
Unit 2 PBAPS 4.2 BASES (cont'd)
The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in a 1 out of 2 twice logic system.
The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency.
The air e]ector off-gas monitors are connected in a 2 out of 2 logic arrangement.
Based on the experience with instruments of similar design, a testing interval of once every three months has been found adequate.
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required only during containment purging through the SGTS and when containment integrity is required, an activity which occurs infrequently.
Therefore, a twelve (12) month calibration interval is appropriate.
The Control Room Intake Air Radiation Monitors are safe- -related and are required tc be operable at all times when secondary containment is required.
The calibration interval is as described in Section 4 ll.A.
The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also. Amendment No. 156,184
~~
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS
- b. The results of laboratory
- d. A dry gas purge shall carbon sample analysis be provided to the filters shall show 90% radioactive to insure that the methyl iodide removal at relative humidity in the a velocity within 20%
filter systems does not of system design, 0.05 exceed 70% during idle to 0.15 mg/m3 inlet periods.
methyl iodide concentra-tion, 2 95% relative
- e. A sample of the charcoal humidity and 2 125 degrees F, filter shall be analyzed once or that filter train shall per year to assure halogen not be considered operable, removal efficiency of at least 99.5 percent.
c.
Fans shall be shown to operate at approximately 3.
Once every 18 months automatic 3,000 CFM 300 CFM initiation of control room (design flow for the emergency ventilation, from filter train).
all designed initiation signals shall be demonstrated.
5.
The main control room ventilation radiation 4.
Operability of the main monitors, which monitor main control room ventilation control room ventilation radiation monitors and flow radiation levels, shall switches shall be functionally be operable at all times tested every 3 months.
when secondary containment is required.
- 5. The main control room radiation monitors shall be
- a. One radiation monitoring calibrated electronically and channel may be inoperable for with a known radioactive 7 days, as long as the source positioned in a remaining radiation monitoring reproducible geometry with channel maintains the respect to the sensor every 18 capability of initiating months.
emergency ventilation on any designed trip functions.
- 6. The main control room' ventilation supply flow
- b. A trip system is operable when switches shall be calibrated 1 of 2 channels is available to every 18 months.
provide its trip function and the inoperable channel is placed in its tripped condition.
If a channel is inoperable or placed in its tripped condition in'both trip systems, then emergency ventilation must be initiated and maintained.
-233a-Amendment No. Il3,184
Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.ll.A (cont'd.)
4.ll.A (cont'd).
- 6. The main control room ventilation supply flow switches shall be operable at
- all times when secondary containment is required encept B.
Emeraency Heat Sink Facility one flow switch may le inoperable for 7 dayr as lo.ig 1.
The level in the emergency as the other flow switch is reservoir of the Emergency operable.
Heat Sink Facility shall be checked once per month.
7 If specification 3.ll.A.5 or 3.11.A.6 cannot be met, 2.
Once a year the portable manually initiate and maintain fire pump which is used to main control room emergency provide makeup water to the ven:;1stier.
emergency reservoir will be checked for operability and E.
Emercency Heat Sink Facility availability.
The level in the emergency 3a. The Emergency Cooling Water reservoir of the Emergency Heat pump and ESW booster Sink Facility shall not be less pumps shall be tested in than 17'.
Should the level accordance with Section XI drop below this point action of the ASME Boiler Pressure shall be taken to restore Vessel Code and applicable-the level to above the minimum, addenda, except where relief within 7 days.
has been granted.
C.
Emercencv Shutdown Control Panel
- b. The Emergency Cooling Tower fans shall be tested every three
- 1. At all times when not in use months to verify operability.
or being maintained, the emergency shutdown control C.
Emeroency-Shutdown Control Panel panels shall be secured.
1.
The emergency shutdown control panels shall be visually checked once per week to verify they are secured.
- 2. Operability of the switches on the emergency shutdown control panels shall be tested by electrical check once per refueling outage.
-234-Amendment No. 170, 184
Unit 2 PBAPS 3.11 BASES A. Main Control Room Emergency Ventilation System The control room emergency ventilation system (CREV) is designed to filter the control room intake air during control room isolation conditions.
