Similar Documents at Maine Yankee |
---|
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:OUTGOING CORRESPONDENCE
MONTHYEARML20212F4321999-09-24024 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 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 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 ML20212B2181999-08-30030 August 1999 Responds to Re 990707 Message from N Allen Re Transportation Incident Involving Shipment from Maine Yankee Nuclear Power Plant 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 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 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 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 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 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 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 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 ML20205D5141999-03-26026 March 1999 Forwards Ser,Accepting Util 980819 Request for Approval of Rev 1 to Util CFH Training & Retraining Program.Rev 1 Adds Two Provisions to CFH Training Program & Changes One Title ML20205D4011999-03-26026 March 1999 Responds to Sent to Lj Callan Re Emergency Preparedness & Financial Protection Exemption Requests Made by Util & Requests Meeting Scheduled at NRC Headquarters Be Rescheduled & Held in Vicinity of Myaps ML20196K9111999-03-26026 March 1999 Forwards Insp Rept 50-309/98-05 on 981101-0213.Determined That Two Violations Occurred Based on Insp Results & Review of 1997 LER Prior to Permanent Shutdown Determined That Addl Violation Occurred.Violations Treated as NCVs ML20205G7431999-03-26026 March 1999 Documents 990224 Telcon During Which Issues Raised in to NRC Were Discussed.Issues Discussed Re Appeal of Director'S Decision on Claim of Backfit Re Beyond DBA in SFPs ML20204C4501999-03-16016 March 1999 Forwards Amend 162 to License DPR-36.Amend Revises App a TSs of Subj License to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20204F2481999-03-15015 March 1999 Responds to Expressing Concern Re 10CFR61, Licensing Requirements for Land Disposal of Radwaste & Perceptions of Insufficient Radiological Monitoring of NRC Regulated Facilities.Addresses Issues Raised ML20205G9801999-03-15015 March 1999 Responds to to Chairman Jackson of Nrc,Expressing Concerns Related to 10CFR61, Licensing Requirements for Land Disposal of Radioactive Waste ML20203H1901999-02-19019 February 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20203D6751999-02-0303 February 1999 Responds to Requesting NRC Evaluate Two Issues Pertaining to Maintaining Isolation Zones & Vehicle Barrier Sys as Backfits Under 10CFR50.109 ML20199C9031999-01-0707 January 1999 Forwards Exemption from Certain Requirements of 10CFR50.54(w) & 10CFR140.11 for Util.Exemption Issued in Response to Licensee Application Dtd 980120,requesting Reduction in Amount of Insurance Required by Facility ML20198J9181998-12-23023 December 1998 Refers to 981109 Response to Notice of Violation Re Violations Stemming from Independent Safety Assessment Team Insp ML20198J3831998-12-21021 December 1998 Reesponds to Which Continued to Raise Several Concerns Re Belief That NRC Regulatory Action Resulted in Loss of Nuclear Generation & Put Industry Future at Risk. Assures That NRC Addressing Impact of Policies on Licensees ML20206N7481998-12-15015 December 1998 Responds to Re NRC Regulatory Oversight of Maine Yankee Atomic Power Station.Although Staff Does Not Agree with Charges That Staff Acted Inappropriately & Ineffectively,Ltr Referred to NRC OIG for Action ML20196G0291998-12-0202 December 1998 Forwards EA & Fonsi Re Util Request for Exemption from Financial Protection Requirement Limits of 10CFR50.54(w) & 10CFR140.11 for Plant,Submitted in Ltr of 980120 ML20196G2751998-11-27027 November 1998 Forwards Insp Rept 50-309/98-04 on 980803-1031.No Violations Noted.During three-month Period Covered by Insp Period, Conduct of Activities During Continued Decommissioning at Maine Yankee Facilities Was Safety Focused ML20195C3771998-11-0606 November 1998 Discusses Director'S Decision Re Maine Yankee Atomic Power Co Claim of Backfit Re beyond-design-basis Accidents in Spent Fuel Pools.Copy of Author Memo to NRR Staff Directing Them to Address Issues Encl