Amend 42 to Facil Oper Lic DPR-36 Rev Tech Specs Re Radiological & Thermal Effluent Monitoring.Changes Involve Environ Surveillance Prog,Air Particulate Charcoal Gamma Monitoring & Estuary Water Temp MonitoringML20148Q124 |
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Maine Yankee |
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Issue date: |
11/08/1978 |
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From: |
Reid R Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20148Q120 |
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NUDOCS 7811290318 |
Download: ML20148Q124 (10) |
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Similar Documents at Maine Yankee |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20206H1521999-05-0505 May 1999 Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant ML20206G5681999-05-0303 May 1999 Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20204C4561999-03-16016 March 1999 Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20217H4991998-03-30030 March 1998 Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety ML20202D3121997-11-26026 November 1997 Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility ML20216F1291997-08-0808 August 1997 Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee ML20141G6301997-05-19019 May 1997 Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing ML20138G3401997-05-0202 May 1997 Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical ML20058E2561993-11-0505 November 1993 Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves ML20056G9321993-09-0101 September 1993 Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 ML20056F7821993-08-23023 August 1993 Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS ML20127D4881993-01-11011 January 1993 Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements ML20126H6071992-12-29029 December 1992 Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 ML20126C0981992-12-0909 December 1992 Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One ML20059D0381990-08-30030 August 1990 Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator ML20246L4291989-07-14014 July 1989 Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246F6231989-07-10010 July 1989 Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation ML20245D4341989-04-24024 April 1989 Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability ML20245D4451989-04-24024 April 1989 Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels ML20207L6021988-10-11011 October 1988 Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 ML20155B4501988-09-27027 September 1988 Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core ML20154A1311988-09-0707 September 1988 Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC ML20196G6801988-06-23023 June 1988 Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 ML20151W5731988-04-26026 April 1988 Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20149H2691988-02-17017 February 1988 Amend 103 to License DPR-36,changing Tech Specs to Update Figures 5.2.-1 & 5.2-2 in Tech Spec 5.2 Organization Depicting Plant Offsite & Facility Organization, Respectively ML20196C4211988-02-0909 February 1988 Amend 102 to License DPR-36,revising Tech Spec 3.10.C.3.1.1 to Reflect Revised LOCA Monitoring Limits to Be Used When in-core Monitoring Sys Inoperable ML20235M4591987-09-29029 September 1987 Amend 101 to License DPR-36,requiring Written Administrative Controls for Implementation of Process Control Program ML20216J0161987-06-25025 June 1987 Amend 99 to License DPR-36,revising Tech Specs 5.9.1.6 & 5.9.1.7,allowing Addl Time for Filing Supplemental Dose & Meteorological Summary Repts & Ensuring Refs to Other Tech Specs Correct ML20234B1691987-06-25025 June 1987 Amend 100 to License DPR-36,revising Tech Specs to Conform W/Generic Ltr 83-37 Requirements Re RCS Vent Sys ML20215E9211987-06-15015 June 1987 Amend 98 to License DPR-36,modifying Tech Specs to Reflect Revised LOCA Limits Using Revised Delta P Injection Penalty Factor During Reflood Phase of LOCA & Limiting Axial Power Shapes ML20214J5961987-05-20020 May 1987 Amend 97 to License DPR-36,deleting Requirement for Emergency Diesel Generator Testing in Event That Any Component of One Train of ECCS Becomes Inoperable ML20206U9001987-04-0909 April 1987 Amend 96 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 10 Reload Core by Modifying steady-state Peak Linear Heat Rate to Reflect Acceptable Fuel Design Limits for Prevention of Centerline Melting ML20197D4181987-03-26026 March 1987 Amend 94 to License DPR-36,revising Tech Specs Re Operability & Surveillance for New Noble Gas Effluent monitors,high-range Monitors & Water Level Monitors in Containment ML20212N6911987-03-0404 March 1987 Amend 93 to License DPR-36,adding Administrative Controls to Limit Overtime of Staff Personnel & Allow Dual Role of Senior