ML15313A160

Yankee ISFSI - Biennial Update to the Final Safety Analysis Report

ML15313A160
Person / Time
Site:	Yankee Rowe
Issue date:	10/08/2015
From:	Norton W Yankee Atomic Electric Co
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
BYR 2015-031
Download: ML15313A160 (80)

Text

~YANKEE 1 ATOMIC ELECTRIC COMPANY 49 Yankee Road, Rowe, Massachusetts01367 October 8, 2015 BYR 2015-03 1 10 CFR 50.71(e)(4) and 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 Yankee Atomic Electric Company Yankee Nuclear Power Station Independent Spent Fuel Storage Installation NRC License Nos. DPR-3 and SFGL-13 (NRC Docket Nos.50-029 and 72-31)

Su~bject: Biennial Update to the Yankee Nuclear Power Station Final Safety Analysis Report Pursuant to the requirements of 10 CFR 50.7 1(e)(4) and 10 CFR 50.4, Yankee Atomic Electric Company (YAEC) provides the December 2014 and October 2015 Revisions of the Yankee Nuclear Plant Station (YNPS) Final Safety Analysis Report (FSAR) (Enclosures 1 and 2). These revisions address the changes made to the YNPS FSAR, since the submittal of the last biennial update on October 23, 2013 (Reference 1). of this letter provides a summary and rationale for the changes to the YNPS FSAR.

This letter contains no commitments.

If you have any questions regarding this submittal, please do not hesitate to contact Brian Smith at (413) 424-5261 ext. 303.

I state under penalty of perjury that the foregoing is true and correct. Executed on October 8, 2015.

Wayne Norton YAEC President and Chief Executive Officer

~L{35

Yankee Atomic Electric Company BYR 2015-031l/October 8, 2015/Page 2 Attachments and Enclosures - Summary of Proposed Changes to the Yankee Nuclear Power Station Final Safety Analysis Report - Yankee Nuclear Power Station Final Safety Analysis Report, December 2014 Revision - Yankee Nuclear Power Station Final Safety Analysis Report, October 2015 Revision References

1. Letter from W. Norton (YAEC) to Document Control Desk (NRC), Biennial Update of the Final Safety Analysis Report, dated October 23, 2013 (BYR 2013-033).

cc: D. Dorman, NRC Region I Administrator R. Powell, Chief, Decommissioning Branch, NRC, Region 1 J. Goshen, NRC Project Manager J. Giarrusso, Planning, Preparedness & Nuclear Section Chief, MEMA J. Cope-Flanagan, Assistant General Counsel, MDPU J. Reyes, State of Massachusetts Office of the Attorney General

ATTACHMENT 1 TO BYR 2015-031

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT

ATTACHMENT 1 TO BYR 2015-031

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision Section # Proposed Change Reason for Change 12/20 14 507.5.1 The FSAR was modified to state: The change to the YNPS FSAR involves External radiation dose will be the removal of specific details regarding monitored, as required by ISFSI the use of TLDs and direct reading procedures and instructions. dosimeters that is detailed in the applicable site procedure (i.e., RP-3, Personnel The discussions regarding the use of Radiation Monitoring). This procedure is thermoluminescent dosimeters maintained in accordance with the (TLDs) and direct reading requirements of 10 CFR 20 and the Quality dosimeters, and the fr~equency of Assurance Program. The change to the processing the TLDs are eliminated. FSAR does not modify the methods of These details are defined in the compliance established in RP-3.

applicable site procedure (i.e., RP-3). ____________________

10/20 15 100.1 Replaced "new storage facility" with The ISFSI is no longer a new facility. It "Independent Spent Fuel Storage has been in operation for a number of Installation (ISFSI)" years.

10/20 15 229.1 Replaced "Massachusetts Electric" This change eliminates an unnecessary with "commercial distribution" description regarding the owner of the line that supplies power to the on-site electrical.

The owner of the line is subject to change.

The use of a generic description of the line is appropriate.

10/2015 305 Replaced "[to" with "to" This change resolves a typographical error.

10/2015 406 The ESAR states "In each case, there The FSAR stated that there were no were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAG-MPG FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAG-MPG FSAR that result in of the postulated explosion event." radiological consequences that are within limits. NAG-MPG FSAR Section 11.2.3.3 defines that there are no radiological consequences for thle postulated explosion event in the NAG-MPG FSAR. Note: the NAG-MPG FSAR is maintained in accordance with 10 CFR 72.48. In addition, the YNPS 10 GFR 72.212 Evaluation Report establishes compliance with the NAG-MPG Gertificate of Gompliance (GoG) and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.2 12 Evaluation Report is also maintained in accordance with 10 CFR 72.48.

1 of 3

ATTACHMENT 1 TO BYR 2015-03 1

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision Section #I Proposed Change Reason for Change 10/2015 407 The FSAR states "In each case, there The FSAR stated that there were no were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAC-MPC FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAC-MPC FSAR that result in of the postulated explosion event." radiological consequences that are within limits (e.g., Blockage ofHalf of the Air Inlets, Small Release of Radioactive Particulate from the Canister Exterior, Fire Accident, Blockage Event, VCC Tip Over, and Tornado/Tornado Missile. Note: the NAG-MPG FSAR is maintained in accordance with 10 CFR 72.48. In addition, the YNPS 10 CFR 72.212 Evaluation Report establishes compliance with the NAC-MPC CoG and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.212 Evaluation Report is also maintained in

________________________accordance with 10 CFR 72.48.

10/2015 408 The FSAR states "In each case, there The FSAR stated that there were no*

were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAG-MPG FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAG-MPG FSAR that result in of the postulated explosion event." radiological consequences that are within limits (e.g., Blockage of Half of the Air Inlets, Small Release of Radioactive Particulate from the Canister Exterior, Fire Accident, Blockage Event, VCG Tip Over, and Tornado/Tornado Missile. Note: the NAG-MPG FSAR is maintained in accordance with 10 GFR 72.48. In addition, the YNPS 10 GFR 72.2 12 Evaluation Report establishes compliance with the NAG-MPG CoG and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.212 Evaluation Report is also maintained in

____________accordance with 10 GFR 72.48.

10/20 15 All The word files for the YNPS FSAR This is an administrative change.

were merged. This permitted the YNPS FSAR to be reformatted by removing page breaks and replacing section based page numbers with document based page numbers. The

____________section numbers were retained.

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ATTACHMENT 1 TO BYR 2015-03 1

SUMMARY

OF CHANGES TO THlE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT These changes did not:

• Adversely affect an FSAR described design function,

• Involve a change to a procedure that adversely affects how FSAR described SSC design functions are performed or controlled.

• Involve revising or replacing an FSAR described evaluation methodology that is used in establishing design bases or used in the safety analysis.

• Involve a test or experiment not described in the FSAR.

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ENCLOSURE 1 TO BYR 2015-03 1 YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT DECEMBER 2014 REVISION

YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision 12/14

YNPS FSAR RV 21 REV. 12/14 TABLE OF CONTENTS Page SECTION 100 100 SPENT FUEL MANAGEMENT PLAN...................................................... 100-I SECTION 200 229 ELECTRICAL SYSTEM ....................................................................... 229-1 232 FIRE DETECTION SYSTEM................................................................. 232-1 256 METEOROLOGICAL TOWER .............................................................. 256-1 257 ThNDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) .................. 257-1 SECTION 300 300 ENVIRONMENTAL - SITE CHARACTERISTICS ....................................... 300-1 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)...................... 301- 1 302 HYDROLOGY.................................................................................. 302-1 303 GEOLOGY AND SEISMOLOGY ............................................................ 303-1 304 WATER SUPPLY ............................................................................... 304-1 305 EFFLUENTS.................................................................................... 305-1 306 ENVIRONMENTAL RADIOLOGICAL STATUS.......................................... 306-1 SECTION 400 400 TRANSIENTS .................................................................................. 400-1 401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY................... 40 1-1 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS ....................................... 403-1 404 LOSS OF SUPPORT SYSTEM EVENTS.................................................... 404-1 405 FIRE EVENTS .................................................................................. 405-1

YNPS FSAR REV. 12/14 406 EXPLOSION EVENTS ........................................................................ 406-1 407 EXTERNAL EVENTS......................................................................... 407-1 408 SPENT FUEL STORAGE EVENTS.... ...................................................... 408-1 SECTION 500 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN ............................ 500-1 501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN ..................... 50 1-1 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES.................. 502-1 503 TRAINING PROGRAM....................................................................... 503-1 504 DEFUELED TECHNICAL SPECIFICATIONS............................................. 504-1 505 PROCEDURES ................................................................................. 505-1 506 MAINTENANCE PROGRAM................................................................ 506-1 507 RADIATION PROTECTION PROGRAM................................................... 507-1 508 RADIOACTIVE WASTE MANAGEMENT................................................. 508-1 509 TESTS ........................................................................................... 509-1 512 SECURITY PLAN.............................................................................. 512-1 513 FIRE PROTECTION ............................................................................ 513-1 514 QUALITY ASSURANCE PROGRAM....................................................... 514-1 515 EMERGENCY PLAN.......................................................................... 515-1

YNPS FSAR REV. 12/14 LIST OF FIGURES Figure No. Title 3 00-1 Historical Site Boundary 3 00-1 300-2 Current 10 CFR Part 50 Licensed Site Boundary 300-2

YNPS FSAR RV 21 REV. 12/14 100 SPENT FUEL MANAGEMENT PLAN 100.1 Background This section documents the YNPS spent fuel management plan in accordance with 10OCFR50.54(bb)

(Reference 100-1). This regulation also requires a funding plan for spent fuel storage. The spent fuel storage cost estimate and funding plan are presented in the PSDAR (Reference 100-4).

YAEC contracted with NAG International to transfer the spent fuel from the spent fuel pit to a dry cask storage facility. The location of the new storage facility is at the south end of the YNPS site (see Figure 300-1). There are 533 fuel assemblies stored in 15 NAG Multi-Purpose Canisters (MPCs) on the ISFSI pad. These fuel assemblies were discharged from the reactor between 1972 and 1992. There were also a number of failed fuel pins that were consolidated into a Reconfigured Fuel Assembly (RFA) which was then transferred to a dry cask. The Greater than Class C (GTCC) radioactive waste in the form of canisters containing reactor vessel internals (core baffle) and dross material and having the same external dimensions as fuel assemblies have also been transferred to a NAG-MPG. Several miscellaneous GTGC radioactive items also are stored in the NAG-MPG containing the GTCC (e.g. neutron sources, fuel assembly cage components, fixed incore detector wires, etc.).

YAEC is currently seeking accelerated acceptance of YNPS's spent fuel by the Department of Energy in accordance with the current fuel disposal contract. The Department of Energy's current position is that they have not yet determined whether priority will be accorded shutdown reactors, or if priority is granted, under what specific circumstances it might be granted. For planning purposes, fuel shipments are assumed to be completed in 2031. This projection is based on the Department of Energy's Acceptance Priority Ranking, Annual Capacity Report, and an extrapolation beyond the 10 year Department of Energy outlook. For planning purposes, YAEC's current cost estimates for 1) decommissioning the ISFSI and 2) the management of spent nuclear fuel and GTCC waste assume storage of fuel in the dry storage facility until 2031.

100.2 Special Nuclear Material Control Information regarding Special Nuclear Material Control is available for inspection by authorized personnel.

100-1

YNPS FSAR RV 12/14 REV. 21 REFERENCES 100-1 59-FR-10267, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, March 4, 1994.

100-2 YRP 43 5/92, Spent Nuclear Fuel Storage Study Report and Recommendations, B. W. Holmgren, J. M. Buchheit, R. A. Mellor to J. K. Thayer, October 9, 1992.

100-3 YRP 303/93, Impact of Wet Spent Fuel Storage on Decommissioning, P. A. Rainey to R. A. Mellor, July 15, 1993.

100-4 Yankee Nuclear Power Station Post-Shutdown Decommissioning Activities Report.

100-2

X'NPS FSAR RV 21 REV. 12/14 229 ELECTRICAL SYSTEM 229.1 Description The on-site electrical system is powered by a Massachusetts Electric Line. The system consists of a transformer, auto throw-over switch, distribution panels and the necessary associated equipment to support ISFSI operations. Also see Sections 257 and 404.

229-1

YNPS FSAR RV 12/14 REV. 21 232 FIRE DETECTION SYSTEM 232.1 Description The Fire Detection System provides the equipment needed to detect fires that could occur in structures supporting the ISFSI. The system consists of detectors, and the necessary associated instrumentation.

The Fire Detection System provides coverage in the Gatehouse, Administration Building and within the Instrument Enclosure Building at the ISFSI. Fire Protection Program requirements are described in Section 513.

232-1

YNPS FSAR RV 12/14 REV. 21 256 METEOROLOGICAL TOWER 256.1 Description There is no Meteorological Tower associated with the ISFSI. If general meteorological information is needed it can be obtained from the internet.

256-1

YNTPS FSAR RV 12/14 REV. 21 257 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 257.1 Description The Independent Spent Fuel Storage Installation (ISFSI) provides dry cask storage of spent nuclear fuel and Greater-Than-Class-C (GTCC) waste generated at the YNPS. Dry cask storage of spent nuclear fuel is conducted under the general license provisions of 10OCFR72, Subpart K and 10OCFR30. The NAC International, Inc., Multi-Purpose Canister (MPC) system (Docket No. 72-.

1025), which received a certificate of compliance in April 2000 (Reference 257-1), is used at the ISFSI.

As a Part 50 Licensee, YAEC is also authorized to store GTCC waste at the ISFSI in accordance with the requirements of 10OCFR3O. The GTCC waste is stored in the NAC-MPC system and was evaluated in accordance with the requirements of I0CFR72.48 and l 0CFR72.21 2 to allow co-placement of the NAC-MPC system containing GTCC waste at the YAEC ISFSI. The NAC-MPC Transport Safety Analysis Report (SAR) describes the GTCC waste Transportable Storage Canister (TSC) design and analysis.

The ISFSI is designed to store a combination of up to 18 NAC-M'PC dry fuel or GTCC waste storage casks. It is located in the southwest corner of the site (Figure 300-2) and consists of a concrete pad, access road, security fences, temperature monitoring instrumentation, lighting, security, ISFSI Instrumentation Enclosure.

The ISFSI facility has 16 Vertical Concrete Casks (VCCs). Each VCC contains a Transportable Storage Canister (TSC). The TSCs contain either spent fuel or GTCC waste.

The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during storage. The VCC is a reinforced concrete structure with a carbon steel inner liner. Each VCC is approximately 160 inches in height, has an outside diameter of approximately 128 inches and weighs approximately 155,000 lbs. Each VCC has 4 inlet vents evenly spaced around the bottom of the VCC. There are also 4 outlet vents spaced evenly around the top of the VCC, offset by 45 degrees in order to provide a non-planar path for the natural circulation of air around the TSC and to minimize radiation streaming.

The TSC is a stainless steel circular cylindrical shell with a welded bottom plate. It has an outside diameter of approximately 71 inches and is approximately 123 inches in height. The TSC can accommodate up to 36 Yankee Class spent fuel assemblies. The TSC may also contain one or more Reconfigured Fuel Assemblies (RFAs), which are designed to hold Yankee Class spent fuel rods as intact or damaged fuel or fuel debris. An RFA can accept up to an equivalent of 64 full length spent fuel rods in an 8 by 8 array. The stainless steel RFA container has the same external dimensions of a standard fuel assembly. The NAC-MPC also has a damaged fuel configuration to provide storage for Yankee fuel classified as damaged. This configuration provides four stainless steel damaged fuel cans located in the four corner positions of the basket. A damaged fuel can may contain either an intact or a damaged spent fuel assembly but may not contain individual fuel rods not in an assembly alTay. The primary function of the damaged fuel can is to confine fuel material within the can and to facilitate handling and irretrievability. The placement of the damaged fuel can is restricted to the four corner positions of the fuel basket. The weight of a fully loaded TSC is approximately 55,000 lbs.

257-1

YNPS FSAR RV 12/14 REV. 21 The VCC Temperature Monitoring System is designed to monitor the thermal performance of each concrete cask. The system is comprised of a network of thermocouples at the outlet vents of all the casks and at four different points for ambient temperature that can be monitored either locally, at the ISFSI Instrument Enclosure or remotely in the Gatehouse.

Radiation monitoring using Thermoluminesent Dosimeters (TLDs) is in place to demonstrate compliance with 10CFR72.104 and 40CFR190.

The ISFSI pad is within a protected area located to the south of the general site area of the YNPS.

The ISFSI pad is a reinforced structural concrete pad that was designed to store and support the loaded VCCs. The pad is approximately 48 feet wide by 160 feet long. The east end of the pad is elevated approximately 30 inches above the grade of the access road to facilitate the loading/removal of the VCCs from the heavy-haul trailer. The VCCs are moved by using air pads and a specially rigged fork lift vehicle (cask primary mover).

The ISFSI Enclosure Building is a free standing building, measuring approximately 12 feet wide by 15 feet long by 10 feet in height, located within the protected area to the west of the ISFSI pad. The ISFSI Enclosure Building houses the temperature monitoring panel, I/O racks, transformers, Uninterruptible Power Supplies (UPS), communications, fire detection and other JSFSI and security related equipment.

The ISFSJ protected area is fenced, monitored by security, and has alarms to prevent unauthorized access. Access to the ISFSI area is controlled in accordance with the YNPS ISFSI Physical Security P lan.

257.2 Status The ISFSI construction is complete. Spent nuclear fuel and GTCC waste transfer is complete. The YNPS ISFSI contains 15 NAC-MPC Spent Fuel Storage Casks in addition to 1 NAC-MPC Cask that contains GTCC waste.

REFERENCES 257-1 Letter, NRC to NAC International, Inc., dated March 17, 2000, Certificate of Compliance for the NAC International, Inc., Multi-Purpose Canister (MPC) System (TAC No. L22907).

257-2

YNPS FSAR RV 12/14 REV. 21 300 ENVIRONMENTAL - SITE CHARACTERISTICS 300.1 Demography YNPS is located in the Berkshire Hills of Franklin County in Rowe, Massachusetts. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir.

The area surrounding the site is mostly wooded with very steep gradients on both sides of the Deerfield River.

The YNPS Historical Site Boundary is provided in Figure 300-1.

The YNPS Current 10 CFR Part 50 Licensed Site Boundary is provided in Figure 300-2.

300.2 Geography and Land Use The population density in the rural area surrounding the YNPS site is low. Within one mile of the site, for example, the population is 48 (based on 1989 Massachusetts municipal census counts). The populations of the two closest towns, Rowe and Monroe, are 347 and 96, respectively. The nearest population center of 25,000 or more is Pittsfield, Massachusetts, located about 21 miles south-west of the site. The regional population is expected to remain virtually unchanged over the next decade.

Land use near the site is made up of a few farms and some commercial businesses. The centers of Rowe and Monroe have small, mixed clusters of local businesses, municipal buildings, and residences, with homes scattered throughout the area. There is no large industrial activity within five miles of the site; the only industry in the area is the YNPS and several hydroelectric facilities along the Deerfield River.

The nearest highway and railroad are each about five miles south of the site. The closest airport is in North Adams, Massachusetts, about ten miles west of the site.

300-1

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YNPS FSAR RV 21 REV. 12/14 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)

The site lies in the prevailing westerlies, the belt of eastward moving air that is found in middle latitudes. Many storms pass over Massachusetts compared to other parts of the United States. This is a result of extensive air masses originating at higher and lower latitudes. The three major air mass types that affect the site are cold, dry, subartic air from Canada; warm, moist air from the Gulf of Mexico; and cool, damp air from the North Atlantic Ocean.

The hills on either side of the site rise about 1000 feet above ground level within one mile and extend from 12 miles north to 8 miles south southeast of the site. This feature affects the winds.

There is, for instance, a high frequency of occurrence of "channel flow" up and down the Deerfield River valley. Also, night -time drainage flow down the east side of the river valley occurs frequently.

Normal daily temperatures range from 10°F in January to 80°F in July. Recorded extreme temperatures for the site region are -25°F and 98°F. Thunderstorms occur about 28 days per year; the annual flash density of ground lightning strikes is four flashes per square kilometer.

The site design wind speed (defined as the "fastest-mile" wind speed at 30 feet above the ground with a 100 year return period) is 80 mph. Hail storms occur about two days annually and freezing rain about 12 days per year. The maximum radial ice thickness expected for the region is 1.25 inches. Mean annual snowfall at the site totals 100 inches, with maximum snow depth on the ground totaling about 40 inches.

30 1-1

YNPS FSAR RV 12/14 REV. 21 302 HYDROLOGY The site is located on the east bank of the Deerfield River adjacent to Sherman Reservoir. The drainage area upstream of the site is characterized by a dendritic pattern, is 236 square miles, and has an average annual rainfall of between 40 and 50 inches.

The Deerfield River flow is highly regulated b two large, upstream hydroelectric reservoirs. The average long-term flow near the plant is 738 ft /sec.

Bedrock in the region is not a significant source of groundwater nor are there major bedrock aquifers within the site area, The direction of groundwater flow under the site is from the recharge areas on the slopes surrounding the plant toward the Deerfield River.

302-1

YNPS FSAR RV 12/14 REV. 21 303 GEOLOGY AND SEISMOLOGY The regional bedrock geology is complex;, bedrock age ranges from 100 million to over one billion years old and is comprised of mostly a mosaic of metamorphic and igneous rocks. The youngest deposits are glacial soils, 10 to 12 thousand years old. Most volcanic and sedimentary rock in the area are now metamorphosed.

