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Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARJPN-99-029, Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirement for Nuclear Power Reactors1999-09-20020 September 1999 Comment Supporting Proposed Rules 10CFR50 & 72 Re Reporting Requirement for Nuclear Power Reactors JPN-99-022, Comment Supporting Proposed Rule 10CFR50 Re Requirements for Industry Codes & Stds1999-06-22022 June 1999 Comment Supporting Proposed Rule 10CFR50 Re Requirements for Industry Codes & Stds JPN-98-052, Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Util Endorses & Supports Position Presented by NEI & Commends Commission for Initiative to Address Disconnects1998-12-21021 December 1998 Comment Supporting Proposed Rules 10CFR50,52 & 72 Re Changes,Tests & Experiments.Util Endorses & Supports Position Presented by NEI & Commends Commission for Initiative to Address Disconnects JPN-98-050, Comment on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Encourages NRC Staff to Withdraw Proposed Change & to Work with Nuclear Power Industry & Other Stakeholders to Accomplish Goal1998-12-14014 December 1998 Comment on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Encourages NRC Staff to Withdraw Proposed Change & to Work with Nuclear Power Industry & Other Stakeholders to Accomplish Goal JPN-98-021, Comment Opposing Proposed Rule 10CFR50 Re Codes & Stds1998-05-26026 May 1998 Comment Opposing Proposed Rule 10CFR50 Re Codes & Stds JPN-97-037, Comment on Final Direct Rule Changes to Paragraph (H) of 10CFR50.55a Codes & Standards. Effective Date of New Rule Should Be Delayed Until Listed Concerns Can Be Resolved & Appropriate Changes Incorporated1997-12-0101 December 1997 Comment on Final Direct Rule Changes to Paragraph (H) of 10CFR50.55a Codes & Standards. Effective Date of New Rule Should Be Delayed Until Listed Concerns Can Be Resolved & Appropriate Changes Incorporated ML20029C5771994-03-11011 March 1994 Comment on Proposed Rule 10CFR20 Re Draft Rule on Decommissioning.Informs That 15 Mrem/Yr Unreasonably Low Fraction of Icrp,Ncrp & Regulatory Public Dose Limit of 100 Mrem/Yr ML20045F2451993-06-28028 June 1993 Comment on Proposal Re Radiological Criteria for Decommissioning NRC-licensed Facilities.Opposes Proposed Criteria ML20128B0581993-01-29029 January 1993 Order Imposing Civil Monetary Penalties in Amount of $300,000.Violations Indicate Significant Breakdown in Mgt & Administrative Control of Licensed Activities at Plant JPN-02-034, Comment Supporting Proposed Rule 10CFR50.54 Re Receipt of Byproduct & Special Nuclear Matl1992-07-0606 July 1992 Comment Supporting Proposed Rule 10CFR50.54 Re Receipt of Byproduct & Special Nuclear Matl ML20079P9961991-11-0404 November 1991 Response of PASNY to Objections of DM Manning to Settlement Agreement.* Concludes That DM Manning Request That NRC Deny PASNY & NRC Joint Motion for Approval of Settlement Agreement Should Be Denied.W/Certificate of Svc ML20086B9681991-06-0606 June 1991 Affidavit of RA Locy Re DM Manning Refusal to Provide Second Urine Sample on 901009 ML20086B9351991-06-0606 June 1991 Affidavit of W Fernandez Re DM Manning Refusal to Provide Second Urine Sample on 901009 ML20086B8931991-06-0606 June 1991 Affidavit of DM Manning,Senior Reactor Operator,Being Duly Sworn,Response to Order Suspending License & Order to Show Cause Why License Should Not Be Revoked ML20086B9891991-06-0606 June 1991 Affidavit in Support of DM Manning Application to Have Certain Records Withheld from Public Disclosure,Per 10CFR2.790 JPN-91-021, Comment on Proposed Rules 10CFR71,170 & 171, Rev of Fee Schedules;100% Fee Recovery. Endorses NUMARC Comments. Approx 300% Increase in NRC Fees for FY91 Will Have Major Impact Upon Operating & Maint Budgets of Plants1991-05-13013 May 1991 Comment