Reactor Operator & Shift Technical Advisor ML20210V1531987-02-0909 February 1987 Amend 92 to License DPR-36,revising Tech Specs to Increase Fuel Enrichment Limit to 3.5 Weight Percent U-255 for Cycle 10 & Beyond ML20207M8151987-01-0606 January 1987 Errata to Amend 91 to License DPR-36,including Revised Table 4.2-2, Min Frequencies for Equipment Tests ML20215E7851986-12-11011 December 1986 Amend 91 to License DPR-36,revising Tech Specs,Including Restating Spec 3.14B for Clarity & Deleting Ref to Cycle 7 & Dividing Section 3.15 Re Reactor Power Anomalies Into Spec & Remedial Action ML20197B6001986-10-27027 October 1986 Amend 90 to License DPR-36,revising Tech Specs to Incorporate Specific Requirements for Iodine Spiking Into Annual Rept Per Generic Ltr 85-19 & to Delete Primary Coolant Iodine Activity Rept ML20195D3931986-05-27027 May 1986 Amend 89 to License DPR-36,adding Addl Manual Containment Isolation Valves & Blowdown & Body Vent Valves on Instrument Lines to List of Manual Containment Isolation Valves That May Be Repositioned ML20140C8821986-03-17017 March 1986 Amend 88 to License DPR-36,requiring Operability of Three Independent Steam Generator Auxiliary or Emergency Feedwater Pumps to Supply Emergency Feedwater to All Three Steam Generators ML20137Y7231986-03-0404 March 1986 Amend 87 to License DPR-36,changing Tech Specs to Require Monthly Operability Testing of turbine-driven Auxiliary Feedwater Pump ML20137A0391985-12-31031 December 1985 Amend 86 to License DPR-36,modifying Tech Specs to Assure Compliance W/App I,10CFR50,50.36 & 50.34a to Ensure Releases of Radioactive Matl to Unrestricted Areas During Normal Operation Remain ALARA ML20137Y8421985-09-30030 September 1985 Amend 85 to License DPR-36,modifying Tech Specs to Reflect Cycle 9 Power Distributions,Insertion Limits & Peaking Factors & Describe Max Reactor Inlet Temp Used in Modified Safety Analyses ML20134K8651985-08-20020 August 1985 Amend 84 to License DPR-36,changing Tech Specs to Require More Extensive Insp of Steam Generator Tubes in Critical Areas ML20062E2511982-07-21021 July 1982 Tech Spec Page 5.2-3 Figure 5.2-2) Establishing Separate Training Dept & Other Organization Changes.Page Inadvertently Omitted from Original Transmittal ML20062A0961982-07-14014 July 1982 Amend 61 to License DPR-36,increasing Required Number of Operable Safety Injection Actuation Signal Sensors & Establishing Training Dept & Other Organizational Changes ML20148Q1241978-11-0808 November 1978 Amend 42 to Facil Oper Lic DPR-36 Rev Tech Specs Re Radiological & Thermal Effluent Monitoring.Changes Involve Environ Surveillance Prog,Air Particulate Charcoal Gamma Monitoring & Estuary Water Temp Monitoring 1999-05-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206H1521999-05-0505 May 1999 Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant ML20206G5681999-05-0303 May 1999 Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20204C4561999-03-16016 March 1999 Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20236T4711998-07-14014 July 1998 Application for Amend to License DPR-36,consisting of Proposed Change 209,amending TS to Revise Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing Requirements ML20216F8831998-04-13013 April 1998 Application for Amend to License DPR-36,consisting of Proposed Change 208,revising TS to Base LCO for Fuel Storage Pool on Revised Analysis for Fuel Handling Accident & on New Analysis for Radiological Shielding During Movement of Fuel ML20217H4991998-03-30030 March 1998 Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety ML20202D3121997-11-26026 November 1997 Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility ML20212A6021997-10-20020 October 1997 Application for Amend to License DPR-36,consisting of Proposed TS Change 207,reflecting Permanently Defueled Status of Plant ML20211H6691997-09-30030 September 1997 Application for Amend to License DPR-36,eliminating Conditions,No Longer Appropriate in Permanently Defueled Condition ML20210M5801997-08-15015 August 1997 Application for Amend to License DPR-36,consisting of TS Change 206,revising TS Re Facility Staffing & Training ML20216F1291997-08-0808 August 1997 Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee ML20141G6301997-05-19019 May 1997 Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing ML20138G3401997-05-0202 May 1997 Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical ML20136B5161997-03-0505 March 1997 Application for Amend to License DPR-36,requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6551997-02-0707 February 1997 Proposed TS Change 203 to License DPR-36,revising TS Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6261997-02-0707 February 1997 Proposed TS Change 204 to License DPR-36,requesting one-time Extension of SG Tube Surveillance Interval as Specified in TS 4.10.C.2 ML20133A7011996-12-19019 December 1996 Application