The site is situated on dense Wisconsinian-aged glacial till. YNPS structures are founded on this till, which ranges from 0 to 140 feet thick across the site. Bedrock under the till is part of the lower Cambrian Hoosac formation and consists of quartz-albite-biotite gneiss and a rusty gneiss in adjacent areas. Underlying these are garnet schist and a layered gneiss with some dolomitic marble, with the latter units belonging to the lower Cambrian or older Cavendish formation. A south-plunging anti-eline, whose axis is just east of the site, defines local bedrock structure.

Site bedrock is hard, internally welded metamorphic rock, not subject to significant deterioration.

Bedrock fracturing is not a prominent structural feature of this bedrock; outcrops exhibit either no joints or minor, discontinuous joint surfaces. Fracture pattern analysis of site vicinity joints, joint sets, and faults show no anomalous trends for fractures. This suggests the absence of any through-going zones of post-metamorphic faulting or shear.

The site is in the Western New England Fold Belt province. It borders the Adirondack Uplift province to the west, the Valley and Ridge province to the southwest, and the New York Recess to the south. The Southeast New England Platform and Merrimack Synclinorium occur to the east and northeast, respectively.

Regional seismic events are very infrequent and do not cause surface faulting. Only two events in the province were greater than Intensity V (MM). These events were 125 miles and 210 miles from the site. The site seismic design level for the ISFSI is contained in the NAC-MPS FSAR.

REFERENCE:

NAC-MPC-FSAR, Multi-Purpose Canister System, Docket No. 72-1025 303-1

YNPS FSAR RV 12/14 REV. 21 304 WATER SUPPLY Potable water is supplied by an on site bedrock well.

3 04-1

YNPS FSAR RV 12/14 REV. 21 305 EFFLUENTS There are no liquid effluents from the ISFSI.

Stormwater and surface water runoff follows various swales, ditches, and culverts [to the Deerfield River or Sherman Pond that were created during final site grading.

Surface water use downstream from the site is mostly for recreation and sport fishing, with limited irrigation. Water supply for the municipalities within five miles downstream of the plant is from private wells. The closest public water supplies are well fields 20 to 25 miles downstream of the site.

305-1

YNPS FSAR RV 12/14 REV. 21 306 ENVIRONMENTAL RADIOLOGICAL STATUS 306.1 Radiological Environmental Monitoring Program The Yankee Quality Assurance Program establishes the requirements for the Radiological Environmental Monitoring Program as defined in the YN-PS Off-Site Dose Calculation Manual (Reference 306-1). The purpose of the program is to monitor the radiation in the environs of the ISFSI.

REFERENCES 306-1 YNPS Off-Site Dose Calculation Manual.

306-2 Yankee Nuclear Power Station's License Termination Plan 306-1

YNPS FSAR Rv 12/14 Rev. 21 400 TRANSIENTS 400.1 General Overview Decommissioning activities for the Yankee Rowe Site are complete, with the exception of those areas associated with the ISFSI. All fuel and GTCC material has been transferred to dry fuel storage and is located at the ISFSJ. The NAC-MPC FSAR contains the design basis safety analysis for the NAC-MPC system components in use at the Yankee-Rowe ISFSI.

400-1

YNPS FSAR RV 21 REV. 12/14 401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY With the completion of decommissioning of the Yankee Nuclear Power Station and the passive storage of spent nuclear fuel and GTCC waste at the ISFSI, the potential for radiological and industrial safety events which could effect site personnel or the public is minimized. The ISFST structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste.

This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met. Radiological events are minimized or the consequences are mitigated through the implementation of the Radiation Protection Program (Section 507) and the Emergency Plan (Section 515). Industrial safety events are minimized by implementing the site safety program for site activities.

The primary objective of the Radiation Protection Program is to protect workers and visitors to the site from radiological hazards from ISFSI operations. Activities conducted during ISESI operations that have only a small potential for exposure of personnel to either radiation or radioactive materials and it will be managed by qualified individuals who will implement program requirements in accordance with established procedures. Radiological conditions wilt be monitored and evaluated on a routine basis to maintain radiation exposures to unrestricted areas as far below specified limits as is reasonably achievable. Radiation protection training will be provided to individuals classified as occupationally exposed to ensure that they understand and accept the responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

The Emergency Plan defines an on-site emergency response capability. This capability includes removal of personnel from an affected area, including site evacuation, if necessary. The plan is implemented by ISFSI personnel.

Implementation of these programs ensures that potential radiological and industrial safety events will be sufficiently minimized and mitigated to not warrant further consideration in this analysis.

401-1

YN'PS FSAR RV 12/14 REV. 21 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS With the completion of decommissioning of the Yankee Nuclear Power Station and the transfer of fuel and GTCC material to the ISFSI for storage until ownership is transferred to DOE, the potential for the creation of events with radiological consequences is significantly reduced.

None of the ISFSI structures, systems or components contain surface contamination that could result in the creation of a significant radiological event. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste. This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met.

403-1

YNPS FSAR RV 12/14 REV. 21 404 LOSS OF SUPPORT SYSTEM EVENTS Electric power is provided to support ISESI operations. Loss of this system could potentially affect many ISFSI areas and support facilities simultaneously; however, the support system is not quality or safety related.

Loss of Off-Site Power Off-site power is used to energize the ISFSI Systems, Structures and Components (SSCs).

Back-up power sources such as site UIPS Units and the Security Diesel Generator will be maintained to support Gatehouse and ISFSI operations.

The public health and safety are not adversely affected by a loss of off-site or back-up power event.

404-1

YNPS FSAR RV 12/14 REV. 21 405 FIRE EVENTS A fire event could affect several ISFSI systems, structures and components simultaneously.

Combustible materials can be ignited by external ignition sources (e.g., oxyacetylene torches).

Adequate levels of the following fire protection features will be maintained through implementation of the Fire Protection Program (Section 513) minimizing the potential of occurrence of a fire:

• Fire detection equipment and systems.

• Personnel training and qualification programs.

• Fire Protection Program procedures.

• Control of transient combustible materials and ignition sources.

The public health and safety are not adversely affected by a fire event.

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YNPS FSAR RV 12/14 REV. 21 406 EXPLOSION EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, natural and manmade events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

All YN-PS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MP Cs). Chapter 11 of the NAC-MLPC FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

REFERENCES NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025 406-1

YNPS FSAR RV 12/14 REV. 21 407 EXTERNAL EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, external events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site.

The material for the VCCs and ISFSI storage pads are not expected to be highly activated.

However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MPCs). Chapter 11 of the NAC-MPC FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

REFERENCE NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

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YNPS FSAR RV 21 REV. 12/14 408 SPENT FUEL STORAGE EVENTS 408.1 Events All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MPCs). Chapter 11 of the NAC-MPC PSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

The YNPS developed and maintains a 10CFR72.212 Evaluation Report, which concludes that all site-specific parameters found at the YNPS site are bounded by the NAC-MPC design basis analyses performed for the NAC-MPC system.

REFERENCE NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

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YNPS FSAR RV 12/14 REV. 21 500) ADMINISTRATION OF TH:E DECOMMISSIONING PLAN 500.1 Regulatory Basis for Administration of the Decommissioning Plan Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report)" (Reference 500-6), encourages licensees with an approved Decommissioning Plan to "extract the pertinent detail from the Decommissioning Plan and submit a PSDAR update in the format and content specified by the regulatory guide." As a result, information from the approved YNPS Decommissioning Plan that was incorporated into the FSAR has since been extracted, updated and relocated to the PSDAR. The PSDAR is maintained as a stand-alone document in accordance with 10 CFR 50.82(a)(7).

REFERENCES 500-1 Letter, YAEC to USNRC, dated December 20, 1993.

500-2 Draft Regulatory Guide DG-1005, "Standard Format and Content For Decommissioning Plans for Nuclear Reactors."

500-3 Letter, USNRC to YAEC, dated February 14, 1995.

500-4 Letter, YAEC to USNRC, dated August 22, 1995.

500-5 NUREG-05 86, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, August 1988.

500-6 Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report, dated July 2000."

500-1

YNPS FSAR RV 12/14 REV. 21 501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN Decommissioning Cost Estimate This information has been extracted, updated and relocated to the PSDAR.

Decommissioning Funding This information has been extracted, updated and relocated to the PSDAR.

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YNPS FSAR RV 12/14 REV. 21 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES YAEC Commitment Yankee Atomic Electric Company (YAEC) is committed fully to compliance with the existing license and applicable regulatory requirements during all phases of YNPS of ISFSI operations.

YAEC's commitment to the safe storage of fuel and GTCC will be accomplished with diligence and quality. Corporate principles, policies, and goals will be followed to ensure performance excellence, management competence, and high standards in every facet of 1SF SI operations.

Goals The primary goal of the YNPS is to safely store spent nuclear fuel and GTCC material until it can be removed from the site. While achieving this primary goals, YAEC will conduct all ISFSI operations consistent with applicable regulations.

YAEC Organization and Functions The YAEC organizational structure that will be implemented as described in Section 1 of the Yankee Quality Assurance Program (QAP). The functions are described in site administrative' procedures.

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YNPS FSAR RV 12/14 REV. 21 503 TRAINING PROGRAM YAEC will maintain a training program commensurate with ISFSI operational activities. The training program, in conjunction with other administrative programs and controls, will ensure that qualified individuals are available to operate and maintain the ISFSI in a safe manner. The training programs will be based on job performance requirements.

Access Training Initial and requalification access training will be provided to designated personnel as required by ISFSI procedures.

Radiation Worker Training Initial and requalification radiation worker training will be provided to designated personnel as required by ISFSI procedures.

Specific Job Training YNPS training programs will assure the following:

• Personnel responsible for performing activities are instructed as to the purpose, scope, and implementation of applicable controlling procedures.

• Personnel performing activities are trained as appropriate, in the principles and techniques of the activity being performed.

• The methods of implementing the training programs are documented.

Training Records Training records will be maintained and retained in accordance with administrative procedures.

REFERENCES 503-1 NYR 93-149, NRC Partial Exemption fr'om the Training Rule, 10CFR5Q.120 (TAG No. M87 168), M. B. Fairtile (USNRC) to J. M. Grant (YAEC), November 19, 1993.

503-2 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment #157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

503-1

YNPS FSAR RV 12/14 REV. 21 504 DEFUELED TECHNICAL SPECIFICATIONS The Deflieled Technical Specifications was initially approved on December 23, 1992 and has been maintained with additional changes to reflect the current condition of the site. Reference the Deflieled Technical Specifications for information related to the License and facility requirements.

504-1

YNPS FSAR REV. 21 RV 12/14 505 PROCEDURES ISFSI Operating Procedures The ISFSI Operating Procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures, utilized by ISFSI personnel for the conduct of operations, are contained in the ISFSI Procedures Manual and are available for inspection.

Emergency Procedures The Emergency procedures are comprised of the Emergency Operating Procedures. These procedures are revised, reviewed and controlled in accordance with the Yankee Quality Assurance Program.

The Emergency Operating Procedures have been developed to provide instructions to the ISFSI personnel. These procedures provide ISFSI personnel with the guidance needed to respond to emergency events and provide instructions that assist in mitigating an event and its consequence(s) to the ISFSI, site personnel, the public and the environment.

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YNPS FSAR RV 21 REV. 12/14 506 MAINTENANCE PROGRAM The Maintenance Program is designed to ensure continued system reliability for those systems used to support dry cask storage at the YNPS ISFSI. The program is implemented through administrative and maintenance procedures. These procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures are utilized for the conduct of maintenance activities and are available for inspection.

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YNPS FSAR Rv 12/14 Rev. 21 507 RADIATION PROTECTION PROGRAM 507.1l Introduction YNPS intends to maintain essential elements of the Radiation Protection Program, that were implemented successfully during its 31 year operating life and subsequent decommissioning, to apply to ISESI operations activities. Changes to the program will be made as necessary to meet the needs of ISFSI operations.

The Radiation Protection Program has undergone and continues to undergo inspections and audits from both the NRC and the YAEC Quality Assurance responsible individual as required by the Yankee QAP. The purpose of these reviews is to ensure that the program complies with the Code of Federal Regulations, applicable regulatory guidance documents, and industry standards. YAEC is committed to maintaining a high level of performance and to enhancing the quality of the Radiation Protection Program throughout the YNPS ISFSI operations.

The YN-PS Radiation Protection Program for site closure will continue to be implemented through existing YNPS ISFSI procedures and instructions.

This section of the FSAR presents an overview of the Radiation Protection Program that will be implemented for ISFSI operations.

507.2 Management Policies 507.2.1 Management Policy Statement YAEC is committed to the safe operation of the YNPS ISFSI. The primary objective of the Radiation Protection Program is to minimize the actual and potential exposure of workers, visitors, and general public to radiation. YAEC and its contractors will provide sufficient qualified staff, facilities, and equipment to conduct radiologically safe ISFSI operations. YAEC will continue to comply with regulatory requirements, radiation exposure limits, and radioactive material release limits. In addition, YAEC will make every effort to maintain radiation exposures as low as is reasonably achievable (ALARA). The ALARA philosophy will be incorporated into all ISFSI operations and will have full management support.

YAEC requires good radiation work practices as a condition of employment. Each radiation worker is responsible for performing work in a radiologically safe manner, consistent with the standards of conduct described in the Radiation Protection Program ISFSI procedures and instructions.

507-1

YNPS FSAR Rv 12/14 Rev. 21 This management policy will continue to be communicated to all radiation workers through Site Access and Training and will continue to be incorporated into all applicable ISFSI procedures and instructions.

507.2.2 Administrative Policy YAEC will ensure that activities conducted during ISFSI operation will be managed by qualified individuals who will perfonri program operations in accordance with established procedures and instructions. Radiological hazards will be monitored and evaluated on a routine basis to maintain radiation exposures as far below specified limits as is reasonably achievable. Each element of the Radiation Protection Program will be defined and implemented using written ISFSI procedures and instructions. Radiation protection training will be provided to all occupationally exposed individuals to ensure that they understand and accept their responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

YAEC management will ensure that work specifications, designs, and work packages involving potential radiation exposure or handling of radioactive materials incorporate effective radiological controls.

Radiation protection records will be prepared and maintained using high standards. of accuracy, traceability, and legibility to meet the requirements of regulatory agencies and company procedures.

507.2.3 ALARA Policy YAEC is committed to maintain the ALARA concept. All activities at YNPS involving radiation and radioactive materials will be conducted such that exposure of employees, contractors, and the general public to radiation is maintained as low as is reasonably achievable. This determination will consider the current state of technology and the economics of improvements in relation to their benefit (i.e., reduction of dose).

Appropriate ALARA considerations will be incorporated into ISFSI operation activity planning and design activities at an early stage to allow full consideration of reasonable alternatives. All design modifications will be reviewed to ensure that ALARA was incorporated into the activities.

507.2.4 Regulatory Compliance Policy YAEC is committed to maintain the Radiation Protection Program in compliance with the requirements of the Code of Federal Regulations and, to the extent practical, information contained in industry standards, regulatory guides, and other guidance documents. The Radiation Protection Program is assessed against all new regulatory guidance and modified as necessary.

507-2

YNPS FSAR Rv 12/14 Rev. 21 507.3 Radiation Work Permits (RWP)

Radiation Work Permits will continue to be used to administratively control designated radiological work activities. The primary function of the RWP is to allow authorized activities to be conducted in a safe manner and with radiologically sound practices. The permit documents the work description, the worker names, the radiological conditions, and the radiological precautions and requirements. The RWP implements the ALARA concept and establishes any necessary ALARA Controls.

An ISFSI procedure presents the requirements for generating and using RWP's.

507.4 Area Definitions and Postings An TSFSI procedure describes the requirements for radiological postings. The purpose of the postings is to advise workers of radiological hazards that may be encountered in the areas.

Informational postings may also be used to provide additional radiological instructions to workers.

Each worker is responsible for the observance of the area postings and compliance with the indicated requirements.

507.5 External Dosimetry 507.5.1 General Considerations External radiation dose will be monitored, as required by ISFSI procedures, and instructions. [

507.5.2 Monitoring Whole Body Dose All radiation workers are required to wear external radiation monitoring devices in accordance with ISFSI procedures and instructions. These dosimetry requirements are specified on a Radiation Work Permit.

507.5.3 Dosimetry Quality Control The dosimetry processing laboratory will be accredited by the National Institute of Standards and Technology (NIST) under the National Voluntary Laboratory Accreditation Program (NVLAP) for dosimetry.

507.6 Radioactive Material Controls The Radiation Protection Program establishes radioactive material controls that ensure the following:

• Prevention of inadvertent radioactive material release to uncontrolled areas.

• Assurance that personnel are not exposed inadvertently to radiation from radioactive materials.

Materials will be released if no discemnable plant-related activity is detected within the capability of the survey methods utilized. Any radioactive material that is shipped from the site is handled in 507-3

YNPS FSAR Rv 12/14 Rev. 21 accordance with guidance provided in YNSP ISFSI procedures and instructions, which will ensure compliance with applicable NRC and Department of Transportation requirements.

507.7 Surveillance Routine radiological surveys in compliance with the requirements of 10CFR2O will be performed to evaluate radiological conditions in support of ISFST operational activities. YNPS ISFSI procedures and instructions will be used to implement the surveys.

507.8 Instrumentation A sufficient inventory and variety of operable and calibrated portable, radiological instrumentation will be maintained on site to allow for effective measurement and control of radiation exposure and radioactive material and to provide back-up capability for inoperable equipment. Equipment will be capable of measuring the range of gamma, beta, alpha and neutron dose rates expected.

Instrumentation will be calibrated at prescribed intervals or prior to use against certified equipment having known valid relationships to nationally recognized standards. A YNPS ISFSI procedure or instruction will be used to control the use of radiation protection instrumentation.

507.9 Review and Audit To ensure the Radiation Protection Program is effectively implemented and maintained, an organized system of reviews and audits will continue to be implemented during ISFSI Operations in

• accordance with the Yankee Quality Assurance Program.

507.10 Radiation Protection Program Performance Analysis YNPS ISFSI Corrective Action procedure will be used to evaluate the causes of unacceptable performance, to initiate corrective actions. An annual assessment of the Radiation Protection Program wvil] be performed. This process will be used to address the following types of deficiencies:

• Work activities generating unnecessary radiation exposure.

• Procedural actions resulting in unacceptable radiological performance.

• Unacceptable radiological work practices resulting in unnecessary radiation exposure.

• Activities violating Radiation Work Permit instructions, postings, and radiation protection implementing procedures and instructions.

507-4

YNPS FSAR REV.

RV 12/14 21 508 RADIOACTIVE WASTE MANAGEMENT The decormmissioning of YNPS required the handling of a large volume of radioactive materials to reduce residual radioactivity to a level permitting release of the site for unrestricted use in preparation to complete the partial site release of the License to the ISFSI. With the completion of decommissioning of the Yankee Nuclear Power Station and the storage of fuel and GTCC at the ISFSI there is only a small potential to generate radiological material that will have to be managed as radioactive waste until the decommissioning of the ISFSI. The YAEC will continue to maintain programmatic controls within the Yankee Quality Assurance Program to ensure that federal and state regulations and disposal site requirements would be satisfied should the need arise for radioactive waste management. The YNPS radioactive waste management program would be implemented through the Radiation Protection Program (Section 507).

During the decommissioning of the ISFSI, the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

REFERENCES 508-1 58-FR-34947, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, June 30, 1993.

508-2 Yankee Nuclear Power Station Off-site Dose Calculation Manual.

508-3 Yankee Quality Assurance Program 508-1

YNPS FSAR RV 12/14 REV. 21 509 TESTS Tests may be performed to ensure the continuous, safe, and efficient operation of equipment necessary to support safe fuel storage. The various types of tests are those conducted in accordance with the QAP and governing applicable engineering practices and standards (ASME, IEEE, ISA, etc.), or those based on good engineering judgement and operational experience.

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YNPS FSAR RV 12/14 REV. 21 512 SECURITY PLAN The "Physical Security Plan for Yankee Rowe Independent Spent Fuel Storage Installation" provides the requirements and measures to ensure the safe storage of spent nuclear fuel at the Yankee Rowe ISFSI. Procedures have been developed to implement the Security Plan and Program to ensure requirements are fully achieved.

YNPS access control requirements are established and are presented in an administrative procedures.

REFERENCES 5 12-1 BYR 92-077, Defueled Security and Training and Qualification Plans, J. K..Thayer to M. B. Fairtile (USNRC), August 11l, 1992.

5 12-2 BYR 92-102, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), October 22, 1992.

512-3 NYR 92-194, Exemptions From Certain Requirements of 10CFR73.55 For The Yankee Nuclear Power Station (YNPS) (TAC No. M84267), M. B. Fairtile to J. M. Grant, November 24, 1992.

512-4 BYR. 2000-068, Proposed Amendment to YNPS Security Plan, B. Wood (YAEC) to NRC, dated October 12, 2000.

5 12-5 NYR 2002-023, YNPS - Issuance of Amendment and Exemption from Requirements of 10OCFR73.55 (TAC No. MB0209), J. Hickman (NRC) to J. Kay (YAEC), dated March 13, 2002.