on Proposed Rules 10CFR71,170 & 171, Rev of Fee Schedules;100% Fee Recovery. Endorses NUMARC Comments. Approx 300% Increase in NRC Fees for FY91 Will Have Major Impact Upon Operating & Maint Budgets of Plants JPN-91-005, Comment Re SECY-90-347, Regulatory Impact Survey Rept. Util Concurs W/Numarc Comments.Analysis of Info from NUREG-1395 Insufficient to Complete Evaluation.Root Cause Analysis of Seven Themes Listed in SECY-90-347 Recommended1991-01-28028 January 1991 Comment Re SECY-90-347, Regulatory Impact Survey Rept. Util Concurs W/Numarc Comments.Analysis of Info from NUREG-1395 Insufficient to Complete Evaluation.Root Cause Analysis of Seven Themes Listed in SECY-90-347 Recommended JPN-90-068, Comment Supporting Proposed Rule 10CFR51 Re Renewal of Nuclear Plant OLs & NRC Intent to Prepare Generic EIS1990-10-22022 October 1990 Comment Supporting Proposed Rule 10CFR51 Re Renewal of Nuclear Plant OLs & NRC Intent to Prepare Generic EIS JPN-90-067, Comment on Proposed Rules 10CFR2,50 & 54 Re Nuclear Power Plant License Renewal.Endorses Comments Submitted by NUMARC1990-10-15015 October 1990 Comment on Proposed Rules 10CFR2,50 & 54 Re Nuclear Power Plant License Renewal.Endorses Comments Submitted by NUMARC JPN-90-052, Comment Supporting Petition for Rulemaking PRM-50-55 Re Revs to FSAR1990-07-0909 July 1990 Comment Supporting Petition for Rulemaking PRM-50-55 Re Revs to FSAR JPN-90-050, Comment on Proposed Rule 10CFR55 Re Operators Licenses Mod for fitness-for-duty.Proposed Rule Will Place More Stringent Restrictions on Licensed Operators & Unnecessary1990-07-0202 July 1990 Comment on Proposed Rule 10CFR55 Re Operators Licenses Mod for fitness-for-duty.Proposed Rule Will Place More Stringent Restrictions on Licensed Operators & Unnecessary JPN-89-008, Comment Opposing Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants1989-02-27027 February 1989 Comment Opposing Proposed Rule 10CFR50 Re Ensuring Effectiveness of Maint Programs for Nuclear Power Plants JPN-88-063, Comment on Proposed Rule 10CFR26 Re Fitness for Duty Program.Util Has Constitutional Concerns Re Proposed Random Testing Which Should Be Fully Addressed Prior to Rule Being Promulgated.Endorses NUMARC & EEI Comments1988-11-18018 November 1988 Comment on Proposed Rule 10CFR26 Re Fitness for Duty Program.Util Has Constitutional Concerns Re Proposed Random Testing Which Should Be Fully Addressed Prior to Rule Being Promulgated.Endorses NUMARC & EEI Comments JPN-88-056, Comment Supporting Proposed Rule 10CFR50 Re Advanced Notice of Proposed Rulemaking Concerning Regulatory Options for Nuclear Plant License Renewal.Supports Comments Made by NUMARC Nuplex1988-10-28028 October 1988 Comment Supporting Proposed Rule 10CFR50 Re Advanced Notice of Proposed Rulemaking Concerning Regulatory Options for Nuclear Plant License Renewal.Supports Comments Made by NUMARC Nuplex ML20247N7531988-07-28028 July 1988 Petition for Rulemaking PRM-50-53 Requesting NRC Action to Review Undue Risk Posed by BWR Thermal Hydraulic Instability.Nrr Should Issue Order Requiring All GE BWRs to Be Placed in Cold Shutdown for Stated Reasons JPN-88-015, Comment Opposing Proposed Rule 10CFR50 Re Licensee Announcements of Inspectors.Rule Includes Requirement Contrary to Mgt Notification Practices.Rule Should Clarify Length of Time Applicable Once Inspector Arrives on Site1988-04-18018 April 1988 Comment Opposing Proposed Rule 10CFR50 Re Licensee Announcements of Inspectors.Rule Includes Requirement Contrary to Mgt Notification Practices.Rule Should Clarify Length of Time Applicable Once Inspector Arrives on Site ML20154G6131988-04-0101 April 1988 Comment Supporting Proposed Rule 10CFR50 Re Alternative Method for Leakage Rate Testing.Believes Method Accurately Calculates Containment Leakage Rate W/Less Statistical Uncertainty than Total