ML20077S419
| ML20077S419 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/09/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20077S421 | List: |
| References | |
| NPF-68-A-041, NPF-81-A-021 NUDOCS 9108270250 | |
| Download: ML20077S419 (14) | |
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GEORGIA POWER COMPANY I
OplETHORPEPOWERCORPORATION l
MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA
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CITY OF DALTON, GEORGIA f
DOCKET NO. 50-424 I
V0GTLE ELECTRIC GENERATING PLANT, UNIT 1 l
AMENDMENT-TO FACILITY-OPERATING LICENSE Amendment No. 41 License No. NPF-68 t
The Nuclear Regulatory Commission (the Comission) has found that:
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The application-for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility)~ Facility Operating License No. NPF-68 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-t
. ration, Municipal Electric Authority of Georgia, ar.d City of Dalton, Georgia (the licensees) dated March 29, 1991, complies with the standards and requirements of the Atomic-Energy 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
- t provisions-of the Act, and the rules and regulations of the-
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Commission; C.
There is-~ reasonable assurance (1) that the. activities authorized by this amendment can be-conducted without-endangering the health and i
safety of the public,'and (ii) that such activities will be-conducted i
in compliance with the-Commission's' regulations' set forth in 10 CFR Chapter I; D.
-The issuance.of.this license amendment will not-be-inimical to the common defense and security or to the-health and safety of the public;-
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The issuance of this amendment is in-accordance with 10 CFR Part 51 of the Commission's regulations and-all-applicable requirements htye been satisfied.
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Accordingly, the license is hereby amended by page changes to the Technical Specifications as-indicated in the attachment to this license amendment and paragraph 2.C.(2) of. Facility Operating License No. NPF-68 is hereby amended to read as-follows:
Technical Specifications and Environmental Protection Plan The. Technical Specifications contained in Appendix A, as revised through Amendment-No. 41 and the Environmental Protection Plan contained in Appendix B, both of which'are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications _and the-Environmental Protection Plan.
4 3.
This-license-amendment is effective as of~its date of issuance and shall be implemented within 30 days.of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
. Technical Specification Changes Date of' Issuance: August-9, 1991 d
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NUCLEAR REGULATORY COMMISSION 6
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GEORG,IA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-425 V0GTLE ELECTRIC GENERATING PLANT, UNIT 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No. NPF-81 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The app (lication for amendment to the Vogtle Electric Generating Plant, A.
Unit 2 the facility) Facility Operating License No. NPF-81 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated March 29, 1991, complies with the standards and requirements of the Atomic Energy 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; 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 set forth in 10 CFR Chapter I; D.
The issuance of this license 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's regulations and all applicable requirements have been satisfied.
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4.
5 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in.the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended.to read as follows:
Technical Specifications and Environmental Protection Plan
'The Technical Specifications contained in Appendix A, as revised.
through Amendment No. 21, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.
GPC shall operate the facility in accordance with the Technical Specifications.and the Environmental Protection Plan.
3.
This-license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: August 9,1991 y
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-4 ATTACMMENT TO LICENSE AliENOMENT NO. 41
[093b3Il_9ff.Ehl309.[JCENSE_ NO._ NPF-68 AND L 1CEN,S,E, AM,EppMEN,T, pp.,,21,
[0.CJ[JJy,pfffpJJpp,[JCENSEfl0.NPF-81 DOCKET NOS.,,50,,42,4, App,,50,,425 Replace the following pagesHof the Appendix "A" Technical Specifications.with
-the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages in, sert Pages ix
- ix
- X X
3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-24a 3/4 7-24b B 3/4 7-5 B 3/4 7-5 B 3/4 7-Sa B 3/4 7-6
- B 3/4 7-6 *
- Overleaf pages i
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity....................................
3/4 6-1 Containment Leakage......................................
3/4 6-2 Containment Air Locks....................................
3/4 6-4
-Internal Pressure........................................
3/4 6-6 Air Temperature..........................................
3/4 6-7 Containment Structural Integrity.........................
3/4 6-8 Containment Ventilation System...........................
3/4 6-11 3/4.6.2 DEJ. ESSURIZATION AND t00 LING SYSTEMS Containment Spray Systum.................................
3/4 6-13 Spray Additive System....................................
3/4 6-14 Containment Cooling System..............................
3/4 6-15 3/4.6.3 CONTAINMENT ISO LATION VALVES.............................
3/4 6-16 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................
3/4 6-18 Electric Hydrogen Recombiners............................
3/4 6-19 V0GTLE UNITS - 1 & 2 IX
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................
3/4 7-1 TABLE 3.7-1 HAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES........
3/4 7-2 TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P.....................
3/4 7-3 i
Auxi l i a ry Fee dwate r Sys tem...............................
