Similar Documents at Maine Yankee |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8371999-10-13013 October 1999 Forwards Summary of Changes Made to Maine Yankee Defueled Security Plan,Iaw 10CFR50.54(p)(2).Without Encl ML20217J0241999-10-13013 October 1999 Documents 991005 Telcon Between NRC & Util to Address All of Areas Identified in Reg Guide 1.179 & NUREG-1700 Re Final Survey Plan Except for One Area ML20212F4321999-09-24024 September 1999 Responds to 990921 e-mail to E Poteat,Requesting Waiver of Late Charges of Listed Amount for Annual Fee Invoice AR0431-99.Request Denied Because 10CFR15.37 Does Not Provide for Waiver Based on Info Provided in e-mail ML20212M2431999-09-22022 September 1999 Expresses Concern Re NRC Consideration of Adoption of Policy Based on Requests from Licensees,To Allow as Part of Decommissioning of Nuclear Power Plants & Demolition of Onsite Structures at Reactor Plant Sites ML20212E4611999-09-20020 September 1999 Responds to Concerning Possible Involvement in Weekly Telephone Calls NRC Staff Has with Maine Yankee Staff ML20212F1361999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212F2521999-09-20020 September 1999 Confirms That NMSS Has Received 990916 Submittal & Will Be Included as Attachment to Commission Paper Along with State of Maine Submittal ML20212B7011999-09-14014 September 1999 Submits Comments & Raises Questions Re Generation of White Paper for Commission to Decide Merits of Rubberization ML20212A5911999-09-0808 September 1999 Responds to 990816 e-mail & 990901 Telcon with Respect to Comments Re Decommissioning of Maine Yankee Site.Concerns Raised with Respect to Status of Fuel at Maine Yankee Have Been Raised in Previous Ltrs to Us NRC ML20211M9371999-08-30030 August 1999 Addresses Two Issues Raised in s to Senator Collins & Governor a King That Relate to Construction of ISFSI at Maine Yankee ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant ML20212E4841999-08-27027 August 1999 Informs That at 990429 Meeting of Myap Community Advisory Panel,R Shadis,Asked If Given Lack of Resident Inspectors & Limited NRC-license Review Correspondence,If Shadis Could Take Part in Weekly NRC Conference Calls with Licensee ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211C0591999-08-19019 August 1999 Forwards Addl Justification for Proprietary Request Re 990809 Submittal Info on Maine Yankee License Termination Plan ML20212A5981999-08-16016 August 1999 Expresses Appreciation for with Respect to e-mail Message Re Site Release Criteria Standards Can Never Be Verified Using Existing Database ML20211D7041999-08-0909 August 1999 Forwards Rev 17 of Maine Yankee Defueled Safety Analysis Rept (Dsar), Per 10CFR50.71 & 10CFR50.4 ML20217M6501999-08-0909 August 1999 Responds to 990719 E-mail Re Cleanup Stds at MYAPC Station & Verification of Meeting Cleanup Stds.Informs That NRC Criteria for Licensing NPPs Contained in 10CFR50 & That 10CFR50.82 Addresses Requirements for License Termination ML20210Q7201999-08-0909 August 1999 Forwards non-proprietary & Proprietary Draft Documents Re Info on Myap License Termination Plan & Diskette.Proprietary Info & Diskette Withheld ML20212B2271999-08-0606 August 1999 Discusses Concerns Re Recent Incindent Involving Transport of Nuclear Matl from Maine Yankee ML20210M8171999-08-0505 August 1999 Forwards Draft License Termination Plan/Amend Plan for Maine Yankee Atomic Power Co, to Enhance Dialogue Between Various Stakeholders & Provide Springboard for Clarifying Mutual Expectations.With Three Oversize Drawings ML20210L2211999-08-0202 August 1999 Forwards Two Copies of Objectives & Sequence of Events for Maine Yankee Emergency Preparedness