ML18058B362

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Proposed Tech Specs Re Corrected Pages to Correct Editorial Errors in Amend 154 Radiological Environ TSs
ML18058B362
Person / Time
Site: Palisades Entergy icon.png
Issue date: 01/20/1993
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18058B361 List:
References
NUDOCS 9301280155
Download: ML18058B362 (11)
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Text

ENCLOSURE Consumers Power Company Pali sades Pl ant Docket 50-255 AMENDMENT 154 Corrected Technical Specifications Pages 9301280155 930120 PDR ADOCK 05000255 P

PDR 10 Pages

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION 1.0 DEFINITIONS 1.1 REACTOR OPERATING CONDITIONS 1.2 PROTECTIVE SYSTEMS 1.3 INSTRUMENTATION SURVEILLANCE 1.4 MISCELLANEOUS DEFINITIONS 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS - REACTOR CORE 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS Table 2.3.1 Reactor Protective System Trip Setting Limits B2.l Basis - Reactor Core Safety Limit B2.2 Basis - Primary Coolant System Safety Limit B2.3 Basis - Limiting Safety System Settings 3.0 LIMITING CONDITIONS FOR OPERATION 3.0 APPLICABILITY

3. I 3.2 3.3 3.4 3.5
3. I. I Figure 3-0 3.1.2 Figure 3-1 Figure 3-2 Figure 3-3 3.1.3 3.1.4 3.1.5 3.1.6 3.1. 7 3.1.8 PRIMARY COOLANT SYSTEM Operable Components Reactor Inlet Temperature vs Operating Pressure Heatup and Cooldown Rates Pressure - Temperature Limits for Heatup Pressure - Temperature Limits for Cooldown Pressure - Temperature Limits for Hydro Minimum Conditions for Criticality Maximum Primary Coolant Radioactivity Primary Coolant System Leakage Limits Maximum PCS Oxygen and Halogen Concentration Primary and Secondary Safety Valves Overpressure Protection Systems CHEMICAL AND VOLUME CONTROL SYSTEM EMERGENCY CORE COOLING SYSTEM CONTAINMENT COOLING STEAM AND FEEDWATER SYSTEMS 3.6 CONTAINMENT SYSTEM 3.7 3.8 3.9 Table 3.6.1 Containment Penetrations and Valves ELECTRICAL SYSTEMS REFUELING OPERATIONS Deleted PAGE NO 1-1 1-1 1-3 1-3 1-4 2-1 2-1 2-1 2-1 2-2 B2-l B2-2 B2-3 3-1 3-1 3-lb 3-1 b 3-3a 3-4 3-9 3-10 3-11 3-12 3-17 3-20 3-23 3-25 3-25a 3-26 3-29 3-34 3-38 3-40 3-40b 3-41 3-46 3-50 Amendment 154 January 1, 1993

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION 3.0 LIMITING CONDITIONS FOR OPERATION (continued) 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 Figure 3-6 CONTROL ROD AND POWER DISTRIBUTION LIMITS Shutdown Margin Requirements Deleted Part-Length Control Rods Misaligned or Inoperable Rod Regulating Group Insertion Limits Shutdown Rod Limits Low Power Physics Testin~

Center Control Rod Misalignment Control Rod Insertion Limits 3.11 POWER DISTRIBUTION INSTRUMENTATION 3.11.1 Incore Detectors PAGE NO 3-1 3-58 3-58 3-59 3-59 3-60 3-60 3-61 3-61 3-61 3-62 3.11.2 Excore Power Distribution Monitoring System Figure 3.11-1 Axial Variation Bounding Condition 3-65 3-65 3-66a

. 3-66d 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 3.13 Deleted 3-69 3.14 CONTROL ROOM VENTILATION 3-70 3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3-70a 3.16 ESF SYSTEM INITIATION INSTRUMENTATION SETTINGS 3-71 Table 3.16.1 ESF System Initiation Instrument Setting Limits 3-75 3.17 INSTRUMENTATION AND CONTROL SYSTEMS 3-76 Table 3.17.1 Instrument Requirements for RPS 3-78 Table 3.17.2 Instrument Requirements for ESF Systems 3-79 Table 3.17.3 Instrument Conditions for Isolation Functions 3-80 Table 3.17.4 Instrument Requirements for Other Safety Features 3-81 3.18 Deleted 3-82 3.19 IODINE REMOVAL SYSTEM 3-84 3.20 SHOCK SUPPRESSORS (Snubbers) 3-88 3.21 MOVEMENT HEAVY LOADS 3-92 3.22 Deleted 3-96 3.23 POWER DISTRIBUTION LIMITS 3-103 3.23.1 Linear Heat Rate 3-103 Table 3.23.1 Linear Heat Rate Limits 3-107 Table 3.23.2 Radial Peaking Factor Limits 3-107 Table 3.23-3 Power Distribution Measurement Uncertainty 3-107 Figure 3.23-1 Allowable LHR vs Peak Power Location 3-108 3.23.2 Radial Peaking Factors 3-111 3.23.3 Quadrant Power Tilt - Tq 3-112 3.24 Deleted 3.25 ALTERNATE SHUTDOWN SYSTEM Table 3.25.1 Alternate Shutdown Minimum Equipment i i 113 3-134 3-135 Amendment 154 January 1, 1993

