ML20033H017
| ML20033H017 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/23/1990 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20033H016 | List: |
| References | |
| NUDOCS 9004160050 | |
| Download: ML20033H017 (13) | |
Text
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. OPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 176 This Facility Operating License Amendment Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION
'l BY:
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Vice President & Director, TMI-1 Sworn and subscribed to before me this ef8^f
[
day of 111,n e / G, 1990.
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Notary Public Shvan P. kw y%
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9004160050 900323
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PDR ADOCK 03000289 P
Ia FAttLITY OPERATING LICENSE AMENDMENT REOUEST Not_276 CPUN requests that the attached revised page replace the following page of existing THI-1 Operating License No. DPR-50:
Replace Page 7.
II.
REASON FOR CHANGE section 103.c of the Atomic Energy Act of 1954 provides that a license is to be issued for a specified period not exceeding 40 years.
10 cFR 50.51 specifies that each license will be issued for a fixed period of time not to exceed 40 years from the date of issuance.
The current licensed term for THI-1 is 40 years commencing with issuance of the construction permit on May 18, 1968. Thus, the Facility operating License for THI-2 will expire at midnight May 18, 2000.
Accounting for the time that was required for plant construction, this reprecents an effective operating license term of 34 years rather than 40 years. Therefore, CPUN requests that the THI-1 Facility operating License be extended from May 18, 2008 to April 19, 2014 to refleet forty (40) years from the date of issuance of the full-power license.
This request represents a license extension of 5 years and la months to allow operation for the full design life.
Operation of THI-1 until April 19, 2014 will be both practicable and economical.
The plant is a major asset to Dauphin County and surrounding communities'by virtue of its ongoing contributions to the property tax base and secondary benefits to the local economy from employee payroll, and from expenditures for goods and services to operate the plant. As a baseloaded generating station, it provides power and stability to the Pennsylvania-New Jersey-Maryland interconnection. The additional years of plant operation allowed by the proposed change would defer the need to install replacement bcseload capacity, (which would result in substantial additional capital expenditures) or the need to purchase supplemental power from outside our system. Utilitation of domestic sources of energy such as nuclear power helps reduce our nation's dependence on expensive imported oil.
This change is consistent with actions taken by the Commission in granting similar license extensions for the period between construction permit issuance and full power license issuance.
III.
SAFETY EVALUATION JUSTIFYING CH.\\NGE The justification for this change addresses the suggested guidelines issued by NRC to supplement the hpril 30, 1985 policy letter from H. L. Thompson, Jr. to H. R. Denton on extending the operating life of nuclear power plants. These guidelines suggest thet the following four items be addressed: significant environmental impacts, pressurized thermal shock, equipment qualification and technical specifications for inservice inspection and testing.
I
- THI-1 w23 designed, C nstruct d cnd lic;n:ed f;r a 40-y;;r C:rv103 life as discussed in the TMI-1 Final Safety Analysis Report (FSAR).
This design life is based upon operation at a thermal power level of 2568 MWt with a cumulative lifetime capacity factor of 80s. The Unit cumulative capacity factor to date is less than 80%, due in part to the fact that TMI-1 was maintained in a cold shutdown condition for a period of approximately six years from 1979-1985. Accordingly, none of the licensing issues forming the basis for the initial issuance of the operating license need be reconsidered in connection with this proposed amendment, since the amendment, if granted, would be fully supported by the initial licensing record.
The rated thermal power upgrade to 2568 MWt was described in THI-1 Technical Specification Change Request No. 184 which resulted in License Amendment No. 143, dated July 26, 1988.
The 40-year service life design criteria does not imply that some equipment and components will not west out or require replacement during the plant lifetime. Design features were included in the construction and subsequent modification of THI-1 which ensure the ability to test, inspect, and perform preventive and corrective maintenance of the plant structures, systems and components.
Existing surveillance and maintenance programs are sufficient to maintain or determine the need for replacement of safety related components.
Periodic inservice inspection and testing requirements have been incorporated into the plant Technical Specifications and procedures to provide further assurance that any unanticipated degradation of safety related systems, equipment or structures will be identified and corrected in a timely manner.
A.
Eauipment Imnact 1.
Mechanical Equipment The primary side pressure boundary components within the Nuclear Steam Supply System (NSSS) scope were designed and constructed for a 40-yest design life.
The equipment design life is based on the time period of exposure to an operating environment.
The 40-year design life is equivalent to 32 Effective Full power Years (EFPYs).