ML20154J3421998-10-0808 October 1998 Responds to Forwarding Response of 2 Individuals to NRC DFI Issued 971219 to Yaec & Duke Engineering & Services Inc.Dfi Did Not Require Response from Individuals Identified in DFI as LOCA Group Mgr & Lead Engineer ML20154J4361998-10-0808 October 1998 Responds to Forwarding Response of Duke Engineering & Services,Inc to NRC DFI Issued 971219 to Duke Engineering & Services,Inc & Yaec ML20154J8451998-10-0808 October 1998 Responds to Which Forwarded Response to NRC Demand for Info Issued on 971219 Re OI Rept 1-95-050. Related Ltr Also Issued to Maine Yankee Identifying Apparent Violations IR 05000306/19960091998-10-0808 October 1998 Discusses Results of Several NRC Insp Repts 50-306/96-09, 50-309/96-10,50-309/96-11,50-309/96-16 & 50-309/97-01, Conducted Between 960715 & 970315,three Investigations Repts 1-95-050,1-96-025 & 1-96-043 & Forwards Notice of Violation ML20154J4511998-10-0808 October 1998 Responds to Which Replied to NRC DFI Issued 971219 to Yaec & Duke Engineering & Services,Inc.Nrc Staff Completed Review of Responses of Yaec & Duke Engineering & Services Inc & 2 Individuals ML20154D7271998-10-0202 October 1998 Forwards RAI Re Spent Fuel Pool & Fuel Assemblies.Response Requested within 30 Days of Date of Ltr ML20154A9041998-09-28028 September 1998 Forwards Insp Rept 50-309/98-03 on 980503-0801.No Violations Noted.Insp Exam of Licensed Activities as They Relate to Radiation Safety & to Compliance with Commission Regulations ML20153G0941998-09-18018 September 1998 Refers to CAL 1-96-15 Issued on 961218 & Suppl Issued 970130,confirming That Facility Will Not Restart Until Addl Actions Were Completed.Issues That Were Subj of CAL & Suppl Were Re Operation of Facility & Not Permanent Shutdown ML20153C0851998-09-16016 September 1998 Responds to 980723 e-mail to Senator SM Collins of Maine Re Several Concerns Raised About Disposal of Reactor Vessel from Maine Yankee Atomic Power Station.Nrc Made No Generic Decision,Acceptable for All Rv with Internal Components ML20197J5931998-09-16016 September 1998 Informs That on 980903 NRC Granted Exemption to Maine Yankee Atomic Power Co from Certain Sections of 10CFR50 Re Emergency Response Planning,Allowing Licensee to Discontinue Offsite Emergency Planning Activities ML20151V0461998-09-0707 September 1998 Responds to Which Raised Several Concerns Re NRC Oversight of Decommissioning of Plant ML20197C7981998-09-0303 September 1998 Forwards Exemption,Environ Assessment & SER in Response to 971106 Request to Discontinue Offsite Emergency Planning Activities & to Reduce Scope of Onsite Emergency Planning as Result of Permanently Shutdown & Defueled Status of Plant 1999-09-08
[Table view] |
Text
_m . _ _ _ _ _ - _ ___ _ _ _ _ ________m_.._.._._ . _._. .. __ _ ..__ _._
f uauq
[ k g
o
,j
't UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3086b0001 y* *4 *** /
May 23, 1997 l
Mr. David A. Lochbaum Nuclear Safety Engineer l Union of Concerned Scientists 1616 P Street., NW, Suite 310 l Washington, DC 20036 l
Dear Mr. Lochbaum:
l 1 am responding to your letter to me of March 21, 1997, on the subject of t
reactor safety margin. In your letter, you clarified the positions previously stated in your letter of January 6,1997, to Hubert J. Miller, Regional Administrator, Region I, U.S. Nuclear Regulatory Commission (NRC), regarding licensee nonconformance with NRC regulations. You also commented on NRC's policy on allowing plants to continue to operate when a licensee has determined that it is not in conformance with its design or licensing bases.
I will address these issues in the order you raised them in your letter.
t In clarifying your positions on a licensee's nonconformance with its design and licensing bases, you first stated that "when a licensee makes a physical change to the facility to correct a nonconformance, it is reasonable to conclude that these actions restored safety margin that had otherwise been missing." This is a reasonable conclusion.
You later take this conclusion a ster further to indicate that you believe that "the NRC's cwn expectations would dictate that nonconformance resolved by physical plant changes must be considered to reflect prior unsafe operations unless specific evaluations indicate adequate margins existed."