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 4-1 4-le 4-le 4-3 4-6 4-10 4.0 SURVEILLANCE REQUIREMENTS 4.1 4.1. l 4.2 4.3 4.4 Table 4.1.1 Table 4.1.2 Table 4.1.3 Table 4.2.1 Table 4.2.2 Table 4.2.3 Table 4.3.1 Table 4.3.2 4.5 4.5.1 4.5.2 4.5.3 4.5.4 4.5.5 4.5.6 4.5.7 4.5.8 4.6 4.6.l 4.6.2 4.6.3 4-,6.4 4.6.5 4.7 4.7.1 4.7.2 4.7.3 4.8 4.9 4.10 4.11 4.12 4.-13 4.14 4.15 4.16 4.17 INSTRUMENTATION AND CONTROL Overpressure Protection Systems Frequencies for Testing of RPS Instrumentation Frequencies for Testing of EFS Instrumentation Frequencies for Testing of Misc. Instrumentation EQUIPMENT AND SAMPLING TESTS Minimum Frequencies for Sampling Tests Minimum Frequencies for Equipment Tests HEPA Filter and Charcoal Adsorber Systems SYSTEMS SURVEILLANCE Primary Coolant System Pressure Isolation Valves Miscellaneous Surveillance Items Deleted CONTAINMENT TESTS Integrated Leakage Rate Tests Local Leak Detection Tests Recirculation Heat Removal Systems Surveillance for Prestressin~ System End Anchorage Concrete Surveillance Containment Isolation Valves Deleted

_Dome Delamination Surveillance SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS Safety Injection System Containment Spray System Pumps Deleted Containment Air Cooling System EMERGENCY POWER SYSTEM PERIODIC TESTS Diesel Generators Station Batteries Emergency Lighting MAIN STEAM STOP VALVES AUXILIARY FEEDWATER SYSTEM REACTIVITY ANOMALIES Deleted AUGMENTED ISi PROGRAM FOR HIGH ENERGY LINES Deleted AUGMENTED ISi PROGRAM FOR STEAM GENERATORS PRIMARY SYSTEM FLOW MEASUREMENT ISi PROGRAM FOR SHOCK SUPPRESSORS (Snubbers)

Deleted i i i 4-13 4-14 4-15 4-15c 4-16 4-19 4-23 4-24 4-25 4-25 4-27 4-28a 4-29

  • 4-32 4-32 4-32a 4-32a 4-39 4-39 4-39 4-40 4-40 4-40 4-42 4-42 4-42 4-43 4-44 4-45 4-46 4-46 4-60 -65 4-66 4-70 4-71 4-75 Amendment 154 January 1, 1993

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION 4.0 SURVEILLANCE REQUIREMENTS (Continued) 4.18 4.18.1 4.18.2 4.19 4.19.1 4.19.2 POWER DISTRIBUTION INSTRUMENTATION Incore Detectors Excore Monitoring System POWER DISTRIBUTION LIMITS Linear Heat Rate Radial Peaking Facto,rs 4.20 MODERATOR TEMPERATURE COEFFECIENT (MTC) 4.21 ALTERNATE SHUTDOWN SYSTEM Table 4.21.1 Alternate Shutdown Monitoring System Surveillance Requirements 5.0 DESIGN FEATURES 6.0 5.1 SITE 5.2 5.2.1 5.2.2 5.2.3 5.3 5.3.1 5.3.2 5.3.3 5.4 5.4.1 5.4.2 Figure 5-1 CONTAINMENT DESIGN FEATURES Containment Structures Penetrations Containment Structure Cooling Systems NUCLEAR STEAM SUPPLY SYSTEM (NSSS)

Primary Coolant System Reactor Core and Control Emergency Core Cooling System FUEL STORAGE New Fuel Storage Spent Fuel Storage Site Environm~nt TLD Stations ADMINISTRATIVE CONTROLS 6.1 6.2 6.2.1 6.2.2 6.3 Table 6.2-1 6.4 6.5 6.5.1 6.5.2 6.5.3 RESPONSIBILITY ORGANIZATION Offsite and Onsite Organizations Plant Staff PLANT STAFF QUALIFICATIONS Minimum Shift Crew Composition TRAINING REVIEW AND AUD IT Plant Review Committee Nuclear Performance Assesment Department Plant Safety and Licensing iv PAGE NO 4-81 4-81 4-82 4-83 4-83 4-84 4-85 4-86 4-87 5-1 5-1 5-1 5-1 5-2 5-2 5-2 5-2 5-3 5-3 5-4 5-4 5-4a 5-5 6-1 6-1 6-1 6-1 6-2 6-3 6-4

  • 6-5 6-5 6-5 6-6a 6-9 Amendment 154.

January 1, 1993

SECTION PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS DESCRIPTION PAGE NO 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.6 6.7 6.8 6.9 6.9.1 6.9.1.a.