The CREV system is designed to automatically start upon receipt of control room isolation signals and to maintain the control room at a positive pressure so that all leakage should be out-leakage.
High efficiencf particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential intake of radiolodine to the control room.
The in place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the officiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
One main control room emergency ventilation air supply fan provides adequate ventilation flow under accident conditions.
Should one emergency ventilation air supply fan and/or fresh air filter train be ou of service during reactor operation, the allowable repair time for 7 days is justified.
At least 1 of 2 channels per trip system in the Control Room Ventilation Radiation Monitoring System for indication and alarm of radioactive air being drawn into the main control room is considered adequate, provided that 3 of the 4 channels are available.
With one channel of control room radiation monitoring inoperable the capability of automatically initiating emergency ventilation on receipt of any trip signal is still maintained and at no cime is the ability to manually initiate emergency ventilation lost.
Therefore, the allowable time for repair of 7 days is justified. When one (1) radiation monitoring channel in both trip systems are inoperable, then emergency ventilation shall be initiated and maintained. Main control room emergency ventilation is initiated when a trip signal from the radiation detectors is given via high radiation or dovnscale/ failure signal (one out of two twice logic) or loss of divisional power to local radiation monitoring system panel. Main control room emergency ventilation is also initiated on a low flow signal from one of two flow switches in the main control room normal supply after a time delay, 4
U
-235 Amendment No.184
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Me 2
Unit'2 2 --
PBAPS e
TABLE 4.15**
SEISMIC MONITORING INSTRUMENTATION SURVEIr.TANCE REOUIREMENTS Instrument
- Instrument
- Functional Instrument'-
~
Instruments and Sensor Locations #
Check Test Calibration
- 1. Triaxial Time-History Accelerographs
~
a'. Containment Foundation (torus compartment)
M SA R
- b. Refueling Floor M
SA' R
- c. RCIC Pump (Rm #7)
M
'SA-R d.
"C" Di'esel Generator M
SA R
-2 '. Triaxial Peak Accelerographs
- a. Reactor Piping (Drywell)
NA NA'
'R
- b. Refueling Floor NA NA R
c.
"C" Diesel Generator NA -
NA R
3.
Central Recording and Analysis System j
- a. Cable Spreading Rm M
SA R
1
- ' Surveillance Frecuencies' M:
every month i
SA:
every 6 months
{
R:
every 24 months j
- Effactive upon completion of installation.
Seismic instrumentation located in Unit 2.
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-240v-Amendment No. 75, 85, Z79. 184 1
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- 3 UNITED STATES l'T NUCLEAR REGULATORY COMMISSION
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WASHINGTON D.C. 2055W1 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 189 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found thai:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated November 1,1993 as supplemented c'1 January 26, 1994 and February 18, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amendt.d (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter 1.
B.
The facility will operate in conformity with the application, the provisions 'of the Act, and the rules and regulations of the Commission; 1
C.
There is reasonable assurance (i) that the activities authorized by I
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 or safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of 3
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. DPR-56 is hereby amended to read as follows:
-l 1
i
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.189, are hereby ' incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented upon completion of modification 5281.
FOR THE NUCLEAR REGULATORY COMMISSION hr llUkW Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 15, 1994 i
i
ATTACHMENT TO LICENSE AMENDMENT NO.189 FACILITY OPERATING LICENSE N0. DPR-56 DOCKET NO 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Removg Insert 59 59 75 75 t
84 84 93 93 97 97 233a 233a 234 234 235 235 240v 240v
=
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.2.D.
Radiation Monitorinc 4.2.D.
Radiation Monitorina Systems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions 1.
Reactor Buildina Isolation 1.
Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D.
brated and checked as indi-cated in Table 4.2.D.
2.
Main Control Room System logic shall be The limiting conditions for functionally tested as operation are given in indicated in Table 4.2.D.
Table 3.2.D.
2.
Main Control Room E.
