ML18052A605
| ML18052A605 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 07/17/1986 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| TAC-61848, NUDOCS 8607230039 | |
| Download: ML18052A605 (18) | |
Text
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Docket No. 50-255 July 17', 1986 MEMORANDUM FOR:
FROM:
SUBJECT:
Charles E. Norelius, Director Divisi-0n of Reactor Projects Region III
- Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B PALISADES PLANT - AMENDMENT REQUEST to INCREASE ALLOWABLE QUANTITY OF SOURCE MATERIAL By application dated June 20, 1986,.Cqnsumers Power Company requested a change to the license condition for allowable Cs-137 quantities to 1000 Ci.
As.part of our evaluation of the acceptability of this increase, we ask that you provide us with input on the Palisades Health Physics Program as it might relate to handling and use of these stronger sources.
The* largest single source is 400 Ci.
We would appreciate your experience in monitoring and inspecting Palisades with regard to the H. P. qualifications, any overexposures related to source use, source accountability, and anything in this area that should be the subject of programmatic upgrading, if any.
In order to try to. meet the 1icensee 1 s *request for.urgency, we would appreciate a reply by August 30, 1986.
A copy of the application is enclosed.
The TAC No. fo,r this task is 61848.
Enclosure:
As stated
- cc w/enclo~~re:
L. R.*Greger, Region III' Distribution:
Docket File Memo File IS/
Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B t'.
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- ~= ~;~. '12 r POWERllWi MICHIGAN'S PROGRESS General Offices:
1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-1636 June 20, 1986
- Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSE AND TECHNICAL SPECIFICATIONS CHANGE REQUEST -
ALLOWABLE QUANTITY OF SOURCE MATERIAL Kenneth W Ber,Y Director Nuclear licensing Attached are three (3) originals and thirty-seven (37) conformed copies of a request to change the Palisades Provisional Operating License DPR-20 and the Palisades Technical Specifications.
The attached proposal requests a change to the allowable quantity of Cesium-137 as a-sealed calibration source specified in the Palisades Provisional Operating License.
An increase in this limit is required to allow possession of sealed sources for calibration of high range radiation detection instruments.
The addition of the Cesium-137 calibration source is to fulfill a commitment to INPO.
Since the receipt of this additional source is dependent upon approval of the requested License amendment we ask for prompt NRC action to approve this change.
The proposal also requests the addition of new technical specifications that describe the leak test requirement.s for sealed. sources.
The additional requirements are adopted from those provided in the CE Standard Technical Specifications (NUREG-0212, rev. 2) section 3/4.7.10.
A revised Table of Contents and correction of a typographical error are also included in this request.
In a letter dated January 24, 1975, to Consumers Power Company, Big Rock Point Docket 50-155, D L Ziemann, NRC, described improvements that could be made to the license in regard to special nuclear, byproduct, and source materials.
Enclosed with the letter were standardized requirements which removed reference to specific quantities of the materials.
The standardized requirements were suggested to licensees to circumvent the need for issuing, on a priority basis, a license amendment when the required quantities of on-site material were to be changed.
- The License Change Request herein does
~e06260309 Oe0b20 PDR ADDCK 05000255 P
PDR OC0686-0097-NL04
I -
Director, Nuclear Reactor Regulation Palisades Plant License & TSCR - Source Material June 20, 1986 not incorporate these requirements however it is our intent to submit an appropriate License Change Request in the near future that will be consistent with these requirements.
A check in the amount of $150.00 is enclosed as required by 10CFR170.21.
Kenneth W Berry Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Attachment OC0686-0097-NL04 2
CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Provisional Operating License DPR-20 and the Technical Specifications 1
For the reasons hereinafter set forth, it is requested that the Provisional Operating License DPR-20, and the Technical Specifications, Docket 50-255, issued to Consumers Power Company on October 16, 1972, for the Palisades Plant
.be changed as described in Section I below:
I.
Changes:
A.
Change item 2(C) of the Provisional Operating License to read:
"C.
Pursuant to the Act and 10CFR30, "Rules of General Applicability of Licensing of Byproduct Material", to receive, possess, and use in connection with operation of the facility 1500 curies of Polonium-210 as two sealed sources not to exceed 750 curies each, 1000 curies of Cesium-137 as multiple sealed calibration sources and up to 500 millicuries per nuclide of any byproduct material with Atomic Numbers 3 to 83, inclusive, without restriction to chemical and physical form to a total of 10 curies;"
B.
