ML20094J332
| ML20094J332 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/05/1992 |
| From: | Hall J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20094J334 | List: |
| References | |
| NUDOCS 9203120338 | |
| Download: ML20094J332 (13) | |
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UNITED STATES 3,.,
i NUCLEAR REGULATORY COMMISSION 2-f W ASHINGToN. O C 2%66 o,gv f
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UNION ELECTRIC CCM ANY CALLAWAY FL/t;T, UNIT 1 CCCKET NO. STN 50-453 AMENDMENT TO FACILITY OPERATING LICEt!SE Amendment No. 67 License No. NPF-30 1.
The Nuclear Regulatory Cornission (the Commiss i) has found that:
A.
The application for amendn.ent filed by Union Electric Company (UE, tFe licensee) dated August 1,1991, as supplemented by letter dated February 19, 1997, coniplies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (th 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.
liare is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amn" ment will not be inimical to the common defense and security or the health and safety of the publict and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and para-graph 2.C.(2) of Facility Operating License No. NPF-30 is hereby amended to read as follows:
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in /ppendix A, as revised through Amendment No. 67, and the Environmental Protection Plan -
contained in Appendix B, both of which are attached hereto, are hereby incorporated into the license.
UE shall operate the facility i
in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This-license amendment is effective as of-its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1sbj k
/
Jemes-R. Hall, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects 111/IV/V-Office of Nuclear Reactor Regulation
Attachment:
Changes-to the Technical Specifications Date of issuance:
March 5,-1992-
-~
e ATTACHMENT TO LICENSE AMENDMENT NO. 67 OPERATING LICENSE NO. NPF-30 DOCKET N0. !0-483 i
' Revise Appendix A Technical Specifications by removing the pages identified f
below and inserting the enclosed pages.
The revised pages are identified by the captioned amendmert number and contain marginal lines indicating the area of change.
Corresponding overleaf pages are provided to maintain document completeness.
REMOVE INSERT X
X 3/4 7-19 3/4 7-19 3/4 7-20 3/4 7-20 3/4 7-23 3/4 7-23 3/4 7-23a 3/A 7-23b 3/4 7-03b 3/4 7-24 3/4 7-24 8 3/4 7-5 B 3/4 7-5
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE20!R,EMENTS SECTION PAGE PLANT SYSTEMS (Continued)
TABLE 3.7-2 STEAM LINE SAFETY VALVES PER L00P...........
3/4 7-3 Auxiliary feedwater System.....,,,...................
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 Valves........................
3/4 7-9 Main Feedwater System...................................
3/4 7-9a Steam Generator Atmospheric Steam Dump Valves............
3/4 7-9b 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 ESSENTIAL SERVICE WATER SYSTEM...........................
3/4 7-12 3/4.7.S ULTIMATE HEAT SINK.......................................
3/4 7-13
' 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM................
3/4 7-14 3/4,7.7 EMERGENCY EXHAUST SYSTEM.................................
3/4 7-17 3/4.7.8 S N U B B E RS.................................................
3 / 4 7 - 19 TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL,..................
3/4 7-23a l
- FIGURE 4.7-1 SAMPLING PLAN 2) FOR SNUBBER FUNCTIONAL TEST.........
3/4 7-24 3/4.7.9 SEALED SOURCE CONT AMI NATION............................-..
3/ 4 7-2S 3/4.7.10 Deleted 3/4.7.11 Deleted
- 3/4.7,12 AREA TEMPERATURE M0NITORING..............................
3/4 7-37 TABLE 3.7-4 AREA TEMPERATURE MONITORING.,......................
3/4 7-38 CALLAWAY - UNIT 1 X
Amendment No. 30, AE. 67
INDEX LIMlllNG CON 0lI10NS,FOR OPERATION AND SURVE!LLANCE REQUIREMENTS SEC110N PAGE (MERGENCY CORE COOLING SYSTEMS (Continued) 3/4=5.5 REFUELING WATER STORAGE TANK.
3/4 S 10 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 lemperature.
3/4 6-7 Containment Vessel Structural Integrity....
3/4 6-8 Containment Ventilation System.
3/4 6-11 3/4.6.2-DEPRESSURIZATION AND COOLING SYSTEMS Containment spray System.
3/4 6-13 3/4 6-14 Spray Additive System.
Containment Cooling System.
3/4 6-15 3/4 6-16 3 / +1. 6. 3 CONTAINMENT ISOLATION VALVES...