Time Method JPN-88-002, Comment Supporting Proposed Rule 10CFR50 Re Proposed Policy Statement on Integrated Schedules for Implementation of Plant Mods.Concerns Re Schedule as License Amend Expressed1988-01-25025 January 1988 Comment Supporting Proposed Rule 10CFR50 Re Proposed Policy Statement on Integrated Schedules for Implementation of Plant Mods.Concerns Re Schedule as License Amend Expressed JPN-87-062, Comment on Proposed Rules 10CFR4,11,25,30,31,32,34,35,40,50, 60,61,70,71,73,74,75,95 & 110 Re Retention Period for Records.Proposed Changes Ineffective in Reducing Record Vol & Rule Remains Inconsistent & Complex1987-12-31031 December 1987 Comment on Proposed Rules 10CFR4,11,25,30,31,32,34,35,40,50, 60,61,70,71,73,74,75,95 & 110 Re Retention Period for Records.Proposed Changes Ineffective in Reducing Record Vol & Rule Remains Inconsistent & Complex JPN-87-053, Comment Supporting Proposed Rule 10CFR50 Re Revising Backfitting Process for Power Reactors.Minor Alterations Urged Re Conditions Under Which Backfit Needed to Assure Adequate Protection1987-10-15015 October 1987 Comment Supporting Proposed Rule 10CFR50 Re Revising Backfitting Process for Power Reactors.Minor Alterations Urged Re Conditions Under Which Backfit Needed to Assure Adequate Protection JPN-87-051, Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl1987-09-28028 September 1987 Comment Opposing Draft NUREG-1150, Reactor Risk Ref Document. Reduced Uncertainty in Risk Assessment Found to Be Significant W/Respect to NUREG-1150.NUREG Also Does Not Consider Value of Operator Actions.Addl Comments Encl ML20039G7411981-12-0707 December 1981 Affidavit Supporting NRC Motion to Dismiss Ucs & Ny Pirg Petitions for Review of NRC Decision Re Status of Offsite Radiological Emergency Response Plan.Emergency Planning Evaluation Process Incomplete.Related Correspondence ML20038B9421981-12-0404 December 1981 Petition to Enforce & Modify License Conditions.Director of NRR Should Find Util in Violation of License Conditions. Conditions Should Be Modified to Prevent Anticompetitive Activities.Apps & Certificate of Svc Encl ML19262C1121980-01-22022 January 1980 Response to Show Cause Order Re Implementation of Lessons Learned Task Force Category a Requirements.Util Has Complied W/All Requirements Except 2.1.4.2,due to Unavailability of Equipment.Affirmation of Pj Early & Certificate of Svc Encl ML20064C9411978-10-0606 October 1978 Requests Hearing on Application for OL Amend Filed on 780726.Amend Would Authorize Increase in Spent Fuel Storage Capacity & Revise Design Features & Operating Limits 1999-09-20
[Table view] Category:PLEADINGS
MONTHYEARML20079P9961991-11-0404 November 1991 Response of PASNY to Objections of DM Manning to Settlement Agreement.* Concludes That DM Manning Request That NRC Deny PASNY & NRC Joint Motion for Approval of Settlement Agreement Should Be Denied.W/Certificate of Svc ML20038B9421981-12-0404 December 1981 Petition to Enforce & Modify License Conditions.Director of NRR Should Find Util in Violation of License Conditions. Conditions Should Be Modified to Prevent Anticompetitive Activities.Apps & Certificate of Svc Encl ML19262C1121980-01-22022 January 1980 Response to Show Cause Order Re Implementation of Lessons Learned Task Force Category a Requirements.Util Has Complied W/All Requirements Except 2.1.4.2,due to Unavailability of Equipment.Affirmation of Pj Early & Certificate of Svc Encl ML20064C9411978-10-0606 October 1978 Requests Hearing on Application for OL Amend Filed on 780726.Amend Would Authorize Increase in Spent Fuel Storage Capacity & Revise Design Features & Operating Limits 1991-11-04
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE COMMISSION In the Matter of l POWER AUTHORITY OF THE STATE [
Docket No. 50-333 OF NEW YORK ,
(James A. FitzPatrick Nuclear !