Revise the Table of Contents to remove deleted section 3.1.9, add Listing of Tables and Figures, add section 6.2.1 Sealed Source Contamination, and make miscellaneous corrections.
C.
Revise Table 3.17.4 note (g) to read:
"(g) Calculate the Quandrant Power Tilt using the excore readings at least once per *12 hours when the excore detectors deviation alarms are inoperable."
D.
Add a new Section 6.21 to read:
"6.21 SEALED SOURCE CONTAMINATION 6.21.1 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries qf alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
6.21.2 With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:
- 1.
Decontaminate and repair the sealed source, or TS0586-0001A-LI01-NL04
- 2.
Dispose of the sealed source-in accordance with applicable regulations.
6.21.3 Each category of sealed sources as described in 6.21.1 (excluding startup sources and fission detectors previously subjected to core flux) with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.
2 6.21.4 The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
6.21.5 The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.
6.21.6 The periodic leak test does not apply to sealed sources that are stored and not being used.
These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous six months.
Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
6.21.7 Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.
6.21.8 A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination."
II.
Discussion The proposed change requests an increase in the possession limit for Cesium-137 as sealed sources.
The change consolidat.es the individual listing of each Cesium-137 source into a single stated quantity.
In addition, a new administrative section is requested to describe the leak test requirements for calibration sources.
Also a typographical error that was incorporated in Amendment 96, 1/30/86 has been corrected in item I.C.
The increased Cesium-137 quantity limit is needed to allow the possession of a calibration source for high range radiation detection instruments.
The source will allow the verification of the accuracy of these instruments on all measurement scales.
This is a desirable TS0586-0001A-LI01-NL04
feature that can be expected to improve radiation protection capabilities.
The consolidation of the individual Cesium-137 sources into a single possession limit is intended to remove the need for further amendments.*
3 The additional administrative requirements are based on the guidance provided in the Standard Technical Specifications.
These requirements have been modified sufficiently for application to the Palisades Plant.
The significant variations and other items of interest are as follows:
- 1.
The proposed Section 6.21.5 includes provisions that allow for a test sample to be taken from the surface of a mounting device.
This allowance was deemed necessary to limit the potential dose received from attempting to achieve direct access to these sources.
- 2.
Current Technical Specifications provide record retention requirements for sealed source leak tests in Section 6.10.l(i).
Analysis of No Significant Hazards Considerations Possession of byproduct materials is licensed under the requirements of 10CFR30.
Typically, commercial nuclear plants have incorporated this byproduct license into the plant operating license.
Inclusion in the operating license necessitates an application for an amendment to the byproduct license through a more restrictive process than that prescribed by 10CFR30.
A request to amend a 10CFR30 byproduct license does not require an*
analysis of the significant hazards considerations.
As provided in 10CFR30.38, the application for amendment needs only to specify the desired changes and the grounds for the change.
This information has been detailed in the preceding Sections I and II.
Although not required by 10CFR30, the significant hazards evaluation of this change is presented in support of the request for an amendment to the operating license.
The effects of the additional administra-tive requirements are also presented.
The analysis is as follows:
- 1.
The requested changes do not result in an increase in the probability or consequences of a previously evaluated accident.
The change affects the allowable quantity of Cesium-137 as sealed source material.
~he change also provides additional admin-istrative requirements for the control of sealed sources.
The types of occurrences that would result from sealed sources are not evaluated in the FSAR.
Formal evaluation of these potential occurrences is not required to assure nuclear safety, and does not relate to nuclear safety or previously evaluated accidents.
TS0586-0001A-LI01-NL04
4
- 2.
The change does not create the possibility of a new or difreren:t~
kind of accident.
The operating license previously authorized the possession of sealed sources.
Potential occurrences from these sources were not required to be formally analyzed.
An analysis remains unnecessary for this category of occurrence.
The administrative requirements provided by this proposal result in additional controls not presently included in the Technical Specifications.
As such, these controls will enhance the radiation safety program and the control of sealed sources.
- Also, these requirements are not new in that the leak testing of sealed sources is an existing program.
This request only results in further emphasis on the importance of this program.
- 3.
The change does not result in a reduction in the margin of safety.
The increased possession limit affects an aspect of plant operation that is unrelated to nuclear safety.
