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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20236T4781998-07-14014 July 1998 Proposed Tech Specs Revising Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing 10CFR20.1302 Requirements ML20216F8951998-04-13013 April 1998 Proposed Tech Specs Re Fuel Storage Pool Water Level ML20216E1841998-03-10010 March 1998 Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry ML20202H5041998-02-10010 February 1998 Proposed Tech Specs Page 5-8,including Specification Re Cold Weather Operations ML20212A6211997-10-20020 October 1997 Proposed Tech Specs Re Permanently Defueled Status of Plant ML20210M5871997-08-15015 August 1997 Proposed Tech Specs Revising Facility Staffing & Training Requirements ML20137S8891997-04-0808 April 1997 Proposed Tech Specs Reducing RCS Flow ML20136B5261997-03-0505 March 1997 Proposed Tech Specs,Requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant 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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M8251999-08-0303 August 1999 Draft License Termination/Amend Plan for Maine Yankee Atomic Power Co ML20206D7981998-11-10010 November 1998 Revised Maine Yankee Odcm ML20237D0671998-08-19019 August 1998 Rev 1 to Maine Yankee Certified Fuel Handler Training & Retraining Program ML20236T4781998-07-14014 July 1998 Proposed Tech Specs Revising Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing 10CFR20.1302 Requirements ML20216F8951998-04-13013 April 1998 Proposed Tech Specs Re Fuel Storage Pool Water Level ML20216E1841998-03-10010 March 1998 Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry ML20202H5041998-02-10010 February 1998 Proposed Tech Specs Page 5-8,including Specification Re Cold Weather Operations ML20212A6211997-10-20020 October 1997 Proposed Tech Specs Re Permanently Defueled Status of Plant ML20210M5871997-08-15015 August 1997 Proposed Tech Specs Revising Facility Staffing & Training Requirements ML20210L9601997-08-15015 August 1997 Certified Fuel Handler Training & Retraining Program ML20137S8891997-04-0808 April 1997 Proposed Tech Specs Reducing RCS Flow ML20135F7261997-03-0707 March 1997 Restart Readiness Plan ML20136B5261997-03-0505 March 1997 Proposed Tech Specs,Requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6641997-02-0707 February 1997 Proposed Tech Specs Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6311997-02-0707 February 1997 Proposed Tech Specs 4.10.C.2 Re SG Tube Surveillance Requirements ML20133N0471997-01-15015 January 1997 Proposed Tech Specs 4.4 Re Containment Testing ML20133G3281996-12-23023 December 1996 Cycle 15 Startup Test Rept Suppl 5 ML20133A7131996-12-19019 December 1996 Proposed Tech Specs 3.13 Re Refueling & Fuel Consolidation Operations & Table 4.2-1 Re Minimum Frequencies for Sampling Tests ML20129F8831996-09-25025 September 1996 Proposed Tech Specs Re Organization Change Affecting Nuclear Safety Audit & Review Committee ML20138F4031996-04-11011 April 1996 Revised Maine Yankee Odcm ML20148C6511994-12-31031 December 1994 Diagnostic Evaluation Team Managers Handbook,Dec 1994, Rev 1 ML20148C6581994-12-31031 December 1994 Guidelines for Diagnostic Evaluation,Dec 1994,Rev 4 ML20128D6761993-01-28028 January 1993 Co ISI Program for Third ISI Interval 921228-021228 ML20127P2471993-01-25025 January 1993 Proposed Tech Specs Change 177 Re Main Yankee Spent Fuel Pool Reracking ML20126B6911992-12-15015 December 1992 Proposed TS 3.19 Re Position Restrictions on Loop Isolation Valves,Safety Injection Header Isolation Valves & Safety Injection Tank Isolation Valves ML20198D0771992-05-0808 May 1992 Proposed Tech Spec 1.4.D, Containment Purge Sys ML20141M1181992-03-24024 March 1992 Proposed TS Spec 1.3 Re Fuel