Drywell Leak Detection Instrumentation shall be The limiting conditions of functionally tested, operation for the instru-calibrated and checked as mentation that monitors indicated in Table 4.2.D.
drywell leak detection are given in Section 3.6.C, E.
Drvwell Leak Detection
" Coolant Leakage".
Instrumentation shall be calibrated and checked as indicated in table 4.2.E.
i 1 Amendment No. IN, 162, 189
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Unit 3-PBAPS TABLE 3.2.D
. RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOIATE SYSTEMS Minimum No.
of Operable Instrument-No. of Instrument Channels.per Channels Provided Action?
Trip System
" rip Function Trip Level Setting by Design (2)-
(1)'
2 Refuel Area Exhaust Upscale, <16 mr/hr 4 Inst. Channels-A or B -
Monitor 2
Reactor Building Upscale, <16 mr/hr 4 Inst. Channels B
Exhaust Monitors 1
(3)
Main Stack Monitor Upscale, 510' cps 2 Inst. Channels C
l 2
(4)
Main Control Room Upscale, <400 cpu 4 Inst. Channels D
Notes for Table 3.2._D_
- 1. Whenever the systems are required to be operable, the specified number of instrument channels shall be operable or placed in the tripped condition.
If this cannot be met, the indicated action shall be taken.
>g
- 2. Action
'Eg A. Cease operation of the refueling equipment.
B.~ Isolate secondary containment and start the standby gas treatment system.
_ C. Cease purging of primary containment, and close vent and purge valves greater than 2' inches-
.z_
P in diameter, Il D. As described in LCO 3.11.A.5 w
- 3. The trip function is required to be operable only-when the containment is purging through the O
SGTS and containment. integrity is required.
If both radiation monitors are-out of service, action shall'be taken as indicated in Note 2,-(C).-
- 4. The1 trip function -is required to be operable whenever secondary containment ~ is required on either unit.-
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Unit'3 PBAPS TABLE 4.2.D-MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS-Instrument Functional Instrument Instrument Channels Test Calibration Check (2)
I 1)
Refuel Area Exhaust
. (1)
Once/3 months once/ day Monitors - Upscale 2)
Reactor Buildin'g Area (1)-
Once/3 months Once/ day.
3)
Main Stack Monitor Once/3 months once/12'~ months once/ day cb as described in 7
4.8.C.4.a 4)
Main Control Room Once/3 months Once/18 months Once/ day _
as described in 4.11.A.5 R
Loaic System Functional-Test (4)
-(6)
Frecuency 5
. Reactor Building Isolation Once/ Operating Cycle 3
1) z
~.
2)
Standby Gas Treatment Once/ Operating-Cycle System Actuation ~-
w E
y
,~ -
03 m
2 c
J' e
- 4
Unit 3 PBAPS 3.2 BASES (Cont'd)
Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system.
Four instrument channels monitor the radiation from the refueling area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor.
Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.
Trip settings of less than 16 mr/hr for the monitors in the refueling area ventilation exhaust ducts are based upon ini-tiating normal ventilation isolatio. and standby gas treatment system operation so that none of the activity released during the i
refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.
Two channels of nonsafety-related radiation monitors are provided in the main stack.
Trip signals from these monitors are required only when purging the containment through the SGTS and containment integrity is required.
The trip signals isolate pri-i mary containment vent and purge valves greater than 2 inches in diameter to prevent accidental releases of radioactivity offsite when the valves are open.
This signal is added to fulfill the requirements of item II.E.4.2(7) of NUREG-0737.
Four channels of in-duct radiation monitors are provided j
which initiate the Main Control Room Emergency Ventilation System.
Each set of instrument channels are arranged in a one (1) out of two (2) twice trip logic.
Flow integrators are used to record the integrated flow of liquid from the drywell sumps.
The integrated flow is indica-tive of reactor coolant leakage.
A Drywell Atmosphere Radioactivity Monitor is provided to give supporting information to that supplied by the reactor coolant leakage monitoring system.
(See Bases for 3.6.C and 4.6.C)
Some of the surveillance instrumentation listed in Table 3.2.F are required to meet the accident monitoring requirements of NUREG-0737, Clarification of TMI Action Plan Requirements.
