Application for Amend to License NPF-3,deleting Tech Spec 4.02b Surveillance Requirement Interval Extension Limit to Provide Flexibility for Scheduling Surveillances & Consideration of Plant Operating ConditionsML20246K267 |
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Davis Besse |
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Issue date: |
08/23/1989 |
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From: |
Shelton D TOLEDO EDISON CO. |
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To: |
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Shared Package |
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ML20246K252 |
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References |
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1702, NUDOCS 8909050421 |
Download: ML20246K267 (5) |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - 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Depressurization & Cooling Sys - Containment Spray Sys ML20117K1871996-05-28028 May 1996 Application for Amend to License NPF-3,revising TS 3/4.3.1.1 RPS Instrumentation & TS 3/4.3.2.2 - Anticipatory RTS Instrumentation to Increase Trip Device Test Interval ML20107L3541996-04-18018 April 1996 Application for Amend to License NPF-3,requesting NRC Review & Approval to Use Alternate Electrical Lineup.Station Blackout DG as Standby Emergency Power Source to Supply Loads Normally Supplied by EDG 1,while Being Reworked ML20101M1601996-03-29029 March 1996 Application for Amend to License NPF-3,App A,Re Surveillance Requirements for Charcoal Filter Lab Testing to Revise Testing Methodology Used to Determine Operability of Charcoal Filters in ESF Air Handling Units ML20101C6911996-03-0606 March 1996 Application for Amend to License NPF-3,revising TS 3/4.5.2 to Allow Deferment of SR 4.5.2.b for ECCS Flowpath Containing HPI 1-2 Pump Until 10th Refueling Outage, Scheduled to Begin 960408 ML20100E0051996-02-0505 February 1996 LAR 93-0003 to License NPF-3,revising Table 3.3-3 of TS 3/4.3.2.1 Re Safety Features Actuation Sys Instrumentation to More Accurately Reflect Design & Actuation Logic of Plant Sequencers & Undervoltage Relays ML20095F5861995-12-12012 December 1995 Application for Amend to License NPF-3,revising TSs Re Containment Sys ML20098C5131995-10-0202 October 1995 Application for Amend to License NPF-3,revising TS Section 5.0,design Features & Adopting Improved STS for B&W Plants Format & Content ML20098C1071995-09-29029 September 1995 Application for Amend to License NPF-3,modifying TS 3.4.3 & Associated Bases for Pressurizer Code Safety Valve Lift Setpoint Tolerances ML20098C3931995-09-29029 September 1995 Application for Amend to License NPF-3,revising Tech Spec 3/4.1.2.8, Reactivity Control Sys - Borated Water Sources - Shutdown, Tech Spec 3/4.1.2.9, Reactivity Control Sys - Operating & TS 3/4.5.1, ECCS - Core Flooding Tanks 1999-09-07
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20216E6051999-09-0707 September 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20210H0631999-07-28028 July 1999 Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, by Allowing Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G4131999-07-27027 July 1999 Application for Amend to License NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G8831999-07-26026 July 1999 Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrumentation - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5251999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G4631999-07-26026 July 1999 Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumention & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20212H9901999-06-22022 June 1999 Amend 233 to License NPF-3,relocating TS Surveillance Requirement from TS 3/4.6.5.1, Shield Building - Emergency Ventilation Sys to TS Section 3/4.6.5.2, Shield Building Integrity ML20195F9121999-06-10010 June 1999 Application for Amend to License NPF-3,changing TS 3/4.6.4.4 Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20207G6591999-06-0808 June 1999 Amend 232 to License NPF-3,revising TSs in Response to 990309 Application.Changes Increase Inservice Insp Interval & Reduce Scope of Volumetric & Surface Examinations for Reactor Coolant Pump Flywheels ML20207E7861999-05-21021 May 1999 Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capability ML20206U7301999-05-19019 May 1999 Amend 231 to License NPF-3,revising Administrative Requirements Re TS 6.5.1.6,TS 6.8.4.d,TS 6.10,TS 6.11, TS 6.12 & TS 6.15 ML20205E4961999-03-19019 March 1999 Application for Amend to License NPF-3,requesting Withdrawal of Proposed New Action B to TS 3.6.5.2,previously Submitted in 981027 Application ML20204F1691999-03-0909 March 1999 Application for Amend to License NPF-3,adopting Changes in Frequency & Scope of Volumetric Exams Justified by W TR WCAP-14535A ML20206U2381999-02-0909 February 1999 Amend 229 to License