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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20196D0241999-06-16016 June 1999
Proposed Tech Specs Re Reactivity Control Incorporating Operating Requirements That Are Consistent with NEDO-21231, Banked Position Withdrawal Sequence
ML20206R8161999-05-11011 May 1999
Proposed Tech Specs Re HPCI & RCIC Surveillance Testing
ML20206H9771999-05-0505 May 1999
Proposed Tech Specs Modifying Licensing Basis for EDG on- Site Diesel Fuel Storage Requirements & Corresponding TSs
ML20205A1451999-03-23023 March 1999
Core Shroud Insp Plan
ML20207F1171999-03-0303 March 1999
Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule
ML20151S3851998-08-31031 August 1998
Long-Term Program:Semi-Annual Rept
ML20237E0851998-08-24024 August 1998
Proposed Tech Specs Pages Supporting Proposed TS Amend Related to EDG AOT
ML20236X7191998-07-31031 July 1998
Proposed Tech Specs Page 3/4.9-5 Re Suppl to EDG for Allowed Outage Time
ML20249C7101998-06-26026 June 1998
Proposed Tech Specs Correcting Typos & Updating Bases
ML20249B3231998-06-15015 June 1998
Revised Complete Set of TS Pages Re Relocation of Radioactive Effluent TS & Radiological Environ Monitoring Program to ODCM
ML20217F9341998-03-26026 March 1998
Proposed Tech Specs Re EDG Allowed Outage Time
ML20217H2791998-03-25025 March 1998
Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A
ML20203D4981998-02-20020 February 1998
Proposed Tech Specs Pages,Incorporating Ultimate Heat Sink Temperature of 75 F Into TS 3/4.5.B & Bases,As Required by Amend 173
ML20217K5691997-10-24024 October 1997
Proposed Tech Specs Page Adding Footnote Declaring One Containment Isolation valve,30-CK-432,operate for Limited Period Despite Not Being within IST Interval for Reverse Flow Testing
ML20211N6871997-09-16016 September 1997
Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20211G2381997-09-15015 September 1997
Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm
ML20211G2311997-09-12012 September 1997
Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM
ML20216C0631997-08-29029 August 1997
Semi-Annual Long Term Program Schedule
ML20210K4381997-08-0808 August 1997
Revised TS Pages 3/4.5-7,B3/4.5-6 & B3/4/.5-7 Requiring Verification That SBO-DG Is Operable Prior to Voluntarily Entering LCO
ML20196J0041997-07-22022 July 1997
Proposed Revised TS Bases for Section 3.5.F,correcting Volume of Water Available in Refuel Cavity & Dryer/Separator Pool When Flooded to Elevation 114 Ft & Revising Torus Water Volume to Reflect Volume Above Min Pump NPSH
ML20210K3551997-07-0101 July 1997
Rev 16 to Procedure 7.8.1, Water Quality Limits
ML20136J5501997-03-0707 March 1997
Proposed Tech Specs Rev for Section 3.10, Core Alterations Allowing Removal of Suspect Fuel Bundles Out of Planned Sequence
ML20134C9671997-01-24024 January 1997
Proposed Tech Specs 2.0 Re Safety Limits
ML20133A6511996-12-23023 December 1996
Proposed Revised Tech Specs 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
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A1451999-03-23023 March 1999
Core Shroud Insp Plan
ML20151S3851998-08-31031 August 1998
Long-Term Program:Semi-Annual Rept
ML20211N6871997-09-16016 September 1997
Rev 9 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20211G2381997-09-15015 September 1997
Rev 8 to PNPS-ODCM, Pilgrim Nuclear Power Station Odcm
ML20216C0631997-08-29029 August 1997
Semi-Annual Long Term Program Schedule
ML20210K3551997-07-0101 July 1997
Rev 16 to Procedure 7.8.1, Water Quality Limits
ML20117K6611996-07-17017 July 1996
Rev 15 to PNPS Procedure 1.2.2 Administrative OPS Requirements
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
ML20077Q1181995-01-13013 January 1995
Owner'S Specification for Reactor Shroud Repair
ML20127N2711992-11-24024 November 1992
Rev 4 to Pilgrim Nuclear Power Station Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20128M7701992-03-31031 March 1992
Amend 92-01 to Second Ten Year ISI Program
ML20094P5411992-03-19019 March 1992
Rev 23 to Procedure 5.4.6, Primary Containment Venting & Purging Under Emergency Conditions, Revising Coversheet & Attachment 1,Sheet 3 of 5,page 8 of 20
ML20058E5281990-10-25025 October 1990
Rev 1 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program
ML20005F0791989-12-13013 December 1989
Rev 0 to Procedure 8.I.1.1, Inservice Pump & Valve Testing Program.