for Amend to License DPR-36,requesting Rev to Boronometer Operability Requirement & Reactor Coolant Boron Sampling ML20058E2561993-11-0505 November 1993 Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves ML20056G9321993-09-0101 September 1993 Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 ML20056F7821993-08-23023 August 1993 Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS ML20127P2191993-01-25025 January 1993 Application for Amend to License DPR-36,consisting of Proposed TS Change 177 to Allow Increase in Number of Spent Fuel Assemblies Stored in Spent Fuel Pool from 1,476 to 2,019.Rev 0 to Licensing Rept... Encl ML20127D4881993-01-11011 January 1993 Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements ML20126H6071992-12-29029 December 1992 Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 ML20126B6821992-12-15015 December 1992 Proposed TS Change 176 to License DPR-36,modifying TS 3.19 & 4.6 for Consistency W/Change in Normal Operating Position of LPSI motor-operated Isolation Valves from Closed to Open ML20126C0981992-12-0909 December 1992 Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One ML20198D0701992-05-0808 May 1992 Proposed TS Change 166 to License DPR-36,revising Section 1.4 to Eliminate Ref to Containment Air Recirculation Sys from TS 1.4.D, Containment Purge Sys ML20141M1121992-03-24024 March 1992 Application for Amend to License DPR-36,consisting of TS Proposed Change 165,revising Fuel Enrichment Limit & Allowing Radial & Axial Zoning of Enrichment Up to 3.95 Weight Percent U-235 ML20062D2801990-11-0505 November 1990 Application for Amend to License DPR-36,consisting of Proposed Change 151 Re Removal of cycle-specific Limits in Response to Generic Ltr 88-16 ML20058B5941990-10-15015 October 1990 Proposed Change 156 Requesting Amend to License DPR-36, Modifying Tech Spec 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20059D0381990-08-30030 August 1990 Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator ML20058L9271990-07-30030 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,revising Page 5.2-2 Re Manager Qualification Requirements for Operations ML20055G3101990-07-10010 July 1990 Application for Amend to License DPR-36,consisting of Tech Spec Change 155 Re Safety Injection Actuation Sys ML20055E0951990-07-0505 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,modifying Tech Specs Re Qualification Requirements for Operations Manager ML20246L4291989-07-14014 July 1989 Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246F6231989-07-10010 July 1989 Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation ML20245D4451989-04-24024 April 1989 Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels ML20245D4341989-04-24024 April 1989 Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability ML20235H5401989-02-15015 February 1989 Application for Amend to License DPR-36,consisting of Proposed Change 146,amending Tech Spec Sections 3.9 & 4.1 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability ML20196B5261988-11-22022 November 1988 Application for Amend to License DPR-34,consisting of Proposed Change 134 Re Main Steam Excess Flow Check Valve. Amend Modifies Tech Spec 4.6 Re Periodic Testing by Extending Specified Surveillance Testing Interval ML20206F2281988-11-0808 November 1988 Application for Amend to License DPR-36,modifying Tech Spec 1.1, Fuel Storage. Fee Paid ML20205T2091988-11-0202 November 1988 Application for Approval to Leave Inplace,Slightly Contaminated Soil Next to Reactor Water Storage Tank. Radiological Assessment Encl.Fee Paid ML20206C2571988-10-26026 October 1988 Application for Amend to License DPR-36,amending Tech Spec Section 5.2 to Delete Offsite & Facility Organization Charts,Per Generic Ltr 88-06.Fee Paid ML20205M9611988-10-18018 October 1988 Application for Amend to License DPR-36,consisting of Proposed Change 133,modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test from Once Every 2 Wks to Monthly.Fee Paid ML20207L6021988-10-11011 October 1988 Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 ML20155B4501988-09-27027 September 1988 Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core ML20154A1311988-09-0707 September 1988 Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC ML20150E8971988-06-30030 June 1988 Application for Amend to License DPR-36,consisting of Proposed Change 141,revising Tech Specs to Reflect Cycle 11 Operation.Cycle 11 Core Performance Analysis Rept Encl.Fee Paid ML20196G6801988-06-23023 June 1988 Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 ML20151W5731988-04-26026 April 1988 Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20150E4071988-03-24024 March 1988 Application for Amend to License DPR-36,increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235.Fee Paid 1999-05-05
[Table view] |
Text
. _ _ _ _ _ _ _ _ _ _ _ - _
/ % UNITED STATES )
y* .
