ML20070G441
| ML20070G441 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/13/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070G442 | List: |
| References | |
| NUDOCS 9407200105 | |
| Download: ML20070G441 (33) | |
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UNITED STATES Ei j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20565-0001 l
Q i
COMMONWEALTH EDIS0N COMPANY b.NQ IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 t
00AD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 149 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 11, 1994, 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 (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 amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
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 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
i 9407200105 940713 PDR ADOCK 05000254 p
. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 149, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificatic: s.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION T MO-.0f-l Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 13, 1994
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ATTACHMENT TO LICENSE AMENDMENT NO. 149 FACILITY OPERATING LICENSE N0. DPR-29 l
t DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 11 11 y
v 3.6/4.6-12a 3.6/4.6-12a 3.6/4.6-13 3.6/4.6-13 3.6/4.6-14 3.6/4.6-14 3.6/4.6-15 3.6/4.6-15 3.6/4.6-15a 3.6/4.6-15b 3.6/4.6-15c 3.6/4.6-15d 3.6/4.6-24 (Bases) 3.6/4.6-24 (Bases) 3.6/4.6-24a (Bases) 3.6/4.6-25 (Bases) 3.6/4.6-25 (Bases) 3.6/4.6-25a (Bases) 3.6/4.6-36 (Table 4.6-3) 3.6/4.6-36 (Table 4.6-3)
Figure 4.6-2 i
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l QUAD CITIES DPR-29 TABLE OF CONTENTS (Cont'd) l Page 3.4/4.4 STANDBY LIQUID CONTROL SYSTEM 3.4/4.4-1 A.
Normal Operation 3.4/4.4-1 B.
Operation with Inoperable Components 3.4/4.4-2 C.
Liquid Poison Tank-Boron Concentration 3.4/4.4-2 i
3.4 Limiting Conditions for Operation Bases 3.4/4.4-4 3.5/4.5 CORE CONTAINMENT COOLING SYSTEMS 3.5/4.5-1 A.
Core Spray Subsystems and the LPCI Mode of the RHR Systems 3.5/4.5-1 B.
Containment Cooling Mode of the RHR System 3.5/4.5-3 l
C.
HPCI Subsystem 3.5/4.5-5 D.
Automatic Pressure Relief Subsystems 3.5/4.5-6 E.
Reactor Core Isolation Cooling System 3.5/4.5-7 F.
Minimum Core and Containment Cooling System Availability 3.5/4.5-8 G.
Maintenance of Filled Discharge Pipe 3.5/4.5-10 l
H.
Condensate Pump Room Flood Protection 3.5/4.5-11 I.
Average Planar Linear Heat Generation Rate (APLHGR) 3.5/4.5-13 J.
Local LHGR 3.5/4.5-13 i
K.
Minimum Critical Power Ratio (MCPR) 3.5/4.5-14 3.5 Limiting Conditions for Operation Bases 3.5/4.5-15 4.5 -
Surveillance Requirements Bases 3.5/4.5-23 3.6/4.6 PRIMARY SYSTEM BOUNDARY 3.6/4.6-1 A.
Thermal Limitations 3.6/4.6-1 B.
Pressurization Temperature 3.6/4.6-2 C.
Coolant Chemistry 3.6/4.6-3 D.
Coolant Leakage 3.6/4.6-5 E.
Safety and Relief Valves 3.6/4.6-6 F.
Structural Integrity 3.6/4.6-6 G.
Jet Pumps 3.6/4.6-9 H.
Recirculation Pump Flow Limitations 3.6/4.6-11 I.
Shock Suppressors (Snubbers) 3.6/4.6-12a 3.6 Limiting Conditions for Operation Bases 3.6/4.6-16 3.7/4.7 CONTAINMENT SYSTEMS 3.7/4.7-1 i
A.
Primary Containment 3.7/4.7-1 i
B.
Standby Gas Treatment System 3.7/4.7 12
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C.
