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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212A9081997-10-16016 October 1997
Proposed Tech Specs 3.7.9 Re Fuel Storage Pool Makeup Water Sources
ML20211M9021997-08-31031 August 1997
Proposed Tech Specs 3.7.2 Re MSIVs
ML20216C2581997-08-31031 August 1997
Proposed Tech Specs 3.4.10 Re RCS Leakage Detection Instrumentation
ML20202B4411997-08-31031 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Changes to Reflect Ssar Chapter 15 Analyses Setpoints
ML20198S8741997-08-31031 August 1997
Proposed Tech Specs,Incorporating NRC Comments Resolved During 971027 Telcon
ML20216D2331997-08-29029 August 1997
Proposed Tech Specs,Providing Draft RCS PIV Integrity TS
ML20216D2511997-08-28028 August 1997
Proposed Tech Specs,Modifying SR 3.6.9.4 & SR 3.6.9.2, Consistent W/Nrc Example Provided in Question 68 & Consistent w/NUREG-1432
ML20198G5951997-08-27027 August 1997
Proposed Tech Specs Re Response to NRC Reactor Sys Branch RAI Re AP600 TS
ML20198G5641997-08-27027 August 1997
Proposed Tech Specs Pages 5.0-15,5.0-21 & IV to Reporting Requirements 5.6.1 to Be Incorporated in Rev 7 of AP600 TS to Be Transmitted to NRC on 970902
ML20210P2921997-08-19019 August 1997
Proposed Tech Specs,Reflecting Responses to Comments on AP600 TS Containment Sys
ML20210P4181997-08-19019 August 1997
Proposed Tech Specs 3.8.1 & 3.8.5,documenting Changes Agreed Upon W/Nrc Re Electrical Power Sys
ML20210Q0581997-08-19019 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & Engineered Safety Features Actuation
ML20140C4571997-06-0606 June 1997
Proposed Tech Specs Providing Explanation for AP600 TS Completion Times & Surveillance Frequencies Which Are Not Identical to Standardized TS Completion Times & Surveillance Frequencies
ML20141C6961997-05-0909 May 1997
Proposed Tech Specs LCO 3.0.2 & 3.0.3,reflecting Compliance W/Nrc Staff Position of Ltr
ML20137C6781997-03-19019 March 1997
Proposed Tech Specs Rev Re LCO 3.0.3,Key Licensing Issue 19 Deleting Exemption for Entry
ML20141B1351996-08-31031 August 1996
Proposed Tech Specs Re Advance Markup of AP600
ML20141K2571996-08-31031 August 1996
Proposed Tech Specs 3.7.6 Re Main Room Habitability Sys
ML20111B0501996-05-0101 May 1996
Proposed Tech Specs 5.1,5.2 & 5.3
1997-08-31
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20153G9561998-09-25025 September 1998
Nonproprietary Figure 1-3 of PCS-T2R-050, Large-Scale Test Data Evaluation
ML20236F6911998-05-29029 May 1998
Rev 6 to AP600 Emergency Response Guidelines, Including Guidelines SDG-1,SDG-2,SDG-3 & Change Pages for Background Documents AE-1,SDF-0.1,SDG-1,SDG-2 & SDG-3
ML20198S7471997-10-31031 October 1997
Rev 5 to AP600 Emergency Response Guidelines
ML20212A9081997-10-16016 October 1997
Proposed Tech Specs 3.7.9 Re Fuel Storage Pool Makeup Water Sources
ML20198S8741997-08-31031 August 1997
Proposed Tech Specs,Incorporating NRC Comments Resolved During 971027 Telcon
ML20202B4411997-08-31031 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Changes to Reflect Ssar Chapter 15 Analyses Setpoints
ML20216C2581997-08-31031 August 1997
Proposed Tech Specs 3.4.10 Re RCS Leakage Detection Instrumentation
ML20211M9021997-08-31031 August 1997
Proposed Tech Specs 3.7.2 Re MSIVs
ML20216D2331997-08-29029 August 1997
Proposed Tech Specs,Providing Draft RCS PIV Integrity TS
ML20216D2511997-08-28028 August 1997
Proposed Tech Specs,Modifying SR 3.6.9.4 & SR 3.6.9.2, Consistent W/Nrc Example Provided in Question 68 & Consistent w/NUREG-1432
ML20198G5641997-08-27027 August 1997
Proposed Tech Specs Pages 5.0-15,5.0-21 & IV to Reporting Requirements 5.6.1 to Be Incorporated in Rev 7 of AP600 TS to Be Transmitted to NRC on 970902
ML20198G5951997-08-27027 August 1997
Proposed Tech Specs Re Response to NRC Reactor Sys Branch RAI Re AP600 TS
ML20210P2921997-08-19019 August 1997
Proposed Tech Specs,Reflecting Responses to Comments on AP600 TS Containment Sys
ML20210P4181997-08-19019 August 1997
Proposed Tech Specs 3.8.1 & 3.8.5,documenting Changes Agreed Upon W/Nrc Re Electrical Power Sys
ML20210Q0581997-08-19019 August 1997
Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & Engineered Safety Features Actuation
ML20149H5111997-07-0101 July 1997
