ML20092N249
| ML20092N249 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/02/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092N252 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9510050188 | |
| Download: ML20092N249 (13) | |
Text
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j Att Cro UNITED STATES g
j NUCLEAR REGULATORY COiJMISSION 1
4 WASHINGTON, D.C. 20066 0001
%q*****4 0
METROPOLITAN EDISON COMPANY j
JERSEY CENTRAL POWER & LIGHT COMPANY
]
PENNSYLVANIA ELECTRIC COMPANY i
GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 197 License No. DPR-50 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated June 1, 1995, as supplemented August 23, 1995, l
complies with the standards and requirements of the Atomic Energy j
Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
)
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the common l
defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have j
been satisfied.
i i
4
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating Licens a No.
DPR-50 is hereby amended to read as follows:
(2) Technical Soecifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 120 days of issuance.
i FOR THE NUCLEAR REGULATORY COMMISSION l4 I
Phillip F. McKee, Director i
Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications 4
Date of Issuance:
October 2, 1995 4
0 4
h m
f ATTACHMENT TO LICENSE AMENDMENT NO. 197 FACILITY OPERATING LICENSE NO. DPR-50 l
+
DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with 4
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove.
Insert i
t iii 111 iv iv vi vi 1-6 1-6 3-96 3-96 3-97 through 3-120 3-122 3-125 3-126 3-127 4-Sa 4-5a 4-87 4-87 4-88 through 4-122 6-11a 6-11a 6-11b 6-24 6-24 i
i
- ~
wt
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TABLE OF CONTENVS
'Soction Paae
'3.16 SHOCK SUPPRESSORS
' SNUB 8ERS) 3-63 3.17 REACT 04 $)ll.D :NG A R TEMPERATURE 3-80 3.18 F : E f ic EC7LUN (DELETED) 3-86 3.19 C0( 'A BM ( fT SYSTEMS 3-95 3.20 SP CIn EST EXCEP"LONS (DELETED) 3-95a 1
1 3.21 RA).0ACT"VE E "LUEN" INSTRUMENTATION (DELETED) 3-96 3.21.1 RADI0 ACTIVE LIQUl0 EFFLUENT INSTRUMENTATION (DELETED) 3-96 3.21.2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION (DELETED) 3-96 3.22 RADI0 ACTIVE EFF.UENTS (DELETED) 3-96 3.22.1 LIQUID EFFLUENTS (DELETED)-
3-96 3.22.2 GASEOUS EFFLUENTS (DELETED) 3-96 3.22.3 SOLID RADI0 ACTIVE WASTE (DELETED) 3-96 3.22.4 TOTAL DOSE (DELETED) 3-96 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING (DELETED) 3-96 3.23.1 MONITORING PROGRAM (DELETED) 3-96 3.23.2 LAND USE CENSUS (DELETED) 3-96
'3.23.3 INTERLABORATORY COMPARISON PROGRAM (DELETED) 3-96 3.24 REACTOR VESSEL WATER LEVEL 3-128
~4 SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 RlAC70R CD)LANT SYST EM INSERVICE INSPECTION 4-11 4.3 T EST PNi FOLLOWING OPGNING OF SYSTEM 4-28 4.4 R EAC"0R BUILDING 4-29 4.4.1 CONTAINMENT LEAKAGE TESTS 4-29 4.4.2 STRUCTURAL INTEGRITY 4-35 4.4.3 DELETED 4-37 4.4.4 HYDROGEN RECOMBINER SYSTEM 4-38 4.5 EMERGENCY LOA)!NG SEQUENCE AND POWER TRANSFER.
4-39 EMERGENCY COR ? COOL >$ SYSTEM AND REACTOR BUILDING COOL NG SYSTEM PER 001C TESTING
)
4.5.1 EMERGENCY LOADING Sf00ENCE 4-39 4.5.2 EMERGENCY CORE C00LIMG SYSTEM 4-41 4.5.3 REACTOR BUILDING CCUL!NG AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOVAL SYSTEM LEAKAGE 4-45 i
4.6
,tMERGENCY POWER SYSTEM P ERIDOIC TESTS 4-46 4.7 REACTOR CONTROL 000 SYST EM TESTS 4-48 4.7.1 CONTROL R00 DRIVE SYSTEM FUNCTIONAL TESTS 4-48 1
i 4.7.2 CONTROL R00 PROGRAM VERIFICATION 4-50 l
)
l i
-iii-j Amendment 11, $1,199,119,157,199,197, ISS,191,197 "b
di
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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 COOLANT TEMPERATURE 250*F OR LESS) 4.10 REACTIVITY AN0MALIES 4-53 4.11 REACTOR COOLANT SYSTEM VENTS 4-54 4.12 AIR TREATMENT SYSTEMS 4-55 4.12.1 EMERGENCY CONTROL RD0M 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 RADIOACTIVE 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 SH0CK SUPPRESSORS (SNUB 8ERS) 4-60 A.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 PROGR/.M (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, 2S, 39, (J, (7, 55, 72, 7S, 95, 97, JJ9, J22, 129, J77, JJS,197 so
LIST OF TAB!ES TABLE TITLE PAGE 1.2 Frequency Notation 1-8 2.3 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 3-29 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 l
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 i
j 4.21-2 DELETED s
4.22-1 DELETED 4.22-2 DELETED i
4.23-1 DELETED vi Amendment No. pp, 72,199, Jpp, lip, JJ7, Jig, JJ7, J59, J7),197 j
I
l l
l.9 ' DELETED i
1.10 DELETED 1.11 DELETED 1.12 DOSE EQUIVALENT I-131 The DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, 1-134 and I-135 l
actually present. The thyroid dnse 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".
[Or in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.]
