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Category:Inspection Report Correspondence
MONTHYEARIR 05000220/20184102018-10-16016 October 2018 Material Control and Accounting Program Inspection Report 05000220/2018410 and 05000410/2018410 (Letter Only) IR 05000220/20070012007-03-0202 March 2007 Annual Assessment Letter - Nine Mile Point Nuclear Station (Report 05000220-07-001 and 05000410-07-001) ML0527205072005-09-29029 September 2005 Requalification Program Inspection - Nine Mile Point Nuclear Station, Unit 2 ML0534600942005-09-12012 September 2005 Inspection Request, NMP PI&R - IR 2005-007 IR 05000220/20040052005-01-26026 January 2005 IR 05000220-04-005, 05000410-04-005; on 10/01/2004 - 12/31/2004; Nine Mile Point, Units 1 and 2; Licensed Operator Requalification Program and Operability Evaluations IR 05000220/20030082003-06-16016 June 2003 IR 05000220-03-008, IR 05000410-03-008, on 05/05/2003 - 05/08/2003, Nine Mile Point Nuclear Station Unit 1 and Unit 2, Temporary Instruction 2515/148, Inspection of Nuclear Reactor Safeguards Interim Compensatory Measures. ML0308500772003-03-26026 March 2003 Notification of Conduct of a Triennial Fire Protection Baseline Inspection IR 05000220/20020042002-07-19019 July 2002 IR 05000220-02-004, IR 05000410-02-004, on 05/19-06/29/2002, Nine Mile Point Nuclear Station, LLC, Nine Mile Point, Units 1 & 2. Resident Inspector Report IR 05000220/20020032002-06-0707 June 2002 IR 05000220-02-03, IR 05000410-02-03, on 3/31-5/18/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000220/20020022002-04-26026 April 2002 IR 05000220/2002-002, IR 05000410/2002-002, on 2/17-4/6/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations Identified IR 05000220/20010112002-03-21021 March 2002 IR 05000220/2001-011, IR 05000410/2001-011, on 12/30/01-02/15/2002; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Emergency Work Control. Non-cited Violations Identified IR 05000220/20010102002-01-24024 January 2002 IR 05000220/2001-010, IR 05000410/2001-010, on 11/11-12/29/2001; Nine Mile Point Nuclear Station, LLC; Nine Mile Point, Units 1 & 2. Resident Inspector Report. No Violations ML18018B0742000-03-27027 March 2000 ADAMS Distribution Notification ML17037C1621974-09-0404 September 1974 Letter Referring to Two Significant Matters Identified During the August 26 to 30, 1974 Inspection at Nine Mile Point-1 Reactor Facility ML17037C2091974-06-13013 June 1974 Letter Responding to the May 30, 1974 Letter Informing the Commission of the Corrective and Preventive Actions in Response to a May 15, 1974 Letter ML17037C2141973-11-14014 November 1973 Letter Responding to the September 13, 1973 Informing the Commission of the Action Taken to Correct the Items of Noncompliance Following the Recent Inspection and Advising That the Action Will Be Verified During the Next .. ML17037C2151973-10-25025 October 1973 Letter Responding to the September 10, 1973 Letter Informing the Commission of the Action Taken to Correct the Item of Noncompliance Brought to Attention Following the Recent Inspection and Advising That Corrective Action .. ML17037C1111972-08-10010 August 1972 Letter Regarding Action Taken in Response to a June 22, 1972 Letter Relating to Wall Thickness of Nuclear Service Valves ML17037C0991972-05-10010 May 1972 Letter Responding to an April 14, 1972 Letter Requesting Results of the Inspection on the Pressure Suppression Torus 2018-10-16
[Table view] Category:Letter
MONTHYEARNMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARNMP1L3001, Response to Apparent Violations in Inspection Report No. 05000220 & 05000410/2014005; EA-14-1922015-03-0505 March 2015 Response to Apparent Violations in Inspection Report No. 05000220 & 05000410/2014005; EA-14-192 ML0911903062009-04-15015 April 2009 Reply to a Notice of Violation ML0710703792007-04-0909 April 2007 NRC Inspection Report No. 50-220/2006-011, Reply to a Notice of Violation: EA-07-001 ML0318800152003-06-23023 June 2003 Reply to Notice of Violation - NRC Inspection Report 50-220/03-003 ML17037C2111974-05-14014 May 1974 Response to Atomic Energy Commission Letter Dated April 5, 1994 Regarding Inspection No. 50-220/74-02 ML17037C2141973-11-14014 November 1973 Letter Responding to the September 13, 1973 Informing the Commission of the Action Taken to Correct the Items of Noncompliance Following the Recent Inspection and Advising That the Action Will Be Verified During the Next .. ML17037C2151973-10-25025 October 1973 Letter Responding to the September 10, 1973 Letter Informing the Commission of the Action Taken to Correct the Item of Noncompliance Brought to Attention Following the Recent Inspection and Advising That Corrective Action .. 2015-03-05
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Text
UNITED STATES o<sss
<II' ATOMIC ENERGY COMMISSION i~ OIRECTORATE OF RCGVLATORY OPCRATIONS goIII REGION I 0 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406
~'e~s Niagax'a Mohawk Power Corporation Attention: Mr. R. R. Schneider Vice President, Electric Operations 300 Erie Boulevard Hest Syracuse, N. Y. 13202
Reference:
Youx letter dated September 13, 1973 Xn xesponse to our letter dated August 23, 1973 I
Gentleman:
Thank you for your letter informing us of the action yon have taken to correct the items of noncompliance which we brought to your atten-tion following our recent inspection of youx'icensed program. Your corrective action will be verified during our next inspection of your program.