During the plant construction, materials were not exposed to the operating environment except for system functional tests.
The system components were not subjected to a radiation environment until after the operating license became effective.
GPUN is committed to a periodic inservice inspection program for the Reactor Coolant System per Technical Specification Section 4.2.
Additional monitoring programs are currently in effect or are being developed to evaluate thermal / pressure cycles and to monitor fatigue effects on key components.
The B&W Owners Group Integrated Reactor Vessel Material Surveillanco 2
l
. Program (RAW-1543, Rev. 2A), approved by NRC f r TMI-1 in o lettCr dated May 27, 1986, provides the means for continuously monitoring the cumulative effects of the neutron esposure on the materials of the reactor vessel throughout the life of the plant.
The analyses of the THI-2 plant specific surveillance capsules have confirned that the predictione used in the analytical techniques for establishing operating limitations for the reactor vessel are conservative.
Future TMI-1 plant specific material surveillance capsules will be analyzed at specified times throughout plant life in order to continue to ensure that the predictions used in the analytical techniques for establishing future operating limitations for the reactor vessel remain conservative.
Equipment outside the NSSS scope which is safety-related were similarly designed and constructed, and are being inspected and tested by appropriate Technical Specification and ISI/IST program requirwments.
It is concluded that the above equipment, with any necessary replacement, will be satisf actory for a 40 year operating life.
2.
Pressurized Thermal Shock GPUN provided an assessment of the fracture toughness requirements for protection against pressurized thermal shock as required by 10 CFR 50.61 (5211-86-2007, January 23, 1986). That assessment concluded that the screening criteria would be met for the limiting weld at the expiration of the current operating license.
The NRC evaluation and acceptance of the fracture toughness assessment is documented in a safety evaluation for protection against pressurized thermal shock events, dated November 25, 1986.
Other recent THI-1 reactor pressure vessel fluence projections have been provided in B&W Topical Report BAW-1901, ' Analysis of capsule THI-1-C, GPUN, THIal, ' March, 1986 (GPUN letter to NRC 5211-86-2080, dated May 5, 1986).
Based on the analysis of capsule THI-1-C, the calculated cumulative fast fluences of the reactor vessel were below those previously projected, resulting in a reduction of the previously reported RTPTS. At the proposed license expiration date of April 19, 2014, TMI-1 core exposure is estimated at 2G' EPPY, assuming a 0.80 utilization factor (EFPY/ calendar year) for future cycles.
The accumulated fluence at the inside reactor vessel surface at 26 EFPY, assuming 24monthcycleswithamodifiedverylowleakagecogedesign, and operation at 2568 MWt, is new projected to be 6.8E18n/cm Utilizing Regulatory Guide 1.99, Revision 2, which is expected to be adopted for application to the PTS Evaluation in the near future, this fluence gives a PTS Evaluation reference temperature of 262*F at the critical weld (SA-1526) which meets the screening criteria of 270'F at the proposed license expiration date.
GPUN is monitoring reactor vessel fluence with external reactor cavity dosimetry installed for operating Cycle 7 and will continue to participato in efforts to refine the evaluation of material fracture toughness properties, fluence analyses and dosimetry and vessel flux reduction using improved cycle design techniques.
Any undesirable changes with respect to the screening criteria will be identified early and appropriate corrective actions er analyses undertaken.
Current fluence projections at the proposed license expiration date are therefore considered to be acceptable.
3112112 3.
3.
Electrical Equipnent and Environmental Ovalification The Environmental Qualification (E?) program for electrical equipment operating in & harsh Ouvironment is described in the TMI-1 FSAR, Appendix 63.
The program ensuree that EQ is maintained for required electrical equipment within the scope of 10 CFR $0.49.
Aging analyses have been perforned for safety-related electrical equipment in accordance with 10 CFR $0.49, Environmental Qualification, to identify qualified lifetines for this equipment.
These lifetines are incorporated into plant equipment maintenance and replacenent practices to ensure that safety-related electrical equipment remains qualified and available to perform its safety function regardless of the overall age of the plant.
Therefore, the electrical systems design, electrical equipment selection and application, and environmental qualification of electrical equipment has adequately considered or is not impacted by a 40-year operational lifetime.
The THI-1 EQ program was evaluated by NRC and found acceptable in a safety evaluation dated April 18, 1985.
4.
Spent Fuel storage spent fuel generated between 2008 and 2014 is not a concern with respect to spent fuel pool storage capacity.