Rev 4 to GW-GJR-100, AP600 Emergency Response Guidelines
ML20140C4571997-06-0606 June 1997
Proposed Tech Specs Providing Explanation for AP600 TS Completion Times & Surveillance Frequencies Which Are Not Identical to Standardized TS Completion Times & Surveillance Frequencies
ML20141B6551997-05-31031 May 1997
to AP600 Emergency Response Guidelines
ML20141H1501997-05-16016 May 1997
Rev 3 to DE-AC03-90SF18495, Simplified Passive Advanced LWR Plant Program,AP600 Certified Design Matl
ML20141C6961997-05-0909 May 1997
Proposed Tech Specs LCO 3.0.2 & 3.0.3,reflecting Compliance W/Nrc Staff Position of Ltr
ML20137C6781997-03-19019 March 1997
Proposed Tech Specs Rev Re LCO 3.0.3,Key Licensing Issue 19 Deleting Exemption for Entry
ML20134A5621997-01-15015 January 1997
Rev 2 to Design Reviews
ML20141B1351996-08-31031 August 1996
Proposed Tech Specs Re Advance Markup of AP600
ML20141K2571996-08-31031 August 1996
Proposed Tech Specs 3.7.6 Re Main Room Habitability Sys
ML20117J1071996-08-30030 August 1996
Revised Background Info for AP600 Emergency Response Guidelines,Including Rev 1A to EA-1,Rev 1A to AES-1.1,Rev 1A to AES-1.2 & Rev 1A to AE-2
ML20116A4421996-07-31031 July 1996
Westinghouse AP600 Chapter 14,Initial Test Program
ML20116J8331996-07-31031 July 1996
Rev 2 to SDG-6, AP600 Response to Unexpected RCS Temp Changes During Shutdown
ML20116J8231996-07-31031 July 1996
Rev 2 to SDG-5, AP600 Response to Cold Overpressure During Shutdown
ML20116J8151996-07-31031 July 1996
Rev 2 to SDG-4, AP600 Response to Increasing Nuclear Flux During Shutdown
ML20116J8101996-07-31031 July 1996
Rev 2 to SDF-3, AP600 Response to High Containment Radiation During Shutdown
ML20116J7941996-07-31031 July 1996
Rev 2 to SDF-0.1, AP600 Shutdown Safety Status Tree During Shutdown
ML20116J8031996-07-31031 July 1996
Rev 2 to SDG-2, AP600 Response to Loss of Rns During Shutdown
ML20116J8001996-07-31031 July 1996
Rev 2 to SDF-1, AP600 Response to Loss of RCS Inventory During Shutdown
ML20111B0501996-05-0101 May 1996
Proposed Tech Specs 5.1,5.2 & 5.3
ML20107C7421996-04-0808 April 1996
Non-proprietary Man-In-The-Loop Test Plan Description
ML20107C7401996-04-0808 April 1996
Non-proprietary Programmatic Level Description of AP600 Human Factors Verification & Validation Plan
ML20101N8341996-03-31031 March 1996
Non-proprietary Version of AP600 Reactor Internals Flow-Induced Vibration Assessment Program
ML20096F1261996-01-15015 January 1996
Revised Pages 1-3 & 1-4 of Rev 1 to AP600 SPES-2 Test Analysis Rept
ML20095E6721995-12-0808 December 1995
Plan to Resolve AP600 PRA MAAP4 Success Criteria Issues
ML20091M3831995-07-31031 July 1995
SPES-2 Hot Preoperational Test H-06 Inadvertent ADS Stage 1 Actuation (with No ADS Stage 4)
ML20134A5501995-06-0101 June 1995
Rev 2 to AP600 Sys Specification Documents
ML20134A6001995-06-0101 June 1995
Rev 1 to Control of Subcontractor Submittals
ML20083R3451995-05-31031 May 1995
Nonproprietary Large-Scale Test Data Evaluation
ML20085E4261995-05-31031 May 1995
AP600 Emergency Response Guidelines
ML20083B8901995-02-28028 February 1995
Rev 3 to Simplified Passive Advanced Light Water Reactor Plant Program AP600 Probabilistic Risk Assessment
ML20073C9101994-08-26026 August 1994
Rev 2 to WCAP-13234, Test Spec for Long-Term Cooling Test
ML20065M2971994-05-31031 May 1994
Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992
ML20069A3761994-05-0606 May 1994
Rev 6 to AP600 Design Certification Test Program Overview
NRC-94-4120, Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93)1994-04-27027 April 1994
Rev 0 to in Situ Check Valve Test Rept (Fall Outage 93)
NRC-94-4116, Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test1994-04-21021 April 1994
Nonproprietary Passive Containment Cooling Sys Bench Scale Wind Tunnel Test
1998-09-25
[Table view] |
Text
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nua teosage veceut..vo instruciencauc,n
, 3.4.10 I
. 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 RCS Leakage Detection Instrumentation LC0 3.4.10 The following RCS leakage detection instrumentation shall be OPERABLE:
- a. One containment sump level channel:
- b. One containment atmosphere radioactivity monitor (gaseous N13/F18).