3/4 7-4 Condensate Storage Tank..................................
3/4 7-6 Specific Activity........................................
3/4 7-7 TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PR0 GRAM.....................................
3/4 7-8 Main Steam Line Isolation Va1ves.........................
3/4 7-9 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................
3/4 7-11 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM..............
3/4 7-12 3/4.7.S ULTIMATE HEAT SINK.......................................
3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (Common System).
3/4 7-14 3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SY3 TEM....
3/4 7-17 3/4.7.8 SNUBBERS.................................................
3/4 7-19 i
FIGURE 4.7-1 SAMPLE PLAN 2 FOR SNUBBER FUNCTIONAL TEST............
3/4 7-24 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL.....................
3/4 7-24a l
3/4.7.9 SEALED SOURCE L0NTAMINATION...............................
3/4 7-2S 3/4.7.10 AREA TEMPERATURE M0HITORING..............................
3/4 7-27 TABLE 3.7-3 AREA TEMPERATURE MONITORING...........................
3/4 7-28 3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM...................................
3/4 7-29 3/4.7.12 REACTOR COOLANT PUMP THERHAL BARRIER COOLING WATER IS0LATION................................................
3/4 7-30 3/4.7.13 OIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER PUMPHOUSE ESF HVAC SYSTEMS..............................
3/4 7-31 Y
V0GTLE UNITS - 1 & 2 X
Amendment No. 41 (Unit 1)
Amendment No. 21 (Unit 2)
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PLANT SYSTEMS 3/4.7.8 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.8 All snubbers shall be OPERABLE.
The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
APPLICABILITY _:
MODES 1, 2, 3, and 4.
MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
With one or mcre snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or re-store the inoperable snubber (s) to OPERABLE status and perform an engineering eval-uation per Specification 4.7.8g. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.8 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program in addition to the requirements of Specification 4.0.5.
a.
Inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during) reactor operation.
Each of these groups (inaccessible and accessible may be inspected independently according to the schedule determined by Table 4.7-2.
The visual inspection interval for each category of snubber shall be detemined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before Amendment
/N and S / for Vogtle Units 1 and 2, respectively.
V0GTLE UNITS - 1 & 2 3/4 7-19 Amendment No. 41 (Unit 1)
Amendment No. 21 (Unit 2)
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1 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Visual Inspection Acceptance Criteria Visual inspections shall verify that:
(1) there are no visible indi-cations of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fatteners for attachment of the snubber to the component and to the snuober anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers, irrespective of type, that may be l
generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specifi-cation 4.7.8f.
All snubbers found connected to an inoperable common l
hydraulic fluid reservoir shall be counted as unacceptable and may be reclassified as acceptable for determining the next inspection inter-val provided that criteria (1) and (2) donve are met.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
d.
Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients as determined from a review of operational data and a visual inspection of the systems within 6 months following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified ming at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in place snubber piston setting; or
-(3) stroking the mechanical snubber through its full range of travel.
e.
Functional Tests Du ing the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of snubbers of each type shall be tested using one of the following sample plans.
-The sample plan for each type shall be selected prior te tne test period and cannot be changed during the test period.
The NRC Regional Administrator shall be notified in writing of the sample plan selected for each snubber type prior to the test period or the sample plan used in the prior test period shall be impleunted:
1)
At least 10% of the total of each type of snubber shall be functionally tested either in place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.8f., an additional 10%
of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or V0GTLE UNITS - 1 & 2 3/4 7-20 Amendment No. 41 (Unit 1)
Amendment No. 21 (Unit 2)
i TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF UNACCEPTABLE SNUBBERS Population Column A Column B Colu:n C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber population or cate-gory size shall be determined based upon the previous inspection inter-val and the number of unacceptable snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly.
However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubber; as determined by interpolation.
Note 3:
If the number of unacceptable snubbers is equal to or less,than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 46 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the number in Column 5 but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
V0GTLE UNITS - 1 & 2 3/4 7-24a Amendment No. 41 (Unit 1)
Amendment No. 21 (Unit 2) i
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TABLE 4.7-2'(ContinuedL 3
SNUBBER VISUAL INSPECTION INTERVAL Note 5:' If the_ number-of unacceptable sn'!bbers is eqval #2 1r greater than the l
number in Column C, the next inspection interva;,;all be two-thirds of the previous interval.
However, if the number of unacceptable
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-i snubbers is-less than the numter in Column C but greater than the num-ber'in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall-be reduced by a i
factor that is one-third of the ratio of the difference between the i
number of unacceptable snubbers found during the previous intervals and the number in Column B to the difference in tie numbers in Columns B and C.
j Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and-including 48 months.