5 12-6 NYR 2012-027, Response to Request for Exemption from Specific Requirements of 10 CER 73.55 (TAC No. L24500), D. W. Weaver (NRC) to R. Mitchell (YAEC), dated September 21, 2012.

5 12-1

YNPS FSAR RV 21 REV. 12/14 513 FIRE PROTECTION A Fire Protection Plan has been developed to minimize any potential impacts on the ISFSI from fire related events. This Fire Protection Plan has been incorporated into the ISFSI set of Procedures and its implementation is supported by other fire protection procedures.

Administrative controls are established for controlling materials and events that could create potential fire hazards at the ISFSI.

The onsite incipient fire response (utilizing fire extinguishers) is adequate to protect the facility until off-site assistance provided by the Town of Rowe arrives. The Rowe Fire Department is available within a 30-minute response time.

Fire detection capabilities will remain in place to protect those facilities associated with the ISFSI, REFERENCES 5 13-1 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment 157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

5 13-1

YNPS FSAR RV 12/14 REV. 21 514 QUALITY ASSURANCE PROGRAM Yankee Atomic Electric Company (YAEC) has developed and implemented a comprehensive Quality Assurance Program to assure conformance with established regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) and accepted industry standards. The participants in the Yankee Quality Assurance Program (QAIP) assure that the storage of spent fuel and GTCC at the Yankee Nuclear Power Station is performed in a safe and effective manner. All remaining applicable operational and administrative requirements that were contained in the YNPS Defueled Technical Specifications have been relocated to the QAP.

The QAP complies with the requirements set forth in Appendix B of 10OCFR Part 50, along with applicable sections of the Updated Final Safety Analysis Report (I-FSAR) for the license application.

The QAP is also established, maintained and executed to comply with the requirements of 10OCFR7 1, Subpart H, and 10OCFR72, Subpart G for the storage and transportation of spent nuclear fuel and high level waste under the provisions of a General License contained in these parts.

The QAP is submitted periodically to the NRC in accordance with 10CFR50.54(a).

REFERENCES 5 14-i License No. DPR Yankee Nuclear Power Station 514-2 10OCFR Part 50 Appendix B; Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants 514-1

YNPS FSAR RV 12/14 REV. 21 515 EMERGENCY PLAN The Defueled Emergency Plan for YNPS was approved by the NRC and issued on October 30, 1992.

There are no longer any events (radiological or non-radiological) that could occur at the site outside of the ISFSI that could cause activation of'the Defueled Emergency Plan. Therefore on March 3, 2005, Revision 12 to the Emergency Plan was issued which eliminated all facets of the Plan not related to the ISFSI, and the Plan was re-titled ISFSI Emergency Plan.

On October 26, 2006, Revision 14 (Maj or) was issued eliminating the remaining power plant and decommissioning accidents from the ISFSI Emergency Plan and the Plan was retitled "Emergency Plan".

The Emergency Plan is implemented through the use of Emergency Operating Procedures and administrative procedures which are referenced in the Plan. The Emergency Plan is formally audited as part of the Quality Assurance Program.

5 15-1

ENCLOSURE 2 TO BYR 2015-03 1 YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT OCTOBER 2015 REVISION

YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision 10115

YNPS FSAR REV. 10/15 TABLE OF CONTENTS Page SECTION 100 100 SPENT FUEL MANAGEMENT PLAN ........................................................... 1 SECTION 200 229 ELECTRICAL SYSTEM............................................................................ 2 232 FIRE DETECTION SYSTEM ...................................................................... 2 256 METEOROLOGICAL TOWER.................................................................... 2 257 INJDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)........................ 2 SECTION 300 300 ENVIRONMENTAL - SITE CHARACTERISTICS ............................................. 5 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER) ............................ 5 302 HYDROLOGY....................................................................................... 6 303 GEOLOGY AI"D SEISMOLOGY.................................................................. 6 304 WATER SUPPLY ................................................................................... 7 305 EFFLUENTS ......................................................................................... 7 306 ENVIRONMENTAL RADIOLOGICAL STATUS............................................... 7 SECTION 400 400 TRANSIENTS ........................................................................................ 8 401 EXVENTS AFFECTING OCCUPATIONAL HEALTH ANT) SAFETY ........................ 8 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS ............................................. 8 404 LOSS OF SUPPORT SYSTEM EVENTS ......................................................... 9 405 FIRE EVENTS........................................................................................ 9 406 EXPLOSION EVENTS.............................................................................. 9 Page i of iii

YNPS FSAR REV. 10/15 407 EXTERNAL EVENTS ............................................................................... 10 408 SPENT FUEL STORAGE EVENTS................................................................ 10 SECTION 500 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN................................. 12 501 DECOMMISSIONING COST ESTIMATE ANT) FUNDING PLAN ......................... 12 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES...................... 12 503 TRAINING PROGRAM........................................................................... 13 504 DEFUELED TECHNICAL SPECIFICATIONS................................................. 14 505 PROCEDURES ..................................................................................... 14 506 MAINTENANCE PROGRAM.................................................................... 14 507 RADIATION PROTECTION PROGRAM....................................................... 15 508 RADIOACTIVE WASTE MANAGEMENT ............................................... i..... 18 509 TESTS ............................................................................................... 19 512 SECURITY PLAN.................................................................................. 19 513 FIRE PROTECTION ............................................................................... 20 514 QUALITY ASSURANCE PROGRAM .......................................................... 20 515 EMERGENCY PLAN.............................................................................. 21 Page ii of iii

YNPS FSAR RV 10/15 REV. 01 LIST OF FIGURES FIGURE NO. TITLE 300-1 Historical Site Boundary 300-2 Current 10 CFR Part 50 Licensed Site Boundary Page iii of iii

YNPS FSAR RV 10/15 REV. 01 100 SPENT FUEL MANAGEMENT PLAN 100.1 Background This section documents the YNPS spent fuel management plan in accordance with 10OCFR50.54(bb)

(Reference 100-1). This regulation also requires a funding plan for spent fuel storage. The spent fuel storage cost estimate and funding plan are presented in the PSDAR (Reference 100-4).

YAEC contracted with NAG International to transfer the spent fuel from the spent fuel pit to a dry cask storage facility. The location of the Independent Spent Fuel Storage Installation (ISF SI) is at the south end of the YNPS site (see Figure 300-1). There are 533 fuel assemblies stored in 15 NAG Multi-Purpose Canisters (MPCs) on the ISFSI pad. These fuel assemblies were discharged from the reactor between 1972 and 1992. There were also a number of failed fuel pins that were consolidated into a Reconfigured Fuel Assembly (RFA) which was then transferred to a dry cask. The Greater than Class C (GTCC) radioactive waste in the form of canisters containing reactor vessel internals (core baffle) and dross material and having the same external dimensions as fuel assemblies have also been transferred to a NAC-MPC. Several miscellaneous GTCC radioactive items also are stored in the NAC-MPC containing the GTCC (e.g. neutron sources, fuel assembly cage components, fixed incore detector wires, etc.).

YAEC is currently seeking accelerated acceptance of YNPS 's spent fuel by the Department of Energy in accordance with the current fuel disposal contract. The Department of Energy's current position is that they have not yet determined whether priority will be accorded shutdown reactors, or if priority is granted, under what specific circumstances it might be granted. For planning purposes, fuel shipments are assumed to be completed in 2031. This projection is based on the Department of Energy's Acceptance Priority Ranking, Annual Capacity Report, and an extrapolation beyond the 10 year Department of Energy outlook. For planning purposes, YAEC's current cost estimates for 1) decommissioning the ISFSI and 2) the management of spent nuclear fuel and GTCC waste assume storage of fuel in the dry storage facility until 2031.

100.2 Special Nuclear Material Control Information regarding Special Nuclear Material Control is available for inspection by authorized personnel.

REFERENCES 100-1 59-FR-10267, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, March 4, 1994.

100-2 YIRP 43 5/92, Spent Nuclear Fuel Storage Study Report and Recommendations, B. W. Holmgren, J. M. Buchheit, R. A. Mellor to J. K. Thayer, October 9, 1992.

100-3 YRP 303/93, Impact of Wet Spent Fuel Storage on Decommissioning, P. A. Rainey to R. A. Mellor, July 15, 1993.

100-4 Yankee Nuclear Power Station Post-Shutdown Deconmmissioning Activities Report.

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YNPS FSAR RV 10/15 REV. 01 229 ELECTRICAL SYSTEM 229.1 Description The on-site electrical system is powered by a commercial distribution line. The system consists of a transformer, auto throw-over switch, distribution panels and the necessary associated equipment to support ISFSI operations. Also see Sections 257 and 404.

232 FIRE DETECTION SYSTEM 232.1 Description The Fire Detection System provides the equipment needed to detect fires that could occur in structures supporting the ISFSI. The system consists of detectors, and the necessary associated instrumentation.

The Fire Detection System provides coverage in the Gatehouse, Administration Building and within the Instrument Enclosure Building at the ISFSI. Fire Protection Program requirements are described in Section 513.

256 METEOROLOGICAL TOWER 256.1 Description There is no Meteorological Tower associated with the JSFSI. If general meteorological information is needed it can be obtained from the internet.

257 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 257.1 Description The Independent Spent Fuel Storage Installation (ISFSI) provides dry cask storage of spent nuclear fuel and Greater-Than-Class-C (GTCC) waste generated at the YNPS. Dry cask storage of spent nuclear fuel is conducted under the general license provisions of 10OCFR72, Subpart K and 10OCFR30. The NAG International, Inc., Multi-Purpose Canister (MPG) system (Docket No. 72-1025), which received a certificate of compliance in April 2000 (Reference 257-1), is used at the ISFSI.

As a Part 50 Licensee, YAEC is also authorized to store GTCG waste at the JSFSI in accordance with the requirements of 10CFR30. The GTCC waste is stored in the NAC-MPC system and was evaluated in accordance with the requirements of 10CFR72.48 and 10CFR72.212 to allow co-placement of the NAC-MPC system containing GTCC waste at the YAIEC ISFSI. The NAC-MPC Transport Safety Analysis Report (SAR,) describes the GTCC waste Transportable Storage Canister (TSC) design and analysis.

The ISFSI is designed to store a combination of up to 18 NAG-MPG dry fuel or GTCC waste storage casks. It is located in the southwest corner of the site (Figure 3 00-2) and consists of a concrete pad, Page 2 of 21

YNPS FSAR RV 01 REV. 10/15 access road, security fences, temperature monitoring instrumentation, lighting, security, ISFSI Instrumentation Enclosure.

The ISFSI facility has 16 Vertical Concrete Casks (VCCs). Each VCC contains a Transportable Storage Canister (TSC). The TSCs contain either spent fuel or GTCC waste.

The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during storage. The VCC is a reinforced concrete structure with a carbon steel inner liner. Each VCC is approximately 160 inches in height, has an outside diameter of approximately 128 inches and weighs approximately 155,000 lbs. Each VCC has 4 inlet vents evenly spaced around the bottom of the VCC. There are also 4 outlet vents spaced evenly around the top of the VCC, offset by 45 degrees in order to provide a non-planar path for the natural circulation of air around the TSC and to minimize radiation streaming.

The TSC is a stainless steel circular cylindrical shell with a welded bottom plate. It has an outside diameter of approximately 71 inches and is approximately 123 inches in height. The TSC can accommodate up to 36 Yankee Class spent fuel assemblies. The TSC may also contain one or more Reconfigured Fuel Assemblies (RFAs), which are designed to hold Yankee Class spent fuel rods as intact or damaged fuel or fuel debris. An RFA can accept up to an equivalent of 64 full length spent fuel rods in an 8 by 8 array. The stainless steel RFA container has the same external dimensions of a standard fuel assembly. The NAC-MPC also has a damaged fuel configuration to provide storage for Yankee fuel classified as damaged. This configuration provides four stainless steel damaged fuel cans located in the four corner positions of the basket. A damaged fuel can may contain either an intact or a damaged spent fuel assembly but may not contain individual fuel rods not in an assembly array. The primary function of the damaged fuel can is to confine fuel material within the can and to facilitate handling and irretrievability. The placement of the damaged fuel can is restricted to the four corner positions of the fuel basket. The weight of a fully loaded TSC is approximately 55,000 lbs.

The VCC Temperature Monitoring System is designed to monitor the thermal performance of each concrete cask. The system is comprised of a network of thermocouples at the outlet vents of all the casks and at four different points for ambient temperature that can be monitored either locally, at the ISFSI Instrument Enclosure or remotely in the Gatehouse.

Radiation monitoring using Thermoluminesent Dosimeters (TLDs) is in place to demonstrate compliance with 10CFR72.104 and 40CFR190.

The ISFSI pad is within a protected area located to the south of the general site area of the YNPS.

The ISF:SI pad is a reinforced structural concrete pad that was designed to store and support the loaded VCCs. The pad is approximately 48 feet wide by 160 feet long. The east end of the pad is elevated approximately 30 inches above the grade of the access road to facilitate the loading/removal of the VCCs from the heavy-haul trailer. The VCCs are moved by using air pads and a specially rigged fork lift vehicle (cask primary mover).

The IS PSI Enclosure Building is a free standing building, measuring approximately 12 feet wide by 15 feet long by 10 feet in height, located within the protected area to the west of the ISFSI pad. The ISFSI Enclosure Building houses the temperature monitoring panel, I/O racks, transformers, Page 3 of 21

YNPS FSAR RV 10/15 REV. 01 Uninterruptible Power Supplies (UPS), communications, fire detection and other ISFSI and security related equipment.

The ISFSI protected area is fenced, monitored by security, and has alarms to prevent unauthorized access. Access to the ISFSI area is controlled in accordance with the YNPS ISFSI Physical Security Plan.

257.2 Status The ISFSI construction is complete. Spent nuclear fuel and GTCC waste transfer is complete. The YNPS ISFSI contains 15 NAC-MPC Spent Fuel Storage Casks in addition to 1 NAC-MPC Cask that contains GTCC waste.

REFERENCES 257-1 Letter, NRC to NAC International, Inc., dated March 17, 2000, Certificate of Compliance for the NAC International, Inc., Multi-Purpose Canister (MPC) System (TAC No. L22907).

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YNPS FSAR RV 10/15 REV. 01 300 ENVIRONMENTAL - SITE CHARACTERISTICS 300.1 Demography YNPS is located in the Berkshire Hills of Franklin County in Rowe, Massachusetts. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir.

The area surrounding the site is mostly wooded with very steep gradients on both sides of the Deerfield River.

The YNPS Historical Site Boundary is provided in Figure 3 00-1.

The YNPS Current 10 CFR Part 50 Licensed Site Boundary is provided in Figure 300-2.

300.2 Geography and Land Use The population density in the rural area surrounding the YNIPS site is low. Within one mile of the site, for example, the population is 48 (based on 1989 Massachusetts municipal census counts). The populations of the two closest towns, Rowe and Monroe, are 347 and 96, respectively. The nearest population center of 25,000 or more is Pittsfield, Massachusetts, located about 21 miles south-west of the site. The regional population is expected to remain virtually unchanged over the next decade.

Land use near the site is made up of a few farms and some commercial businesses. The centers of Rowe and Monroe have small, mixed clusters of local businesses, municipal buildings, and residences, with homes scattered throughout the area. There is no large industrial activity within five miles of the site; the only industry in the area is the YNPS and several hydroelectric facilities along the Deerfield River.

The nearest highway and railroad are each about five miles south of the site. The closest airport is in North Adams, Massachusetts, about ten miles west of the site.

301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)

The site lies in the prevailing westerlies, the belt of eastward moving air that is found in middle latitudes. Many storms pass over Massachusetts compared to other parts of the United States. This is a result of extensive air masses originating at higher and lower latitudes. The three major air mass types that affect the site are cold, dry, sub artic air from Canada; warm, moist air from the Gulf of Mexico; and cool, damp air from the North Atlantic Ocean.

The hills on either side of the site rise about 1000 feet above ground level within one mile and extend from 12 miles north to 8 miles south southeast of the site. This feature affects the winds.

There is, for instance, a high frequency of occurrence of "channel flow" up and down the Deerfield River valley. Also, night -time drainage flow down the east side of the river valley occurs frequently.

Normal daily temperatures range from 1 0°F in January to 80°F in July. Recorded extreme temperatures for the site region are -25°F and 98 0 F. Thunderstorms occur about 28 days per year; the annual flash density of ground lightning strikes is four flashes per square kilometer.

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YNPS FSAR RV 10/15 REV. 01 The site design wind speed (defined as the "fastest-mile" wind speed at 30 feet above the ground with a 100 year return period) is 80 mph. Hail storms occur about two days annually and freezing rain about 12 days per year. The maximum radial ice thickness expected for the region is 1.25 inches. Mean annual snowfall at the site totals 100 inches, with maximum snow depth on the ground totaling about 40 inches.

302 HYDROLOGY The site is located on the east bank of the Deerfield River adjacent to Sherman Reservoir. The drainage area upstream of the site is characterized by a dendritic pattern, is 236 square miles, and has an average annual rainfall of between 40 and 50 inches.

The Deerfield River flow is highly regulated by two large, upstream hydroelectric reservoirs. The average long-term flow near the plant is 738 fta/sec.

Bedrock in the region is not a significant source of groundwater nor are there major bedrock aquifers within the site area. The direction of groundwater flow under the site is from the recharge areas on the slopes surrounding the plant toward the Deerfield River.

303 GEOLOGY AND SEISMOLOGY The regional bedrock geology is complex; bedrock age ranges from 100 million to over one billion years old and is comprised of mostly a mosaic of metamorphic and igneous rocks. The youngest deposits are glacial soils, 10 to 12 thousand years old. Most volcanic and sedimentary rock in the area are now metamorphosed.

The site is situated on dense Wisconsinian-aged glacial till. YNPS structures are founded on this till, which ranges from 0 to 140 feet thick across the site. Bedrock under the till is part of the lower Cambrian Hoosac formation and consists of quartz-albite-biotite gneiss and a rusty gneiss in adjacent areas. Underlying these are garnet schist and a layered gneiss with some dolomitic marble, with the latter units belonging to the lower Cambrian or older Cavendish formation. A south-plunging anti-dine, whose axis is just east of the site, defines local bedrock structure.

Site bedrock is hard, internally welded metamorphic rock, not subject to significant deterioration.

Bedrock fracturing is not a prominent structural feature of this bedrock; outcrops exhibit either no joints or minor, discontinuous joint surfaces. Fracture pattern analysis of site vicinity joints, joint sets, and faults show no anomalous trends for fractures. This suggests the absence of any through-going zones of post-metamorphic faulting or shear.

The site is in the Western New England Fold Belt province. It borders the Adirondack Uplift province to the west, the Valley and Ridge province to the southwest, and the New York Recess to the south. The Southeast New England Platform and Merrimack Synclinorium occur to the east and northeast, respectively.

Regional seismic events are very infrequent and do not cause surface faulting. Only two events in the province were greater than Intensity V (MM). These events were 125 miles and 210 miles from the site. The site seismic design level for the ISFSI is contained in the NAC-MPS FSAR.

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YNPS FSAR RV 10/15 REV. 01

REFERENCE:

NAC-MPC-FSAR, Multi-Purpose Canister System, Docket No. 72-1025.

304 WATER SUPPLY Potable water is supplied by an on-site bedrock well.

305 EFFLUENTS There are no liquid effluents from the ISFSI.

Stormwater and surface water runoff follows various swales, ditches, and culverts to the Deerfield River or Sherman Pond that were created during final site grading.

Surface water use downstream from the site is mostly for recreation and sport fishing, with limited irrigation. Water supply for the municipalities within five miles downstream of the plant is from private wells. The closest public water supplies are well fields 20 to 25 miles downstream of the site.

306 ENVIRONMENTAL RADIOLOGICAL STATUS 306.1 Radiological Environmental Monitoring Program The Yankee Quality Assurance Program establishes the requirements for the Radiological Environmental Monitoring Program as defined in the YNPS Off-Site Dose Calculation Manual (Reference 306-1). The purpose of the program is to monitor the radiation in the environs of the ISFSI.

REFERENCES 306-1 YNPS Off-Site Dose Calculation Manual.

306-2 Yankee Nuclear Power Station's License Termination Plan.

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ThPS FSAR REV. 01 RV 10/15 YNPS HistoriCa! Site BO'andm'ry Fgur 300-i

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YNPS FSAR REV.

RV 10/1501 400 TRANSIENTS 400.1 General Overview Decommissioning activities for the Yankee Rowe Site are complete, with the exception of those areas associated with the ISFSI. All fuel and GTCC material has been transferred to dry fuel storage and is located at the ISFSI. The NAG-MPG FSAR contains the design basis safety analysis for the NAC-MPG system components in use at the Yankee-Rowe ISFSI.

401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY With the completion of decommissioning of the Yankee Nuclear Power Station and the passive storage of spent nuclear fuel and GTCC waste at the ISFSI, the potential for radiological and industrial safety events which could effect site personnel or the public is minimized. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISF SI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste.

This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met. Radiological events are minimized or the consequences are mitigated through the implementation of the Radiation Protection Program (Section 507) and the Emergency Plan (Section 515). Industrial safety events are minimized by implementing the site safety program for site activities.

