ML20105D216
| ML20105D216 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/16/1992 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20105D217 | List: |
| References | |
| NUDOCS 9209240468 | |
| Download: ML20105D216 (18) | |
Text
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~,j NUCLEAR REGULATORY COMMISSION g
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PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LfGHT COMPANY ATLAN11C CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No.170 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 January 10, 1992, as revised by letter dated July 20, 1992 and as supplemented by letter dated April 3, 1992, 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 Commissit,n'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:
9209240460 920916 PDR ADOCK 05000277 P
(2) Inhnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 170, 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.
5 FOR THE NUCLEAR REGULATORY COMMISSION Qu y W
\\
Charles L. Miller, Director Project Directorata 12 Division of Reactor Projects - 1/11 Office of Nuc1"u ivactor Regulation e
Attachment:
Changes to the Technical Specifications Date of Issuance: September 16, 1992 O
i
ATTACHMEt1T 10 t ICEtJ5E AMENIFtdi f40.170 fACillTY OPERATit!G tl.ENSE NO. DPR-44 EqLKET NO 50-277 Rerlace the following pages of the Appendtv A le.hnical Specifications with the enclosed pages.
The revised areas are dicated by marginal lines.
Remove jnjari 221 221 223 223 224 224
?34 234 235a 235a 230a 236a W
'6 a-A
Unit.
44 s
PB-PS i
LIMITING CONDITIONS FOR OPERA 110N SURVEILLANCE REQUIREMENTS 3.9.C Emergency Service Water 4.9.C Emergency Service Water System Sy stem
- 1. The Emergency Service Water
- 1. The ESWS shall be tested System (ESWS) shall be operable once every 3 months as at all times when tne reactor follows:
coolant temperature is greater than 212 F.
- a. Pump operability -
the pump shall be
- 2. If one ESW pump becomes manually started ana increretle, the reactor flow capability tested in may remain in operation accordance with the Section for a period not to XI of the ASME Boiler exceed seven (7) days.
If fressure Vessel Code ano this requirement cannot be applicable addenda except met, an orderly shutdown shall where relief has been be initiated and the reactor granted.
shall be placed in the cold shutdown condition
- b. Valve operability -
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
the automatic valves shall be strched
- 3. If two ESW pumps become individually from inoperable, the reactor shall their control switches, be placed in hot shutdown within six (6) hours
- 2. The associated pump room and in cold shutdown fans shall be tested for within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
operability every 3 mortns.
- 4. To consider the ESW pump
- 3. Each manual valve and operable the associated each electric motor pump room fans must be operated valve that is available for normal operation in the system flow except that a) one pump path and that is not room supply and/or exhaust locked,-sealed or fan for each compartment otherwise secured in may be out of service for position, shall be one month'or b) temporary verified-monthly to be fans may be used in place of in its correct position.
permanently installed fans toprovideroomgemperatures at less then 120 F.
- 4. Once per refuel outage the bottom of the 'A' ESW pump intake structure will be inspected and cleaned as necessary to remove excessive.
silt.
-221-Amendment No.170
PBAPS 3.9 BA$ls (Cont'd.)
The 125-Volt Dattery system chall have a minimum of 105 Volts at the battery 1erminals to be considered operable, The 250-Volt portion of the 125/250-Volt battery system shall have a minimum of 210 Volts at the battery terminals to be considered operable.
The E5W5 has two 100 percent cooling capacity pumps, each powered f rom a separate standby power suppl;,
in 'te event one of the ESW pLn4 i becomes inoperable the 7 day allowbtit cat of service time is conservatlie given the probability of an event requiring the use of both ESW pumps occurring in that amount of time.
One ESW pump is capable of supplying the entire system, if both of the ESW pumps become inoperable placing the reactor in a shutdewn condition is consistent with the severity of the situation.
4.9 BAS [5 The monthly test of the diesel generator is conducted to check for equipment failures and deterioration.
lesting is conducted up to equilibrium operating conditions to demonstrate proper operation at these conditions.
The diesel generator will be manually started, synchronized and connected to the bus and load picked up.
The diesel generator should be loaded to at least 75% of rated load to prevent fouling of the engine, it is expected that the diesel generator will be run for one to two hours. Diesel generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the syftem be required.
