ML20084N350
| ML20084N350 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/01/1995 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20084N349 | List: |
| References | |
| RTR-NUREG-1430 GL-89-01, GL-89-1, NUDOCS 9506080004 | |
| Download: ML20084N350 (10) | |
Text
TABLE OF CONTENTS l
Section Page 3.16 SH0CK SUPPRESSORS (SNUBBERS) 3-63 3.17 REACTOR BUILDING AIR TEMPERATURE 3-80 3.18 FIRE PROTECTION (DELETED) 3-86 3.19 CONTAINMENT SYSTEMS 3-95 3.20 SPECIAL TEST EXCEPTIONS (DELETED) 3-95a 3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION (DELETED) 3-96 3.21.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION (DELETED) 3-96 3.21.2 RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION (DELETED) 3-96 3.22 3-96 RADI0 ACTIVE EFFLUENTS (DELETED) 3.22.1 LIQUID EFFLUENTS (DELETED) 3-96 i 3.22.2 GASE0US EFFLUENTS (DELETED) 3-96 3.22.3 SOLID RADI0 ACTIVE WASTE (DELETED) 3-96 i
3.22.4 TOTAL DOSE (DELETED) 3-96 l 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING (DELETED) 3-96 1 3.23.1 MONITORING PROGRAM (DELETED) 3-96 1 3.23.2 LAND USE CENSUS (DELETED) 3-96 3.23.3 INTERLABORATORY COMPARIS0N PROGRAM (DELETED) 3-96 3.24 REACTOR VESSEL WATER LEVEL 3-128 4 SURVEILLANCE STANDARDS 4-1 l
4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION 4-11 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4-28 4.4 REACTOR BUILDING 4-29 4.4.1 CONTAINMENT LEAKAGE TESTS 4-29 ,
4.4.2 STRUCTURAL INTEGRITY 4-35 1 4.4.3 DELETED 4-37 4.4.4 HYDR 0 GEN RECOMBINER SYSTEM 4-38 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4-39 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 EMERGENCY LOADING SEQUENCE 4-39 ,
4.5.2 EMERGENCY CORE COOLING SYSTEM 4-41 l' 4.5.3 REACTOR BUILDING C0OLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOVAL SYSTEM LEAKAGE 4-45 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 4.7 REACTOR CONTROL R0D SYSTEM TESTS 4-48 1 4.7.1 CONTROL R0D DRIVE SYSTEM FUNCTIONAL TESTS 4-48 I 4.7.2 CONTROL R0D PROGRAM VERIFICATION 4-50 l
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-iii-Amendment 77, SJ, Jps, 179, J37, JH , U7, U S, 191, JDR50608o004 950601 p ADOCK 05000289
TABLE OF CONTENTS Section Page 4.8 MAIN STEAM ISOLATION VALVES 4-51 4.9 DECAY HEAT REMOVAL CAPABILITY - PERIODIC TESTING 4-52 !
4.9.1 EMERGENCY FEEDWATER SYSTEM - PERIODIC TESTING 4-52 (REACTOR COOLANT TEMPERATURE GREATER THAN 250*F) 4.9.2 DECAY HEAT REMOVAL CAPABILITY - PERIODIC TESTING 4-52a (REACTOR C0OLANT TEMPERATURE 250*F OR LESS) !
4.10 REACTIVITY ANOMALIES 4-53 4.11 REACTOR COOLANT SYSTEM VENTS 4-54 4.12 AIR TREATMENT SYSTEMS 4-55 4.12.1 EMERGENCY CONTROL ROOM AIR TREATMENT SYSTEM 4-55 ;
4.12.2 REACTOR BUILDING PURGE AIR TREATMENT SYSTEM 4-55b <
4.12.3 AUXILIARY AND FUEL HANDLING BUILDING AIR TREATMENT 4-55d SYSTEM 4.13 RADI0 ACTIVE MATERIALS SOURCES SURVEILLANCE 4-56 4.14 DELETED 4-56 4.15 MAIN STEAM SYSTEM INSERVICE INSPECTION 4-58 4.16 REACTOR INTERNALS VENT VALVES SURVEILLANCE 4-59 4.17 SHOCK SUPPRESSORS (SNUBBERS) 4-60 l 4.18 FIRE PROTECTION SYSTEMS (DELETED) 4-72 4.19 OTSG TUBE INSERVICE INSPECTION 4-77 4.19.1 STEAM GENERATOR SAMPLE SELECTION AND INSPECTION 4-77 METHODS 4.19.2 STEAM GENERATOR TUBE SAMPLE SELECTION AND INSPECTION 4-77 4.19.3 INSPECTION FREQUENCIES 4-79 4.19.4 ACCEPTANCE CRITERIA 4-80 4.19.5 REPORTS 4-81 4.20 REACTOR BUILDING AIR TEMPERATURE 4-86 4.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION (DELETED) 4-87 4.21.