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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny ML20206S2541999-01-20020 January 1999 Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001 ML20199J2631999-01-18018 January 1999 Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station ML20199D0271999-01-11011 January 1999 Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area ML20199A6521999-01-0707 January 1999 Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101 ML20198T1061999-01-0606 January 1999 Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs ML20198K0331998-12-23023 December 1998 Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months ML20198H0181998-12-22022 December 1998 Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs ML20198H8521998-12-16016 December 1998 Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416 ML20196H4461998-12-0202 December 1998 Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits ML20196B4471998-11-23023 November 1998 Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed ML20195J8451998-11-12012 November 1998 Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC ML20195C7201998-11-11011 November 1998 Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment, ML20195E1221998-11-10010 November 1998 Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability ML20155J6851998-11-0505 November 1998 Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability ML20155H5641998-11-0202 November 1998 Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented ML20155G3741998-10-29029 October 1998 Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-30
[Table view] |
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Mr. Joseph M. Hendrie Chairman I-Nuclear Regulatory Commission F Washington, D. C. 20555 ..
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Dear Mr. Chairman:
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I have recently been contacted by one of my ccustituents, a Freeholder in Ocean County, New Jersey, with respect to the adequacy of safety systems at the Oyster Creek Nuclear Generating ..
Station. - _
I am enclosing, for your use and information, p.
a copy of the correspondence I received. I would '
very much appreciate your looking into the =atters raised in Mr. Gasser's letter, and providing me with ,'.
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any thoughts or observations you might have on this .,__
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With kind personal regards.
Since y, illiam Hu ' es ~"-~~
Member of Congress WJH:ecs h. .. ..
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THE BOARD OF CHOSEN FREEHOLDERS Ocean County Toms River, New Jersey Robert A. Gasser 08753 244 2121 Freeho! ' Eat.420
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AIay 22,1979 Congressman William J. Hughes Cannon House Office Building #327 Washngton, D. C. 2051v
Dear Congressman Hughes:
This letter will confirm our conversation of Friday concerning the failure o'f JCP&L Co. to install a safety device, namely a recircula-ting pump trip, required of it by the N. R. C. The entire episode began approximately two years ago when then Assemblyman Peter Shapiro
" leaked" the results of a study being done for the D. E. P. by a Mr. P. R.
Ihvis who ' stated in his advance re-findings that the possibility of an accident at Oyster Creek was 100 to 1. Not particularly encouraged by the poor odds, I took it upon myself to write to Mr. Davis and ask him for his findings and conclusions. After much effort, I finally received a letter from Air. Davis which stated that the odds were actually 1,000 to L based upon the installatioa at the plant of the recirculating pump trip.
I naively assumed that that would be installed under the supervision of the N. F.. C. or by the D. E. P. for whom the study was made. Shortly after the 3-11ile accident, I read a report in the newspaper by Dr. Glen Paulson of the D.E. P. in which he stated that he was satisfied with the safety of Oyster Creek in reliance upon a study made by the D.E.P. of its safety. I was disturbed by that statement and wrote to air. Paulson citing to him the findings of Alr. Davis and questioned the installation of the recirculation pump trip. To date I have not received a reply from air.
Pauison although I have followed up that letter in the last week or two.
1034 . o
Congressman William J. Hughes Page 2 May 22,1979 Within the month. Oyster Creek has been shut down with a severe problem in its cooling devise. In speaking with a reporter from the Asbury Park Press who covered that well-publicized event in the Asbury Park Press dated May 11. 1979, it was determined that the recirculating pump trip had not, in fact, been installed nor had the procedures ordered by the N.R.C. and agreed to in the Spring of 1978 by G. P. U. been implemented and put into effect.
I attach to this letter my notes to substantiate this event and would hope that you would seek, on behalf of my constituents, an answer from the N. R. C.of why they did not see fit to require and insure that G. P.U. would, in fact, actually installthis device so that the odds could be 1,000 to I instead of 100 to 1.
Your continued help in this regard is greatly appreciated by me, 8,erely, I'* Y c.'
ROBERT A. GASSER RAG:rdv 1034 7
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. .. 'l-P. R. Davis 1935 Sabin Driva Idaho Falls, Idaho 83401 Robert A. Gasser, Freeholder Board of Chosen Freeholders Ocean County Toms River, New Jersey 08753 Dear Mr. Gasser This is in response to your letter to me dated May 17, 1977 in which you ask a number of questions related to the safety of nuclear power, specifically regarding my accident analycis of the Oyster Creek 31 ant. I appreciate your interest in this matter. I hope I can clear up
_ome of the confusion that undoubtedly exis relative to my Oyster Creek analysis.