Secondary Containment 3.7/4.7-17 D.
Primary Containment Isolation Valves 3.7/4.7-18 il Amendment No. 149 J
QUAD CITIES DPR-29 TECHNICAL SPECIFICATIONS APPENDIX A LIST OF TABLES Number Title Page 3.1-1 Reactor Protection System (Scram)
Instrumentation Requirements-Refuel Mode 3.1/4.1-11 3.1-2 Reactor Protection System (Scram) Instrumentation Requirements-Startup/ Hot Standby Mode 3.1/4.1-12 3.1-3 Reactor Protection System (Scram) Instrumentation Requirements-Run Mode 3.1/4.1-13 3.1-4 Notes for Tables 3.1-1, 3.1-2, and 3.1-3 3.1/4.1-14 4.1-1 Scram Instrumentation and Logic Systems Functional Test-Minimum Functional Test Frequencies for Safety Instrumentation, Logic Systems, and Control Circuits 3.1/4.1-15 4.1-2 Scram Instrument Calibration-Minimum Calibration Frequencies for Reactor Protection Instrument Channels 3.1/4.1-17 3.2-1 Instrumentation that Initiates Primary Containment j
isolation Functions 3.2/4.2-15 3.2-2 Instrumentation that Initiates or Controls the Core and Contaimnent Cooling Systems 3.2/4.2-17 3.2-3 Instrumentation that Initiates Rod Block 3.2/4.2-19 3.2-4 Postaccident Monitoring Instrumentation Requirements 3.2/4.2-21 3.2-5 Radioactive Liquid Effluent Monitoring Instrumentation 3.2/4.2-24 3.2-6 Radioactive Gaseous Effluent Monitoring Instrumentation 3.2/4.2-25 4.2-1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks and Isolations 3.2/4.2-27 4.2-2 Postaccident Monitoring Instrumentation Surveillance Requirements 3.2/4.2-30 4.2-3 Radioactive Liquid Effluent Monitoring Instrumentation' Surveillance Requirements 3.2/4.2-32 4.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3.2/4.2-33 4.6-1 Inservice Inspection Requirements for Quad-Cities 3.6/4.6-26 4 6-2 Revised Withdrawal Schedule 3.6/4.6-35 4.6-3 Snubber Visual Inspection Criteria 3.6/4.6-36 l
3.7-1 Primary Containment Isolation 3.7/4.7-33 3.7.2 Primary Containment Leakage Test Penetrations 3.7/4.7-39 4.7-1 Temporarily Untested Pathways 3.7/4.7-40 4.8-1 Radioactive Gaseous Waste Sampling and Analysis Program 3.8/4.8-27 l
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Amendment No.149
QUAD-CITIES DPR-29 l.
Snubbers 1.
- 1. During Run, Startup/ Hot Standby, and Hot Each snubber shall be demonstrated Shutdown, and during Cold Shutdown and operable by the performance of the Refuel for snubbers located on systems following augmented inservice inspection
?
required operable during Cold Shutdown
Insoection Tvoes this requirement are those installed on nonsafety-related systems and then only if As used in this specification, " type of i
their failure or failure of the system on snubber" shall mean snubbers of the which they are installed would have no same design and manufacturer, adverse impact on any safety-related irrespective of capacity.
system.
2.
Visual Insoections Snubbers are categorized as
- 2. With one or more snubbers inoperable, on inaccessible or accessible during any system, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
reactor operation. Each of these categories (inaccessible and accessible) a.
Replace or restore the inoperable may be inspected independently l
snubber (s) to operable status, and according to the schedule determined by Table 4.6-3. The visual inspection b.
Perform an engineering evaluation per interval for each type of snubber shall Specification 4.6.l.7 on the attached be determined based upon the criteria component.
provided in Table 4.6-3'd.
Otherwise, declare the attached system 3.
Visual Insoection Acceotance Criteria inoperable and follow the appropriate ACTION statement for that system.
