ML20065A867

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Proposed Tech Specs Supporting Change in Frequency for Submitting Semiannual Effluent Release Rept to NRC from Semiannually to Annually
ML20065A867
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/24/1994
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20065A857 List:
References
NUDOCS 9404010095
Download: ML20065A867 (9)
v • d • e


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J ATTACHMENT 2 LIMERICK GENERATING STATION UNITS 1 AND 2 DOCKET NOS. 50-352 50-353 LICENSE NOS. NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST No. 9219-0 LIST OF AFFECTED PAGES -

_ynit 1 Unit 2 1-4 1-4 3/4 11-7 3/4117 6-17 6-17 6-22 6-22 9404010095 940324 PDR ADOCK 05000352 -.

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I ~ ' DEFINITIONS DRilC SYSIEM FUNCTIONAL TEST 1.20 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc, of a logic circuit, from sensor through and including the actuated device, to verify 0PERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be  !

performed by any series of sequential, overlapping or total system steps l such that the entire logic system is tested. l LOW (POWER) TRIP SETPOINT (LTSP) 1.20a The low power trip setpoint associated with the Rod Block Monitor (RBM) rod block trip setting applicable between 30% and 65% reactor thermal power.

1.21 (Deleted) ,

LiEMBER(S) 0F THE PUBLIC ,

1.22 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally l associated with the plant. This category does not include employees of i the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries, i This category does include persons.who use portions of the site for recrea- ,

tional, occupational, or other purposes not associated with the plant.

MAPFAC(F)-(MAPLHGR FLOW FACTOR) 1.22a A core flow dependent multiplication factor used to flow bias the standard Maximum Average Planar linear Heat Generation Rate (MAPLHGR) limit.

MAPFAC(P)-(POWER DEPENDENT MAPLHGR MULTIPLIER) 1.22b A core power dependent multiplication factor used to power bias the standard Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit.  !

MINIMUM CRITICAL POWER RATIO (MCPR) 1.23 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core (for each class of fuel). Associated with the minimum critical power ratio is a core flow dependent (MCPR(F)) and core power dependent (MCPR(P)) minimum critical power ratio.

0FFSITE DOSE CALCULATION MANUAL 1.24 The 0FFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct i of the Radiological Environmental Monitoring Program. The ODCM shall i also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent l Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY j 1.25 A system, subsystem, train, component or device shall be OPERABLE or have i OPERABILITY when it is capable of performing its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, i cooling or seal water, lubrication or other auxiliary equipment that are l required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

i LIMERICK - UNIT 1 1-4

RADI0 ACTIVE EFFLUENTS:

' LIOUID HOLDUP TANKS

[IMITINGCONDITIONFOROPERATION ___

L3.11.1.4_ The quantity of radioactive material' contained in any outside

temporary tanks shall be limited to less than or equal to 10 curies, excluding. ,

' tritium and dissolved or entrained noble gases.

APPLICABILITY: At all times. ,

AC1I911:

a, With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit and describe the events. leading to this condition in the next Annual Radioactive Effluent Release- l Report.

b. The provisions of Specification 3.0.3 are not applicable. .

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained ~ in each of the above tanks shall be determined to be within the above limit by analyzing a 'repre-sentative sample of the tank's contents at least once per 7 days when radio-active materials are being added to the tank.

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LlHERICK - UNIT 1 3/4 11-7 :l l

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ADMIUJSTRATIVE CONTROLS

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~ ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT

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-6.9.1.8 The . Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be sub .

mittedtwithin 60 days after January 1 of each year. The report shall include a. summary of the quantities-of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the. objectives outlined in the ODCM and PCP and (2) in-conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 1 10 CFR:Part 50. ,

  • A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

LIMERICK - UNIT 1 6-17 i

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j ADfjNTSTRAIJVE CONTROLS )

l PROCESS CONTROL PROGRAM (Continued)

2. A determination that the change did not reduce the overall i conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b. Shall become effective upon review and acceptance by the PORC and approval of the Plant Manager.

