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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195D0451999-06-0303 June 1999
Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format
ML20206N2751999-05-11011 May 1999
Proposed Tech Specs Deleting Figure 5.1-1 Brp Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes
ML20154M5431998-10-14014 October 1998
Proposed Defueled Tech Specs & Bases for Big Rock Plant
ML20238E8141998-08-31031 August 1998
Revised Big Rock Point Defueled Emergency Plan
ML20236T6681998-07-21021 July 1998
Proposed Defueled Tech Specs for Big Rock Nuclear Plant
ML20248L5511998-06-0505 June 1998
Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI
ML20217P3811998-02-28028 February 1998
Revised Defueled Emergency Plan
ML20138G2021997-04-30030 April 1997
Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6
ML20138A9131997-04-22022 April 1997
Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50
ML20216A9611997-01-0101 January 1997
Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20134H6411996-11-0707 November 1996
Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys
ML20129C4871996-10-15015 October 1996
Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests
ML20199J7411995-10-0303 October 1995
Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers
ML20058N6421993-10-11011 October 1993
Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22
ML20056G3931993-08-24024 August 1993
Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual
ML20058N6401993-07-15015 July 1993
Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start
ML20058N6331993-07-15015 July 1993
Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation
ML20128D7251993-01-29029 January 1993
Proposed Tech Specs Re Administrative Controls
ML20127N4321993-01-11011 January 1993
Third Interval ISI Program
ML20141M5531992-03-10010 March 1992
Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program
ML20059A2181990-08-14014 August 1990
Proposed Tech Specs,Reflecting Administrative & Organizational Changes
ML20246J1841989-08-25025 August 1989
Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program
ML20245K6991989-06-30030 June 1989
Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing
ML20247L1141989-05-25025 May 1989
Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test
ML20204F8321988-10-10010 October 1988
Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs
ML20154S6481988-09-22022 September 1988
Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee
ML20154P2191988-09-21021 September 1988
Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency
ML20154D4821988-09-0808 September 1988
Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes
ML20207C2291988-07-13013 July 1988
Rev 7 to Suitability,Training & Qualification Plan. W/
ML20150C7921988-07-0505 July 1988
Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves
ML20154L7961988-05-26026 May 1988
Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b)
ML20153G0861988-04-13013 April 1988
Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual
ML20153G1041988-04-12012 April 1988
Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20155A5221988-04-0606 April 1988
Rev 30 to Procedure T30-22, ECCS Valve Tests
ML20148Q4681988-03-31031 March 1988
Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20148H6331988-03-22022 March 1988
Proposed Tech Specs Re Reactor Depressurization Sys
ML20147E3701988-01-14014 January 1988
Rev 6 to Suitability,Training & Qualification Plans
ML20215M3281987-12-31031 December 1987
Emergency Plan Exercise Scenario
ML20237B9691987-12-14014 December 1987
Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle
ML20236P0671987-11-13013 November 1987
Rev 1 to Big Rock Point IGSCC Insp Program
ML20236N5501987-11-0909 November 1987
Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl
ML20236B1201987-07-22022 July 1987
Proposed Tech Specs Changes Consisting of Administrative Corrections
ML20214N9801987-05-29029 May 1987
Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment
ML20213A1761987-04-22022 April 1987
Rev 5 to Suitability Training & Qualification Plan
ML20206B4211987-03-12012 March 1987
Public Version of Rev 3 to General Ofc Emergency Planning Procedure GEN-1, Overview, Rev 9 to Copyholders List & Index & Rev 3 to App G, Emergency Telephone Numbers
ML20207T5511987-03-12012 March 1987
Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages
ML20210V2981987-02-10010 February 1987
Corrected Page 11 to Tech Spec,Reflecting New Signature Dates
ML20210E5601987-02-0606 February 1987
Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg
ML20210C6341987-02-0404 February 1987
Proposed Tech Spec Changes,Adding Table of Uncertainty Factors Associated W/Core thermal-hydraulic Parameters Heat Flux,Maplhgr,Max Bundle Power & Min Critical Power Ratio
ML20207L6871986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Training Program
1999-06-03
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20238E8141998-08-31031 August 1998
Revised Big Rock Point Defueled Emergency Plan
ML20217P3811998-02-28028 February 1998
Revised Defueled Emergency Plan
ML20216A9611997-01-0101 January 1997
Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20199J7411995-10-0303 October 1995
Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers
ML20058N6421993-10-11011 October 1993
Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22
ML20058N6331993-07-15015 July 1993
Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation
ML20058N6401993-07-15015 July 1993
Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start
ML20127N4321993-01-11011 January 1993
Third Interval ISI Program
ML20141M5531992-03-10010 March 1992
Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program
ML20246J1841989-08-25025 August 1989
Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program
ML20207C2291988-07-13013 July 1988
Rev 7 to Suitability,Training & Qualification Plan. W/
ML20154L7961988-05-26026 May 1988
Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b)
ML20153G0861988-04-13013 April 1988
Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual
ML20153G1041988-04-12012 April 1988
Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20155A5221988-04-0606 April 1988
Rev 30 to Procedure T30-22, ECCS Valve Tests
ML20148Q4681988-03-31031 March 1988
Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20147E3701988-01-14014 January 1988
Rev 6 to Suitability,Training & Qualification Plans
ML20215M3281987-12-31031 December 1987
Emergency Plan Exercise Scenario
ML20236P0671987-11-13013 November 1987
Rev 1 to Big Rock Point IGSCC Insp Program
ML20214N9801987-05-29029 May 1987
Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment
ML20213A1761987-04-22022 April 1987
Rev 5 to Suitability Training & Qualification Plan
ML20206B4211987-03-12012 March 1987
Public Version of Rev 3 to General Ofc Emergency Planning Procedure GEN-1, Overview, Rev 9 to Copyholders List & Index & Rev 3 to App G, Emergency Telephone Numbers
ML20207T5511987-03-12012 March 1987
Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages
ML20207L7441986-12-30030 December 1986
Technical Guidelines. Basis for Guidelines & Description of Plant Encl
ML20207L7171986-12-30030 December 1986
Rev 0 to Plant-Specific Writers Guide for Emergency Operating Procedures
ML20207L7031986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Validation Procedure
ML20207L6921986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Verification Procedure
ML20207L6871986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Training Program
ML20203H6761986-07-21021 July 1986
Public Version of Revised Emergency Plan Implementing Procedures Including,Rev 2 to GEN-1, Overview, Rev 2 to GEN-3, On-Shift Sys Power Controller & Rev 0 to GORT-1, General Ofc Response Team (Gort). W/860730 Release Memo
ML20137X7321986-02-17017 February 1986
Revised Offsite Dose Calculation Manual
ML20154A1081986-02-12012 February 1986
Plan for Big Rock Point Integrated Assessment
ML20138S1081985-10-28028 October 1985
Public Version of Revised General Ofc Response Team/ Emergency Operations Facility Emergency Implementing Procedures,Including Rev 1 to GEN-1, Overview & Rev 1 to EOF-1, Emergency Officer. W/851114 Release Memo
ML20134K2541985-08-26026 August 1985
Plant,Offsite Dose Calculation Manual
ML20134K2661985-08-26026 August 1985
Plant,Process Control Program
ML20136G5481985-08-0202 August 1985
Public Version of Rev 0 to General Ofc Emergency Planning Procedures. W/850814 Release Memo
ML20127G8471985-04-22022 April 1985
Public Version of Revised Emergency Implementing Procedures, Including Rev 12 to General Ofc Response Team/Emergency Operations Facility & Rev 10 to Review & Control of General.... W/850513 Release Memo
ML18047A3241982-05-0303 May 1982
Requalification Program - Reactor Operator & Senior Reactor Operator.
ML18045A4801980-07-31031 July 1980
Cpco Hot License Program-Reactor Operator.
1998-08-31
[Table view] |
Text
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BIG ROCK POINT NUCLEAR POWER PLANT PROCESS CONTROL PROGRAM (PCP)
August 26, 1985 8
J P l l
l
PROCESS CONTROL PROGRAM (PCP) 1.0 Liquid vastes are treated by filtering and demineralization for clean vastes and either recycled or released to Lake Michigan. Bead resin and filter media vill be shipped devatered as described in Section 2.0.
Liquid vastes, if required, will be processed using the methodology described in Section 3.0, if solidified, or Section 5.0, if absorbed for shipment to Richland only.
2.0 DEWATERING SOLIDS IN HIGH INTEGRITY CONTAINERS (HIC) 2.1 Solids such as bead resin and filter media vill be devatered and shipped in HICs per approved vendor procedures and the HIC certificate of com-pliance.
2.2 High integrity containers are approved by the individual hurial ground agreement states as meeting 10 CFR 61 waste form stability- ceouirements.
2.3 Free water determination shall be verified by the successful completion and documentation of the vendors approved devatering procedure.
3.0 DELWARE CUSTOM MATERIAL (DCM) - SILICATE CEMENT Liquid vastes can be solidified by the DCM method. The silicate solidi-fies and the cement gives structural strength.
3.1 For solidification, acquire a representative sample of vaste. Before following the guidelines outlined below, determine the type of vaste to be solidified, example, lab waste, laundry vaste, decon solutions, boric acid, oil, etc. Sample for pH. borie acid, visible organics and radio-activity.
Use analysis to determine the proper laboratory procedure to test.
All batches shall be lab tested prior to solidification in a larger con-tainer unless sample analysis (pH
- 20%) matches the analysis of a vaste type which has previously passed lab test criteria.
For all oil vaste, do not exceed 50% by volume. Oil must be emulsified with a detergent or boric acid in some type of neutral aqueous vaste or tap water.
NOTE: Oil cannot be shipped to Barnwell, South Carolina.
For spent resins, liquid abosrbent, or other earthen-like material, di-lute with an equal volume of concentrate or tap water to solidify.