The existing THI-1 spent-fuel pool racks will lose full core reserve margin after the refueling outage in 1991. GPUN has contracted for services to design, license and install new high density, poison spent fuel racks in the TMI-1 spent fuel pools.
While the design and'11 censing will provide for a maximum total safe capacity, the actual installation of new racks will occur in stages.
The first increment of rack installation in early 1992 is planned to include sufficient rack capacity to provide storage capacity through 2008. Additional racks can be added as necessary thereaf ter to support continued operation up to the new licensed limit.
In any event, it is anticipated that the new design using high density, poison racks will assure spent fuel storage capacity in the THI-1 spent fuel pools to provide storage capacity substantially in excess of that required to support operation through 2014 based on current operational plans.
g TMI-1 is currently operating on an 18 month cycle and is implementing 24 month cycles beginning with Cycle 9.
This will result in less total spent fuel generated than previously projected even with the extended operating period.
4
5.
Inservice Inspection (ISI) and Inservice Test (287) Programs The TM2-1 ongoing 182 and 2ST programs are maintained in accordance with 10 CrR 50.55a.
The surveillance requirements for the 282 and IST programs for AsME Code Class le Class 2, and Class 3 components are contained in TM2-1 Technical Specification Section 4.2, Reactor Coolant system.
The requirements for the IST program are specified by the racility operating License, No. DPR-50, Section C, license condition (6).
In addition to the 252 and 2ST programs, the following TM2-1 Technical specifications also provide additional requirements for monitoring, component aging and the cumulative effects of power operation over the life of the plant.
a)
Specification 4.19 - Once Through Steam Generator (OTSG) Tube Inservice Inspection.
This specification provides augmented 282 of the OTSO tube portion of the reactor coolant pressute boandary to assure continued integrity. The results of these augmented inspections are submitted by report to NRC and include:
- 1. Number and extent of tubes inspected
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
- 3. 2dentification of tubes repaired or removed from
- service, b)
Specification 3.1.2 Pressuritation Heatup and Cooldown Limitations Temperature and pressure changes during heatup, cooldown and normal operation of the reactor coolant system are limited to protect against non-ductile failure of the reactor coolant system. These limits are established in accordance with the requirements of 10 CFR 50, Appendix 0, and calculated utilizing the procedures defined in Regulatory Guide 1.99, Revision 2.
This specification includes a reactor vessel material surveillance program that monitors reactor vessel embrittlement over the 40-year design life in accordance with 10 CFR 50, Appendix H.
Reactor vessel irradiation specimens are removed and examined at specific intervals to determine changen in material properties. The results of these examinations are then submitted for NRC review and are used to update the pressure and temperaturi
.its.
5
.' 0 )
SpecificatiCn 4.2 Re;ctCr Coo 1Cnt System InserviO2 2n:pe;tiCn As described above, this specification contains the ISI and IST surveillance requirements for ASME Code Class 1, Class 2, and Class 3 components that ensure the continuing integrity of the reactor coolant system throughout the life of the plant.
In addition to the !$2 and !$T programs, this specification also contains requirements for special inspections of the reactor coolant pump motor flywheel assemblies and primary coolant system pressure isolation valves.
d)
Specification 3.19.1 Centainment structural Integrity This specification defines the inservice tendon surveillance-program for the reactor building prostressing system.
This j
surveillance program monitors potential tendon steel relaxation
.j or concrete creep and ensures continued structural integrity of i
the reactor building throughout the life of the plant.
i 4
e)
Specification 4.4.1 Containment Leakage Tests This specification establishes the requirements for the performance of periodic integrated and local leakage rate tests in accordance with 10 CFR 50, Appendix J.
These tests'are performed during the life of the plant to ensure that reactor building leakage remains within allowable linits.
B.
Environmental Imonet CPU:3 has reviewed the Environmental Reports (Environmental Report -
Operating License Stage, October 1, 1970 revised December. 10, 1971 and Amendments dated March 6. 1972 and April 30, 1973; Environmental Report - THI-2, February 28, 1975) to determine if this license expiration extension would involve any previously unconsidered environmental impacts.
Since these environmental reports were written presuming a 40 year plant life, we have identified no additional' impacts associated with plant operation for a 40 year operating period.
In conjunction with the effects of the. accident at TMI-2 and its continuing shutdown, a final environmental impact statement was developed for TMI-2 (Programmatic Environmental Impact Statement, NUREG-0683, March 1981 Supplements 1, 2 and 3) which does not significantly affect the conclusions of the environmental report.
This is substantiated further in the annual environmental reports provided in May of each year.
