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Category:QUALITY ASSURANCE PROGRAM
MONTHYEARML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A3161998-06-0202 June 1998 Rev 25 to QA Program for Station Operation. Draft of Program,Included ML17265A2631998-05-0505 May 1998 Rev 25 to QA Program. ML17264B1431997-12-17017 December 1997 Rev 24 to QAP for Stations Operation. Draft Copy of Program,Encl ML17264A7661996-12-13013 December 1996 Rev 23 to QA Program for Station Operation. ML17264A3091995-12-19019 December 1995 Rev 22 to QA Program for Station Operation. ML17263A8891994-12-21021 December 1994 Rev 21 to QA Program for Station Operation. ML17263A7561994-08-31031 August 1994 Rev 20 to QA Program for Operation. ML17263A6501994-05-31031 May 1994 Rev 20 to QA Program for Station Operation. ML17263A6231994-03-0202 March 1994 Rev 2 to QA Manual App C Inservice Pump & Valve Testings Program for 1990-1999. ML17309A5351993-12-31031 December 1993 Rev 19 to QA Program for Station Operation. ML17263A3511992-12-31031 December 1992 Rev 18 to QA Program for Station Operation. ML17262A7201991-12-31031 December 1991 Rev 17 to QA Program for Station Operation. ML17262A6381991-09-23023 September 1991 Rev 1 to QA Manual,App C, Inservice Pump & Valve Testing Program for 1990-1999 Interval. ML17262A2831990-12-31031 December 1990 Rev 16 to QA Program for Station Operation. ML17261A9041989-12-31031 December 1989 Rev 15 to QA Program for Station Operation. ML17309A4931989-07-20020 July 1989 Rev 0 to QA Program Ginna Station Inservice Insp Program for 1990-1999 Interval. ML17251A5231989-05-23023 May 1989 Rev 0 to App C Inservice Pump & Valve Testing Program for 1990-1999 Interval, QA Manual ML17261A7981988-12-31031 December 1988 Rev 14 to QA Program for Station Operation ML17251A9431988-02-19019 February 1988 Corrected Pages 5 & 53 to Rev 13 to QA Program ML17261A6991987-12-31031 December 1987 Rev 13 to QA Program for Station Operation. ML17261A5621987-07-24024 July 1987 Rev 11 to App B Ginna Station Inservice Insp Program for 1980-1989 Interval. ML17309A3901986-12-31031 December 1986 Rev 12 to QA Program for Station Operation ML17251A8461986-09-22022 September 1986 Rev 9 to QA Manual,App B Re Inservice Insp Program for 1980-1989 Interval ML17254A7431986-01-24024 January 1986 Rev 7 to QA Manual,App C, Ginna Station Inservice Pump & Valve Testing Program for 810101-891231 Period. ML17254A7141985-12-31031 December 1985 Rev 11 to QA Program for Station Operation. ML17254A4141985-06-30030 June 1985 Rev 10 to QA Program for Station Operation ML17254A4231985-01-10010 January 1985 Rev 6 to QA Manual,App C Re Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1989 ML17254A7911984-06-30030 June 1984 Rev 9 to QA Program for Station Operation. ML17255A7681984-04-0303 April 1984 QA Manual App B, Inservice Insp Program for 1980-1989 Interval. ML17255A5711983-11-29029 November 1983 Rev 4 to Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990 ML17255A5751983-10-14014 October 1983 Rev 7 to Inservice Insp Program for 1980 - 1989 ML17255A2981983-06-15015 June 1983 Rev 3A to App C to QA Manual Re Inservice Pump & Valve Testing Program for Jan 1981 - Dec 1990 ML17258A4581982-01-11011 January 1982 to QA Manual Re Inservice Insp Program for 1980-1989 Interval, App B ML17258A3291981-11-19019 November 1981 Proposed QA Manual,App B,Inservice Insp Program for 1980-89 Interval Reflecting Tech Specs Changes Re safety-related Snubbers.Safety Evaluation Encl ML17258A9801981-04-21021 April 1981 to App B of QA Program for Inservice Insp ML17258A8531981-02-0101 February 1981 to QA Program Manual,App C Re Inservice Pump & Valve Testing for 810101-901231 ML17250A7541980-11-0505 November 1980 Inservice Insp Program for 1980-89,Revision 4,App B to QA Manual ML17255A5171980-07-22022 July 1980 Rev 3 to QA Manual:App A,Quality & safety-related Listing & Diagrams ML17249A2901979-11-15015 November 1979 App C to QA Manual Re Revised Inservice Pump & Valve Testing Program for May 1979-Dec 1980 ML17244A5871979-07-0202 July 1979 Inservice Insp Program for 1980-89 (App B of QA Manual) ML17255A5761979-06-30030 June 1979 Rev 0 to Inservice Insp Program for 1980 - 1989 1999-03-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp. ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30
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Attachment 2 ROCHESTER GAS AND ELECTRIC CORPORATION R.E. GINNA NUCLEAR POWER PLANT Quality Assurance Program for Station Operation Revision 26 DOCKET NO. SO-244 March 1, 1999 W~GSZooa<7 eqosoa .
