ML20035G460
| ML20035G460 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/20/1993 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035G461 | List: |
| References | |
| NUDOCS 9304270273 | |
| Download: ML20035G460 (17) | |
Text
'.
/pm no v
O"
'n UNITED STATES 3
.DI E NUCLEAR REGULATORY COMMISSION
- [s.,v[f l4 WASHINGTON, D C. 20S56 o
PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No. NPF-39 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated January 8, 1993, 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.
9304270273 930420 PDR ADOCK 05000352 P
r t
l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-39 is hereby i
amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 60
, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
This license amendment is effective as of its date of issuance, to be implemented within 2 weeks from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION lY s
Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 20, 1993 i
I i
i 1
i i
ATTACHMENT TO LICENSE AMENDMENT NO.60 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 e
a h
Replace the following pages of the Appendix A Technical Specifications with l
the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*
7 Remove Insert 3/4 3-91 3/4 3-91*
3/4 3-92 3/4 3-92 3/4 3-92a 3/4 3-92a B 3/4 3-5 B 3/4 3-5*
f 8 3/4 3-6 B 3/4 3-6 1
k i
i s
t 1
i i
i l
l
^
INSTacwEs :'::N i
\\
T0xIC GA5 CE'ECTION SYSTEM l
l L:v:'!NG CONDI' ION EDE OPERATION 3.3.7.5.2 T-o incependent toxic gas detection system subsystems shall be ODERAELE witn tneir alarm setpoints adjusted to actuate at a toxic ga.s concen-tratico e' less tnan or equal to:
MONITOR i
SET POINT l
CHE"! CAL (opm) i Ammonia 25 Etnylene Oxide 50 Formaldehyde 5
vinyl Ch'orice 10 Phosgene 0.4 A?:LICABILITY:
All OPERATIONAL CONDITIONS.
i AC ION:
'aith one toxic gas detection subsystem inoperable, restore the inoperable detection system to OPERABLE status within 7 days or, i
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 emergency filtration system subsystem in the chlorine isolation moce of operation.
I With both toxic gas detection subsystems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> b.
initiate and maintain operation of at least one control room emer-gency filtration system subsystem in the chlorine isolation mode of operation.
SURVEILLANCE REQUIREWENTS 4.3.7.8.2 Each of the above required toxic gas detection system subsystems shall be demonstrated OPERABLE by performance of a-l CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a.
b.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and c.
CHANNEL CALIBRATION at least once per 18 months.
l l
LIMERICK - UNIT 1 3/4 3-91 Amencment No. 11 110V i IBBB
4 INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.9-1 shall be OPERABLE.
APPLICABILITY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
ACTION:
a.
With the number of OPERABLE fire detection instruments in one or more zones:
1.
Less than, but more than one-half of, the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside an inaccessible zone, then inspect the area surrounding the inaccessible zone at least once per hour.
2.
One less than the Total Number of Instruments shown in Table 3.3.7.9-1 for Function B, or one-half or less of the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A, or with any two or more adjacent instruments inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside an inaccessible zone, then inspect the area surrounding the inaccessible zone at least once per hour.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.9.1 The above required fire detection instruments which are accessible during unit operation shall be demonstrated OPERABLE:
a.
For smoke detectors, at least once per 12 months by performance of a CHANNEL FUNCTIONAL TEST.
b.
For heat detectors, at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST -on one or more detectors in each signal-initiation circuit.
Detectors shall be selected such that different detectors are-tested in each test. All detectors shall be tested at least once per 5 years.
LIMERICK - UNIT 1 3/4 3-92 Amendment No. II,60
INSTRUMENTATICN I
SURVEILLANCE REQUIREMENTS (Continued) c.
For all other types of fire detectors, at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detectors which are not accessible during unit operation shall be demonstrated l
OPERABLE by performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the past 12 months for smoke detectors, or 6 months for all other types of fire detectors.