6.9.1.b 6.9.1.c 6.9.1.d 6.9.1.e 6.9.2 6.9.3 6.9.4 6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17 6.18 6.19 6.20 6.21 6.22 Deleted SAFETY LIMIT VIOLATION PROCEDURES AND PROGRAMS REPORTING REQUIREMENTS Routine Reports Start-up Report Annual Report 6-10 6-10 6-11 Monthly Operating Report Radioactive Effluent Release Report Radiological Environmental Operating Report Reportable Events Nonroutine Reports Special Reports 6-14 6-14 6-14 6-14 6-15 6-15 6-15 6-15 6-15 6-26 RECORD RETENTION RADIATION PROTECTION PROGRAM HIGH RADIATION AREA Deleted Deleted SYSTEMS INTEGRITY IODINE.MONITORING POST ACCIDENT SAMPLING OFFSITE DOSE CALCULATION MANUAL PROCESS CONTROL PROGRAM Deleted SEALED SOURCE CONTAMINATION SECONDARY WATER CHEMISTRY v

6-26 6-28 6-28 6-33 6-33 6-33 6-33 6-34 6-35 6-35 6-36 6-37 6-38 Amendment 154 January 1, 1993

3.9 EFFLUENT RELEASE DELETED IN ITS ENTIRETY 12 Pages 3-50 3-50a 3-51 3-51a 3-52 3-52a 3-53 3-53a 3-54 3-55 3-56 3-57 3-50 Amendment No 8-S, 154 January 1, 1993

e POWER DISTRIBUTION LIMITS 3.23.3 QUADRANT POWER TILT - Tq LIMITING CONDITION FOR OPERATION References (1)

FSAR, Section 7.4.2.2 (2)

FSAR, Se~tion 7.6.2.4 3.24 Deleted (Next page is 3-134) 3-113 Amendment No ~~' 1~~' 154 January 1, 1993

TABLE 4.1.3 Minilll.lll Frequencies for Checks, Calibrations and Testing of Miscellaneous lnstrunentation and Controls (Cont'd)

Channel Description

1.

Source Range Neutron Monitors

2.

Primary Rod Position Indication System

3.

Secondary Rod Position Indication System

4.

Area Monitors

5.

Emergency Plan Radiation lnstrunents

6.

(Deleted)

7.

Pressurizer Level lnstrunents Surveillance Function

a. Check
  • b. Test
c. Calibrate
a. Check
b. Check
c. Calibrate
a. Check
b. Check
c. Calibrate
a. Check
b. Calibrate
c. Test
a. Calibrate
b. Test
a. Check
b. Calibrate
c. Test frequency s

p R

s M

R s

M R

D R

M A

M s

R M

4-10 Surveillance Method

a. Corrparison of both channel count rate indications when in service.
b.

Internal test signals.

c. Channel aligrment through measurement/adjustment of internal test points.
a. Corrparison of output data with secondary RPIS.
b. Check of power dependent insertion limits monitoring system.
c. Physically measured rod drive position used to verify system accuracy.

Check rod position interlocks.

a. Corrparison of output data with primary RPIS.
b.

Same as 2Cb) above.

c. Same as 2Cc) above, including out-of-sequence alarm function.
a. Normal readings observed and internal test signals used to verify instrunent operation.
b. Exposure to known external radiation source.
c. Detector exposed to remote operated radiation check source or integral electronic check source.
a. Exposure to known radiation source.
b. Battery check.
a. Coq>arison of two wide and two narrow range independent level readings.
b.

Known differential pressure applied to sensor.

c. Signal to meter*relay adjusted with test device.

Amendment No. W, 'f'//, W, ~,

  • l)"/, l)JV, JJfJ, 154 January 1, 1993

I L -

ADMINISTRATIVE CONTROLS 6.8.4 The following programs shall be established, implemented, and maintained:

a.

Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the

. control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.

The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM,

2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR 20, Appendix B, Table II, Column 2.

3) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,
4)

Limitation on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR 50,

5)

Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR 20, Appendix B, Table II, Column 1.

6)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50,

7)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particul~te form with half-lives greater than -

8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50,

8)

Limitations on the annual doses or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR 190.

6-12 Amendment No. $~,~~,154 January 1, 1993

ADMINISTRATIVE CONTROLS 6.18 OFFSITE DOSE CALCULATION MANUAL (ODCM}

Changes to ODCM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.20. This documentation shall contain:

1)
2)

Sufficient information to support the change to~ether with the appropriate analyses or evaluations justifying the change(s) and A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 4 CFR 190, 10 CFR 50.36a, and Appendix I to 10 CFR 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b.

Shall become effective after the review and acceptance by the PRC and the approval of the Plant General Manager.

c. Shall be submitted to the Commission in the form of a compete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the 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.

6.19 PROCESS CONTROL PROGRAM Changes to the PROCESS CONTROL PROGRAM:

a.

Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.20. This documentation shall contain:

1)
2)

Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.

b.

Shall become effective after review and acceptance by the PRC and approval of the Plant General Manager.

6-35 Amendment No.

~~' 154 January 1, 1993

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