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TABLE 17.1.7-1 (cont'd)
Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.144 Rev.(1)-Auditing of Quality Alternate RG 1.144 Rev.(1) incorporates ANSI N45.2.12-1977. Ginna conforms to RG 1.144 Rev.(1)
Assurance Programs for Nuclear Power Plants and...AI'Igrblj$@"';:I@Ipyy,: with the foilowtoglexceptionsf dtal-a gmm period of 90 days may be applied to the perfo~mce of triennial supplier audits and annual supplier evaluations described in Section C.3.b.(2).
a:::s'chc'dn'Ic'4:."daI'e",:fo','ore rbitiroi'ictooit Regulatory Guide 1.146 Rev.(0)-Qualification of QA Alternate RG 1.146 Rev.(0) incorporates ANSI N45.2.23-1978. Ginna conforms to RG 1.146 Rev.(0)
Progratn Audit Personnel for Nuclear Power Plants and::,Affgl":::II4$%@g.:.".I 9+0:: with the fdliowlng'aexceptionst that-a grace period of 90 days may be applied to the performance of annual lead auditor recertifications described in Sections 3.2 and 5.3~of,":A'NSI"::F49","2.".,'23";:,f978.
'alldit'pmc'es's':'mtd.:'a'ffcrttyely,Ie'ad:*,':,alt, aU$ ilt:te'am::::",,:IttsdlB;:will..,deter'tb'e:,thts ies'uI'ts'.:,'o':.::.ih'e!'d$ monst'rattotIt"'.:,;'RegasrdIex's's.';".o',:;:Ih'e:;:.rn'ethods
'dt'e" jiiospe'cII'se':::iced!tshiidit'or':.shsII',:I,ihba':'r9'iItpteait,e'drain,"'sass::Itegahsii'ernie;nubfte'ar;:,'9'ushestiiy, a's'suiiin'ee'hudif w'jism';,."tb'eyearpmcedfii'9:ih'olnd'smut'diijI!dseffetc iiy":d't'I note 8'ectt
.jiia1i fIed.:,:,ti,;::,IeatI:.":audtts'-'inna Regulatory Guide 1.152 Rev.(0)-Criteria for Alternative conforms to Generic Letter 95-02, and its endorsement of NUMARC/EPRI Report TR-Programmable Digital Computer System Software in 102348 "Guidelines on Licensing Digital Upgrades".
Safety-Related Systems of Nuclear Power Plants Regulatory Guide 4.15 Rev.(1)-Quality Assurance Adopted Ginna conforms to the intent of this Regulatory Guide as addressed in the Process Control for Radiological Monitoring Program (Normal Program and applicable to Ginna effluent and environmental radioactivity measurements.
Operations)-Effluent Streams and the Environment RG&E QAPSO, Revision 26 March 1, 1999
Enclosure 1 ROCHESTER GAS AND ELECTRIC CORPORATION R.E. QINNA NUCLEAR POWER PLANT Quality Assurance Program for Station Operation Revision 26 DOCKET NO. 50-244 March 1, 1999
TABLE 17.1.7-1 (cont'd)
Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.39 Rev.(2)-Housekeeping Conforms RG 1.39 Rev.(2) incorporates ANSI N45.2.3-1973.
Requirements for Water-Cooled Nuclear Power Plants Regulatory Guide 1.54 Rev.(0)-Quality Assurance Alternative Quality assurance requirements apply only when a coating performs a safety related function Requirements for Protective Coatings Applied to instead of the provisions stated in this Regulatory Guide and its referenced standard, ANSI Water-Cooled Nuclear Power Plants N101.4-1972.
See the UFSAR for quality assurance requirements used for existing coatings. For new coatings and configuration changes to existing coatings, either the quality assurance requirements of the UFSAR or the quality assurance requirements of 10CFR50, Appendix B are used instead of the detailed requirements included in this Regulatory Guide.
