|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F ML20154C0491998-09-28028 September 1998 Proposed Tech Specs Revising FSAR Separation Requirement of Six Inches Which Is Applied to Redundant Vital Cables, Internal Wiring of Redundant Vital Circuits & Associated Devices ML20154A3701998-09-28028 September 1998 Proposed Tech Specs Sections 3.3.2.1,3.4.6.2,3.4.8,3.6.2.1, 3.6.5.1,3.7.6.1 & 3.9.15,revising Info Re Revised MSLB Analyses & Revised Determinations of Radiological Consequences of MSLB & LOCA ML20151V5011998-09-0909 September 1998 Proposed Tech Spec Changing TS Definitions 1.24,1.27,1.31, 3.0.2,4.0.5,3.2.3,3.3.2.1,3.4.1.1,3.4.11 & Adding TS 3.0.6 B17385, Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified1998-08-12012 August 1998 Proposed Tech Specs 6.9.1.8b,updating List of Documents Describing Analytical Methods Specified B17341, Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval1998-08-0606 August 1998 Proposed Tech Specs Surveillance 4.4.5.3.a Re SG Tube Insp Interval ML20236Y0831998-08-0404 August 1998 Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves ML20236X2521998-07-30030 July 1998 Proposed Tech Specs Bases 3/4.9.1,3/4.1.1.3,3/4.7.1.6, 3/4.7.7,3/4.5.4 & 3/4.3.3.10,resolving Miscellaneous Condition Repts ML20236W0201998-07-30030 July 1998 Proposed Tech Specs Bases Section 3/4.6.1.1,clarifying Administrative Controls for RHR Isolation Valves When RHR Sys Is in Svc for Core Cooling ML20236T2681998-07-21021 July 1998 Proposed Tech Specs Re Reactor Protection & ESFs Trip Setpoints ML20236T5301998-07-17017 July 1998 Proposed Tech Specs Pages for TS Bases Section 3/4.4.9, Pressure/Temperature Limits ML20236T7331998-07-17017 July 1998 Proposed Tech Specs Modifying DG Testing Requirements ML20249A2811998-06-10010 June 1998 Proposed Tech Specs Re Post Accident Access to Vital Areas (Plar 3-98-6) ML20249A3121998-06-0606 June 1998 Proposed Tech Specs Re SLCRS Bypass Leakage (Plar 3-98-5) ML20249A2681998-06-0505 June 1998 Proposed Tech Specs Re Revised Steam Generator Tube Rupture Analysis (Plar 3-98-4) ML20248M2221998-06-0404 June 1998 Revised Tech Specs Pages,Changing TS Bases Section 3/4.7.1.5 to Reword Section Which Describes Limiting Temperature Case for Containment Analysis ML20247G6841998-05-14014 May 1998 Proposed Tech Specs,Modifying TSs 3.3.1.1 & 3.3.2.1 to Restrict Time Most Reactor Protection or Esfa Channels Can Be in Bypass Position to 48 Hours,From Indefinite Period of Time B17211, Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage1998-05-0707 May 1998 Proposed Tech Specs Re Refueling Water Storage Tank Back Leakage ML20247B9411998-05-0101 May 1998 TS Change Pages for TS Bases Section 3/4.5.4,modifying Wording Associated W/Refueling Water Storage Tank Minimum Boron Concentration ML20217D5941998-04-30030 April 1998 Proposed Tech Specs Re Change to Basis 3/4.6.4 Which Modifies Accuracy Range Associated W/Measured Std Cubic Feet Per Minute & Corrects Listed Component Number 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program 1999-09-07
[Table view] |
Text
n.
a 347 5 2/19/97 REACTOR c00LANT 5YSTDI 15 day g
j DPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant S each of the above limits by:ystem leakages shall be demonstrated to be within a.
Monitoring the containment atmosphere (gaseous or particulate) radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; b.
Monitoring the containment drain sump inventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; Measurement of the CONTROLLED LEAXAGE to the reactor coolant pump c.
seals when the Reactor Coolant System pressure is 2250 1 20 least once per 31 days with the modulating valve' fully open. psia at The MODE 3 or 4; provisions of Specification 4.0.4 are not applicable for entry into 1
d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and Monitoring the Reactor Head Flange Leakoff System at least once per e.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 Table 3.4-1 shall be demonstrated OPERABLE by verifying lea its limit:
At least once each REFUELING INTERVAL,
-a.
[
b.
Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous g months, Prior to returning the valve to service following maintenance, c.
repair or replacement work on the valve',
d.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual W
(c.3 4
e.
e.