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION (DELETED) 4-87 4.21.2 RADI0 ACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING MONITORING INSTRUMENTATION (DELETED) 4-87 4.22 RADI0 ACTIVE EFFLUENTS (DELETED) 4-87 4.22.1 LIQUID EFFLUENTS (DELETED) 4-87 4.22.2 GASE0US EFFLUENTS (DELETED) 4-87 4.22.3 SOLID RADI0 ACTIVE WASTE (DELETED 4-87 4.22.4 TOTAL DOSE (DELETED) 4-87 4.23.1 MONITORING PROGRAM (DELETED) 4-87 4.23.2 LAND USE CENSUS (DELETED) 4-87 4.23.3 INTERLABORATORY COMPARISON PROGRAM (DELETED) 4-87 iv Amendment No. JJ, 75, S@, JJ, 57, 55, 72, 7S, 95, 97, JJP, JRR, 179, I Jil, 199, J
I LIST OF TABLES TABLE- TITLE PAGE-1.2 Frequency Notation 1-8 2.3-1 Reactor Protection System Trip Setting Limits 2-9 3.1.6.1 Pressure Isolation Check Valves Between the 3-15a Primary Coolant System and LPIS 3.5-1 Instruments Operating Conditions 3 3.5-1A DELETED 3.5-2 Accident Monitoring Instruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d 3.21-1 DELETED 3.21-2 DELETED 3.23-1 DELETED 3.23-2 DELETED 4.1-1 Instrument Surveillance Requirements 4-3 4.1-2 Minimum Equipment Test Frequency 4-8 4.1-3 Minimum Sampling Frequency 4-9 4.1-4 Post Accident Monitoring Instrumentation 4-10a 4.19-1 Minimum Number of Steam Generators to be 4-84 Inspected During Inservice Inspection 4.19-2 Steam Generator Tube Inspection 4-85 4.21-1 DELETED 4.21-2 DELETED 4.22-1 DELETED 4.22-2 DELETED 4.23-1 DELETED vi Amendment No. 59, 77, Jpp, Jpp, 11S, JJ7, JJE, JJ7, 159, J77,
1.9 DELETED 1.10 DELETED f 1.11 DELETED f
1.12 DOSE EQUIVALENT I-131 j l
The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the i quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 !
I actually present. The thyroid dose conversion factors used for this !
calculation shall be those listed in Table III of TID 14844, " Calculation of Distance Factors for Power and Test Reactor Sites". [0r in Table E-7 of NRC l Regulatory Guide 1.109, Revision 1, October 1977.] '
l.13 SOURCE CHECK A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
1.14 DELETED
, 1.15 0FFSITE DOSE CALCULATION MANUAL (ODCM) l l 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 effluent, in the calculation of gaseous and liquid effluent monitcring 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 Release Reports required by Specifications 6.9.3 and 6.9.4.
1.16 PROCESS CONTROL PROGRAM (PCP)
The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste.
1.17 GASE0US RADWASTE TREATMENT l The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the l
environment.
1-6 Amendment No. 77, 177, 177, 1 .- -_ __
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3.21 RADI0 ACTIVE EFFLUENT INSTRUMENTATION l Deleted 3.21.1 Radioactive Liquid Effluent Instrumentation Deleted 3.21.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation )
i Deleted 1
3.22 RADI0 ACTIVE EFFLUENTS j 1
i Deleted ;
3.22.1 Liquid Effluents :
Deleted 3.22.2 Gaseous Effluents ,
Deleted ,
3.22.3 Solid Radioactive Waste ,
Deleted 3.22.4 Total Dose Deleted .;
3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING l Deleted :
3.23.1 Monitoring Program Deleted 3.23.2 Land Use Census Deleted -
3.23.3 Interlaboratory Comparison Program Deleted i
3-96 (3-97 thru 3-127 deleted) ;
Amendment No. 77, 7S, 55, SS, 19), J99, JER, IEP, J)7, Jf9, J57, JES, 77),
J77, JSP, JSE,
i TABLE 4.1-1 (Continued) il CHANNEL DESCRIPTION CALIBRATE g CHECK TEST REMARKS
- 27. Makeup Tank Level Channels D(1) NA F (1) When Makeup and Purification System is A in operation.
