ML20195E126
| ML20195E126 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/21/1988 |
| From: | Michael Ray TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-R00443, TAC-R00444, TAC-R443, TAC-R444, TAC-R445, NUDOCS 8806230298 | |
| Download: ML20195E126 (27) | |
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l TENNESSEE VALLEY AUTHORITY SN 157B Lookout Place t
l JUN 211988 l
TVA-SQN-TS-88-23 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - OPERATING LICENSE AMENDMENT 88-23 In accordance with 10 CFR 50.90, we are enclosing a requested amendment to licenses DPR-77 and DPR-79 to change the operating licenses for SQN units 1 and 2. The proposed change will revise the expiration dates for the operating licenses to 40 years from the date of issuance of the full-power license for each unit. This request is in accordance with current NRC policy. The present license expiration dates are based on 40 years from the date of issuance of the construction permit.
In accordance with NRC suggested guidelines. TVA has included information to address each of the four recommended areas: (1) Significant environmental impacts, (2) Pressurized Thermal Shock (PTS), (3) Equipment Qualification (10 CFR 50.49), and (4) Inservice Inspection (ISI) and Inservice Test (IST)
Programs.
The proposed operating licenses amendment is identified in enclosure 1. The justification for the proposed operating license amendment is provided in enclosure 2. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in enclosure 3.
Enclosed is a check for the $150 amendment application fee required by 10 CFR 170.12.
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'I W(deek}l50 dlN 8806230298 880621 PDR ADOCK 05000327 P DCD An Equal Opportunity Employer L_--_------------------
- 4 U.S. Nuclear Regulatery Comission JUN 211988 Please direct questions you may have concerning this issue to D. V. Goodin at (615) 870-7734. '
Very truly yours.
TENNESSEE JALLEY AUTHORITY
) l' J-t lLp M. J 4 Ray, Managg,r.
Sequoyah Site Licensing 9
uasi AA1}au fiotary'Pu'bl'ic '
i My Comission Expires '
7/8M
/
Enclosures cc (Enclosures):
Mr. Michael H. Mobley, Director (w/o enclosures) division of Radiological Health T.E.R.R.A. Building 150 9th Avenue, N Nashville, Tennessee 37203
] Mr. K. P. Barr, Acting Assistant Director for Inspection Programs l TVA Projects Division '
U.S. Nuclear Regulatory Comission Region II j 101 Marietta Street, NW, Suite 2900 i Atlanta, Georgia 30323 Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Comission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 l Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 cc See page 3 i
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ENCLOSURE 1 PROPOSED OPERATING LICENSE AMENDMENT J I I
'SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 i
DOCKET NOS. 50-327 AND 50-328 ;
3 (TVA-SQN-TS-8S-23) l i
LIST OF AFFECTED PAGES l i
Unit 1. DPR-77 )
page 13, item 2.K
'l Unit 2. DPR-79 .
page 13, item 2.K I
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.T *~^ ' D f l1. ~ ~l ']
When the evaivation an environmental evaluation of such activity. 'a indicates that such activity may result in a significant acu - '
l y environmental impact that was not evaluated, or that is siar -
greater than that evaluated in the Final Environmental S -
Valley Authority shall provide a written evaluation of suc and obtain prior approval from the Director, Office of Nuclear Re_ .or Regul ation. ,
G.
If TVA plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the Sequoyah Nuclear Plant, the Commission shall be notified in writing regardless of whether the change affects the
- amount of radioactivity in the effluents.
H.
TVA shall report any violations of the requirements contained in Sections 2.C(3) through 2.C.(24), 2.E, 2.F and 2.G of this 'iicense + thin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or Tacsimile transmission to the Director of the Regional Office, or his desigr. ate, no later than the first working day following the violation with a written followup report within 14 days.
I.
TVA shall imediately notify the Comission of any accident at this f acility which could result in an unplanned release of quantities of fission products in excess of allowable limits for normal operation established by the Comission.
J TVA shall have and maintain financial protection of such type and in sech amounts as the Comission shall require in accorcance with Section 170 of the Atomic Energy Act of 1954, as amenced,.to cover public liability claims.
K.
This license is effective as cf the date of issuance and shall expire M:. T , : Cit:"
FOR THE NUCLEAR REGULATORY COMMISSION 6eplembu l7,2024 )
- - - - ~ - -
., < >- /
Harold R. Lenton, Director Office of huclear Reactor Regulation
Attachment:
Apoendices A anc 5 Technical Specifications i
1 Date of issuanc_
September 17, 1980
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D P R.- 79
- 13 -
K. Tnis amenced license is effective as of the date of issuance ind shall expire "U 27, 20'O. '
STu IS 2021,
/ FOR THE NUCLEAR REGULATORY COMMISSION S k 0_.!, ~
Harold R. Denton, Director Office of Nuclear Reactor Regulation Attachments:
l'. Attachment 1
- 2. Appendices A and B Technial Specifications Date of Issuance: septe=ber 15, 1981 e
6 Amendment 2 9/15/81
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- n ENCLOSURE 2 PROPOSED OPERATING LICENSE AMENDMENT l
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 ;
DOCKET NOS. 50-327 AND 50-328 l
-(TVA-SQN-TS-88-23)
DESCRIPTION AND JUSTIFICATION FOR ,
OPERATING LICENSE AMENDMENT TO EXTEND EXPIRATION DATE l TO 40 YEARS FROM DATE OF. ISSUANCE OF THE j FULL-POWER LICENSE l l
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t ENCLOSURE 2 Description of Change TVA, pursuant to 10 CFR 50.90, requests an amendment to the SQN operating license for unit 1 (DPR-77) and un'. 2 (DPR-79). The proposed amendment revises the expiration date of the unit 1 operating license from May 27, 2010, to September 17, 2020, and unit 2 from May 27, 2010, to September 15, 2021.
Reason for Change The current operating license expiration date is 40 years from the date of issuance of the Construction Permit (May 27, 1970, for both units). Because 10 years and 4 months were required in the construction and issuance of the unit 1 full-power operating license (11 years and 4 months for unit 2). The effectiv6 period of the unit 1 license would be approximately 29 years and 8 months (28 years and 8 months for unit 2). Current NRC policy is to issue operating licenses for a 40-year period beginning with the date of issuance.
The requested amendment to the expiration date of the SQN operating licenses would provide for the 40-year period of operation that the units were initially designed for.
The proposed amendment is an administrative change that allows TVA to operate SQN for the full-design life and spread the capital cost of SQN over a longer period of time. This change will effectively lower the cost of electricity and thereby benefit the residential and industrial customers wit'ain TVA's service area.
