ML20045H042

Errata to Amend 154 to License DPR-20,correcting Several Minor Typos & Providing Page 3-50 Inadvertently Omitted from Original Issuance

ML20045H042
Person / Time
Site:	Palisades
Issue date:	07/01/1993
From:	Office of Nuclear Reactor Regulation
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ML20045H043	List: ML20045H042
References
NUDOCS 9307160281
Download: ML20045H042 (11)

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9 ERRATA ATTACHMENT TO LICENSE AMENDMENT NO. 154 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

CORRECTED PAGES REMOVE INSERT i

i ii ii iii iii iV iV V

V 3-50 3-50 3-113 3-113 4-10 4-10 6-12 6-12 6-35 6-35 9307160281 930701 PDR ADOCK 05000255 p

PDR 3 -

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PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE N0 1.0 DEFINITIONS 1-1 1.1 REACTOR OPERATING CONDITIONS 1-1 1.2 PROTECTIVE SYSTEMS 13 1.3 INSTRUMENTATION SURVEILLANCE l-3 1.4 MISCELLANE0US DEFINITIONS 14 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1 2.1 SAFETY LIMITS - REACTOR CORE 2-1 2.2 SAFETY LIMITS - PRIMARY COOLANT SYSTEM PRESSURE 2-1 2.3 LIMITING SAFETY SYSTEM SETTINGS - RPS 2-1 Table 2.3.1 Reactor Protective System Trip Setting Limits 2-2 B2.1 Basis - Reactor Core Safety Limit B2-1 B2.2 Basis - Primary Coolant System Safety Limit B2-2 B2.3 Basis - Limiting Safety System Settings B2-3 3.0 LIMITING CONDITIONS FOR OPERATION 3-1 3.0 APPLICABILITY 3-1 3.1 PRIMARY COOLANT SYSTEM 3-lb 3.1.1 Operable Components 3-lb Figure 3-0 Reactor Inlet Temperature vs Operating Pressure 3-3a 3.1.2 Heatup and Cooldown Rates 34 Figure 3-1 Pressure - Temperature Limits for Heatup 3-9 Figure 3-2 Pressure - Temperature Limits for Cooldown 3-10 Figure 3-3 Pressure - Temperature Limits for Hydro 3-11 l

3.1.3 Minimum Conditions for Criticality 3-12 3.1.4 Maximum Primary Coolant Radioactivity 3-17 3.1.5 Primary Coolant System Leakage Limits 3-20 l

3.1.6 Maximum PCS 0xygen and Halogen Concentration 3-23 3.1.7 Primary and Secondary Safety Valves 3-25 3.1.8 Overpressure Protection Systems 3-25a 3.2 CHEMICAL AND VOLUME CONTROL SYSTEM 3-26 3.3 EMERGENCY CORE COOLING SYSTEM 3-29 3.4 CONTAINMENT COOLING 3-34 3.5 STEAM AND FEEDWATER SYSTEMS 3-38 3.6 CONTAINMENT SYSTEM 3-40 Table 3.6.1 Containment Penetrations and Valves 3-40b 3.7 ELECTRICAL SYSTEMS 3-41 3.8 REFUELING OPERATIONS 3-46 i

3.9 Deleted 3-50

(

i Amendment tio JSD, 154 Corrected Page

R j

PALISADES PLANT TELHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 1

3.0 LIMITING CONDITIONS FOR OPERATION (continued)

]

3.10 CONTROL' ROD AND POWER DISTRIBUTION LIMITS.

3 -

3.10.1 Shutdown Margin Requirements 3-58.

3.10.2 Deleted 3-59 3.10.3 Part-length Control Rods

3-59 3.10.4 Misaligned or Inoperable Rod.

3-60 3.10.5 Regulating Group Insertion Limits 3 60-3.10.6 Shutdown Rod Limits 3 61 3.10.7 Low Power Physics Testing 3-61 3.10.8 Center Control Rod Misalignment 3-61 Figure 3-6 Control Rod Insertion Limits 3-62 3.11 POWER DISTRIBUTION INSTRUMENTATION 3-65 1

3.11.1 Incore Detectors 3-65

.l 3.11.2 Excore Power Distribution Monitoring System 3-66a Figure 3.11-1 Axial Variation Bounding Condition 3 66d 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 3.13 Deleted 3-69 l