Visual inspections shall verify that:
(1) the snubber has no visible indications of damage or impaired operability, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the i
component and to the snubber t
anchorage are functional. Snubbers which appear inoperable as a result of i
a-The first inspection intervai determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before amendment (149),
)
3.6/4.6-12a Amendment No.149
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QUAD CITIES i
DPR-29 visual inspections shall be classified as unacceptable. 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 requirements of Specification 3.6.l.2 shall be met.
Snubbers originally classified as unacceptable may be reclassified as 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 generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined operable per Specification 4.6.l.6.
4.
Trsnsient Event insoection 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 or a visual inspection of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible systems and 6 months for inaccessible systems following this determination. 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) eveluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
3.6/4.6-13 Amendment No.149
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QUAD-CITIES DPR-29 5.
Functional Tests At least once per 18 months, a representative sample of snubbers shall be tested using one of the following sample plans for each type of snubber.
The sample plan shall be selected prior to the test period and cannot be changed 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 l
period shall be implemented:
l a.
At least 10% of the total of each f
type of snubber shall be functionally tested either in-place or in a bench test. For each snubber l
of a type that does not meet the functional test acceptance criteria of Specification 4.6.l.6, an additional 10% of that type of snubber shall be functionally tested I
until no more failures are found or until all snubbers of that type have been functionally tested; or b.
A representative sample of each type of snubber shall be functionally tested, in accordance with Figure 4.6-2. "C" is the total number of snubbers of a type l
found not meeting the acceptance i
requirements of Specification 4.6.l.6. The cumulative number of snubbers of a type tested is denoted by "N". At the end of each day's testing, the new values of "N" and "C" (previous day's I
total plus current day's increments) shall be plotted on Figure 4.6-2.
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l 3.6/4.6-14 Amendment No. 149
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!E _ _ _ ___- - _________-----_-_-----__----_----____------__ _ -- -------------_-- _ ___
i
t QUAD-CITIES DPR-29 If at any time the point plotted falls on or above the " Reject" line, all snubbers of that type shall be i
functionally tested. if at any time the point plotted falls on or below the " Accept" line, testing of snubbers of that type may be terminated. When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the
" Reject" region, or all the snubbers i
of that type have been tested.
Testing equipment failure during functional testing may invalidate that day's testing and allow that day's testing to resume anew at a later time, providing all snubbers testod with the failed equipment during the day of equipment failure are retested; or ~
c.
An initial representative sample of 55 snubbers of each type shall be functionally tested. For each
. snubber type which does not meet j
i the functional test acceptance criteria, another sample of at least one-half the size of the initial i
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 snubbers found which do not meet the functional test acceptance criteria. The results from this sample plan shall be plotted using an " Accept" line which follows the equation N = 55(1 + C/2). Each snubber point should be plotted as soon as the snubber is tested. If the point plotted falls on or below the 3.6/4.6-15 Amendment No.149
QUAD-CITIES DPR-29
" Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the
" Accept" line, testing must continue until the point falls on or below the " Accept" line or all the '
snubbers of that type have been tested.
The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and I
capacity of snubbers of each type.
Snubbers placed in the same location as snubbers which failed'the previous functional test shall be retested at the time of the next functional test but shall not be included in the sample plan, and failure of this functional test shall not be the sole cause for increasing the sample size under the sample plan if during testing, additional sampling is required due to failure of only one type of snubber, the functional testing results shall be reviewed at the time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
l 6.
Functional Test Acceptance Criteria j
i The snubber functional test shall verify that:
I a.
Activation (restraining action) is achieved within the specified range i
in both tension and compression; i
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3.6/4.6-15a Amendment No.149
QUAD-CITIES DPR-29 b.
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range (hydraulic snubbers, only);
i c.
For mechanical snubbers, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and i
d.
For snubbers specifically required l
not to displace under continuous load, the ability of the snubber to withstand load without displacement.
i Testing methods may be used to measure parameters indirectly or l
parameters other than those specified if those results can be correlated to the specified parameters through established methods.