Justification f_or Change The justification for this change is patterned after the suggested guidelines issued by NRC (reference 1) to supplement the April 30, 1985 policy letter by H. L. Thompson to H. R. Denton to extend the operating license for nuclear power plants. These guidelines suggest that the license address four items:
significant environmental impacts, pressurized thermal shock, equipment qualification, and technical specifications for in-service inspection and !
testing.
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Potential Environmental, Health, and Safety Impacts :
1 TVA has reviewed the S3quoyah Nuclear Plant Final Environmental Statement and j has concluded that the Environmental Statement is suitable for operation of i SQN for a 40-year period ending in the year 2010. The Environmental Statement
, does not generally use or discuss a specific period of plant operation in the ]
i evaluations presented. However, offsite population doses are based on the year 2010 population.
In the anoroximately 14 years since the Environmenta. Statement was issued, a number of modifications have been made to the SQN and surrounding site and l facilities. These modifications, in general, had the effect of improving the reliability and safety of the plant or reducing the environmental impact of plant operation. They include:
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s Facilities - Many modifications to the plant have been made since the original operating license has been issued. Significant modifications are described *r. the Sequoyah updated Final Safety Analysis Report.
Modifications made without prior NRC approval, in accordance with the provisions of 10 CFR 50.59, were reported on an annual basis to the Commission. Modifications requiring prior NRC approval were made following receipt of an NRC Safety Evaluation Report. No modification was found to affect the conclusions of the Sequoyah Environmental Statement.
Land Use - Additional site buildings have been constructed and existing buildings have been expanded. The actual land area occupied by site buildings has not significantly increased, however.
Thermal Ef fects . Thermal discharges f rom SQN are regulated through the National Pollutant Discharge Elimination System (NPDES) Permit. Data collected to date has indicated that the water quality and indigenous biota of Chickamauga Reservoir are protected by the thermal limits specified in the NPDES Permit. Operation of SQN will continue to be governed by the NPDES Permit with no different or greater impact.
Occupational radiation exposure at SQN remains below the average of U.S.
nuclear generating plants. This is attributed to an excellent history of fuel integrity and a management commitment to as low as reasonably achievable (ALARA) exposures. We expect that below average occupational exposures will continue to be the norm for the life of the SQN facility.
TVA has an aggressive ALARA program at SQN to maintain occupational radiation exposure. Exposure goals have been established for station man-rem to minimize collective doses. ALARA reviews and analyses are conducted for workplans for proposed jobs which are projected to evceed one man-rem. Steps are built in to the jobs to reduce dose. All proposed facility modifications receive similar reviews. Pre-job briefings are held wi'.h workers to cover dose savings measures and mock-ups are used as appropriate tc trcin workers.
Radiological impacts to offsite individuals due to releases of radioactive liquid and gaseous wastes from the plant remain well within all applicable regulatory limits. Computed gaseous offsite doses are typically less than 3 percent of the 10 CFR 50, Appendix I, guidelines (for a two-unit plant) of 20 millirad / year gamma and 40 millirad / year beta air dose and 30 millirem / year organ dose. Computed offsite liquid doses are typically less than 10 percent of the 10 CFR 50, Appendix I, guidelines of 6 milli:em/ year total body and 20 millirem / year organ dose. Radioactive effluent releases are controlled by the technical specifications in section 3.11. These specifications implement the release limits specified in 10 CFR 20 and set performance goals based on 10 CFR 30, Appendix I.
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.o TVA does not expect any increase in the annual dose for the operations of SQN for the years of 2010 to 2021. Doses calculated for offsite populations in the year 2021 would be less than 15 percent greater than those estimated for the 2010 population. This increase would be due solely to an estimated growth of population during 2010 through 2021. However, population doses would remain less than 0.1 percent of the natural background dose to the offsitu population. We expect decommissioning doses beginning in 2022 to be reduced as compared to doses that would be expected for a 2011 decommissioning due to improvements made in the technology.
Table 1 shows TVA's projected operational schedule for SQN. Table 2 shows projected occupational exposure for Sequoyah. Tabla 3 shows TVA's past personnel exposure for SQN for the years 1982 through 1987. The person-rem exposure is by olant area regardless of how these exposures were obtrined (normal operatz 4s, maintenance, repair or refueling operations, etc./ and by whom (plant operations / maintenance personnel, contractor / vendor personnel, etc.). This data is the same data provided yearly as required by 10 CFR 20.407(b) and SQN technical specification 6.9.1.5.
The following information is furnished consistent with 10 CFR 51.52(a):
- 1) The licensed reactor core thermal power limit for SQN is 3411 megawatts.
- 2) The initial uranium-235 enrichment for fuel assemblies at SQN is less than 4 percent by weight. Fuel pellets are clad in zircaloy rods.
These parameters are controlled by technical specification 5.3.1
- 3) The average expected level of burnup of the irradiated fuel from SQN l is about 45,000 megawatt-days per metric ton of uranium (MWD /MTU). !
Although this is greater than the burnup of 10 CFR 51.52(a), the effective levels of radioactivity from a fuel assembly with an average burnup of 45,000 MWD /MTU will be cooled for a period of time to meet the requirements of a fuel assembly with an average burnup of 33,000 MWD /MTU that has cooled for 90 days. Additionally, based on TVA's contract with the Department of Energy and the current progresc of th>
development of a high level waste repository, most fuel assemblies will have decayed for several years.
- 4) All radioactive waste, other than irradiated fuel, is packaged and transported in solid form by either truck or rail. SQN technical specification 3.11.3 establishes requirements for the Solid Radioactive Waste System,
- 5) Irradiated fuel assemblies will be transported either by truck, rail, or barge from the reactor.
- 6) The transportation of radioactive material is regulated by the Department of Transportation and the NRC. The regulations provide protection of the public and transport workers from radiation. This protection is achieved by a combination of standards and requirements applicable to packaging, limitations on the contents of packages and radiation levels from packages, and procedures to limit the exposure of persons under normal and accident conditions.
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l Primary reliance for safety in transport of radioactive material is placed on the packaging. The packaging must meat regulatory standards j (10 CFR 71 and 49 0FR 173) established according to the type and form of material for containment, shielding, nuclear criticality safety, and heat dissipation.
The standards provide that the packaging shall prevent the loss or l dispersal of the radioactive contents, retain shielding efficiency, l assure nuclear criticality safety, and provide adequate heat !
dissipation under normal conditions of transport and under specified accident damage test conditions. The contents of packages not designed to withstand accidents are limited, thereby limiting the risk !
from releases which could occur in an accident. The contents of the l package also must be limited so that the standards for external radiation levels, temperature, pressure, and containment are met. l l
Furthermore, the additional amount of nuclear fuel and waste resulting l from an extended operating period will continue to be within the )
limits assumed for the original licensing basis. Because of improved l fuel cycle designs and longer operation between refueling outages, the total amount of spent fuel produced over a 40-year operating lifetime will be less than that originally projected by the Final Safety Analysis Report (FSAR) for SQN.