I do not agree with your assertion that a licensee's decision that a system, structure, or components may not be able to perform its safety function (i.e., is operable) equates to unsafe operation. For example, Generic Letter (GL) 91-18, "Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability," directs licensees, if a nonconforming condition which also may pose an immediate threat to public health and safety is identified, to first place the plant in a safe condition, then proceed with restoring the system, t/ '/-/bl-structure, or component to the current licensing basis. See Technical Guidance, " Resolution of Degraded and Nonconforming Conditions," Section 4.1.
A plant's li:ensing and design bases include substantial margin. Acceptance limits in a plant's final safety analysix .,, ort or the staff's safety evaluation report are conservatively chov.... Therefore, not meeting a regulatory limit does not necessarily equate to an unsafe condition. The i
guidance in GL 91-18 notes that licensees should be conservative in making an l
9QD QC $ 05 ? $t g 1g 9706020130 970523 {
PDR P
ADOCK0500g9 [/du4 i "I'
4 4- ,
I
} =.
l D. Lochbeua -2_ May 23, 1997 i
i operability determination. Specifically, " Operable / Operability," Section 3.3
- of the technical guidance states that "[w] hen system capability is degraded to a point where it cannot perform with reasonable assurance or reliability, the system should be judged inoperable, even if at this instantaneous point in time the system could provide the specified safety functions."
As I stated in my letter of February 27, 1997 to you, although compliance with the Commission's regulations, as a genera,l matter, provides reasonable assurance of protection of public health and safety, the agency must exercise its judgement regarding thresholds for determining the safety of plant operation. Also, the NRC's approach to protecting public health and safety is
- based on the' philosophy of defense in depth. The appropriate regulatory response to an identified deficiency can and should vary, depending on the safety significance of the identified deficiency.
Additiont11y, when a licensee discovers a nonconforming condition, it examines its options and may select the most expeditious means for correcting the nonconformance and restoring or revising regulatory margin, it may be more expedient for a licensee te make a modification to the plant than to perform the analysis necessary to demonstrate that the current condition of the plant would still provide adequate safety margin.
Finally, with regard to the findings of the Maine Yankee Independent Safety Assessment Team (ISAT), you stated that you "do not understand how it can possibly be more prudent, from a nucler.r safety perspective, to require a licensee to correct nonconformances when a plant is shut down than when the plant is operating....[or how] a problem....could be so significant as to prevent a plant from starting up yet be so insignificant as to not warrant shutting that plant down if it were operating....In short, the NRC cannot wait until some other event causes the plant to shut down before running in wich a long list of safety issues that must be resolved."
First, unless a nonconformance poses an undue risk to public health and safety, it is not prudent to require a plant to shut down and thus risk that a plant transient might occur and increase operational risks. Once a plant is shut down, however, it may be more prudent to correct the nonconformance before allowing startup, because a delayed startup does not usually leave a plant in a condition that could cause an undesirable transient.
Moreover, in the case of Maine Yankee, the staff continued to conduct inspections and to evaluate certain nonconformances after issuance of the ISAT Report on October 7, 1996. The NRC staff issued Confirmatory Action Letter 1-96-015 (December 18,1996) and Confirmatory Action Letter 1-96-015, Supplement 1 (January 30,1997) to address problems fully evaluated or first identified after issuance of the ISAT Report, and to document the licensee's
D. Loc 5brum -3_ May 23,1997 agreement to take s:ertain corrective action before restart. Additionally, actions necessary to correct some of the nonconformances at Maine Yankee can be performed only during a plant shutdown.
I trust this discussion provides you with a clearer understanding of the NRC's policy on which our guidance to licensees regarding nonconforming conditions is based. Note that the NRC recently published NUREG-1606, " Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 (Changes, Tests, or Experiments)" for public comment and that we are continuing to evaluate our positions on many of the issues discussed in the NUREG, including those raised in your letter.
I Sincerely, n i det LY.
Samuel J.M ollin irector Office oMuclear P.eactor Regulation l
e D. Lochbaum -3_ May 23, 1997 i agreement to take certain corrective action before restart. Additionally, actions necessary to correct some of the nonconformances at Maine Yankee can be performed only during a plant shutdown.