7.
Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the j
functional test acceptance criteria to j
determine the cause for the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the operability of other snubbers irrespective of type which may be subject to the same failure mode.
For the 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 attached were adversely affected by the inoperability of the 3.6/4.6-15b Amendment No.149
QUAD-CITIES DPR-29 snubbers in order to ensure that the component remains capable of meeting the designed service.
l If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen-in-place, the cause l
will be evaluated and, if caused by manufacturer or design deficiency, all l
snubbers of the same type subject to I
the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in Specification 4.6.l.5 for snubbers not meeting the functional test acceptance criteria.
l 8.
Functional Testino cf Reoaired and l
Reolaced Snubbers l
Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or j
replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in tho unit. Mechanical snubbers shall 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 i
being installed in the unit.
l 9.
SnubbeLService Life Prooram The service life of all snubbers shall be monitored to ensure that the service life is not exceeded between surveillance l
inspections. The maximum expected service life for various seals, springs, and other critical parts shall be extended or shortened based on monitored test results and failure l
history. Critical parts shall be replaced so that the maximum servico life will l
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3.6/4.6-15c Amendment Nr l
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QUAD-CITIES i
DPR 29 not be exceeded during a period when the snubber is required to be operable.
l The parts replacements shall be i
documented and the documentation shall be retained in accordance with i
Specification 6.5.B.
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i 3.6/4.6-15d Amendment No.149 t j
i QUAD CITIES DPR-2g H.
Recirculation Pump Flow limitations The LPCI loop selection logic is described in the SAR, Section 6.2.4.2.5.
For some limited low probability accidents with the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection.
For these limited conditions, the core spray itself is adequate to prevent -
i fuel temperatures from exceeding allowable limits. However, to limit the probability even further, a procedural limitation has been placed on
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the allowable variation in speed between the recirculation pumps.
The licensee's analyses indicate that above 80% power the loop select logic could not be expected to function at a speed differential of 15%.
Below 80% power, the loop select logic would not be expected to function at a speed differential of 20%. This specification provides a margin of 5% in pump speed differential before a problem could arise.
If the reactor is operating on one pump, the loop select logic trips that pump before making the loop selection.
Analyses have been performed which support indefinite single loop operation provided the appropriate restrictions are implemented within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The MCPR Safety Limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used in the i
statistical analysis of the safety limit. The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, has also been increased by 0.01 to maintain the same margin to the safety limit as during Dual Loop operation.
The flow biased scram and rod block setpoints are reduced to account for uncertainties associated with backflow through the idle jet pumps when the operating recirculation pump is above 20-40% of rated speed. This assures that the flow biased trips and blocks occur at conservative neutron flux levels for a given core flow.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop. temperature shall be within 50 *F of each other prior to startup of an idle loop. The loop temperature must also be within 50 *F of the reactor pressure vessel steam space coolant temperature to prevent thermal shock to the recirculation pump and rectreulation nozzles. Since the coolant in the bottom of the vessel is at a lower tatsperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145 *F.
Additionally, asymmetric speed operation of recirculation pumps during idle loop startup induces levels of jet pump riser vibration that are higher than normal. The specific limitation of 45% of rated pump speed for the operating recirculation pump prior to the start of the idle recirculation pump ensures that the recirculation pump speed mismatch requirements presented in l
Specification 3.6.H.1 are maintained.
3.6/4.6-24 Amendment No.
149
1 QUAD-CITIES DPR-29 3.6/4.6.1 Enubbers
'l Mechanical and hydraulic snubbers are provided to ensure that the structuralintegrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic event or other event initiating dynamic loads. Snubbers are classified and grouped by design, manufacturer and accessibility. A list of individual snubbers with information of snubber location, classification or group, and system affected is maintained at the plant. The accessibility l
of each snubber is determined and documented for each snubber. The determination is 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 operation (e.g.,
temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to the systems. Therefore, the required inspection interval varies with the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval. A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visual inspection. Snubbers may be categorized, based
-l upon their accessibility during power operation, as accessible or inaccessible. These categories may be examined separately or jointly as determined and documented prior to the inspections. The categorization is used as the basis for determining the next inspection interval for that category.