Enrichment Limit in Reactor Core ML20062D2851990-11-0505 November 1990 Proposed Tech Specs Re Removal of cycle-specific Operating Limits ML20058B6071990-10-15015 October 1990 Proposed Tech Specs Modifying 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20059N7671990-10-0101 October 1990 Cycle 12 Startup Test Rept ML20058L9311990-07-30030 July 1990 Proposed Tech Spec Page 5.2-2 Re Manager Qualification for Operations ML20055G3121990-07-10010 July 1990 Proposed Tech Specs Consisting of Proposed Change 155 Re Safety Injection Actuation Sys ML20055E0981990-07-0505 July 1990 Proposed Tech Specs Re Qualification Requirements for Operations Manager ML20055D4651990-02-20020 February 1990 Rev 3 to Procedure 0-07-1, Matl Receipt ML20055D4691989-08-15015 August 1989 Rev 4 to Procedure 0-15-1, Nonconformance Repts (Ncr) ML20235H5581989-02-15015 February 1989 Proposed Tech Specs,Adding Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability & Surveillance Requirements to Sections 3.9 & 4.1 ML20196B5301988-11-22022 November 1988 Proposed Tech Specs Supporting Change 134 Re Main Steam Excess Flow Check Valve & Turbine Valve Testing Frequency ML20206F2341988-11-0808 November 1988 Proposed Tech Spec 1.1, Fuel Storage ML20246H5281988-10-31031 October 1988 Reactor Containment Bldg Integrated Leak Rate Test for Oct 1988 ML20206C2901988-10-26026 October 1988 Proposed Tech Specs,Deleting Offsite & Facility Organization Charts,Figures 5.2-1 & 5.2-2 ML20205M9751988-10-18018 October 1988 Proposed Tech Specs,Modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test Frequency,Per C-E STS ML20204G1191988-08-31031 August 1988 Rev 1 to Procedure 26.1, Offsite Dose Calculation Manual ML20207E2611988-08-0202 August 1988 Errata to Proposed Tech Specs Figure 3.10-4,showing Allowable Unrodded Radial Peak as Function of Cycle Average Burnup for Cycle 11 Operation ML20150E9021988-06-30030 June 1988 Proposed Tech Specs,Consisting of Proposed Change 141,to Reflect Operating Parameters for Cycle 11 ML20150G0531988-03-28028 March 1988 Proposed Tech Specs,Increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235 ML20147G9011988-03-0101 March 1988 Proposed Tech Specs Reflecting Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20155D3801988-02-0101 February 1988 Rev 3 to Procedure 18-340-1, Maine Yankee Simulator Work Order ML20235A8321988-01-0606 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organizational Charts ML20237G2191987-08-10010 August 1987 Co Simulator Certification Test Plan ML20236G5111987-07-30030 July 1987 Proposed Tech Specs,Consisting of Proposed Change 132, Replacing Page 3.10-4 Re Incore Monitoring Sys 1999-08-03
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AUACHMENLB TECHNI. CAL _ SPEC IEICAIION_ CHANGE _PAGES )
E0R_ PROP _0 SED _CHANGEJi0._202 3.13 Refueling and Fuel Consolidation Operations Page 3.131 3.15 Reactivity Anomalies Page 3.151, and !
Table 4.21, Minimum Frequencies for Sampling Tests Page 4.2 2 j 9
l 9701.020071 961219 PDR ADOCK 05000309.
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, 3.13 REEUELING_AND lVEL_ CONS 0LIDATION 0RERATIONS Applicability:
Applies to operating limitations during refueling and fuel consolidation operations. l l
Objective To minimize the possibility of an accident occurring during refueling and fuel consolidation operations that could affect the health and safety of plant personnel l and the public. i
- Specification: )
A. Prior to each refueling a complete checkout, including a load test, shall be conducted on fuel handling cranes that will be used to handle irradiated fuel j assemblies.
B. Irradiated fuel shall not be moved until 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> after the reactor has been made subcritical.