Exercise for 990922. Without Encl ML20210G3751999-07-28028 July 1999 Ack Receipt of June 30th Ltr That Responded to EDO Backfit Appeal Determination Re Bdba in Sfps.Staff Completed All Actions Associated with Backfit Appeal & Awaiting for New Info for Consideration Prior to Taking Addl Action ML20216D4311999-07-19019 July 1999 Informs That Util Intends to Construct ISFSI Located on Owner Controlled Property Currently Part of Maine Yankee Reactor Site ML20217M6571999-07-19019 July 1999 Expresses Concern Re Verification of Cleanup Stds at Maine Yankee Atomic Power Co Power Station ML20210C6271999-07-15015 July 1999 Forwards Draft Site Characterization Summary in Support of 10CFR50 License Termination & Copy of Latest Decommissioning Schedule with Milestones Identified.Info Submitted Per License Termination Plan ML20196K4751999-07-0606 July 1999 Informs That Confirmatory Orders ,830314,840614 & 960103 Have Been Rescinded.Staff Determined That Due to Permanently Shutdown & Defueled Status of Facility,Orders No Longer Necessary for Safe Operation & Maint.Se Encl ML20210G3981999-06-30030 June 1999 Discusses Review of Ltr Re Maine Yankee Backfit Appeal with Respect to Emergency Plan Exemptions for Decommissioning Plants ML20209C7731999-06-30030 June 1999 Responds to EDO Backfit Appeal Determination Re Emergency Plan Exemptions for Decommissioning Plants ML20209B4611999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Plant Is Y2K Ready.Contingency Plans Developed to Mitigate Potential Impact of non-plant Y2K-induced Events ML20196D9191999-06-22022 June 1999 Informs That NRC Has Completed Review of Issues Raised in of Appeal to NRC Edo.Submits List Summarizing Actions Taken Since ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20207H3371999-06-11011 June 1999 Expresses Appreciation for Participation at 990413 Reactor Decommissioning Public Meeting & Responds to Concern Re Absense of Timeliness on Part of NRC Replying to Letters ML20195G9411999-06-10010 June 1999 Informs That Maine Yankee Considers Backfit Claim & Appeal Request of 980716 & 990316,to Be Acceptably Resolved Based on Staff 990518 Response ML20195F7531999-06-0707 June 1999 Forwards Copy of Insurance Endorsement Dtd 990429,reflecting Change in Nuclear Energy Liability Insurance,Iaw Requirements of 10CFR140.15(e) ML20195F6721999-06-0707 June 1999 Forwards Insp Rept 50-309/99-01 on 990214-0513.No Violations Noted.Operations & Radiological Protection Programs, Including Radioactive Liquid & Gaseous Effluent Control Programs,Were Inspected During Insp ML20206U9711999-05-18018 May 1999 Responds to & Addl Info Re Appeal of NRC Determination Re Claim of Backfit Concerning Permanently Shutdown Reactor Security Plan ML20207A2851999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206H1391999-05-0505 May 1999 Forwards Amend 164 to License DPR-36 & Safety Evaluation. Amend Consists of Changes to License in Response to 970930 Application ML20206H2311999-05-0404 May 1999 Responds to to Chairman Jackson.Forwards Copy of Recent Staff Response to Petition Submitted on Behalf of Ucs Re Fuel Cladding at Operational Reactors ML20206G5561999-05-0303 May 1999 Forwards Amend 163 to License DPR-36 & Safety Evaluation. Amend Revises Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D7191999-04-29029 April 1999 Forwards Listed Radiological Repts for 1998 Submitted IAW Relevant Portions of License DPR-36 & ODCM ML20206E2911999-04-28028 April 1999 Requests NRC Review of ISFSI Licensing Submittals,As Scheduled & ISFSI Approval for Operation by Dec 2000.Util Will Support Any NRC RAI on Expedited Basis.Licensing Milestone Schedule,Encl ML20206E3101999-04-28028 April 1999 Forwards