If a review and evaluation can not justify continued operation with an unacceptable snubber, the snubber is declared inoperable and the applicable action taken. To determine the next surveillance interval, the unacceptable snubber may be reclassified as acceptable if it can be demonstrated that 1
I the snubber is operable in its as-found condition by the performance of a functional test. The next visual inspection interval may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval, depending on the number of unacceptable snubbers found in proportion to the size of the population or category for each type of snubber included in the previous inspection. The inspection interval may be as long as 48 months and the provisions of Specification 1.0.DD may be applied.
l 1
When a snubber is found to be inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure,in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
l To provide additional assurance of snubber functional reliability, a representative sample of the
)
installed snubbers will be functionally tested at 18 month intervals. This sample is identified using one of three methods:
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 4.6-2, or 3.6/4.6-25 Amendment No.149
. _. i QUAD-CITIES DPR-29 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
l Figure 4.6-2 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 l
granted by the NRC if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted are listed in the list of individual snubbers indicating the extent of the exemptions.
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 replace, spring replaced, in high radiation area, in high l
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 provide statistical bases for future consideration of snubber service life.
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3.6/4.6-25a Amendment No.149
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OUAD-CITIES DPR-29 i
Table 4.6-3 i
jiNUBBER VISUAL INSPECTION CRITERIA NUMBER OF UNACCEPTABLE SNUBBERS Population""
Column A ""9 Column B 'd""
Column C """
or Catecorv Extend Interval Reoeat interval Reduce Interval 1
0 0
1 80 0
0 2
l 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 21000 29 56 109 I
1 1
a The next visualinspection intervsl for a snubber population or category size shall be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon thair accessibility during power operation, as accessible or inaccessible. These categories may be examined j
separately or jointly. However, the decision must be made and documented before any inspection and shall be used as the basis upon which to determine the next inspection interval for that category, b
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.
j c
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, d
if the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
e 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, but not less than 31 days. However, if the number of unacceptable j
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 f actor that is one-third of the ratio of the dif ference 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.
I f
The provisions of Specification 1.0.DD are applicable for allinspection intervals up to and including 48 months.
3.6/4.6-36 Amendment No.149 ;
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QUAD-CITIES DPR-29 Fiaure 4.0-2 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TESTING l
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0 10 20 30 40 50 60 70 80 90 100 i
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N = Cumulative number of snubbers of a type tested C = Total number of snubbers of a type not meeting acceptance Amendment No.149
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t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20E50001
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. COMMONWEALTH EDISON COMPANY l
AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 145 License No. DPR-30
+
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 11, 1994, 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 1
Commission; C.
There 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; i
D.
The issuance of this 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
1
. 8.
Technical Soecifications 1
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
145, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
It should be implemented prior to the startup from 13th refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION
% N G, h,=
Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 13, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 145 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET N0. 50-265 l
1 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number ano contain marginal lines indicating the area of change.
