ML20099H870
| ML20099H870 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/31/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099H872 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9208190247 | |
| Download: ML20099H870 (13) | |
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UNITED STATES g
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DfTROIT EDISON COMPANY FERMI-2 DOCKET NO. 50-341 AMENDMENT TO FACitiTY OPERATING LICENS1 Amendment No. 84 License No NPF-43 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Detroit Edison Company (the licensee) dated January 28, 1992, 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; C.
The facility will operate in conformity with the application, t,a provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health end safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendnient will not be inimical to the common defensa 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:
lTgchnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9200190247 920731 DR ADocK 0500 1
. 1 3.
This license amendment is effective as of the date of its issuance with full implementation within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 31,1992 1
ATTACHMENT TO LICENSE AMENDMENT NO. 84
[A(JLily_DPERATING LICENSE N0. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
ElbDYE INSERT xxiv xxiv 3/4 7-15*
3/4 7-15*
g 3/4 7-16 3,4 7-16 3/4 7-17 3/4 7-17 3/4 7-18*
3/4 7-18*
3/4 7-20a 3/4 7-20b B 3/4 7-2 B 3/4 7-2 B 3/4 7-3 8 3/4 7-3 B 3/4 7-4 B 3/4 7-4 T
t h1
- 0verleaf page provided to maintain document completeness.
No changes contained in these pages.
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7 LIST OF TABLFS (Continued)
TABLE EAGI 3.3.7.9-)
DELETED..........................................
3/4 3-68 3.3.7.12-1 EXPLOSIVE GAS MONITORING INSiRUMENTATION.........
3/4 3-77 4.3.7.12 1 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQVIREMENTS........................
3/4 3-81 3.3.9-1 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION..................................
3/4 3-87 3.3.9 2 FEEDWATER/ MAIN TURBINE TRIP SYSTEM ACTVATION INSTRUMENTATION SETP0lNTS........................
3/4 3 88
-4.3.9.1-1 FEEDWATER/ MAIN TUR8INE TRIP SYSTEM ACTVATION INSTRUMENTATION SURVEILLANCE REQVIREMEN1$........
3/4 3 89 3.3.11-1 APPENDIX R ALTERNATIVE SHUT 00WN INSTRUMC,TATION.,
3/4 3 91 4.3.11.1-1 APPENDIX R ALTERNATIVE SHVTDOWN INSTRUMENTAT10'2. SURVEILLANCE REQVIREMENTS........
3/4 3 92 e
3.4.3.2-1 REACTOR COOLANT SYSTF.M PRESSURE ISOLATION VALVES.............
3/4 4-12 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE M0NITORS................................
3/4 4-12 1.4.4-1 REACTOR C00LAhi SYSTEM CHEMISTRY LIMITS..........
3/4 4-15 4.4.5-1 PRIMARY COOLANT SPECIFIC ACTIVITY SNMPLE AND ANALYSIS PR0 GRAM.................................
3/4 4-18 4.4.6.1.3-1 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM--
WITHDRAWAL SCHEDULE..............................
3/4 4 22
-4.6.1.1-1 PRIMARY CONTAINMENT ISOLATION VALVES / FLANGES LOCATED IN LOCKED HIGH RADIATION AREAS...........
3/4 6-lb 3.6.3 1 PRIMARY CONTAINMENT ISOLATION VALVES.............
3/4 6-22 3.6.5.2-1 SECONDARY CONTAINMCNT VENTILATION SYSTEM AUTOMATIC YSOLATION DAMPERS......................
3/4 6 53 3.7.3-1 SURVEY POINTS FOR SHORE BARRILT...................
3/4 7-12 4.7.5-1 SNVBBER VISUAL INSPECTION INTERVAL...............
3/4 7-20a j
3.7.7.5-1 DELETED..........................................
3/4 7-32 3.7.7.6 1 DELETE0........................
3/4 7-37 4.8.1.1.2-1 DIESEL GENERATOR TEST SCHEDULE...................
3/4 8-8 FERMI - UNIT 2 xxiv Amendment No. f),JJ,$J,EJB4
1 PLAtlT SYSTEMS SURVEIllAt1CE RE0VIREMENTS (Continued)
P c.