My rough first draf t report, which was unfortunately " leaked" to the public by Assemblyman Shapiro, did contain a preliminary conclusion stating that the odds of a s cre meltdown accident in the Oyster Creek reactor,were 100 to 1 over its remaining 30 year operating life. This first draft was given a very restricted distribution for technical review and comment to knowledgeable people in the nuclear field (not all of whom were associated with the pro-nuclear establishment). The purpose of this distribution was to obtain input from appropriate individuals and organizations relative t2 the validity of the analysis. Due to the limited' time I had available to' do the study and the limited resources which could be supplied by the state, Dr. Glenn Paulsen (the Assistant Commissioner for Science in the New Jersey Department of Environmental Prctection) and I agreed that. such a pee. review would be mandatory to help assure that all relevant and definitive technical information had
':een included in the study. We do not knew how Mr. Shapiro obtained a copy of the report, given the extremely limited circulation of the first draft.
Folicwing my completion of the first draf t, two sets of information were obtained which subsequently led me to conclude that the odds of a core melt accident in Oyster Creek were icwer than those quoted in the first draf t. First, it was pointed out by GPU Corporation (the company
.. which controls Jersey Central Power and Light, the owner / operator of Oyster Creek) that I had neglected to account for the fact that the Oyster Creek plant contains certain pressure relief capability substantially greater than that included in the Peach Bottom reactor used as the basis for boiling water reactor risks in the Rasmussen Study (WASH-1400).
Since I had used the WASH-1400 results as the basis for the Oyster Creek accident probabilities (with modifications which I believed appropriate),
my result, according to GPU, was not valid. I have since verified that indeed the Oyster Creek plant does have substantially greater, pressure relief capacity than the WASH-1400 analysis assumed.
greater pressure relief capacity would act as an effective FurthermoYe N hTI B , g p {-
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feature, reducing the probability of a core melt accident. Sc ., p
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~ Mr. Robert A. Gasser June 27, 1977 Nuclear Regulatory Commission issued a letter to GPU requiring than an automatic recirculating pump switch be installed on the Oyster Creek plant. This feature, which was included in the Peach Bottom reactor analy7ed in WASH-1400, would also effectively reduce the core melt probability in Oyster Creek after its installation. It is my understanding that GPU has cormitted to install this device next spring.
The net result of these two considerations was to reduce the core melt probability in Oyster Creek to a value of about 1 in 30,000 per year, which is the conclusion in the final draft of my report. (This would ue equivalent tn a core melt probability of about 1 in 1,000 over the remaining 30 year life of the plant if,the annual probability remains constant.) These two changes, plus other less significant ones, are fully explained in the final draft of my report, which I believe you have previously received directly from Dr. Paulson.
I agree completely with your belief th'at the state should provide surveillance activities for nuclear plants within its borders. The NRC does a reasonable job in this area, but they are spread quite thin. I have believed for some years that nuclear power can be made safe only if continuous, competent, and objective surveillance is supplied for all aspects of the industry. Some of this is underway at present, but more can and should be done. Recent proposed intentions by NRC to upgrade and intensify their nuclear power plant surveillance activities are gratifying in this regard, but I believe the states should augment and supplement some of these activities. -
Regarding the article you enclosed dealing with alleged shortcomings of the Rasmussen Study, I cannot make a substantive evaluation since the allegations are very general and not supported with specific technical detail. I can assure that the study has been carefully scrutinized by over 100 groups and individuals throughout the country. I myself directed a very extensive review of the Study for the U.S. Environmental Protection Agency, and although we found many errors and emissions, we could find very few deficiencies which would tend to'significantly alter the final result. (Some of these deficiencies would tend to lower the risks . ) It is easy to find problems and questionable analyses in the Study, but these shortcomings must be shown to be quantitativel, significant before the end results can be claimed invalid.
If you have further questions on the report, or on information contained in this letter, do not hesitate to contact me.
. Sincerely, W O c< L P. R. Davis -
1034 _i
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'd the NTX'. workmg on an ea- One nue! car s.afety expert $6 eses e -
t?.3t the n :ml s.5tdown on *.:ay sad t!!e y Gif*erent protdern, dectded to raqua:v (hster Crect mesent is a gW cram!c .
r.v.;ur; d on in de bel of reac'er coolio.t tants taie Oystee Creelt to inenrporate as the meannesses ar.herent in the re!atic~*
2:er - may hase been ac -avstcJ by a.rtomatic feature known as a "reciren!ati:n twae t the nue! car po cr me.stry and ?"
puttto st*p
4 W J .c;i=3 :n mame the piar.t ufer, May *e ****9a?. !te Witcr btj in* ne ic !::re, part of the automatse m.fe+y Rahrrt Ivi!.arif. * %o cugned frem t! .
eLacuitry, wou4 turn c,t! powcr to the Dve N':cl*2r 1(c::W.uory Acency us!! . .t
- a:le the renetar vessel, necessary to cJol the ' purops in certain rituations.