4.3.7.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 12 months.
i l
l t
i l
t e
P
{
I i
LIMERICK - UNIT 1 3/4 3-92a Amendment No.60
BASES
(
3/4.3.7.2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
i This capability is required to permit comparison of the measured response to i
that used in the design basis for the unit.
i 3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.
3/4.3.7.4 REMOTE SHUTOOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of j
HOT SHUTDOWN of the unit from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with
{
General Design Criterion 19 of 10 CFR Part 50, Appendix A.
t 3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION i
The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and h
assess important variables following an accident. This capability is consistent with the recomendations 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-0737, " Clarification of TMI Action Plan Requirements,"
November 1980.
3/4.3.7.6 SOURCE RANGE MONITORS I
The source range monitors provide the operator with infonnation 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 shall not be n.ade without this flux level i
i information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can ':e retracted.
l 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM l
The OPERABILITY 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 distribution of the reactor Cort.
j i
The TIP system OPERABILITY is demonstrated by normalizing all probes (i.e.,
l detectors) prior to performing an LPRM calibration function.
Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to be OPERABLE. The OPERABILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector (s) output in the resultant heat balance calculation (P-1) with data obtained during a previous heat balance calculation (P-1).
LIMERICK - UNIT 1 B 3/4 3-5 Arte...dment No. 48,53
.;LLNGS 3 CIA LYL. /Z if W
\\
INSTRUMENTATION BASES 3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS The OPERABILITY of the chlorine and toxic gas detection systems ensures that an accidental chlorine and/or toxic gas release will be detected promptly and the necessary protective actions will be automatically initiated for chlo-rine and manually initiated for toxic gas to provide protection for control room personnel. Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine isolation mode of operation to provide the required protection. Upon detection of a high concentration of toxic gas, the control room emergency ventilation system will manually be placed in the chlorine isolation mode of operation to provide the required protection. The detection systems required by this speci-fication are consistent with the recommendations of Regulatory Guide 1.95, " Pro-tection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975.
3/4.3.7.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the detection instrumentation ensures that both adequate warning capability is available for prompt detection of fires and that fire suppression systems, that are actuated by fire detectors, will discharge extin-guishing agent in a timely manner.
Prompt detection and suppression of fires will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
Fire detectors that are used to actuate fire suppression systems represent l
a more critically important component of a plant's fire protection program than detectors that are installed solely for early fire warning and notification.
l Consequently, the minimum number of OPERABLE fire detectors must be greater.
i The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant degradation of fire protection for any area. As a result, the establishment of a fire watch patrol must be initi-ated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols in the affected areas is required to provide detection capability until the l
inoperable instrumentation is restored to OPERABILITY.
l, The surveillance requirements for demonstrating the OPERABILITY of the fire l
detectors are based on the recommendations of NFPA 72E - 1990 Edition.
i 3/4.3.7.10 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose-part detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components.
The allowable out-of-service times and surveillance requirements are consistent with the recom-i mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.
1 LIMERICK - UNIT 1 B 3/4 3-6 Amendment No. //S,60
faareg?V 2
3' F
'n UNITED STATES
/.i NUCLEAR REGULATORY COMMISSION I
'o '
f WASMNGTON. D C. 20555 Y
J
....+
L PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated January 8, 1993, 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common t
defense and security or to the health and 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.
t 6
f f t I
I i
2.
Accordingly, the license is amended by changes to the Technical l
Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby
}
amended to read as follows:
f Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental i
Protection Plan contained in Appendix B, as revised through Amendment
[
No. 25
, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the j
Technical Specifications and the Environmental Protection Plan.
l i
3.
This license amendment is effective as of its date of issuance, to be
{
implemented within 2 weeks from the date of issuance.