Your cooperation with us is appreciated.
Sincexely, James P. O'Reilly Director bcc: RO, Chief PS&KB HQ RO: HQ (4)
RO Files Central Hail & Files Directorate of Licensing (4)
PDR NSIC DTIE tate f New York gAR CRESS
......@IE,. o Plumlee/jy Caphton Brunler O'Reilly SURNAME >
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r NIAGARA MOHAWK POWER CORPORATION NIAGARA I~ MOHAWK 300 ERIE 8OUI EVARD WEST SYRACUSE, N.Y. I3202 September 13, 1973 Mr. James P. O'Reilly Region I Directorate of Regulatory Operations United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA. 19406 Re: Provisional Operating License: DPR-17 Docket No.: 50-220
Dear Mr. O'Reilly:
This letter is in reply to your letter received August 24, 1973 regarding the inspection conducted by Mr. Cantrell of your office on March 7-9, 28-30, 1973 at the Nine Mile Point Nuclear Station. The above mentioned letter also references the meeting held in Newark, N.J. on June 14, 1973 between Mr.
O'Reilly and members of his staff and Mr. Haehl and other corporate representatives of Niagara Mohawk Power Corporation.
Following a thorough review of your letter we have concluded that no information contained in the inspection report is proprietary and it can be placed in the A.E.C.'s Public Document Room without changes.
In response to the concerns identified in your letters regarding actions taken or planned to improve the effectiveness of our management control system, we wish to advise you of the following activites, some of which were stated in my letter of July 5, 1973:~
A number of conferences were held with Corporate management of the Company and Plant Supervision impressing upon the latter that the Technical Specifications must be adhered to in all circumstances whether limits requiring shutdown or administrative requirements.
Technical Specification changes to improve the Management Control of Plant Operations .;cr' submitted on June 7, 1973 "".." "pprovcd by letter on Junc "', 1973.
Also plant reviews of Technical Specification regarding changes to enhance the accuracy of the methods of surveillance is underway. Corporate management of the Company has firmly impressed upon Plant Supervision that the proper course of action to be taken in determining a limiting condition for Operation is that as specified in the Technical Specifications. If an alternate method is better than the existing method then a change should be requested to the Technical Specification.
In all cases the Technical Specifications that exist at that time must be followed.
Ltr. Haehl to Kruesi-DRL July 5, 1973
~ Ltr. Skovholt DRL - Raymond June 21, 1973
u e Mr. James P. O'Reil eptember 13, 1973 U.S. Atomic Energy Commission 0
SORC minutes were expanded, then reviewed and attached to much more thorough SR5A Board minutes and forwarded to the, required Management People.
The SORC minutes will be numbered as an additional improvement in Management Control of Plant Operations.
As was stated in the meeting in Mr. 0 Reilly s office, it is the intention of Niagara Mohawk's Management that Nine Mile Point Station shall be operated in full compliance with all A.E.C. Regulations and the Technical Specifications.
The items concerning failure to report are for the most part the result of differing interpretations of what constitutes' reportable occurance rather than an intent not to inform the commission.
Considerable reorganization of our Management was in progress, while your management audit was taking place (January, 1973). A letter dated March 12, 1973, from President James A. O'eill, deceased, to Mr. L. Manning Muntzing, indicated the scope of these changes.
In addition, an expansion of the Quality Assurance and Quality Control Groups has been undertaken since your inspection. This includes: (1) A corporate level-Quality Assurance group reporting directly to the Executive Vice President; (2) Assignment of a Quality Control position at Nine Mile Point Site with the individual now stationed at the site and reporting to the General Superintendent of Nuclear Generation; (3) An additional expansion of the Quality Control Group at Nine Mile Point Site with. selection of proper individuals now taking'place; (4) Expansion of the Quality Control Group located in Syracuse.
The following are responses to each indiVidual item as delineated by your enclosure:
ITEM Al The four areas that were not posted as radiation areas were corrected on the spot at the time of the plant inspection. In addition the drain drum at the shutdown cooling system has been removed. Those individuals responsible for surveying and posting radiation areas have been refamiliarized with 10 CFR 20 requirements.
Also a supervisor in the Radiochemistry and Radiation Protection group will survey the plant once per week to prevent reoccurance of this item. As a result no areas now exist within the plant that are not now properly posted.