REMOVE INSERT v
v 3.6/4.6-Sc 3.6/4.6-5c 3.6/4.6-5d 3.6/4.6-Se 3.6/4.6-5f 3.6/4.6-5g 3.6/4.6-5h 3.6/4.6-6 3.6/4.6-6 3.6/4.6-7 3.6/4.6-7 3.6/4.6-14 (Bases) 3.6/4.6-14 (Bases) 3.6/4.6-14a (Bases) 3.6/4.6-14a (Bases) 3.6/4.6-22 (Table 4.6-3)
Figure 4.6-2
QUAD CITIES DPR-30 TECHNICAL SPECIFICATIONS APPENDIX A LIST OF TABLES Number Title Page 3.1-1 Reactor Protection System (Scram) Instrumentation 1
Requirements-Refuel Mode 3.1/4.1-8 3.1-2 Reactor Protection System (Scram) Innrumentation Requirements-Startup/ Hot Standby Mode 3.1/4.1-9 3.1-3 Reactor Protection System (Scram) Instrumentation Requirements-Run Mode 3.1/4.1-10 3.1-4 Notes for Tables 3.1-1, 3.1-2, and 3.1-3 3.1/4.1-11 j
4.1-1 Scram Instrumentation and Logic Systems Functional Tests-Minimum Functional Test Frequencies for Safety
]
Instrumentation, Logic Systems, and Control Circuits 3.1/4.1-12 4.1-2 Scram Instrument Calibration-Minimum Calibration Frequencies for Reactor Protection Instrument Channels 3.1/4.1-14 3.2-1 Instrumentation that Initiates Primary Containment Isolation Functions 3.2/4.2-11 3.2-2 Instrumentation that Initiates or Controls the Core and Containment Cooling Systems 3.2/4.2-12 3.2-3 Instrumentation that Initiates Rod Block 3.2/4-2-14 3.2-4 Postaccident Monitoring Instrumentation Requirements 3.2/4.2-15 3.2-5 Radioactive Liquid Effluent Monitoring Instrumentation 3.2/4.2-15b 3.2-6 Radioactive Gaseous Effluent Monitoring Instrumentation 3.2/4.2-15e 4.2-1 Minimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks and Isolation 3.2/4.2-16 4.2-2 Postaccident Monitoring Instrumentation Surveillance Requirements 3.2/4.2-18 4.2-3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3.2/4.2-19 4.2-4 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3.2/4.2-20 4.6-1 Inservice Inspection Requirements for Quad-Cities 3.6/4.6-16 4.6-2 Revised Withdrawal Schedule 3.6/4.6-21 A i
4.6-3 Snubber Visual Inspection Criteria 3.6/4.6-22 1
3.7-1 Primary Containment Isolation 3.7/4.7-20 3.7-2 Primary Containment Leakage Test Penetrations 3.7/4.7-23 4.8-1 Radioactive Gaseous Waste Sampling and Analysis Program 3.8/4.8-20 v
Amendment No.145
4 QUAD-CITIES DPR-30 1.
Snubbers I.
- 1. During Run, Startup/ Hot Standby, and Hot Each snubber shall be demonstrated l
Shutdown, and during Cold Shutdown and operable by the performance of the Refuel for snubbers located on systems following augmented inservice inspection required operable during Cold Shutdown program.
and Refuel, all required snubbers shall be operable. The only snubbers excluded from 1.
Insoection Tvoes this requirement are those installed on nonsafety-related systems and then only if As used in this specification, " type of I
their failure or failure of the system on snubber" shall mean snubbers of the I
which they are installed would have no same design and manufacturer, j
adverse impact on any safety-related irrespective of capacity.
I system.
l 2.
Visual Insoections Snubbers are categorized as
- 2. With one or more snubbers inoperable, on inaccessible or accessible during l
any system, within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s:
reactor operation. Each of these categories (inaccessible and accessible) a.
Replace or restore the inoperable may be inspected independently snubber (s) to operable status, and according to the schedule determined by Table 4.6-3. The visual inspection b.
Perform an engineering evaluation per interval for each type of snubber shall Specification 4.6.l.7 on the attached be determined based upon the criteria component.
provided in Table 4.6-3*.
Otherwise, declare the attached system 3.
Visual Insoection Acceotance Criteria inoperable and follow the appropriate l
ACTION statement for that system.
Visual inspections shall verify that:
l (1) the snubber has no visible indications of damage or impaired operability, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional. Snubbers which appear inoperable as a result of a
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 (145).
3.6/4.6-5c Amendment No.145
QUAD-CITIES DPR-30 visual inspections shall be classified as unacceptable. 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 requirements of Specification 3.6.1.2 shall be met.
