ML20083M337

Proposed Tech Specs Re Relocation of Fire Protection Requirements

ML20083M337
Person / Time
Site:	Limerick
Issue date:	05/12/1995
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20083M329	List: ML20083M326 ML20083M337
References
NUDOCS 9505190210
Download: ML20083M337 (5)

Text

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ATTACHMENT 1 l l

LIMERICK GENERATING STATION UNIT 1 AND UNIT 2 Docket Nos.

50452 50-353 License Nos.

NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 89-10-0

' Relocation of Fire Protection Requirements' i

Revised Pages ,

1 Unit 1 Unit 2 FOL FOL B 3/4 3-6 B 3/4 3-6

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'9505190210 950512 PDR ADOCK 05000352 p PDR

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(3) Fire Protection (Section 9.5. SSER-2;-4)*

- Philadelphia Electric Company shall implement and ' maintain ~ in effect all provisions of the approved Fire Protection Program as described lin the Updated Final Safety Analysis' Report for the facility, and as approved in the NRC Safety Evaluation Report dated August 1983 through Supplement.9, dated August 1989, subject to the following provision:

The licensee may make changes to.the approved fire protection program -

without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the.

event of a fire.

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• The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed. ~

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i INSTRUMENTATION 1 ' .. .

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BASES 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified minimum co:plement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spacial neutron flux distribution of the reactor core.

The TIP system operability is demonstrated by normalizing all probes (i.e.,

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).

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 prom)tly and the necessary protective actions will be automatically initiated for c110-rine and manually initiated for toxic gas to provide protection for control room personnel. Upon detection of a hiin 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.

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There are three toxic gas detection subsystems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three subsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the ,

Wipped condition. Placing the keylock switch in the INOP position initiates one of l i the two inputs required to initiate the alarm in the Main Control Room. '

Specified surveillance intervals and maintenance outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowe1 Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D. l Binz, IV, fr.m C.E. Rossi dated July 21,1992).  ;

af_4J.7.9 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE TRM. ,

l LIMERICK - UNIT 1 B 3/4 3-6

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, ,3 (4); ' Pursuant.to theLAct an'd 10 CFR Parts 30, 40_and 70, to receive, l

possess, and use in amounts as required any byproduct, source or-  ;

special nuclear material without restriction-to chemical or-  ;

physical form, for sample' analysis or instrument calibration ~ or i associated with radioactive apparatus or components;land j (5) . Pursuant to the Act and 10 CFR Parts-30,140 and- 70, to pos :ef , l but-not separate, such byproduct and special nuclear.materi i as 1 may be produced by the operation of_the facility, and to receive _

and' possess, but not separate, such source, byproduct, and .

i special nuclear materials as contained in the fuel assemblies and fuel channels from the-Shoreham Nuclear Power Station. . .

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C. This license shall be deemed to contain and is subject to the ..

conditions specified in the Commission's regulations set forth in 10 ,

CFR Chapter I (except as exempted:from compliance in Section 2.D.

below) M is subject to all applicable provisions of the Act and to .

the rules, regulations, and orders of the Commission .now or. hereafter in effect; and is subject to the additional conditions specified or- i incorporated below: i (1) Maximum Power' Level j Philadelphia Electri Company is authorized to operate the j facility at reactor core power levels of 3458' megawatts thermal (100 percent' rated power) in accordance with the conditions  !

specified herein. l (2) Technical Soecifications ~- l The Technical Specifications contained in Appendix A and the . l Environmental Protection Plan contained in Appendix B, as~ revised l through Amendment No. , are hereby incorporated into this  ;

license. Philadelphia Electric Company shall' operate the 1 facility 'in .accordance with the Technical Specifications and the  !

Environmental Protection Plan.  ;

(3) 9 re' Protection (Section 9.5. SSER-2.-4)*

Philadelphia Electric Company shall implement and' maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the .

facility, and as approved in the NRC Safety Evaluation Report i dated August 1983 through Supplement 9,' dated August 1989, 1 subject to the following provision:

The licensee may make changes'to the approved fire protection ~)

program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and

, maintain safe shutdown in the event of a fire.

• The parenthetical notation following the title of license conditions denotes the'section of the Safety Evaluation Report and/or its supplements wherein-the: license condition is discussed.

. - _ .. , - ... .. - . i

y ,JJLTR)3ENTATION-BASES 3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified ninimum complement of equipment ensures that the measurements obtained ,from use of this equipment accurately represent the spacial neutron flux distribution of the reactor core.

The TIP system operability is demonstrated by normalizing all probes-(i.e.,

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).

3/4.3.7.8 CHLORINE AND T0XIC GAS DETECTION SYSTEMS The OPERABILITY of the chlorine and toxic pas detection systems ensures that an accidental chlorine and/or toxic gas re: ease will be detected promatly and the necessary protective actions will be automatically initiated for c110-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 emergersy 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, "Pri -  !

tection of Nuclear Power Plant Control Room Operators against an Accidental Chlorine Release," February 1975. _ .

There are three toxic-gas detection subsy. stems. The high toxic chemical concentration alarm in the Main Control Room annunciates when two of the three tabsystems detect a high toxic gas concentration. An Operate /Inop keylock switch is provided for each subsystem which allows an individual subsystem to be placed in the tripped condition. Placing the keylock switch in the INOP position initiates one of the two inputs required to initiate the alarm in the Main Control Room.

Specified surveillance intervals and maintenarce outage times have been determined in accordance with GENE-770-06-1, " Bases for Changes to Surveillance Test i Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," as approved by the NRC and documented in the SER (letter to R.D.  ;

Binz, IV, from C.E. Rossi dated July 21,1992). j 3/4.3.7.9 (Deleted) - INFORMATION FROM THIS SECTIO 4 RELOCATED TO THE TRM.

1 LIMERICK - UNIT 2 B 3/4 3-6