The primary objective of the Radiation Protection Program is to protect workers and visitors to the site from radiological hazards from ISFSI operations. Activities conducted during ISFESI operations that have only a small potential for exposure of personnel to either radiation or radioactive materials and it will be managed by qualified individuals who will implement program requirements in accordance with established procedures. Radiological conditions will be monitored and evaluated on a routine basis to maintain radiation exposures to unrestricted areas as far below specified limits as is reasonably achievable. Radiation protection training will be provided to individuals classified as occupationally exposed to ensure that they understand and accept the responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

The Emergency Plan defines an on-site emergency response capability. This capability includes removal of personnel from an affected area, including site evacuation, if necessary. The plan is implemented by ISFSI personnel.

Implementation of these programs ensures that potential radiological and industrial safety events will be sufficiently minimized and mitigated to not warrant further consideration in this analysis.

403 ISFSI DECOMMISSIONING ACTIVITY EVENTS With the completion of decommissioning of the Yankee Nuclear Power Station and the transfer of fuel and GTCC material to the ISFSI for storage until ownership is transferred to DOE, the potential for the creation of events with radiological consequences is significantly reduced.

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YNPS FSAR RV 10/15 REV. 01 None of the 1SF SI structures, systems or components contain surface contamination that could result in the creation of a significant radiological event. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste. This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met.

404 LOSS OF SUPPORT SYSTEM EVENTS Electric power is provided to support ISFSI operations. Loss of this system could potentially affect many ISFSI areas and support facilities simultaneously; however, the support system is not quality or safety related.

Loss of Off-Site Power Off-site power is used to energize the ISFSI Systems, Structures and Components (SSCs).

Back-up power sources such as site UPS Units and the Security Diesel Generator will be maintained to support Gatehouse and ISFSI operations.

The public health and safety are not adversely affected by a loss of off-site or back-up power event.

405 FIRE EVENTS A fire event could affect several ISFSI systems, structures and-components simultaneously.

Combustible materials can be ignited by external ignition sources (e.g., oxyacetylene torches).

Adequate levels of the following fire protection features will be maintained through implementation of the Fire Protection Program (Section 513) minimizing the potential of occurrence of a fire:

• Fire detection equipment and systems.

• Personnel training and qualification programs.

• Fire Protection Program procedures.

• Control of transient combustible materials and ignition sources.

The public health and safety are not adversely affected by a fire event.

406 EXPLOSION EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the JSFSI, natural and manmade events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer Page 9 of 21

YNPS FSAR RV 10/15 REV. 01 be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MIPCs). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." There were no radiological consequences as a result of the postulated explosion.

REFERENCES NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

407 EXTERNAL EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, external events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site.

The material for the VCCs and ISFSI storage pads are not expected to be highly activated.

However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MP~s). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." The NAG-MPG FSAR describes the radiological consequences, if any, for each analyzed event.

REFERENCE NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

408 SPENT FUEL STORAGE EVENTS 408.1 Events All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MP~s). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." The NAG-MPG FSAR describes the radiological consequences, if any, for each analyzed event.

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YNPS FSAR RV 10/15 REV. 01 The YNPS developed and maintains a 10OCFR72.212 Evaluation Report, which concludes that all site-specific parameters found at the YNPS site are bounded by the NAC-MPC design basis analyses performed for the NAG-MPG system.

REFERENCE NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

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YNPS FSAR RV 10/15 REV. 01 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN 500.1 Regulatory Basis for Administration of the Decommissioning Plan Regulatory Guide 1.185, "Standard Format 'and Content for Post-Shutdown Decommissioning Activities Report)" (Reference 500-6), encourages licensees with an approved Decommissioning Plan to "extract the pertinent detail from the Decommissioning Plan and submit a PSDAR update in the format and content specified by the regulatory guide." As a result, information from the approved YNPS Decommissioning Plan that was incorporated into the FSAR has since been extracted, updated and relocated to the PSDAR. The PSDAR is maintained as a stand-alone document in accordance with 10 CFR 50.82(a)(7).

REFERENCES 500-1 Letter, YAEC to USNRC, dated December 20, 1993.

500-2 Draft Regulatory Guide DG-1005, "Standard Format and Content For Decommissioning Plans for Nuclear Reactors."

500-3 Letter, USNRC to YAEC, dated February 14, 1995.

500-4 Letter, YAEC to USNRC, dated August 22, 1995.

500-5 NUREG-0586, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, August 1988.

500-6 Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report, dated July 2000."

501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN Decommissioning Cost Estimate This information has been extracted, updated and relocated to the PSDAR.

Decommissioning Funding This information has been extracted, updated and relocated to the PSDAR.

502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES YAEC Commitment Yankee Atomic Electric Company (YAEC) is committed fuilly to compliance with the existing license and applicable regulatory requirements during all phases of YNPS of ISFSI operations.

YAEC's commitment to the safe storage of fuel and GTCC will be accomplished with diligence and Page 12 of 2l

YNPS FSAR RV 10/15 REV. 01 quality. Corporate principles, policies, and goals will be followed to ensure performance excellence, management competence, and high standards in every facet of ISFSI operations.

Goals The primary goal of the YNPS is to safely store spent nuclear fuel and GTCC material until it can be removed from the site. While achieving this primary goals, YAEC will conduct all ISFSI operations consistent with applicable regulations.

YAEC Organization and Functions The YAEC organizational structure that will be implemented as described in Section 1 of the Yankee Quality Assurance Program (QAP). The functions are described in site administrative procedures.

503 TRAINING PROGRAM YAEC will maintain a training program commensurate with ISFSI operational activities. The training program, in conjunction with other administrative programs and controls, will ensure that qualified individuals are available to operate and maintain the ISFSI in a safe manner. The training programs will be based on job performance requirements.

Access Training Initial and requalification access training will be provided to designated personnel as required by ISFSI procedures.

Radiation Worker Training Initial and requalification radiation worker training will be provided to designated personnel as required by ISFSI procedures.

Specific Job Training YNPS training programs will assure the following:

,, Personnel responsible for performing activities are instructed as to the purpose, scope, and implementation of applicable controlling procedures.

• Personnel performing activities are trained as appropriate, in the principles and techniques of the activity being performed.

• The methods of implementing the training programs are documented.

Page 13 of 21

YNPS FSAR RV 10/15 REV. 01 Training Records Training records will be maintained and retained in accordance with administrative procedures.

REFERENCES 503-1 NYR 93-149, NRC Partial Exemption from the Training Rule, 10CFR50.120 (TAC No. M87168), M. B. Fairtile (USN\RC) to J. M. Grant (YAEC), November 19, 1993.

503-2 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment #157 RE: Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

504 DEFUELED TECHNICAL SPECIFICATIONS The Defueled Technical Specifications was initially approved on December 23, 1992 and has been maintained with additional changes to reflect the current condition of the site. Reference the Defueled Technical Specifications for information related to the License and facility requirements.

505 PROCEDURES ISFSI Operating Procedures The ISFSI Operating Procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures, utilized by ISFSI personnel for the conduct .of operations, are contained in the ISFSI Procedures Manual and are available for inspection.

Emergency Procedures The Emergency procedures are comprised of the Emergency Operating Procedures. These procedures are revised, reviewed and controlled in accordance with the Yankee Quality Assurance Program.

The Emergency Operating Procedures have been developed to provide instructions to the ISFSI personnel. These procedures provide 1SF SI personnel with the guidance needed to respond to emergency events and provide instructions that assist in mitigating an eventand its consequence(s) to the ISFSI, site personnel, the public and the environment.

506 MAINTENANCE PROGRAM The Maintenance Program is designed to ensure continued system reliability for those systems used to support dry cask storage at the YNPS ISFSI. The program is implemented through administrative and maintenance procedures. These procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures are utilized for the conduct of maintenance activities and are available for inspection.

Page 14 of 21

YNPS FSAR RV 10/15 REV. 01 507 RADIATION PROTECTION PROGRAM 507.1 Introduction Y-NPS intends to maintain essential elements of the Radiation Protection Program that were implemented successfully during its 31 year operating life and subsequent decommissioning, to apply to ISFSI operations activities. Changes to the program will be made as necessary to meet the needs of ISFSI operations.

The Radiation Protection Program has undergone and continues to undergo inspections and audits from both the NRC and the YAEC Quality Assurance responsible individual as required by the Yankee QAP. The purpose of these reviews is to ensure that the program complies with the Code of Federal Regulations, applicable regulatory guidance documents, and industry standards. YAEC is committed to maintaining a high level of performance and to enhancing the quality of the Radiation Protection Program throughout the YNPS ISFSI operations.

The YNPS Radiation Protection Program for site closure will continue to be implemented through existing YNPS ISFSI procedures and instructions.

This section of the FSAR presents an overview of the Radiation Protection Program that will be implemented for ISFSI operations.

507.2 Management Policies 507.2.1 Management Policy Statement YAEC is committed to the safe operation of the YNPS ISFSI. The primary objective of the Radiation Protection Program is to minimize the actual and potential exposure of workers, visitors, and general public to radiation. YAEC and its contractors will provide sufficient qualified staff, facilities, and equipment to conduct radiologically safe ISFSI operations. YAEC will continue to comply with regulatory requirements, radiation exposure limits, and radioactive material release limits. In addition, YAEC will make every effort to maintain radiation exposures as low as is reasonably achievable (ALARA). The ALARA philosophy will be incorporated into all ISFSI operations and will have full management support.

YAEC requires good radiation work practices as a condition of employment. Each radiation worker is responsible for performing work in a radiologically safe manner, consistent with the standards of conduct described in the Radiation Protection Program ISFSI procedures and instructions.

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YNPS FSAR RV 10/15 REV. 01 This management policy will continue to be communicated to all radiation workers through Site Access and Training and will continue to be incorporated into all applicable ISFSI procedures and instructions.

507.2.2 Administrative Policy YAIEC will ensure that activities conducted during ISFSI operation will be managed by qualified individuals who will perform program operations in accordance with established procedures and instructions. Radiological hazards will be monitored and evaluated on a routine basis to maintain radiation exposures as far below specified limits as is reasonably achievable. Each element of the Radiation Protection Program will be defined and implemented using written ISFSI procedures and instructions. Radiation protection training will be provided to all occupationally exposed individuals to ensure that they understand and accept their responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

YAEC management will ensure that work specifications, designs, and work packages involving potential radiation exposure or handling of radioactive materials incorporate effective radiological controls.

Radiation protection records will be prepared and maintained using high standards of accuracy, traceability, and legibility to meet the requirements of regulatory agencies and company procedures.

507.2.3 ALARA Policy YAEC is committed to maintain the ALARA concept. All activities at YNPS involving radiation and radioactive materials will be conducted such that exposure of employees, contractors, and the general public to radiation is maintained as low as is reasonably achievable. This determination will consider the current state of technology and the economics of improvements in relation to their benefit (i.e., reduction of dose).

Appropriate ALARA considerations will be incorporated into ISFSI operation activity planning and design activities at an early stage to allow full consideration of reasonable alternatives. All design modifications will be reviewed to ensure that ALARA was incorporated into the activities.

507.2.4 Regulatory Compliance Policy YAEC is committed to maintain the Radiation Protection Program in compliance with the requirements of the Code of Federal Regulations and, to the extent practical, information contained in industry standards, regulatory guides, and other guidance documents. The Radiation Protection Program is assessed against all new regulatory guidance and modified as necessary.

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YNPS FSAR RV 10/15 REV. 01 507.3 Radiation Work Permits (RWIP)

Radiation Work Permits will continue to be used to administratively control designated radiological work activities. The primary function of the RWP is to allow authorized activities to be conducted in a safe manner and with radiologically sound practices. The permit documents the work description, the worker names, the radiological conditions, and the radiological precautions and requirements. The RWP implements the ALARA concept and establishes any necessary ALARA Controls.

An ISFSI procedure presents the requirements for generating and using RWP's.

507.4 Area Definitions and Postings An ISFSI procedure describes the requirements for radiological postings. The purpose of the postings is to advise workers of radiological hazards that may be encountered in the areas.

Informational postings may also be used to provide additional radiological instructions to workers.

Each worker is responsible for the observance of the area postings and compliance with the indicated requirements.

507.5 External Dosimetry 507.5.1 General Considerations External radiation dose will be monitored, as required by ISFSI procedures, and instructions.

507.5.2 Monitoring Whole Body Dose All radiation workers are required to wear external radiation monitoring devices in accordance with ISFSI procedures and instructions. These dosimetry requirements are specified on a Radiation Work Permit.

507.5.3 Dosimetry Quality Control The dosimetry processing laboratory will be accredited by the National Institute of Standards and Technology (NIST) under the National Voluntary Laboratory Accreditation Program (NVLAP) for dosimetry.

507.6 Radioactive Material Controls The Radiation Protection Program establishes radioactive material controls that ensure the following:

• Prevention of inadvertent radioactive material release to uncontrolled areas.

• Assurance that personnel are not exposed inadvertently to radiation from radioactive materials.

Materials will be released if no discernable plant-related activity is detected within the capability of the survey methods utilized. Any radioactive material that is shipped from the site is handled in Page 17 of 21

YNPS FSAR RV 10/15 REV. 01 accordance with guidance provided in YNSP ISFSI procedures and instructions, which will ensure compliance with applicable NRC and Department of Transportation requirements.

507.7 Surveillance Routine radiological surveys in compliance with the requirements of 10OCFR20 will be performed to evaluate radiological conditions in support of ISFSI operational activities. YNPS ISFSI procedures and instructions will be used to implement the surveys.

507.8 Instrumentation A sufficient inventory and variety of operable and calibrated portable, radiological instrumentation will be maintained on site to allow for effective measurement and control of radiation exposure and radioactive material and to provide back-up capability for inoperable equipment. Equipment will be capable of measuring the range of gamma, beta, alpha and neutron dose rates expected.

Instrumentation will be calibrated at prescribed intervals or prior to use against certified equipment having known valid relationships to nationally recognized standards. A YNPS ISFSI procedure or instruction will be used to control the use of radiation protection instrumentation.

507.9 Review and Audit To ensure the Radiation Protection Program is effectively implemented and maintained, an organized system of reviews and audits will continue to be implemented during ISFSI Operations in accordance with the Yankee Quality Assurance Program.

507.10 Radiation Protection Program Performance Analysis YNPS JSFSI Corrective Action procedure will be used to evaluate the causes of unacceptable performance, to initiate corrective actions. An annual assessment of the Radiation Protection Program will be performed. This process will be used to address the following types of deficiencies:

• Work activities generating unnecessary radiation exposure.

• Procedural actions resulting in unacceptable radiological performance.

• Unacceptable radiological work practices resulting in unnecessary radiation exposure.

• Activities violating Radiation Work Permit instructions, postings, and radiation protection implementing procedures and instructions.

508 RADIOACTIVE WASTE MANAGEMENT The decommissioning of YNPS required the handling of a large volume of radioactive materials to reduce residual radioactivity to a level permitting release of the site for unrestricted use in preparation to complete the partial site release of the License to the ISFSI. With the completion of decommissioning of the Yankee Nuclear Power Station and the storage of fuel and GTCC at the ISFSI there is only a small potential to generate radiological material that will have to be managed as Page 18 of 2l

YNPS FSAR RV 10/15 REV. 01 radioactive waste until the decommissioning of the ISFSI. The YAEC will continue to maintain programmatic controls within the Yankee Quality Assurance Program to ensure that federal and state regulations and disposal site requirements would be satisfied should the need arise for radioactive waste management. The YNPS radioactive waste management program would be implemented through the Radiation Protection Program (Section 507).

During the decommissioning of the ISFSI, the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

REFERENCES 508-1 58-FR-34947, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, June 30, 1993.

508-2 Yankee Nuclear Power Station Off-site Dose Calculation Manual.

508-3 Yankee Quality Assurance Program.

509 TESTS Tests may be performed to ensure the continuous, safe, and efficient operation of equipment necessary to support safe fuel storage. The various types of tests are those conducted in accordance with the QAP and governing applicable engineering practices and standards (ASME, IEEE, ISA, etc.), or those based on good engineering judgement and operational experience.

512 SECURITY PLAN The "Physical Security Plan for Yankee Rowe Independent Spent Fuel Storage Installation" provides the requirements and measures to ensure the safe storage of spent nuclear fuel at the Yankee Rowe ISFSJ. Procedures have been developed to implement the Security Plan and Program to ensure requirements are fully achieved.

YNPS access control requirements are established and are presented in an administrative procedures.

REFERENCES 5 12-1 BYR 92-077, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), August 11, 1992.

5 12-2 BYR 92-102, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), October 22, 1992.

5 12-3 NYR 92-194, Exemptions From Certain Requirements of 10CFR73.55 For The Yankee Nuclear Power Station (YNPS) (TAC No. M84267), M. B. Fairtile to J. M. Grant, November 24, 1992.

Page 19 of 21

YNPS FSAR RV 01 REV. 10/15 5 12-4 BYR 2000-068, Proposed Amendment to YNPS Security Plan, B. Wood (YAEC) to NRC, dated October 12, 2000.

512-5 NYR 2002-023, YNPS - Issuance of Amendment and Exemption from Requirements of 10CFR73.55 (TAG No. MB0209), J. Hickman (NRC) to J. Kay (YAEC), dated March 13, 2002.

5 12-6 NYR 2012-027, Response to Request for Exemption from Specific Requirements of 10 CFR 73.55 (TAG No. L24500), D. W. Weaver (NRC) to R. Mitchell (YAEC), dated September 21, 2012.

513 FIRE PROTECTION A Fire Protection Plan has been developed to minimize any potential impacts on the ISFSI from fire related events. This Fire Protection Plan has been incorporated into the ISESI set of Procedures and its implementation is supported by other fire protection procedures.

Administrative controls are established for controlling materials and events that could create potential fire hazards at the ISFSI.

The onsite incipient fire response (utilizing fire extinguishers) is adequate to protect the facility until off-site assistance provided by the Town of Rowe arrives. The Rowe Fire Department is available within a 30-minute response time.

Fire detection capabilities will remain in place to protect those facilities associated with the ISFSI.

REFERENCES 513-1 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment 157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

514 QUALITY ASSURANCE PROGRAM Yankee Atomic Electric Company (YAEC) has developed and implemented a comprehensive Quality Assurance Program to assure conformance with established regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) and accepted industry standards. The participants in the Yankee Quality Assurance Program (QAP) assure that the storage of spent fuel and GTCC at the Yankee Nuclear Power Station is performed in a safe and effective manner. All remaining applicable operational and administrative requirements that were contained in the YNPS Defueled Technical Specifications have been relocated to the QAP.

The QAP complies with the requirements set forth in Appendix B of 10CFR Part 50, along with applicable sections of the Updated Final Safety Analysis Report (UFSAR) for the license application.

Page 20 of 21

YNPS FSAR RV 01 REV. 10/15 The QAP is also established, maintained and executed to comply with the requirements of 10CFR7 1, Subpart H, and 10CFR72, Subpart G for the storage and transportation of spent nuclear fuel and high level waste under the provisions of a General License contained in these parts.

The QAP is submitted periodically to the NRC in accordance with 10CFR50.54(a).

REFERENCES 514-1 License No. DPR-3 - Yankee Nuclear Power Station.

5 14-2 10CFR Part 50 Appendix B; Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

515 EMERGENCY PLAN The Defueled Emergency Plan for YNPS was approved by the NRC and issued on October 30, 1992.

There are no longer any events (radiological or non-radiological) that could occur at the site outside of the ISFSI that could cause activation of the Defueled Emergency Plan. Therefore on March 3, 2005, Revision 12 to the Emergency Plan was issued which eliminated all facets of the Plannot related to the ISFSI, and the Plan was re-titled ISFSI Emergency Plan.

On October 26, 2006, Revision 14 (Major) was issued eliminating the remaining power plant and decommissioning accidents from the ISFSI Emergency Plan and the Plan was retitled "Emergency Plan".

The Emergency Plan is implemented through the use of Emergency Operating Procedures and administrative procedures which are referenced in the Plan. The Emergency Plan is formally audited as part of the Quality Assurance Program.

Page 21 of 21

~YANKEE 1 ATOMIC ELECTRIC COMPANY 49 Yankee Road, Rowe, Massachusetts01367 October 8, 2015 BYR 2015-03 1 10 CFR 50.71(e)(4) and 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 - 0001 Yankee Atomic Electric Company Yankee Nuclear Power Station Independent Spent Fuel Storage Installation NRC License Nos. DPR-3 and SFGL-13 (NRC Docket Nos.50-029 and 72-31)

Su~bject: Biennial Update to the Yankee Nuclear Power Station Final Safety Analysis Report Pursuant to the requirements of 10 CFR 50.7 1(e)(4) and 10 CFR 50.4, Yankee Atomic Electric Company (YAEC) provides the December 2014 and October 2015 Revisions of the Yankee Nuclear Plant Station (YNPS) Final Safety Analysis Report (FSAR) (Enclosures 1 and 2). These revisions address the changes made to the YNPS FSAR, since the submittal of the last biennial update on October 23, 2013 (Reference 1). of this letter provides a summary and rationale for the changes to the YNPS FSAR.

This letter contains no commitments.

If you have any questions regarding this submittal, please do not hesitate to contact Brian Smith at (413) 424-5261 ext. 303.

I state under penalty of perjury that the foregoing is true and correct. Executed on October 8, 2015.

