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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20134H3771996-11-0606 November 1996 Proposed Tech Specs of Appendix a Re Cooling Water Sys ML20134E4551996-10-25025 October 1996 Proposed Tech Specs Changing TS 4.4.A, Containment Leakage Tests, Bases to TS Section B.4.4, Containment Sys Tests & Adding TS.6.5.J, Containment Leakage Rate Testing Program ML20129E2591996-09-24024 September 1996 Proposed Tech Specs,Changing TS 4.12 to Incorporate Revised Acceptance Criteria for SG Tubes W/Degradation in Tubesheet Region ML20117P4311996-09-11011 September 1996 Proposed Tech Specs,Revising Plant TS Governing Cw Sys ML20117B2381996-08-15015 August 1996 Proposed Tech Specs 3.3.B.2 Re Containment Cooling Sys & Bases to Conform to Supporting Analyses ML20115G8121996-07-15015 July 1996 Proposed Tech Specs Re Moveable Incore Detector Thimble Reduction ML20095J7951995-12-14014 December 1995 Proposed Tech Specs for Conformance of Administrative Controls Section 6 to Guidance of STS ML20094S2791995-11-28028 November 1995 Proposed Tech Specs Re Radiological Effluent TS Conformance ML20087F3571995-08-0909 August 1995 Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request 1999-08-31
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure 1999-08-31
[Table view] |
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Exhibit B
>: I Prairie Island Nuclear Generating Plant l 1
License imendment Roquest Dated September 13, 1990 Proposed Changes Marked Up on Existing Technical Specification Pages j Exhibit B consists of the existing Technical Specification page with the proposed changes written on that page. The existing page affected by this License Amendment Request is listed below-1 D
TS 6.7 4 ]
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?l " 02 0/10/90
- ( .7. A.5. Annual S-= ries of Meteorolorical Data An annual summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability at the request of the Commission.
6.7.A.6. Core Ocaratina Limits Reeort
- a. Core operating limits shall be established and documented in the CeRE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
- 1. Heat Flux Hot Channel. Factor Limit (FRPT),q Nuclear Enthalpy Rise Hot Channel Factor Limit (F (Specifications 3.10.B.1, 3.10.H ), and B.2 PFDH, K(Z) and V(Z) 3.10.B.3)
- 2. Axial Flux Difference Limits and Target Band (Specifications 3.10 B.4 through 3.10.B.9)
- 3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)
- 4. Reactor Coolant System Flow Limit (Specification 3.10.J)
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
NSPNAD 8101 A, " Qualification of Reactor Physics Methods for Application to PI Units" (latest approved. version)
NSPNAD 8102 A, " Prairie Island Nuclear Powet Plant Reload Safety Evaluation Met. hods for Application to PI Units" (latest approved version)
WCAP 9272 P A, " Westinghouse Reload Safety Evaluation Methodology", July,1985 l
. VCAP 10924 P.A Volume 1, WCAP 10054-P A, " Westinghouse Small Break ECCS Evaluation Model J Addendum 4. "Vestinghouse Using the NOTRUMP Code", August, 1985 f Large Break IDCA Best EOtimate Methodology *, WCAP 10924 P A, " Westinghouse Large Break LOC /. Best Estimate October 1990 Methodology", December,1988 XN-NF-77 57 (A), XN NF 77 57, Supplenient 1 (A), " Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981
- c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. ,
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Exhibit C .)
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License' Amendment Request Dated September 13, 1990 -: !
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r REVISED TECHNICAL SPECIFICATIONS PAGES l
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' Exhibit C consists'of revised pages for'the Prairie' Island Nuclear Generating-E
-j Plant Technical Specifications with the proposed changes incorporated as J
- - listed below:' l
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TS ix TS.6'.7 4 ,
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TS.6,7 6.
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TS ix TABLE OF CONTENTS (Continued)
TS SECTION TITLE PAGE 6.7, Reporting Requirements TS.6.7 1 A. Routine Reports TS.6.7 1 1.~ Annual Report _ TS.6.7 1
- a. Occupational Exposure Report . .TS.6.7 1
- b. Report of Safety and Relief Valve .
Failures and Challenges TS.6.7 1
- c. Primary Coolant Iodine Spike Report. TS 6.7 1
- 2. Startup Report TS.6.7 2
- 3. Monthly Operating Report TS.6.'7 2
- 4. Semiannual Radioactive Effluent Release Report TS.6.7 3 S.LAnnual Summaries of Meteorological Data TS.6.7-4
- 6. Core Operating Limits Report TS 6.7 4 B. Reportable Events TS.6.7 5
- c. Environmental Reports ~ TS.6.7 6-1.' Annual Radiation Environmental Monitoring.
Reports _ .
TS.6.7 6
- 2. Environmental Special Reports _ TS.6.7 6
- 3. Other. Environmental Reports TS.6.7 7' (non radiological, non-aquatic)
D.:Special' Reports TS.6.7 7
TS.6.7 4 6.7. A.5. Anraal Summaries of Meteoro1orical Data An annual summary of meteorological data shall be submitted for the previous calendar year in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability at the request of the Commission.