Data Diskette Containing 1998 Individual Monitoring NRC Form 5 Rept,Per 10CFR20.2206(b).Without Diskette ML20206A5521999-04-23023 April 1999 Forwards Environ Assessment & Finding of No Significant Impact Related to Util Application Dtd 980714,for Amend to License DPR-36 to Revise App a TSs to Change Liquid & Gaseous Release Rate Limits to Reflect Revs Made to 10CFR20 ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co ML20205N6211999-04-0707 April 1999 Ack Receipt of Which Appealed NRC Staff Determination That Util Had Not Raised Valid Backfit Claim in to Nrc.Staff Began Process of Convening Backfit Review Panel to Evaluate Appeal ML20205K6541999-04-0707 April 1999 Submits Nuclear Property Insurance Coverage Presently in Force to Protect Maine Yankee at Wiscasset,Me ML20206H2401999-03-30030 March 1999 Informs That Myap Recently Revealed That Approx 20% of Fuel Assemblies Now in SFP Are non-std & Require Special Handling & Dry Cask Packaging.Info Confirms Growing Evidence of Periodic Loss of Radiological Control ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N8371999-10-13013 October 1999 Forwards Summary of Changes Made to Maine Yankee Defueled Security Plan,Iaw 10CFR50.54(p)(2).Without Encl ML20217J0241999-10-13013 October 1999 Documents 991005 Telcon Between NRC & Util to Address All of Areas Identified in Reg Guide 1.179 & NUREG-1700 Re Final Survey Plan Except for One Area ML20212M2431999-09-22022 September 1999 Expresses Concern Re NRC Consideration of Adoption of Policy Based on Requests from Licensees,To Allow as Part of Decommissioning of Nuclear Power Plants & Demolition of Onsite Structures at Reactor Plant Sites ML20212B7011999-09-14014 September 1999 Submits Comments & Raises Questions Re Generation of White Paper for Commission to Decide Merits of Rubberization ML20212E4841999-08-27027 August 1999 Informs That at 990429 Meeting of Myap Community Advisory Panel,R Shadis,Asked If Given Lack of Resident Inspectors & Limited NRC-license Review Correspondence,If Shadis Could Take Part in Weekly NRC Conference Calls with Licensee ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211C0591999-08-19019 August 1999 Forwards Addl Justification for Proprietary Request Re 990809 Submittal Info on Maine Yankee License Termination Plan ML20212A5981999-08-16016 August 1999 Expresses Appreciation for with Respect to e-mail Message Re Site Release Criteria Standards Can Never Be Verified Using Existing Database ML20210Q7201999-08-0909 August 1999 Forwards non-proprietary & Proprietary Draft Documents Re Info on Myap License Termination Plan & Diskette.Proprietary Info & Diskette Withheld ML20211D7041999-08-0909 August 1999 Forwards Rev 17 of Maine Yankee Defueled Safety Analysis Rept (Dsar), Per 10CFR50.71 & 10CFR50.4 ML20212B2271999-08-0606 August 1999 Discusses Concerns Re Recent Incindent Involving Transport of Nuclear Matl from Maine Yankee ML20210M8171999-08-0505 August 1999 Forwards Draft License Termination Plan/Amend Plan for Maine Yankee Atomic Power Co, to Enhance Dialogue Between Various Stakeholders & Provide Springboard for Clarifying Mutual Expectations.With Three Oversize Drawings ML20210L2211999-08-0202 August 1999 Forwards Two Copies of Objectives & Sequence of Events for Maine Yankee Emergency Preparedness Exercise for 990922. Without Encl ML20217M6571999-07-19019 July 1999 Expresses Concern Re Verification of Cleanup Stds at Maine Yankee Atomic Power Co Power Station ML20216D4311999-07-19019 July 1999 Informs That Util Intends to Construct ISFSI Located on Owner Controlled Property Currently Part of Maine Yankee Reactor Site ML20210C6271999-07-15015 July 1999 Forwards Draft Site