.i.cle:r core cet"t ~ ~ -
- **-ks far the Um of Csemed emtu aster t:te f!ssiaa Decause the pum;s were not to neep ra:> Met e: 1.4 "~his e s pt 2N.A'r ex2ma r e a c "t tas beca nac. sht.tting their valves hecar.e unneces. of me aistervice beseg ocn ...a puo'ic ra tt,
. sary. JC1s1. never changed its procedsrs, N"AC ard the (auc; ear) ind.st y by centira.
sbi.t devt. d.mpped c.CO.,y313 l r e fts re ::113 'o , hawawr. aHi asr.;ttng the rubtae :r t - - pw -
li feet (3 bettvee3 vThus, when the reactor taut down May 2, p. ants a-e see because at tne mult pie uve-ene and two fed. oprTatars ebned the v31Ves. but, for us- of Iafety 5Diete.S.
W .g to restfrf:ory Macsd:y_ at as bion reastms, they shut not two. but four valns. . accanse L.acy a!!ow the piants to F-
.m2 *nce'M ut t'.'at'ain.70ft. punt oer-stars sete S cning a procedure written by S;ne the ff.h silve already had tees a'e s . - 4 safety sys: ems out of servic '
- CNI die's prever.ted a pro 5iem 2st bs s' tut to a'!aw n
- s!.atenance en that aurrp. tlus mthey ets:r,w re desp recedan.y.
3 tricadent ist- 0"te- N' p'a :ca "te piant smee it s .,s bust. ; eft no nsy u ty for ce aater fre.n 'tu com
- Lt reevnt char.ces Itt tre purfs auto
~ decsers 'o get bactt into me enra. P w',;at an. . m W bee" "a ' .1 fk
- e ma:1c r. fety equt; ment may have inade cc" Only fne small (twunen o'amater) m 4 mnt mes at A , an nrwWu stsolete. vaWs &Ilowed witte to flew trito de corn, pm p as M m a e p
"'"""'8'I"
&uuse the e;e=1fers fr.' lowed the otuieN Since steam was sn3 f!ouing from the top of 1."e -3:cd.;te eng*r. cars paesent at the the *eartor veasel, the water level a00arent. D
' "I '" N mecuni : peculated the over level in the ly drytvad until it reached eqt:ibbrtum. *mese sM be ccr .dered earsm;s."
rever Jr- ;v4 ;curr man it tLas in the 10- the fuel rg semewnere betweca oue and two feet aanve Pc-d ws wm eth m PAets shcid N dasicaed ta hante s.txt::ns .,.ae year ha'- y of e p* set. -
'"a-' # : Me's s'.sJ A e-e mts'ed by in-
. ILid the e'us Nes unenvered. he >me*tse that cf Ly 12;tomat.ca.!y.
cc: s 4 vc't ;'tve fPc"I a distor*cd ee's heat genc*atad by de raGsc3chve Mc3y "The opers: Ors sMud % sd had 2'
. f :r.e s :c.:wt inside 2e reactor.
- hey gom; on m.skte them could have esused them "lonitor the gc.; ment !cr the .rst -
.rcJ ea a ::-n *tch marned them of the to spint. rescasm; radioactive partaces and T. mutes or so," he suces:ed. ""up;s h3p-rnri dr.p. bMeeng the sarer ;evel us gases into the etwng e ater. pen too quickly for h.m:ns w ev
- r.t .-:.1 seme M mmutes r.fter te of*;t* At about 2.M degees, the metal of the Perard reraded a !ctter sent 'o 2e L
- Pal f t: 9. fods would beg n to re.et chem:caJy with Atomic Energy Cammnen in %6 ty -
1 c.'.*ir to : the t'teery advanced the water and steam croemd ' hem, reicating ttu:hty (on'rol vacubst 4ho w.s :tsc:r; hydregen, muen nke happened at the D.rce
- w. :nc trcubie actuaJy started hacic The m.an erote. "! abou!d it.nx *sen P-otas-i.i ?: M.le IMand accent in March, -
d.m m : 1 ferrcJ sht:t.bm11 or ser Lwra.wn it5 mathrc of a remrase-siM n:~a " :n Se;tamber of :hst yt'ar. opera' Experts enently agee : hat no hy,.'.rt> reactnr *.-fny st t) *ul realize that J 102 mu. *: tr.c p:aat's two .soution ecn. gen bubble tout.1 have to- ref, howeve . due have 2 number of 'icir. misses suh 4 arn
. . .s 9 c-ol dm. tne reic'er. to the dt!!c ence bemen Three !.1Je 1.s. numner cf -eac ors cwrating. **en :.ca :)
"fe too large radiator.t;ke devices land's pre *sururd safer *cartar and Cyuer ti a Iarce number, sooner nr later, you sd
. v'i %1 --6 0 r;bes af 37ter, and are de. Creek's bonmg miter rescior. get a hat."