Based on the above concludes that the radiological impact froro the transportation of 1..adiated fuel and solid radioactive waste is in accordance l with the impacts set forth in table S A of 10 CFR 51.52. The environmental costs will not be significantly affected during the additional years of operation.
As originally predicted, approximately 70 percent of the population within the 10-mile zone is concentrated in the southern one-third of the zone. The land l use in the vicinity of SQN has remained predominately rural although the l growth in the southern area has exceeded original estimates especially in development along Lake Chickamauga. Highways, both east and west of the Tennessee River (Interstate I-75, Highway 29, Highway 153, south Hixson Pike, and Highway 58), have been upgraded and bridges across the Tennessee River have been 3xpanded (Chickamauga Dam expanded from 2 to 4 lanes, the new C. B.
Robinson 3r Q e added 6 lanes, and the new Veteran's Bridge addeo 4 additional lanes). Highway 29 is also in the final stages of construction to provide an interceptor to Interstate I-124 and thereby further improving the traffic flow I from the southern evacuation area. With the improved highway system compensating for the expansion, there continues to be assurance that appropriate measures can be taken to protect the populace in the event of a radiological release.
Pressurized Thermal Shock IVA provided an assessment of the fracture tourhrebs requirements for protection against pressurized thermal shock as required by 10 CFR 50.61 (reference 2). That assessment concluded that the screening values would not be exceeded for the SQN reactor pressure vessels through at least 32 effective full-power years. This time is consistent with tho design life of 40 years for the reactor pressure vessels as presented in FSAR, table 5.1-1, wii.h a
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9 projected capacity factor of 80 percent. The NRC evaluation and acceptance of ttc fracture toughness assessment is documented in a safety evaluation for protection against pressurized thermal shock events (reference 3).
Equipment Qualification The environmental qualification (EQ) program for electrical equipment operating in a harsh environment is described in section III.1 of the SQN Nuclear Performance Plan (NPP) (reference 4). The program ensures that EQ is maintained for electrical equipment necessary to ensure reactor coolant pressure boundary integrity, shut down of the reactor and maintain it in a safe chutdown condition, and to prevent or mitigate the consequences of accidents that could result in offsite exposures comparable to the 10 CFR 100 guidelines. Non-safety-related electrical equipment whose failure under postulated harsh environmental conditions could prevent satisfactory accomplishment of safety functions by safety-related equipment was also included in the program.
5 Aging analyses have been performed for all safety-related electrical equipment within the scope of 10 CFR 50.49 (harsh environment). The qualified life of the equipment or component is incorporated within SQN's maintenance and replacement practices to ensure that this safety-related electrical equipment remains qualified and available to perform its safety function regardless of the overall age of the plant.
The SQN EQ was evaluated by NRC and found acceptable. The acceptance is documented in section 3.2 of the safety evaluation report for the SQN NPP (NUREG-1232, Volume 2).
TVA is currently working with the NRC staff to establish the program to extend the qualified life of silicone rubber cable (reference 5). TVA is also working with the NRC staff to perform confirmatory work for the ice condenser containment analyses for main steam line breake that involve superheat (reference 6). These ongoing program activities have also been considered by NRC in their evaluation of the EQ program. This consideration is documented in sections 3.12 and 3.2.2.2, respectively, of NUREG-1232, Volume 2.
Inservice Inspection (ISI) and Inservice Test (IST) Programs TVA has ongoing ISI and IST programs for SQN that arr. maintained in accordance with 10 CFR 50.55a. The surveillance requirements for these programs are contained in SQN technical specification 4.0.5 and are required to conform to section XI of the ASME Boiler and Pressure Vessel Code. Where specific relief from the section XI code was necessary, TVA has provided written relief requests to NRC for review and approval in accordance with 10 CFR 50.55(a)
(g)(6)(i).
In addition to the ISI and IST programs, the following SQN technical specifications also provide an additional requirements for monitoring component aging and the cumulative effects of power operation over the life of the plant.
e A. Specification 3.4.5 - Steam Generators In addition to the-requirements of specification 4.0.5, TVA has an augmented ISI program for ensuring operability of the SQN steam generators. The results of these augmented !nspections are submited by report to NRC and include:
- 1. Number of steam generator tubes inspected.
- 2. Location and percent of wall thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged.
B. Specification 3.4.9.1 - Reactor Coolant System Pressure / Temperature Limits 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 collant system. These limits are calculated using the methods derived from Appendix G in section III of the ASME Boiler and Pressure Vessel Code as required by Appendix G to 10 CFR 50.
The above specification also 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 irradation specimens are removed and examined at specific intervals to determine changes in material properties. The results of the examinations are used to update the pressure and temperature limits.
C. Specification 3.4.10 - Reactor Coolant System Structural Integrity The ISI and IST programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational ,
readiness of these components will be maintained at in l acceptable level throughout the life of the plant. I In addition to the ISI and IST programs, tdditional special .
inspections are specified for the Reactor Coolant Pump flywheels '
and reactor vessel nozzles.
D. Spraffication 5.7.1 - Component Cyclic or Transient Limit 1
This requirement ensures that certain components within the l I
reactor coolant and secondary systems are maintained within their cyclic or transient limits over the life of the plant.
These limits are monitored, recorded, and evaluated for component fatigue to provide confidence that each component will perform its intended function over a 40-year design life.
4 Conclusion No new safety concerns are introduced by this proposed amendment since (1) a 40-year life was considered in the design of the plant and since (2) new or revised accident analyses, plant nodifications, procedure changes FSAR revisions, nd technical specification revisions are not required. Note, however, that since the issuance of the operating licenses, numerous changes I have been implemented to enhance safety and to address issues such as fire protection, ALARA, Equipment Qualification, and the TMI-2 Lessons Learned (NUREG 0737).
References
- 1. Memorandum from Thomas A. Novak to Projec; Directors and Project Managers dated November 25, 1986, "Suggested Guidelines for Preparing License l
Amendment Dealing with Extension of Expiration Date of Operating Licenses"
- 2. Letter from TVA to NRC dated January 21, 1986.
- 3. Letter from NRC to TVA dated May 5, 1988, "Safety Evaluations on Fracture i Toughness Requirements for Protection Against Frensurized Thermal Shock l Events, 10 CFR 50.61 (TAC 59983/59984, MPA A-21)"
- 4. Sequoyah Nuclear Performance Plan, Revision 3.