I trust this discussion provides you with a clearer understanding of the NRC's policy on which our guidance to licensees regarding nonconforming conditions is based. Note that the NRC recently published NUREG-1606, " Proposed Regulatory Guidance Related to Implementation of 10 CFR 50.59 (Changes, Tests, or Experiments)" for public comment and that we are continuing to evaluate our positions on many of the issues discussed in the NUREG, including those raised in your letter.
Sincerely, Original signed by Frank J. Miraglia Samuel J. Collins, Director
" Office of Nuclear Reactor Regulation
\
/
9 DISTRIBUTION: See attached page DOCUMENT NAME: G:\siml\YT970039 See Previous Concurrences
- To escelwe e copy of thle document,iswRoste in the box: "C" = Copy without attachment / enclosure *E fopy wnh attachment /p l-sure "N" = Peo copy l ( {f 0FFICE PM:PGE8 b SC:PGE8 l l TEditor l C:PGEBQ)fI l (A)D:DR(MhlkkM NAME SMagruder:sw Sin FAkstulewicI* BCature* DMattheUs MStosson" (TV DATE 05/ M J97 04/15/97 04/15/97 05/])/ /97 05/@/97 0FF1CE OGC ! PDI 3 D:NMd- l NAME GLongo* DDorman* SCOT l M T/j DATE 04/30/97 05/06/97 d5/f(/97/
p ~
OFFIdIAL RECORD COPY
l i DISTRIBUTION: YT970039 Ltr to D. Lochbaum fm M. Slosson dated May 23. 1997 l Central-File (w/ incoming) (YT 970039) l PUBLIC (w/ incoming) (YT 970039) l PGEB r/f (w/ incoming) (YT 970039) i' NRR Mailroom (w/ incoming) (YT 970039)
LCallan EJordan HThompson l PNorry JBlaha SBurns. OGC HMiller, RI SCollins FMiraglia RZimmerman TTMartin MSlosson DMatthews FAkstulewicz SMagruder JGoldberg OGC GLong. OGC DDorman
! l l
l l
l l
l t
, i
,W0 hcetoed l 330s, i, FROM: ORIGINAL DUE DT: 04/18/97 TICKET NO: 0970039 DOC DT: 03/21/97 1 t .
NRR RCVD DATE: 03/28/97 l D. A'. LOCHBAUM, UCS
'TO:
OR/.
I S. COLLINS FOR SZGNATURE OF : ** YEL ** Amh:>ss I
/)OA. .
, DESC: ROUTING:
REACTOR SAFETY MARGIN COLLINS
- MIRAGLIA l
THADANI ZIMMERMAN MARTIN
, TRAVERS BOHRER
' ASSIGNED TO: CONTACT:
(
He m *N l %3)R m imaw SPECIAL INSTRUCTIONS OR REMARKS -
L I l
l -
l ACTION i !
l DUE TO NRR DIRECTORS OFFICE BY + pd 76gY Ij y,de& b Sh3l't7 i
i i
I y-- .ey--- ,,3y e- , - - - - - - - -
m l UNION OF l<- CONCERNED SCIENTISTS March 21,1997 Mr. Samuel J. Collins, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission l Washington, DC 20555-0001 SUBJECf: REACTOR SAFETY MARGIN
Dear Mr. Collins:
Thank you for your letter dated February 27,1997, in response to my letter of January 6,1997, to Mr.
Hubert J. Miller, Regional Administrator, Region 1.
In your response, you indicated that I had implied that any licensee's failure to comply with the NRC's regulations corresponds to that licensee's facility having been operated unsafely during the period of nonconformance. That has never been my position, so I will attempt to clarify what I am advocating.
l The safety implications of any nonconformance,in my opinion, are best measured by the corrective actions implemented by the licensee to resolve it. The originally reviewed and approved safety margins a: the facility are clearly unaffected when the licensee is able to address a nonconformance via " soft" actions, such as successfully completing a surveillance test that had not been performed on time or accepting an apparent degraded condition as-is based on a. rigorous engineering evaluation.
However, when the licensee makes a physical change to the facility to correct a nonconformance, it is reasonable to conclude that these actions ustond safety margin that had otherwise been missing.
