ML20212N785

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Proposed Tech Specs,Removing All Refs to Ammonia Detector Monitoring Instrument Sys
ML20212N785
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/06/1987
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20212N774 List:
References
2814K, NUDOCS 8703130153
Download: ML20212N785 (13)
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Text

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.3 INSTRUMENTATION 3/4 3-1 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION....................

3/4 3-9 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..........................

3/4 3-23 j 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION......

3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation. . . . . . . . . . 3/4 3-35 End-of-Cycle Recirculation Pump Trip System 3/4 3-39 Instrumentation............................................

3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 3/4 3-45 INSTRUMENTATION............................................

3/4 350 3/4.3.6 CONTR0( R00 WITH0RAWAL BLOCK INSTRUMENTATION.................

3/4.3.7 MONITORING INSTRUMENTATION 3/4 3-56 Radi ati on Moni tori ng Instrumentati on. . . . . . . . . . . . . . . . . . . . . . . . .

3/4 3-60 Seismic Monitoring Instrumentation...........................

3/4 3-63 Meteorological Monitoring Instrumentation....................

3/4 3-66 Remote Shutdown Monitoring Instrumentation...................

3/4 3-69 Accident Monitoring Instrumentation..........................

3/4 3-72 Source Range Monitors........................................

Traversing In-core Probe System.............................. 3/43-73p

@ _, .. 4.. e...._ _

3/4374)l 3/4 3-75 Fire Detection Instrumentation...............................

3/4 381 Radioactive Liquid Effluent Monitoring Instrumentation.......

3/4 386 Radioactive Gaseous Effluent Monitoring Instrumentation......

3/4 3-91 Loose-Part Detection System..................................

3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION 3/4 3-92 INSTRUMENTATION.............................................

V Amendment No. 38 LA SALLE - UNIT 1 8703130153 870306 PDR ADOCK 05000373 P PDR

& l' C hCcl f.

STRUMENTATION j l l AMMONIA DETECTION SYSTEM .

i LIMITING CONDITION FOR OPERATION 1

1 1

. 3.3.7.8 Two independent ammonia detection system subsystems shall be OPERA 8LE,*

each with two ammonia detectors, with their alarm / trip setpoints adjusted to i

actuate at an ammonia concentration of less than or equal to 25 ppe.

APPLICABILITY: All CPERATIONAL CONDITIONS.

ACTION:

a. With one ammonia detector in either detection subsystem inoperable. l restore the inoperable detector (s) 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 at l

1 east one control room charcoal filter system train in the recircu-lation mode of operation. ,

$ b. With both ammonia detection subsystems inoperable, within I hour j

!' initiate and maintain operation of at least one control room charcoal filter system train in the recirculation mode of operation.

! c. The provisions of Specification 3.0.4 are not applicable.

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SURVEILLANCE REQUIREMENTS i

k4.3.7.8 Each of the above required ammonia detection system subsystems shall l

- ( be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL T

\once per 31 days and a CHANNEL CALIBRATION at least once per -

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h /h 844 1

1 s

"The normal or emergency power source may be inoperable in OPERATIONAL ONDITION 4 or 5.

3/4 3-74 Amendment No. 38 LA SALLE - UNIT 1 l

?

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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 communicating with the train by:
1. Verifying that the train satisfies the in place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the train flow rate is 4000 cfm' t 10%.
2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
3. Verifying a train flow rate of 4000 cfm + 10% during subsystem operation when tested in accordance with ANSI N510-1975.

~

c. After every 720** hours of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Positon 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.
d. 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 8 inches Water e Gauge while operating the train at a flow rate of 4000 cfm /O t 10%. / -

/

Verifying that on a simulated ammonia signal, the recirculath. j f 2.

. charcoal filter automatically switches to the recirculation mode ,

of operation and the isolation dampers close within 6 seconds.,/

.# l "This surveillance shall include the recirculating charcoal filter, " odor eater,"

in the normal control room supply filter train using ANSI N510-1975 as a guide

- to verify > 70% efficiency in removing freon test gas.