f' NUCLEAR REGULATORY COMMISSION
]
g WASHINGTON, D. C. 20555 l
%, ...../ MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment *h, 42 i License No. DPR-36
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The applications for amendment by Maine Yankee Atomic Power Company (the licensee) dated November 7 and December 1, 1977, comply with the standards.and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I, 1
l B. The facility will operate in confomity with the applications, I the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized )
by this amendment can be conducted without endangering the health 1 and safety of the public, and (ii) that such activities will be 1 conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public-and j l
E. The issuance of this amendment is in accordance with 10 CPR Part !
51 of the Comission's regulations and all applicable requirements i have been satisfied.
l i
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- 7 8112 90 3/ $ f
F-I l
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B.(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
1 (b) Technical Specifications '
The Technical Specifications contained in Appendices i A and B, as revised through Amendment No. 42, are I hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its 1 issuance.
FOR THE NUCLEAR REGULATORY COMISSION
) Y Robert N. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: November 8, 1978 k-
(? .
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 42 r FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise-the Appendix A Technical Specifications as follows:
Remove Pages Insert New Pages j 4.8-2 & 4.8-3 4.8-2 & 4.8-3 Revise the Appendix B Technical Specifications as follows:
Remove Page Insart Page 1.6 1.6-1 Fig. 1.6-1 Fig. 1 6-1 The changed areas on the revised pages are indicated by marginal 1tnes, 1
6 r
F A . .
TABLE 4.8-1 %
MAINE YANKEE q
ENVIRONMENTAL SURVEILLANCE PROGRAM
(
1.m FREQUENCY ANALYSIS SAMPLE )"'"l"2 ?
weekly gross beta y Air Particulate 9 quarterly composite gamma spectroscopy }!
' fh weekly gamma spectroscopy Charcoal Filter 9 ,5 17' monthly integrated gamma dose Direct Radiation two TLD readouts a.
.)
monthly composite gamma spectroscopy },
Estuary ut.er 3 quarterly composite tritium , j p
tritium, gamma spectroscopy [,f 4 quarterly Fresh Water Ra-226 h9 once per 3 years II 2 annually (harvest) gamma spectroscopy, Sr-89-90** ;
Food Crop I-131 on green leafy portion te of vegetables j Marine Biological 9 quarterly gamma spectroscopy Media (Fish, Lenthic) S r-89-90**
Algae quarterly gamma spectroscopy [l 3
Sr-89-90** y semiannually gamma spectroscopy /
Bottom Sediments 4
- Milk *** 2 monthly gamma spectroscopy, I-131 [
Sr-89-90 {
monthly composite
- gamma spectroscopy Sr-89-90**
weekly
- I-131 twice during gamma spectroscopy g vegetation 4 Sr-89-90** t growing season V
monthly composite tritium C/g Precipitation 2 t
- . Per forned wheneve r plant related Cs-137 concentration is 10X non-plant .-
related Cs-137 concentration.
- Further, the licensee will ascertain by a semi-annual survey whether milk cows have been introduced at localities closer than the above two dairies. If positive results are found and the milk cow owner agrees with.the licensee on a reasonable environmental surveillance program, 3 1
milk from these sources will also be sampled and analyzed as above. /
1-131 in milk will be sampled with a sensitivity of 0.5 picoeuries per . ,
H liter at the time of sampling with an overall crror of +25 percent.