............................N0TE ... ..- ... -
The N13/F18 containment atmosphere radioactivity monitor is only required to be OPERABLE in MODE 1 with RTP > 20%.
APPLICABILITY: MODES 1, 2, 3. and 4.
............................N0TE - -
Containment sump level measurements cannot be used for leak detection if leakage is prevented from draining to the sump such as by redirection to the IRWST by the containment shell gutter drains.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Two A. Sequired containment -
NOTE - -
sump channels LC0 3.0.4 is not applicable.
inoperable. - - - -
A.1 Perform SR 3.4.8.1 (RCS Once per inventory balance). 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND Ont Y h0D A.2 Restore 3 containment sump 30 deys channel to OPERA 8LE status.
(continued) h AP600 3.4 15 08/97 Amendment 0 APC1unneoec\16010410 #07 073097 9709080254 970829 PDR ADOCK 052C V.)O3' A DR
i m teosaye veceuiva uiscrumentation B 3.4.10 BASES APPLICABILITY H0 DES 1, 2, 3, and 4, the likelihood of leakage and crack (continued) propagation are much smaller. Therefore, the requirements of this LCO are not applicable in MODES 5 and 6.
Contain sump level monitoring is a valid method for detecting leakage in MODES 1, 2, 3, and 4. The containment atmosphere N13/F18 radioactivity leakage measurement during H00E 1 is valid only for reactor power > 20% RTP. RCS inventory monitoring via the pressurizer level changes is valid in H0 DES 1, 2, 3, and 4 only when RCS conditions are stable, i.e., temperature is constant, pressure is constant.
no makeup and no letdown.
The containment sump level change method of detecting leaks during H0 DES 1, 2, 3 and 4 is not valid while containment purge occurs or within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the end of containment purge.
l The containment atmosphere N13/F18 radioactivity leakage measurement during MODE 1 is not valid while containment purge occurs or within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the end of containment purge.
The containment sump level change method of detecting leaks during MODES 1, 2, 3, and 4 is not valid during extremely cold outside ambient conditions when frost is forming on the interior of the containment vessel, ACTIONS A.1 and A.2 No With the required containment sump level channel 5 inoperable, no other form of sampling can provide the equivalent information: however, the containment atmosphere N13/F18 radioactivity monitor will provide indications of changes in LEAKAGE. Together with the atmosphere monitor, the periodic surveillance for RCS inventory balance, SR 3.4.8.1, must be performed at an increased frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to provide information that is adequate to detect LEAKAGE.
Restoration of tksump channel to OPERABLE status is required to regain the function in a Completion Time of SON N days after the monitor's failure. This time is acceptable, considering the frequency and adequacy of the RCS inventory balance required by Action A.1, (continued) h AP600 B 3.4 43 08/97 Amenchnent 0 AP01\seosoecs t &O30410 f07 071197
m,a teoAage vecection anstrumentation
. B 3.4.10 s
. BASES ACTIONS A.1 and A.2 (continued)
Required Action A.1 is modified by a Note that indicates that the provisions of LC0 3.0.4 are not applicable. As a result, a MODE change is allowed when the containment sump channels finoperable. This allowance is provided because other instrumentation is available to monitor RCS Leakage.
B.1.1 B.1.2. and B.2 With one gaseous N13/F1B containment atmosphere radioactivity monitoring instrumentation channel inoperable, alternative action is required. Either grab samples of the containment atmosphere must be taken and analyzed or RCS inventory balanced, in accordance with SR 3.4.8.1. to provide alternate periodic information.
With a sample obtained and analyzed or an RCS inventory balance performed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor may be operated for up to 30 days to allow restoration of the radioactivity monitor.
The 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval for grab samples or RCS inventory balance provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time recognizes at i
least ene other form of leak detection is available.
Required Action B.1 and Required Action B.2 are modified by a Note that indicates that the provisions of LC0 3.0.4 are not applicable. As a result, a MODE change is allowed when the gaseous N13/F18 containment atmosphere radioactivity monitor channel is inoperable. This allowance is provided because other instrumentation is available to monitor for RCS LEAKAGE.
C.1 and C.2 If a Required Action of Condition A or B cannot be met within the required Completion Time, the reactor must be brought to MODE 5 where the probability and consequences of an event are minimized. To achieve this status, the plant must be brought to at least M00E 3 within-6 hours and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner without challenging plant systems.
(continued) h AP500 B 3.4 44 08/97 Amendment 0 A80htecaspeco 6030410 07 073097