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 d

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 3-113 3.25 ALTERNATE SHUTDOWN SYSTEM 3-134 Table 3.25.1 Alternate Shutdown Minimum Equipment 3-135 s

ii Amendment JE2,154 Corrected Page

PALISADES PLANT TECHNICAL SPECIFICATIONS i

TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE RE0VIREMENTS 4-1 4.1 INSTRUMENTATION AND CONTROL 4-le 4.1.1 Overpressure Protection Systems 4-le Table 4.1.1 Frequencies for Testing of RPS Instrumentation 4-3 Table 4.1.2 Frequencies for Testing of EFS Instrumentation 46 Table 4.1.3 Frequencies for Testing of Misc. Instrumentation 4-10 l

4.2 EQUIPMENT AND SAMPLING TESTS 4-13 Table 4.2.1 Minimum Frequencies for Sampling Tests 4-14 Table 4.2.2 Minimum Frequencies for Equipment Tests 4-15 Table 4.2.3 HEPA Filter and Charcoal Adsorber Systems 4-15c 4.3 SYSTEMS SURVEILLANCE 4-16 Table 4.3.1 Primary Coolant System Pressure Isolation Valves 4-19 Table 4.3.2 Miscellaneous Surveillance Items 4-23 4.4 Deleted 4-24 4.5 CONTAINMENT TESTS 4-25 4.5.1 Integrated Leakage Rate Tests 4-25 4.5.2 Local Leak Detection Tests 4-27 4.5.3 Recirculation Heat Removal Systems 4-28a 4.5.4 Surveillance for Prestressing System 4-29 4.5.5 End Anchorage Concrete Surveillance 4-32 4.5.6 Containment Isolation Valves 4-32 4.5.7 Deleted 4-32a 4.5.8 Dome Delamination Surveillance 4-32a 4.6 SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS 4-39 4.6.1 Safety injection System 4-39 4.6.2 Containment Spray System 4-39 4.6.3 Pumps 4-40 4.6.4 Deleted 4-40 4.6.5 Containment Air Cooling System 4-40 4.7 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-42 4.7.1 Diesel Generators 6-42 4.7.2 Station Batteries 4-42 4.7.3 Emergency Lighting 4-43 4.8 MAIN STEAM STOP VALVES 4-44 4.9 AUXILIhRY FEEDWATER SYSTEM 4-45 4.10 REACTIVITY ANOMALIES 4-46 4.11 Deleted 4-46 4.12 AUGMENTED ISI PROGRAM FOR HIGH ENERGY LINES 4-60 4.13 Deleted 4-65 4.14 AUGMENTED ISI PROGRAM FOR STEAM GENERATORS 4-66 4.15 PRIMARY SYSTEM FLOW MEASUREMENT 4-70 4.16 ISI PROGRAM FOR SHOCK SUPPRESSORS (Snubbers) 4-71 4.17 Deleted 4-75 iii Amendment No. 252, 154 Corrected Page

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 4.0 SURVEILLANCE RE0VIREMENTS (Continued) l 4.18 POWER DISTRIBUTION INSTRUMENTATION 4-81 4.18.1 Incore Detectors 4-81 4.18.2 Excore Monitoring System 4-82 4.19 POWER DISTRIBUTION LIMITS 4-83 4.19.1 Linear Heat Rate 4-83 4.19.2 Radial Peaking Factors 4-84 4.20 MODERATOR TEMPERATURE COEFFECIENT (MTC) 4-85 4.21 ALTERNATE SHUTDOWN SYSTEM 4-86 d

Table 4.21.1 Alternate Shutdown Monitoring System Surveillance Requirements 4-87 5.0 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT DESIGN FEATURES 5-1 5.2.1 Containment Structures 5-1 5.2.2 Penetrations 5-2 5.2.3 Containment Structure Cooling Systems 52 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5-2 5.3.1 Primary Coolant System 5-2 5.3.2 Reactor Core and Control 53 5.3.3 Emergency Core Cooling System 5-3 5.4 FUEL STORAGE 5-4 5.4.1 New Fuel Storage 5-4 5.4.2 Spent Fuel Storage 5-4a Figure 5-1 Site Environment TLD Stations 5-5 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION 6-1 6.2.1 Offsite and Onsite Organizations 6-1 6.2.2 Plant Staff 6-2 6.3 PLANT STAFF QUALIFICATIONS 6-3 Table 6.2-1 Minimum Shift Crew Composition 6-4 6.4 TRAINING 6-5 6.5 REVIEW AND AUDIT 6-5 6.5.1 Plant Review Committee 6-5 6.5.2 Nuclear Performance Assesment Department 6-6a 6.5.3 Plant Safety and Licensing 6-9 iv Amendment ho. JAF, 154 Corrected Page

PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION DESCRIPTION PAGE NO 6.0 ADMINISTRATIVE CONTROLS (Continued) 6.6 Deleted 6-10 6.7 SAFETY LIMIT VIOLATION 6-10 6.8 PROCEDURES AND PROGRAMS 6-11 6.9 REPORTING REQUIREMENTS 6 14 6.9.1 Routine Reports 6 14 6.9.1.a Start-up Report 6-14 6.9.1.b Annual Report 6-14 6.9.1.c Monthly Operating Report 6 15 6.9.1.d

. Radioactive Effluent Release Report 6-15 6.9.1.e Radiological Environmental Operating Report _

6-15 6.9.2 Reportable Events 6 15 6.9.3 Nonroutine Reports 6-15 6.9.4 Special Reports 6-26 6.10 RECORD RETENTION 6-26 6.11 RADIATION PROTECTION PROGRAM 6-28 6.12 HIGH RADIATION AREA 6-28 6.13 Deleted 6-33 6.14 Deleted 6-33 6.15 SYSTEMS INTEGRITY 6-33 6.16 IODINE MONITORING 6-33 6.17 POST ACCIDENT SAMPLING 6 6.18 0FFSITE DOSE CALCULATION MANUAL 6 6.19 PROCESS CONTROL PROGRAM 6-35 6.20 Deleted 6-36 6.21 SEALED SOURCE CONTAMINATION 6-37 6.22

-SECONDARY WATER CHEMISTRY 6-38 1

Amendment No. 122,_154 Corrected Page

3.9 EFFLVENT RELEASE DELETED IN ITS ENTIRETY I

12 Pages 3-50 3-50a 3-51 3-51a 3-52 3-52a 3-53 3-53a i

3-54 3-55 3-56 3-57 i

3-50 Amendment No. Es, 154

E POWER DISTRIBUTION LIMITS 3.23.3 00ADRANT POWER TILT - T; LIMITING CONDITION FOR OPERATION References (1)

FSAR, Section 7.4.2.2 1

(2)

FSAR, Section 7.6.2.4 1

)

3.24 Deleted l

'I i

(Next page is 3-134)

-l 1

i 3-113 1

Amendment No. JAF, 154 Corrected Page' i

1

TAgtE 4.1.3 Minimum fregarries for Checks, Cet ibraticns and testing of Miscellaneous Instrisme t ti on and Controle (Cont'd) na Chemet Description Surveillance Fmc t ion freta.sency Survelltence Method I.

Source Range Neutron

a. Check Monitors S

a.

Casperison of both chamet count rate indicatione iAen in service.

b. Test P

b.

Internet test signals.

c. Calibrate R

c.

Channet eligrument through mesoureunent/ adjustment of internet test points.

2.

Primary Rod Poeltien

e. Check Indication System 5

b. Check Comparison of output data with secondary RPts.

e.

M b.

Check of power deperutent insertion limits monitorine system.

c. Calibrate R

c.

Physically measured rod drive position used to verify system accuracy. Check rod position interlocks.

3.

Secorriory Rod Position

s. Check Indication System 5

m.

b. Check Comperison of output data with primary RPIS.

M b.

Some as 2tb) above,

c. Cetibrate R

c.

Some es 2(c) above, including out of-sequence storm fmction.

4 Aree Monitors

a. Check 0

e.

Mormet readings cheerved and internet test signets

b. Catibrate used to verify instrument operation.

R b.

c. Test Estposure to knoin enternet radiation source.

M Detector erposed to remote operated radiation check source c.

w O

or integret electronic check source.

5.

Emergency Plan Radiation Instrumente

a. Calibrate A

b. Test Esposure to kneem radiatim source.

e.

M b.

Battery check.

6 (Deleted) l:

T.

Pressurizer levet

a. Check Ins truments 1

b. Calibrate Camperison of tuo ulde and two narrow range 44. A.t e.

R tevet readings.

b.

c. Test Knone dif ferential pressure applied to eenoor, M

c.

Signal to meter reley adjusted with test device.

7 3

fD CL o 53 r+

(D tb 3 CL r+

'Po w

b 4

M 4.M b

P I

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

l Radioactive Effluent Controls Proaram a.

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 particulate 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, B)

Limitations on the annual doses or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to i

radiation from uranium fuel cycle sources conforming to 40 CFR 190.

6-12 Amendment No. M. 154 Corrected Page

ADMINISTRATIVE CONTROLS 6.18 0FFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to ODCH:

Shall be documented and records of reviews performed shall be a.

retained as required by Specification 6.10.20.

This documentation shall contain:

1)

Sufficient information to support the change together with the appro change (s)priate analyses or evaluations justifying the and 2)

A determination that the chan n will maintain the level of radioactive effluent control iequired 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.

Shall be submitted to the Comission in the form of a complete, c.

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)

Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change (s) and 2)

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. EE, 154 Corrected Page