Each diesel generator 'ias one air compressor and two ai receivers for
- stcrting, it is expected that the air compressors will run only infrequently.
During the monthly check of the diesel generator, one receiver in each set of receivers will be drawn down below the point at which tre corresponding compressor automatically starts to check operation and tae ability cf the compressors to recharge the receivers.
The Jiesel generator f uel consumotion rate at full load is approximately 200 gallons per hour.
Thus, the monthly load test of the diesel generators will test the operation and th' ability of the fuel oil transfer pumps to refill the day tank and will check tie operation of these pumps from the emergency source, lhe test of the diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system; i.e., it will check diesel generator starting and closure of diesel generator breaker and sequencing of load on the diesel generator. The diesel generator will be started by simulation of a loss-of-coolant accident.
In addition, an undervoltage condition will be imposed to simulate a loss of off-site power.
The timing sequence will be chacked to assure that the diesel generators r.an operate the LPCI pumps at rated speed within 18 seconds, and the core spray pumps at rated speed within twenty-four seconds.
-223 Amendment No.170 1
________.______.-______._________________.________.________.___m
Unit 2 PBAPS 4.9 BASES (Cont'd.)
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment couling pumps to deliver full flow.
Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates there is almost no possibility of precipitous failure.
The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
In addition, the checks described also provide adequate indication that the batteries ht.ve the specified ampere hour cepability.
The station batteries shall be subjected to a performance test every third refueling outage and a service test during the other refueling outages.
This testing frequency complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450(1975)
" Recommended Practice for Mair.;enance, lesting and Replacement of Large Lead Storage Batteries," and Regulatory Guide 1.129 Revision 1 (February 1978), " Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants."
A performance test determines the aLility of the battery to meet a specified discharge rate and duration based on the manufacturer's rating.
A service test proves the capability of the battery to deliver the design requirements of the dc systems; i.e., supply and maintain in operable status e.11 of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battery at manufacturer's rating shortens the service life of the battery. A service test is performed at design load instead of manufacturer's ratings.
The diesel fuel oil quality must be checked to ensure proper operation of the diesel generators. Water content should be minimized because water in the fuel could contribute to excessive damage to the diesel engine.
Amendment No. 131 centralized commitments related to Position C.2 of Regulatory Guide 1.137 Revision 1 (October, 1979) " Fuel Oil Systems for Standby Diesel Generators".
When it is determined that some auxiliary electrical equipment is out-of-sarvice, the increased surveillance required in Section 4.5.F is deemed adequate to provide assurance that the remaining equipment will be operable.
The test interval for the Emergency Service Water System, and pump room fans associated with the ESW pumps is deemed adequate to provide assurance that the equipment will be operable based on good engineering judgment and system redundancy, plus the additional testing accomplished wten the diesel generators are tested.
Pump flow tests during normal operation will be performed by
' -measuring the head and flow in the system using suitable flow eouipment and pressure instrumentation.
-224-Amendment No. T U, IM,170
PBAPS l
LIM]T]NG COND]TIONS FOR OPERATION SURVEILLANCE REQUIPEMENTS 3.ll.A (Cont'd.)
4.ll.A (Cont'd.)
d.
A sample of the charcoal filter shall be analyzed once per year to assure halogen removal efficiency of at least of at least 99.5 percent.
2.
At least 1 of the 2 main 2.
Operability of the main control room intake air radiation cont-ol room air intake fronitors shall be operable with radiation monitors shall be the inoperable channel failed tested every 3 months.
safe whenever the control room emergency ventilation air supply i B.
Emergency Heat Sink Iacility fans and filter trains are required to be operable by 3.11.A.1 or 1.
The level in the emergency filtration of the control room j
reservoir of the Emergency ventilation intake air must be Heat Sink facility shall be initiated, checked once per month.
lB.
Emergency Heat Sink Facility 2.
Once a year the portable fire pump which is used to The level in the emergency provide makeup water to the reservoir of the Emergency Heat emergency reservoir will be Sink facility shall not be less checked for operability and than 17'.
Should the level availability.
drop below this point action shall be taken to restore 3a.
The Emergency Cooling Water the level to above the minimum, pump and ESW booster within 7 days, pumps shall be tested in accordance with Section XI C.