At least once per 18 months by:
1.
Performing a system functional test which included simulated I
automatic actuation and restart and verifying that each automatic valve in the flow path actuates to its correct position. Actual injection of coolant into the reactor vessel may be excluded.
2.
Verifying that the system will develop a flow of greater than or equal to 600 gpm in the test flow path vita a system head corresponding to reactor vessel operating p. essure including injection line losses when steam is being supplied to the turbine at a pressure of 150 + 50, 0 psig.*
3.
Verifying that the suction fo-the RCIC system is automatically transferred from the condensate storage tank to the suppression pool on a condensate storage tank water level low signal.
M he provisions of Specification 4.0.4 are not appitcable provided the surveillance is performed within 12 hcars after reactor steam pressure is adequate to perform the tests.
FERMI UNIT 2 3/4 7-15
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PLANT SYSTEMS 3/4.7.5 SNUBBERS LIMITitG CONDITION FOR OPERATIOJ 3.7.5 All* hydraulic mo !tewanical snubbers shall be OPERABLE.
82Pl!CABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
OPEPATIONAL CON 0lT10NS 4 and 5 for snubbers located on systems required OPERABLE in those OPEPATIONAL CONDITIONS.
ACTION:
With one or more 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 restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.5g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.-
-lyRJEILL ANCE REQUIREMENTS 4.7.5 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 Tvoes As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections Snubbe-s are categorized as inaccessible or accessible during 5
-reactor operation.
Each of these categories (inaccessible and I
accessible) may be inspected independently according to the i
schedule determined by Table 4.7.51.
The visual inspection interval for each category of snubber shall be determined based upon the criteria-provided in Table 4.7.5-1.
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
- As described in the bases, i
FERMI'- UNIT-2_
3/4 7-16 Amendment No. 84 1.
t, PLANT SYSTEMS SVRVEILLANCE REDVIREHENTS (Continued) i l
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yj a l Inspection Acceptance Criteria Visual inspections shall verify that:
(1) there are no visible indications of damage or impaired OPERABILITY and (2) attachments to the foundation or supporting structure are functional, and (3) l fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for tha purpose of establishing the next visual inspection interval, provided that:
(1) the cause of the rejection is clearly esta)11shed and remedied for that particular snubber and for other snubbers that j
may be genericc11y susce)tible; and (2) the affected snubber is functionally tested in tie as-found condition and determined OPERABLE per Specification 4.7.5f.
For those snubbers common to more than one system, the OPERABILITY of such snubbers shall be considered in assessing the OPERABILITY of each of the related systems.
A review and evaluation shall be performed and documented to justify continued operation with an unacceptable I
- snubber, if continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.
L d.
Transient Event insoection An inspection shall.be performed of all hydraulic and mechanical 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 L
within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible areas and 6 months for inaccessible areas following such an event.
In addition to satisfying the visual inspection acceptance criteria, freedom-of motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber phton setting; or (3) stroking the mechan _ical snubber through its full range of travel.
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-FERMI - UNIT 2 3/4 7 17 Amendment No. 84 e
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PLANT SYSTEMS SURVElllANCE REQUIREMENTS _(Continued) l' e.
Functional Tests During the first refueling shutdown and at least once per 18 months thereafter during shutdown, a representative sample of snubbers shall be tested using one of the following sample plans.
The sample alan shall be selected prior to the test period and cannot be clanged during the test period.
The NRC Regional Administrator shall be notified in writing of the sample plan selected prior to the test period or the sample plan used in the prior test period shall be implemented:
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 4.7.5f., an additional 5% 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 2)
A representative sample of each type of snubber shall be functionally tested in accordance with Figure 4.7.5-1.
"C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.7.5f.
The cumulative number of snubbers of a type tested is denoted by "H"
At the end of each day's testing, the new values of "N"
and "C" (previous day's total plus current day's increments) shall be plotted on figure 4.7.5-1.
If at any time the point plotted falls in the " Reject" region all snubbers of that type shall be functionally tested.
