ML20204H350
From kanterella
| ML20204H350 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/26/1988 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20204H358 | List: |
| References | |
| 2.206, CAL-86-10, NUDOCS 8810240389 | |
| Download: ML20204H350 (601) | |
Similar Documents at Pilgrim | |
|---|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999
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1.0 Re definitions,3.4 Re Standby Liquid Control sys,3.5 Re Core & Containment Cooling systems,3.7 Re Containment Systems & 3.9 Re Auxiliary Electrical Sys ML20132E5491996-12-10010 December 1996 Proposed Tech Specs Table 3.2.C.1 Re Instrumentation That Initiates Rod Blocks,Table 3.2.C.2 Re Control Rod Block Instrumentation Setpoints & Table 4.2.C Re Minimum Test & Calibr Frequency for Control Rod Blocks Actuation ML20135C1461996-11-26026 November 1996 Proposed Tech Specs,Modifying Definition 1.M, Primary Containment Integrity, to Include All Instrument Line Flow Check Valves to Make Definition Consisten W/Lco 3/4.7.A.2.a.4 ML20134K4361996-11-0707 November 1996 Proposed Tech Specs Re Installation of BWROG Enhanced Option 1A ML20117K6551996-09-0505 September 1996 Proposed Tech Specs,Providing Revised TS Pages 3/4.5-7 & 3/4.5-6 ML20116M1561996-08-12012 August 1996 Proposed Tech Specs to Plant TS Section 6.0,Administrative Controls & Sections 6.5.B.10.C & 6.14 of Util Quality Assurance Manual ML20117K6611996-07-17017 July 1996 Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements ML20108C0581996-05-0101 May 1996 Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment ML20111B4201996-05-0101 May 1996 Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B ML20111C2761996-05-0101 May 1996 Proposed Tech Specs 3.1.1 Re Reactor Protection Sys (Scram) instrumentation,3.2.C.1 Re Instrumentation That Initiates Rod Blocks & 3/4.4 Re Standby Liquid Control ML20108C1071996-05-0101 May 1996 Proposed Tech Specs,Relocating Administrative Controls Re QA Review & Audit Requirements of Section 6 from Plant TS to Boston Edison QA Manual ML20108A6561996-04-25025 April 1996 Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant ML20095E0771995-12-0808 December 1995 Proposed Tech Specs Bases Page B2-2,including GE11 GEXL Correlation Axial Power Profile & R-factor Ranges & Correcting Error in GE11 GEXL Correlation Mass Flux Range in GE Design ref,NEDE-31152-P, GE Fuel Bundle Designs ML20100J2521995-11-22022 November 1995 Rev 7 to Pilgrim Nuclear Power Station Odcm ML20092B5861995-09-0101 September 1995 Rev 0 to Third Ten-Yr Interval ISI Plan for Pilgrim Nuclear Power Station ML20092C4331995-09-0101 September 1995 Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20092A4421995-08-31031 August 1995 Corrected Tech Spec Page Re Reactor High Pressure Trip Setting ML20086K2661995-07-14014 July 1995 Proposed Tech Specs Re Section 2.1,Bases:Safety Limits; Section 3.3.C,scram Insertion Times & Section 4.11.C, Minimum Critical Power Ratio to Reflect Use of Advanced GE-11 Fuel Design in Cycle 11 ML20078R6221995-02-15015 February 1995 Proposed Tech Specs Substituting for Pages Contained in Proposed TS Amends Submitted Prior to 950130 Authorization ML20078N4861995-02-0909 February 1995 Proposed Tech Specs,Increasing Reactor High Water Level Isolation Trip Level Setting ML20077Q1181995-01-13013 January 1995 Owner'S Specification for Reactor Shroud Repair ML20077M6921995-01-0909 January 1995 Proposed Reformatted Tech Specs & Bases ML20077A8991994-11-22022 November 1994 Proposed Tech Specs Re Suppression Chamber Water Level ML20077B1861994-11-22022 November 1994 Proposed Tech Specs 3.5.F,4.5.F.1 & 3.9.B.1 & 2 Re EDG Allowed out-of-svc Time ML20078K7961994-11-22022 November 1994 Proposed Tech Specs Re Changes to MSIV Leakage Requirement ML20078K8151994-11-22022 November 1994 Proposed TS Pages 3/4.2-20 & 3/4.2-35 Re Tables 3.2.C-1 & 4.2.C ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test 1999-06-16 Category:TEST REPORT MONTHYEARML20092C4331995-09-0101 September 1995
[Table view]Startup Test Rept for Pilgrim Nuclear Power Station Cycle 11 ML20078N8421994-11-18018 November 1994 Rev 32 to Procedure 8.7.3, Secondary Containment Leak Rate Test ML20056E2221993-05-19019 May 1993 Final Pilgrim Nuclear Power Station Unit 1 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20045H5381993-01-29029 January 1993 Procedure 8.7.3,Secondary Containment Leak Rate Test. BECO-91-148, Reactor Containment Bldg Integrated Leakage Rate Test Rept1991-08-0505 August 1991 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20076D4891991-07-22022 July 1991 Procedure 8.7.3, Secondary Containment Leak Rate Test, Containment Results of Leak Rate Tests Performed on 910505 & 0620 ML20204H3501988-09-26026 September 1988 Restart Readiness Assessment Rept for Pilgrim Nuclear Power Station BECO-88-049, Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test1987-12-31031 December 1987 Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test ML20209D4721987-04-23023 April 1987 Secondary Containment Leak Rate Test Rept ML20236M1111987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1021987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1001987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0911987-03-0404 March 1987 Smoke Density Test (Nbs) ML20236M1211987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M1281987-03-0404 March 1987 Flooring Radiant Panel Test ML20236M0811987-03-0404 March 1987 Smoke Density Test (Nbs) ML20112F8381985-01-0808 January 1985 Rev 15 to Secondary Containment Leak Rate Signoff ML20100F6031984-12-31031 December 1984 Reactor Containment Bldg Integrated Leakage Rate Test,Type A,B & C Periodic Test,Pilgrim Nuclear Power Station,Unit 1 ML20107A1861984-09-30030 September 1984 Rev 1 to Statistical Analysis of Boundary Strengths for Masonry Walls from Field Test Data ML20064B8921982-10-27027 October 1982 Mark I Containment Program:Plant-Unique Analysis Rept of Torus Suppression Chamber for Pilgrim Station - Unit 1 ML19331D1341980-08-18018 August 1980 Results of Startup Physics Testing Program Conducted for Cycle V Operation. ML19344B3271980-05-31031 May 1980 Primary Containment Integrated Leak Rate Test,Second Periodic Test & Local Leak Rate Tests Results,Jan-May,1980. ML19312E0011980-04-30030 April 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, Final Rept for 790907 Testing ML19320C9891980-04-23023 April 1980 Secondary Containment Leak Rate Test Data.Includes Test Conditions,Base Reading & Standby Gas Treatment Sys a & B Performance ML19312D9971980-03-31031 March 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Generating Station, Final Rept for 790829 Testing ML19305D2591980-03-20020 March 1980 Secondary Containment Leak Rate Test Data. ML20126B3691980-03-0303 March 1980 Secondary Containment Leak Rate Test Data ML19312D9951980-01-31031 January 1980 Test of Cable Penetration Fire Stops for Pilgrim 1 Nuclear Power Generating Station, for 790531 Testing ML20236Q8821976-11-0505 November 1976 Friction Coefficients of Water-Lubricated Stainless Steels for Spent Fuel Rack Facility 1995-09-01 |
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