...........................,,........,,,......,...... m,. m.
e y
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 cr 4.
h P
MILLSTONE UNIT 3 osaa 3/4 4-23 Amendment No. J99.133
0 Docket No. 50-423 B17764 i
Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification 1
Reactor Coolant System Operational Leakage (TSCR 3-29-98)
Retyped Pages May 1999 h i.m
...a
.n s
t Nucisar Rngulatory Commission B17764/ Attachment 2/Page 1 RETYPE OF PROPOSED REVISION Refer to the attached retype of the proposed revision to the Technical Specifications (TS). The attached retype reflects the incorporation of the proposed changes to the TS.
Pending Technical Specification revisions are not reflected in the enclosed retype. The enclosed retype should be checked for continuity with recently issued TS prior to issuance.
l
-REhCTORCOOLANTSYSTEN OPERATIONAL LEAKAGE SURVEILLANCE REQUIRENENTS 4.4.6.2.1 Reactor Coolant System leakages shall be demonstrated to be within f each of the above limits by:
a.
' Monitoring the containment atmosphere (gaseous or particulate) radioactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; b.
Monitoring the containment drain sump inventory and discharge at I
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump c.
seals when the Reactor Coolant System pressure is 2250 i 20 least once per 31 days with the modulating valve fully open. psia at The provisions.of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d.
Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and Monitoring the Reactor Head Flange Leakoff System at least once per e.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:
At least once each REFUELING INTERVAL, a..
b.
Prior to entering N0DE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, Prior to returning the valve to service following maintenance, c.
repair or replacement work on the valve, d.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' following valve actuation due to automatic or manual action or flow through the valve, and When tested pursuant to Specification 4.0.5.
l e..
The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.
NILLSTONE - UNIT 3-3/4 4-23 Amendment No. 199, J77, i
os44
Docket No. 50-423 B17764 i
Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specification Reactor Coolant System Operational Leakage (TSCR 3-29-98)
Background and Safety Summary i
i May 1999
i Nuclear Rtgul: tory Commission B17764/ Attachment 3/Page 1 Backaround in accordance with the requirements of 10CFR50.55a(f)(4)(ii) inservice Testing (IST) programs are required to be updated every 10 years to the edition of the ASME Code endorsed by the NRC 12 months prior to the start of the next 120 month interval. The MP-3 IST Program second 10 year interval began in February 1998. In this regard the MP-3 program is compliant with the 1989 edition of the Code. During a review of the TS a discrepancy between the revised IST program requirements and Technical Specification 4.4.6.2.2.e was self identified. TS section 4.4.6.2.2.e references ASME Code paragraph IWV 3427(b) which is included in the 1983 Edition of the Code and was employed during the first ten year interval. The provisions of IWV 3427(b) requires trending for 6 inch and larger valves and increased frequency of valve leakage testing based upon increasing leakage trends. However this requirement was eliminated from the Code as it was not deemed to provide a worthwhile benefit based upon industry i
experience. As such the requirements of IWV 3427(b) were not carried forward and included in the 1989 Edition of the Code.
l i
The Technical Specifications need to be revised to align the test requirements with the current IST Program requirements and industry practices. With respect to the above reference to IWV 3427(b) as presented in TS 4.6.6.2.2.e is deleted. Surveillance
)
requirements for valve leakage tests will be accomplished pursuant to the provisions of TS 4.0.5 as presented in this PTSCR. As such this TS is revised to align with test requirements as presented in the current MP-3 IST program.
Safety Summary This PTSCR revises TS section 4.4.6.2.2.e such that reference to ASME Code paragraph IWV-3472(b) which pertains to frequency of leakage rate testing for valves 6 inches nominal pipe size and larger is deleted. TS 4.4.6.2.2.e is revised to indicate that the surveillance interval and frequency of surveillance leakage rate testing for these valves will be performed pursuant to the requirements of TS 4.0.5 and the MP-3 IST program.
The elimination of the IWV requirement and specifying that testing be performed in accordance with the IST Program results in TS which are more consistent with the testing requirements specified in Westinghouse Owr.ers Group (WOG) Standard Technical Specification (STS) for Pressure isolation Valves (PlVs). This PTSCR change will not affect the ability of a PlV to perform its required Reactor Coolant System (RCS) pressure isolation safety function of limiting RCS leakage to prevent overpressure failure of attached low pressure systems.
4 Nucl:ar R gulatory Commission B17764/ Attachment 3/Page 2 -
- This proposed TS change does not alter or affect the design, operation, maintenance or surveillance associated with MP-3 Structures, Systems, and Components in a detrimental manner during normal or accident operations.
This proposed change is considered safe because it will not result in the plant being operated in an unsafe condition, decrease available safety margins, operate outside of design bases parameters, nor adversely impact the consequences of an accident. It will cause no increase in risk to the public health or safety. It does not increase either the probability of event occurrence, the probability of human errors mitigating the event, the probability of the failure of mitigating equipment, nor does it introduce any new accidents or equipment malfunctions.