All results must be recorded initially, at approximately 2h hours and approximately h8 hours after testing. Grade observations to evaluate sample mixes. The h8-hour test can be omitted if the 2h-hour test is good.
The quantity of chemicals added to sclidify radvaste shall be within 20%
of the quantity as determined by the laboratory test of Step G.
3.2 sotmTrIcATION AND 7977 WAM DMrDMTNATION Solidification shall be considered successful if, h8 hours after com--
pletion of Appendix A solidification, there is not standing water on the vaste surface and the surface is not penetrated more than 2" with a 1" diameter rod. If deeper penetration is possible, then the' drum can still be considered solid if the penetration hole remains open after the rod is withdrevn.
Silicate cement shall cure for a minimum of 28 days prior to shipment for . disposal. For silicate cement drums, the following shall be done:
Each drum shall be inspected for absence of detectable freestanding liquid after curing at least 28 days. With the drum lid installed, invert each drum and allow drum to remain upside down for at least 2h hours.
After 2h hours, inspect each drum by placing upright and removing the lid. The Radvaste Supervisor or designate and a QC Inspector shall inspect each drum for presence of liquid. Drums which failed the h8 hour solidification evaluation should be capable of passing at this point. If no detectable freestanding liquid is present, the drum can be prepared for shipment. Radvaste Supervisor and QC Inspector docu-ment if no detectable freestanding liquid is present.
In the event liquid is observed, those drums with liquid shall be drain-ed of all liquid. When no further liquid can be drained from the drum
(.. in a 2h-hour period, the drum shall be core-bored or overpacked with two bags of approved' absorbent and inspected by QC and Radvaste Super-visor to verify that the drum is dry. After this verification (and documentation) the drum may.be prepared for shipment.
Inspect the drum lid and gasket for defects prior to lid installation.
Install lid. Use a different lid if defects are found which prevent a tight seal between drum and lid.
h.0 10 CFR 61 REQUIPEbENTS h.1 10 CFR 61 classification requirements will be met using Wastetrak computer software program using the scaling factor methodology of AIF/
NESP-027, Methodologies for Classification of Low-Level Radioactive Wastes From Nuclear Power Plants, 1983 The scaling factors vill be updated by an ongoing analysis program of actual vaste streams. The program vill initiate with semiannual samples of available vaste stresms and may be modified to longer intervals if the data base warrants. Waste streams should include, if available; bead resin, reactor coolant, clean vaste, filter crud, and compacted trash, h.2 Documentation of the vaste stream analysis, vaste form stability and computer software scaling factor security shall be maintained by the Falisades RMC section.
m r , -. ,
' 50 ABSORBED MATERIALS (Richland Burial Site Only) 5.1 PACKAGING ABSORBFD LIQUIDS. INCLUDING OILS Container must meet DCT Specification TA requirements as listed in h9 CFR.
Container must be lined with h mil plastic liner and sealed at the top when container is packed.
Container must be filled with enough absorbent material to absorb at least twice the volume of radioactive liquid contents (ratio based on absorbency and not on volume or weight). Liquid should be placed at approximately every 12 inches of absorbent to ensure even dispersion.
52 PACKAGING OF SCINTILLATION VIALS Container must meet DOT Specification TA requirements as listed in h9 CFR.
Container must be lined'vith h mil plastic liner and sealed at the top when container is packed. It is recommended that a layer of absorbent be placed in the bottom of the drum prior to the installation of the plastic liner.
Place approximately 3 inches of abosrbent at the ~oottom of the con-tainer, inside the plastic liner. Vials and absorbent must be placed C in the container in alternate layers not exceeding 6 inches in depth.
The vials are NOT to be opened.
Container must be filled with enough absorbent material to absorb at least twice the volume of radioactive liquid contents (ratio based on absorbency not on volume or weight).
ATTACHMENT I t
TABLE I - ABSORBENTS A. Diatomaceous Earth (Medium Grind)
B. Speedi Dry C. Celatom (M-P 78)
D. Floor Dry - Super Fine E. Hi Dri F. Florco and Florcox G. Instant-Dri H. Safe-T-Sorb I. Oil-Dri (Safe n Dri)
J. Zonolite - Grade No. 2, 3 or h (vermiculite)
Absorbency efficiencies and volumes of absorbent required could vary. In all cases, it is the responsibility of the vaste generator and/or packager to de-termine the efficiency and proper proportions required for the liquids being absorbed.
A written request must be submitted and Departmental approval received prior to use of any absorbent not listed in Table 1. This. request must contain the fol-Icving information:
- 1. A statement of the absorbency of the material as determined by the manu-
- (v ,
facturer and copy of the manufacturer's descriptive information.
- 2. Absorbency for the actual liquid to be disposed must be determined by a bench test (e.g., Westinghouse, Gardner Coleman).
3 Additional factors such as vibration tests, gas generation, long term chem-ical and radiological stability.
Approval of the absorbent or the procedure approval by the Department does not alter any liability or surety arrangements.
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