By way of illustration, consider a facility with a technical specification limit that containment ambient
- air temperature must'be <120'F. The accident analyses of design bases events assume an initial l ambient air temperatute of 120'F in the containment. The licensee verifies compliance with the
- technical specification by averaging a number of temperature instruments located within the containment. The licensee reports a nonconforming condition when it discovers that the methodology used to calculate average ambient air temperature is nonconservative by up to 8'F. A review of past operating data reveals that temperatures of Il6-119'F had routinely been experienced during full power operation in past summer months.
If the licensee reanalyzed all applicable design bases events for an initial ambient air temperature of
]
130*F in the containment and determined margin to safety limits, then it would be appropriate to :
conclude that the facility had not been operating unsafely. The physical plant configuration of the l facility was adequate despite the nonconformance.
Washington Office: 1616 P Street NW Suite 310
- FAX: 202-332-0905 l Carnbridge Headquarters: Two Brattle Square
- FAX: 617-864-9405 Cahfornia Ofhce: 2397 Shattuck Avenue Suite 203
% \y ic4 O b o J b] ),h l
e However,if the licensee upgraded the containment cooling system to maintain the cometed ambient air temperature of the containment $120*F, then it would not appropriate to conclude that the facility had been operating unsarcly. The physical plant configuration of the facility was inadequate. This -
' situation also applies in the case where the licensce revises procedures to direct its operating stafr to start another containment cooling unit when necessary to maintain the uncometed ambient air temperature below 110*F (i.e., to maintain the corrected ambient air temperature below 120*F). !
My position on the safety implications of nonconformances appears consistent with the guidance provided by the NRC to its licensees in Generic Letter 91-18, "Information to Licensee Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability." This guidance permits remondle eng!neeringfudgement to be used to determine that a safety function can be perfonned by a system, structure on component despite the nonconfonning l condition. When a licensee makes a physical change to the plant to resolve a nonconformance, remondle enginceringfudgement should conservatively conclude that the safety function could not be peifonned un!ca there is an analysis showing that margin existed in the nonconforming condition.
l '
This position is further reinforced by NRC actions relative to nonconservative decision making by licensces. Following the marsh grass event at Salem in April 1994, the NRC was very critical of the decision-making by the licensee's operating staff. The NRC was also critical of the command and control capabilities of the operating staff at Zion during this month's inadvertent shutdown and restart l cvent. The NRC has repeatedly informed its licertsees that it expects them to make conservative decisions when faced with uncertain and unanalyzed situations. Thus,it seems that the NRC's own expectations would dictate that nonconformances resolved by physical plant changes must be considered to rcilect prior unsafe operations unless specific evaluations indicate adequate margins existed Absent such evaluations, the conservative decision must be to assume that adequate margin did nel exist for the nonconforming conditions. !
- l It is from this perspective that I evaluate the safety implications of nonconformances. It is why 1 l cannot reconcile the findings of Maine Yankcc's Independent Safety Assessment Team (ISAT) with j the reassuring statements made to the public by NRC officials. The ISAT documented numerous nonconformances involving safety systems that were resolved by physical plant changes. The ISAT conducted vertical slico evaluations of four of the top five risk significant systems as ranked by the Maine Yankee licensce in its Individual Plant Examination The ISAT documented missing wiring for the High Pressure Safety injection (HPSI) pump, inadequate ventilation for the containment spray pump rooms, lack of overpressure protection for piping penetrating the contamment, and numerous other prob! cms. While some of these problrms were resched by "soA" setions, many of them involved physical plant changes. I am not aware of any evaluation perfonned by the licensee or by the NRC that would indicate that this facility had adequate safety margin with all of these nonconforming conditions existing prior to their resolution. In fact, the licensee reported that the missing HPSI pump wiring done increased the core damage frequency at Mainc Yankee by 6%.
Therefore, any NRC oUicial who concludes that Maine Yankee was not being operated unsafely with all of these nonconforming conditions is making, in my opinion, a nonconservative decision that is contrary to the expectations established by the NRC for its licensees..