NPF-3,revising TS 3/4.8.2.3 & Associated Bases & SRs for Battery Testing ML20196F3791998-11-30030 November 1998 Supplemental Application for Amend to License NPF-3, Proposing Changes to License Conditions 2.C(6) & 2.E by Transferring Operating Authority for DBNPS from Toed & Centerior Svc Co to Firstenergy Nuclear Operating Co ML20155E3181998-10-28028 October 1998 Application for Amend to License NPF-3,revising Various Sections of TS 6.0, Administrative Controls, Including Relocation of Contents of 6.11 to Plant Ufsar,Per NUREG-1430,Rev 1 ML20155D8481998-10-27027 October 1998 Application for Amend to License NPF-3,revising Existing TS SRs 4.8.2.3.2.d,4.8.2.3.2.e,4.8.2.3.2.f & Table 4.8-1 Re Testing of 125 Volt DC Station Batteries & Applicable TS Bases ML20155D7731998-10-27027 October 1998 Application for Amend to License NPF-3,relocating Existing TS SR 4.6.5.1.d.4 Re Evs Negative Pressure Testing to TS 3/4.6.5.2,deleting TS Definition 1.24 & Making Related Changes Associated with Deletion of Subject Definition ML20155E0701998-10-27027 October 1998 Application for Amend to License NPF-3,revising TSs 3/4.3.1.1 Re RPS Instrumentation & 3/4.3.2.3 Re ARTS Instrumentation by Providing Potential Reduction in Spurious Trip Rate to Provide Cost Savings in Excess of $50,000 ML20151W2851998-09-0808 September 1998 Application for Amend to License NPF-3,revising TS Section 3/4.7.6, Plant Systems - CREVS & Associated Bases ML20151W2811998-09-0808 September 1998 Application for Amend to License NPF-3,permitting Use of Framatome Cogema Fuels M5 Advanced Alloy Fuel Rod Cladding & Fuel Assembly Spacer Grids ML20236M9321998-07-0707 July 1998 Amend 225 to License NPF-3,relocating TS Tables of Response Time Limits to Davis-Besse Technical Requirements Manual ML20236K4231998-06-30030 June 1998 Amend 224 to License NPF-03,revises TS Section 1.0, Definitions, to Clarify Meaning of Core Alteration, Relocates TS Section 3/4.9.5 & Associated Bases to Technical Requirements Manual ML20236G6461998-06-29029 June 1998 Application for Amend to License NPF-3,transferring Operating Authority for DBNPS from TE & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Marked Up License,Safety & Environ Assessments Included ML20236R2301998-06-29029 June 1998 Resubmitted Application for Amend to License NPF-3, Transferring Operating Authority for DBNPS from Teco & Centerior Svc Co to New Operating Company Called Firstenergy Nuclear Operating Co.Safety Assessment & EA Included ML20249A7511998-06-11011 June 1998 Amend 223 to License NPF-3,revising TS Section 3/4.6.1.3 & Associated Bases ML20249A7611998-06-11011 June 1998 Amend 222 to License NPF-3,revising TS Section 3/4.2 ML20217P8671998-04-24024 April 1998 Application for Amend to License NPF-3,modifying Existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2 & Associated Bases by Relocating Tables of Response Time Limits from TS to Plant USAR Technical Requirements Manual ML20217P8251998-04-24024 April 1998 Application for Amend to License NPF-3,clarifying Discussion of Margin Between RPS High Pressure Trip Setpoint & Lift Setting for Pressurizer Code Safety Valves ML20216B8291998-04-14014 April 1998 Amend 220 to License NPF-3,revising TS 3/4.4.5,TS 3/4.4.6.2 & Associated Bases to Allow Use of Repair Roll SG Tube Repair Process ML20203L0861998-02-26026 February 1998 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Amend 218 to License NPF-3,extending SR Intervals from 18 to 24 Months Based on Results of Plant Instrument Drift Study ML20203C1341997-12-0202 December 1997 Amend 217 to License NPF-3,revising Surveillance Interval from 18 Months to Each Refueling Interval for TS 3/4.5.2, TS 3/4.6.5.1,TS 3/4.7.6.1,TS 3/4.7.7.2,TS 3/4.9.12 & TS Bases 3/4.7.7 ML20217R2801997-08-26026 August 1997 Application for Amend to License NPF-3,clarifying LCO 3.6.1.3.a & Revising Surveillance Requirement 4.6.1.3.c ML20217R2831997-08-26026 August 1997 Application for Amend to License NPF-3,modifying TS 3.2.5 Action Statement to Require Power Reduction to Less than 5% of Rated Thermal Power within Four Hrs If RCS Flow Rate Is Less than Specified Limit for Greater than Two Hrs ML20217G5931997-07-29029 July 1997 Suppl 950929 to Application for Amend to License NPF-3, Change TS 3/4.4.3 Re Safety Valves & Pilot Operated Relief valve-operating & Associated Bases 3/4.4.2 & 3/4.4.3 ML20141F1051997-06-24024 June 1997 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Procedural Control Requirement Added to TS That Will Ensure Monthly Review of Overtime for Personnel Who Perform Safety Related Functions 1999-09-07
[Table view] |
Text
._
. Dockat Numb:r 50-346 Licensa Nunb r NPF-3
- S:ric1 Number 1702 Enclosure Page 1 APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NUMBER NPF-3 DAVIS-BESSE NUCLEAR POVER STATION UNIT NUMBER 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit Number 1 Facility Operating License Number NPF-3.