Snubbers originally classified as unacceptable may be reclassified as 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 generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and dete'rmined operable per Specification 4.6.l.6.
4.
Transient Event insoection 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 or a visual inspection of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible systems and 6 months for inaccessible systems following this determination.
b.
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 piston setting; or (3) stroking the mechanical snubber through its full range of travel.
I 3.6/4.6-5d Amendment No.145
QUAD-CITIES DPR-30 l
5.
Functional Tests -
At least once per 18 months, a representative sample of snubbers shall 4
be tested using one of the following i
sample p!ans for each type of snubber.
The sample plan shall be selected prior to the test period and cannot be changed during the test p?riod. 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:
a.
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 4.6.l.6, 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 b.
A representative sample of each type of snubber shall be functionally tested, in accordance with Figure 4.6-2. "C" is the total number of snubbers of a type found not meeting the acceptance requirements of Specification 4.6.l.6. The cumulative number of snubbers of a type tested is denoted by "N". 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 4.6-2.
3.6/4.6-Se Amendment No.145
[
QUAD-CITIES DPR-30 if at any time the point plotted falls on or above the " Reject"line, all snubbers of that type shall be functionally tested. If at any time the point plotted falls on or below the " Accept" line, testing of snubbers of that type may be terminated. When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region or the
" Reject" region, or all the snubbers of that type have been tested.
Testing equipment failure during functional testing may invalidate 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 the day of equipment failure are retested; or c.
An initial representative sample of 55 snubbers of each type shall be functionally tested. For each snubber type which does not meet the functional test acceptance criteria, another sample of at 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 f actor,1 + C/2, where."C" is the number of snubbers found which do not meet the functional test acceptance criteria. The results from this sample plan shall be plotted using an " Accept" line which follows the equation.
N = 55(1 + C/2). Each snubber point should be plotted as soon as the snubber is tested. If the point plotted falls on or below the i
r 3.6/4.6-5f Amendment No.145 t
QUAD-CITIES DPR-30
" Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the
" Accept" line, testing must continue until the point falls on or below the " Accept" line or all the snubbers of that type have been tested.
The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall ensure as far as practical that they are representative of the various configurations, operating environments, range of size, and I
capacity of snubbers of each type.
Snubbers placed in the same location as snubbers which failed-the previous j
functional test shall be retested at the i
time of the next functional test but shall not be included in the sample plan, and failure of this functional test shall not be the sole cause for increasing the sample size under the sample plan. If during testing, additional sampling is required due to failure of only one type of snubber, the functional testing results shall be reviewed at the time to determine if additional samples should be limited to the type of snubber which has failed the functional testing.
6.
Functional Test Acceptance Criteria The snubber functional test shall verify that:
a.
Activation (restraining action) is achieved within the specified range in both tension and compression; 3.6/4.6-5g Amendment No.145
i!
QUAD-CITIES j
DPR-30 b.
Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range (hydraulic '
snubbers, only):
c.
For mechanical snubbers, the force l
required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and d.
For snubbers specifically required not to displace under continuous I
load, the ability of the snubber to withstand load without displacement, Testing methods may be used to l'
measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.
7.
Functional Test Failure Analvsis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause for the failure. The results of this evaluation shall be used, if applicable,in selecting snubbers to l
be tested in an effort to determine the operability of other snubbers irrespective of type which may be 4
subject to the same failure mode.
For the 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 attached were adversely affected by the inoperability of the 3.6/4.6-Sh Amendment No.145
i QUAD CITIES DPR-30 i
snubbers in order to ensure that the component remains capable of meeting the designed service.
i If any snubber selected for functional testing either fails to activate or fails to move, i.e., frozen-in-place, the cause will be evaluated and,if caused by manufacturer or design deficiency, all i
snubbers of the same type subject to the same defect shall be functionally i
tested. This testing requirement shall be independent of the requirements stated in Specification 4.6.l.5 for snubbers not meeting the functional test acceptance criteria.