Emergency Shutdown Control Panel of the ASME Boiler Pressure Vessel Code and applicable 1
At all times when not in use addenda, except where relief or being maintained, the has been granted, emergency shutdown control panels shall be secured, b.
The Emergency Cooling Tower fans shall be tested every threc months to verify operability.
C.
Emergency Shutdown Control Panel 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
PBAPS 3.11 BAS [$-
Emeroency Heat Sink l
The emergency heat sink it provided as an alternate source of cooling water to the plants in the unlikely event of loss of the normal heat sink (Conowingo Pond) or the maximum credible flood, for the condition Of loss of the normal heat sink, the contained volume of water (approximately J.7 million gallons, which corresponds to a gauge reading of 17') provides a minimum of seven days cooling water to both plants for decay heat removal.
C.
Emergency Shutdown Control Panels The Emergency Shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condition external to the control room for the unlikely condition that the control room becomes uninhabitable.
D.
Shock Suppressors (Snubbers) on Safety Related Systems Snubbers are provided to ensure that the structural ir.tegrity of the reactor coolant system and all other safety-related system > are maintained during and following a seismic or other event initiating dynamic loads.
Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of seismic or other event initiating dynamic loads.
It is therefore required that all snubbers necessary to protect the primary coolant system or any other safety system or components be operable during reactor operation.
Because the snubber protection is required only during low probability events a '
period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allcwed for repairs or replacements.
A determined effort will be made to repair the snubber as soon as possible. This allowable repair period is consistent with the allowable repair items of other safety related components such as RHR pumps, HPCI subsystems, ADS valves e.nd diesel generators.
An engineering analysis must be performed on supported components when a snubber is determined to be inoperable.
The purpose of this analysis is to assure that the supported components have not been damaged as a result of the l
snubber inoperability, l
-235a-Amendment No, I0I.
l 107, 170 l
~
PBAPS 4.11.
BASES l
B.
Emergency Heat Sink facility The testing of the ESW Booster Pumps and the ECW pump is in accordance with existing ASME codes and applicable addenda except where relief has been granted and assures the required availability of the equipment.
C.
Emergency Shutdown-Control Panels Once per week verification of the panels being properly secured is considered adequate.
The associated equipment is proven operable during surveillance testing of that equipmer.t. An operability verification by electrical test at each refueling outage is adequate to assure that the panels are available and can perform their design function.
D.
Shock Suppressors (Snubbers) on Safety Related Systems All safety-related snubbers are visually inspected to verify, 1) proper orientation, 2) freedom of movement where possible to induce motion manually without disconnecting the snubber, 3) proper attachment to structures and equipment, and 4) proper hydraulic fluid level for hydraulic snubbers.
Snubbers are categorized into two groups, " accessible" or " inaccessible",
based on their accessibility for inspection during reactor operation and drywell inertment.
The required inspection interval varies inversely with the observed snuDber failures.
The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.
Inspections performed t;afore that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of suct early inspections will only be used to shorten the required interval and nei to lengthen it.
When the cause of the rejection of a snubber is clearly established and remedied for that !.nubber and for any other snubbers-that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vi; ration. When a snubber is found inoperable an engineering evaluation is performed to determine a) snubber mode of failure and, b) if there is any adverse effect or degradation on the supported piping or equipment due to the failure.
To 'urther increase the assurance of snubber reliability, functional tests will be performed once each operating cycle, i
l 236a-Amendment No. ZOI._170 l
l
- ps Hog'o UNITED STATES
[' >g#[,h NUCLEAR REGULATORY COMMISSION y
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a s.
PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DJLMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET N0. 50-2))
ELACH BOTTOM ATOMIC POWER ST" ION. UNIT NO. 3 AMENDMENT TO FACILITY OEERATING LICENSE Amendment No.174 License No. OPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated January 10, 1992, as revised by letter dated July 20, 1992 and as supplemented by letter dated April 3, 1992, 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 fortt 'n 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; 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 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 beer, satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment h this license amendment, and paragraph 2.C(2) of facility Operating Lics.se No. DPR-56 is hereby amended to read as follows:
,c (2) lechnical._ Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.174, are hereby incorporated in the license.