TABit 3.6-1 CONTAINMENT ISOLATION VALVES,.
3/4 6-18 3/4.6.4 COMBUSTIBLE GAS CONTROL-Hydrogen Analyzers..
3/4 6-31 3/4 6-32 Hydrogen Control Systems.
1/4; / PLANI 5) STEMS 3/4. 7.1 TilRBlNE CYCLE 3/47-1 Safety Valves..
1ABLt 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING FOUR LOOP OPERATION.,
3/4 7-2 Call AWAf - UNii 1 It
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PLANTSYSTE?l-3/ 4 ~. 7. 8 SNUBBERS _
L!MITING CONDITION FOR OPERAT10N 3.7.8 All snubbers shall be OPERASLE.
The only snubbers excluded from _the requirement are those installed on nonsafety-related systems, and then only if theirLfailure or failure of the _ system.on which they are installed would have no adverse' ef fect on any. safety-related system.
APPLICABILITY:
MODES 1, 2, 3, and 4 1100ES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.
ACTION:
i' With one or more snubbers inoperable on any system, within 72_ hours replace or restore the inoperable snubber (s) to GPEPABLE-status and perform an enaineering
_ evaluation per Specification 4.7.89. cn the atteched 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 lieu of the requirements of Specification 4.0.5.
-a.
' Inspection Type _s_
As used 'in this specification, type of snubber shall mean snubbers
- of -tne same des ign and manuf acturer,- irrespective of capacity, b.
Visual Inspections Snubbers _are_categori:ed as inaccessible or accessible during.
reactor operation.
Each of these categories (inaccessible and-accessible) may be inspected independently according to the-schedule determined by Table 4.7-2.
The visual inspection interval for each type of snubber:shall be determined-based upon the criteria provided in Table 4.7-2 and the first inspection interval detennined -
using_this criteria shall be based upon the previous inspection interval as established by the requirements in-effect before-
-Amendment No. 67 l-l L
CALLAWAY - UNIT 1 3: 4 7-19 Amenoment No. 67
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'SURVEILLANCEREQUIREMENTS(Continued c.
Lisual Inspection Acceptance Criteria-
-Visual inspections shall verify that (1) there are no visible indications of damace or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to tho-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 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 generic-l ally susceptible; and (2) the affected snubber is functionally tested _in the as-found condition and determined OpEp.ABLE per Specification 4.7,8f.
All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval.
A review and: evaluation shall be performed and documented to i-determine system operability with an unacceptable snubber.
If operability cannot be -justified, the system shall be declared inoperable and the ACTION requirements shall be met.
d.
Transient Event Inspection 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 cf the systems within 6 months following such an event.
In addition to satisfy-ing 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 pisto_n setting; or (3) stroking the mechanical
= snubber through its full-range of travel, l
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CALLAWAY --UNIT 1 3/4 7-20 Amendment No. 67
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TABLE J 7.?
S 4U. I:C E.R..V I_SU AL.I.N5 P E C.i t DN _I NT. E..R.V At
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NpgR nr UNACCEPT ADt.E SWDBERS C ol'u ti B" ' ~ " ~
Col'umn T ~ ~ ~ ^
Population
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s or (3tegory stend Intersal Pe;> eat Interval Reduce Interval (Notes 1 and ?$
tiptes 3_and.fl
,(Not es 4 a nd 6). _, jf!c t e', 5 and,6) _ _
1 0
0 1
l 00 0
0 2
100 0
1 4
150 0
3 I
I 200 2
5 13 300 5
12 25 i
1 400 8
18 36 l
500 12 24 48 l
1 750 20 40 78 1000 or greater 29 56 109 i
I Note 1:
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval and j
the numcer of unacceptable snubbers found during that interval. Snubbers l
may be categorized based upon their accessibility during power opera-6 tion, 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 at the basis upon which to determine the next inspection interval for that I
category.
flote 2:
Interpolation between population or category s h es 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 f ractional 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 ruonths, Note 4:
!f the number of unacceptable snubbers is equal to or less than the number in Column B but areater than the number in Column A the next inspection interval shall be the same as the previous interval.
CALLAWAY - UNIT 1 3/4 7-23::
Amendment No. 67
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Service Life Monitoring (Continued) f o r t ht-snubbers found inoperable. an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached.
The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are l
I attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains c4Dable of meeting the designed service.