The proposed TS changes are considered safe and do not represent an Unreviewed Safety Question.
l
)
5 Docket No. 50-423 B17764 Millstone Nuclear Power Station, Unit No. 3 Reactor Coolant System Operational Leakage (TSCR 3-29-98)
Significant Hazards Consideration and Environmental Considerations May 1999
Nucirr Regulatory Commission B17764/ Attachment 4/Page 1 Sianificant Hazards Consideration Northeast Nuclear Energy Company (NNECO) has reviewed the proposed revision in accordance with 10 CFR 50.92 and has concluded that the revision does not involve any Significant Hazards Considerations (SHC). The basis for this conclusion is that the three criteria of 10 CFR 50.92(c) are not satisfied.
The proposed Technical Specification revision does not involve a SHC because the revision would not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change revises Technical Specification surveillance requirement 4.4.6.2.2.e to eliminate reference to ASME Code paragraph IWV-3427(b) and state instead to perform testing pursuant to TS 4.0.5.
Compliance with IWV-3427(b) imposes trending requirements and tracking of increased frequency test i
requirements on Reactor Coolant System PlVs 6 inches or greater nominal size.
The latest endorsed Edition of ASME Section XI (1989 Edition) requires the use of ASME/ ANSI OM-1987 including the OMa-1988 Addenda. However there is no similar paragraph in the current ASME/ ANSI OM Code with requirements such as those contained in IWV 3427(b). The IWV-3427(b) requirements were eliminated when transferred from the ASME B&PV Code Section IWV, to ASME/ ANSI Code OM-1987 (OM-10).
The test conditions for PlV leakage testing are unchanged and represent analyzed configurations. This change eliminates an unnecessary test requirement and incorporates Westinghouse Owner's Group (WOG)
Standard Technical Specifications (STS) frequency requirements which are deemed to "..substantially reduce the probability of an intersystem LOCA." This change in testing frequency requirements does not affect the accident mitigation capabilities of the RCS PlVs.
This change is bounded by existing accident analysis.
Therefore, it is concluded that, with no effect on accident mitigation, the proposed revision does not involve a significant Mcrease in the probability or consequences of an accident previously evaluated F 3e to the public is unchanged).
2.
Create.the possibility of a new or different kind of accident from any accident previously evaluated.
Eliminating the IWV-3427(b) trending for 6 inch and larger valves (and the accompanying increased frequency testing requirement) will not effectively change actual testing frequencies since the frequencies are eclipsed by the remaining Technical Specification requirements. Specifying testing in accordance with the IST Program makes the Technical Specifications more consistent with testing requirements specified in Westinghouse Owners Group STS for PlVs. This change
Nucl:nr Regulatory Commission B17764%ttachment 4\\Page 2 will not affect the ability of a PlV to perform its required RCS pressure isolation safety function of limiting RCS leahage to prevent overpressure failure of attached low pressure systems.
The frequency of testing or the testing itself are not initiating events to postu tod accidents. Therefore, no different accidents than previously evaluated are created by this change.
Thus, the proposed revision does not create the possibility of a new or different kind of accident from any previously evaluated.
3.
Involve a significant reduction in the margin of safety.
There is no impact on the Margin of Safety as defined in the Basis of any Technical Specification. Periodic surveillances provide continued assurance in the capability of safety related equipment to perform its design safety (accident mitigating) function. Per the Westinghouse Owners Group STS, periodic leakage testing of Reactor Coolant System PlV's substantially reduces the probability of intersystem LOCAs. This change brings the required level of surveillance testing into closer compliance with the STS.
The proposed Technical Specification change does not affect the four " Defense-in-Depth" protecbve boundaries of fuel matrix and fuel cladding, RCS pressure boundary, Containment and site radiological limits. This TS change presents no reduction in the margin of safety pertaining to the fuel, RCS or Containment. The lack of an effect on the probability and consequences of accident occurrence, as discussed in the previous paragraphs, ensures a high degree of confidence with respect to protecting the public health and safety.
1 In conclusion, based on the information provided, it is determined that the proposed 1
revision does not involve a SHC.
Environmental Coasiderations NNECO has reviewed the poposed license amendment against the ciiteria of 10CFR51.22 for environmental considerations. The proposed revision does not involve a SHC, does not signi'icantly increase the type and amounts of effluents that may be released offsite, does not significantly increase individual or cumulative occupational rari!ation exposure. Based on the foregoing, NNECO concludes that the proposed revision meets the criteria delineated in 10CFR51.22(c)(9) for categorical exclusion from the requirements for environmental review.