ML20045H539
| ML20045H539 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/12/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045H535 | List: |
| References | |
| NUDOCS 9307200345 | |
| Download: ML20045H539 (10) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 g.....,
GPU NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-73 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by GPU Nuclear Corporation (the licensee), dated August 1, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission 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; C.
There is reasonable assurance (i) 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 regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common 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 regulations and all applicable requirements have been satisfied.
9 9307200345 930712 PDR ADOCK 05000320 P
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 License No. DPR-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44, are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to March 28, 1979.
3.
This license amendment is, effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 2A d Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactors Support Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Appendix A Date of Issuance:
July 12, 1993
1 ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-73 4
DOCKET N0. 50-320 Replace the following pages of the Appendix A Technical Specifications with-the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 11 11 1-6 1-6 3.9-3 3.9-3 3.9-4 8 3/4 9-1 B 3/4 9-1 B 3/4 9-2 B 3/4 9-2 6-11 6-11 9
)
INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITION _S - (Continued) 1.21 CONTAINMENT ISOLATION.....................
1-6 1.22 OFFSITE DOSE CALCULATION MANUAL (ODCM).............. 1-6 1.23 MEMBER (S) OF THE PUBLIC 1-6 1.24 U N R ESTRICTED AREA................................. 1-6 1.25 SITE BOUNDARY 1-6 1.26 B A S E C A S E WATER................................... 1-6 F A CI LITY M O D ES (TA BLE 1.1)................................ 1-7 FREQUENCY NOTATION (TABLE 1.2)........................... 1-8 2.0 S A F ETY LI M ITS.......................
2-1 THREE MILE ISLAND - UNIT 2 ii Amendment 44 1
1.0 DEFINITIONS J
1.21 CONTAINMENT ISOLATION shall exist when:
'a.
Each penetration is:
1.
Closed by an accessible manual valve, a welded or bolted blind flange, or a deactivated automatic valve secured in the closed position to provide isolation of each penetration, or; 2.
Open per an approved procedure but can be closed pursuant to Specification 1.21.a.1.
Controls shall be implemented to minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open.
Penetrations shall be expeditiously closed upon completion of the conditions specified in the approved procedures.
b.
The Equipment Hatch is closed and sealed.
c.
Each Containment Airlock is OPERABLE pursuant to Specification 3.6.1.6.
1.22 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of off-site doses resulting from radioactive gases and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological 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 Report and the Annual Radioactive Effluent Release Report required by Specifications 6.9.1.1 and 6.9.1.2, respectively.
1.23 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
1.24 1)NRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
1.25 SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by GPU Nuclear.
1.26 BASE CASE WATER is ACCIDENT GENERATED WATER that contains the average activity levels provided in Table 2.2 of the Supplement 2 to the PEIS (NUREG-0683). These activity levels form the basis for the NRC staff's analysis of the environmental impacts of evaporator discharge.
THREE MILE ISLAND - UNIT 2 1-6 Amendment 44
pMiiINb LUNUI1IUN5 PUJ,,$ghKA IIUN J
AUXILIARY BUILDING AIR CLEANUP EXHAUST SYSTEh1 1
3.9.12.2 The Auxiliary Building Air Cleanup Exhaust System shall be OPERABLE with one of the four system air cleanup exhaust fans OPERABLE.
APPIICABILITY:
MODES 1, 2, and 3 ACTION:
With the Auxiliary Building Air Cleanup Exhaust System inoperable, restore the system to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or suspend all operations involving movement of liquid and solid radioactive wastes in the Auxiliary Building (other than sampling evolutions required by the Technical Specifications or RECOVERY OPERATIONS PLAN), the release of which could exceed 50% of the Appendix B Technical Specification instantaneous release rate for gaseous effluent, until the system is restored to OPERABLE status.
AC_CIDENT GENERATED WATER 3.9.13 When processing ACCIDENT GENERATED WATER through the Processed Water Disposal System (PWDS) Vaporizer, concentrations of radioactive contaminants (except tritium) in the vapor vented to the atmosphere shall, on a quarterly average, be less than or equal to the activity levels in Table 3.9-1. These activity levels equate to 0.1% of the concentrations for BASE CASE WATER.
APPLICABILITY: For the duration of ACCIDENT GENERATED WATER processing ACTION:
With the release rate (s) exceeding the above limit (s), or if any operating condition exists which would prevent the quarterly average activity levels to be maintained below those listed in Table 3.9-1, the environmental release will be terminated and corrective action taken.
THREE MILE ISLAND - UNIT 2 3.9-3 Amendment 44
TABLE 3.9-1 PROCESSED WATER DISPOSAL SYSTEM ENVIRONMENTAL RELEASE RATES (nC1/ml)
Environmental Release Rate Constituent limit Cesium-137 3.7E-8 Cesium-134 8.8E-10 Strontium-90 1.lE-7 Antimony-125/ Tellurium-125m 2.3E-9 Carbon-14 1.0E-7 Technetium-99 1.0E-9 Iron-55 4.8E-10 Cobalt-60 4.8E-10 Iodine-129
<6.0E-10 Cerium-144
<l.8E-9 Manganese-54
<4.0E-Il Cobalt-58
<4.0E-11 Nickel-63
<6.0E-10 Zinc-65
<9.8E-Il Ruthenium-106/ Rhodium-106
<3.3E-10 Silver-110m
<5.6E-11 Promethium-147
<4.8E-9 Europium-152
<3.8E-13 Europium-154
<4.4E-Il Europium-155
<l.lE-10 Uranium-234
<l.0E-11 Uranium-235
<l.2E-11 Uranium-238
<l.2E-Il Plutonium-238
<l.2E-11 Plutonium-239
<l.4E-Il Plutonium-240
<l.4E-11 Plutonium-241
<6.5E-10 Americium-241
<l.2E-Il Curium-242
<1.0E-10 THREE MILE ISLAND - UNIT 2 3.9-4 Amendment 44
3/4.9 RADIOACTIVE WASTE STORAGE BASES i
3/4.9.1 SPENT FUEL STORAGE POOL "A" WATER LEVEL MONITORING
+
i Spent Fuel Storage Pool "A" Water Level Monitoring instrumentation has been provided to assure
~
the capability to monitor water level in the Spent Fuel Storage Pool "A."
