Proposed Tech Specs Changes Allowing Controlled Liquid Effluent Releases from Points Other than Radwaste Facility| ML20064M931 |
| Person / Time |
|---|
| Site: |
Pilgrim |
|---|
| Issue date: |
08/30/1982 |
|---|
| From: |
BOSTON EDISON CO. |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML20064M918 |
List: |
|---|
| References |
|---|
| NUDOCS 8209080161 |
| Download: ML20064M931 (3) |
|
|
|---|
Category:TECHNICAL SPECIFICATIONS
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
ML20207F1171999-03-0303 March 1999
Proposed Tech Specs Page 3/4.6-13 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule
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
ML20211G2311997-09-12012 September 1997
Proposed Tech Specs Re Radiological Environ Monitoring Program Moved to ODCM
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
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
ML20111B4201996-05-0101 May 1996
Proposed Tech Specs,Reflecting Implementation of 10CFR50 App J,Option B
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
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
ML20108C0581996-05-0101 May 1996
Proposed Tech Specs Re Core Alteration to LCO & Surveillance Conditions Associated W/Secondary Containment
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
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
ML20077M6921995-01-0909 January 1995
Proposed Reformatted Tech Specs & Bases
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
ML20078K7961994-11-22022 November 1994
Proposed Tech Specs Re Changes to MSIV Leakage Requirement
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
ML20072T0521994-09-0606 September 1994
Proposed Tech Specs Modification to Append a of Operating License DPR-35 Re Maintenance of Filled Discharge Pipe
ML20072S0501994-09-0606 September 1994
Proposed Tech Specs Re Instrumentation That Initiates Primary Containment Isolation & Initiates or Controls Core & Containment Systems
ML20072S0081994-09-0606 September 1994
Proposed Tech Specs Re Primary Containment,Oxygen Concentration & Vacuum Relief
ML20072S0861994-09-0606 September 1994
Proposed Tech Specs Re Standby Gas Treatment & Control Room High Efficiency Air Filtration Sys Requirements
ML20069M3311994-06-0909 June 1994
Proposed Tech Specs,Increasing Allowed out-of-service Time from 7 Days to 14 Days for Ads,Hpci & RCIC Sys,Including Section 4.5.H, Maint of Filled Discharged Pipe
ML20067B7111994-02-0909 February 1994
Proposed Tech Specs Revising Wording for Page 3 of License DPR-35,clarifying Words to Aid Operators & Removing Obsolete Mechanical Snubber Acceptance Criterion
BECO-93-156, Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)1993-12-10010 December 1993
Proposed Tech Specs Requesting Changes Supporting 24 Month Fuel Cycle (Submittal 3)
ML20059A9361993-10-19019 October 1993
Proposed Tech Specs for Removal of Scram & Group 1 Isolation Valve Closure Functions Associated W/Msl Radiation Monitors
BECO-93-132, Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint1993-10-19019 October 1993
Proposed Tech Specs Removing Low Condenser Vacuum Scram in Order to Reduce Spurious Scrams,Unnecessary Plant Transients & Turbine First Stage Pressure Setpoint
ML20046D0441993-08-0909 August 1993
Proposed Tech Specs,Proposing 24 Month Fuel Cycle
ML20044G1331993-05-20020 May 1993
Proposed Tech Specs Reducing MSIV Low Turbine Inlet Pressure Setpoint from Greater than or Equal to 880 Lb Psig to Greater than or Equal to 810 Psig & Reducing Min Pressure in Definition of Run Mode from 880 Psig to 785 Psig
BECO-93-016, Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively1993-02-11011 February 1993
Proposed TS 3.5.C,D & E Re k-infinity Factor,Spent Fuel Pool Storage Capacity & Max Loads Allowed to Travel Over Fuel Assemblies,Respectively
1999-06-16
[Table view]
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] |
Text
..
LIMITING CONDITIONS FOR OPERATION
- 3. The annual average concentration 3.
of tritium prior to dilution in a natural body of water shall not exceed 1 x 10-5 uCi/cc.
4.1 During release of radioactive wastes from the radwaste facility the following conditions shall be
- 4. A monthly proportional composite met:
liquid waste sample, including an aliquot of each bat,ch released during the month, shall be
- a. The minimum dilution water analyzed for tritium, Sr-89, required to satisfy 3.8.A.1 shall be met.
Sr-90, and gross alpha radio-activity.
- b. The gross activity monitor and recorder on the radwaste effluent line shall be operable.
- 5. At least one representative
- c. The effluent control monitor liquid waste batch per month shall be set to alarm and shall be analyzed for dissolved automatically close the waste discharge valve fission and activated gases.
prior to exceeding the limits specified in 3.8.A.1 6.
above.