If at any time the point plotted falls in the
- Accept" region, testing of snubbers of that tyoe may be terminated. When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the points falls in the " Accept" region or the " Reject" region, or all the snubbers of that type have ben tested.
Testing equipment failure during functional testing may invalitte that day's testing and allow that day's testing to resume anew at a later time, providing all snubbers tested with the failed equipment during tl.e day of equipment failure are retested; or 3)
An initial representative sample of 55 snubbers shall be functionally tested.
For each snubber type which does not meet the functional test acceptance criteria, another sample of 4t least one half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the factor,1 + C/2, where "C" is the number of stubbers found which do not meet the functional test acceptance criteria.
The results from this sample plan shall be FERMI - UNIT 2 3/4 7-18
TABLE 4.7.5-1 SMEIJLVISUAL INSPECTION INTERVAL NUMBER OF UNALCEPTABLE SNUBBERS I
Population Column A Column B Column C or Category Extend Interval Repeat Interval Reduce Interval INotes 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 j
400 8
18 36 500 12 24 48 750
?0 40 78 1600 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber population or categury shall be determined based u>on the ?revious inspection interval and the number of unaccepta)1e snubsers 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.
FERMI - UNIT 2-3/4 7-20a Amendment No.84
e TABLE 4.7.5 1 NOTES (Continued)
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 snubbers 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 48 months.
Note 4:
If the nun,ber of unacceptable snubbers is equal to or less than thenumberinColumnBbutkreaterthanthenumberinColumnA, the next inspection interva shall be the same as the previous I
- interval, i
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation; that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previcus interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
l FERMI - UNIT 2 3/4 7-20b Amendment No. 84
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l PLANT SYSTEMS BASES REACTOR CORE ISOLATION COOLING SYSTid (Continued)
With the RCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCI system and justifies the specified 14-day out of service period.
The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required.
Although all active components are testable and full flow car, be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage and to start cooling at the earliest possible moment.
3/4.7.5 SNUBBERS All snubbers are required OPERAu.E to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are taose installed on nonsafety-rclated 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.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, a*d 100 ktp capacity manufactured by Company "A" are of the same type. The sa;..e design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be a different type, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of sr.ubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Onsite Review Organization.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,
temperature, atmosphere, location, etc.), and the recommendations of Regulatory-Guides 8.8 and 8.10.
The addition or deletion of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to each safety-related system.
Therefere, the required inspection interval varies based upon the number of unacceptable snubbers found during the previous inspection in proportion to the sizes of the various snubber populations or categories and the previous inspection interval as specified in NRC Generic Letter 90-09, " Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions".
In order to j
establish the inspection frequency for each type of snubber on safety-related FERMI - UNIT 2 B 3/4 7-2 Amendment No. 84 l
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PLANT SYSTEMS BASES SNUBBERS (Continued) systems it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on any system could cause the system to become unprotected and, therefore, result in failure during an assumed initiating event.
Inspections performed before the interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous j
schedule.
The acceptance criteria used in both the visual inspections and the functional testing determines the OPERABILITY of the snubber (s).
When a snubber is determined to be inoperable, an Engineering Evaluation is required.
This provides for an evaluation of the snubber mode of-failure to determine if the snubber mode of failure has adversely affected the safety-related component or system to which it was attached.
This evaluation will further verify that the system is still capable of meeting its design function.
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 5%
l tested for each functional testing failure, or 2.
Functionally test a. sample size and determine sample acceptance or rejection using figur? 4.7.5-1, or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7.5-1 was developed using "Wa'id'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 completion 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.
FERMI - UNIT 2 B 3/4 7-3 Amendment No. 84 IS
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PLANT SYSTEMS BASES 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 snubber, 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 previde statistical bases for future consideration af snubber service life.
3/4.7.6 SEALED SOURCE _C.0NTAMINATION The limitations on removable contamination for sources requiring-leak testing, including alpha emitters, is based on 10 CFR 70.39(c) 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 grou)s according to their use, with surveillance requirements commensurate with tie 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 continuously enclosed within a shielded mechanism, 1.e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
3.1.7.7 DELETED 3/1.7.8 DELETED i
FERMI
-UNIT 2 B 3/4 7-4 Amendment No. 51,84
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