ITEM A2 On September anthem 20, 1972 the primary means for determining reactor coolant system leakage rate indicated a value greater than 2S gpm. The primary method is monitoring the levels in the drywell floor drain and equipment drain tanks using probes within the tank. The time .t takes for liquid to rise between the probes determines the rate of reactor cool.ant system leakage. However as the probes heatup the accuracy of the system deteriorates and reliance has been placed upon the integrated flow pumped from the sumps to the waste disposal system. Therefore the following corrective actions have been or will be taken:
- a. Corporate Management has had conferences with Plant Supervision and told that the Technical Specification must and will be followed in all circumstances.
0 4
4P
Mr. James P. O'Reil~
U.S, Atomic Energy CURmission
- b. Revision to the Technical Specification governing Reactor Coolant Leakage Rate has been written and following necessary approvals will be submitted for approval by the Atomic Energy Commission. However until such time as this change is approved and incorporated strict adherence to the existing specification will be required.
Again it is the intention of Corporate Management that Nine Mile Point Station will be operated in full compliance with all AEC Regulations and the Technical Specifications. Full compliance with this item has been a fact since the incident.
Although there has not been high drywell leakage since the 1973 Spring Refueling Outage, Plant Supervision appears to be much more aware of the necessity to abide by the limits as set forth in the Technical Specifications.
ITEM A3
/
This item concerns itself with the failure of Plant Supervision to recognize that the LCO (Item A2) had been reached or violated and therefore no reviews of the incident were made in the SORC meetings or reported in the SRGA Board.
The Technical Specifications will no longer be a subject of interpretation.
SORC will review any condition which may lead to an Abnormal Occurrance to
'etermine objectively the action needed. The method of determining the LCO and the surveillance associated with that item will be followed. Anytime an LCO's reached it will be reported, reviewed and necessary notifications made to Corporate Management and the Atomic Energy Commission. The SORC minutes which have been expanded will be reviewed in detail by the SR'oard. The SR6A Board's review of the incident will be much greater depth and forwarded to appropriate Corporate Management Personnel. Since this incident a review of SORC and SR5A Board minutes shows improvement in reporting, review and depth of the reports. These reports will be critically monitored to assure that conformity to Technical Specifications is maintained.
ITEM A4 h
During the SORC meeting of February 10, 1973 discussion was held determining the course of action to be followed with control rod 30-23 stuck in the fully inserted positi:on. General Electric was contacted and asked to furnish a recommendation for rod removal. The Unit was shutdown at the time therefore the control rod drive was replaced. Prior to replacing the control rod drive, however, the rod was withdrawn using a procedure furnished by G.E. That procedure was subsequently approved by SORC. As a result any time a control rod is stuck in the core this approved procedure will be used. In'addition plant supervision has been notified by Corporate Management that all procedures must be approved prior to use. The expansion of the Q.A. and Q.C..Staff should provide necessary Management Controls to oversee adherence to the Technical Specifications.
ITEM Bl
- a. In connection with this item the responses to Item A3 are appropriate, in that, Plant Supervision relied upon a method other than the primary one as specified in Technical Specification Bases 3.2.5. As a consequence of this action appropriate SORC and SR6A Board reviews were not accomplished and a letter to DRL stating the Abnormal Occurance was not written. The improve-ment of Management Control Systems as well as numerous conferences with Plant Supervi'sion by Corporate Management will correct this situation.
J1 I(
4 Mr. James P. O'Reil ptember 13, 1973 U.S. Atomic Energy Commission Results of these conferences has been rewarding in that full compliance has been achieved.
- b. In connection with this item a letter dated November 15, 1972 was sent supplying the requi.red information. In addition those individuals responsible for analyzing and reviewing plant conditions have been refamiliarized with the Reporting Requirements. Full compliance has been achieved on this item.
This item concerns the lack of safety analysis for the non-conservative change in set point of three of the four reactor triple low water level sensors in our letter of October 31, 1972 to Directorate of Licensing; In evaluating the safety consequences of this item there would have been no undue hazard presented to the general public as a result of 3 of 4 triple low level sensors being non-conservative. The remaining sensor would have fulfilled the necessary function. Full compliance has been achieved on this item.
- d. Regarding this item, inoperable control rods, in the future all inoperative control rods will be treated as an abnormal occurance. At the present time no control rods are inoperable nor have any been inoperable since the 1973 spring refueling outage. Therefore full compliance has been achieved on this item.
- e. In connection with this item the corrective action taken included reviewing with operations the proper method to "rack in a breaker" as well as testing of all safety. related equipment, its function and physical difficulties that could render that system inoperative. No problems have been experienced since then with this system and thorough complete training of operators none is expected. Full compliance has been achieved on this item.
Many of the items in B concern themselves with the need to review the reporting requirements with those people directly involved in these activities.
These reviews have been completed and thru audits the reporting, review and analysis will be kept at a high level. Special forms are being prepared to maintain records of all occurances. These forms will be made available to all departments in order to streamline the reporting process. In addition the comprehensive review by SORC members of reports should aid in achieving the desired and necessary level of correspondence on these matters.
Very truly yours;
.k~
Vice President - Electric Operations RRS:cm