The provisions for formalized leak testing requirements in conjunction with existing procedural controls are adequate to ensure no reduction in any type of radiological safety margin.
III.
Conclusion The Palisades Plant Review Committee has reviewed this Technical Specification Change Request and has determined that this change does not involve an unreviewed safety question and therefore involves no significant hazards consideration.
This change has also been reviewed under the cognizance of the Nuclear Safety Board.
A copy of this Technical Specification Change Request has been sent to the State ot Michigan official designated to receive such Amendments to the Operating License.
CONSUMERS POWER COMPANY Sworn and subscribed to before me this 20th day of June 1986.
Elaine E Buehrer, Notary Public Jackson County, Michigan My commission expires October 31, 1989 TS0586-0001A-LI01-NL04
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED PAGES PROPOSED TECHNICAL SPECIFICATIONS CHANGE REQUEST
-SSOQ2eO&l5 860620
~DR ADOCK 05000255 PDR TSP0686-0097-NL04 ALLOWABLE QUANTITY OF SOURCE MATERIAL June 20, 1986 10 Pages
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555 CONSUMERS POWER COMPANY (Palisades Plant)
DOCKET NO 50-255 PROVISIONAL OPERATING LICENSE License No DPR-20 Provisional Operating License No DPR-20, issued to the licensee for operation of the facility, on September 1, 1972, is hereby amended in its entirety to read as follows:
- 1. Provisional Operating License No DPR-20 applies to the Palisades Plant, a pressurized, light water moderated and cooled reactor, and electric generating equipment (the facility).
The facility is located in Covert Township on the Consumers Power site in Van Buren County, Michigan, and is described in the "Final Safety Analysis Report", as supplemented and amended.
- 2. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Consumers Power Company (the licensee):
A. Pursuant to Section 104b of the Atomic Energy Act of 1954, as amended (the Act), and 10 CFR Part50, "Licensing of Production and Utilization Facilities", to possess, use and operate the facility as a utilization facility at the designated location; B. Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material", to receive, possess and use 15,000 kilograms of Uranium-235 and 96 grams of encapsulated plutonium-beryllium in connection with operation of the facility; C. Pursuant to the Act and 10 CFR Part 30, "Rules of General Applicability of Licensing of Byproduct Material", to receive, possess and use in connection with operation of the facility 1500 curies of Polonium-210 as two sealed sources not to exceed 750 curies each, 1000 curies of Cesium-137 as multiple sealed calibration sources and up to 500 millicuries per nuclide of any byp'roduct material with Atomic Numbers 3 to 83, inclusive, without restriction to chemical and physical form to a total of 10 curies; TSP0686-0097-NL04
SECTION 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 2.3 3.0 3.0 3.1 Table 2.3.1 Figure 2-1 Figure 2-2 Figure 2-3 3.1.1 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 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 PAL TC PALISADES PLANT TECHNICAL SPECIFICATIONS.
TABLE OF CONTENTS - APPENDIX A DESCRIPTION DEFINITIONS REACTOR OPERATING CONDITIONS PROTECTIVE SYSTEMS INSTRUMENTATION SURVEILLANCE MISCELLANEOUS DEFINITIONS SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SAFETY LIMITS - REACTOR CORE SAFETY LIMITS -
PRIMARY COOLANT SYSTEM PRESSURE LIMITING SAFETY SYSTEM SETTINGS - REACTOR PROTECTIVE SYSTEM Reactor Protective System Trip Setting Limits Reactor Core Safety Limits 2 Pump Operation Reactor Core Safety Limits 3 Pump Operation Reactor Core Safety Limits 4 Pump Operation LIMITING CONDITIONS FOR OPERATION APPLICABILITY 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 Test Minimum Conditions for Criticality Maximum Primary Coolant Radioactivity Primary Cooiant System Leakage Limits Maximum Primary Coolant Oxygen and Halogens Concentrations Primary and S~condary Safety Valves Overpressure Protection Systems CHEMICAL AND VOLUME CONTROL SYSTEM EMERGENCY CORE COOLING SYSTEM CONTAINMENT COOLING STEAM AND FEEDWATER SYSTEMS CONTAINMENT SYSTEM ELECTRICAL SYSTEMS REFUELING OPERATIONS EFFLUENT RELEASE (DELETED).