8.
Functional Testina of Repaired and j
Reolaced Snubbers Snubbers which fail the visual inspection or the functiorial test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall 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.
9.
Snubber Service Life Proaram The service life of all snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for various seals, springs, and other critical parts shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will 3.6/4.6-6 Amendment No.145
QUAD-CITIES DPR-30 not be exceeded during a period when j
the snubber is required to be operable.
l The parts replacements shall be documented and the documentation shall be retained in accordance with
]
Specification 6.5.B.
I i
i 3.6/4.6-7 Amendment No.145
i QUAD-CITIES DPR-30 i
3.6/4.6.1 Snubbers Mechanical and hydraulic snubbers are provided to ensure that the structuralintegrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic event or other event initiating dynamic loads. Snubbers are classified and grouped by design, manufacturer and accessibility. A list of individual snubbers with information of snubber location, classification or group, and system affected is maintained at the plant. The accessibility of each snubber is determined and documented for each snubber. The determination is 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 operation (e.g.,
temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to the systems. Therefore, the required inspection interval varies with the number of unacceptable snubbers found during the previous inspection, the total population or category size for each snubber type, and the previous inspection interval. A snubber is considered unacceptable if it fails to satisfy the acceptance criteria of the visualinspection. Snubbers may be categorized, based upon their accessibility during power operation, as accessible er inaccessible. These categories may be examined separately or jointly as determined and documented prior to the inspections. The categorization is used as the oasis for determining the next inspection interval for that category.
If a review and evaluation can not justify continued operation with an unacceptable snubber, the snubber is declared inoperable and the applicable action taken. To determine the next surveillance 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. The next visual inspection interval may be twice, the same, or reduced by as much as two-thirds of the previous inspection interval, depending on the number of unacceptable snubbers found in proportion to the size of the population or category for each type of snubber included in the previous inspection. The inspection interval may be as long as 48 months and the provisions of Specification 1.0.DD may be applied.
When a snubber is found to be inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure,in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
To provide additional assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested at 18 month intervals. This sample is identified using one of three methods:
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 4.6-2, or 3.6/4.6-14 Amendment No.145
s:
QUAD-CITIES l
DPR-30 l
i 3.
Functionally test a representative sample size and determine sample acceptance or rejection using the stated equation.
l t
Figure 4.6-2 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 NRC if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at
[
either the completion of their fabrication or at a subsequent date. Snubbers so exempted are listed in the list of individual snubbers indicating the extent of the exemptions.
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 replace, 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 provide statistical bases for future consideration of snubber service life.
I I
3.6/4.6-14a Amendment No. 145
i QUAD-CITIES DPR-30 Table 4.6-3 SNUBBER VISUAL INSPECTION CRITERIA i
I NUMBER OF UNACCEPTABLE SNUBBERS l
Population""W Column A """
Column B """
Column C "H" or Cateaorv Extend Interval Reoeat interval Reduce Interval 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 21000 29 56 109 s
The next visual inspection interval for a snubber population or category size shall be determined based upon the previous inspection interval 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 decision must be made and documented before any inspection and shall be used as the basis upon which to determine the next inspection interval for that category.
b 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.
c if the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval j
may be twice the previous interval, but not greater than 48 months, d
if the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
e 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, but not less than 31 days. 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 f actor that is one-third of the ratio 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.
f The provisions of Specification 1.0.DD are applicable for allinspection intervals up to and including 48 months.
3.6/4.6-22 Amendment No.145
j 1
QUAD-CITIES DPR-30 Fiaure 4.6-2 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TESTING 10 l
l 9
8 1
/
7
/
/
1 6
auct 0 5
- 'i*M V
C' 4
/
/
3 ustm g
1/
2 f
)of er 1
0 0
10 20 30 40 50 60 70 80 90 100 N
N = Cumulative number of snubbers of a type tested C = Total number of snubbers of a type not meeting acceptance Amendment No.145
-