    • Except that recirculating charcoal filter samples shall be removed and analyzed at least once per 18 months.

3/4 7-5 Amend:ct.: S.^^

LA SALLE - UNIT 1

i.

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3.

X Verifying that on each of the below pressurization mode actuation test signals, the emergency train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch W.G. relative to the adjacent areas during emergency train operation at a flow rate less than or equal to 4000 cfa:

, a) Outside air smoke detection, and b) Air intake radiation monitors.

2 JK Verifying that the heaters dissipate 20 t 2.0 Kw when tested in accordance with ANSI N510-1975. This reading shall include the appropriate correction for variations from 480 volts at the bus. l

e. After each complete or partial replacement of a HEPA filter banP. by 1 verifying that the HEPA filter banks remove greater than or equal to 99% of the 00P when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 4000 cfm '

213. .

f. Aftegeach complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 4000 cfm 210%. . ,

l 5 l

1

" This surveillance shall include the recirculating charcoal filter, " odor eater,"

l in.the normal control room supply filter train using ANSI N510-1975 as a guide to verify >_ 70% efficiency in removing freon test gas.

I LA SALLE - UNIT 1 3/4 7-6 Amendment No. 26 y 4,y, ,,,,,-__y--.______--.---.-------------_----.---+-------_-_,,..c---,-----,---,__---------.---.,_.-----..------m--,,r--_.

r INSTRUMENTATION BASES MONITORING INSTRt#4ENTATION (Continued) 3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERA 8ILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is con-sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons i Learned Task Force Status Report and Short-Tern Recommendations".

I 3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made

~ without this flux level information available to the operator. When the inter-mediate range monitors are on scale adequate information is avafiable without

.the SRMs and they can be retracted.

7

3/4.3.7.7 TRAVERSING IN-CO'RE PRO 8E SYST m i

The OPERA 8ILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from

' use of this equipment accurately represent the , spatial neutron flux distribu l

tion of the reactor core.

3/ 6 7.8 AdONIADETECTIONSYSTEM The OPERA 8ILITY of the ammonia detection system ensures that an accidenta '

/ ammonia release will be detected promptly and the necessary protective actions l

/ will be automatically initiated to provide protection for control room per-l

[

sonnel. Upon detection of a high concentration of ammonia, the control room emergency ventilation system will automatically be placed in the recirculation mode of operation to provide the required protection. The detection systems required by this specification are consistent with the recommendations of Regula-

' tory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room Ouring a Postulated Hazardous Chemical Release."

3/4.3.7.9 FIRE DETECTION INSTRUMENTATION OPERA 8ILITY 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 reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

8 3/4 3-5 Amendment No. 20 LA SALLE - UNIT 2 *  ;

INDEX LIMITING E M ITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.3 INSTRUMENTATION 3/4 3-1 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION....................

3/4 3-9 3/4.3.2 ISCLATION ACTUATION INSTRUMENTATION...............'...........

3/4 3-23 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION......

3/4.3.4 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip System Instrumentation.......... 3/4 3-35 End-of-Cycle Recirculation Pump Trip System 3/4 3-39 Instrumentation............................................

1 3/4.3.5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 3/4 3-45

' INSTRUMENTATION............................................

3/4 3-50 3/4.3.6 CONTROL R00 WITHORAWAL BLOCK INSTRUMENTATION. . . . . . . . . . . . . . . . .

3/4.3.7 MONITORING IN'STRUMENTATION .

' Radi ati on Moni toring Instrumentation. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-57 Seismic Monitoring Instrumentation........................... 3/4 3-60 Meteorological Monitoring Instrumentation.................... 3/4 3-63 Remote Shutdown Monitoring Instrumentation................... 3/4 3-66 Accident Monitoring Instrumentation.......................... 3/4 3-69 .

Source Range Monitors........................................

3/4 3-72 l Traversing In-core Probe System.............................. 3/43-73g J/ l

[AmeoniaDetectionSystem.....................................

3/4 3-75 Fire Detection Instrumentation...............................