The analysis for I-131 will be completed within'8 days of taking the sample.
' Amendment'No. , 42 4.8-2
,a y
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TABLE 4.8-2' '(
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AIR PAP.TliTLA!E CilARCOAL GAMMA MCNITORING STATIONS
- Station Distance From Direction Designation- Location Plant (miles) from Plant f f
AP1 Bath' 6.8 SW
.AP2 Montsweag 1.7 NW AP3 Eaton Farm 0.3 W
-AP4 Baily Farm House 0.4 NE AP5 Mason Station 3.0 NE l AP6 Edgecomb Fire House 3.5 ENE j AP7 Westport Fire. House 1.1 S AP8 Harrisons 4.0 SW
-AP9 Dresden 12.4 NNW TABLE 4.8-3 ESTUARY WATER SAMPLE STATIONS
Station Distance From Direction g Il Designation Location Plant.(miles) from Plant !
WEll Plant Intake ** ' -- -- i WE12 Plant Outfall** -- --
l WE20 Kennebec Rive r*** 6.8 SW ')
CDeviations from the sampling schedule are permitted if specimens are unavailable due to automatic sampling equipment malfunctions or other icgitimate reasons. If automatic equipment malfunctions, a reasonable j effort shall be made to complete. corrective action prior to the end of l the next sampling period. All deviations from the sampling schedule 3 i
shall be reported annually. If an estuary. water sampler is inoperable, I weekly grab samples.will be substituted for continuously composited 6 samples.
C* Continuously compositing sampler, analytical frequencies as per Table j 4.8-1. t o** Grab samples,' weekly collection--frequency. .l 1
1
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4.8-3
~
Amendmert No. ,42:
1.6 MONIf0 RING ESTUARY WATER TEMPERATURE Appl icabil it y : Applies to t':e enuarine waters in the vicinity of the Maine Yankee Atomic Power Station.
Obj ect ive: To provide estuarine temperature data during plant operation.
Speci ficati on: A minimum of four of the estuarine sensors currentiy in us' l
by the Maine Yankee Environmental Studies Department sili continue to be used during the monitoring program after plant startup. Figure 1.6-1 shows the approximate location of the sensors.
Basis: The location of the temperature recording stations extends from Cheney's Landing in the Sheepscot River in the north throughout Montsweag Bay to Harrison's (Westport) in the south. Water temperatures at these stations are recorded at one ft below the water surface and at 20 ft below MSL.
Graphs of the data are made from the maximum daily temperatures at each station to indicate warming or cooling trends taking place as a result of plant operation. Maintaining the location of the sensors at their present locations will also allow j comparison of water temperatures taken before and after plant j operation, although the natural variability of water temperature at a given location is such that precise conparisons will be of littic value, only trend data.
Amendment No. 42 1.6-1
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Amendment No. 42
j 9 UNITED STATES j
- - *i NUCLEAR REGULATORY COMMISSION l WASHINoToN, D. C. 20665 ;
APPRAISAL OF CHANGES IN THE RADIOLOGICAL l AND THERMAL EFFLUENT MONITORING PROGRAMS TECHNICAL SPECIFICATIONS FOR MAINE YANKEE ATOMIC POWER STATION DOCKET N0. 50-309 Introduction By letter dated December 1,1977, Maine Yankee Atomic Power Company (licensee) proposed changes to the Environmental Technical Specifications (ETS), Appendix B to Facility Operating License No. DPR-36, for Maine Yar.kee. This change would reduce the scope of the estuary temperature monitoring program from the present seven stations to four stations.
In a separate action, by letter dated November 7,1977, the licensee proposed an Appendix A Technical Specification change to delete the requirements for weekly grab samples of estuary water at Mason Station (EWS 1), Bailey Point (EWS 2), Long Ledge (EWS 3), and Harrison's Dock (EWS 4). Replace-ment sampling would be a continuously composited sample from the plant in- ,
take. Also, the licensee proposed that the requirement for continuously composited samples from the Sasanoa River (EWS 5 - central location) be replaced by a requirement for weekly grab samples from the Kennebec River.