}
t FOR THE NUCLEAR REGULATORY COMMISSION i
i l$k '
i l
(x Charles L. Miller, Director Project Directorate 1-2 I
Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation
}
Attachment-I Changes to the i
Technical Specifications l
Date of Issuance: April 20, 1993 t
O i
\\
i
. ~ -.
i ATTACHMENT TO LICENSE AMENDMENT NO. 25 i
i FACILITY OPERATING LICENSE NO. NPF-85 DOCKET NO. 50-353 9
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and i
contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.*
f Remove Insert
{
s 3/4 3-91 3/4 3-91*
3/4 3-92 3/4 3-92 i
3/4 3-92a 3/4 3-92a
{
i B 3/4 3-5 B 3/4 3-5*
B 3/4 3-6 B 3/4 3-6 l
I 1
I i
i i
i f
I l
l i
?
[
i f
l INSTRUMENTATION T0XIC GAS DETECTION SYSTEM l
LIMITING CONDITION FOR OPERATION l
^
3.3.7.8.2 Two independent toxic gas detection system subsystems shall be OPERABLE with their alarm setpoints adjusted to actuate at a toxic gas concen-tration of less than or equal to:
MONITOR f
SET POINT i
CHEMICAL (ppm) i Ammonia 25 i
Ethylene Oxide 50 i
Fors. aldehyde 5
i Vinyl Chloride 10 j
Phosgene 0.4 f
APPLICABILITY:
All OPERATIONAL CONDITIONS.
r ACTION:
i With one toxic ~ gas detection subsystem inoperable, restore the a.
inoperable detection system to OPERABLE status within 7 days or, i
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 emergency filtration system subsystem in the chlorine isolation mode of operation..
b.
With both toxic gas detection subsystems inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> f
initiate and maintain operation of at least one control room emer-gency filtration system subsystem in the chlorine isolation mode of operation.
SURVEILLANCE REQUIREMENTS i
4.3.7.8.2 Each of the above required toxic gas detection system subsystems shall be demonstrate) OPERABLE by performance of a:
a.
CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
b.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and
[
c.
CHANNEL CALIBRATION at least once per 18 months.
i LIMERICK - UNIT 2 3/4 3-91
INSTRUMENTATION
+
' FIRE DETECT 10N' INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire l
detection zone shown in Table 3.3.7.9-1 shall be OPERABLE.
i APPLICABILITY:
Whenever equipment protected by the fire detection instrument is required to be OPERABLE.
I ACTION:
a.
With the number of OPERABLE fire detection instruments in one or
[
{
more zones:
1.
Less than, but more than one-half of, the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A, restore i
the inoperable Function A instrument (s) to OPERABLE status within 14 days or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol l'
to inspect the zone (s) with the inoperable instrument (s) at i
least once per hour, unless the instrument (s) is located inside j
an inaccessible zone, then inspect the area surrounding the inaccessible zone at least once per hour.
l 2.
One less than the Total Number of Instruments shown in l
Table 3.3.7.9-1 for Function B, or one-half or 'less of the Total
-l Number of Instruments shown in Table 3.3.7.9-1 for Function A, or with any.two or more adjacent instruments inoperable, within l
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> establish a fire watch patrol to. inspect,the zone (s) with "j
the inoperable instrument (s)~ at least once per hour, unless the instrument (s) is located inside an inaccessible zone, then ing F t i
the area surrounding the inaccessible zone at least once per hour.
I l
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS l
4.3.7.9.1 The above required fire detection instruments which are accessible during unit cperation shall be demonstrated OPERABLE:
a.
For smoke detectors, at least once per 12 months by performance of a CHANNEL FUNCTIONAL TEST.
b.
For heat detectors, at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST on one or more detectors in each signal-initiation circuit.
Detectors shall be selected such that different detectors are i
tested in each test. All detectors shall be tested at least once per j
5 years.
1 LIMERICK - UNIT 2 3/4 3-92 Amendment No. 25
i INSTRUMENTATION SURVEILLANCE REQUIREMENTS (Continued) c.
For all other types of fire detectors, at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless performed in the past 12 months for smoke detectors, or 6 months for all other types of fire detectors.