3/4.9.2 SPENT FUEL STORAGE POOL "A" WATER LEVEL The water level in the Spent Fuel Storage Pool "A" has been established to limit the dose rate, due to the storage of Canisters, to acceptable levels.
3/4.9.3 FUEL TRANSFER CANAL (DEEP END) WATER LEVEL MONITORING Fuel Transfer Canal Water Level Monitoring instrumentation has been provided to assure the capability to monitor water level in the deep end of the Fuel Transfer Canal.
3/4.9.4 FUEL TRANSFiiR CANAL (DEEP END) WATER LEVEL The water level in the Fuel Transfer Canal (deep end) has been established to limit the dose rate, due to the storage of the plenum assembly and Canisters, to acceptable levels.
3/4.9.12 FUEL HANDLING BUILDING /AU.JILIARY BUILDING AIR CLEANUP SYSTEM The requirement for the Fuel Handling Building / Auxiliary Building -Air Cleanup System to be operating or OPERABLE ensures that radioactive material released to these buildings will be filtered through the HEPA filters prior to release to the release to the atmosphere. In the event the systems are not restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the Technical Specifications require the suspension of any liquid or solid radioactive waste handling, the release of which could exceed 50%
of the instantaneous release rate limits for gaseous effluents specified in Section 2.1.2 of the Appendix B Technical Specifications. These restrictions correspond to solid radioactive waste with a total activity of greater than 1 curie of particulates with half-lives greater than eight (8) days and liquid radioactive waste with an activity greater than 0.5 curies of particulates with half-lives greater than eight (8) days.
3/4.9.13 ACCIDENT GENERATED WATER The analyses in Supplement 2 of the PEIS (NUREG-0683) assumed processing BASE CASE WATER with a vaporizer discharge to the atmosphere containing s0.1% of the radioactive particulates contained in the PWDS influent. Thus, the PEIS release values for effluent discharge have been established as the Limiting Condition for Operation.
THREE MILE ISLAND - UNIT 2 -
B3/4 9-1 Amendment 44
J/&9 RADIOACTlWE WASTE STORAGE
!!ASES _
The Processed Water Disposal System (PWDS) is designed to operate, in the coupled mode, with an overall system Decontamination Factor (DT) of at least 1000 for particulates. That is, the ratio of the concentration of a constituent in the influent stream to the concentration of the same constituent in the effluent vapor stream is equal te or greater than 1000. To comply with PElS (NUREG-0683) limits, periodic sampling is conducted to verify that system DF is at least 1000.
This sampling ensures that the effluents are within 0.1% of BASE CASE WATER concentrations, which are listed in Table 3.9-1.
When operating the vaporizer in the decoupled mode, the vaporizer feed shall be limited to concentrations of contaminants such that the resulting effluent shall be less than 1/1000 of BASE CASE WATER concentrations for all radionuclides except tritium.
Tritium is not included in Table 2.2 of the PEIS (NUREG-0683), Supplement 2, since the PWDS does not remove tritium. Tritium releases have been evaluated by the licensee in Section 5.1 of the PWDS Technical Evaluation Report (TER), which has been reviewed and approved by the NRC staff.
The activity releases resulting from PWDS processing and discharge of BASE CASE WATER are a small fraction of the releases permissible in accordance with existing regulatory requirements.
Even though higher levels of contaminant releases are permissible in accordance with 10 CFR 20 and the TMI-2 Appendix B Technical Specifications, and would be of very minor environmental consequence, the PWDS shall be operated in a manner such that the PElS (NUREG-0683) projections of environmental impact are not exceeded.
e THREE MILE ISLAND - UNIT 2 B3/4 9-2 Amendment 44
ADMINISTR^TIVE CONTROLS 6.8.2.1 Each procedure and any change to any procedure prepared pursuant to 6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.
6Property "ANSI code" (as page type) with input value "ANSI 18.7 - 1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..8.2.2 Deleted.
6.8.3.1 Temporary changes to procedures of 6.8.1 may be made provided that:
a.
The intent of the original procedure control is not altered, and b.
(1) For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License. (Note: The requirement for a Senior Reactor Operator's License applies during Mode 1 only.)
If one of the two above signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of that supervisory person within the department will also be required, or
- 2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization.
If one of the two above signatures is not by a section manager / director within the Department having cognizance of the procedure being changed, the signature of that section manager / director within the department will also be required, and c.
The change is documented, Independent Safety Review completed, and the required reviews and approvals are obtained within 14 days.
6.8.4 The following programs shall be established, implemented, and maintained:
a.
Radioactive EffluenLControls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) OF THE PUBLIC from radioactive effluents as low as is 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, l
THREE MILE ISLAND - UNIT 2 6-11 Amendment 44
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