PECO shall operate the facility in accordance with the Technical Specifications.
3.
This license amt<dment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION a
Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the lechnical Specifications Date of Issuance: September 16, 1992 t
_~
-- ~ -.......
f P
eTTACHMENT TO LICENSE AMENDMENT N0J4 FAClllTY OPERATING LICEjiSE NO. 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-Remove Insert 2L 221 223 223 224 224 234 234 235a 235a 236a 236a P
-.,,.;-....-....,,,--..z.----
_ _ _ _ _ __ -.. _. _ _ _ _..__.__ ~. _._
._.._____...m Unit 3
- 3. ' '
i PBAPS LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS i
3.9.C Emergency Service Water 4.9.C Emergency Service Watee System System i
- 1. The Emergency Service Water
- 1. The ESWS shall be tested -
i System (ESWS) shall be operable once every 3 months as at all times when the reactor follows:
coolant temperature is greater than 212 F.
- a. Pump operability -
the pump shall be
- 2. If one ESW pump becomes manually started and inoperable, the reactor flow capability tested in may-remain in operation accordance with the Section for a period not to XI of the ASME Boiler exceed seven (7) days.
If Prcssure Vessel Code and this requirement cannot be applicable addenda except--
met, an orderly shutdown shall where relief has been be initiated and the reactor granted..
shall br ' laced in the cold sho,vown condition
- b. Valve operability -
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
the automatic valves shall-be stroked
- 3. If two ESW pumps become individually.from inoperable, the reactor shall their control switches.
be placed in hot shutdown within six (6) hours 2.-The associated pump room and in cold shutdown fans shall be tested for within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
operability every 3 months.
- 4. To consider the ESW pump
- 3. Each manual _ valve and operable the associated each electric motor.
pump room fans _must be
_ operated valve that is.
available for normal operation in the system flow-except that a) one oump path and that is not room supply and/or exhaust locked. sealed or fan for each compartment
.otherwise secured in may be out of service for position, shall be one month or b) temporary verified monthly to'be fans may be used in place of in its correct position, permanently installed fans toprovideroomgemperatures at less than 120 F,
- 4. Once per refuel outage' the bottom of the 'B' ESW pump intake structure will be inspected and cleaned as necessary to remove excessive
. silt.
c l
221-Amendment No '769,;174 4
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3,,3-
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{
3.9 BASE _5 (Coat'd.)
l The 125-Volt battery system shall hr 1 a minimum of 105 Volts et the battery
.c terminals to be considered operable. The 250-Volt portion of the 125/250-volt battery :;ystem shsll have a minimum of 210 Volts at the battery terminals to be considered operable.
The ESWS has two 100 percent cooling capacity purps, each powered from a separate standby power supply.
In the event one of the ESW pumps becomes inoperable the 7 day allowable out of service time is conservative given the probability of an event raquiring the use of both ESW pumps xcurring in that amount of time. One ESW pump is capable of supplying the entire system.
If both of the ESW pumps become inoperable placing the re6ctor in a shutdown condition is consistent with the severity of the situation.
4.9 BASES The monthly test of the diesel generator is conducted to check for equipment failures and deterioration.
lesting is-conducted up to equilibrium operating conditions to demonstrate proper operation at these cenditions.
The diesel generator will be manually started, synchronized and connected to the bus and load picked up.
The diesel generator should be loaded to at least 75% of rated load to prevent fouling of the engine, it is expected that the diesel generator will be run for one to two hours. Diesel generator experience at other generating stations indicates that the testing frequency is adequate and provides a high reliability of operation should the system be required.
Each diesel generator has one air
,. ressor and two air receivers for starting.
It is expected that the 2 compressors will run on), infrequently.
During the monthly check of the diesel generator, one receiver in each set of receivers will be drawn down below the point at which the corresponding compressor automatically starts to check operation and the ability of 'he compressors to recharge the receivers.
The diesel generator fuel consumption rate a full load is approximately 200 gallons per hour.
Thus, the monthly load test of the diesel generators will test the operation and the ability of the fuel oil transfer pumps to refill-the-day tank and wiil check the operation of these pumps from the emergency source.