' :: co 4 stam covg fra.3 the hot But the raittatran relewd frem the sp'it *he pLitit W1 not he adowed to *r%2r*a
~~ ef me cactor 2 :d turn it back into rods at the sery least wou;d have me eased epenuers i.nni :Ss acesend or ;arar. NT
%: '?. the radiatiert th.st,?.out the piar.t, necessi.
tatm; an egenw cicanu;). 't cou;J pcssiblY say,y e ,y.rts .cc retteslet me mce'.
Tha :r-r Cows bac!c demi mto the reac- and att kcap t*e p tSt sl tut dawn Tita Fy
- . r. = x.J same af the ce:.densers' u3ter is have resutted in the idease af abncr'r.al are saumed wi h tne pewr cc te.."-
arvd eto s:e: t aad vented outside the amounts of rManon from the plart.
' ir t. Should the ro s thven e hot er:our % to oce.g me:sures mg.
to keep a samr:ar m den: frJe L.t t's op rators had no scener ac'ivat* melt. exper's bei;ese t'. y rouid siump in a One measure already t:tett by JCFC .
.=1 :*.e et.n fea. seas m ".e't they recetved as molten mass to the bottom of the resctor and at rm anfi s :i.ded a breajt n the pipes even mett thrtnr:n the bottom of the steet wasaccordm; to r!envers to ivtall plasue ant rr.anseer Domid Ron.
over ^.e -ecnu.
c.a.y *a 2e ee. denser. and cor.erete strue'ures surroundin; : hem.
ation pii p vse cont-et:; to forc= t*e
~.. M :*e at rm 240maticaJr shuts off causag s .aasor sccet,
,= ri-;ee:g.r, mey mere loret'd to outw;L the The meldest on my 2 was euce Wed valves. cpeastor to 'hinst talce* Mt can: g tre a :.. : :c e;re:::r by / resetung is each tme by the iacit of one qi tuJ au%i3ry power Afthot.gi it uas nct mt.da s'i:;r uhy the
-r.2 era ; ? f :7 so .rd-d. transformers. Decause one of the trusfo-*n- remor operstar elesed fnur viiws instead c.
d..- +t 3r.s!yts shewed that 3 flow ers mas out of mee at me time of the ace 1- tso, P.scs assumed sor e respt'tm.bj.ty. c .r*-
J
- etr .rr-t n 1 of te cast ree'I~.d.2tson Jent, two (mtwate* pumps *tuch norma'jy
- c. ~ -* :rA ?ts rese*or w1s csurtne the.-would have surpFed mater to the reactar
.w wnre,.u. patld n enung. "We t .:y h2se era h.m a0"313 t
- c. r . -ii. n, e.fr,,e.m7 ware i t. vel rertw s r'-
". pre
' aj ';*s an (h.** Ort! alaf"t ?#'ITES A thed ; vre which us d v'*c4 in r;n o k iep **? problem from repeating 13 on e!cetrie.ty sufT' c'J by te tranif0 t".** nit ~t !rvi :he fact $st tre sr sc r Mr :*a 9t.* ;:n hst year. r.
t hach %ns wo k'e2. faded lee 3use o( 33 s3?ct Cd lesci inth*.aters "I !Pe et***at -ar"1
-nc.3, :pe sters were :c;J to tr:au Jy pun:o grebicm. a*e ic1?M Pt f *:e reafter Vc 4e! EaJ. :n 3n
- one emer;;ency tesci pcrater s:;ried. e rNec $cc arud L'e ere ca ' "
Enr;tus.
I
'his mce is sepanted fmt de c"e t -
a e trutar Weiri. Normady. r;;h 3r ;ct.st y c f'cCtre'faWs hp Opedi. A 4 ?er :es el .s f f;e same in the enre 2.d in tre annu;us.
, 248 #U3 alI I Mr's close't. 'he aster n !
c3re ein 'a:t wir*.eul af!cch?C "e .a- Ns bel Dus orcnnrs use1 to LN cma; s.tc.:.on "Ltd N.M s1 d.dn Iow.t resMe $at 'Pc c'te xa et A* lent".e 904 .aw 'ow" 4.J a-=st % < -t V8 5:" lh** t*3C Ite *1?er di l,*e ye gag D4s f 3 2 #w*l fryr f"at e-? t. 5,sg .5.n 3 me f ael. ' *y rs Ssco to 3e..cre e. vm W *J 2n t*IcC!r**:2rl *o cVeX egt !"*
1 1034 -