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V0GTLE UNITS - 1 & 2 3/4 7-24b Amendment No. 41 (Unit 1)
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Amendment No. 21 (Unit.2)
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PLANT SYSTEMS BASES SNU8BERS (Continued)
Nuclear Regulatory Commission (NRC) Generic letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions,'
dated December 11, 1990, provides an alternate method for determining the next interval for the visual inspection cf snubbers from that to which the plant was originally licensed.
The original schedule for snubber visual inspection was based only on the number of inoperable snubbers found during the previous visual inspection irrespective of the size of the snubber population.
As a result, plantshav}ngalargenumberofsnubbersfoundtheoriginalinspectionschedule to be excessively restrictive.
Significantresources,includingsubjecting piant personnel to unnecessary radiological exposure, were expended in order to com)1y with the visual inspection requirements.
The alternate schedule provided by 1RC Generic letter 90-09 maintains the same confidence level as that to which the plant was originally licensed and generally allows for the performance of visual inspections and any corrective actions during plant outages.
Incorporated herein es Table 4.7-2, " Snubber Visual Inspection Interval," the alternate intpection schedule is based upon the number of unacceptable snubbers found during the previous inspection in proportion to the size of various snubber populations or categories.
Snubbers may be categorized based u)on their accessibility during power operation, as accessible or Inaccessiale.
The categories may be inspected separately or jointly.
However, categorization and inspection thereof must be made end documented prior to any inspection and that decision will constitute the basis for determining the next inspection interval for that category.
A snubber is considered unacce the acceptance criteria for the visual inspection.ptable if it fails to satisfy If review and evaluation shall be declared inoperable and the applicable ACTION requirements shall be met.
To determine the next inspection interval, the unacceptable snubber may be reclassified as acceptable if it can be demonstrated that the snubber is operable in its as-found condition by the performance of a functional test and if it satisfies the acceptance criteria for functional testing.
The next inspection interval may be twice, the same, or reduced to as much as two-thirds of the previous inspection interval and is cuntingent upon the number of unacceptable snubbers found in proportion to the population or category for each type of snubber included in the previous inspection.
While the original inspection schedule requirements established inspection intervals of 18 months (the length of a nominal fuel cycle) or a fraction thereof based on the number of inoperable snubbers of each type for the previous inspection period, the alternate method allows inspection intervals to be compatible with a 24-month fuel :ycle.
The interval may be increased to every other refueling outage for plants on a 24-month fuel cycle cr up to 48 months for plants with other fuel cv s if few unacceptaole snubbers are found from the previous inspection.
Taole 4.7-2 establishes limits for determining the next inspection interval and is consistent with the guidance provided in NRC Generic Letter 90-09.
l V0GTLE UNITS - 1 & 2 B 3/4 7-5 Amendment No.41 (Unit 1) l Amendment No.21 (Unit 2)
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PLANT SYSTEMS BASES SNUBBERS (Continued)
The acceptance criteria are to be used in the visual inspection to deter-mine OPERABILITY of the snubbers.
For example, if a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be counted as unacceptable and may be reclassified as acceptable for determining the next visual inspec-tion interval provided that certain criteria in Specification 4.7.8c are met.
Areviewandevaluationshallbeperformedanddocumentedtojustifycontinued operation with the unacceptable snubber..If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
To provide assurance of snubber functional reliability, one of three functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 10% of a type of snubber with an additional 10%
tested for each functional testing failure, or 2.
Functionally test a sample size and determine sample acceptance or rejectionusingFigure4.7-1,or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was develooed using "Wald's Sequential Probability Ratio Plan" as described in " Quality Control and Industrial Statistics" by Acheson J. Duncan.
Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the com-pletion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
V0GTLE UNITS - 1 & 2 B 3/4 7-Sa Amendment No.41 (Unit 1)
Amendment No. 21 (Unit 2)
PLANT SYSTEMS BASES SNUBBERS (Continued)
The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (newly installed snubbers, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits for plutonium.
This limitation will ensure that leakage from Byproduct, Source, and Special Nuclear Material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with Surveillance Requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are
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continuously enclosed within a shielded r.echanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3/4.7.10 AREA TEMPERATURE MONITORING The area temperature limitations specified in Table 3.7-3 ensure that safety-related equipment not serviced by ESF HVAC systems and necessary for safe shut-down will not be subjected to temperatures in excess of their environmental qualification temperatures.
Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY.
3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM The operation of the ESF Room Cooler and Safety-Related Chiller System ensures that the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment cooled by the system.
3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER ISOLATION This isolation function is designed to prevent a spill of the reactor coolant from a postulated breached thermal barrier should a break occur in the nonsafety-related ACCW piping downstream of the isolation valve.
V0GTLE UNITS - 1 & 2 B 3/4 7-6
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