Regulatory Guide 1.58 Rev.(1)-Qualification of Alternate RG 1.58 Rev.(1) incorporates ANSI N45.2.6-1978. Ginna conforms to Reg. Guide 1.58 Nuclear Power Plant Inspection, Examination, and Rev.(1) and ANSI N45.2.6-1978 with the following exceptions:
Testing Personnel A 90 day grace period may be applied to the performance of annual evaluations of inspection, examination and testing personnel qualifications defined in Section 2.3 of ANSI N45.2.6-1978.
RG&E's ISI Plan endorses ASME Code Section XI. The version of the ASME code endorsed is updated periodically. ASME Code Section XI references standards for the qualification and certification of nondestructive testing personnel.Section XI of the.ASME Code contains specific requirements for nondestructive examination and also references the use of other supplementary standards for the qualification and certification of personnel performing nondestructive examinations. The applicable versions of the standards referenced in Section XI of the ASME code, as permitted for use by 10 CFR Part 50.55a, may be used for the qualification and certification of personnel performing nondestructive examinations required by Section III and Section XI of the ASME Code in lieu of the standard identified in Reg. Guide 1.58, Rev. 1, (SNT-TC-lA-1975) provided that other applicable rules contained in Section XI of the ASME Code are met.
Regulatory Guide 1.64 Rev.(1)-Quality Assurance Conforms RG 1.64 Rev.(1) incorporates ANSI N45.2.11-1974.
Requirements for Design of Nuclear Power Plants RG&E QAPSO, Revision 26 March 1, 1999
TABLE 17.1.7-1 (cont'd)
Standard Re uirement or Guide Conformance Remarks Status Regulatory Guide 1.144 Rev.(l)-Auditing of Quality Alternate RG 1.144 Rev.(1) incorporates ANSI N45.2.12-1977. Ginna conforms to RG 1.144 Rev.(1)
Assurance Programs for Nuclear Power Plants and ANSI N45.2.12-1977 with the following exceptions:
~ a grace period of 90 days may be applied to the performance of triennial supplier audits and annual supplier evaluations described in Section C.3.b.(2).
~ In lieu of the 30 day requirement of Section 4.5.1 of ANSI N45.2.12-1977 the following is used: Corrective action response due dates and priority shall be based on safety significance. For audit findings that are determined to be significant conditions adverse to quality, the audited organization's response shall be provided within 30 days. In the event that the corrective action for an audit finding cannot be completed by the response due date, the audited organization's. response shall include a scheduled date for corrective action.
Regulatory Guide 1.146 Rev.(0)-Qualification of QA Alternate RG 1.146 Rev.(0) incorporates ANSI N45.2.23-1978. Ginna conforms to RG 1.146 Rev.(0)
Program Audit Personnel for Nuclear Power Plants and ANSI N45.2.23-1978 with the following exceptions:
~ a grace period of 90 days may be applied to the performance of annual lead auditor recertifications described in Sections 3.2 and 5.3 of ANSI N45.2.23-1978.
~ In lieu of the requirements of 2.3.4 of ANSI N45.2.23-1978 the following is used:
Prospective lead auditors shall demonstrate their ability to effectively implement the audit process and effectively lead an audit team. RG&E will describe this demonstration process in written procedures and shall evaluate and document the results of the demonstration. Regardless of the methods used for the demonstration, the prospective lead auditor shall have participated in at least one nuclear quality assurance audit within the year preceding the individual's effective date of qualification. Upon successful demonstration of the ability to effectively implement the audit process and effectively lead audits, and having met the other provisions of Section 2.3 of ANSI N45.2.23-1978, the individual may be certified as being qualified to lead audits.
Regulatory Guide 1.152 Rev.(0)-Criteria for Alternative Ginna conforms to Generic Letter 95-02, and its endorsement of NUMARC/EPRI Report TR-Programmable Digital Computer System Software in 102348 "Guidelines on Licensing Digital Upgrades".
Safety-Related Systems of Nuclear Power Plants Regulatory Guide 4.15 Rev.(1)-Quality Assurance Adopted Ginna conforms to the intent of this Regulatory Guide as addressed in the Process Control for Radiological Monitoring Program (Normal Program and applicable to Ginna effluent and environmental radioactivity measurements.
Operations)-Effluent Streams and the Environment RG&E QAPSO, Revision 26 March 1, 1999