Also included are the Technical Description and Significant Hazards Consideration.
The proposed changes (submitted under cover letter Serial Letter 1702) concern:
Section 3/4.0, Limiting Condition for Operations and Surveillance Requirements
- Applicability, Surveillance Requirement 4.0.2.
For: D. C. Shelton Vice President Nuclear By:
T. J.
er, Technical Services Director 292
$8 Sworn and subscribed before me this 23rd day of August, 1989.
hs$
nu 4Q Yath Y L
o m
Notary Pu6lic, State of Ohio oct
$fa EVELYNL DRESS NOTARY PU3' C, STATE OF 040 J
MyComWr.r,a : AV 2,134
. Dockat Nurbar 50-346-Liernse'Numbtr NPF-3:
~
-Serial Number'1702 Enclosure.
Page-2 The following information is provided to support. issuance of the requested changes to the Davis-Besse Nuclear' Power Station, Unit Number 1 Operating License Number NPF-3, Appendix A, Technical Specification, Section 3/4.0.
A.
Time Required to Implement: This change is to be implemented by 1 November. 13, 1989.
'B.
Reason for Change (License Amendment Request Number 88-0004):
Surveillance Requirement 4.0.2 includes a provision that allows-surveillance intervals to-be extended by 25 percent of the specified time interval..This provides flexibility for. scheduling the performance of surveillance and to permit consideration of plant operating conditions that may not be suitable for conducting'of a surveillance at its specified time interval.
Such conditions include transient plant operation or safety, systems that may be out-of-service due to maintenance or other ongoing surveillance activities.
Specification 4.0.2 further limits the 25 percent allowance for extending surveillance intervals by' requiring-that the combined time interval for any three consecutive surveillance not exceed 3.25 times the specified surveillance interval. This request proposes the removal of the 3.25 limit required by SR 4.0.2b.
C.
Technical
Description:
See attached Technical Description (Attachment 1).
D.
Significant Hazards Consideration:
See attached Significant Hazards Consideration (Attachment 2).
l l
l 1
.~ Docket Number 50-346 Licpnse Number NPF-3 Serial Number 1702
' Attachment 1 Page 1 TECHNICAL DESCRIPTION Description of Proposed Technical Specification Change The purpose of'this technical description is to review a proposed change to the Davis-Besse Nuclear Power Station (DBNPS) Technical Specifications (TS) 3/4.0 (Limiting conditions for Operations and Surveillance Requirements -
Applicability), Surveillance Requirement (SR) 4.0.2. SR 4.0.2 includes a provision that allows surveillance intervals to be extended by 25 percent of the specified time interval. This provides flexibility for scheduling the
. performance of-surveillance and to permit consideration of plant operating conditions that may not be suitable for conducting of a surveillance at its specified time interval.
Such conditions include transient plant operation or safety systems that may be out-of-service due to maintenance or other ongoing surveillance activities.
Specification 4.0.2 further limits the 25 percent allowance for extending surveillance intervals by requiring that the combined time interval for any three consecutive surveillance not exceed 3.25 times the specified surveillance interval. This request proposes the removal of the 3.25. limit required by SR 4.0.2b. This request is similar to the License Amendments issued by the NRC on July 19, 1989, that deleted SR 4.0.2b from the Operating Licenses Technical Specifications for LaSalle County Station, Units 1 and 2.
Systems Affected No hardware changes vould be required for implementation of this proposed change.
Effects on Safety Many surveillance have a specified surveillance interval of 18 months.
Generally, an 18-month surveillance interval is intended to allow the surveillance.to be performed when the unit i; shut down during a refueling outage. Therefore, the actual time interval for the perfornence of these surveillance is dependent on the length of a fuel cycle, but it cannot exceed 18 months plus the 25 percent allowance. The safety benefit of performing these surveillance during a plant shutdown is that systems do not have to be removed from service at a time that they are required to be operable. This minimizes the amount of time which systems are unavailable during power operation due to surveillance requirements, thereby minimizing the impact on safety.