Characterization Summary in Support of 10CFR50 License Termination & Copy of Latest Decommissioning Schedule with Milestones Identified.Info Submitted Per License Termination Plan ML20210G3981999-06-30030 June 1999 Discusses Review of Ltr Re Maine Yankee Backfit Appeal with Respect to Emergency Plan Exemptions for Decommissioning Plants ML20209C7731999-06-30030 June 1999 Responds to EDO Backfit Appeal Determination Re Emergency Plan Exemptions for Decommissioning Plants ML20209B4611999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. Plant Is Y2K Ready.Contingency Plans Developed to Mitigate Potential Impact of non-plant Y2K-induced Events ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195G9411999-06-10010 June 1999 Informs That Maine Yankee Considers Backfit Claim & Appeal Request of 980716 & 990316,to Be Acceptably Resolved Based on Staff 990518 Response ML20195F7531999-06-0707 June 1999 Forwards Copy of Insurance Endorsement Dtd 990429,reflecting Change in Nuclear Energy Liability Insurance,Iaw Requirements of 10CFR140.15(e) ML20206J2801999-04-30030 April 1999 Forwards 1998 Annual Financial Repts for CT Light & Power Co,Western Ma Electric Co,Public Svc Co of Nh,North Atlantic Energy Corp,Northeast Nuclear Energy Co & North Atlantic Energy Svc Corp,License Holders ML20206D7191999-04-29029 April 1999 Forwards Listed Radiological Repts for 1998 Submitted IAW Relevant Portions of License DPR-36 & ODCM ML20206E2911999-04-28028 April 1999 Requests NRC Review of ISFSI Licensing Submittals,As Scheduled & ISFSI Approval for Operation by Dec 2000.Util Will Support Any NRC RAI on Expedited Basis.Licensing Milestone Schedule,Encl ML20206E3101999-04-28028 April 1999 Forwards Data Diskette Containing 1998 Individual Monitoring NRC Form 5 Rept,Per 10CFR20.2206(b).Without Diskette ML20205K6541999-04-0707 April 1999 Submits Nuclear Property Insurance Coverage Presently in Force to Protect Maine Yankee at Wiscasset,Me ML20206H2401999-03-30030 March 1999 Informs That Myap Recently Revealed That Approx 20% of Fuel Assemblies Now in SFP Are non-std & Require Special Handling & Dry Cask Packaging.Info Confirms Growing Evidence of Periodic Loss of Radiological Control ML20206A6951999-03-29029 March 1999 Request Confirmation That No NRC Action or Approval,Required Relative to Proposed Change in Upstream Economic Ownership of New England Power Co,Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee ML20205C3331999-03-24024 March 1999 Submits Rept on Status of Decommissioning Funding for Year Ending 981231.Requested Info Provided in Attachment ML20205B7321999-03-24024 March 1999 Documents Withdrawal of Previously Submitted Request for Exemption from Requirements of 10CFR70.24 Re Criticality Accident Requirements, ML20204E5671999-03-18018 March 1999 Forwards Rev 1 to Maine Yankee Atomic Power Station Security Plan & Description of Changes & Summary of 10CFR50.54(p) Effectiveness Evaluation.Without Encl ML20206K6811999-03-16016 March 1999 Forwards Background & Details Re Backfits Claimed in Util Re Permanently Shutdown Reactor Security Plan ML20205G9841999-01-0505 January 1999 Discusses 1997 Maff - Sepa Radioactivity in Food & Environ ML20197J9001998-12-0707 December 1998 Submits Appeal of DD Re Myap Claim of Backfit Re Beyond Design Basis Accidents in Spent Fuel Pools.Discussion of Licensee Reasons,Provided ML20198J4061998-11-0909 November 1998 Ack Receipt of Roe Response to & Copy of Chairman 981014 address,S-98-25.Informs That Root of NRC Problems Lies in Inability to Create multi-dimensional Vision,Mission or Picture of Future NRC in 2003,2008 or Any Time Frame ML20195E8961998-11-0909 November 1998 Provides Response to