This instrumentation and the applicable NUREG-0737 requirements are:
1.
Wide range drywell pressure (II.F.1.4) 2.
Subatmospheric drywell prescure (II.F.1.4) 3.
Wide range suppression chamber water level (II.F.1.5) 4.
Main stack high range radiation monitor (II.F.1.1) 5.
Reactor building roof vent high range radiation monitor (II.F.1.1) 6.
Drywell hydrogen concentration analyzer and monitor (II.F.1.6) 7.
Drywell high range radiation monitors (II.F.1.3) 8.
Reactor Water Level - wide and fuel range (II.F.2) 9.
Safety-Relief Valve position indication (II.D.3) Amendment No.104, Ild,117,158,189
Unit 3 PBAPS 4.2 BASES (cont'd)
The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in a 1 out of 2 twice logic system.
The bases given above for the rod blocks apply here also and were used to arrive at the functional testing frequency.
The air ejector off-gas monitors are connected in a 2 out of 2 logic arrangement.
Based on the experience with instruments of similar design, a testing interval of once every three months has been found adequate.
Radiation monitors in the main stack which initiate containment isolation are not safety-related and are required only during containment purging through the SGTS and when containment integrity is required, an activity which occurs infrequently.
Therefore; a twelve (12) month calibration interval is appropriate.
The Control Room Intake Air Radiation Monitors are safety-related and are required to be operable at all times when secondary containment is required.
The calibration interval is as described in Section 4.ll.A.
The automatic pressure relief instrumentation can be considered to be a 1 out of 2 logic system and the discussion above applies also. Amendment No. 158, 189
i r
Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS t
- b. The results of laboratory
- d. A dry gas purge shall carbon sample analysis be provided to the' filters shall show 90% radioactive to insure that the methyl iodide removal at relative humidity in the a velocity within 20%
filter systems does not of system design, 0.05 exceed 70% during idle to 0.15 mg/m3 inlet
- periods, methyl iodide concentra-tion, 2 95% relative
- e. A sample of the charcoal humidity and 2 125 degrees F, filter shall be analyzed once or that filter train shall por year to assure halogen not be considered operable.
removal efficiency of at least 99.5 percent.
c.
Fans shall be shown to operate at approximately 3.
Once every 18 months automatic 3,000 CFM 300 CFM initiation of control room (design flow for the emergency ventilation, from filter train).
all designed initiation signals shall be demonstrated.
5.
-The main control room ventilation radiation 4.
Operability of the main monitors, which monitor main control room ventilation control room ventilation radiation monitors and flow radiation levels shall switches shall be functionally be operable at all times tested every 3 months.
when secondary containment is required.
- 5. The main control room radiation monitors shall be-
- a. One radiation monitoring calibrated electronically and channel may be inoperable for with a known radioactive 7 days, as long as the source positioned in a remaining radiation monitoring reproducible geometry with channel maintains the respect to the sensor every 18 capability of initiating months.
emergency ventilation on any designed trip functions.
6.
The main control room ventilation supply flow
- b. A trip system is operable when switches shall be calibrated 1 of 2 channels is available to every 18 months.
provide its trip function and the inoperable channel is placed in its tripped condition.
If a channel is inoperable or placed in its tripped condition in both trip systems, then emergency ventilation must be initiated and maintained.
-233a-Amendment.4o. ZZ7,jgg
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J.
5 ;:4' ' <
UnitD,3 :
p PBAPS u
LI :: TING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENT$,)
t' 3.1".A (cont'd.)
4.ll.A (cont'd).
- 6. The main' control room ventilation-supply flow-switches.shall1be operable at all' times when secondary containment is required except B.
Emeroency Heat Sink Facility-one. flow switch may be
-inoperable.for 7 days as long 1.
The level inxthe emergency as the other flow switch is reservoir of the Emergency.
HeattSink Facility shall be checked'once.per' month.'
7 If specification 3.ll.A 5 or 3.ll.A.6 cannot be met, 2.
Once a year the; portable.