The test of the diesel generator during the refueling outage will be more comprehensive in that it will functionally test the system; i.e., it will check diesel generator starting and closure of diesel generator breaker and sequencing of load on the diesel generator. The diesel generator will be started by simelation of a loss-of-coolant accident.
In addition, an undervoltage condition will be imposed to simulate a loss of off-site power.
The timing sequence will be checked to assure tnat the diesel generators can operate the LPC) pumps at rated speed within 18 seconds, and the core spray pumps at rated speed within twenty four seconds.
-223-Amerdment No.174
.~
m.
Unit 3 PBAPS 4.9 BASES (Cont'd.)
Periodic tests between refueling outages verify the ability of the diesel generator to run at full load and the core and containment cooling pumps to deliver full flow.
Periodic testing of the various components, plus a functional test one-a-cycle, is sufficient to maintain adequate reliability.
Although station batteries will deteriorate with time, utility experience indicates tnere is almost no poisibility of precipitous failure. The type of surveillance described in this specification is that which has been demonstrated over the years to provide an indication of a cell becoming irregular or unserviceable long before it becomes a failure.
In addition, the checks described also provide adeyuate indication that the batteries have the spe.cified ampere hour capability.
The station batteries shall be subjected to a performance test every third refueling outage and a service test during the other refueling outages.
This testing frequency complies with the testing requirements of the Institute of Electrical and Electronics Engineers (IEEE) Standard 450(1975)
"Accommended Practice for Maintenance, lesting and Replacement of Large Lead Storage Batteries," and Regulatory Guide 1.129, Revision 1 (February 1978), " Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power plants."
A performance test determines the ability of the battery to meet a specified discharge rate and duration based on the manufacturer's rating. A service test proves the capability of the battery to dtliver the design requirements of the dc systems; i.e., supply and maintain in operable status all of the actual emergency loads for the design basis accident. A performance test is the most severe test because the cycling on the battary at manufacturer's rating shortens the service life of the battery.
A service test is performed at design load instead of manufacturer's ratings.
The diesel fuei oil quality must be checked to ensure proper operation of the diesel gtnera: ors. Water content should be minimized because watrr in the fuel could cortribute to excessive damage to the diesel engine.
Amendment No. 134 centralized commitment s related to Position C.2 of Regulatory Guide 1.137 Revision 1 (October, 1979) " Fuel Oil Systems for Standby Diesel Ger.erators".
When it is determined that some auxiliary electrical equipment is out-of-service,
(
the increased surveillance required in Section 4.5.f is deemed adequate to provide assa :nce that the remaining equipment will be operable.
The test interval for the Emergency Service Water System, and pump room fans associated with the ESW pumps is deemed adequate to provide assurance that the equipment will be operable based on good engineering judgment and system redundancy, plus the additional testing accomplithed when the diesel generators
, are tested.
Pump flow tests during normal operation will be performed by
- measuring the head and flow in the system using suitable flow equipment and pressure instrumentation.
-224-Amendment No. 103, 734, If9, 174
! W VING CONDITIONS FOR 0;ERATION SURVElLLANCE REQUIREMENTS 3.ll.A (Cont'd.)
4.11.A(Cont'd.)
d.
A sample of the charcoal filter shall be analyzed once per vear to essure halogen removal etficiency of at least of at least 99.5 percent.
7.
At least 1 of the 2 main 2.
Operability of the main control room intake air radiation control room air intake monitors shall be operable with radiation monitors shall be the iroperable channel failed tested every 3 months, safe whenever the control room emergency ventilation air supply l B.
Emergency Heat Sink facility fans and filter trains are required to be opera W L) 3.ll.A.1 or 1.
The level in the emergency filtration of the control room reservo'r of the Emergency ventilation intake air must be Heat Sink facility shall be initiated, checked once_per month.
l B.
Emergency Heat Sink iacilih 2.
Once a year the portable fire pump which is used to The level in the emergency provide makeup water to the l
reservoir of'the Emergency Hcst emergency reservoir will be Sink Facility shall not be less checked for operability and than 17'.
Should the level availability.1 drop below this point action shall be taken to restore 3a. The Emergency Cooling Wate'r the level to above the minimum, pump and iSW booster within 7 days.
pumps shall be tested in accordance with Section XI C.