Wayne Norton YAEC President and Chief Executive Officer

~L{35

Yankee Atomic Electric Company BYR 2015-031l/October 8, 2015/Page 2 Attachments and Enclosures - Summary of Proposed Changes to the Yankee Nuclear Power Station Final Safety Analysis Report - Yankee Nuclear Power Station Final Safety Analysis Report, December 2014 Revision - Yankee Nuclear Power Station Final Safety Analysis Report, October 2015 Revision References

1. Letter from W. Norton (YAEC) to Document Control Desk (NRC), Biennial Update of the Final Safety Analysis Report, dated October 23, 2013 (BYR 2013-033).

cc: D. Dorman, NRC Region I Administrator R. Powell, Chief, Decommissioning Branch, NRC, Region 1 J. Goshen, NRC Project Manager J. Giarrusso, Planning, Preparedness & Nuclear Section Chief, MEMA J. Cope-Flanagan, Assistant General Counsel, MDPU J. Reyes, State of Massachusetts Office of the Attorney General

ATTACHMENT 1 TO BYR 2015-031

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT

ATTACHMENT 1 TO BYR 2015-031

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision Section # Proposed Change Reason for Change 12/20 14 507.5.1 The FSAR was modified to state: The change to the YNPS FSAR involves External radiation dose will be the removal of specific details regarding monitored, as required by ISFSI the use of TLDs and direct reading procedures and instructions. dosimeters that is detailed in the applicable site procedure (i.e., RP-3, Personnel The discussions regarding the use of Radiation Monitoring). This procedure is thermoluminescent dosimeters maintained in accordance with the (TLDs) and direct reading requirements of 10 CFR 20 and the Quality dosimeters, and the fr~equency of Assurance Program. The change to the processing the TLDs are eliminated. FSAR does not modify the methods of These details are defined in the compliance established in RP-3.

applicable site procedure (i.e., RP-3). ____________________

10/20 15 100.1 Replaced "new storage facility" with The ISFSI is no longer a new facility. It "Independent Spent Fuel Storage has been in operation for a number of Installation (ISFSI)" years.

10/20 15 229.1 Replaced "Massachusetts Electric" This change eliminates an unnecessary with "commercial distribution" description regarding the owner of the line that supplies power to the on-site electrical.

The owner of the line is subject to change.

The use of a generic description of the line is appropriate.

10/2015 305 Replaced "[to" with "to" This change resolves a typographical error.

10/2015 406 The ESAR states "In each case, there The FSAR stated that there were no were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAG-MPG FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAG-MPG FSAR that result in of the postulated explosion event." radiological consequences that are within limits. NAG-MPG FSAR Section 11.2.3.3 defines that there are no radiological consequences for thle postulated explosion event in the NAG-MPG FSAR. Note: the NAG-MPG FSAR is maintained in accordance with 10 CFR 72.48. In addition, the YNPS 10 GFR 72.212 Evaluation Report establishes compliance with the NAG-MPG Gertificate of Gompliance (GoG) and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.2 12 Evaluation Report is also maintained in accordance with 10 CFR 72.48.

1 of 3

ATTACHMENT 1 TO BYR 2015-03 1

SUMMARY

OF CHANGES TO THE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision Section #I Proposed Change Reason for Change 10/2015 407 The FSAR states "In each case, there The FSAR stated that there were no were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAC-MPC FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAC-MPC FSAR that result in of the postulated explosion event." radiological consequences that are within limits (e.g., Blockage ofHalf of the Air Inlets, Small Release of Radioactive Particulate from the Canister Exterior, Fire Accident, Blockage Event, VCC Tip Over, and Tornado/Tornado Missile. Note: the NAG-MPG FSAR is maintained in accordance with 10 CFR 72.48. In addition, the YNPS 10 CFR 72.212 Evaluation Report establishes compliance with the NAC-MPC CoG and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.212 Evaluation Report is also maintained in

________________________accordance with 10 CFR 72.48.

10/2015 408 The FSAR states "In each case, there The FSAR stated that there were no*

were no radiological consequences radiological consequences as a result of as a result of the postulated event." any of the events postulated in the This statement was replaced with the NAG-MPG FSAR. This statement is following statement: "There were no inaccurate. There are a few events in the radiological consequences as a result NAG-MPG FSAR that result in of the postulated explosion event." radiological consequences that are within limits (e.g., Blockage of Half of the Air Inlets, Small Release of Radioactive Particulate from the Canister Exterior, Fire Accident, Blockage Event, VCG Tip Over, and Tornado/Tornado Missile. Note: the NAG-MPG FSAR is maintained in accordance with 10 GFR 72.48. In addition, the YNPS 10 GFR 72.2 12 Evaluation Report establishes compliance with the NAG-MPG CoG and FSAR, and ensures that those analyses bounds site specific conditions. The 10 CFR 72.212 Evaluation Report is also maintained in

____________accordance with 10 GFR 72.48.

10/20 15 All The word files for the YNPS FSAR This is an administrative change.

were merged. This permitted the YNPS FSAR to be reformatted by removing page breaks and replacing section based page numbers with document based page numbers. The

____________section numbers were retained.

2 of 3

ATTACHMENT 1 TO BYR 2015-03 1

SUMMARY

OF CHANGES TO THlE YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT These changes did not:

• Adversely affect an FSAR described design function,

• Involve a change to a procedure that adversely affects how FSAR described SSC design functions are performed or controlled.

• Involve revising or replacing an FSAR described evaluation methodology that is used in establishing design bases or used in the safety analysis.

• Involve a test or experiment not described in the FSAR.

3 of 3

ENCLOSURE 1 TO BYR 2015-03 1 YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT DECEMBER 2014 REVISION

YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision 12/14

YNPS FSAR RV 21 REV. 12/14 TABLE OF CONTENTS Page SECTION 100 100 SPENT FUEL MANAGEMENT PLAN...................................................... 100-I SECTION 200 229 ELECTRICAL SYSTEM ....................................................................... 229-1 232 FIRE DETECTION SYSTEM................................................................. 232-1 256 METEOROLOGICAL TOWER .............................................................. 256-1 257 ThNDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) .................. 257-1 SECTION 300 300 ENVIRONMENTAL - SITE CHARACTERISTICS ....................................... 300-1 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)...................... 301- 1 302 HYDROLOGY.................................................................................. 302-1 303 GEOLOGY AND SEISMOLOGY ............................................................ 303-1 304 WATER SUPPLY ............................................................................... 304-1 305 EFFLUENTS.................................................................................... 305-1 306 ENVIRONMENTAL RADIOLOGICAL STATUS.......................................... 306-1 SECTION 400 400 TRANSIENTS .................................................................................. 400-1 401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY................... 40 1-1 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS ....................................... 403-1 404 LOSS OF SUPPORT SYSTEM EVENTS.................................................... 404-1 405 FIRE EVENTS .................................................................................. 405-1

YNPS FSAR REV. 12/14 406 EXPLOSION EVENTS ........................................................................ 406-1 407 EXTERNAL EVENTS......................................................................... 407-1 408 SPENT FUEL STORAGE EVENTS.... ...................................................... 408-1 SECTION 500 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN ............................ 500-1 501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN ..................... 50 1-1 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES.................. 502-1 503 TRAINING PROGRAM....................................................................... 503-1 504 DEFUELED TECHNICAL SPECIFICATIONS............................................. 504-1 505 PROCEDURES ................................................................................. 505-1 506 MAINTENANCE PROGRAM................................................................ 506-1 507 RADIATION PROTECTION PROGRAM................................................... 507-1 508 RADIOACTIVE WASTE MANAGEMENT................................................. 508-1 509 TESTS ........................................................................................... 509-1 512 SECURITY PLAN.............................................................................. 512-1 513 FIRE PROTECTION ............................................................................ 513-1 514 QUALITY ASSURANCE PROGRAM....................................................... 514-1 515 EMERGENCY PLAN.......................................................................... 515-1

YNPS FSAR REV. 12/14 LIST OF FIGURES Figure No. Title 3 00-1 Historical Site Boundary 3 00-1 300-2 Current 10 CFR Part 50 Licensed Site Boundary 300-2

YNPS FSAR RV 21 REV. 12/14 100 SPENT FUEL MANAGEMENT PLAN 100.1 Background This section documents the YNPS spent fuel management plan in accordance with 10OCFR50.54(bb)

(Reference 100-1). This regulation also requires a funding plan for spent fuel storage. The spent fuel storage cost estimate and funding plan are presented in the PSDAR (Reference 100-4).

YAEC contracted with NAG International to transfer the spent fuel from the spent fuel pit to a dry cask storage facility. The location of the new storage facility is at the south end of the YNPS site (see Figure 300-1). There are 533 fuel assemblies stored in 15 NAG Multi-Purpose Canisters (MPCs) on the ISFSI pad. These fuel assemblies were discharged from the reactor between 1972 and 1992. There were also a number of failed fuel pins that were consolidated into a Reconfigured Fuel Assembly (RFA) which was then transferred to a dry cask. The Greater than Class C (GTCC) radioactive waste in the form of canisters containing reactor vessel internals (core baffle) and dross material and having the same external dimensions as fuel assemblies have also been transferred to a NAG-MPG. Several miscellaneous GTGC radioactive items also are stored in the NAG-MPG containing the GTCC (e.g. neutron sources, fuel assembly cage components, fixed incore detector wires, etc.).

YAEC is currently seeking accelerated acceptance of YNPS's spent fuel by the Department of Energy in accordance with the current fuel disposal contract. The Department of Energy's current position is that they have not yet determined whether priority will be accorded shutdown reactors, or if priority is granted, under what specific circumstances it might be granted. For planning purposes, fuel shipments are assumed to be completed in 2031. This projection is based on the Department of Energy's Acceptance Priority Ranking, Annual Capacity Report, and an extrapolation beyond the 10 year Department of Energy outlook. For planning purposes, YAEC's current cost estimates for 1) decommissioning the ISFSI and 2) the management of spent nuclear fuel and GTCC waste assume storage of fuel in the dry storage facility until 2031.

100.2 Special Nuclear Material Control Information regarding Special Nuclear Material Control is available for inspection by authorized personnel.

100-1

YNPS FSAR RV 12/14 REV. 21 REFERENCES 100-1 59-FR-10267, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, March 4, 1994.

100-2 YRP 43 5/92, Spent Nuclear Fuel Storage Study Report and Recommendations, B. W. Holmgren, J. M. Buchheit, R. A. Mellor to J. K. Thayer, October 9, 1992.

100-3 YRP 303/93, Impact of Wet Spent Fuel Storage on Decommissioning, P. A. Rainey to R. A. Mellor, July 15, 1993.

100-4 Yankee Nuclear Power Station Post-Shutdown Decommissioning Activities Report.

100-2

X'NPS FSAR RV 21 REV. 12/14 229 ELECTRICAL SYSTEM 229.1 Description The on-site electrical system is powered by a Massachusetts Electric Line. The system consists of a transformer, auto throw-over switch, distribution panels and the necessary associated equipment to support ISFSI operations. Also see Sections 257 and 404.

229-1

YNPS FSAR RV 12/14 REV. 21 232 FIRE DETECTION SYSTEM 232.1 Description The Fire Detection System provides the equipment needed to detect fires that could occur in structures supporting the ISFSI. The system consists of detectors, and the necessary associated instrumentation.

The Fire Detection System provides coverage in the Gatehouse, Administration Building and within the Instrument Enclosure Building at the ISFSI. Fire Protection Program requirements are described in Section 513.

232-1

YNPS FSAR RV 12/14 REV. 21 256 METEOROLOGICAL TOWER 256.1 Description There is no Meteorological Tower associated with the ISFSI. If general meteorological information is needed it can be obtained from the internet.

256-1

YNTPS FSAR RV 12/14 REV. 21 257 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 257.1 Description The Independent Spent Fuel Storage Installation (ISFSI) provides dry cask storage of spent nuclear fuel and Greater-Than-Class-C (GTCC) waste generated at the YNPS. Dry cask storage of spent nuclear fuel is conducted under the general license provisions of 10OCFR72, Subpart K and 10OCFR30. The NAC International, Inc., Multi-Purpose Canister (MPC) system (Docket No. 72-.

1025), which received a certificate of compliance in April 2000 (Reference 257-1), is used at the ISFSI.

As a Part 50 Licensee, YAEC is also authorized to store GTCC waste at the ISFSI in accordance with the requirements of 10OCFR3O. The GTCC waste is stored in the NAC-MPC system and was evaluated in accordance with the requirements of I0CFR72.48 and l 0CFR72.21 2 to allow co-placement of the NAC-MPC system containing GTCC waste at the YAEC ISFSI. The NAC-MPC Transport Safety Analysis Report (SAR) describes the GTCC waste Transportable Storage Canister (TSC) design and analysis.

The ISFSI is designed to store a combination of up to 18 NAC-M'PC dry fuel or GTCC waste storage casks. It is located in the southwest corner of the site (Figure 300-2) and consists of a concrete pad, access road, security fences, temperature monitoring instrumentation, lighting, security, ISFSI Instrumentation Enclosure.

The ISFSI facility has 16 Vertical Concrete Casks (VCCs). Each VCC contains a Transportable Storage Canister (TSC). The TSCs contain either spent fuel or GTCC waste.

The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during storage. The VCC is a reinforced concrete structure with a carbon steel inner liner. Each VCC is approximately 160 inches in height, has an outside diameter of approximately 128 inches and weighs approximately 155,000 lbs. Each VCC has 4 inlet vents evenly spaced around the bottom of the VCC. There are also 4 outlet vents spaced evenly around the top of the VCC, offset by 45 degrees in order to provide a non-planar path for the natural circulation of air around the TSC and to minimize radiation streaming.

The TSC is a stainless steel circular cylindrical shell with a welded bottom plate. It has an outside diameter of approximately 71 inches and is approximately 123 inches in height. The TSC can accommodate up to 36 Yankee Class spent fuel assemblies. The TSC may also contain one or more Reconfigured Fuel Assemblies (RFAs), which are designed to hold Yankee Class spent fuel rods as intact or damaged fuel or fuel debris. An RFA can accept up to an equivalent of 64 full length spent fuel rods in an 8 by 8 array. The stainless steel RFA container has the same external dimensions of a standard fuel assembly. The NAC-MPC also has a damaged fuel configuration to provide storage for Yankee fuel classified as damaged. This configuration provides four stainless steel damaged fuel cans located in the four corner positions of the basket. A damaged fuel can may contain either an intact or a damaged spent fuel assembly but may not contain individual fuel rods not in an assembly alTay. The primary function of the damaged fuel can is to confine fuel material within the can and to facilitate handling and irretrievability. The placement of the damaged fuel can is restricted to the four corner positions of the fuel basket. The weight of a fully loaded TSC is approximately 55,000 lbs.

257-1

YNPS FSAR RV 12/14 REV. 21 The VCC Temperature Monitoring System is designed to monitor the thermal performance of each concrete cask. The system is comprised of a network of thermocouples at the outlet vents of all the casks and at four different points for ambient temperature that can be monitored either locally, at the ISFSI Instrument Enclosure or remotely in the Gatehouse.

Radiation monitoring using Thermoluminesent Dosimeters (TLDs) is in place to demonstrate compliance with 10CFR72.104 and 40CFR190.

The ISFSI pad is within a protected area located to the south of the general site area of the YNPS.

The ISFSI pad is a reinforced structural concrete pad that was designed to store and support the loaded VCCs. The pad is approximately 48 feet wide by 160 feet long. The east end of the pad is elevated approximately 30 inches above the grade of the access road to facilitate the loading/removal of the VCCs from the heavy-haul trailer. The VCCs are moved by using air pads and a specially rigged fork lift vehicle (cask primary mover).

The ISFSI Enclosure Building is a free standing building, measuring approximately 12 feet wide by 15 feet long by 10 feet in height, located within the protected area to the west of the ISFSI pad. The ISFSI Enclosure Building houses the temperature monitoring panel, I/O racks, transformers, Uninterruptible Power Supplies (UPS), communications, fire detection and other JSFSI and security related equipment.

The ISFSJ protected area is fenced, monitored by security, and has alarms to prevent unauthorized access. Access to the ISFSI area is controlled in accordance with the YNPS ISFSI Physical Security P lan.

257.2 Status The ISFSI construction is complete. Spent nuclear fuel and GTCC waste transfer is complete. The YNPS ISFSI contains 15 NAC-MPC Spent Fuel Storage Casks in addition to 1 NAC-MPC Cask that contains GTCC waste.

REFERENCES 257-1 Letter, NRC to NAC International, Inc., dated March 17, 2000, Certificate of Compliance for the NAC International, Inc., Multi-Purpose Canister (MPC) System (TAC No. L22907).

257-2

YNPS FSAR RV 12/14 REV. 21 300 ENVIRONMENTAL - SITE CHARACTERISTICS 300.1 Demography YNPS is located in the Berkshire Hills of Franklin County in Rowe, Massachusetts. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir.

The area surrounding the site is mostly wooded with very steep gradients on both sides of the Deerfield River.

The YNPS Historical Site Boundary is provided in Figure 300-1.

The YNPS Current 10 CFR Part 50 Licensed Site Boundary is provided in Figure 300-2.

300.2 Geography and Land Use The population density in the rural area surrounding the YNPS site is low. Within one mile of the site, for example, the population is 48 (based on 1989 Massachusetts municipal census counts). The populations of the two closest towns, Rowe and Monroe, are 347 and 96, respectively. The nearest population center of 25,000 or more is Pittsfield, Massachusetts, located about 21 miles south-west of the site. The regional population is expected to remain virtually unchanged over the next decade.

Land use near the site is made up of a few farms and some commercial businesses. The centers of Rowe and Monroe have small, mixed clusters of local businesses, municipal buildings, and residences, with homes scattered throughout the area. There is no large industrial activity within five miles of the site; the only industry in the area is the YNPS and several hydroelectric facilities along the Deerfield River.

The nearest highway and railroad are each about five miles south of the site. The closest airport is in North Adams, Massachusetts, about ten miles west of the site.

300-1

Y!NPS PSAR RV 21 REV. 12/14 Scal.e 1.2.,0oO O.5taii 0 00nO C.5m1 'o 1*,Ooo Figure 300 Historical Site Boundary Yankee Nuclear Power Station - Rowe, MA Y'NPS Historical Site Boundary Figure 300-1

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YNPS FSAR RV 21 REV. 12/14 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)

The site lies in the prevailing westerlies, the belt of eastward moving air that is found in middle latitudes. Many storms pass over Massachusetts compared to other parts of the United States. This is a result of extensive air masses originating at higher and lower latitudes. The three major air mass types that affect the site are cold, dry, subartic air from Canada; warm, moist air from the Gulf of Mexico; and cool, damp air from the North Atlantic Ocean.

The hills on either side of the site rise about 1000 feet above ground level within one mile and extend from 12 miles north to 8 miles south southeast of the site. This feature affects the winds.

There is, for instance, a high frequency of occurrence of "channel flow" up and down the Deerfield River valley. Also, night -time drainage flow down the east side of the river valley occurs frequently.

Normal daily temperatures range from 10°F in January to 80°F in July. Recorded extreme temperatures for the site region are -25°F and 98°F. Thunderstorms occur about 28 days per year; the annual flash density of ground lightning strikes is four flashes per square kilometer.

The site design wind speed (defined as the "fastest-mile" wind speed at 30 feet above the ground with a 100 year return period) is 80 mph. Hail storms occur about two days annually and freezing rain about 12 days per year. The maximum radial ice thickness expected for the region is 1.25 inches. Mean annual snowfall at the site totals 100 inches, with maximum snow depth on the ground totaling about 40 inches.

30 1-1

YNPS FSAR RV 12/14 REV. 21 302 HYDROLOGY The site is located on the east bank of the Deerfield River adjacent to Sherman Reservoir. The drainage area upstream of the site is characterized by a dendritic pattern, is 236 square miles, and has an average annual rainfall of between 40 and 50 inches.

The Deerfield River flow is highly regulated b two large, upstream hydroelectric reservoirs. The average long-term flow near the plant is 738 ft /sec.

Bedrock in the region is not a significant source of groundwater nor are there major bedrock aquifers within the site area, The direction of groundwater flow under the site is from the recharge areas on the slopes surrounding the plant toward the Deerfield River.

302-1

YNPS FSAR RV 12/14 REV. 21 303 GEOLOGY AND SEISMOLOGY The regional bedrock geology is complex;, bedrock age ranges from 100 million to over one billion years old and is comprised of mostly a mosaic of metamorphic and igneous rocks. The youngest deposits are glacial soils, 10 to 12 thousand years old. Most volcanic and sedimentary rock in the area are now metamorphosed.

The site is situated on dense Wisconsinian-aged glacial till. YNPS structures are founded on this till, which ranges from 0 to 140 feet thick across the site. Bedrock under the till is part of the lower Cambrian Hoosac formation and consists of quartz-albite-biotite gneiss and a rusty gneiss in adjacent areas. Underlying these are garnet schist and a layered gneiss with some dolomitic marble, with the latter units belonging to the lower Cambrian or older Cavendish formation. A south-plunging anti-eline, whose axis is just east of the site, defines local bedrock structure.

Site bedrock is hard, internally welded metamorphic rock, not subject to significant deterioration.

Bedrock fracturing is not a prominent structural feature of this bedrock; outcrops exhibit either no joints or minor, discontinuous joint surfaces. Fracture pattern analysis of site vicinity joints, joint sets, and faults show no anomalous trends for fractures. This suggests the absence of any through-going zones of post-metamorphic faulting or shear.