i PAGE NO 1-1 1-1 1-3 1-3 1-4 2-1 2-1 2-3 2-4 2-5 2-11 2-12 2-13 3-1 3-1 3-lb 3-lb 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 3-41 3-46 3-50 Propo*sed
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SECTION 3.0 3.10 3.10.l 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS ~*APPENDIX A DESCRIPTION LIMITING CONDITIONS FOR OPERATION (Continued)
CONTROL ROD AND POWER DISTRIBUTION LIMITS Shutdown Margin Requirements Individual Rod Worth Part-Length Control Rods Misaligned or Inoperable Control Rod or Part-Length Rod Regulating Group Insertion Limits Shutdown Rod Limits Low Power Physics Testing Center Control Rod Misalignment Figure 3.11 3.11.l 3.11.2 3-6 Control Rod Insertion Limits POWER DISTRIBUTION INSTRUMENTS Incore Detectors Excore Power Distribution Monitoring System Figure 3.12 3.11-1 Axial Variation Bounding Condition 3.13 3.14 3.15 3.16 Table 3.16.l 3.17 Table 3.17.l Table 3.17.2 Table 3.17.3 Table 3.17.4 3.18 Table 3.18.1 3.19 3.20 Table 3.20.1 Table 3.20.2 3.21 3.22 3.22.1 Table 3.22.1 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES CONTROL ROOM VENTILATION REACTOR PRIMARY SHIELD COOLING SYSTEM ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENTATION SETTINGS Engineered Safety Features System Initiation Instrument Setting Limits INSTRUMENTATION AND CONTROL SYSTEMS Instrumentation Operating Requirements for Reactor Protective System Instrumentation Operating Requirements for Engineered Safety Feature Systems Instrument Operating Conditions for Isolation Functions
_Instrumentation Operating Requirements for-Other Safety Feature Functions SECONDARY WATER MONITORING REQUIREMENTS Secondary Water Monitoring Control Parameters IODINE REMOVAL SYSTEM SHOCK SUPPRESSORS (SNUBBERS)
Safety-Related Hydraulic Shock Suppressors (Snubbers)
Safety-Related Mechanical Shock Suppressors (Snubbers)
MOVEMENT OF SHIELDED CASK IN FUEL HANDLING AREAS FIRE PROTECTION SYSTEM Fire Detection Instrumentation Fire Detection Instrumentation - Minimum Instruments Operable ii PAGE NO 3-58 3-58 3-58 3-58 3-60 3-60 3-61 3-61 3-61 3-62 3-65' 3-65 3-66a 3-66d 3-67 3-69 3-70 3-70a 3-71 3-75 3-76 3-78 3-79
- 3-80 3-81 3-82 3-83 3-84 3-88 3-89 3-91 3-92 3-96 3-96 3-97 Proposed PAL TC
SECTION 3.0 3.22.2 3.22.3 3.22.4 3.22.5 3.23 3.23.l Table 3.23.l Table 3.23.2 Fig. 3.23-1 Fig. 3.23-2 Fig. 3.23-3 3.23.2 3.23.3 3.24 3.24.l Table 3.24-1 3.24.2 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTION LIMITING CONDITIONS FOR OPERATION (Continued)
Fire Suppression Water System Fire Sprinkler System Fire Hose Stations Penetration Fire Barriers POWER DISTRIBUTION LIMITS Linear Heat Rate (LHR)
Linear Heat Rate Limits Radial Peaking Factor Limits, F Allowable LHR as a Function of Peak Power Location Allowable LHR as a Function of Burnup Allowable LHR as a Function of Active Fuel Height for Interior Fuel Rods Radial Peaking Factors Quadrant Power Tilt - Tq RADIOLOGICAL EFFLUENT RELEASES Radioactive Liquid Effluent Monitoring Instrumentation Radioactive Liquid Effluent Monitoring Instrumentation Bases for 3.24.l Radioactive Gaseous Effluent Monitoring Instrumentation Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.24.3 3.24.4 3.24.5 3.24.5.l 3.24.5.2 3.24.5.2 3.24.6 3.24.7 3.24.8 Bases for 3.24.2
.Liquid Effluents Concentration Bases for 3.24.3 Liquid Effluent Dose Bases for 3.24.4 Gaseous Effluents Dose Bases for 3.24.5 Dose Rate Bases for 3.24.5.l Noble Gases Bases for 3.24.5.2 Dose - Iodine-i31, Iodine-133, Tritium and Radionuclides in Particulate Form Bases for 3.24.5.2 Gaseous Waste Treatment System Bases.for 3.24.6 Solid Radioactive Waste Bases for 3.24.7 Total Dose Bases for 3.24.8 iii PAGE NO 3-98 3-100 3-101 3-102 3-103 3-103 3-107 3-107 3-108 3-109 3-110 3-111 3-112 3-114 3-114 3-115 3-128 3-117 3-118 3-128 3-120 3-129 3-121 3-129 3-122 3-130 3-122 3-130 3-123 3-131 3-124 3-131 3-125 3-132 3-126 3-132 3-127 3-133 Proposed PAL TC