6.7.A,6. Core Operatine Limits Report
- a. Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT cefore each reload cycle or any remaining part of a reload cycle for the following:
- 1. Heat Flux Hot Channel Factor Limit (FRPT),q Nuclear Enthalpy Rise Hot Channel Factor Limit (F n ), PFDH, K(Z) and V(Z)
(Specifications 3.10 B.1, 3.10.B.2 and 3.10.B.3)
- 2. Axial Flux Difference Limits tad Target Band (Specifications 3.10.B.4 through 5.10.B.9)
- 3. Shutdown and Control Bank Insertion Limits (Specification 3.10.D)
- 4. Reactor Coolant System Flow Limit (Specification 3.10.J)
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NPO, specifically those described in the following documents:
NSPNAD 8101 A, " Qualification of Reactor Physics Methods for i Applic.ation to PI Units" (latest approved version)
NSPNAD 8102 A, " Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units" (latest approved version)
WCAP 9272 P A, " Westinghouse Reload Safety Evaluation Methodology", July,1985 WCAP 10054 P A, " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code", August, 1985 WCAP-10924 P A. " Westinghouse Large Break LOCA Best Estimate Mnthodology", December, 1988 WCAP 10924 P A, Volume 1, Addendum 4. "Westinghnuse Large Break LOCA Best Estimate Methodology", October,1990 l;
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TS.6.7 5 l XN NF-77 57 (A), XN NF-77 57, Supplement 1 (A), ' Exxon Nuclear Power Distribution Control for Pressurized Water Reactors Phase II", May, 1981
- c. The core operating limits shall be determined such that all l i
applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, ECCS timits, nuclea limits such as shutdown margin, and transient and accident a alysis limits) of l the safety analysis are met. j i
- d. The CORE OPERATINC LIMITS REPORT, including at.y mid cycle. revisions- l or supplements thereto, shall be supplied upon issuance, for each ;
reload cycle, to the NRC Document Control Desk with copies to the !
Regional Administrator and Resident Inspector, ,
B. REPORTABLE EVENTS The following actions shall be takeri for REPORTABLE EVENTS:
- a. The Commission shall be notified by a report submitted pursuant 3 to the requiremeatn of Section 50.73 to 10 CFR Part 50, and '
- b. Each REPORTABLE EVENT shall be reviewed by the Operations Committee and the results'of this review shall be submitted to the Safety Audit Committee and the Vice President Nuclear Generation.
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TS 6.7 6 L
C. Environmertal Reoorts The reports listed below shall be submitted to the Administrator of the appropriate Regional NRC Office or his designate:
1, Annual Radiation Environmental Monitorine Reoort (a) Annual Radiation Environmental Monitoring Reports covering the operation of the program during the previous calendar year shall be submitted prior to May 1 of each year.
(b) The Annual Radiation Environmental Monitoring Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of land use censuses required by Specification 4.10 B.1, If harmful effects or evidence of irreversible damage are detected by.the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. -
(c) The Annual Radiation Environmental Monitoring Reports shall include summarized and tabulated results in the format of Regulatory cuide 4.8, December 1975 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be aubmitted as soon as possible in a supplementary report.
(d) The reports shall also include the following: a summary description of the radiological environmental monitoring program; a map of all sampling locations keyed to a table giving distances and directions from one reactor; and the results of licensees participation in the Interlaboratory Comparison Program, required by Specification 4.10.C.1,
- 2. Environmental Special Reports (a) When radioactivity levels in samples exceed limits specified in Table 4.10 3, an Environmental Special Report shall be subinitted within 30 days from the end of the affected calendar quarter. For certain cases involving long analysis time, determination of quarterly averages may extend beyond the 30 day period. In these cases the potential for exceeding the quarterly limits will be reported within the 30 day period to be followed by the Environmental Special Report as soon as practicable.
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- 3. Other Environmental Reports (non radiolorical. non anuatic)
Written reports for the following items shall be submitted to l the appropriate NRC Regional Administrator: !
- a. Environmental events that indicate or could result in a l significant environmental impact casually related to plant :
operation. The following are examples: excessive bird l impaction; onsite plant or animal disease outbreaks; unusual mortality of any spec!.es protected by the ,
Endangered Species Act of 1973; or increase in nuisance organisms or. conditions. This report shall be submitted I within 30 days of the event and shall (a) describe, analyze, and evaluate the event, including extent and magnitude of1 the impact and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the >
action caken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar ,
components or systems, and (e) indicate the agencies notified and their preliminary responses. -
- b. Proposed changes, test or experiments which may result in a significant increase in any adverse environmental impact which was not previously reviewed or evaluated in the Final Environmental Statement or su; elements thereto. This :
report shall include an evaluattus of the environmental -
impact of the proposed activity and shall be submitted 30 days prior to implementing the proposed change, test or experiment.
D. Soccial Reports Unless otherwise indicated, special reports required by t' e Technical Specifications shall be submitted to the appropriate NRC Aegional Administrator within the time period specified for each report. +
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