The site is in the Western New England Fold Belt province. It borders the Adirondack Uplift province to the west, the Valley and Ridge province to the southwest, and the New York Recess to the south. The Southeast New England Platform and Merrimack Synclinorium occur to the east and northeast, respectively.

Regional seismic events are very infrequent and do not cause surface faulting. Only two events in the province were greater than Intensity V (MM). These events were 125 miles and 210 miles from the site. The site seismic design level for the ISFSI is contained in the NAC-MPS FSAR.

REFERENCE:

NAC-MPC-FSAR, Multi-Purpose Canister System, Docket No. 72-1025 303-1

YNPS FSAR RV 12/14 REV. 21 304 WATER SUPPLY Potable water is supplied by an on site bedrock well.

3 04-1

YNPS FSAR RV 12/14 REV. 21 305 EFFLUENTS There are no liquid effluents from the ISFSI.

Stormwater and surface water runoff follows various swales, ditches, and culverts [to the Deerfield River or Sherman Pond that were created during final site grading.

Surface water use downstream from the site is mostly for recreation and sport fishing, with limited irrigation. Water supply for the municipalities within five miles downstream of the plant is from private wells. The closest public water supplies are well fields 20 to 25 miles downstream of the site.

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YNPS FSAR RV 12/14 REV. 21 306 ENVIRONMENTAL RADIOLOGICAL STATUS 306.1 Radiological Environmental Monitoring Program The Yankee Quality Assurance Program establishes the requirements for the Radiological Environmental Monitoring Program as defined in the YN-PS Off-Site Dose Calculation Manual (Reference 306-1). The purpose of the program is to monitor the radiation in the environs of the ISFSI.

REFERENCES 306-1 YNPS Off-Site Dose Calculation Manual.

306-2 Yankee Nuclear Power Station's License Termination Plan 306-1

YNPS FSAR Rv 12/14 Rev. 21 400 TRANSIENTS 400.1 General Overview Decommissioning activities for the Yankee Rowe Site are complete, with the exception of those areas associated with the ISFSI. All fuel and GTCC material has been transferred to dry fuel storage and is located at the ISFSJ. The NAC-MPC FSAR contains the design basis safety analysis for the NAC-MPC system components in use at the Yankee-Rowe ISFSI.

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YNPS FSAR RV 21 REV. 12/14 401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY With the completion of decommissioning of the Yankee Nuclear Power Station and the passive storage of spent nuclear fuel and GTCC waste at the ISFSI, the potential for radiological and industrial safety events which could effect site personnel or the public is minimized. The ISFST structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste.

This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met. Radiological events are minimized or the consequences are mitigated through the implementation of the Radiation Protection Program (Section 507) and the Emergency Plan (Section 515). Industrial safety events are minimized by implementing the site safety program for site activities.

The primary objective of the Radiation Protection Program is to protect workers and visitors to the site from radiological hazards from ISFSI operations. Activities conducted during ISESI operations that have only a small potential for exposure of personnel to either radiation or radioactive materials and it will be managed by qualified individuals who will implement program requirements in accordance with established procedures. Radiological conditions wilt be monitored and evaluated on a routine basis to maintain radiation exposures to unrestricted areas as far below specified limits as is reasonably achievable. Radiation protection training will be provided to individuals classified as occupationally exposed to ensure that they understand and accept the responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

The Emergency Plan defines an on-site emergency response capability. This capability includes removal of personnel from an affected area, including site evacuation, if necessary. The plan is implemented by ISFSI personnel.

Implementation of these programs ensures that potential radiological and industrial safety events will be sufficiently minimized and mitigated to not warrant further consideration in this analysis.

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YN'PS FSAR RV 12/14 REV. 21 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS With the completion of decommissioning of the Yankee Nuclear Power Station and the transfer of fuel and GTCC material to the ISFSI for storage until ownership is transferred to DOE, the potential for the creation of events with radiological consequences is significantly reduced.

None of the ISFSI structures, systems or components contain surface contamination that could result in the creation of a significant radiological event. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste. This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met.

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YNPS FSAR RV 12/14 REV. 21 404 LOSS OF SUPPORT SYSTEM EVENTS Electric power is provided to support ISESI operations. Loss of this system could potentially affect many ISFSI areas and support facilities simultaneously; however, the support system is not quality or safety related.

Loss of Off-Site Power Off-site power is used to energize the ISFSI Systems, Structures and Components (SSCs).

Back-up power sources such as site UIPS Units and the Security Diesel Generator will be maintained to support Gatehouse and ISFSI operations.

The public health and safety are not adversely affected by a loss of off-site or back-up power event.

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YNPS FSAR RV 12/14 REV. 21 405 FIRE EVENTS A fire event could affect several ISFSI systems, structures and components simultaneously.

Combustible materials can be ignited by external ignition sources (e.g., oxyacetylene torches).

Adequate levels of the following fire protection features will be maintained through implementation of the Fire Protection Program (Section 513) minimizing the potential of occurrence of a fire:

• Fire detection equipment and systems.

• Personnel training and qualification programs.

• Fire Protection Program procedures.

• Control of transient combustible materials and ignition sources.

The public health and safety are not adversely affected by a fire event.

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YNPS FSAR RV 12/14 REV. 21 406 EXPLOSION EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, natural and manmade events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

All YN-PS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MP Cs). Chapter 11 of the NAC-MLPC FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

REFERENCES NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025 406-1

YNPS FSAR RV 12/14 REV. 21 407 EXTERNAL EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, external events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site.

The material for the VCCs and ISFSI storage pads are not expected to be highly activated.

However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MPCs). Chapter 11 of the NAC-MPC FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

REFERENCE NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

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YNPS FSAR RV 21 REV. 12/14 408 SPENT FUEL STORAGE EVENTS 408.1 Events All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAC Multi-Purpose Canisters (MPCs). Chapter 11 of the NAC-MPC PSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." In each case, there were no radiological consequences as a result of the postulated event.

The YNPS developed and maintains a 10CFR72.212 Evaluation Report, which concludes that all site-specific parameters found at the YNPS site are bounded by the NAC-MPC design basis analyses performed for the NAC-MPC system.

REFERENCE NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

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YNPS FSAR RV 12/14 REV. 21 500) ADMINISTRATION OF TH:E DECOMMISSIONING PLAN 500.1 Regulatory Basis for Administration of the Decommissioning Plan Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report)" (Reference 500-6), encourages licensees with an approved Decommissioning Plan to "extract the pertinent detail from the Decommissioning Plan and submit a PSDAR update in the format and content specified by the regulatory guide." As a result, information from the approved YNPS Decommissioning Plan that was incorporated into the FSAR has since been extracted, updated and relocated to the PSDAR. The PSDAR is maintained as a stand-alone document in accordance with 10 CFR 50.82(a)(7).

REFERENCES 500-1 Letter, YAEC to USNRC, dated December 20, 1993.

500-2 Draft Regulatory Guide DG-1005, "Standard Format and Content For Decommissioning Plans for Nuclear Reactors."

500-3 Letter, USNRC to YAEC, dated February 14, 1995.

500-4 Letter, YAEC to USNRC, dated August 22, 1995.

500-5 NUREG-05 86, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, August 1988.

500-6 Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report, dated July 2000."

500-1

YNPS FSAR RV 12/14 REV. 21 501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN Decommissioning Cost Estimate This information has been extracted, updated and relocated to the PSDAR.

Decommissioning Funding This information has been extracted, updated and relocated to the PSDAR.

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YNPS FSAR RV 12/14 REV. 21 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES YAEC Commitment Yankee Atomic Electric Company (YAEC) is committed fully to compliance with the existing license and applicable regulatory requirements during all phases of YNPS of ISFSI operations.

YAEC's commitment to the safe storage of fuel and GTCC will be accomplished with diligence and quality. Corporate principles, policies, and goals will be followed to ensure performance excellence, management competence, and high standards in every facet of 1SF SI operations.

Goals The primary goal of the YNPS is to safely store spent nuclear fuel and GTCC material until it can be removed from the site. While achieving this primary goals, YAEC will conduct all ISFSI operations consistent with applicable regulations.

YAEC Organization and Functions The YAEC organizational structure that will be implemented as described in Section 1 of the Yankee Quality Assurance Program (QAP). The functions are described in site administrative' procedures.

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YNPS FSAR RV 12/14 REV. 21 503 TRAINING PROGRAM YAEC will maintain a training program commensurate with ISFSI operational activities. The training program, in conjunction with other administrative programs and controls, will ensure that qualified individuals are available to operate and maintain the ISFSI in a safe manner. The training programs will be based on job performance requirements.

Access Training Initial and requalification access training will be provided to designated personnel as required by ISFSI procedures.

Radiation Worker Training Initial and requalification radiation worker training will be provided to designated personnel as required by ISFSI procedures.

Specific Job Training YNPS training programs will assure the following:

• Personnel responsible for performing activities are instructed as to the purpose, scope, and implementation of applicable controlling procedures.

• Personnel performing activities are trained as appropriate, in the principles and techniques of the activity being performed.

• The methods of implementing the training programs are documented.

Training Records Training records will be maintained and retained in accordance with administrative procedures.

REFERENCES 503-1 NYR 93-149, NRC Partial Exemption fr'om the Training Rule, 10CFR5Q.120 (TAG No. M87 168), M. B. Fairtile (USNRC) to J. M. Grant (YAEC), November 19, 1993.

503-2 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment #157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

503-1

YNPS FSAR RV 12/14 REV. 21 504 DEFUELED TECHNICAL SPECIFICATIONS The Deflieled Technical Specifications was initially approved on December 23, 1992 and has been maintained with additional changes to reflect the current condition of the site. Reference the Deflieled Technical Specifications for information related to the License and facility requirements.

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YNPS FSAR REV. 21 RV 12/14 505 PROCEDURES ISFSI Operating Procedures The ISFSI Operating Procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures, utilized by ISFSI personnel for the conduct of operations, are contained in the ISFSI Procedures Manual and are available for inspection.

Emergency Procedures The Emergency procedures are comprised of the Emergency Operating Procedures. These procedures are revised, reviewed and controlled in accordance with the Yankee Quality Assurance Program.

The Emergency Operating Procedures have been developed to provide instructions to the ISFSI personnel. These procedures provide ISFSI personnel with the guidance needed to respond to emergency events and provide instructions that assist in mitigating an event and its consequence(s) to the ISFSI, site personnel, the public and the environment.

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YNPS FSAR RV 21 REV. 12/14 506 MAINTENANCE PROGRAM The Maintenance Program is designed to ensure continued system reliability for those systems used to support dry cask storage at the YNPS ISFSI. The program is implemented through administrative and maintenance procedures. These procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures are utilized for the conduct of maintenance activities and are available for inspection.

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YNPS FSAR Rv 12/14 Rev. 21 507 RADIATION PROTECTION PROGRAM 507.1l Introduction YNPS intends to maintain essential elements of the Radiation Protection Program, that were implemented successfully during its 31 year operating life and subsequent decommissioning, to apply to ISESI operations activities. Changes to the program will be made as necessary to meet the needs of ISFSI operations.

The Radiation Protection Program has undergone and continues to undergo inspections and audits from both the NRC and the YAEC Quality Assurance responsible individual as required by the Yankee QAP. The purpose of these reviews is to ensure that the program complies with the Code of Federal Regulations, applicable regulatory guidance documents, and industry standards. YAEC is committed to maintaining a high level of performance and to enhancing the quality of the Radiation Protection Program throughout the YNPS ISFSI operations.

The YN-PS Radiation Protection Program for site closure will continue to be implemented through existing YNPS ISFSI procedures and instructions.

This section of the FSAR presents an overview of the Radiation Protection Program that will be implemented for ISFSI operations.

507.2 Management Policies 507.2.1 Management Policy Statement YAEC is committed to the safe operation of the YNPS ISFSI. The primary objective of the Radiation Protection Program is to minimize the actual and potential exposure of workers, visitors, and general public to radiation. YAEC and its contractors will provide sufficient qualified staff, facilities, and equipment to conduct radiologically safe ISFSI operations. YAEC will continue to comply with regulatory requirements, radiation exposure limits, and radioactive material release limits. In addition, YAEC will make every effort to maintain radiation exposures as low as is reasonably achievable (ALARA). The ALARA philosophy will be incorporated into all ISFSI operations and will have full management support.

YAEC requires good radiation work practices as a condition of employment. Each radiation worker is responsible for performing work in a radiologically safe manner, consistent with the standards of conduct described in the Radiation Protection Program ISFSI procedures and instructions.

507-1

YNPS FSAR Rv 12/14 Rev. 21 This management policy will continue to be communicated to all radiation workers through Site Access and Training and will continue to be incorporated into all applicable ISFSI procedures and instructions.

507.2.2 Administrative Policy YAEC will ensure that activities conducted during ISFSI operation will be managed by qualified individuals who will perfonri program operations in accordance with established procedures and instructions. Radiological hazards will be monitored and evaluated on a routine basis to maintain radiation exposures as far below specified limits as is reasonably achievable. Each element of the Radiation Protection Program will be defined and implemented using written ISFSI procedures and instructions. Radiation protection training will be provided to all occupationally exposed individuals to ensure that they understand and accept their responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

YAEC management will ensure that work specifications, designs, and work packages involving potential radiation exposure or handling of radioactive materials incorporate effective radiological controls.

Radiation protection records will be prepared and maintained using high standards. of accuracy, traceability, and legibility to meet the requirements of regulatory agencies and company procedures.

507.2.3 ALARA Policy YAEC is committed to maintain the ALARA concept. All activities at YNPS involving radiation and radioactive materials will be conducted such that exposure of employees, contractors, and the general public to radiation is maintained as low as is reasonably achievable. This determination will consider the current state of technology and the economics of improvements in relation to their benefit (i.e., reduction of dose).

Appropriate ALARA considerations will be incorporated into ISFSI operation activity planning and design activities at an early stage to allow full consideration of reasonable alternatives. All design modifications will be reviewed to ensure that ALARA was incorporated into the activities.

507.2.4 Regulatory Compliance Policy YAEC is committed to maintain the Radiation Protection Program in compliance with the requirements of the Code of Federal Regulations and, to the extent practical, information contained in industry standards, regulatory guides, and other guidance documents. The Radiation Protection Program is assessed against all new regulatory guidance and modified as necessary.

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YNPS FSAR Rv 12/14 Rev. 21 507.3 Radiation Work Permits (RWP)

Radiation Work Permits will continue to be used to administratively control designated radiological work activities. The primary function of the RWP is to allow authorized activities to be conducted in a safe manner and with radiologically sound practices. The permit documents the work description, the worker names, the radiological conditions, and the radiological precautions and requirements. The RWP implements the ALARA concept and establishes any necessary ALARA Controls.

An ISFSI procedure presents the requirements for generating and using RWP's.

507.4 Area Definitions and Postings An TSFSI procedure describes the requirements for radiological postings. The purpose of the postings is to advise workers of radiological hazards that may be encountered in the areas.

Informational postings may also be used to provide additional radiological instructions to workers.

Each worker is responsible for the observance of the area postings and compliance with the indicated requirements.

507.5 External Dosimetry 507.5.1 General Considerations External radiation dose will be monitored, as required by ISFSI procedures, and instructions. [

507.5.2 Monitoring Whole Body Dose All radiation workers are required to wear external radiation monitoring devices in accordance with ISFSI procedures and instructions. These dosimetry requirements are specified on a Radiation Work Permit.

507.5.3 Dosimetry Quality Control The dosimetry processing laboratory will be accredited by the National Institute of Standards and Technology (NIST) under the National Voluntary Laboratory Accreditation Program (NVLAP) for dosimetry.

507.6 Radioactive Material Controls The Radiation Protection Program establishes radioactive material controls that ensure the following:

• Prevention of inadvertent radioactive material release to uncontrolled areas.

• Assurance that personnel are not exposed inadvertently to radiation from radioactive materials.

Materials will be released if no discemnable plant-related activity is detected within the capability of the survey methods utilized. Any radioactive material that is shipped from the site is handled in 507-3

YNPS FSAR Rv 12/14 Rev. 21 accordance with guidance provided in YNSP ISFSI procedures and instructions, which will ensure compliance with applicable NRC and Department of Transportation requirements.

507.7 Surveillance Routine radiological surveys in compliance with the requirements of 10CFR2O will be performed to evaluate radiological conditions in support of ISFST operational activities. YNPS ISFSI procedures and instructions will be used to implement the surveys.

507.8 Instrumentation A sufficient inventory and variety of operable and calibrated portable, radiological instrumentation will be maintained on site to allow for effective measurement and control of radiation exposure and radioactive material and to provide back-up capability for inoperable equipment. Equipment will be capable of measuring the range of gamma, beta, alpha and neutron dose rates expected.

Instrumentation will be calibrated at prescribed intervals or prior to use against certified equipment having known valid relationships to nationally recognized standards. A YNPS ISFSI procedure or instruction will be used to control the use of radiation protection instrumentation.

507.9 Review and Audit To ensure the Radiation Protection Program is effectively implemented and maintained, an organized system of reviews and audits will continue to be implemented during ISFSI Operations in

• accordance with the Yankee Quality Assurance Program.

507.10 Radiation Protection Program Performance Analysis YNPS ISFSI Corrective Action procedure will be used to evaluate the causes of unacceptable performance, to initiate corrective actions. An annual assessment of the Radiation Protection Program wvil] be performed. This process will be used to address the following types of deficiencies:

• Work activities generating unnecessary radiation exposure.

• Procedural actions resulting in unacceptable radiological performance.

• Unacceptable radiological work practices resulting in unnecessary radiation exposure.

• Activities violating Radiation Work Permit instructions, postings, and radiation protection implementing procedures and instructions.

507-4

YNPS FSAR REV.

RV 12/14 21 508 RADIOACTIVE WASTE MANAGEMENT The decormmissioning of YNPS required the handling of a large volume of radioactive materials to reduce residual radioactivity to a level permitting release of the site for unrestricted use in preparation to complete the partial site release of the License to the ISFSI. With the completion of decommissioning of the Yankee Nuclear Power Station and the storage of fuel and GTCC at the ISFSI there is only a small potential to generate radiological material that will have to be managed as radioactive waste until the decommissioning of the ISFSI. The YAEC will continue to maintain programmatic controls within the Yankee Quality Assurance Program to ensure that federal and state regulations and disposal site requirements would be satisfied should the need arise for radioactive waste management. The YNPS radioactive waste management program would be implemented through the Radiation Protection Program (Section 507).

During the decommissioning of the ISFSI, the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

REFERENCES 508-1 58-FR-34947, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, June 30, 1993.

508-2 Yankee Nuclear Power Station Off-site Dose Calculation Manual.

508-3 Yankee Quality Assurance Program 508-1

YNPS FSAR RV 12/14 REV. 21 509 TESTS Tests may be performed to ensure the continuous, safe, and efficient operation of equipment necessary to support safe fuel storage. The various types of tests are those conducted in accordance with the QAP and governing applicable engineering practices and standards (ASME, IEEE, ISA, etc.), or those based on good engineering judgement and operational experience.

509-1

YNPS FSAR RV 12/14 REV. 21 512 SECURITY PLAN The "Physical Security Plan for Yankee Rowe Independent Spent Fuel Storage Installation" provides the requirements and measures to ensure the safe storage of spent nuclear fuel at the Yankee Rowe ISFSI. Procedures have been developed to implement the Security Plan and Program to ensure requirements are fully achieved.

YNPS access control requirements are established and are presented in an administrative procedures.

REFERENCES 5 12-1 BYR 92-077, Defueled Security and Training and Qualification Plans, J. K..Thayer to M. B. Fairtile (USNRC), August 11l, 1992.

5 12-2 BYR 92-102, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), October 22, 1992.

512-3 NYR 92-194, Exemptions From Certain Requirements of 10CFR73.55 For The Yankee Nuclear Power Station (YNPS) (TAC No. M84267), M. B. Fairtile to J. M. Grant, November 24, 1992.

512-4 BYR. 2000-068, Proposed Amendment to YNPS Security Plan, B. Wood (YAEC) to NRC, dated October 12, 2000.

5 12-5 NYR 2002-023, YNPS - Issuance of Amendment and Exemption from Requirements of 10OCFR73.55 (TAC No. MB0209), J. Hickman (NRC) to J. Kay (YAEC), dated March 13, 2002.

5 12-6 NYR 2012-027, Response to Request for Exemption from Specific Requirements of 10 CER 73.55 (TAC No. L24500), D. W. Weaver (NRC) to R. Mitchell (YAEC), dated September 21, 2012.

5 12-1

YNPS FSAR RV 21 REV. 12/14 513 FIRE PROTECTION A Fire Protection Plan has been developed to minimize any potential impacts on the ISFSI from fire related events. This Fire Protection Plan has been incorporated into the ISFSI set of Procedures and its implementation is supported by other fire protection procedures.

Administrative controls are established for controlling materials and events that could create potential fire hazards at the ISFSI.

The onsite incipient fire response (utilizing fire extinguishers) is adequate to protect the facility until off-site assistance provided by the Town of Rowe arrives. The Rowe Fire Department is available within a 30-minute response time.

Fire detection capabilities will remain in place to protect those facilities associated with the ISFSI, REFERENCES 5 13-1 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment 157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

5 13-1

YNPS FSAR RV 12/14 REV. 21 514 QUALITY ASSURANCE PROGRAM Yankee Atomic Electric Company (YAEC) has developed and implemented a comprehensive Quality Assurance Program to assure conformance with established regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) and accepted industry standards. The participants in the Yankee Quality Assurance Program (QAIP) assure that the storage of spent fuel and GTCC at the Yankee Nuclear Power Station is performed in a safe and effective manner. All remaining applicable operational and administrative requirements that were contained in the YNPS Defueled Technical Specifications have been relocated to the QAP.

