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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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Spec Pages 3.11-2 & 3.11-5 Re Containment Isolation Valves Under Administrative Controls 1998-07-14
[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 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MaineYankee '
ATTACHMENT 4 Proposed Technical Specification 8811210038 SS110s Pf6 ADOCK 05000309 P PDC 0395L-RHS
MaineYankee 1.1 EUIL STORAGE 6pp.llcabili ty:
Applies to the capacity and storage arrangements of the new and spent fuel facility.
s Qbjective:
To describe and define those aspects of fuel storage which relate to the prevention of criticality in the fuel storage facility.
Spacification:
A. The new and spent fuel pool structures inclading fuel racks are designed to withstend the anticipated earthquake loadings as Class I structures. The spent fuel pool is lined with stainless steel to ensure against loss of water.
B. Fuel is stored vertically in racks. The racks are designed to maintain fuel assembly center to center distances that will assure Kerr is less than or equal to 0.95 even with the pool filled with unborated water.
C. Whenever there is fuel in the spent fuel pcol, except for initial new fuel storage, the spent fuel storage pool is filled with water borated to the refueling water boron concentration. This concentration matches that in the reactor cavity and refueling canal during refueling operations.
i D. Spent fuel shipping casks shall not be liftsd over the spent fuel storage pool until all irradiated fuel within ten rows of the cask )
- laydown area has cooled a minimum of 60 days. ]
i E. No more than 1476 standard fuel assemblies are to be stored in permanent spent fuel racks in the spent fuel pool.
F. No more than 121 standard fuel assemblies may b3 temporarily stored in a temporary spent fuel storage rack to be located in the spent fuel cask Idydown area. These are in addition to the 1476 standard fuel assemblies of specification E.
G. No more than 20 standard fuel assemblies may be in consolic'ated form. These are included in the 1476 standard assemblies of specification E.
Bulli Safety analyses, Reference (a) and NRC safety evaluation reports, Rcrevence (b), document the configuration of Haine Yankee's spent fuel rack design, consolidated pin storage design, and temporary storage i contingency design. These reports demonstrate the safety and environmental acceptability of storing any combiaation of standard and i consolidated spant fuel assemblies in the 1176 permanent storage locations together with up to 121 additional standard fuel assemblies in temporary
- storage in the spent fuel cask laydown area.
1.1-1 11/08/88 0395L-RHS
MaincYankee If a 17 1/2 foot long, 7.33 foot diameter spent fuel cask tipped and fell )
into the 10 foot square cask laydown area, it would not impact more than ]
10 rows of fuel assemblies. Analyses conducted in accordance with Standard ]
Review Plan 15.7.5 show that if the assemblies impacted by the cask have )
i cooled a minimum of 60 days, 25% of the part 100 limits will not be exceeded. ]
Therefore, by ensuring that fuel wthin the cask drop area (10 rows from the ]
laydown area) has cooled at least 60 days, 25% of the part 100 limits could )
never be exceeded. ]
Refarences:.
(a) Maine Yankee letter to USNRC dated October 5, 1981, "Maine Yankee Spent fuel Storage Modification - Complete P.eport" with enclosure, as supplemented and amended on February 10, 1982, May 7, 1982, and May 26, 1983.
(b) UNSRC letter to Maine Yankee dat*d June 16, 1982, "Safety Evaluation i and Envrionmental Impact Appraisal Regarding Maine Yanke? Spent Fuel Storage" as supplemented via ijSMC letter to Maine Yankee Vated
- October 22, 1982, "Resolution of Open Items - Safety Evaiuation of i Maine Yankee Spent fuel Storage".
I j
i 4
1.1-2 11/08/P3 0395L-RHS