ML20247N3611989-07-31031 July 1989
Rev 2 to Dcrdr Program Plan
ML20245D6551989-04-21021 April 1989
Power Ascension Program Resumption Plan
ML20235R3441988-12-28028 December 1988
Rev 26 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test
ML20235R4671988-12-22022 December 1988
Rev 25 to, Pilgrim Nuclear Power Station Secondary Containment Leak Rate Test
ML20155C0141988-09-28028 September 1988
Rev 3 to Appendices to Restart Plan
ML20155F9041988-09-0707 September 1988
Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures
ML20153H6481988-08-31031 August 1988
Ascension Program
ML20235R3801988-08-0909 August 1988
Special Post-Startup Training Program to Satisfy Requirements of NUREG-1021,Section ES-109,Parts B.2.e & B.2.f for Reactor Operator Licensed Personnel & Parts D.2.e & D.2.f for Senior Reactor ..
ML20150C0271988-05-26026 May 1988
Rev 2 to Vol 2 to Apps to Restart Plan
ML20151F9481988-04-0606 April 1988
Rev 2 to Emergency Operating Procedure 1.3.4-13, Emergency Operating Procedures Verification Program
ML20151C8111988-04-0606 April 1988
Rev 3 to Emergency Operating Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures
ML20151F9681988-04-0606 April 1988
Rev 2 to Emergency Operating Procedure 1.2.4-14, Emergency Operating Procedure Validation Program
ML20151C8151988-03-28028 March 1988
Emergency Operating Procedures Training Program Summary Description
ML20153B1061988-03-14014 March 1988
Rev 1B to Inservice Testing Program for Pumps & Valves, Pilgrim Nuclear Power Station
ML20236T2171987-11-20020 November 1987
Rev 3 to Pilgrim Nuclear Power Station Plant-Specific Technical Guidelines for Emergency Operating Procedures
ML20236T2241987-11-20020 November 1987
Rev 3 to Apps to Pilgrim Nuclear Power Plant-Specific Technical Guidelines
ML20236T2361987-11-20020 November 1987
Collection of Plant Operating Procedures Utilized to Develop,Process & Issue Plant-Specific Emergency Operating Procedures
ML20236N7751987-11-12012 November 1987
Rev 1 to Procedure 3.M.1-1, Preventive Maint
ML20236F0201987-10-26026 October 1987
Rev 1 to Vol 2 of Pilgrim Nuclear Power Station Apps to Restart Plan
ML20155F9171987-10-16016 October 1987
Rev 1 to Procedure 1.3.4-13, Emergency Operating Procedure Verification Program
ML20155F9111987-10-15015 October 1987
Rev 2 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures
ML20235X2461987-10-15015 October 1987
Power Ascension Program
ML20195H6341987-09-22022 September 1987
Rev 23 to Procedure 8.7.3, Secondary Containment Leak Rate Test
ML20238E8311987-09-0101 September 1987
Revised Nuclear Operations Dept Procedures,Including Rev 5 to Procedure 5.7.4.1.1, Post-Accident Sampling Sys,Small Vol Liquid Sample from Jet Pump Flow Sensing Line & Rev 6 to Procedure 5.7.4.1.2, ...Undiluted Liquid Sample..