Power Plant) ,
POWER AUTHORITY OF THE STATE OF NEW YORK'S ANSWER TO ORDER TO SHOW CAUSE REQUIRING IMPLEMENTATION OF CATEGORY "A" REQUIREMENTS FOR THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT On January 2, 1980 the Nuclear Regulatory Commission's Director of the Office of Nuclear Reactor Regulation issued an order to show cause requiring that the Power Authority of the State of New York (" Authority") demonstrate why, by January 31, 1980, it should not implement all of the " Category A" require-ments of NUREG-0578 as supplemented by the Nuclear Regulatory Commission's ("Commis sion 's " ) letters dated September 13, 1979 and October 30, 1979.
The Authority submits that it has complied with all such applicable requirements as of January 1, 1980, except for require-ment 2.1.3.a which concerns installation of equipment to provide a direct indication of pressure relief valve position. With respect to this requirement, the Authority has ordered the necessary equip-ment but it is not presently available. The Authority expects that the nectasary equipment will be available in March 1980.
1816 273' 8001280
. RESPONSE TO THE ORDER TO SHOW CAUSE With respect to the allegations of Paragraph I of the order to show cause, the Authority admits each of the allegations.
With respect to the allegations of Paragraph II, the Authority admits each of the allegations, except the Authority denies knowledge or information sufficient to admit or deny what the Commission has concluded concerning prompt implementation of certain actions.
With respect to the allegations of Paragraph III, the Authority admits each of the allegations insofar as they apply to the Authority and denies knowledge or information sufficient to respond to the allegations as they affect or apply to other licensees. The Authority expects, based on its current information and the undertakings made to it by vendors and contractors, that a thirty day period after delivery of equipment is a reasonable and practical time to complete installation of such equipment and that all equip-in quest,on should be delivered and installed by June 1, 1980.
The Authority denies knowledge or information sufficient to respond to the allegation that implementation by January 31, 1980 is necessary to provide continued assurance of public health and safety.
With respect to the allegations in Paragraph IV,
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the Authority respectfully refers the Commission to the following demonstration:
1816 274'
DEMONSTRATION OF UNAVAILABILITY OF NECESSARY EQUIPMENT Equipment
Description:
The Authority has purchased a safety relief valve monitoring system from Babcock and Wilcox, Power Generation Division ("B&W"). The system consists of an acoustical monitor mounted on each valve, a charge amplifier, signal conditioning equipment and a control cabinet to be located in the control room. Associated cabling has been purchased separately.
Equipment Fabrication and Delivery:
The critical path item in fabrication of the monitor-ing system is the control cabinet. The Authority has been informed by B&W that the cabinet is NEMA 12 design, manufac-tured by Hoffman Engineering Company and will be qualified to IEEE-344. The earliest anticipated receipt of the cabinet by B&W is February 23, 1980. B&W must install the electrical components and wiring in the cabinet and ship it to the site.
On this basis, B&W's earliest estimate of date of delivery is March 15, 1980. A copy of a letter to the Authority from B&W detailing B&W's schedule is attached as Exhibit "1". The Authority is monitoring the progress of B&W and where possible will continue to expedite fabrication and delivery.
Installation:
The Authority will install the direct relief valve indication system within 30 days of receipt of the equipment unless it appears that the 1980 refueling outage will begin within the 30 days. If this should occur, the installation 1816 215
_4 will be scheduled consistent with other outage activities and will be completed prior to plant start-up.
Public Health and Safety Implications:
The Authority has proposed a reasonable schedule for implementing the relief valve indication system and believes that, pending installation, public health and safety are adequately protected because of the following considerations:
- 1. The relief valves at the FitzPatrick plant serve the safety functions of overpressure protection and backup to a single high pressure coolant injection system. Therefore, they are not isolable. Post accident or post-event response by operators of a BWR are chiefly governed by reactor vessel level instrumentation in order to assure core coverage. Such instrumentation was not present in the PWR design of TMI.
- 2. At the FitzPatrick plant there currently are temperature elements at each relief valve discharge which give indication of individual relief valve opening and which can give indication of slow leak-ages through temperature trend analyses.
- 3. The Authority's procedures for stuck open relief valves and small break LOCA's can be implemented without the proposed relief valve indication system.
- 4. Relief valves in BWR's are frequently used in miti-gating plant transients. The Authority's letter 1816 276
to the Commission dated October 22, 1979 provided a history of events where relief valves have stuck open. In each of the 50 events the reactor was depressurized, the stuck valve was repaired or replaced and the plant placed back into service.