If any snubber selected for functional testing either fails to
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lock up or f eils to move, i.e., f rozen-in place, the cause will be evelvated and, if caused by manuf acturer or design deliciency, all l
snubbers of the sarrie type subject to the same cefect shall be func-This testing requirement shall be independent of l
tionally tested.
the requirements stated in Spacification 4.7.8e. for snubbers not 1
meeting the functional test acceptance criteria.
h.
Functional festing of Repaired _and Replaced _S,nubbert Snuobers which fall the visual inspection or the functional test acceptance criteria shall be repaired or replaced.
Replacement snubbers and snubbers which have repsirs which eight affect the functional test results shall be tested to meet the functional test criteria before installation in the unit.
I Mechanical snubbers shall l
have met the acceptance criteria subsequent to their most recent service, and the freedom of motion test must have been performed within 12 months before being installed in the unit.
i.
Snubber Service life Program The service life of hydraulic and mechanical snubbers shall be moni-I tored to ensure that the service life is not exceeded between sur-l veillance inspections.
The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history, i
Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be
- OPERABLE, The parts replacements shall be documented anc' the docu-mentation shall be retained in accordance with Sp uification 6.10.7.
CALLAWAY - UNIT 1 3/4 7-23
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t TABLE 4./ ? (continued)
SNUBBER VISUAL INSPECTION INTERVAL (continued)-
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Note 6:
If the number of unacceptable snubbers is equal to or creater than the number in Column C. the next inspection interval shall be two-thirds of the previous intervai.
However, if the nunber of unaccept-able snubbers is less than the nucber in Column C but greater than the number in Column B. the next interval shall be reduced propor.
i tionally by interpolation; that is, the previous interval shall be reduced by a factor that is one-third of the ratip of the difference
- between the number of unacceptable snubbers found during the previous.
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 includinq 48 months.
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i PLANT SYSTEMS BASES 3/4.7.9 5NUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant Systen and all other safety related systems are main-tained during and following a seismic or other event initiating dynamic loads.
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Snubbers are classified and grouped by design and manufacturer, but not
~by-site, for example, mechanical snubbers utilizing the same design features i
of the 2 kip. 10-kip and 100-kip capacity mcnufactured by Company "A" are of i
the same type.
The same design mechanical' snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic' snubbers from either manufacturer.
Snubbers may also be classified and grouped be
'essible or accessible for visual inspection o..
purposes.
Therefore, ea t sne.
? Tm may be grouped for inspection in accordance with accessib sit;o A list of individual si a e with detatled infornation of snubber location and size and of systems affected thall be available at the plant in accordar.ce with Section 50.71(c? of 10 CFR pi rt 50.
The accessibility of each snubber-shall be determined and approved t y the On 51te Review Connittee.
The deter
- mination 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., tempera-t ture, 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 on the number of unacceptable snubbers found during the previous inspective) in-proportion to the size of
-t the various snubber populations or categories.
The Snubber Visual Inspection Interval is determined in accordance with Table 4.7-2.
-The maximum inspection interval can be as long as two refuel cycles'but not more than 48 months.
provided the requirements of Table 4.7-2 are met.
A snubber is considered unacceptable if it fai'Is the acceptance criteria of visual inspection.
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 d hydraulic 1
CALLAWAY - UNIT 1-B 3/4 7-5 Amendment No. 67
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j PL ANT SYSTEM 5 BASES SNUB.FJ35 (Continued) snubber is found to be uncovered, the snubber shall be declared inoperable and shall not be determined OPERABLE via functional testing.
Since the visual inspections are augmented by functional testing program, the vi'wal scrutiny suf ficient to assure that fasteners or mountings for connecting t he snubbers to supports or foundations shall have no visible bolts, pins or fasteners missing, or other visible signs of physical damage such as cracking or loosening.
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-To provide assurance of snubber funct.ional reliability one of three l
functional testing methods are used with the stated acceptance criteria:
t 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 rejection using figure 4.7-1, or 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
Figure 4.7-1 was developed 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 perfonned.
to qualify the snubber for the applicable design conditions at either the com-pletion of their fabrication or at a subsequent data.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
P The service life of a snubber is established via manufacturer input and information through consideration of the snubber service conditions and f
associated installation and maintenance records (newly installed snubber, seal replaced sping replaced, in high radiation area, in high temperature area, etc.).
The requirenent to monitor the snubber service life is included to ensure that the snubbers periodically undergo a-performance evaluation in view if their age and operating conditions.
These records will provide statistical bases for future consideration of snubber service life.
- 3/4.7.9 SEALE01$0VRCE-CONTAMINATlqy-
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The limitation 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.
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