In addition, since the operation of THI-2 has been curtailed, the previous environmental assessments bound the present site conditions including the recent power upgrade.
1.
Radiological Impact The region in the immediate vicinity of the plant site is.primarily rural with a number of small communities located within the 10 mile 6
i
,. r: dike, The original licensing basis et111:ed the 1970 c:nsa Cata which showed a population of. 139,599 in the 0-10 mile distribution and projected a population distribution of 166,295 for 1980.. Recent j
population estimates based on 1986 consus data, which is the most j
current available, indicated 167,210 individuals reside within 10 miles of the plant. Therefore, population growth has fairly closely j
approximated that anticipated in 1970.
Population projections, which i
are based on the 198S census data, indicate the population will j
decline within the 10-mile radius to 157,027 by,the year 2010, whereas the existing Environmental Report estimates 281,446 by the year 2011.
Therefore, the existing Environmental Report bounds the anticipated population growth in the immediate vicinity of the plant and would be expected to remain bounding to the year 2014 based on the 1980 population projection trend.
i Ths outer boundary of the low population zone (LPZ) is'at a radius'of I
2 miles from the plant and was also based on the 1970 census data.
j The 1970 ct,cus data indicated that the LP2 population was 2,380.
The l
LPE population was recently determined to be approximately 'L60$ (baseo on 1986 population data and house counts from aerial photographs).
However, the existing Environmental Report had projected the LPZ population to be 2561 by the year 1987 and 2794 by the year 2011.
The nearest population center with more than 25,000 people as defined in
.]
10 CFR 100, was and still remains Harrisburg, PA, (estimated 1986 population = $1,530) located approximately 12 miles from the site.
Therefore, the existing Environmental Report also bounds the anticipated population growth within the.LPE and would be expected to i
remain bounding to the yaar 2014 based on the 1986 population data j
trend.
)
i Based on the above data, the projected population at the proposed license expiration date would not change the overall conclusion of the l
THI-1 TSAR or Environmental Report consequences following postulated
{
accidents. Therefore, the conclusions reached in the original TMI-1 l
FSAR and Environmental Report remain valid..
t 2.
General Public f
i The original estimates of dose to the human population residing around f
74I-1 was calculated for normal gaseous and liquid releases in i
Appendix III of the 1971 Environmental Report projected to the year 2014 which coincides with the request to extend the operating license
[
to 40 years.
As part of the 1976 Appendix I evaluation, the numbers were reviewed.
In August 1981, NRC issued' Technical Specifications f
requiring conformance with 10 crR 50 Appendix 2.
Semi-Annually, THI-1 provides a release report summarizing types and constituents of releases. Although actual source terms resulting from releases have I
been higher than assumed in the 1971 Environmental Reporte.the resulting doses based on actual realtime meteorological data at the time of release combined with actual population / farm distribution, have been lower as demonstrated in the semi-annual reports for TMI-1, 7
3... Occupational Exposuro Impact occupational radiation exposure at THI-1 is typically below the average of U.S. pressurited water reactor generating plants.
It is a CPUN goal that below average occupational exposures will continue for the operating life of THI-1.
THI-1 maintains an aggressive commitment to as low as reasonably achievable (ALARA) exposures.
Exposure goals are established for station man-rem to minimite collective doses. ALARA reviews and evaluations of workplans and plant modifications projected to exceed 6 man-rem are conducted.
Additional work steps are built into the workplan, where appropriate, to reduce occupational exposure.
Pre-$ob briefings and mockups are utilized, as well as post-job reviews.
Robotics and closed circuit television are being used more extensively to perform and monitor tasks resulting in reduced exposures.
Occupational exposure since commercial operation began at THI-2 is a total of 4,339 person-rem through Septenber,1989. Annual exposure in recent years has been well below the industry average.
The projected done for TMI-2 for the years 200B-2014 is also expected to be below the PWR annual average.
During this period of extension approximately 2 more refueling outages would be expected based on 24-month cycles.
Annually GPUN provides person-rem exposure data during normal operating, maintenance, repair and refueling activities for all personnel monitored by dosimetry.
4.
Won-Radiological Impact Irrrestrial specific areas of interest originally included the effects of cooling towers on vegetation due to salt stress, and bird impaction.
Monitoring programs for both showed minimal impact and have been discontinued with NRC concurren m through License Amendtaent No. $1, dated January 28, 1980, lLGBli.E specific areas of interest were impingement of fish into the river water systeins.