At the James A. FitzPatrick plant eight (8) out of eleven (11) relief valves have been modified to a design which has a history of being less susceptable to being stuck open and the remaining three (3) will be modified during the 1980 re-fueling outage.
WHEREFORE, the Authority believes that it has complied with all of the requirements of the order to show cause for the James A. FitzPatrick plant. All of the " Category A" requirements of NUREG-0578 have been met with the exception of the installation of positive indicators for the safety relief valves. The positive indicators,which are currently unavailable, will be installed within thirty (30) days of receipt of materials.
In the event that the plant is shut down for refueling prior to termination of the thirty (30) day period, installation of the positive indicators will be completed prior to re-starting the plant. Should the Commission require implementation on a schedule other than as set forth in this answer, the Authority.
reserves its right to request a hearing on such schedule. ,
Re,spectfully s,ubmitted 1816 277 THbShS R. F5E '
General Counsel Power Authority of the State of New York January 22, 1980 10 Columbus Circle New York, New York 10019 (212) 397-6200
EXHIBIT I Babcock & Wilcox %,c~.mc.
P.o. Bos 3200. Lynchburg, Va. 24505 Tekvene:(Go4)384-5111 January ll, 1980
'a M&
&cwer Authority State of New York L 10 Colunbus Circle New York, NY 10019 Subjcct: Valve Monitoring System PASNY order no. 19083-79 B&W no. 600-5206 Delivery Infomation Attention: Mr. Tom Hannan
Dear Mr. Hannan:
The delivery of the subject Valve Monitoring System is being controlled by the following factors: -
- NEMA-12 cabinet - B&W has ordered NEMA-12 cabinets from Hoffman Engineering Company of Anoka, Minnesota. This cabinet was chosen to benefit from pre-viously perfonted seismic tests. Delivery of this cabinet is due in late February.
An NiC0 cabinet could be used however, this cabinet has not been tested and all plans to test equipment in the near future is based on the use of the Hoffman NEMA-12 equipment.
- Subsequent to receipt of the cabinet B&W will require approximately three weeks for assembly.
- The edgemeters are also long lead items, however, the rneters can be installed in the field after shipment.
B&W is targeting delivery of the subject hardware between March 15, 1980,,
and March 30, 1980.
Please advise if you require further infomation on this subject.
Very truly yours, THC BABC0CK & WILCOX COMPANY M ~
J. M. Brunke iojr 37o Pr9 duct Manager 80iu ci U JMB/kjb The Batcoth & Witox Comyny I rey! het! IBM
AFFIRMATION State of New York )
) ss County of New York )
The undersigned PAUL J. EARLY, being duly sworn, hereby deposes and affirms as follows: that he is the Assistant Chief Engineer-Projects of the Power Authority of the State of New York; that he has read the foregoing Answer To Order To Show Cause Regarding Implementation of Category A Requirements of NUREG 0578 for The James A. FitzPatrick Nuclear Power Plant; and that the facts set forth therein are true and correct to the best of his knowledge, information and belief.
Dated: January 22, 1980.
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PAU /J. EARLYf Subscribed and sworn to before me this 22nd day of January 1980.
4d 3 Notafy~ Publib g // g -
RUTH G. ZAPF Notary Public. State of New York No. 30 4C6M23 coM[sNNd"ctIe*sSia"rc$b l0}h 2[h My Commission expires:
~b' t-/ l> S o, /YPO
UNITED STATES OF AMERIC4 NUCLEAR REGULATORY COMMISSION In the Matter of )
Power Authority of the )
State of New York ) Docket No. 50-333 James A. FitzPatrick ) O.L. No. DPR - 59 Nuclear Power Plant )
CERTIFICATE OF SERVICE I hereby certify that copies of the foregoing Power Authority of the State of New York's Answer to the Order to Show Cause Regarding Implementation of Category A Requirements For The James A. FitzPatrick Nuclear Power Plant have been mailed first class, postage prepaid, this 22nd day of January 1980 to each of the following:
Harold P. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (1) original +
(20) copies Samuel J. Chilk Secretary U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (1) copy Howard K. Shapar, Esq.
Executive Legal Director U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (1) copy
/ ,
By M7 ' j~ ~
Angel Power A/u.Mirtin,Esq.
thority of the State of New York 18115 280~