The QAP complies with the requirements set forth in Appendix B of 10OCFR Part 50, along with applicable sections of the Updated Final Safety Analysis Report (I-FSAR) for the license application.

The QAP is also established, maintained and executed to comply with the requirements of 10OCFR7 1, Subpart H, and 10OCFR72, Subpart G for the storage and transportation of spent nuclear fuel and high level waste under the provisions of a General License contained in these parts.

The QAP is submitted periodically to the NRC in accordance with 10CFR50.54(a).

REFERENCES 5 14-i License No. DPR Yankee Nuclear Power Station 514-2 10OCFR Part 50 Appendix B; Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants 514-1

YNPS FSAR RV 12/14 REV. 21 515 EMERGENCY PLAN The Defueled Emergency Plan for YNPS was approved by the NRC and issued on October 30, 1992.

There are no longer any events (radiological or non-radiological) that could occur at the site outside of the ISFSI that could cause activation of'the Defueled Emergency Plan. Therefore on March 3, 2005, Revision 12 to the Emergency Plan was issued which eliminated all facets of the Plan not related to the ISFSI, and the Plan was re-titled ISFSI Emergency Plan.

On October 26, 2006, Revision 14 (Maj or) was issued eliminating the remaining power plant and decommissioning accidents from the ISFSI Emergency Plan and the Plan was retitled "Emergency Plan".

The Emergency Plan is implemented through the use of Emergency Operating Procedures and administrative procedures which are referenced in the Plan. The Emergency Plan is formally audited as part of the Quality Assurance Program.

5 15-1

ENCLOSURE 2 TO BYR 2015-03 1 YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT OCTOBER 2015 REVISION

YANKEE NUCLEAR POWER STATION FINAL SAFETY ANALYSIS REPORT Revision 10115

YNPS FSAR REV. 10/15 TABLE OF CONTENTS Page SECTION 100 100 SPENT FUEL MANAGEMENT PLAN ........................................................... 1 SECTION 200 229 ELECTRICAL SYSTEM............................................................................ 2 232 FIRE DETECTION SYSTEM ...................................................................... 2 256 METEOROLOGICAL TOWER.................................................................... 2 257 INJDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)........................ 2 SECTION 300 300 ENVIRONMENTAL - SITE CHARACTERISTICS ............................................. 5 301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER) ............................ 5 302 HYDROLOGY....................................................................................... 6 303 GEOLOGY AI"D SEISMOLOGY.................................................................. 6 304 WATER SUPPLY ................................................................................... 7 305 EFFLUENTS ......................................................................................... 7 306 ENVIRONMENTAL RADIOLOGICAL STATUS............................................... 7 SECTION 400 400 TRANSIENTS ........................................................................................ 8 401 EXVENTS AFFECTING OCCUPATIONAL HEALTH ANT) SAFETY ........................ 8 403 ISFSI DECOMMISSIONING ACTIVITY EVENTS ............................................. 8 404 LOSS OF SUPPORT SYSTEM EVENTS ......................................................... 9 405 FIRE EVENTS........................................................................................ 9 406 EXPLOSION EVENTS.............................................................................. 9 Page i of iii

YNPS FSAR REV. 10/15 407 EXTERNAL EVENTS ............................................................................... 10 408 SPENT FUEL STORAGE EVENTS................................................................ 10 SECTION 500 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN................................. 12 501 DECOMMISSIONING COST ESTIMATE ANT) FUNDING PLAN ......................... 12 502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES...................... 12 503 TRAINING PROGRAM........................................................................... 13 504 DEFUELED TECHNICAL SPECIFICATIONS................................................. 14 505 PROCEDURES ..................................................................................... 14 506 MAINTENANCE PROGRAM.................................................................... 14 507 RADIATION PROTECTION PROGRAM....................................................... 15 508 RADIOACTIVE WASTE MANAGEMENT ............................................... i..... 18 509 TESTS ............................................................................................... 19 512 SECURITY PLAN.................................................................................. 19 513 FIRE PROTECTION ............................................................................... 20 514 QUALITY ASSURANCE PROGRAM .......................................................... 20 515 EMERGENCY PLAN.............................................................................. 21 Page ii of iii

YNPS FSAR RV 10/15 REV. 01 LIST OF FIGURES FIGURE NO. TITLE 300-1 Historical Site Boundary 300-2 Current 10 CFR Part 50 Licensed Site Boundary Page iii of iii

YNPS FSAR RV 10/15 REV. 01 100 SPENT FUEL MANAGEMENT PLAN 100.1 Background This section documents the YNPS spent fuel management plan in accordance with 10OCFR50.54(bb)

(Reference 100-1). This regulation also requires a funding plan for spent fuel storage. The spent fuel storage cost estimate and funding plan are presented in the PSDAR (Reference 100-4).

YAEC contracted with NAG International to transfer the spent fuel from the spent fuel pit to a dry cask storage facility. The location of the Independent Spent Fuel Storage Installation (ISF SI) is at the south end of the YNPS site (see Figure 300-1). There are 533 fuel assemblies stored in 15 NAG Multi-Purpose Canisters (MPCs) on the ISFSI pad. These fuel assemblies were discharged from the reactor between 1972 and 1992. There were also a number of failed fuel pins that were consolidated into a Reconfigured Fuel Assembly (RFA) which was then transferred to a dry cask. The Greater than Class C (GTCC) radioactive waste in the form of canisters containing reactor vessel internals (core baffle) and dross material and having the same external dimensions as fuel assemblies have also been transferred to a NAC-MPC. Several miscellaneous GTCC radioactive items also are stored in the NAC-MPC containing the GTCC (e.g. neutron sources, fuel assembly cage components, fixed incore detector wires, etc.).

YAEC is currently seeking accelerated acceptance of YNPS 's spent fuel by the Department of Energy in accordance with the current fuel disposal contract. The Department of Energy's current position is that they have not yet determined whether priority will be accorded shutdown reactors, or if priority is granted, under what specific circumstances it might be granted. For planning purposes, fuel shipments are assumed to be completed in 2031. This projection is based on the Department of Energy's Acceptance Priority Ranking, Annual Capacity Report, and an extrapolation beyond the 10 year Department of Energy outlook. For planning purposes, YAEC's current cost estimates for 1) decommissioning the ISFSI and 2) the management of spent nuclear fuel and GTCC waste assume storage of fuel in the dry storage facility until 2031.

100.2 Special Nuclear Material Control Information regarding Special Nuclear Material Control is available for inspection by authorized personnel.

REFERENCES 100-1 59-FR-10267, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, March 4, 1994.

100-2 YIRP 43 5/92, Spent Nuclear Fuel Storage Study Report and Recommendations, B. W. Holmgren, J. M. Buchheit, R. A. Mellor to J. K. Thayer, October 9, 1992.

100-3 YRP 303/93, Impact of Wet Spent Fuel Storage on Decommissioning, P. A. Rainey to R. A. Mellor, July 15, 1993.

100-4 Yankee Nuclear Power Station Post-Shutdown Deconmmissioning Activities Report.

Page 1 of 21

YNPS FSAR RV 10/15 REV. 01 229 ELECTRICAL SYSTEM 229.1 Description The on-site electrical system is powered by a commercial distribution line. The system consists of a transformer, auto throw-over switch, distribution panels and the necessary associated equipment to support ISFSI operations. Also see Sections 257 and 404.

232 FIRE DETECTION SYSTEM 232.1 Description The Fire Detection System provides the equipment needed to detect fires that could occur in structures supporting the ISFSI. The system consists of detectors, and the necessary associated instrumentation.

The Fire Detection System provides coverage in the Gatehouse, Administration Building and within the Instrument Enclosure Building at the ISFSI. Fire Protection Program requirements are described in Section 513.

256 METEOROLOGICAL TOWER 256.1 Description There is no Meteorological Tower associated with the JSFSI. If general meteorological information is needed it can be obtained from the internet.

257 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI) 257.1 Description The Independent Spent Fuel Storage Installation (ISFSI) provides dry cask storage of spent nuclear fuel and Greater-Than-Class-C (GTCC) waste generated at the YNPS. Dry cask storage of spent nuclear fuel is conducted under the general license provisions of 10OCFR72, Subpart K and 10OCFR30. The NAG International, Inc., Multi-Purpose Canister (MPG) system (Docket No. 72-1025), which received a certificate of compliance in April 2000 (Reference 257-1), is used at the ISFSI.

As a Part 50 Licensee, YAEC is also authorized to store GTCG waste at the JSFSI in accordance with the requirements of 10CFR30. The GTCC waste is stored in the NAC-MPC system and was evaluated in accordance with the requirements of 10CFR72.48 and 10CFR72.212 to allow co-placement of the NAC-MPC system containing GTCC waste at the YAIEC ISFSI. The NAC-MPC Transport Safety Analysis Report (SAR,) describes the GTCC waste Transportable Storage Canister (TSC) design and analysis.

The ISFSI is designed to store a combination of up to 18 NAG-MPG dry fuel or GTCC waste storage casks. It is located in the southwest corner of the site (Figure 3 00-2) and consists of a concrete pad, Page 2 of 21

YNPS FSAR RV 01 REV. 10/15 access road, security fences, temperature monitoring instrumentation, lighting, security, ISFSI Instrumentation Enclosure.

The ISFSI facility has 16 Vertical Concrete Casks (VCCs). Each VCC contains a Transportable Storage Canister (TSC). The TSCs contain either spent fuel or GTCC waste.

The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during storage. The VCC is a reinforced concrete structure with a carbon steel inner liner. Each VCC is approximately 160 inches in height, has an outside diameter of approximately 128 inches and weighs approximately 155,000 lbs. Each VCC has 4 inlet vents evenly spaced around the bottom of the VCC. There are also 4 outlet vents spaced evenly around the top of the VCC, offset by 45 degrees in order to provide a non-planar path for the natural circulation of air around the TSC and to minimize radiation streaming.

The TSC is a stainless steel circular cylindrical shell with a welded bottom plate. It has an outside diameter of approximately 71 inches and is approximately 123 inches in height. The TSC can accommodate up to 36 Yankee Class spent fuel assemblies. The TSC may also contain one or more Reconfigured Fuel Assemblies (RFAs), which are designed to hold Yankee Class spent fuel rods as intact or damaged fuel or fuel debris. An RFA can accept up to an equivalent of 64 full length spent fuel rods in an 8 by 8 array. The stainless steel RFA container has the same external dimensions of a standard fuel assembly. The NAC-MPC also has a damaged fuel configuration to provide storage for Yankee fuel classified as damaged. This configuration provides four stainless steel damaged fuel cans located in the four corner positions of the basket. A damaged fuel can may contain either an intact or a damaged spent fuel assembly but may not contain individual fuel rods not in an assembly array. The primary function of the damaged fuel can is to confine fuel material within the can and to facilitate handling and irretrievability. The placement of the damaged fuel can is restricted to the four corner positions of the fuel basket. The weight of a fully loaded TSC is approximately 55,000 lbs.

The VCC Temperature Monitoring System is designed to monitor the thermal performance of each concrete cask. The system is comprised of a network of thermocouples at the outlet vents of all the casks and at four different points for ambient temperature that can be monitored either locally, at the ISFSI Instrument Enclosure or remotely in the Gatehouse.

Radiation monitoring using Thermoluminesent Dosimeters (TLDs) is in place to demonstrate compliance with 10CFR72.104 and 40CFR190.

The ISFSI pad is within a protected area located to the south of the general site area of the YNPS.

The ISF:SI pad is a reinforced structural concrete pad that was designed to store and support the loaded VCCs. The pad is approximately 48 feet wide by 160 feet long. The east end of the pad is elevated approximately 30 inches above the grade of the access road to facilitate the loading/removal of the VCCs from the heavy-haul trailer. The VCCs are moved by using air pads and a specially rigged fork lift vehicle (cask primary mover).

The IS PSI Enclosure Building is a free standing building, measuring approximately 12 feet wide by 15 feet long by 10 feet in height, located within the protected area to the west of the ISFSI pad. The ISFSI Enclosure Building houses the temperature monitoring panel, I/O racks, transformers, Page 3 of 21

YNPS FSAR RV 10/15 REV. 01 Uninterruptible Power Supplies (UPS), communications, fire detection and other ISFSI and security related equipment.

The ISFSI protected area is fenced, monitored by security, and has alarms to prevent unauthorized access. Access to the ISFSI area is controlled in accordance with the YNPS ISFSI Physical Security Plan.

257.2 Status The ISFSI construction is complete. Spent nuclear fuel and GTCC waste transfer is complete. The YNPS ISFSI contains 15 NAC-MPC Spent Fuel Storage Casks in addition to 1 NAC-MPC Cask that contains GTCC waste.

REFERENCES 257-1 Letter, NRC to NAC International, Inc., dated March 17, 2000, Certificate of Compliance for the NAC International, Inc., Multi-Purpose Canister (MPC) System (TAC No. L22907).

Page 4 of 2l

YNPS FSAR RV 10/15 REV. 01 300 ENVIRONMENTAL - SITE CHARACTERISTICS 300.1 Demography YNPS is located in the Berkshire Hills of Franklin County in Rowe, Massachusetts. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir.

The area surrounding the site is mostly wooded with very steep gradients on both sides of the Deerfield River.

The YNPS Historical Site Boundary is provided in Figure 3 00-1.

The YNPS Current 10 CFR Part 50 Licensed Site Boundary is provided in Figure 300-2.

300.2 Geography and Land Use The population density in the rural area surrounding the YNIPS site is low. Within one mile of the site, for example, the population is 48 (based on 1989 Massachusetts municipal census counts). The populations of the two closest towns, Rowe and Monroe, are 347 and 96, respectively. The nearest population center of 25,000 or more is Pittsfield, Massachusetts, located about 21 miles south-west of the site. The regional population is expected to remain virtually unchanged over the next decade.

Land use near the site is made up of a few farms and some commercial businesses. The centers of Rowe and Monroe have small, mixed clusters of local businesses, municipal buildings, and residences, with homes scattered throughout the area. There is no large industrial activity within five miles of the site; the only industry in the area is the YNPS and several hydroelectric facilities along the Deerfield River.

The nearest highway and railroad are each about five miles south of the site. The closest airport is in North Adams, Massachusetts, about ten miles west of the site.

301 METEOROLOGY (GENERAL CLIMATE, SEVERE WEATHER)

The site lies in the prevailing westerlies, the belt of eastward moving air that is found in middle latitudes. Many storms pass over Massachusetts compared to other parts of the United States. This is a result of extensive air masses originating at higher and lower latitudes. The three major air mass types that affect the site are cold, dry, sub artic air from Canada; warm, moist air from the Gulf of Mexico; and cool, damp air from the North Atlantic Ocean.

The hills on either side of the site rise about 1000 feet above ground level within one mile and extend from 12 miles north to 8 miles south southeast of the site. This feature affects the winds.

There is, for instance, a high frequency of occurrence of "channel flow" up and down the Deerfield River valley. Also, night -time drainage flow down the east side of the river valley occurs frequently.

Normal daily temperatures range from 1 0°F in January to 80°F in July. Recorded extreme temperatures for the site region are -25°F and 98 0 F. Thunderstorms occur about 28 days per year; the annual flash density of ground lightning strikes is four flashes per square kilometer.

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YNPS FSAR RV 10/15 REV. 01 The site design wind speed (defined as the "fastest-mile" wind speed at 30 feet above the ground with a 100 year return period) is 80 mph. Hail storms occur about two days annually and freezing rain about 12 days per year. The maximum radial ice thickness expected for the region is 1.25 inches. Mean annual snowfall at the site totals 100 inches, with maximum snow depth on the ground totaling about 40 inches.

302 HYDROLOGY The site is located on the east bank of the Deerfield River adjacent to Sherman Reservoir. The drainage area upstream of the site is characterized by a dendritic pattern, is 236 square miles, and has an average annual rainfall of between 40 and 50 inches.

The Deerfield River flow is highly regulated by two large, upstream hydroelectric reservoirs. The average long-term flow near the plant is 738 fta/sec.

Bedrock in the region is not a significant source of groundwater nor are there major bedrock aquifers within the site area. The direction of groundwater flow under the site is from the recharge areas on the slopes surrounding the plant toward the Deerfield River.

303 GEOLOGY AND SEISMOLOGY The regional bedrock geology is complex; bedrock age ranges from 100 million to over one billion years old and is comprised of mostly a mosaic of metamorphic and igneous rocks. The youngest deposits are glacial soils, 10 to 12 thousand years old. Most volcanic and sedimentary rock in the area are now metamorphosed.

The site is situated on dense Wisconsinian-aged glacial till. YNPS structures are founded on this till, which ranges from 0 to 140 feet thick across the site. Bedrock under the till is part of the lower Cambrian Hoosac formation and consists of quartz-albite-biotite gneiss and a rusty gneiss in adjacent areas. Underlying these are garnet schist and a layered gneiss with some dolomitic marble, with the latter units belonging to the lower Cambrian or older Cavendish formation. A south-plunging anti-dine, whose axis is just east of the site, defines local bedrock structure.

Site bedrock is hard, internally welded metamorphic rock, not subject to significant deterioration.

Bedrock fracturing is not a prominent structural feature of this bedrock; outcrops exhibit either no joints or minor, discontinuous joint surfaces. Fracture pattern analysis of site vicinity joints, joint sets, and faults show no anomalous trends for fractures. This suggests the absence of any through-going zones of post-metamorphic faulting or shear.

The site is in the Western New England Fold Belt province. It borders the Adirondack Uplift province to the west, the Valley and Ridge province to the southwest, and the New York Recess to the south. The Southeast New England Platform and Merrimack Synclinorium occur to the east and northeast, respectively.

Regional seismic events are very infrequent and do not cause surface faulting. Only two events in the province were greater than Intensity V (MM). These events were 125 miles and 210 miles from the site. The site seismic design level for the ISFSI is contained in the NAC-MPS FSAR.

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YNPS FSAR RV 10/15 REV. 01

REFERENCE:

NAC-MPC-FSAR, Multi-Purpose Canister System, Docket No. 72-1025.

304 WATER SUPPLY Potable water is supplied by an on-site bedrock well.

305 EFFLUENTS There are no liquid effluents from the ISFSI.

Stormwater and surface water runoff follows various swales, ditches, and culverts to the Deerfield River or Sherman Pond that were created during final site grading.

Surface water use downstream from the site is mostly for recreation and sport fishing, with limited irrigation. Water supply for the municipalities within five miles downstream of the plant is from private wells. The closest public water supplies are well fields 20 to 25 miles downstream of the site.

306 ENVIRONMENTAL RADIOLOGICAL STATUS 306.1 Radiological Environmental Monitoring Program The Yankee Quality Assurance Program establishes the requirements for the Radiological Environmental Monitoring Program as defined in the YNPS Off-Site Dose Calculation Manual (Reference 306-1). The purpose of the program is to monitor the radiation in the environs of the ISFSI.

REFERENCES 306-1 YNPS Off-Site Dose Calculation Manual.

306-2 Yankee Nuclear Power Station's License Termination Plan.

Page 7 of 21

ThPS FSAR REV. 01 RV 10/15 YNPS HistoriCa! Site BO'andm'ry Fgur 300-i

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YNPS FSAR REV.

RV 10/1501 400 TRANSIENTS 400.1 General Overview Decommissioning activities for the Yankee Rowe Site are complete, with the exception of those areas associated with the ISFSI. All fuel and GTCC material has been transferred to dry fuel storage and is located at the ISFSI. The NAG-MPG FSAR contains the design basis safety analysis for the NAC-MPG system components in use at the Yankee-Rowe ISFSI.

401 EVENTS AFFECTING OCCUPATIONAL HEALTH AND SAFETY With the completion of decommissioning of the Yankee Nuclear Power Station and the passive storage of spent nuclear fuel and GTCC waste at the ISFSI, the potential for radiological and industrial safety events which could effect site personnel or the public is minimized. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISF SI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste.

This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met. Radiological events are minimized or the consequences are mitigated through the implementation of the Radiation Protection Program (Section 507) and the Emergency Plan (Section 515). Industrial safety events are minimized by implementing the site safety program for site activities.

The primary objective of the Radiation Protection Program is to protect workers and visitors to the site from radiological hazards from ISFSI operations. Activities conducted during ISFESI operations that have only a small potential for exposure of personnel to either radiation or radioactive materials and it will be managed by qualified individuals who will implement program requirements in accordance with established procedures. Radiological conditions will be monitored and evaluated on a routine basis to maintain radiation exposures to unrestricted areas as far below specified limits as is reasonably achievable. Radiation protection training will be provided to individuals classified as occupationally exposed to ensure that they understand and accept the responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

The Emergency Plan defines an on-site emergency response capability. This capability includes removal of personnel from an affected area, including site evacuation, if necessary. The plan is implemented by ISFSI personnel.

Implementation of these programs ensures that potential radiological and industrial safety events will be sufficiently minimized and mitigated to not warrant further consideration in this analysis.