SECTION 4.0 4.1 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 4.6.1 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 PAL TC Table 4.11-1 Table 4.11-2 PALISADES PLANT TECHNICAL SPECIFICATIONS Tl!BLE OF CONTENTS - APPENDIX A DESCRIPTION SURVEILLANCE REQUIREMENTS INSTRUMENTATION AND CONTROL Minimum Frequencies for Checks, Calibrations and Testing of Reactor Protective System Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Feature Instrumentation Controls Minimum Frequencies for Checks, Calibrations and Testing of Misce1laneous Instrumentation and Controls 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 PRIMARY COOLANT SYSTEM INTEGRITY TESTING CONTAINMENT TESTS Integrated Leakage Rate Tests Local Leak Detection Tests Recirculation Heat Removal Systems Surveillance for Prestressing System End Anchorage Concrete Surveillance Liner Plate Surveillance Penetrations Surveillance Dome Delamination Surveillance SAFETY INJECTION AND CONTAINMENT SPRAY SYSTEMS TESTS Safety Injection System Containment Spray System Pumps Valves (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 RADIOLOGICAL ENVIRONMENTAL MONITORING Radiological Environmental Monitoring Program Reporting Levels for Radioactivity Concentrations in Environmental Samples iv PAGE NO 4-1 4-1 4-3 4-6 4-10 4-13 4-14 4-15 4-15c 4-16 4-19 4-23 4-24 4-25 4-25 4-27 4-28 4-29 4-30 4-31 4-32 4-32a 4-39 4-39 4-39 4-39 4-40 4-40 4-42 4-42 4-42 4-43 4-44 4-45 4-46 4..:..47 4-49 4-56 Proposed
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SECTION 4.0 Table 4. 11-3 4.11.1 4.11.3 4.11.5 4.12 4.13 4.14 Fig. 4.12 A Fig. 4.12 B Table 4.14.1 Table 4.14.2 4.15 4.16 4.17 4.17.1 4.17.2
. 4.17.3 4.17.4 4.17.5 4.18 4.18.1 4.18.2 4.19 4.19.1 4.19.2 4.20 4.21 4.22 4.23 4.24 4.24.1 4.24.2 4.24.3 4.24.4 4.24.5 PAL TC PALISADES *PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENtS - APPENDIX A DESCRIPTION SURVEILLANCE REQUIREMENTS (Continued)
Detection Capabilities for Environmental Sample Analysis Bases for Monitoring Program Bases for Land Use Census Bases for Interlaboratory Comparison Program AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT Augmented Inservice Inspection Program - Main Steam Welds Augmented Inservice Inspection Program - Feedwater Line Welds REACTOR INTERVALS VIBRATION MONITORING (DELETED)
AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS Operating Allowances Maximum Allowable Degradation PRIMARY SYSTEM FLOW MEASUREMENT INSERVICE INSPECTION PROGRAM FOR SHOCK SUPPRESSORS (SNUBBERS)
FIRE PROTECTION SYSTEM Fire Detection Instrumentation Fire Suppression Water System Fire Sprinkler System Fire Hose Stations P~net~ation Fire Barriers POWER DISTRIBUTION INSTRUMENTATION Incore Detectors Excore Monitoring System POWER DISTRIBUTION LIMITS Linear Heat Rate Radial Peaking-Factors (Intentionally Left Blank)
(Intentionally Left Blank)
(Intentionally Left Blank)
(Intentionally Left Blank)
(Intentionally Left Blank)
RADIOLOGICAL EFFLUENT RELEASES Radiological Liquid Effluent Monitoring Instrumentation Radiological Gaseous Effluent Monitoring Instrumentation Liquid Effluent Concentration Liquid Effluent Dose Gaseous Effluent Dose v
PAGE NO 4-57 4-59a 4-59a 4-59a 4-60 4-63 4-64 4-65 4-68 4-68d 4-69 4-70 4-71 4-75 4-75 4-76 4-78 4-79 4-80 4-81 4-81 4-82 4-83 4-83 4-84 4-85 4-86 4-87 4-88 4-89 4-90 4-90 4-90 4-90 4-90 4-90 Proposed