My concern over the safety implications of nonconformances goes beyond the issue of the NRC's credibility in its dealings with the public. In your response to my lever, you stated: )
! NRC Generic Letter 91 18, "Information to Licensec Regarding Two NRC Inspection Manual l l Sections on Resolution of Degraded and Nonconforming Conditions and on Operability,"
! provides guidance for licensees when they identify degraded or nonconforming conditions.
l
, i
.~
r **
l l
l However, once a plant has been shut down, for whatever reason, it is often more prudent to !
~
permit restart only after significant nonconformances have been corrected. Thus, it is possible i that a particular deficiency that would have been insufficient by itself to warrant shutdown of a plant might be sufficient to warrant repWr prior to restart. ,
i I confess that I do not understand how it can possibly be more prudent,from a nuclear safety j perspective, to require a license to correct nonconformances when a plant is shut down than when the l plant is operating. I also do not understand how a problem, or even a parcel of problems, could be so l significant as to prevent a plant from starting up yet be so insignificant as to not warrant shutting that l plant down were it operating. The criteria for determining if a plant is safe to operate must be l independent of the plant's operating condition. The reasonable assurance threshold that a system, l structure, or component can pe form its safety function cannot be lower when a plant is running than when it is shut down - that is inversely proportional to the risk and quite frankly potentially dangerous. In short, the NRC cannot wait until some other event causes the plant to shut down before running in with a long list of safety issues that must be resolved. Such behavior has at least two adverse consequences: it erodes public confidence in the NRC's regulatory oversight function and it provides incentive for licensees to keep problem plants running under degraded conditions.
I realize that the NRC is reviewing its inspection and enforcement programs based on lessons learned
!, from Millstone, Salem and Maine Yankee. I am prepared to assist the enhancement of these vital l programs in any way that I can. Please do not hesitate to contact me if further clarification of my.
j position is required or ifI can answer any questions related to my concerns.
Sincerely, l
l002 d 0'
- i David A. Lochbaum l Nuclear Safety Engineer i
l cc: Chairman Shirley Ann Jackson Commissioner Edward McGaffigan, Jr.
l United States Nuclear Regulatory Commission United States Nuclear Regulatory Commission l
[ Washington, DC 20555 Washington, DC 20555 l
l Commissioner Kenneth C. Rogers Mr. Philip A. Olson, Rm. 2440 l United States Nuclear Regulatory Commission United States General Accounting Office Washington, DC 20555 ,
Washington, DC 20548 l Commissioner Greta J. Dieus l United States Nuclear Regulatory Commission Washington, DC 20555 i Commissioner Nils J. Diaz i United States Nuclear Regulatory Commission Washington, DC 20555 l
i l
l i
I 9
C O(O . C O O'O O p eeee s
- a a a m a ._. a _ a ,_ 4
- n o n . ..
- ,,1
<. o ,
....,' q ., , . . ,.
.. , s
. ,,. .o s.
- (. c~ ,
' cc w f- .i g~ e. ^
- rs' s "~o f. ' -Q 9 )em ( J) e e
a .a. e e e e a/ ee e e-o..
(. .a e r t- e e e a "a , n,,se..;
.i a w.
,,) .., . ,. , , 4
,' 1 s, . ,
i
,,,. . - c-
. , .,'.. .*..45
~ g i .
. .u, . . c...
s
- . g..c. 7.. u .
., ,%A w e.K e- (:. ,
If R s@ y t <_' O y n 1f l ,
m '
._ w.' .' '.- : --
~-
.7. ; -:: s ..' . ~ Q^f --&,k _. *}
! UNION OF f a% .- .
lALWAYS1,? t z CONCERNED E , ,#
"7l p.'0~="m a L_.r.
i SCIENTISTS ~ s .
m1 ~~
1616 P Street NW Suite 310 j,
Washington. DC 20036
! Mr. Sarnuel J. Collins 3
- Director of the Office of Nuclear Reactor Regulation 3
United States Nuclear Regulatory Commission ,
Washington, DC 20555-0001
^
~ = = = = =
2esss-eaei 1, ,1,1 l 1, , , ,1,1. ,1,1, ,1,1,11, , ,11, , ,11, , , , , ,11, ,1,1) a .- .
O g .s - O
..w- - ., . , , , ~ ., ,.-m,. -r-..,e.,-.s,,c~..v,,,-,., , ,,w-, ,_-e,,,,,,,,.,y.-.w.,,,,. ,,.,,,w.- .n,,~v... ,w