Nov, Re NRC Insp Repts 50-309/96-09,50-309/96-10,50-309/96-11,50-309/96-16 & 50-309/97-01.Corrective Actions:Util in Compliance with TS 5.5,which Is Current Ref to Cited TS 5.8.2.a ML20155J0871998-11-0505 November 1998 Forwards Supplemental Info for NRC Review Re TS Change 208 Request on Sf Pool Cooling Sys ML20155H9461998-11-0303 November 1998 Informs That All Future Correspondence Being Sent to Myap Should Be Sent to Listed Address ML20155G9451998-11-0303 November 1998 Forwards Rev 1 to M01-1258-002, Decommissioning Cost Analysis for Myaps, Detailing Study of Decommissioning Costs.Rev 1 to Post-Shutdown Decommissioning Rept, Encl. Info Is Submitted as Required by 10CFR50.82(a)(8)(iii) ML20155D6461998-10-29029 October 1998 Forwards Corrected, Occupational Radiation Exposure Rept for 1997, Including Work & Job Function Categories That Were in Effect in 1997 Under Former TS 5.9.1.3.A.Earlier Submittal Contained Incorrect Info ML20155D7971998-10-28028 October 1998 Forwards Response to NRC 981002 RAI Re Modeling Spent Fuel Pool Heatup.Info Is Needed for NRC to Address Future Exemption Requests from Permanently Shutdown Plants in More Generic & Timely Manner ML20155B7221998-10-26026 October 1998 Informs That Util Has Been Unsuccessful in Determining Status &/Or Estimated Completion Date of NRC Evaluation of Licensee Backfit Claim.Assistance in Resolving Matter, Requested ML20154L4821998-10-15015 October 1998 Forwards Maine Yankee Defueled Emergency Plan. Change to Maine Yankee Emergency Plan Has Been Made in Accordance with 10CFR50.54(q) ML20203H2231998-10-14014 October 1998 FOIA Request for Documents Re EAs 96-299,96-320,96-375, 96-397,97-034,97-147 & 97-559 for Myaps.Requested Documents Include OI Repts & Internal Ltrs,Memos & e-mail Messages to & from OE ML20206N7601998-10-13013 October 1998 Discusses Concerns Re Regulatory Failures at Maine Yankee & Requests NRC Convene Public Meeting Between NRC Staff & Maine Yankee Stakeholders to Discuss Events of Past Two Years ML20203A8291998-09-29029 September 1998 Submits follow-up to Last Week Telcon Request That NRC Meet with Maine Advisory Committee on Radiation on Evening of 991104,to Provide Info & Answer Questions to Committee on Recent Exemptions Granted to Maine Yankee on Emergency Plan ML20153E7541998-09-22022 September 1998 Expresses Disappointment in Quality & Approach of Staff SER, to Provide Comments on Some of Bases Considered in Issuance of Exemption to Allow Util to Discontinue Offsite Emergency Planning Activities.Factual Discrepancies Noted ML20153B2971998-09-17017 September 1998 Withdraws Exemption Request from Certain Insurance Coverage & Financial Protection Requirement Limits of 10CFR50.54(w) & 10CFR140.11.If NRC Disagrees W/Conclusion Contained in Ltr, NRC Should Continue to Process 10CFR140.11 Request ML20155D8331998-08-31031 August 1998 Forwards Public Version of, Maine Yankee Emergency Preparedness Exercise, for Exercise Scheduled for 981028. Rept Demonstrates Major on-site Emergency Response Elements for Defueled & Permanently Defueled Shutdown Plant 1999-09-22
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.s. 4 MaineYankee P.O. BOX 408 + WISCASSET, MAINE 04578 a (207) 882-6321 November 5, 1998 MN-98-70 GAZ-98-59 Proposed Change No. 208 Supplement No. 1 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington DC 20555
Reference:
(a) License No. DPR-36 (Docket No. 50-309)
(b) Letter: M. J. Meisner to USNRC: Proposed Technical Specification Change No. 208 - Fuel Storage Pool Water Level: MN-98-25. dated ,
April 13. 1998 ~ J
Subject:
Proposed Technical Specification Change No. 208 - Fuel Storage Pool Water Level: Supplement No. 1 Gentlemen: !