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SECTION 4.0 4.24.6 4.24.7 4.24.8 Table 4.24-1 Table 4.24-2 Table 4.24-3 Table 4.24-5 5.0 5.1 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 6.0 6.1 6.2 6.2.1 6.2.2 6.2.3 6.3 6.4 PAL TC Figure 6.2-1 Figure 6.2-2 Table 6.2-1 PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTION SURVEILLANCE REQUIREMENTS (Continued)
Gaseous Waste System Solid Radioactive Waste Total Dose Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements Radioactive Liquid Waste Sampling and Analysis Program Radioactive Gaseous Waste Sampling and Analysis Program DESIGN FEATURES
. SITE 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 Environment TLD Stations ADMINISTRATIVE CONTROLS RESPONSIBILITY ORGANIZATION Off site Plant Staff Nuclear Activities Plant Organization (NAPO)
PLANT STAFF QUALIFICATION TRAINING Consumers Power Company Offite Organization Consumers Power Company Plant Organization Minimum Shift Crew Composition vi PAGE NO 4-91 4-91 4-91 4-92 4-93 4-95 4-97 5-1 5-1 5-1 5-1 5-2 5-2 5.:-2 5-2 5-3 5-3 5-3 5-3 5-4 5-5 6-1 6-1 6-1 6-1 6-1 6-la 6-lb 6-lb 6-2 6-3 6-4
.Proposed
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SECTION 6.0 6.5 6.5.1 6.5.2 6.6 6.7 6.8 6.9 6.9.1 6.9.2 6.9.3 6.9.3.1 6.9.3.1.A 6.9.3.1.B 6.9.3.2 Table 6.9-1 6.* 9. 3. 3 6.10
- 6. ll 6.12 6.13 6.14 6.15 6.16 6.18 6.19 6.20 6.21 PAL TC PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A DESCRIPTION ADMINISTRATIVE CONTROLS (Continued)
REVIEW AND AUDIT Plant Review Committee (PRC)
Nuclear Safety Board (NSB)
(Deleted)
SAFETY LIMIT VIOLATION PROCEDURES REPORTING REQUIREMENTS Routine Reports Reportable Events Other Reporting Requirements Routine Reports Radioactive Effluent Releases Annual Radiological Environmental Operating Report Nonroutine Reports Environmental Radiological Monitoring Program Summary Special Reports RECORD RETENTION RADIATION PROTECTION PROGRAM HIGH RADIATION AREA FIRE PROTECTION INSPECTION ENVIRONMENTAL QUALIFICATION SYSTEMS INTEGRITY IODINE MONITORING OFFSITE DOSE CALCULATION MANUAL (ODCM)
MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS SEALED SOURCE CONTAMINATION vii PAGE NO 6-5 6-5 6-6a 6-10 6-10 6-10 6-ll 6-11 6-12 6-18 6-18 6-18 6-24 6-25b 6-25c 6-26 6-26 6-28 6-28 6-33 6-33 6-33 6-33 6-35 6-35 6-36 6-37 Proposed
Table 3.17.4 (Cont'd)
(g)
- Calculate the Quadrant Power Tilt using the excore readings at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the excore dete.ctors deviation alarms are inoperable.
(h)
With two flow rate indicators inoperable for a given control valve, the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.
3-Blb TSP0686-0097-NL04 Proposed
- ~.
'~ ~.
,r.
ADMINISTRATIVE CONTROLS 6.21 6.21.1 6.21.2 6.21.3 6.21.4
- 6. 21.5 6.21.6 6.21.7 6.21.8 SEALED SOURCE CONTAMINATION Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.
With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:
- 1.
Decontaminate and repair the sealed source, or
- 2.
Dispose of the sealed source in accordance with applicable regulations.
Each category of sea.led sources as described in 6. 21.1 with a half-life greater than 30 days (excluding Hydrogen-3), and in any*other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed six months.
The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State.
The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.
The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.
The periodic leak test does not apply to sealed sources that are stored and not being used.
These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous six months.
Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.
A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.
6-37 Proposed TSP0686-0097-NL04