1.13 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 COSE CALCULATION MANUAL (00CM)
The OFFSITE 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 monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The 00CM 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 proc #ssing 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 GASEOUS RADWASTE TREATMENT The GASE0US 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 c
environment.
1-6 Amendment No. 72, J77, J77,197
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3.21 RADIOACTIVE EFFLUENT INSTRUMENTATION Deleted 3.21.1 Radioactive Liquid Effluent Instrumentation Deleted 3.21.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation
)
Deleted 3.22 RADI0 ACTIVE EFFLUENTS 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 Deleted 3.23.1 Monitoring Program Deleted 3.23.2* Land Use Census Deleted 3.23.3 Interlaboratory Comparison Program Deleted
.r 3-96 (3-97 thru 3-127 deleted)
' Amendment No. 72, 7S, S5, SS, 19), 19(, J22, 129, J77, Jff, 157, J5S, J7),
J77, JS9, JS2,197 ve
_- ~.-..-
TABLE 4.1-1 (Continued)
~Eg CHANNEL DESCRIPTION CHECK TEST CALIBRATE ~
REMARKS
&g
- 27. Makeup Tank Level Channels D(1)
NA F
(1) When Makeup and Purification System is in operation.
r+
- 28. Radiation Monitoring Systems *
~
2'
- a. RM-G6 (FH Bridge #1 Aux)
W(1)(2)
M(2)
Q(2)
(1) Using the installed check source when 3 (g
- b. RM-G7 (FH Bridge #2 Main)
W(1)(2)
M(2)
Q(2) background is less than twice the expected increase in cpm which would.
- c. RM-G9 (FH Bridge-FH Bldg)
W(1)(3)
M(3)
E(3) result from the check source alone.
~<
35
- d. RM-A2P (RB Atmosphere particulate) W(1)(4)
M(4)
E(4)
Background readings greater than this
W(1)(4)
M(4)
Q(4) value are sufficient in themselves to
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ll
- 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 12 requirements are given in T.S. 3.8.1.
Surveillances are required to be current only when handling irradiated 1
fuel.
.< o
, jl (3) RM-G9 operability requirements are 35 given in T.S. 3.8.1.
~a.
.T (4) RM-A2 operability requirements are g;
given in T.S. 3.1.6.8.
%J
[
- 29. High and Low Pressure N/A N/A F
Injection Systems:
i Flow Channels l
i
- Includes only monitors indicated under this item. Other T.S. required radiation monitors are included in l
specifications 3.5.5.2, 4.1.3, Table 3-5.1 ites C.3.f and Table 4.1-1 item 19e.
1
[
+
' 4.21 RA0!0 ACTIVE EFFLUENT INSTRUMENTATION Deleted 4.21.1 Radioactive liquid Effluent Instrumentation Deleted 4.21.2 Radioactive Gaseous Process & Effluent Monitoring Instrumentation Deleted i
4.22 RADIOACTIVE EFFLUENTS Deleted 4.22.1 Liquid Effluents Deleted 4.22.2 Gaseous Effluents Deleted 4.22.3 Solid Radioactive Waste Deleted 4.22.4 Total Dose Deleted 4.23 RADIOLOGICAL ENVIRONMENTAL MONITORING Deleted 4.23.1 Monitoring Program Deleted 4.23.2' Land Use Census Deleted 4.23.3 Interlaboratory Comparison Program Deleted c
4-87 (4-88 thru 4-122 deleted)
Amendment No. 72, SS, 19f, Jig, 179, 177 JSJ, 173, J77, 197 ws
6.8.4
- a. Radioloaical Environmental Monitorina Procram l
A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential i
exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
j The program shall (1) be contained in the 00CM, (2) conform to the guidance of Appendix ! to 10 CFR Part 50, and (3) include the following:
(1).
Monitoring, sampling, analysis, and reporting of. radiation and i
radionuclides in the environment in accordance with the i
methodology and parameters in the 00CM, l
(2)
A Land Use Census to ensure that changes in the use of areas at 4
and beyond the SITE BOUNDARY are identified and that i
modifications to the monitoring program are made if required by the results of this census, and l
(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.
t
- b. Radioactive Effluent Controls Procram j
A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to i
MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably l
achievable.
The program (1) shall be contained in the 00CM, (2) shall j
be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The l
program shall include the following elements:
3 (1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and 1
)
setpoint determination in accordance with the methodology in the J
- 00CM, I
j (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 -
l 20.2402, Appendix B, Table 2, Column 2, l
(3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the 00CM, 4
i 6-11a Amendment No. W, 197 y-
j 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 i
materials in liquid effluents released from the unit to the site boundary conforming to Appendix I to 10 CFR Part 50, J
(5) Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance 4
with the methodology and parameters in the 00CM at least every 31 days, (6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the i
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 on the dose rate resulting from radioactive material released 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 mres/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 THE PUBLIC from Iodine-131, Iodine-133, tritium, and all i
radionuclides in particulate form with half-lives greater 1
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 I
(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 j
40 CFR Part 190.
l 6-llb 4
. Amendment No. 197 m
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6.14 0FFSITE 00SE CALCULATION MANUAL (00CM) 6.14.1 GPU Nuclear Corporation initiated changes to the 00CM:
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:
sufficiently detailed information to justify the changes a.
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 4
documentation that the changes have been reviewed and c.
approved pursuant to 6.8.2.
2.
Shall become effective upon review and approval by GPUNC Management.
l 4
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 2.
Containment Atmosphere' Sampling Each program shall be maintained and shall include the following:
l 1.
Training of personnel, 2.
Procedures, and 3.
Provisions for maintenance of sampling and analysis equipment.
6-24 Amendment No.
72, 77,192, J7),197 v.