- Silicone Rubber Cable Environmental Qualification"
- 6. Letter from TVA to NRC dated June 1, 1988, "Sequoyah Nuclear Plant (SQN) l Units 1 and 2; Watts Bar Nuclear Plant (WBN) Units 1 and 2 - Request for Additional Informatien Regarding Main Steam Line Breaks in Ice Condenser Plants" l
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ENCLOSURE 2
. TABLE 1 '
e Sequoyah Nuclear. Plant Unit 1 Operation Schedule Refueling Schedule Start End Start End Cycle DATE DATE DATE DATE 3 4/17/84 8/22/85 8/22/85 8/15/88 4 8/15/88 2/07/90 2/07/90 4/26/90 5 4/26/90 10/27/91 10/27/91 1/13/92 6 1/13/92 7/15/93 7/15/93 10/01/93 7 10/01/93 4/03/95 4/03/95 6/20/95 8 6/20/95 12/20/96 12/20/96 3/08/97 9 3/08/97 9/08/98 9/08/98 11/25/98 10 11/25/98 5/27/00 5/27/00 8/13/00 11 8/13/00 2/13/02 2/13/02 5/02/02 12 5/02/02 11/02/03 11/02/03 1/19/04 13 1/19/04 7/21/05 7/21/05 10/07/05 14 10/07/05 4/09/07 4/09/07 6/26/07 15 6/26/07 12/26/08 12/26/08 3/14/09 16 3/14/09 5/31/10 With License Extension +
Operation Schedule Refueling Schedule Start End Start End Cycle DATE DATE DATE DATE 16 3/14/09 9/14/10 9/14/10 12/01/10 17 12/01/10 6/02/12 6/02/12 8/19/12 18 8/19/12 2/19/14 2/19/14 5/08/14 19 5/08/14 11/08/15 11/08/15 1/25/16 20 1/25/16 7/27/17 7/27/17 10/13/17 21 10/13/17 4/15/19 4/15/19 7/02/19 22 7/02/19 8/31/20
+ Cycles 3 through 15 would be the same
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g ENCLOSURE 2 TABLE 1 (Continued)
Sequoyah Nuclear Plant Unit 2 Operation Schedule Refueling Schedule Start End Start End Cycle DATE DATE DATE DATE 3 12/26/84 11/09/88 11/09/88 1/26/89 4 1/26/89 8/02/90 8/02/90 10/19/90 5 10/19/90 4/25/92 4/25/92 7/12/92 6 7/12/92 1/16/94 1/16/94 4/05/94 7 4/05/94 10/10/95 10/10/95 12/27/95 8 12/27/95 7/02/97 7/02/97 9/18/97 9 9/18/97 3/25/99 3/25/99 6/11/99 10 6/11/99 12/15/00 12/15/00 3/03/01 11 3/03/01 9/07/02 9/07/02 11/24/02 12 11/24/02 5/30/04 5/30/04 8/16/04 13 8/16/04 2/20/06 2/20/05 5/09/06 14 5/09/06 11/13/07 11/13/07 1/30/08 15 1/30/08 8/05/09 8/05/09 10/22/09 16 10/22/09 5/31/10 With License Extension +
Operation Schedule Refueling Schedule Start End Start End Cycle DATE DATE DATE DATE 16 10/22/09 4/28/11 4/28/11 7/15/11 17 7/15/11 1/18/13 1/18/13 4/06/13 18 4/06/13 10/11/14 10/11/14 12/28/14 19 12/28/14 7/03/16 7/03/16 9/19/16 20 9/19/16 3/26/18 3/26/18 6/12/18 21 6/12/18 12/16/19 12/16/19 3/04/20 12 3/04/20 8/31/21
+ Cycles 3 through 15 would be the same l
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o ENCLOSURE 2 s
TABLE 2 Sequoyah Nuclear Plant Unit 1 Projected Occupational Exposure
- MAN-REM YEAR OUTAGE NON-0UTAGE TOTAL ;
2010 I 450 180 630 i l
2011' NO OUTAGE 250 250 2012 450 180 630 2013 NO OUTAGE 250 250 2014 450 180 630 2015 275 200 475 2016 150 225 375 2017 450 180 630 2018 NO OUTAGE 250 250 i 2019 450 180 630 2020 450 180 630
- Assumes 20 man-rem per month during .on-outage and 150 man-rem per month during outage.
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.r ENCLOSURE 2 TABLE 2 -(Continusd)
Sequoyah Nuclear Plant Unit 2-Projected Occupational Exposure MAN-REM YEAR OUTAGE NON-0UTAGE Tp i2J.
2011 450 180 630 2012 NO OUTAGE 250 ' 250 2013 450 180 630 2014 450 180 630 2015 NO OUTAGE 250 250 2016 450 180 630 2017 NO OUTAGE 250 250 2018 450 180 630 2019 80 240 320 2020 370 200 570 2021 450 180 630 i
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V L L L L L L L R E E E E E E E L U N N N N N N N A S L NLL L NLL L NLL L NLL L NLL L NLL L NLL T E OEE E OEE N E OEE E OEE E OEE E OEE N E OEE O N & NLSNN NLSNN O NLSNN NLSNN NLSNN NLSNN O NLSNN T O NERNN E NERNN I NERNN E NERNN NERNN NERNN I NERNN I I SONEOO L C ONEOO L T ONEOO L CONEOO t ONEOO L ONEOO L T ONEOO D T NSNPSS A NSNPSS A CSNPSS A NSNPSS A SNPSS A SNPSS A C SNPSS N H C O RO RR T ARO RR T E RO RR T A RO RR T GRO RR T RO RRT N RO RR A A N I ESSEE O NESSEE O P ESSEE O N ESSEE O NESSEE O ESSEEO U ESS E R Y U T PRCPP T EPRCPP T S PRCPP T E PRCPP T LPRCPP T PRCPP T F PRCFP G 0 F A EI L EI N EI T EI S EI EI 0 REPSYG HEPSYG EI I EPSYG N EPSYG S EPSYG EPSYG B EPSYG 0 B EC YRN 1C YRN C YRN I C E C YRN C YRN O C YRN E O P NGHOI A NGHOI E NGHOI A N C. nOI JR N C NGHOI NGHOI J NGHOI S J O ANPSR M ANPSR C ANPSR M ANPSR O ANPSR G ANPSR ANPSR NI IE NI IE I NI IE NI IE R NI IE N NI IE Y NI IE
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S APEUN F APEUN T APEUN L WE MOHSE N MOHSE P MOHSE A MOHSE MOHSE O MOHSE P _R OMOHSE_
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e ENCLOSURE 2 - TABLE 3 .