Emergency Shutdown Control Pang of the ASHE Boiler Pressure Vessel Code and applicable 1.
At all times when not in use addenda, except where relief or being maintained, the has been granted.
emergency shutdown control panels shall be secured.
b.
The Emergency Cooling Tower fans shall be tested every three months to verify operability.
C.
Emergency Shutdown Control Panel
~
1.
The emergency shutdown control panels shall be visually checked once per week to serify they are secured.
2.
Operability of the switches i
on the emergency shutdown control panels shall be tested by electrical check once per refueling outage.
-234-Amendment No. 174 l.
,,.._e
PBAPS 3.11 BASES l
Emergency Heat Sink l
The emergency hest sink is provided as an alternate source of cooling water to the plants in the unlikely event of loss of the nomal heat sink (Conowingo Pond) or the maximum credible flood. for the conditiun of 10$$ cf the normal heat sink, the contained volume of water (approximattly 3.7 million gallons, which corresponds to a gauge reading of 17') provides a minimum of seven days cooling water to both plants for decay heat removal.
C.
. Emergency Shutdown Control Panels The Emergency Shutdown Control Panels are provided to assure the capability of taking the plants to the hot shutdown condition external tc the control room for the unlikely condition that the control room becomes uninhabitable.
D.
Shock Suppressors ($nubbers) on Safety Related Systems Snubt.ers are provided to ensure that the structural integrity of the reactor coolant system and all other safety-related systems are maintained during and following a seismic or other event initiating dynamic loads.
Snubbers are designed to prevent unrestrained pipe motion under dynamfC loads as might occur during an earthquake or severe transient while allowing hormal thermal motion during startup and shutdown.
The consequente of an inoperable snuhber is an increase in the probability of structural damage to piping as s result of seismic or other event initiating dynamic loads.
It 15 theret e required that all snubbers necessary to protect the prir.ory coolant system or any other safety system or components be operable during reactor operation.
Because the snubber protection is required only during low probability events a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for repairs or replacements. A determined effort will be made to repair the snubber as soon as possible.
This aHowable repair period is consistent with the allowable repair items of other seiety related compora !s such as RHR pumps, HPCI subsystems, ADS valves ;,d diesel nr o n aering analysis must be performed on supported cocponents when a ec
'.; W is determined to be inoperable.
Tne purpose of this analysis is to assure that the supported components have not been damaged as a result of the snubber inoperability.
-2355 Amendment No. 203. III.
174 4
Unis 3 PBAPS 4.11.
BASES B.
Emergency Heat., Sink iacility lhe testing of the ESW Booster Pumps and the ECW pump is in accordance with existing ASME codes and applicable addenda except where relief has been granted and assures the required availability of the equipment.
C.
Emergency Shutdown-Control Panels Once per week verification of the panels being properly secured is considered adeqt. ate.
The associated equipment is proven operablu during surveillance testing of that equipment. An operability verification by electrical test at each refueling outage is adequate to assure that the panels are availob'e and can perform their design function.
D.
Shock Suppressors (Snubbers) on Safety Related Systems All safety-relat:cri snubbers are visually inspected to verify,1) proper orientation, y) Treedom of movement where possible to induce motion manually without disconnecting the snubber, 3) proper attachment to structures and equipment, and 4) proper hydraulic fluid level for hydraulic snubbers.
Snutoers are cctegorized into two groups, "acc?ssible" or " inaccessible",
based on their accassibi'ity for inspection during reactor operation and drywell inertment.
The " quired inspection interval varies inversely with the observed snobber f ai h."es.
The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections will only De used to shorten the required interval and not to lengthen it.
When the cause of the rejection of a snubber is clearly established and remedied for-tha; snubber and for any other snubbers that may be generically susceptible, and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable. Generically susceptible snuboers are those which are of a specific make or model and have the same oesign features directly related to rejection of the snubber by visual inspection or are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration. When a snubbe.r is found inoperable an engineering evaluation is performed to determine a) snubber twde of failure and, b) if there is any adverse effect or degradation on tne supported piping or equipment due to the failure.
To further increase the assurance of snubber reli4bility, functional tests' will be performed once each operating cycle.
-236a.
Amendment No. 103.
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