In Reference.(b). Maine Yankee submitted a proposed change to the Technical Specifications to base the Limiting Condition for Operation for the Fuel Storage Pool Water Level on the revised analysis for the Fuel Handling Accident and on a new ;
analysi's for radiological shielding during movement of irradiated fuel. The purpose of this letter is to supplement that submittal with additional information to support NRC's review. This additional information which is provided in Attachment .
A includes a description of the need for the Technical Specification and an !
evaluation of the effect of the requested Technical Specification change on the i Spent Fuel Pool Cooling system.
-This supplementary information does not affect the Significant Hazards Evaluation presented in Attachment I of Reference (b). If you have any questions, please contact us.
Very truly yours, f\
. ,7 George A. Zinke-, i ctor f Nuclear Safety & Regulatory Affairs o\
,"1 - st o 3v' Attachments. ,
ci Mr.(HubertMiller
'Mr.~ Michael Webb-Mr. Mike'Masnik' Mr. Mark' Roberts ~
Mr. Clough Toppan Mr. Patrick J. Dostie
.Mr. Uldis Vanags 9811120020 991105 "
PDR ADOCK 05000309 V W PDR h
_ _ - . ~ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _ _..___
e ATTACHMENT A Page 1 of 3 PROPOSED CHANGE NO. 208 ,
SUPPLEMENT N0. 1-In response to a verbal request from the NRC. Maine Yankee is providing the following additional information supporting the need for the proposed Technical Specification change and its effect on the spent fuel pool cooling system.
DESCRIPTION OF NEED l
Maine Yankee's current Technical Specifications require the fuel storage pool water l- level to be greater than or equal to 23 feet over the top of irradiated fuel l
! assemblies seated in the storage racks during movement of irradiated fuel assemblies o -in the fuel storage pool. This minimal level approximately corresponds to the normal water level of the fuel storage pool. In February 1998. Maine Yankee
~
completed a spent fuel pool elevation study. According to this study, the minimum fuel storage pool level required by Technical Specifications, when applicable, is 0.184 feet (2.208 inches) above the normal water level of the fuel storage pool.
l Accordingly, a change to the Technical Specification basis was processed in accordance with Technical Specification 5.C.4 " Technical Specification (TS) Bases Control Program" This basis change indicated that the minimum fuel storage pool
. level required by Technical Specifications, when applicable, is at the 44.2 foot elevation, which corresponds to 0.2 feet (2.4 inches) above the normal water level (rounded up for operator convenience). .
While it is possible to maintain the fuel storage pool water level at the minimum required by the ' existing Technical Specification, when applicable, it does not provide the operators with the desired operating margin for compliance without L increasing the water level to undesirable elevations. Raising the water level too l
high interferes with the ability of the skimmers to function and floods certain electrical connections. Therefore, in order to provide the operators with !
additional operating margin for compliance with the Technical Specifications. Maine !