NUMBER OF PERSONNEL AND MAN-REM 8Y WORK ANO JOB FUNCTION PLANT- *SE000YAH 1.2 (PWR) 1983 f Number of Personnel (>100 M-REH)
Station Utility Contract Total Station Utility Contract Total WORK & JOB FUNCTION Employees Emnlovees & Others Persons Emploveci EmRlnyges & Others Man-Rems REACTOR OPERATIONS & SURV.
MAINIENANCE PERSONNEL 188 477 6 12.237 19.316 2.408 OPERATING PERSONNEL 86 0 0 8.664 0.000 0.000 HEALTH PHYSICS PERSONNEL 34 0 33 4.686 0.000 10.758
- SUPERVISORY PERSONNEL 32 11 2 5.011 0.720 0.128 ENGINEERING PERSONNEL 48 60 7 5.296 7.044 0.315 10TAL 388 548 48 984 35.894 27.080 13.609 76.583 RQul1NE MAINTENANCE MAINTENANCE PERSONNEL 197 535 3 43.789 78.759 0.031 OPERATING PERSONNEL 86 0 0 6.514 0.000 0.000 HEALTH PHYSICS PERSONNEL 34 0 33 3.573 0.000 1.906
$UPERVISORY PERSONNEL 32 11 2 5.408 1.753 0.109 ENGINEERIFG PERSONNEL 49 74 39 9.364 14.430 9.045 TOTAL 398 620 77 1095 68.648 94.942 11.091 174.681 IN-SERVICE INSPECTION MAINILNANCE PERSONNEL 37 295 0 0.243 29.878 0.000 OPERATING PERSONNEL 38 0 0 0.144 0.000 0.000 HEALTH PHYSICS PERSONNEL 11 0 23 0.284 0.000 3.916 SUPERVISORY PERSONNEL 7 7 1 0.208 0.310 0.000 i ENGINEERING PERSONNEL 32 48 32 2.770 9.914 15.743 TOTAL 125 350 56 531 3.649 40.102 19.659 63.410 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL 174 508 0 3.435 91.244 0.000 OPERATING PERSONNEL 75 0 0 0.445 0.000 0.000 HEALTH PHYSICS PERSONNEL 25 0 21 0.586 0.000 0.311 SUPERVISORY PERSONNEL 24 8 2 0.255 0.266 0.006 ENGINEERING PERSONNEL 46 49 9 4.038 8.542 0.616 TOTAL 344 565 32 941 8.759 100.052 0.953 109.764 WASTE PROCESSING MAINTENANCE PERSONNEL 158 239 2 3.545 3.006 0.250 00ERATING PERSONNEL 81 0 0 7.768 0.000 0.000 HEALTH PHYSICS PERSONNEL 32 0 20 1.586 0.000 0.164
$UPERVISORY PERSONNEL 15 2 0 0.458 0.010 0.000
. ENGINEERING PERSONNEL 28 11 0 0.033 0.040 0.000 TOTAL 314 252 22 588 13.390 3.056 0.414 16.860 REFUELING MAINTENANCE PERSONNEL 113 309 I 4.106 44.872 0.115 OPERATING PERSONNEL 43 0 0 3.081 0.000 0.000 HEALTH PHYSICS PERSONNEL 8 0 20 0.024 0.000 1.893 SUPERVISORY PERSONNEL 17 6 1 2.070 0.069 0.002 ENGINEERING PERSONNEL 42 31 0 2.955 6.552 0.000 TOTAL 223 346 22 591 12.236 51.493 2.010 65.739 TOTAL BY JOB FUNCTION MAINTENANCE PERSONNEL 867 2363 12 3242 67.355 267.075 2.804 337.234 OPERATING PERSONNEL 409 0 0 409 26.616 0.000 0.000 26.616 HEALTH PHYSICS PERSONNEL 144 0 150 294 10.739 0.000 18.948 29.687 SUPERVISORY PERSONNEL 127 45 8 180 13.410 3.128 0.245 16.783 ENGINEERING PERSONNEL 245 273 87 605 24.456 46.522 25.739 96.717 l GRAND TOTAL 1792 2681 257 4730 142.576 316.725 47.736 507.037
- Workers may be counted in more than one category
ENCLOSURE 2 - TABLE 3 .
NUMBER OF PERSONNEL AND MAN-REM BY WORK AND JOB FUNCIION PLANT- "SE000YAH 1.2 ^
(PWR1 1984 Number of Personnel (>100 M-REN)
Station Utility Contract Total Station Utility ' Contract Total WORK & JOB FUNCTION Emolovees Employees 8. Others Eerinos balayees bployees & Others Man-Rees REACTOR OPERA 110NS & SURV.