Radioactive Liquid Effluent Monitoring Instrumentatioi1....... 3/4 3-81 l

Radioactive Gaseous Effluent Monitoring Instrumentation...... 3/4 3-96 3/4 3-91 Loose-Part Detection System..................................

3/4.3.8 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION 3/4 3-92 INSTRUMENTATION.............................................

V Amendment No. 20 LA SALLE - UNIT 2

. Gtg e Cfchcd INSTRUMENTATION

~

  • r AM90NIA DETECTION SYSTEM LIMITING CONDITION FOR OPERATION h '

3.3.7.8 Two independent ammonia detection system subsystems shall be OPERA 8LE," l each with two ammonia detectors, with their alarm / trip setpoints adjusted to actuate at an ammonia concentration of less than or equal to 25 ppe.

/

APPLICA8ILITY: All OPERATIONAL CONDITIONS.

ACTION:

With one ammonia detector in either detection subsystem inoperable, l a.

l restore the inoperable detector (s) to OPERA 8LE 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 at least one control room charcoal filter system trai.n in the recircula-tion mode of operation.

l

b. With both ammonia ' detection subsystems inoperable, within I hour initiate and maintain operation of at least one control room charcoal filter system train in the recirculation mode of operation.
c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS l

4.3.7.8 Each of the above required ammonia detection system subsystems shall shall be demonstrated OPERA 8LE by performance of a CHANNEL FUNCTIONAL TEST 'at ~

least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

t l t { h I V' fM ' " C' l b l* " $ .

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  • The normal or emergency power source may be inoperable in OPERATI

\ .

3/4 3-74 Amepdment No. 20 LA SALLE - UNIT 2

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

' 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 zona communicating with the train by:

1. Verifying that the train satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a. C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the train flow rate is 4000 cfm i 10%.
2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulaton 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. ,
3. Verifying a train flow rate of 4000 cfm + 10% during subsystem -

operation when tested in accordance with ANSI N510-1975.  ;

c. After every 720** hours of charcoal adsorber operation by verifying f

) within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Positon C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboritory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d. 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 8 inches Water Gauge while operating the train at a flow rate of 4000 cfm t 10%.

[q Verif k that on a simulated ammonia detection signal, the re- l-circulating charcoal. filter automatically switches to the recircu-lation mode of operation and the isolation dampers close within 6 seconds.

.NThis surveillance shall incTude the recirculating charcoal filter, " odor eater, in the normal control room supply filter train using ANSI N510-1975 as a guide to verify ,>, 70% efficiency in removing freon test gas.

    • Except that recirculating charcoal filter samp,les shall be removed and l

! analyzed at least once per 18 months.

l 3/4 7-5 Amendment No. 20 l LA SALLE - UNIT 2 1

l

~

SURVEILLANCE REQUIREMENTS (Continued) 2 X Verifying that on each of the below pressurization mode actuation test signals, the emergency train automatically switches to the pressurization mode of operation and the control room is maintained at a positive pressure of 1/8 inch W.G. relative to the adjacent areas during emergency train operation at a flow rate less than or equal to 4000 cfa:

a) Outside air smoke detection, and b) Air intake radiation monitors.

Verifying that the heaters dissipate 20 2 2.0 Kw when tested in accordance with ANSI M510-1975. This reading shall include the appropriate correction for variations from 480 volts at the bus.

e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99% of the DOP when they are tested in place in accordance with ANSI N510-1975 whileoperatingthesystemataflowrateof4000cfag 2 10%. g i
f. Aftegeach complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in p1 tce in accordance with ANSI N510-1975 while operating the systei at a flow rate of 4000 cfm t 10%.

N .

"This surveillance shall include the recirculating charcoal filter, " odor eater,"

in the r.ormal control room supply filter train using ANSI N510-1975 as a guide to verify > 70% efficiency in removing freon test gas.

3/4 7-6 Amendment No.14 LA SALLE - UNIT 2

. - _ . - __ = -

l INSTRUMENTATION

< BASES NONITORING INSTRISIENTATION (Continued) 3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERA 8ILITY of the accident monitoring instrumentation ensures that sufficient information is available on seTected plant parameters to monitor and assess important variables following an accident. This capability is con-sistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0578, "TMI-2 Lessons

! Learned Task Force Status Report and Short-Tern Recommendations".