In a few instances, the TS specifically require some surveillance to be performed during a plant shutdown. When a limit is reached on extending an 18-month interval, a forced plant shutdown to perform these surveillance is generally the only alternative short of a license amendment that defers the performance of these surveillance until the end of the fuel cycle.
Usually,thIlengthofafuelcyclewouldnotexceed18monthsbymorethan the 25 percent allowance, i.e., 4-1/2 months. A more common situation has been to encounter the 3.25 limit on the combined time interval for three consecutive surveillance intervals. The NRC Staff has routinely approved one-time amendment requests to vaive the performance of 18-month surveillance until the end of the fuel cycle when they wou?d exceed the 3.25 limitation on consecutive surveillance yet vould not exceed the 25 percent allowance for extending the ?8-senth surveillance interval. A forced shutdown to perform m
. Docket Number 50-346-
~.- license Number NPF-3
' Serial Number 1702 Page 2 these surveillance is not justified from a risk standpoint to avoid exceeding the 3.25 limit when extending these surveillance is within the 25 percent allowance. Because the 18-month surveillance are generally performed during a refueling outage when the plant is in a desirable condition for conducting
.these surveillance, the risk of the alternative to perform some of these
' surveillance during plant operation is greater than the impact on safety of s
exceeding'the 3.25 limit and using the 25 percent allowance to extend these surveillance. Based on routine safety system instrumentation channel functional testing which adjusts any out of tolerance conditions (except for sensors), instrument drift, due to increased period between calibrations, will not be a concern.
In addition to its application to refueling outage surveillance, the use of the 25 percent allowance for extending surveillance intervals can have a safety benefit when it is used during plant operation. When plant conditions are not suitable for the conduct of surveillance due to safety systems being out-of-service for maintenance or due to other ongoing surveillance activities, safety may be enhanced by the use of the allowance that permits a surveillance interval to be extended.
In such cases, the safety benefit of extending a surveillance interval up to 25 percent would exceed the risk reduction derived by conforming to the 3.25 limitation.
Furthermore, there is a large administrative and logistical burden on licensees that is associated with tracking the use of and exceptions to the 25 percent allowance for prior surveillance intervals >to ensure compliance with the 3.25 limit. This results in a diversion of resources and attention from more safety significant activities.
Based on the above discussion, it is concluded that the removal of the 3.25 limit for all surveillance is justified. In addition, the Bases of this specification is proposed to be updated to reflect this change and noted that it is not the intent of the allowance for extending surveillance intervals-that-it be used as a convenience to repeatedly schedule the performance of surveillance at the allovable extension limit.
Unreviewed Safety Questions / Evaluation The proposed changes vould not increase the probability of occurrence of an accident previously evaluated in the USAR because the accident conditions and assumptions are not affected since no hardware changes are being made nor is testing being degraded.
Surveillance intervals vill continue to be constrained by the maximum 25 percent interval extension criterion of TS 4.0.2a.
The proposed changes vould not increase the consequences of an accident previously evaluated in the USAR because the accident conditions and j
assumptions are not affected since no hardware changes are being made.
The proposed changes vould not increase the probability of a malfunction of equipment important to safety previously evaluated in the USAR because the changes do not involve a test or experiment and no station equipment is being modified. The proposed changes will not prevent any system from functioning as assumed in the USAR. Also, surveillance intervals vill centinue to be constrained by the maximum 25 percent interval extension criterion of TS 4.0.2a.
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. Docket Number 50-346 License Number NPF-3 Serial Number 1702 l
Page 3 The proposed changes vould not increase the consequences of a malfunction of equipment important to safety previously evaluated in the USAR because these proposed changes do not involve a modification to equipment or change the operation of a system. The proposed changes vill not prevent any system from functioning as assumed in the USAR.
The proposed changes vould not create the possibility for an accident of a different type than any evaluated previously in the USAR because the proposed changes do not add or modify any existing equipment.
Surveillance intervals vill continue to be constrained by the maximum 25 percent interval extension criterion of TS 4.0.2a.
The proposed changes would not create the possibility for a malfunction of equipment important to safety of a different type than any evaluated previously in the USAR because the changes do not involve a test or experiment and no station equipment is being modified.
The proposed changes vould not reduce the margin of safety as defined in the basis for any Technical Specification since surveillance intervals vill continue to be constrained by the maximum 25 percent interval extension criterion of TS 4.0.2a.
Conclusion Based on the above, it is concluded that the proposed Technical Specification and Bases changes do not constitute an unreviewed safety question.