l MAINTENANCE PERSONNEL 503 562 9 25.907 21.450 0.548 OPE:'ATING PERSONNEL 95 0 0 16.703 0.000 0.000 HEALTH PHYSICS PERSONNEL 60 2 58 19.472 0.000 21.220 SU?ERVISORY PERSONNEL 74 22 2 10.738 2.388 0.226 ENGINEERING PERSONNEt 62 IQ6 27 12.357 15.559 1.218 TOTAL 794 692 96 1582 85.177 39.397 23.212 147.786 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 540 587 3 120.746 72.022 0.030 OPERATING PERSONNEL 82 0 0 1.737 0.000 0.000 HEALTH PHYSICS PERSONNEL 59 1 51 4.741 0.000 1.288 SUPERVISORY PERSONNEL 63 23 2 6.177 2.743 0.103 ENGINEERING PERSONNEL 62 95 39 10.448 8.477 30.117 TOTAL 806 706 95 1607 143.849 83.242 31.538 258.629 IN-SERVICE INSPECTION MAINTENANCE PERSONNEL 226 236 9 34.218 37.399 7.001 OPERATING PERSONNEL 26 0 0 0.400 0.000 0.000 HEALTH PHYSICS PERSONNEL 30 0 35 2.024 0.000 6.798 SUPERVISORY PERSONNEL 19 6 2 0.938 2.191 0.053 ENGINEERING PERSONNEL 55 54 47 5.960 13.607 31.173 TOTAL 356 296 93 745 43.540 53.197 45.025 141.762 SPECIAL MAINTENANCE MAINIENANCE PERSONNEL 415 622 6 37.351 229.127 1.955 d
OPERATING PERSONNEL 75 0 0 0.990 0.000 0.000 HEALTH PHYSICS PERSONNEL 57 0 37 5.936 0.000 0.618 SUPERVISORY PERSONNEL 60 18 1 8.158 2.120 0.032 ENGINEERING PERSONNEL 58 33 11 12.280 10.183 1.670 TOTAL 665 723 55 1443 64.715 241.430 4.275 3'10.420 WASTE PROCESSING MAINTENANCE PERSONNEL 368 271 3 19.822 8.197 0.840 OPERATING PERSONNEL 91 0 0 11.831 0.000 0.000 HEALTH PHYSICS PERSONNEL 60 0 47 5.849 0.000 0.721 SUPERVISORY PE2SONNEL 40 9 1 0.992 0.105 0.007 ENGINEERING PERSONNEL 45 40 2 0.193 1.024 0.005
] TOTAL 604 320 53 977 38.687 9.326 1.573 4s.Soo REFUELING MAINTENANCE PERSONNEL 352 347 4 69.132 64.188 0.025 OPERATING PERSONNEL 66 0 0 10.394 0.000 0.000 HEALTH PHYSICS PERSONNEL 47 0 30 1.698 0.000 1.106 SUPERVISORY PERSONNEL 35 3 1 12.428 0.997 0.137 ENGINEERING PERSONNEL 55 36 5 8.856 5.648 0.798 TOTAL 555 386 40 981 102.508 70.833 2.066 175.407 TOTAL BY JOB FUNCTION MAINTENANCE PERSONNEL 2404 2625 34 5063 307.176 432.383 10.399 749.958 OPERATING PERSONNEL 435 0 0 435 42.055 0.000 0.000 42.055 HEALTH PHYSICS PERSONNEL 313 3 258 574 39.720 0.000 31.751 71.471 SUPERVISORY PERSONNEL 291 81 9 381 39.431 10.544 0.558 50.533 ENGINEERING PERSONNEL 337 414 131 882 50.094 54.498 64.981 169.573 GRAND TOTAL 3780 3123 432 7335 478.476 497.425 107.689 1083.590
- Workers may be counted in more than one category
ENCLOS'vAE 2 - TABLE 3 s NUMBER Of F.RSONNEL AND MAN-REM BY WORK AND JOB FUNCTION PLANT! SEOUOYAH 1. 2 (PWR1 1985 o Number of Personnel (>100 M-REM)
Station Utility Contract Total Station Utility Contract Total WORK & JOB FUNCTION Emplovers Emolovees & Others Persons Emnlnyees Emolovees & Others Man-Rems REAGOR OPERAI1QNS & SURV.
MAINTENANCE PERSONN';- 613 4 2 519 15.468 1.042 0.040 36.370 OPERATING PERSONNEL 74 1 9 84 14.258 0.005 0.586 14.347 HEALTH PHYSICS PERSONNEL 65 25 14 104 24.649 7.400 3.266 35.515 SUPERVISORY PERSONNEL 33 21 2 56 3.305 0.916 0.190 4.411 ENGINEERING PERSONNEL 119 49 50 218 17.799 3.104 0.792 21.695 TOTAL 904 100 77 1081 95.477 12.467 4.894 112.338 ROL' TINE MAINTENANCE MAINTENANCE PERSONNEL 642 2 2 546 200.390 0.014 0.109 201.013 OPERATING PERSONNEL 66 0 5 71 1.224 v.000 2.922 4.146
- HEALTH PHYSICS PERSONNEL 64 23 11 98 8.549 0.715 1.745 11.027 SUPERVISORY PfRSONNEL 31 15 2 48 5.019 0.137 0.091 5.247 I ENGINEERING PERSONNEL 111 38 _63 212 18.593 5.336 46.645 70.974 4 TOTAL 914 78 83 1075 234.375 6.322 51.510 292.407 LM-SERVICE INSELCIJON MAINIENANCE PERSONNEL 303 5 18 326 56.969 0.201 18.004 75.174 OPERATING PERSONNEL 33 2 4 39 0.599 0.057 0.055 0.711 HEALTH PHYSICS PERSONNEL 48 19 9 76 11.978 3.982 3.019 18.979 SUPERVISORY PERSONNEL 17 17 3 37 0.898 1.753 0.165 2.314 ENGINEERING PERSONNEL 77 42 63 182 7.840 34.478 42.012 84.33Q, TOTAL 478 85 97 660 77.764 40.471 63.253 181.508 SPECIAL MAINTENANCE MAINTEMANCE PERSONNEL 560 2 2 564 164.383 0.037 0.333 164.753 OPERATING PERSONNEL 52 0 3 55 0.386 0.000 0.342 0.728 HEALTH PHYSICS PERSONNEL 62 18 10 90 5.784 - 2.742 2.037 10.563 SUPERVISORY PERSONNEL 25 1 2 28 1.520 0.005 0.003 1.533 ENGINEERING PERSONNEL 108 31 109 248 14.717 2.157 102.805 119.579 4
TOTAL 807 52 126 985 186.790 4.941 105.525 297.256 4 EhSTEPROCESSING MAINTENANCE PERSONNEL 306 0 0 306 14.453 0.000 0.000 14.453 OPERATING PERSONNEL 73 0 5 78 11.417 0.000 2.549 13.965 HEALTH PHYSICS PERSONNEL 63 9 5 77 4.451 0.054 0.265 4.770 SUPERVISORY PERSONNEL 17 0 0 17 1.179 0.000 0.000 1.179 ENGINEERING PERSONNEL 43 2 1 46 0.182 0.022 0.305 0.510 TOTAL 502 11 11 524 31.682 0.076 3.119 34.877 REFUELING MAINTENANCE PERSONNEL 315 2 2 319 70.886 1.350 1.500 74.236 OPERATING PERSONNEL 46 3 2 51 6.563 0.328 2.335 9.226 HEALTH PHYSICS PERSONNEL 39 15 5 59 1.469 2.965 1.423 5.357 SUPERVISORY PERSONNEL 16 0 2 18 7.390 0.000 0.023 7.413 ENGINEERING PERSONNEL 70 21 4 95 11.379 1.153 0.058 12.588 TOTAL 486 41 15 542 97.687 6.296 5.337 109.520
___ TOTAL 8Y JOB FUNCTION MAINTENANCE PERSONNEL 2739 15 26 2780 543.069 3.144 20.006 566.199 OPERATING PERSONNEL 344 6 28 378 34.445 0.390 B.788 43.623
, HEALTH PHYSICS PERSONNEL 341 109 54 504 56.830 17.878 11.753 86.511 SUPERVISORY PERSONNEL 139 54 11 204 18.811 2.811 0.475 22.097 ENGINEERING PERSONNEL 528 183 290 1001 70.610 46.550 192.616 309.776 GRAND TOTAL 4091 367 409 4867 723.795 70.773 233.638 1028.206 J
.- - - _ _ _ _ _-_-______E