6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation .

shall contain:

1. Sufficient information to support the change together with the a appropriate analyses or evaluations justifying the change (s) and
2. A determination that the change will maintain the level of ,

radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective upon review and acceptance by the PORC and the approval of the Plant Manager.
c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l-report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, -

clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.

6.15 (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM. .

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LIMERICK - UNIT 1 6-22

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=0EFINITIONS '

LOGIC SYSTEM FUNCTIONAL TESI

-1.20 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc, of a logic circuit, from sen'sor through and including the actuated-device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

I MAXIMUM FRACTION OF LIMITING POWER DENSITY l 1.21 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall~be the highest )

value of the FLPD which exists in the core.  :

1 MEMBER (S) 0F THE PUBLIC L 1.22 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or.to make deliveries.

lhis category does include persons who use portions of the site for. r'ecrea-tional, occupational, or other purposes not associated with the plant.

MINIMUM CRITICAL POWER RATIO 1.23 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists in the core (for each class of fuel).

0FFSITE DOSE CALCULATION MANUA_L 1.24 The OFFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct'  ;

of the Radiological Environmental Monitoring Program. The ODCM shall ,

also contain (1) the Radioactive Effluent Controls and Radiological >

Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent l Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY 1.25 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and  ;

when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL CONDITION - CONDITION 1.26 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant tempera-ture as specified in Table 1.2.

PHYSICS TESTS 1.27 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

LIMERICK - UNIT 2 1-4

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RADI0 ACTIVE EFFLVENTS i

LIOUID HOLDVP TANKS JIMITINGCONDITIONFOROPERATION 3.11'.1 '4 The quantity'of radioactive material contained in any outside temporary tanks shall be limited to less than or equal to 10 curies, excluding triti~um and dissolved or entrained noble gases.

APPLICABILITY: At all times, q

ACTION: ,

a. With the quantity of radioactive material in any of the above tanks exceeding 'the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce-the tank contents to within the limit and describe the events leading to this condition in the next Annual Radioactive Effluent Release l Report.
b. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE0VIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of-the above tanks shall be determined to be within the above limit by analyzing a repre-

  • sentative sample of the tank's contents at least once per 7 days when radio- <

active materials are being added to the tank. -

I LIMERICK - UNIT'2 3/4.11-7

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INISTRATIVE CONTROLS

. ANNUAL 3ADI0 ACTIVE EFF LUENT RELEASE-REPORT

  • I 6;9.1.8 The' Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within'60 days after January _1 of each year. The initial
. report shall be submitted'during first report' period, as described above, following initial criticality. The report shall include a summary of the +

quantities of radioactive liquid and gaseous effluents and solid waste '

released from the unit. The material provided shall be (1) consistent with-

- the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. .s 5

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4 0A single submittal may be made for a multiple unit station.- The submittal should combine those sections that are common to all units at the station.

_ LIMERICK , UNIT 2 6-17

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gilNTSTRATIVE Q0NTROLS PROCESS CONTROL PROGRAM (Continued) ]

2. A determination that the change did not reduce the overall conformance of the solidified waste product to existing i requirements of Federal, State, or other applicable regulations. H
b. Shall become effective upon review and acceptance by thE PORC and approval of the Plant Manager, i 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 Changes to the ODCM:
a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3n. This documentation shall contain:
1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and- ,
2. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, ,

40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective upon review and acceptance by the PORC and the approval of. the Plant Manager,
c. Shall be submitted to the Commission in the form of a com'plete, legible copy of the entire 00CM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the I report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and 'shall  ;

indicate the date (e.g., month / year) the change was implemented.

LM (Deleted) - INFORMATION FROM THIS SECTION RELOCATED TO THE ODCM.

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'f LIMERICK - UNIT 2 6-22

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