C. Whenever the reactor vessel head is removed and there is fuel in the reactor, the refueling boron concentration shall be maintained in the reactor :
l coolant system and shall be checked by sampling Daily (D) to insure that it I is sufficient to maintain the core 5% delta k/k subcritical.
D. The following conditions shall be satisfied during core alterations or movement of irradiated fuel within the containment:
- 1. The containment equipment hatch must be closed and held in place by a minimum of four bolts when the reactor has been subcritical less than 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />.
- 2. At least one door in the personnel airlock shall be closed when the reactor has been subcritical less than 210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />.
Exception: Both personnel airlock doors may be opened briefly within the 210 hour0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> period to allow passage of long objects through the airlock.
- 3. The containment venting and purge inlet and outlet trip valves shall be closed or be operable and able to isolate the ventilation system in response to high radiation signals. The venting and purge system discharge shall be filtered through the high efficiency particulate air filters and charcoal absorbers.
Exception: The HEPA filters and charcoal absorbers may be bypassed after the reactor has been subcritical for 210 or more hours.
Amendment No. 54r65-73-75-144 3.13 1
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l ' AppGcability:
, Applies to potential reactivity anomalies. )
i- Objective:
To require evaluation of reactivity anomalies within the reactor.
l Specification:
{
Following a normalization of the computed boron concentration as a function of l
~ burnup, the actual boron concentration of the reactor coolant shall be periodically :
compared with the predicted value. The difference between the observed and ,
predicted steady-state concentrations shall be less than the equivalent of 1% of !
-- reactivity. I RemediaLA.ction:
1 The Nuclear Regulatory Commission shall be notified and an evaluation as to the cause of the discrepancy shall be made and reported to the Nuclear Regulatory Commission in accordance with Technical Specification 5.9.1.7.
Basis:
To eliminate possible errors in the calculations of the initial reactivity of the core and ,
the reactivity depletion rate, the predicted relation between fuel bumup and the boron concentration, necessary to maintain adequate control characteristics, must be adjusted (normalized) to accurately reflect actual core conditions. When full power is reached initially, and with the CEA groups in the desired positions, the boron concentration is measured and the predicted curve is adjusted to this point.
As power operation proceeds, the measured boron concentration is compared with the predicted concentration and the slope of the curve relating bumup and reactivity i is compared with that predicted. This process of normalization should be completed i after about 10% of the total core bumup. Thereafter, actual boron concentration can !
.] be compared with prediction and the reactivity status of the core can be periodically l l evaluated, and the occurrence of a discrepancy would be thoroughly investigated i and evaluated. The methods employed in calculating the reactivity of the core vs. ;
bumup, and the reactivity worth of boron vs. burnup, are given in the FSAR. I i
Amendment No. 19, 48.'65. 91 3.15-1
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, , Table 4.2-1 ;
Minimum Frequencies for Sampling Tests l Test Frequency
- 1. Reactor Coolant Gross Activity Determination . At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. ,
Samples ,
Isotopic Analysis for DOSE E@IVALENT I 131 concentra-tion. 1 per 14 days i Radiochemical for 8 -
Determination 1 per 6 months * *
- , Isotopic Analysis for Iodine, Until the spec 111c activity of
. including I 131,1 133, and the primary coolant system is
[ I 135 restored within the limits.
j .- once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, whenever the.
DOSE EWIVALENT I-131 exceeds 1.0 pC1/ gram, and j One Sample between 2 and 6 4 hours following a THERMAL 2
POWER change exceeding 15 percent of the RATED THERMAL :
POWER within a one hour ,
period.
Chemistry (chloride 3 times per week.
and fluoride)
)
Hydrogen Weekly * !
0xygen Prior to heatup above 250 F, and 3 times per week when above 250"F.
Process Radiation Monitor Continuous * *
- 2. Reactor Coolant Boron Boron Concentration H (Power Ops & Hot Standby)
D (Hot Shutdown Transthermal.
Cold Shutdown, Refueling Shutdown & Refueling Ops)
- 3. Refueling Water Tank Boron Concentration Monthly *
- Water Sample Amendment No. 38 d 1 4.2 2