403 ISFSI DECOMMISSIONING ACTIVITY EVENTS With the completion of decommissioning of the Yankee Nuclear Power Station and the transfer of fuel and GTCC material to the ISFSI for storage until ownership is transferred to DOE, the potential for the creation of events with radiological consequences is significantly reduced.

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YNPS FSAR RV 10/15 REV. 01 None of the 1SF SI structures, systems or components contain surface contamination that could result in the creation of a significant radiological event. The ISFSI structures, systems, and components are not expected to be significantly contaminated at the time of decommissioning. During decommissioning of the ISFSI, the material comprising the Vertical Concrete Casks and the ISFSI storage pad will be shipped off-site as low-level radioactive waste. This activity will be managed, so that doses to workers and the public are minimized and federal regulations regarding doses and dose rates are met.

404 LOSS OF SUPPORT SYSTEM EVENTS Electric power is provided to support ISFSI operations. Loss of this system could potentially affect many ISFSI areas and support facilities simultaneously; however, the support system is not quality or safety related.

Loss of Off-Site Power Off-site power is used to energize the ISFSI Systems, Structures and Components (SSCs).

Back-up power sources such as site UPS Units and the Security Diesel Generator will be maintained to support Gatehouse and ISFSI operations.

The public health and safety are not adversely affected by a loss of off-site or back-up power event.

405 FIRE EVENTS A fire event could affect several ISFSI systems, structures and-components simultaneously.

Combustible materials can be ignited by external ignition sources (e.g., oxyacetylene torches).

Adequate levels of the following fire protection features will be maintained through implementation of the Fire Protection Program (Section 513) minimizing the potential of occurrence of a fire:

• Fire detection equipment and systems.

• Personnel training and qualification programs.

• Fire Protection Program procedures.

• Control of transient combustible materials and ignition sources.

The public health and safety are not adversely affected by a fire event.

406 EXPLOSION EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the JSFSI, natural and manmade events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer Page 9 of 21

YNPS FSAR RV 10/15 REV. 01 be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MIPCs). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAC-MPC, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." There were no radiological consequences as a result of the postulated explosion.

REFERENCES NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

407 EXTERNAL EVENTS A systemic assessment of external events was previously made to evaluate the effects of natural and manmade events on decommissioning activities. With the completion of decommissioning of the Yankee Nuclear Power Station there is currently no longer any impact from external events on decommissioning activities. During the decommissioning of the ISFSI, external events would have an insignificant impact, because the spent nuclear fuel and GTCC waste would no longer be on site.

The material for the VCCs and ISFSI storage pads are not expected to be highly activated.

However, they will be considered low-level radioactive waste for the purpose of disposal.

All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MP~s). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." The NAG-MPG FSAR describes the radiological consequences, if any, for each analyzed event.

REFERENCE NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

408 SPENT FUEL STORAGE EVENTS 408.1 Events All YNPS spent fuel is located at the ISFSI and is stored within fifteen NAG Multi-Purpose Canisters (MP~s). Chapter 11 of the NAG-MPG FSAR addresses the various off-normal and accident events which were postulated in support of the licensing and certification of the system for General License, "NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025." The NAG-MPG FSAR describes the radiological consequences, if any, for each analyzed event.

Page 10 of 21

YNPS FSAR RV 10/15 REV. 01 The YNPS developed and maintains a 10OCFR72.212 Evaluation Report, which concludes that all site-specific parameters found at the YNPS site are bounded by the NAC-MPC design basis analyses performed for the NAG-MPG system.

REFERENCE NAG-MPG, Final Safety Analysis Report, Multi-Purpose Canister System, Docket No. 72-1025.

Page 11 of 21

YNPS FSAR RV 10/15 REV. 01 500 ADMINISTRATION OF THE DECOMMISSIONING PLAN 500.1 Regulatory Basis for Administration of the Decommissioning Plan Regulatory Guide 1.185, "Standard Format 'and Content for Post-Shutdown Decommissioning Activities Report)" (Reference 500-6), encourages licensees with an approved Decommissioning Plan to "extract the pertinent detail from the Decommissioning Plan and submit a PSDAR update in the format and content specified by the regulatory guide." As a result, information from the approved YNPS Decommissioning Plan that was incorporated into the FSAR has since been extracted, updated and relocated to the PSDAR. The PSDAR is maintained as a stand-alone document in accordance with 10 CFR 50.82(a)(7).

REFERENCES 500-1 Letter, YAEC to USNRC, dated December 20, 1993.

500-2 Draft Regulatory Guide DG-1005, "Standard Format and Content For Decommissioning Plans for Nuclear Reactors."

500-3 Letter, USNRC to YAEC, dated February 14, 1995.

500-4 Letter, YAEC to USNRC, dated August 22, 1995.

500-5 NUREG-0586, Final Generic Environmental Impact Statement on Decommissioning of Nuclear Facilities, August 1988.

500-6 Regulatory Guide 1.185, "Standard Format and Content for Post-Shutdown Decommissioning Activities Report, dated July 2000."

501 DECOMMISSIONING COST ESTIMATE AND FUNDING PLAN Decommissioning Cost Estimate This information has been extracted, updated and relocated to the PSDAR.

Decommissioning Funding This information has been extracted, updated and relocated to the PSDAR.

502 DECOMMISSIONING ORGANIZATION AND RESPONSIBILITIES YAEC Commitment Yankee Atomic Electric Company (YAEC) is committed fuilly to compliance with the existing license and applicable regulatory requirements during all phases of YNPS of ISFSI operations.

YAEC's commitment to the safe storage of fuel and GTCC will be accomplished with diligence and Page 12 of 2l

YNPS FSAR RV 10/15 REV. 01 quality. Corporate principles, policies, and goals will be followed to ensure performance excellence, management competence, and high standards in every facet of ISFSI operations.

Goals The primary goal of the YNPS is to safely store spent nuclear fuel and GTCC material until it can be removed from the site. While achieving this primary goals, YAEC will conduct all ISFSI operations consistent with applicable regulations.

YAEC Organization and Functions The YAEC organizational structure that will be implemented as described in Section 1 of the Yankee Quality Assurance Program (QAP). The functions are described in site administrative procedures.

503 TRAINING PROGRAM YAEC will maintain a training program commensurate with ISFSI operational activities. The training program, in conjunction with other administrative programs and controls, will ensure that qualified individuals are available to operate and maintain the ISFSI in a safe manner. The training programs will be based on job performance requirements.

Access Training Initial and requalification access training will be provided to designated personnel as required by ISFSI procedures.

Radiation Worker Training Initial and requalification radiation worker training will be provided to designated personnel as required by ISFSI procedures.

Specific Job Training YNPS training programs will assure the following:

,, Personnel responsible for performing activities are instructed as to the purpose, scope, and implementation of applicable controlling procedures.

• Personnel performing activities are trained as appropriate, in the principles and techniques of the activity being performed.

• The methods of implementing the training programs are documented.

Page 13 of 21

YNPS FSAR RV 10/15 REV. 01 Training Records Training records will be maintained and retained in accordance with administrative procedures.

REFERENCES 503-1 NYR 93-149, NRC Partial Exemption from the Training Rule, 10CFR50.120 (TAC No. M87168), M. B. Fairtile (USN\RC) to J. M. Grant (YAEC), November 19, 1993.

503-2 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment #157 RE: Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

504 DEFUELED TECHNICAL SPECIFICATIONS The Defueled Technical Specifications was initially approved on December 23, 1992 and has been maintained with additional changes to reflect the current condition of the site. Reference the Defueled Technical Specifications for information related to the License and facility requirements.

505 PROCEDURES ISFSI Operating Procedures The ISFSI Operating Procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures, utilized by ISFSI personnel for the conduct .of operations, are contained in the ISFSI Procedures Manual and are available for inspection.

Emergency Procedures The Emergency procedures are comprised of the Emergency Operating Procedures. These procedures are revised, reviewed and controlled in accordance with the Yankee Quality Assurance Program.

The Emergency Operating Procedures have been developed to provide instructions to the ISFSI personnel. These procedures provide 1SF SI personnel with the guidance needed to respond to emergency events and provide instructions that assist in mitigating an eventand its consequence(s) to the ISFSI, site personnel, the public and the environment.

506 MAINTENANCE PROGRAM The Maintenance Program is designed to ensure continued system reliability for those systems used to support dry cask storage at the YNPS ISFSI. The program is implemented through administrative and maintenance procedures. These procedures have been developed in accordance with the Yankee Quality Assurance Program. The controlled procedures are utilized for the conduct of maintenance activities and are available for inspection.

Page 14 of 21

YNPS FSAR RV 10/15 REV. 01 507 RADIATION PROTECTION PROGRAM 507.1 Introduction Y-NPS intends to maintain essential elements of the Radiation Protection Program that were implemented successfully during its 31 year operating life and subsequent decommissioning, to apply to ISFSI operations activities. Changes to the program will be made as necessary to meet the needs of ISFSI operations.

The Radiation Protection Program has undergone and continues to undergo inspections and audits from both the NRC and the YAEC Quality Assurance responsible individual as required by the Yankee QAP. The purpose of these reviews is to ensure that the program complies with the Code of Federal Regulations, applicable regulatory guidance documents, and industry standards. YAEC is committed to maintaining a high level of performance and to enhancing the quality of the Radiation Protection Program throughout the YNPS ISFSI operations.

The YNPS Radiation Protection Program for site closure will continue to be implemented through existing YNPS ISFSI procedures and instructions.

This section of the FSAR presents an overview of the Radiation Protection Program that will be implemented for ISFSI operations.

507.2 Management Policies 507.2.1 Management Policy Statement YAEC is committed to the safe operation of the YNPS ISFSI. The primary objective of the Radiation Protection Program is to minimize the actual and potential exposure of workers, visitors, and general public to radiation. YAEC and its contractors will provide sufficient qualified staff, facilities, and equipment to conduct radiologically safe ISFSI operations. YAEC will continue to comply with regulatory requirements, radiation exposure limits, and radioactive material release limits. In addition, YAEC will make every effort to maintain radiation exposures as low as is reasonably achievable (ALARA). The ALARA philosophy will be incorporated into all ISFSI operations and will have full management support.

YAEC requires good radiation work practices as a condition of employment. Each radiation worker is responsible for performing work in a radiologically safe manner, consistent with the standards of conduct described in the Radiation Protection Program ISFSI procedures and instructions.

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YNPS FSAR RV 10/15 REV. 01 This management policy will continue to be communicated to all radiation workers through Site Access and Training and will continue to be incorporated into all applicable ISFSI procedures and instructions.

507.2.2 Administrative Policy YAIEC will ensure that activities conducted during ISFSI operation will be managed by qualified individuals who will perform program operations in accordance with established procedures and instructions. Radiological hazards will be monitored and evaluated on a routine basis to maintain radiation exposures as far below specified limits as is reasonably achievable. Each element of the Radiation Protection Program will be defined and implemented using written ISFSI procedures and instructions. Radiation protection training will be provided to all occupationally exposed individuals to ensure that they understand and accept their responsibility to follow procedures and to maintain their individual radiation dose as low as is reasonably achievable.

YAEC management will ensure that work specifications, designs, and work packages involving potential radiation exposure or handling of radioactive materials incorporate effective radiological controls.

Radiation protection records will be prepared and maintained using high standards of accuracy, traceability, and legibility to meet the requirements of regulatory agencies and company procedures.

507.2.3 ALARA Policy YAEC is committed to maintain the ALARA concept. All activities at YNPS involving radiation and radioactive materials will be conducted such that exposure of employees, contractors, and the general public to radiation is maintained as low as is reasonably achievable. This determination will consider the current state of technology and the economics of improvements in relation to their benefit (i.e., reduction of dose).

Appropriate ALARA considerations will be incorporated into ISFSI operation activity planning and design activities at an early stage to allow full consideration of reasonable alternatives. All design modifications will be reviewed to ensure that ALARA was incorporated into the activities.

507.2.4 Regulatory Compliance Policy YAEC is committed to maintain the Radiation Protection Program in compliance with the requirements of the Code of Federal Regulations and, to the extent practical, information contained in industry standards, regulatory guides, and other guidance documents. The Radiation Protection Program is assessed against all new regulatory guidance and modified as necessary.

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YNPS FSAR RV 10/15 REV. 01 507.3 Radiation Work Permits (RWIP)

Radiation Work Permits will continue to be used to administratively control designated radiological work activities. The primary function of the RWP is to allow authorized activities to be conducted in a safe manner and with radiologically sound practices. The permit documents the work description, the worker names, the radiological conditions, and the radiological precautions and requirements. The RWP implements the ALARA concept and establishes any necessary ALARA Controls.

An ISFSI procedure presents the requirements for generating and using RWP's.

507.4 Area Definitions and Postings An ISFSI procedure describes the requirements for radiological postings. The purpose of the postings is to advise workers of radiological hazards that may be encountered in the areas.

Informational postings may also be used to provide additional radiological instructions to workers.

Each worker is responsible for the observance of the area postings and compliance with the indicated requirements.

507.5 External Dosimetry 507.5.1 General Considerations External radiation dose will be monitored, as required by ISFSI procedures, and instructions.

507.5.2 Monitoring Whole Body Dose All radiation workers are required to wear external radiation monitoring devices in accordance with ISFSI procedures and instructions. These dosimetry requirements are specified on a Radiation Work Permit.

507.5.3 Dosimetry Quality Control The dosimetry processing laboratory will be accredited by the National Institute of Standards and Technology (NIST) under the National Voluntary Laboratory Accreditation Program (NVLAP) for dosimetry.

507.6 Radioactive Material Controls The Radiation Protection Program establishes radioactive material controls that ensure the following:

• Prevention of inadvertent radioactive material release to uncontrolled areas.

• Assurance that personnel are not exposed inadvertently to radiation from radioactive materials.

Materials will be released if no discernable plant-related activity is detected within the capability of the survey methods utilized. Any radioactive material that is shipped from the site is handled in Page 17 of 21

YNPS FSAR RV 10/15 REV. 01 accordance with guidance provided in YNSP ISFSI procedures and instructions, which will ensure compliance with applicable NRC and Department of Transportation requirements.

507.7 Surveillance Routine radiological surveys in compliance with the requirements of 10OCFR20 will be performed to evaluate radiological conditions in support of ISFSI operational activities. YNPS ISFSI procedures and instructions will be used to implement the surveys.

507.8 Instrumentation A sufficient inventory and variety of operable and calibrated portable, radiological instrumentation will be maintained on site to allow for effective measurement and control of radiation exposure and radioactive material and to provide back-up capability for inoperable equipment. Equipment will be capable of measuring the range of gamma, beta, alpha and neutron dose rates expected.

Instrumentation will be calibrated at prescribed intervals or prior to use against certified equipment having known valid relationships to nationally recognized standards. A YNPS ISFSI procedure or instruction will be used to control the use of radiation protection instrumentation.

507.9 Review and Audit To ensure the Radiation Protection Program is effectively implemented and maintained, an organized system of reviews and audits will continue to be implemented during ISFSI Operations in accordance with the Yankee Quality Assurance Program.

507.10 Radiation Protection Program Performance Analysis YNPS JSFSI Corrective Action procedure will be used to evaluate the causes of unacceptable performance, to initiate corrective actions. An annual assessment of the Radiation Protection Program will be performed. This process will be used to address the following types of deficiencies:

• Work activities generating unnecessary radiation exposure.

• Procedural actions resulting in unacceptable radiological performance.

• Unacceptable radiological work practices resulting in unnecessary radiation exposure.

• Activities violating Radiation Work Permit instructions, postings, and radiation protection implementing procedures and instructions.

508 RADIOACTIVE WASTE MANAGEMENT The decommissioning of YNPS required the handling of a large volume of radioactive materials to reduce residual radioactivity to a level permitting release of the site for unrestricted use in preparation to complete the partial site release of the License to the ISFSI. With the completion of decommissioning of the Yankee Nuclear Power Station and the storage of fuel and GTCC at the ISFSI there is only a small potential to generate radiological material that will have to be managed as Page 18 of 2l

YNPS FSAR RV 10/15 REV. 01 radioactive waste until the decommissioning of the ISFSI. The YAEC will continue to maintain programmatic controls within the Yankee Quality Assurance Program to ensure that federal and state regulations and disposal site requirements would be satisfied should the need arise for radioactive waste management. The YNPS radioactive waste management program would be implemented through the Radiation Protection Program (Section 507).

During the decommissioning of the ISFSI, the spent nuclear fuel and GTCC waste would no longer be on site. The material for the VCCs and ISFSI storage pads are not expected to be highly activated. However, they will be considered low-level radioactive waste for the purpose of disposal.

REFERENCES 508-1 58-FR-34947, Notification of Spent Fuel Management and Funding Plans By Licensees of Prematurely Shut Down Power Reactors, June 30, 1993.

508-2 Yankee Nuclear Power Station Off-site Dose Calculation Manual.

508-3 Yankee Quality Assurance Program.

509 TESTS Tests may be performed to ensure the continuous, safe, and efficient operation of equipment necessary to support safe fuel storage. The various types of tests are those conducted in accordance with the QAP and governing applicable engineering practices and standards (ASME, IEEE, ISA, etc.), or those based on good engineering judgement and operational experience.

512 SECURITY PLAN The "Physical Security Plan for Yankee Rowe Independent Spent Fuel Storage Installation" provides the requirements and measures to ensure the safe storage of spent nuclear fuel at the Yankee Rowe ISFSJ. Procedures have been developed to implement the Security Plan and Program to ensure requirements are fully achieved.

YNPS access control requirements are established and are presented in an administrative procedures.

REFERENCES 5 12-1 BYR 92-077, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), August 11, 1992.

5 12-2 BYR 92-102, Defueled Security and Training and Qualification Plans, J. K. Thayer to M. B. Fairtile (USNRC), October 22, 1992.

5 12-3 NYR 92-194, Exemptions From Certain Requirements of 10CFR73.55 For The Yankee Nuclear Power Station (YNPS) (TAC No. M84267), M. B. Fairtile to J. M. Grant, November 24, 1992.

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YNPS FSAR RV 01 REV. 10/15 5 12-4 BYR 2000-068, Proposed Amendment to YNPS Security Plan, B. Wood (YAEC) to NRC, dated October 12, 2000.

512-5 NYR 2002-023, YNPS - Issuance of Amendment and Exemption from Requirements of 10CFR73.55 (TAG No. MB0209), J. Hickman (NRC) to J. Kay (YAEC), dated March 13, 2002.

5 12-6 NYR 2012-027, Response to Request for Exemption from Specific Requirements of 10 CFR 73.55 (TAG No. L24500), D. W. Weaver (NRC) to R. Mitchell (YAEC), dated September 21, 2012.

513 FIRE PROTECTION A Fire Protection Plan has been developed to minimize any potential impacts on the ISFSI from fire related events. This Fire Protection Plan has been incorporated into the ISESI set of Procedures and its implementation is supported by other fire protection procedures.

Administrative controls are established for controlling materials and events that could create potential fire hazards at the ISFSI.

The onsite incipient fire response (utilizing fire extinguishers) is adequate to protect the facility until off-site assistance provided by the Town of Rowe arrives. The Rowe Fire Department is available within a 30-minute response time.

Fire detection capabilities will remain in place to protect those facilities associated with the ISFSI.

REFERENCES 513-1 NYR 03-027, J. Hickman (USNRC) to J. Kay (YAEC), Issuance of Amendment 157 RE:

Deletion of Operational and Administrative Requirements Following Fuel Transfer to ISFSI, April 18, 2003.

514 QUALITY ASSURANCE PROGRAM Yankee Atomic Electric Company (YAEC) has developed and implemented a comprehensive Quality Assurance Program to assure conformance with established regulatory requirements set forth by the Nuclear Regulatory Commission (NRC) and accepted industry standards. The participants in the Yankee Quality Assurance Program (QAP) assure that the storage of spent fuel and GTCC at the Yankee Nuclear Power Station is performed in a safe and effective manner. All remaining applicable operational and administrative requirements that were contained in the YNPS Defueled Technical Specifications have been relocated to the QAP.

The QAP complies with the requirements set forth in Appendix B of 10CFR Part 50, along with applicable sections of the Updated Final Safety Analysis Report (UFSAR) for the license application.

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YNPS FSAR RV 01 REV. 10/15 The QAP is also established, maintained and executed to comply with the requirements of 10CFR7 1, Subpart H, and 10CFR72, Subpart G for the storage and transportation of spent nuclear fuel and high level waste under the provisions of a General License contained in these parts.

The QAP is submitted periodically to the NRC in accordance with 10CFR50.54(a).

REFERENCES 514-1 License No. DPR-3 - Yankee Nuclear Power Station.

5 14-2 10CFR Part 50 Appendix B; Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

515 EMERGENCY PLAN The Defueled Emergency Plan for YNPS was approved by the NRC and issued on October 30, 1992.

There are no longer any events (radiological or non-radiological) that could occur at the site outside of the ISFSI that could cause activation of the Defueled Emergency Plan. Therefore on March 3, 2005, Revision 12 to the Emergency Plan was issued which eliminated all facets of the Plannot related to the ISFSI, and the Plan was re-titled ISFSI Emergency Plan.

On October 26, 2006, Revision 14 (Major) was issued eliminating the remaining power plant and decommissioning accidents from the ISFSI Emergency Plan and the Plan was retitled "Emergency Plan".

The Emergency Plan is implemented through the use of Emergency Operating Procedures and administrative procedures which are referenced in the Plan. The Emergency Plan is formally audited as part of the Quality Assurance Program.

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