Yankee has requested a change to the Technical Specification lowering the level by i two feet-(i.e. at the 42.2 foot elevation). I EFFECT OF THE LEVEL CHANGE ON THE SPENT FUEL P0OL COOLING SYSTEM The purpose of the Spent Fuel Pool (SFP) Cooling. System is to remove decay heat from pool water to maintain SFP water temperature within a normal range. The system also provides for_ SFP filtering and skimming functions. The system is composed of two
-spent fuel pool cooling pumps (primary side), a heat exchanger, two decay heat removal pumps (secondary side), six fan coolers each containing three fans, piping, valves and other associated equipment. This system does not perform a safety related function. Analyses demonstrate that the fuel, the storage racks and the '
l fuel pool structural components are capable of sustaining boiling as a service
- condition. For operational considerations pool temperatures are normally
-maintained below 120 F. . The system is designed to prevent a siphoning event below
'the 40 foot elevation which would provide almost 19 feet of water above the top of fuel assemblies seated in the spent fuel storage racks. In addition, adequate time is available to the operators to identify and remedy a low pool water level condition or loss of cooling incident.
l.-_, . , __._ _- -
l I l ATTACHMENT A Page 2 of 3 )
PROPOSED CHANGE N0. 208 SUPPLEMENT NO, 1 I
Even though the spent fuel pool cooling system does not provide a safety related l function, it is prudent to evaluate the effect of the proposed fuel storage pool water level change on the normal operating function of the spent fuel pool cooling l system. When the level decreases below 6 inches from the normal water level, the skimming function of the spent fuel pool purification system, if in operation, will be interrupted. The loss of the skimming function does not impact the ability of the spent fuel pool cooling system to remove decay heat.
The other impact the proposed fuel storage pool water level change will have on the l
spent fuel pool cooling 'ystem is associated with the two spent fuel pool cooling pumps (primary side). The effect on the pumps is related to (1) net positive suction head of the pumps and (2) the increased possibility of vortexing at the siphon protection piping (located at about 40 foot, 11 inches) and the consequential introduction of air into the pumes. Calculations were performed to determine these effects. The results of these caiculations indicated that two spent fuel pool l cooling pumps may be operated at fuel storage pool Water levels corresponding to 43 foot elevation or above without impacting the minimum net positive suction head and without vortex-induced-air-entrainment. At fuel storage pool levels below that corresponding to the 43 foot elevation, spent fuel pool cooling pump operations need to be limited to one pump to prevent vortex-induced-air-entrainment. Both situations require some throttling of flow at extreme fuel storage pool temperatures (eg. above 200 F). However, at these extreme temperatures, the heat removal capability of the throttled flow is enough to reduce the fuel storage pool temperature to a point at which the flow may be unthrottled. These restrictions will be maintained by administrative controls.
These effects are acceptable because the spent fuel pool cooling system is not required to protect the integrity of the fuel, the storage racks or the fuel storage pool structure itself. Analyses demonstrate that these structures and components are capable of sustaining boiling as a service condition. However, a normal range .
of spent fuel pool temperatures has been established for operational considerations. 1 One spent fuel pool cooling pump provides sufficient heat removal capability to maintain the spent fuel pool temperature in the normal operating range under most conditions and in the acceptable range under all conditions. During extreme summer l temperatures, operations would operate two pumps to maintain the spent fuel pool I temperature in the normal operating range, at which time the fuel storage pool water level would be maintained at or above the 43 foot elevation. Since fuel storage ,
pool water level and temperature transients occur over a long period of time (eg. l l days), there is ample time to recover level, if necessary, should it be lower than I l normal. Furthermore, an analysis of the fuel storage pool shows that a loss of the spent fuel pool cooling system can be sustained indefinitely as long as adequate makeup is supplied to replace fuel storage pool water that is lost due to evaporation. Fuel storage pool water makeup is available from multiple sources independent of the spent fuel pool cooling pumps.
l
l ATTACHMENT A Page 3 of 3 PROPOSED CHANGE N0. 208 SUPPLEMENT NO. 1 l
l Notwithstanding Maine Yankee's request to decrease the minimum fuel storage pool water level by two feet. Maine Yankee does not intend to operate the pool at this
- level. Maine Yankee intends to operate the fuel storage pool at the normal water ,
l level This level preserves the function of the fuel storage pool skimmmers and !
will provide a large margin for compliance with the proposed Technical Specification l
minimum fuel storage pool water level, i 1
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1 t l l
I l
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