ML20236G4071987-07-30030 July 1987
Vol 1 to Pilgrim Nuclear Power Station Restart Plan. Rev 0 to Vol 2,appendices,encl
ML20236F9531987-07-28028 July 1987
Matl Condition Improvement Action Plan
ML20155F9201987-07-10010 July 1987
Rev 0 to Procedure 1.3.4-14, Emergency Operating Procedure Validation Program
ML20204F7431986-06-16016 June 1986
Rev 1 to Temporary Procedure Tp 86-85, RHR Intersys Leakage Assessment & Controlled Leakoff
ML20204F7301986-06-10010 June 1986
Rev 11 to Procedure 2.3.2.1, Panel Procedures Panel 903 Left
ML20204F7481986-06-10010 June 1986
Rev 0 to Temporary Procedure Tp 86-84, RHR Discharge Piping Venting Procedure
ML20137M4811985-08-21021 August 1985
Rev 1 to Procedure 5.7.5, Estimating Core Damage
ML20138R4501985-07-19019 July 1985
Rev 0 to Procedure 1.3.4-10, Writers Guide for Emergency Operating Procedures
ML20128N9341985-03-0606 March 1985
Rev 0 to Procedure 5.7.5, Estimating Core Damage
ML20101S7121984-12-13013 December 1984
Rev 11 to Procedure 2.1.12, Daily Diesel Generator Surveillance
ML20101S7201984-12-12012 December 1984
Rev 15 to Procedure 8.9.1, Manually Start & Load Each Diesel Generator Once Per Month
1999-03-23
[Table view] |
Text
. _ - _
1 BOSTON EUISON RTYPE H6.05 I
PILGRIM NUCLEAR POWER STATION Procedure No. 5.4.6 I
l PRIMARY CONTAINMENT VENTING AND PURGING UNDER EMERGENCY CONDITIONS l
l l
l I
1 REVIEWEjS AND APPR0'fERS y
\
1
// mist) WfM d w ce- 3l/4 lG2
{
Procedure \frLter Date l
? e27&E S YN l Technicil jR viewer Date !
Mtd d -ktwxjz.- 3llfclf7 Validator Date 1:gi um b- Pb Smih 3 ll& lf 2 Procedure Owner Date SAFETY REVIEH REQUIRED o/k 0AD Manaaer Date ORC REVIEH REQUIRED / '
/ M/2!9' NOT-M%'4MD (RC' Chai rman Date h 7 As $bt S/M/f?_
'Piant Manaaer Date Effective Date: S-20-99 5.4.6 Rev. 23 9204080202 920330 3 DR ADOCK 0500
. . . - _ - .. . - ..- - _ - . . . . . . - _ - . - . _ - . ~ .. . . . - . - . .- . . . _ -
ATTACHMENT 1 s.
.e t -
- Sheet 3 of 5 .
(2) Containment Atmosphere Dilution-System Torus Isolation valves
] (C170 and C171) Special' Key CR-V.
- SV-5083A.' TORUS ISOLATION VALVE
- - SV-5084A, . TORUS ISOLATION VALVE
- SV-5083B, TORUS ISOLATION VALVE ,
i
- SV-5084B. TORUS ISOLATION VALVE
....o..........................................................................
CAUTION
. >m performing the following, refer to Emergency Classifications
- 1. : '-100. . Reference EAL 3.4.1.4, EAL 3.5.1.4, and EAL 3.5.2.4.
w- ,
5 01, additional venting capacity is required,
&MD primary containment pressu.re is 1 30 psig, IBER VENT the Torus, bypassing SGTS as follows:
4- (1) CLOSE 08 VERIFY CLOSED the following valves:
- A0-5042A, T0HUS PURGE EXHAUST ISOL VLV e A0-5041A, T0kv5 NORMAL EXHAUST ISOL VLV ,
- AO-5041B, TORUS NORMAL EXHAUST ISOL VLV
- SV-5083A, TORUS ISOLATION VALVE
~
e SV-5084A, TORUS ISOLATION VALVE
- SV-5083B, TORUS ISOLATION VALVE
- SV-50848, TORUS ISOLATION VALVE (2) PLACE the-fan control' switches for SGTS Exhaust Fans VEX-210A L AMQ VEX-210B to "0FF".
P (3) CLOSE QR VERIFY CLOSED the following valves:
i
- j.
- A0-N-112 TRAIN B OUTL DHPR
- AD-N-108, TRAIN A 00TL OMPR L
(4) OPEN AD-50428, TORUS. PURGE EXHAUST ISOL VLV, bypassing isolation interlocks according to PNPS 5.3.21, " Bypassing Selected Interlocks" Attachment 12.
5.4.6 Rev. 23 Page 8 of 20
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