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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
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- - Reporting Requirements 5.6
. 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shcil be submitted in accordance with 10 CFR 50.4.
5.6.1 Occupational Radiation Exposure Report
.............................N0TE----------------------........-
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance, waste processing, and refueling).
supplements the requirements of 10CFR20. W The Thistabulation@
dose ~ -M assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposuras totaling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole body dose received
.('.
from external sources should be assigned to soecific major work functions. The report shall be submitted by ":rc5-31%each year. (The initial report shall be submitted by March ?!\of the year following the initial criticality.]
Apd/ 30 5.6.2 Annual Radiological Environmental Operatina Report
.............................N0TE-------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
.The Annual Radiological Environmental Operating Report covering the operation of the unit-during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix 1, Sections IV.B.2, IV.B.3, and IV.C.
9709040157 970827 (continued)
PDR ADOCK 05200003 P PDR 2
()AP600 5.0-15 08/96 Amendment 0 m%u .o. -.om
fM 5MGY\ High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem /hr but
< 1000 mrem /hr. shall be barricaded and conspicuously posted as a high radiation area and cntrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., [ Health Physics Technicians]) ,
or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates s 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
) Any individual or group of individuals permitted to enter such areas j shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.
C. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the [ Radiation Protection Manager] in the RWP.
4 5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels a 1000 mrem /hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the shift Foreman on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rste levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
5.7.3 For individual high radiation areas with radiation levels of
> 1000 mrem /hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for and where purposes no enclosure of locking, can be reasonably or that cannot be continuously constructed .aroundguarded, the indivi dual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.
u)
( AP600 5.0-)t(a34 08/96 Amendment 0 ,
u m ?.mn a ,ws esa mee l
l
. TABLE OF CONTENTS-aoaiais'ai'ive coa'ao's . . . . . . . . . . . . . . . . . . s.o-1 O ~5.1 s.o-
. Responsibility
- 0iganization 5.0-1 5.0-2 5.2. .
~ 5.3 Unit Staf f Qualifications . . . . . . . . . . . . . . . . 5.0-5 5.0-6 5.4- Procedures . . . . . . . . . . . .-. . . . . . . . .
Programs _ and Manuals -................. 5.0-7 5.5-5.6 Reporting Requirements . . . - . . . . . .-. . . . . . 5.0-15
-&Qp QQ $*0 ~ 0\-
y Q
l 1
4 (continued)
C-t%
- h AP600 iv 08/96 Amendment 0 mi- . sm
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