3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with infonsation of the status of the neutron level in the core at very low power levels during startup and shutdown. At these power levels, reactivity additions should not be made without this flux level information available to the operator. When the inter-mediate range monitors are on scale adequate information is available without 45 the SRMs and they can be retracted. j 3/4.3.7.7 TRAVERSING IN-CO'RE PRO 8E SYSTEM The OPERA 8ILITY of the traversing in-core probe system with the specified minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the . spatial neutron flux distribu-tion of the reactor core.

7.8 AM40NIA DETECTION SYSTEM

/ The OPERABILITY of the ammonia detection system ensures that an accidental

/ ammonia release will be detected promptly and the necessary protective actions

. / will be automatically initiated to provide protection for control room per-l /

' sonnel. Upon detection of a high concentration of ammonia, the control room emergency ventilation system will automatically be placed in the recirculation /l l

I mode of operation to provide the required protection. The detection systems l required by this specification are consistent with the recommendations of Regula-tory Guide 1.78, " Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room Ouring a Postulated Hazardous Chemical Release."

3/4.3.7.9 FIRE DETECTION INSTRUMENTATION OPERASILITY of the fire detection instrumentation ensures that adequate This w

, arning capability is available for the prompt detection of fires. cap stages. Prompt detection of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.

B 3/4 3-5 Amendment No. 20 LA SALLE - UNIT 2

7 --

ATTACESENT C TECHNICAL SPECIFICATION CHANGE RBOUEST LASALLE COUNTY STATION UNITS 1 AND 2 SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specifica-tion Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated because:

The probability of ammonia gas reaching the control room ventilation intake is very low. The Nuclear Station Operators can place the control ventilation system in the recirculation mode manually if necessary. Also the operators have an emergency breathing air supply readily available to them in the control room. The likelihood _of an ammonia release causing an accident, as described in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR), is remote.

(2) Create the possibility of a new or different kind of accident from any accident previously evaluated because:

Ammonia gas does not contribute to or cause or change any type of accident analysis in Chapter 15 of the UFSAR. Removal of the ammonia detectors will only affect the possibility of an ammonia release rendering the control room uninhabitable. The probability of this occurrence has been analyzed and determined to sufficiently low.

l (3) Involve a significant reduction in the margin of safety because:

1 The margin of safety is not significantly reduced because the probability of an ammonia gas release reaching the control room ventilation system intake and incapacitating the operators is small.

Guidance has been provided in Generic Letter 86-03 and 48 FR 14870 for the application of standards, to license change requests, for determination of the existence of significant hazards considerations. 48 FR 14870 provides examples of amendments that are considered not likely to involve a significant

hazards considerations. This amendment request appears to most closely fit example (vi) "A change which either may result in some increase to the probabi-lity or consequences of a previously-analyzed accident or may reduce in some way a safety margin, but where the results of the change are not clearly within all acceptable criteria with respect to the system or component specified in the Standard Review Plan." In 1975, Commonwealth Edison conducted surveys of local industries which determined that anhydrous ammonia was a hazardous chemical stored and transported in significant quantities near LaSalle Station.

At that time an analysis was not performed to determine if there was a signifi-cant threat to the control room environment. Prior to licensing of Unit 1, redundant ammonia detectors were installed in the control room air intakes since a detailed analysis was not performed to determine the potential affects on the plant of all ammonia sources. The detailed analysis has now been performed and it indicates that the probability.of ammonia gas rendering the station control room uninhabitable is remote.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10 CPR 50.92(e), the proposed change does not constitute a significant hazards consideration.

I 2814K l

7_

ATTACHMENT D

" HABITABILITY OF THE LASALLE COUNTY STATION CONTROL ROOM FOLLOWING POSTULATED ACCIDENT INVOLVING SHIPMENTS OF ANHYDROUS AMMONIA IN THE VICINITY OF LASALLE COUNTY STATION", DATED FEBRUARY, 198~1 2814K

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