We have evaluated the proposed changes.
Evaluation Temperature Monitoring Program ETS Section 1.6 currently requires a minimum of seven continuous water temper- '
ature monitoring stations during plant operation to allow comparisons of water temperatures before and after plant operation. The t .'ature data collected during this-program have been submitted in the Mair.c R,kee Environmental ,
Studies - Annual Reports 2 through 4 (1970-1972) and, tnereafter, in the Maine Yankee Environmental Surveillance Reports Nos. 1 through 10.
Upon start-up in 1972, the Maine Yankee plant discharged its condenser cool-ing water to the surface of Montsweag Bay creating a mixing zone of 200 acres.
This surface discharge mode dictated the areal extent of the temperature mon-itoring program. Beginning in July 1975, a submerged diffuser was utilized i to dissipate the heated effluent in order to meet more stringent state regu- l 1ations. This resulting mixing zone is 25 acres and is controlled by Sections 1.1 and 1.2 of the ETS.
The licensee has proposed to eliminate stations 1, 6 and 8 from the present
, temperature monitoring system, contending that while such an extensive l
temperature monitoring program was appropriate for the former surface dis-charge. mode, it has little relevance for the present heat dissipation system L
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and stations 1, 6 and 8 presently contribute nothing to a better understand- l ing of bay' temperatures or the thermal discharge. According to the licensee, the objective of Section l.6 can be fully met with the monitoring stations that would remain as a result of this change.
We have reviewed the licensee's request, the semiannual surveillance reports, and the laboratory design of the submerged diffuser. A major consideration ;
in the elimination of these stations is that their placements reflected !
the' expected influence of the thermal plume before the installation of the~ 1 submerged thermal diffuser and the removal of the causeway across Cowseagan
~ l Narrows. From the data it is clear that station 6 is not influenced by the j thermal effluent from the plant. Station 5 exhibits similar temperature i trends and can serve as a background station; therefore, deletion of station i 6 is acceptable. l Station 1 is near stations 2 and 3 and indicates very similar temperature !
trends to those two stations. In addition, station 8 is near station 4 and field data indicate that no additional information is provided by station j
- 8. Therefore, deletion of stations 1 and 8 is acceptable. .l
- 2. Radiological Samples i
Several years of monitoring have indicated no significant differences in i the. radiological content of samples from the .four subject grab sample loca- I tions which are upstream and downstream from the plant. This similarity !
is expected to continue due to the tidal . flushing experienced in the !
Montsweag Bay and Back River. Therefore, we agree that these four sample l locations can be replaced by one location representative of Montsweag Bay / !
Back River water. The plant's circulating water intake stream is a repre- l sentative location. In addition, the use.of a continuously composited ,
sample will more readily permit detection of short term fluctuations in l the radiological content of tiontsweag Bay. j Reversible flow in the Sasanoa River' has resulted from the replacement' of the Westport Island Causeway near the plant. It is possible that the level of radioactivity in the Sasanoa River could 'be influenced by plant operation, !
- resulting in an inadequate control' sample. Therefore, the Kennebec River i provides a better control (background) sample location. Also, difficul ty !
has been experienced.in maintaining a continuously composited sampler on !
the Sasanoa River. ' Extreme environmental conditions such as. cold tempera- !
' tures, winter ice jams, currents and tides limit effective operation of a )
continuous sampler. The radionuclide content of the Kennebec River is not subject-to rapid fluctuations in radioactivity; therefore, a weekly grab sample is acceptable..
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Based on the above, we find the proposed changes in sampling locations and techniques acceptable.
It is expected that due to certain environmental conditions several of the required samples each year may not be available. Therefore, the licensee has proposed that a footnote be added to the Technical Specifications to allow deviations from the required sampling frequency if samples are unavail-able due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling or other legitimate reasons. If the unobtainable sample is due to sampling equipment malfunction, every reasonable effort is required to complete corrective action prior to the end of the next sampling period.
All deviations shall be documented in the annual report to the NRC. We find this proposed change acceptable.
Dated: November 8,1978