- 28. Radiation Monitoring Systems *
- a. RM-G6 (FH Bridge #1 Aux) W(1)(2) M(2) Q(2) (1) Using the installed check source when g b. RM-G7 (FH Bridge #2 Main) W(1)(2) M(2) Q(2) background is less than twice the e expected increase in cpm which would g c. RM-G9 (FH Bridge-FH Bldg) W(1)(3) M(3) E(3) result from the check source alone.
y d. RM-A2P (RB Atmosphere particulate) W(1)(4) M(4) E(4) Background readings greater than this y e. RM-A21 (RB Atmosphere iodine) W(1)(4) M(4) Q(4) value are sufficient in themselves to g f. RM-A2G (RB Atmosphere gas) W(1)(4) M(4) E(4) show that the monitor is functioning.
~ (2) RM-G6 and RM-G7 operability E
requirements are given in T.S. 3.8.1.
Surveillances are required to be E" current only when handling irradiated fuel.
e M (3) RM-G9 operability requirements are
- 1 N 8 given in T.S. 3.8.1.
.E (4) RM-A2 operability requirements are given in T.S. 3.1.6.8.
- 29. High and Low Pressure N/A N/A F Injection Systems:
Flow Channels
- Includes only monitors indicated under this item. Other T.S. required radiation monitors are included in specifications 3.5.5.2, 4.1.3, Table 3-5.1 item C.3.f, and Table 4.1-1 item 19e.
L 4.21 RADI0 ACTIVE EFFLUENT-INSTRUMENTATION 7 Deleted
+e.
~
4.21.1 Radioactive Liquid Effluent Instrumentation i r
Deleted 4.21.2 Radioactive Gaseous Process & Effluent Monitoring Instrumentation Deleted !
4.22 RADI0 ACTIVE EFFLUENTS ;
Deleted 4.22.1 Liquid Effluents 1
Deleted 4.22.2 Gaseous Effluents Deleted j 4.22.3 Solid Radioactive Waste Deleted 4.22.4 Total Dose i
Deleted 4.23 RADIOLOGICAL ENVIRONMENTAL MONITORING Deleted r 4.23.1 Monitoring Program l Deleted 4.23.2 Land Use Census Deleted 4.23.3 Interlabora. tory Comparison Program Deleted 4-87 (4-88 thru 4-122 deleted)
Amendment No. 77, SS, J9J, JEE, 179, 177, 191, 177, 177, i
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6.8.4 a. Radiological Environmental Monitorina Program A program shall be provided to monitor the radiation and radionuclides in the envirens of the plant. The program shall provide (1) representative measurements of radioactivity in the highest _ potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
(1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, (2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and (3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
- b. Radioactive Effluent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive :- 71uents and for maintaining the doses to MEMBERS OF THE PUBLlt 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 times the concentrations specified in 10 CFR Part 20.1001 - 20.2402, Appendix B, Table 2, Column 2, (3) Monitoring, sampling, and analysis of radioactive liquid l and gaseous effluents in accordance with the methodology and parameters in the ODCM, 6-11a Amendment No. J7),
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- b. Radioactive Effluent Controls Program (continued)
(4) Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive mdterials in liquid effluents released from the unit to the site boundary conforming to Appendix I to 10 CFR Part 50, (5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, (6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, (7) Limitations an the dose rate resulting from radioactive material rr eased in gaseous effluents to areas at, or beyond, the site boundary. The limits are as follows:
(a) For noble gases: less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and (b) For I-131, I-133, tritium and all radionuclides in particulate form with half lives greater than 8 days:
less than or equal to 1500 mrem /yr to any organ.
(8) Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from the '
unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, (9) Limitations on the annual quarterly doses to a MEMBER OF l 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 the unit to areas beyond the site boundary conforming to Appendix I to 10 CFR Part 50, and (10) Limitations on the annual dose 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 Part 190.
4 6-llb I l
Amendment No.
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6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 GPU Nuclear Corporation initiated changes to the ODCM:
- 1. Shall be submitted to the NRC in the Annual Radioactive Effluent Release Report for the period in which the changes were made.
This submittal shall contain:
- a. sufficiently detailed information to justify the changes without benefit of additional or supplemental information;
- b. a determination that the changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations; and
- c. documentation that the changes have been reviewed and approved pursuant to 6.8.2.
- 2. Shall become effective upon review and approval by GPUNC Management.
6.15 DELETED 6.16 POST-ACCIDENT SAMPLING PROGRAMS NUREG 0737 (II.B.3. II.F.1.2)
Program which will ensure the capability to accurately sample and analyze vital areas under accident conditions have been implemented.
The following programs have been established:
- 1. Iodine and Particulate Sampling
- 3. Containment Atmosphere Sampling Each program shall be maintained and shall include the following:
- 1. Training of personnel, l
- 2. Procedures, and
- 3. Provisions for maintenance of sampling and analysis equipment.
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6-24 ,
1 Amendment No. 77, 77, JpE, J7),
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