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Category:TECHNICAL SPECIFICATIONS
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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 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MAIN 3 YANKEE ATCMIC POWER COMPANY Category Inspection Results C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degradesd tubes or more than 1% of the inspected tubes are defective.
Note: In all inspections, previously degraded tubes must exhibit significant (greater than 104) further wall penetrations to be included in the above percentage calc.ulations.
C. Inspection Frequencies - The above required inservice inspections of ateam generator tubes shall be performed at the following frequencies:
- 1. Inservice inspections shall be performed at intervals of not less than ]
12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not includino the preservice inspection, result in all inspection results falling into the C-1 category or if two coniccutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
- 2. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.10-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at 1 cast once por 20 months. The increase in inspection frequency shall apply until the subsequent inspections meet the conditions specified in C-1 and the interval can be extended to a 40 month period.
- 3. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.10-2 during the shutdown subsequent to any of the following conditions.
(a) Primary-to-secondary tube leaks (not including leaks originating from tube-to-tuce sheet welds) in excess of the limits or Specification 3.14.C.5, ))
(b) A main steam line break or feedwater line break, (c) A seismic occurrence greater than the Operating Dasis Earthquake, or (d) A loss-of-coolant accident requiring actuation of the engineered sarcQuards.
D. Acceptanco criteria
- 1. As used in this Specification.
(a) Imerfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 204, of the nominal tube wall thickness may be con:.idered as imperfections.
61gg 4.10-2 06/11/85 5700L-SEN .
MAINE YANK ] ATOMIC POWEQ COMPANY (b) Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
(c) Degraded Tube means a tube containing imperfections greater than or ]
equal to 20% of the nominal wall thickness caused by degradation. ]
(d) % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
(e) Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
(f) Plugging Limit means 'the imperfection depth at or beyond which the ]
tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal ]
tube wall thickness.
(g) Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of a steam line break, feedwater line break, Operating Basis Earthquake, or a loss-of-coolant accident as specified in 4.10.c.3 above.
(h) Ttbe Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.
(1) Critical Area means an area of the steam generator where degraded ]
and/or defective tubes exist due to a steam generator physical and/or ]
operating characteristic which would promote tube degradation in that ]
Identified area. ]
- 2. The steam generator shall be determined OPERA 0LE after completing the correcponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.10-2.
EXCEPTION The steam generator shall be determined operable without performing 100% ]
tube inspection required by Table 4.10-2 when the first or subsequent ]
sample inspection results are at the C-3 level due to defects in a critical ]
area, provided: )
(a) The critical area (s) are identified and bounded. ]
(b) A 100% inspection of the critical area is conducted. ]
(c) A steam generator tube inspection is conducted for the sample size ]
required by Specification 4.10.0 excluding those tubes and results from ]
the inspection of the critical area (s). ]
4.10-3 06/11/85
[ 5780L-SEN
P,
, , MAIN 3 YANKE3 ATOMIC POWER COMPANY E. Reports
- 1. Following each inservice inspection of steam generator tubes, the 3 number of tubes plugged in each steam generator shall be reported T to the Commission within 15 days.
- 2. The complete results of the steam generator tube inservice inspection shall be included in the "NIS-1 Owners Data Report for Inservice .
- Inspections" for the period in which this inspection was completed.
This report.shall include:
! (a) Nuder and extent of tubes inspected.
I
( (b) Location and percent of wall-thickness penetration for each
! indication of an imperfection.
!- (c) Identification of tubes plugged.
]
4.10-4a 06/11/85 5780L-SFN
MAINE YANNEE ATOMIC POWrl COMPANY Basis: The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or i progressive degradation due to design, manufacturing errors, or
!. inservice conditions that lead to corrosion. Inservice inspection of >
steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures .
can be taken. l The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion and of the steam generator tubes. If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking.
Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations. Plugging will be required for all tubes with imperfactions exceeding the plugging limit of 404 of the tube nominal wall thickness. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
]
In the past, Maine Yankee as well as other licensees have experienced ]
steam generator tube degradation in specific localized areas. The ,
exception permits inspecting 100% of the localized area and a .
representative sample of remaining tubes, when degradation of tubes ]
in the localized area would otherwise cause the inspection results to ]
be classified C-3. ]
/
4.10-6 06/11/85 5780L-SEN
TAIR.E A,10-2 STEAM EPERATOR TLEE. INSPECTION ,
l i iI Ii I I lst SAwtE INSPECTION ll 2nd SAWLE INSPECTION l1 3rd SAWLE INSPECTION l l ll I1 -1 I . I I il i 11 I I l Sample Size l Result 1 Action RegJired iI Result i Action Required iI Result i Action Required I ll I I i 11 l I I ll I i i 11 l 1 l l A minimum of l C-1 1 None !I WA I WA Il WA 1 WA i l ISK Times l l 11 1 11 I I ))-
Iper S. G. l l I ll l l , C-2 Plug defective tubes !l C-1 i None iI WA I WA I I iand inspect additionalil l Plug defactive tubes ll C-1 1 None l l l 12SE tubes in this ll C-2 I and inspect additional lI c-z I Plug aerective tunes I ));
l I
1 I
l IS. G.
l Il ll i ASE tubes in this l-S. G.
ll lI C-3 l Perform action for
-l C-3 result of first I
l
))'
! 1 l l ll 1 II I sample i I I I II l Perform action for iI . I l l l l 11 C 1 C-3 result of first 11 WA l WA I I I I ll I sam le ll l l l l C-3 l Inspect all tubes in Ii All other I ii i i i i i this S.G., plug de- 11 S.G.s are ~ l None i 1. WA I WA I I I l fective ttbes and ll C I ll l l l l l inspect 2SE tubes !I Some S.G.sl Perform action for ll l 1 )), '
I l [ each S.G. ll C-2 but nol C-2. result of second ll N/A I WA l I I I II additionall sample iI l l 1 I I Report to leC as 11 S.G. are 1 ll l l )) ;,
I I I necessary pursuant ll C-3 I ll l 1 ))'
l l l to Specification iI Additionali Inspect all tubes in iI I l )) i I I I 5.6 11 i each S.G. and plug 11 I I ))i i i i li i defective tubes. II I I l l l ll l 11 WA l WA I I ll Report to PHC as l l , ,
l ll e nry pursuant to I l ..
l l 1 ll 1 Specification 5.C il l I ))
S = 3 Wn Percent where N is the number of steam generators in the unit, and n is the number of steam generators inspected ))
during an inspection
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