- d. Liquid waste activity and flow rate shall be contin- +
ually monitored and recorded during release. 7. The liquid effluent radiation 4.2 Discharge of radioactive wastes monitor shall be calibrated at least quarterly by means of a check may be made from any point other source and annually with a known than the radwaste facility during radioactive source. Each monitor, normal operations on a batch as described, shall also have an basis if the following conditions are met:
instrument channel test monthly and a sensor check daily,
- a. The minimum dilution water 8. The status and performance of required to satisfy 3.8.A.1 shall be met. automatic isolation valves and discharge tank selection valves and
- b. Two independent samples shall results of indipendent liquid waste samples shall be checked and be obtained and analyzed logged.
prior to discharge.
- c. Calculations of effluent flow shall be performed and in-dependently verified.
- d. Independent verification of applicable valve line ups shall be made.
8209080161 820830 PDR ADOCK 05000293 P FW@ 178
e e
LIMITING CONDITIONS FOR OPERATION
' SURVEILLANCE REQUIREMENTS 3.8.A Liquid Effluents (Cont'd)
- e. All inputs to the batch to be discharged shall be isolated and no other release of radioactive waste discharges shall be allowed at the same time.
- f. While the discharge is in progress it shall be contin-uously attended.
~
- 5. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process, as a minimum.
all liquids prior to their dis-charge when the activity released during any calendar quarter ex-ceeds 1.25 curies.
- 6. When the release rate of radio-active liquid effluents, excluding tritium and noble gases, exceed 2.5 curies during any calendar quarter, the licensee shall notify the Director, Directorate of Licensing within 30 days' identifying the causes and describing the p'roposed program of action to reduce such release rates.
i l 178a Amendment No.
. . . .. . .. .l.. ,
b EASES: ,
3.8.A and 4.8.A Licuid Effluents.
Liquid radieactive r.aterial is released periodically from Thethe statien under controlled cendi:fons as part of p1sened operations. radioactive liquid ef fluente vill be controlled on a batch The basis limits and each cation in Specif: *:stch 3.F.
vill beA sampled and ::alyced prior to dischstge.
are defined to 1.cep radioactive esterial concer.::a: ions (above background) in the dischsrgt canal as lov as practicable and belov the limits given in
! 10 CFR, Part 20.
Specification 3.E.A.1 requires the licensee te limit the concentration of radioactive natorials in liquid effluer.ts fro: the station to levels specified in 10 CFT. Part 20. Appendix 5. for unrestricted creas. This specifiesticn provides ascurance that no p.ctbcr of the general public can he exposed te liquids containing radioactive esterials in execss of limits considered permissible under the Cc= ission's Rules cnd Reguis tions.
Specification 3.E.A.2 establishes an upper lini: for the relesse of radic-active liquid effluen:s. excluding tritium and nobic gases, of 10 curies The during any calendc quarter vi:hout specific Cc= ission approval.
intent of this specificatien is to permit the licensee the firxibf)fty of
- operation te assure that the public is provided a dependable source of in power under unususi operating conditions which may temporarily result relesses higher than the levels normally achievabic when the sta:icn and :he liquid radesste equipment are functioning at designed. . The licensee has shown ths: releases of up to 10 curies during any calendar quarter vill renu)t in cencentrations of radicactive esterial in liquid eff)uents at small perecntages of the limits specified in 10 CFR Part 20; i.e.
approximately one percent on an identified isotope basis.
In nddition to the limiting conditiens for operatien listed cadcr Speci-fication 3.6.A.2, the reporting requirecents that of Specifics:fon the licensea3.S.A.6. in sh.t11 identify addition to the requirements of Section '6.6, the enuse whenever the release rate of radioactive ef fluen:s, cr.eludinr.
t rf t f um and nobic gases, exceeds 2.5 curies during any calendar cuarter.
I and describe the proposed program of action to reduce such release rate.
This report nust he filed within 3C days following the calendar quarter in which the 2.5 curie release occurred.
Specification 3.8.A.3 restricts' the release of tritium in radioactive liquids to less tha'n one percent of the concentration permissible by 10 l CFR Part 20. This release rate is considered as low as practicable on the basis of operating experience at other similar nuclear power' plants.
l l
to Specification 3.8. A.4.1 & 3.8. A.4.2 requires that suitable equipment l dilute and monitor the releases of radioactive materials in liquid effluents are operating during any period these releases are taking place.
Releases of radioactive wastes from any point other than the radwaste facility shall be isolated and no other release of radioactive wastes shall be allowed i at the same time.
Specification 3.8.A.5 requires that the licensee shall maintain and operate the equipment installed in the radwaste system to reduce the release of 189
. 8
, , ~ . . -
. . . ~ _ _ . - , . , - . . . -- ..,___._,._.-_.,-m- -.m-., , _