ENCLOSURE 2 - TABLE 3 NUMBER Of PERSONNEL AND MAN-REH BY WORK AND JOB IUNCTION 0-PLANT- SEOUOYAH 1. 2 (PWR) 1986 Number of Personnel (>100 M-REH)
Station Utility Contract Total Station Utility Contract Total
. WORK & JOB FUNCTION [mRlnyees Emolovees & Others Persons Emoloyees Emolovees & Other1 Han-Rems REACIQ!LDf1RAIIDMS3_SURL MAINTENANCE PERS6NNEL S47 1 IS L63 29.716 0.003 1.582 31.301 OPERATING PERSONNEL 71 0 3 it 11.798 0.000 0.046 11.844 HEALTH PHYSICS PERSONNEL 47 0 0 *7 14.974 0.000 0.000 14.974 SUPERVISORY PERSONNEL 29 24 1 54 2.794 1.918 8.136 4.848 ENGINEERING PERSONNEL 72 17 60 149 9.005 2.436 17.621 29.012_
TOTAL 766 42 79 887 68.297 4.357 19.385 92.039 ROUTINE MAINTENANCE MAINTENANCE PERSONNEL 559 0 16 575 143.973 0.000 3.807 151.780 OPERATING PERSONNEL 56 0 5 71 2.267 0.000 1.727 3.994 HEALTH PHYSICS PERSONNEL 48 0 0 48 7.638 0.000 0.000 7.638 SUPERVISORY PERSONNEL 26 24 1 51 2.189 0.436 0.002 2.627 ENGINEERING PERSONNEL 64 9 62 155 8.510 1.004 14.557 23.871 TOTAL 763 33 84 900 168.377 1.440 20.093 189.910 IN-SERVICE INSPECTION MAINTENANCE PERSONNEL 157 0 0 157 19.495 0.000 0.000 19.495 OPERATING PERSONNEL 16 0 0 16 0.019 0.000 0.000 0.019 HEALTH PHYSICS PERSONNEL 36 0 0 36 3.588 0.000 0.000 3.588
$UPERVISORY PERSONNEL 4 28 0 32 0.038 S.044 0.000 S.082 ENGINEERING PERSONNEL 27 11 2E_ 66 0.518 0.517 6.531 7.566_
TOTAL 240 39 26 307 23.658 5.561 6.531 35.750 SPECIAL MAINTENANCE MAINTENANCE PERSONNEL S49 1 11 561 124.938 0.000 2.251 127.189 ,
OPERATING PERSONNEL 65 0 4 69 3.161 0.000 0.340 3.501 HEALTH PHYSICS PERSONNEL 45 1 0 46 2.514 0.005 0.000 2.519 SUPERVISORY PERSONNEL 17 12 1 30 0.323 0.527 0.000 0.850 ENGINEERING PERSONNEL 69 9 84 162 10.109 1.422 15.957 27.488 TOTAL 745 23 100 868 141.045 1.954 18.548 161.547 WASTE PROCESSING MAINTENANCE PERSONNEL 141 0 0 141 S.827 0.000 0.000 S.827 OPERATING PERSONNEL 16 0 3 19 S.350 0.000 1.332 6.682 HEALTH PHYSICS PERSONNEL 46 0 0 46 1.403 0.000 0.000 1.403 SUPERVISORY PERSONNEL 9 0 0 9 2.423 0.000 0.000 2.423 ENGINEERING PERSONNEL 6 0 0 6 0.210 0.000 0.000 0.210 TOTAL 218 0 3 221 15.213 0.000 1.332 16.545 REFUELING MAINTENANCE PERSONNEL 109 0 2 111 17.972 0.000 9.022 17.994 OPERATING PERSONNEL 17 0 0 17 0.190 0.000 0.000 0.190
, HEALTH PHYSICS PERSONNEL 22 0 0 22 0.785 0.000 0.000 0.785 SUPERVISORY PERSONNEL 4 7 0 11 0.718 0.150 0.000 0.868 ,
ENGINEERING PERSONNEL 9 2 2 13 0.567 0.175 0.500 1.242 TOTAL 161 9 4 174 20.232 0.325 0.522 21.079 2893 146 298 3337 436.822 13.637 66.411 516.870 TOTAL BY JOB FUNCTION MAINTEN?.NCE PERSONNEL 2062 2 44 2108 345.921 0.003 7.662 353.586 OPERATING PERSONNEL 251 0 15 266 22.785 0.000 3.445 26.230 HLALTH PHYSICS PERSONNEL 244 1 0 245 30.902 0.005 0.000 30.907 SUPERVISORY PERSONNEL 89 95 3 187 8.485 8.075 0.146 16.698 ENGINEERING PERSONNEL 247 48 236 531 28.129 5.554 55.166 89.449 TOTAL 2893 146 298 3337 436.822 13.637 66.411 516.870
ENCLOSURE 2 - TABLE 3 ,
NUMBER Of PERSONNEL AND MAN-REM BY WORK APD JOB FUNCTION PLANT- SE000YAH 1. 2 (PWR1 1987 *-
Number of Personnel (>100 M-REM)
Station utility Contract Total Station Utility Contract 10tal WORK & JOB FUNCTION [m91DJcts Emolovees & Others PersoaA Employees Emplovets & Others Mda-Rems REACTOR OPERATIOr(S_&_S1EL MAINTENANCE PERSONNEL 583 5 4 592 19.386 0.063 0.045 19.494 OPERATING PERSONNEL 55 9 0 64 5.644 0.243 0.000 5.887 HEALTH PHYSICS PERSONNEL 57 15 0 72 13.023 2.933 0.000 15.956 SUPERVISORY PERSONNEL 12 0 0 12 1.102 0.000 0.000 1.102 ENGINEERING PERSONNEL 87 16 110 213 3.128 0.642 5.800 9.570 TOTAL 794 45 114 953 42.283 3.881 5.845 52.009 ROUTINE MAINTEPENE MAINTENANCE PERSONNEL 637 7 3 647 69.521 0.321 0.230 70.072 OPERATING PERSONNEL 33 1 0 34 0.386 0.002 0.000 0.388 HEALTH PHYSICS PERSONNEL 61 15 0 76 4.294 0.555 0.000 4.849 SUPERVISORY PERSONNEL 11 0 1 12 0.189 0.000 0.000 0.189 ENGINEERING PERSQNNEL 77 21 85 183 2.222 0.199 1.687 4.108 TOTAL 819 44 89 952 76.612 1.077 1.917 79.606 IN-SERVICE INSPECTION MAINIENANCE PERSONNEL 94 0 1 95 23.833 0.000 0.072 23.905 OPERATING PERSONNEL 2 0 0 2 0.072 0.000 0.000 0.072 HEALTH PHYSICS PERSONNEL 38 8 0 46 19.691 0.061 0.000 19.752 SUPERVISORY PERSONNEL 6 1 2 9 1.003 0.220 0.565 1.788 ENGINEERING PERSONNEL 19 11 57 87 1.614 8.661 48.604 58.879 TOTAL 159 20 60 239 46.213 8.942 49.241 104.396
$EECIAL MAINTENANG MAINTENANCE PERSONNEL 596 8 5 609 101.780 0.435 0.769 102.984 OPERATING PERSONNEL 23 1 0 24 0.136 0.006 0.000 0.142 HEALTH PHYSICS PERSONNEL 49 8 0 57 2.606 0.109 0.000 2.715 SUPERVISORY PERSONNEL 4 0 0 4 0.031 0.000 0.000 0.031 ENGINEERING PERSONNEL 75 27 162 264 9.507 2.057 35.711 47.275 TOTAL 747 44 167 958 114.060 2.607 36.480 153.147 REFUELING NONE WASTE PROCESSING MAINTENANCE PERSONNEL 112 0 0 112 2.225 0.000 0.000 2.225 OPERATING PERSONNEL 5 0 6 11 5.048 0.000 2.861 7.909 HEALTH PHYSICS PERSONNEL 30 1 0 31 1.116 0.004 0.000 1.120 SUPERV120RY PERSONNEL 4 0 0 4 0.211 0.000 0.000 0.211 ENGINEERING PERSONNEL 3 0 1 4 0.000 0.000 0.000 0.000 10TAL 154 1 7 162 8.600 0.004 2.861 11.465 TOTAL BY JOB FUNCTION MAINTENANCE PERSONNEL 2022 20 13 2055 216.745 0.819 1.116 218.680 OPERATING PERSONNEL 118 11 6 134 11.286 0.251 2.861 14.398 HEALTH PHYSICS PERSONNEL 235 47 0 282 40.730 3.662 0.000 44.392 SUPERVISORY PERSONNEL 37 1 3 41 2.536 0.220 0.565 3.321 ENGINEERING PERSONNEL 261 75 415 751 16.471 11.559 91.802 119.832 TOTAL 2673 154 437 3264 287.768 16.511 96.344 400.623