-i manually initiate and maintain fire pump.which is used.co' main control room emergency provide makeup water'to the.
t ventilation, emergency reservoir.will be checked for operability'and B.
Emercenev Heat Sink Facility availability.
The level in the emergency 3a. The Cinergency Cooling-Water reservoir of the Emergency Heat pump.and ESW booster Sink Facility shall not be less pumps shall-be: tested-in
- )
than 17'.
Should the' level accordance with Section XI i
drop below this point action of the ASME Boiler! Pressure ar.sil be taken to restore.
Vessel Code andLapplicable:
tne level to above the minimum, addenda,Lexcopt whereLrelief within 7 days' has -been grar.ted.-
.j 4
-C. Emercencv Shutdown control Panel
- b. The: Emergency Cooling: Tower j
m
- fans shall.be tested every three:
9 in use monthsfto: verify operability.-
1
'l.
At all times when not or being maintained,.the o
i emergency. shutdown control C.-
Emeroency Shutdown: Control' Panel 1
panels shall be secured.
. j 1.
The' emergency shutdown'controlf R
panels shall be visually; checked once-per week to verifyithey a
c are secured.
4
- 2. OperabilityJof: the switches; 3
on the emergency shutdown control' panels shall'be',
y tested'~by. electrical check once per refuelingLoutage.'
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-234-Amendment No. U(,189
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t
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i Unit 3 PBAPS 3.11 BASES A. Egin Control Room Emereenev Ventilation System The control room emergency ventilation system (CREV) is designed to filter the control room intake air during control room isolation conditions.
The CREV system is designed to automatically start upon receipt of control room isolation signals and to maintain the control room at a positive pressure so that all leakage should be out-leakage.
High efficiency particulate absolute (HEPA) filters are installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential intake of radiciodine to the control room.
The in place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
One main control room emergency ventilation air supply fan provides adequate ventilation flow under accident conditions.
Should one emergency ventilation air supply fan and/or fresh air filter train be out of service during reactor operation, the allowable repair time for 7 days is justified.
At least 1 of 2 channels per trip system in the Control Room Ventilation Radiation Monitoring System for indication and alarm of radioactive air being drawn into the main control room is considered adequate, provided that 3 of the 4 channels are available.
Wich one channel of control room radiation monitoring inoperable the capability of automatically initiating emorgency ventilation on receipt of any trip signal is still maintained and at no time is the ability to manually initiate emergency ventilation lost.
Therefore, the allowable time for repair of 7 days is justified. When one (1) radiation monitoring channel ir both trip systems are inoperable, then emergency ventilation shall be initi, ed and maintained. Main control room emergency ventilation is initiated when a trip
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signal from the radiation detectors is given via high radiation or downscale/ failure signal (one out of two twice logic) or loss of divisional power to local radiation monitoring system panel. Main control room emergency ventilation is also initiated on a low flow signal from one of two flow switches in the main control room normal supply after a time delay.
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i
-235-Amendment No.189
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Unit 3 PBAPS TABLE 4.15**
SEISMIC MONITORING INSTRITMENTATION SURVEIT.rANCE REOUIREMENTS Instrument *-
Instrument
- Functional ' Instrument Instruments and Sensor Locations #
Check Test Calibration
- 1. Triaxial Time-History Accelerographs
- a. Containment Foundation (torus compartment)
M SA R
- b. Refueling Floor M
SA R'
- c. RCIC Pump (Rm #7)
M SA R-d.
"C" Diesel Generator M
SA R
- 2. Triaxial Peak Accelerographs
- a. Reactor Piping (Drywell)
NA NA R
- b. Refueling Floor NA NA R
c.
"C" Diesel Generator NA NA R
3.
Central Recording and Analysis System a.
Cable Spreading Rm M
SA R
Surveillance Frecuencies M:
every month SA:
every 6 months R:
every 24 months l
- Effective upon completion of installation.
b Seismic instrumentation located in Unit 2.
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-240v-Amendment No. 74, 84, 182,189'
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