4.3.7.9.2 The NFPA Standard 72D supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 12 months.
i i
LIMERICK - UNIT 2 3/4 3-92a Amendment No.25
t E*5Ei i
i 3/4.3.7.2 SEISMIC MONITORING INSTRUMENTATION h
Tne OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
TMs capacility is recuired to permit comparison of the measured response to that used in the design basis for the unit.
3/4.3.7.3 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE OD 3/4.3.7.4 REMOTE SHUTOOWN SYSTEM INSTRUMENTATION AND CONTROLS The OPERABILITY of tne remote shutdown system instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the Control This capability is required in the event control room habitability is room.
lost and is consistent with General Design Criterion 19 of 10 CFR Part 50, Appendix A.
The Unit 1 RHR transfer switches are included only due to their i
potential impact on the RHRSW system, which is common to both units.
3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and i
assess important variables following an accident. This capability is consistent with the recornendations of Regulatory Guide 1.97, " Instrumentation for Light j
Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980.
3 /4. 3. 7. 6 SOURCE RANGE MONITORS i
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 j
ano shutdown.
At these power levels, reactivity additions shall not be made without this flux level information available to the operator.
When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM i
a The OPERABILITY of the traversing in-core probe system with the soecified l
minimum complement of equipment ensures that the measurements obtaind from use j
of this equipment accurately represent the spatial neutron flux distribution of l
the reactor core.
The TIP system OPERABILITY is demonstrated by nonnalizing all probes (i.e.,
i detectors) prior to performing an LPRM calibration function. Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to be OPERABLE.
The OPERABILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector (s) output in the resultant heat balance I
calculation (P-1) with data obtained during a previous heat balance calculation (P-1).
l L
t LIMERICK - UNIT 2 B 3/4 3-F Amendment No. II,17 tDJ4Gud DLeun n
/ Z /f 91
INSTRUMENTATION BASES l
3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS l
The OPERABILITY of the chlorine and toxic gas detection systems ensures that an accidental chlorine and/or toxic gas release will be detected promptly l
and the necessary protective actions will be automatically initiated for chlo-rine and manually initiated for toxic gas to provide protection for control room personnel.
Upon detection of a high concentration of chlorine, the control room emergency ventilation system will automatically be placed in the chlorine i
isolation mode of operation to provide the required protection.
Upon detection of a high concentration of toxic gas, the control room emergency ventilation l
i system will manually be placed in the chlorine isolation mode of operation to provide the required protection. The detection systems required by this speci-fication are consistent with the recommendations of Regulatory Guide 1.95, " Pro-tection of Nuclear Power Plant Control Room Operators against an Accidental i
Chlorine Release," February 1975.
3/4.3.7.9 FIRE DETECTION INSTRUMENTATION I
l OPERABILITY of the detection instrumentation ensures that both adequate warning capability is available for prompt detection of fires and that fire j
suppression systems, that are actuated by fire detectors, will discharge extin-guishing agent in a timely manner.
Prompt detection and suppression of fires j
will reduce the potential for damage to safety-related equipment and is an integral element in the overall facility fire protection program.
l Fire detectors that are used to actuate fire suppression systems represent a more critically importcnt component of a plant's fire protection program than l
detectors that are installed solely for early fire warning and notification.
j Consequently, the minimum number of OPERABLE fire detectors must be greater.
l The loss of detection capability for fire suppression systems, actuated by fire detectors, represents a significant degradation of fire protection for i
any area. As a result, the establishment of a fire watch patrol must be init.-
i ated at an earlier stage than would be warranted for the loss of detectors that provide only early fire warning. The establishment of frequent fire patrols j
in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY.
{
i The surveillance requirements for demonstrating the OPERABILITY of the fire detectors are based on the recomendations of NFPA 72E - 1990 Edition.
3/4.3.7.10 LOOSE-PART DETECTION SYSTEM l0 The OPERABILITY of the loose-eart detection system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate damage to primary system components. The allowable out-of-service times and surveillance requirements are consistent with the recom-
)
a mendations of Regulatory Guide 1.133, " Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.11 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.
LIMERICK - UNIT 2 B 3/4 3-5 Amendment No. II,25
_