w- 3 m e-. E..a,. J- mm.. A a
'6 ENCLOSURE 3 PROPOSED OPERATING LICENSE AMENDMENT SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 (TVA-SQN-TS-88-23)
DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS b
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4 ENCLOSURE 3 Significant Hazards Evaluation TVA has evaluated the proposed operating license amendment change and has determined that it does not represent a significant hazards c;-sideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the proposed amendment will not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated. SQN unit 1 and unit 2 were designed and constructed on the basis of 40 years of plant operation. SQN's reactor vessel was fabricated and designed for a 40-year life. A comprehensive-vessel materials surveillance program is maintained in accordance with 10 CFR 50, Appendix H. An analysis was performed to demonstrate compliance with the NRC pressurized thernal shock (PTS) screening criteria in accordance with 10 CFR 50.61(b)(2). The assessment of the projected PTS reference temperature demonstrated that the SQN units 1 and 2 pressure vessels would meet the toughness requirements of 10 CFR 50.61 for 32 effective full-power years of operation which is equivalent to a 40-year design life with an 80-percent capacity factor. Aging analyses have been performed for all safety-related electrical equipment in accordance within the scope of 10 CFR 50.49 (harsh environment). The qualified life of the equipment or component is incorporated within SQN's maintenance and replacement practices to ensure that this safety-related electrical equipment remains qualified and available to perform its safety function regardless of the overall age of the plant. Programs are in place to detect abnormal deterioration and aging of critical plant components. These programs include:
A. ASME Boiler and Pressure Vessel Code,Section XI, and 10 CFR 50 Section 50.55(g).
- 1. In-Service Inspection (ISI) Program - This program ensures that plant pressure retaining vessels, piping, and support systems are inspected in accordance with the ASME Section XI code.
- 2. In-Service Test (IST) Program - This program ensures that safety-related pumps and valves are tested in accordance with the ASME Section XI code.
B. Technical Specifications.
In addition to the ISI and IST programs, the following SQN technical specifications also provide a means of monitoring the i cumulative effects of power operation during the lifetime of the l plant.
- 1. Specification 3.4.5 - Steam Generators l 1
An augmented steam generator inservice inspection program l demonstrates operability of SQN's steam generators over the j life of the plant. l l
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- 2. Specification 3.4.9.1 - Reactor Coolant System Pressure / Temperature Limits The pressure and temperature of the reactor coolant system are limited to protect against non-ductile failure of the reactor coolant system. These limits are updated periodically over the life of the plant to ensure that the fracture toughness requirements for the ferritic material within the reactor coolant pressure boundary are maintained.
- 3. Specification 3.4.10 - Reactor Coolant System Structural Integrity The ISI and IS'.' programs, in conjuction with the additional inspections required for the Reactor Coolant Pump flywheel and reactor vessel nozzels, ensure the structural integrity and operational readiness of these components will be maintained throughout the life of the plant.
Specification 5.7.1 - Component Cyclic or Transient Limit Monitoring, recording, and evaluation of certain cyclic and transient limits provides a high level of confidence that certain components within the reactor coolant and secondary systems will not experience fatigue failure over their 40 year design life.
(2) Create the possibility of a new or different kind of accident from any previously analyzed. The proposed amendment is administrative in nature and does not affect the safety analyais, plant equipment, or j the physical facility. Bec6use the accident analysis of SQN's FSAR !
remains bounding, no new or different kind of accident scenarios are l
created by this change.
(3) Involve a significant reduction in a margin of safety. The proposed amendment involves only a change to the expiration dates of the operating licenses. Because SQN is based on a 40-year service life, this change will not affect the safety margins.
Based on the above considerations, we conclude that the extension of the !
SQN operating licenses in accordance with the proposed amendment will not involve a significant increase in the probability or consequences of ;
accidents previously of a new or different kind of accident and w'11 not involve a significant reduction in a cafety margin. Therefore, we conclude that there is no significant hazards consideration associated with the proposed revision to the SQN operating licenses.
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>* ENCLOSURE 2 - TABLE 3 NUMBER OF PERSONNEL AND MAN-REM BY !.'ORK AND JOB FUNC1 Illegal width.
Printout terminated by system.
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