Based on approxiinately nJne years of aquatic monitoring, the NRC and the Pcnnsylvania Popartment of Environmental Resources concludod that there were no adverse environmental impacts resulting from the impingement of fish.
Previous aquatic monitoring programs have been discontinued.
Chemical and Thermal Direharoe Effect chemical and thermal discharges are now controlled by the effective Nhtional Pollutant Discharge Elimination Systen. (NPDES) permits under the Clean Water het and Pennsylvania's Clean Streams Law.
8
.. A review of tho history of ths Environnental R> ports providad annually shows no adverse inpact to the environment f rom the site. Adequate controls are provided to ensure continued monitoring of the plant discharges to the environment throughout plant life.
Extension of the operating license by 5 years and la months would not adversely af fect the environment.
5.
Economic As6essment Operation of THI-1 beyond it s current operating license period will provide a financial benefit to the customers served by GPU.
TMI 1 currently provides approximately 13t of the total electric power g
requirements of the GPU system. The operation of THI-2 f or an W
additional 5 years and il months would defer the need to design and construct an 600 MW coal-fired replacement facility, and the environmental impacts associated with such construction. The installed cost of this facility, which is assumed to utilise Fluidised-Bed Combustion (FBC) technology, is estimated to cost $4 billion in 2009.
Present value net benefits of operating THI-1 during the 2009-2014 time period are estimated to be $100-200 million.
These estimated not savings would reduce consumer rates compared to the coal replacement option.
IV.
NO SIGNIFIcANT MhfhRDS OONSIDERATIONS GPUN has determined that the proposed change to the Facility Operating License for THI-1 involves no significant hasards consideration as defined by NRC in 10 CFR 50.92.
1.
Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated.
The proposed revision to the Facility Operating License does not affect the safety analysis and does not involve any physical changes to the plant, nor any changen in the format or restraints on plant operations, and only contemplates a change to the expiration date of the current license.
Therefore, this change is unrelated to the possibility of increasing the consequences of previously analyzed accidents.
This change will not increase the probability of previously analyzed accidents because the plant is designed and constructed for 40 years of operation.
2.
Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any previously evaluated.
The proposed revision to the Facility Operating License does not affect the safety analysis and does not involve any physical changes to the plant, nor any changes in the format or restraints on plant operations, and only contemplates a change to the expiration date of the current license.
The plant is designed and constructed for 40 years of operation. Therefore, this change has no effect on the possibility of creating a new or different kind of accident from any previously evaluated.
9
,. 3.
Oper;tiCn cf the fccility in CO :rd:nce with th] pr:po::d amendment would not involve a significant reduction in a nargin of safety.
The proposed revision to the racility operating License does not involve any physical changes to the plant, nor any changes in the format or restraints on plant operatione, and only contemplates a change to the expiration date of the current license.
The safety analyses described in the TSAR are based on a 40-year operating life. Therefore, the overall nargin of safety for the plant is maintained.
The commission has provided guidelines pertaining to the application of the three standards by listing specific exan;ples in 48 TR 14670.
The proposed anendment is considered to be in the same category as example (1) of amendments that are considered not likely to involve significant hasards considerations in that the proposed change is purely an administrative change to allow operation for the design lif e of the plant and does not involve any physical changes to the plant or restraints on plant operations.
The proposed change bearing upon duration of operations is within the range permissible by the commission's regulations, specifically 10 CTR 50.61.
Thus, operation of the facility in accordance with the proposed amendment involves no significant hatards considerations.
V.
2MPLEMENTATIQH It is requested that this license amendment become ef fective upon issuance.
10 a
r ATTACHMENT TACILITY OPERATING LICENSE CHANGE 11
='s s
5.
GPU Nuclear Corporation shall provide routine reporting of the long-term corrosion " lead tests" test results en a quarterly basis as well as more timely notification if adverse c:orrosion test results are discovered.
(9) long Range Planning Program The ' Plan for the Long Range Planning Program for the Three Mile Island Nuclear Station - Unit 1" (the Plan) submitted by GPUN letter C311-88-2030 dated March 16, 1988 is approved, a.
The Plan shall be followed by the Licensee from and after May 27, 1988.
b.
The Category A schedule shall not be changed without prior approval from the NRC.
Categories 8 and C schedules may be changed without prior approval by NRC.
This license is effective as of the date of issuance and shall expire at midnight, April 19, 2014.
FOR THE ATOMIC ENERGY C0!911$$10N Original Signed by A. Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing
Attachment:
Appendix A Techical Specifications Date of Issuance:
April 19, 1974
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