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| {{Adams | | {{Adams |
| | number = ML20203L263 | | | number = ML20213F304 |
| | issue date = 04/24/1986 | | | issue date = 11/12/1986 |
| | title = Insp Rept 50-155/86-04 on 860124-0408.No Violation or Deviation Noted.Major Areas Inspected:Licensee Actions on Previous Insp Findings,Operational Safety,Maint,Ler Followup & Licensing Actions | | | title = Forwards Evaluation Re Util Commitment to Replace Diesel Engine for Diesel Fire Pump,Per Insp Rept 50-155/86-04 |
| | author name = Boyd D | | | author name = Keppler J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| | addressee name = | | | addressee name = Buckman F |
| | addressee affiliation = | | | addressee affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | docket = 05000155 | | | docket = 05000155 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-155-86-04, 50-155-86-4, NUDOCS 8605010198 | | | document report number = NUDOCS 8611140144 |
| | package number = ML20203L251 | | | package number = ML20213F307 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 8 | | | page count = 1 |
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| U.S. NUCLEAR REGULATORY COMMISSION
| | NOV 121986 Docket No. 50-155 Consumers Power Company ATTN: Dr. F. W. Buckman Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 Gentlemen: |
| | On April 24, 1986, Region III issued Inspection Report No. 50-155/86004(DRP) |
| | documenting your commitment to replace the diesel engine for the diesel fire pump at the Big Rock Point Nuclear Plant. This commitment was required by my staff following discussions with your staff on the diesel engine reliability and maintainability. |
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| ==REGION III==
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| Report No. 50-155/86004(DRP)
| | Pursuant to NRC Manual Chapter 0514, "NRC Program for Management of Plant Specific Backfitting of Nuclear Power Plants," we have prepared an evaluation setting forth the justification for our position. A copy of this evaluation is enclosed for your informatio Please call me if you have any questions regarding this evaluation. If you wish to appeal our decision, the basis for your appeal should be addressed to me with a copy to the NRC Executive Director for Operation |
| Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant Inspection At: Charlevoix, MI 49720 Inspection Conducted: January 24 through April 8,1986
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| Inspector: S. Guthrie Approved By: D. ,
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| YM Reactor Projects Section 2D Date Inspection Summary Inspection on January 24 through April 8,1986 (Report No. 50-155/86004(DRP))
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| Areas Inspected: Routine, unannounced inspection conducted by the Senior Resident Inspector of Licensee Actions on previous Inspection Findings, Operational Safety, Maintenance, Licansee Event Report followup, and Licensing Action Results: Of the five areas inspected, no violations or deviations were identified. No significant safety items were identified. However, the question of diesel fire pump dependability in light of its age and difficulties encountered in obtaining parts and experienced repair service is a source of increasing concern because of that pump's crucial role in providing low pressure core spray water as well as water for fire protection purpose C*
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| In 8605010198 860424 PDR ADOCK 05000155 O PDR
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| | Sincerely, cr!ainnl |
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| | .' r r, O. KeT(19@orD P |
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| | James G. Keppler Regional Administrator Enclosure: As stated cc w/ enclosure: |
| DETAILS 1. Persons Contacted
| | 4 Mr. Kenneth W. Berry, Director Nuclear Licensing |
| *D. Hoffman, Plant Superintendent G. Petitjean, Planning and Administrative Services Superintendent G. Withrow, Engineering Maintenance Superintendent R. Alexander, Technical Engineer R. Abel, Production and Plant Performance Superintendent
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| *L. Monshor, Quality Assurance Superintendent R. Barnhart, Senior Quality Assurance Consultant P. Donnelly, Senior Review Supervisor, Nuclear Activities Department D. Swem, Senior Engineer G. Sonnenberg, Senior Technical Analyst D. Staton, Shift Supervisor W. Trubilowicz, Operations Supervisor
| | D. P. Hoffman, Plant |
| *J. Beer, Chemistry / Health Physics Superintendent E. Evans, Senior Engineer J. Tilton, General Engineer D. Kelly, Maintenance Supervisor D. Ball, Maintenance Supervisor W. Blosh, Maintenance Engineer L. Darrah, Shift Supervisor J. Horan, Shift Supervisor R. May, Shift Supervisor R. Scheels, Shift Supervisor J. Warner, Property Protection Supervisor T. Fisher, Senior Quality Assurance Consultant S. Bartosik, General Quality Assurance Consultant R. Krchmar, General Quality Assurance Analyst | | { Superintendent DCS/RSB (RIDS) |
| *D. Hice, Technical Engineer (Acting)
| | Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan s611140144 861112 5 Public Service Commission PDR ADOCK 0500 P |
| *R. Schrader, Engineering, Maintenance Superintendent (Acting)
| | Nuclear Facilities and - |
| The inspector also contacted other licensee personnel in the Operations, Maintenance, Radiation Protection, and Technical department * Denotes those present at exit intervie . Licensee Action on Previous Inspection Findings Section 10 of Inspection Report No. 85021 describes the licensee's administrative procedures permitting the Shift Supervisor (SS), as the only licensed Senior Reactor Operator (SRO) on shift, to be absent from the control room and, in his abrence, delegating an operator holding c Reactor Operator (RO) license to assume command of the control room. Both of these activities are prohibited by 10 CFR 50.54(m).
| | Environmental Monitoring Section T. H. Cox, ED0 p |
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| The staff of NRR, by letter May 2, 1980, accepted the licensee's proposal to assign " primary management responsibility" for the plant to the SS and recognizes that certain emergency situations may require the SS to leave the control room in the interests of plant safet Subsequent to this acceptance by the staff the requirements of 10 CFR 50.54(m) were imposed by regulatio .
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| The licensee indicated their intention to submit a change to technical specification During this review the inspector noted that Administrative Procedures Volume I, Chapter 4, Section 1.4.a.l.5 states that the SS may leave the control room during emergency situations other than site or general emergency "provided the Shift Technical Advisor / Shift Engineer remains in the control room during his absence." The Shift Technical Advisor / Shift Engineer positions is no longer staffed at Big Rock as the licensee fulfills that positions requirements with an On-call Technical Advisor (OTA). The OTA is required to be onsite during certain evolutions and within one hour of being summoned by the SS and thus it is not reasonable to require an OTA, who does not hold an SRO license, to be present before the SS is allowed to leave the control room in the interest of plant safet The licensee agreed to review the procedural requiremen b. Section 5.d of Inspection Report No. 85021 described failure of the diesel fire pump (DFP) to start within the required start time during performance of weekly Surveillance T7-20, DFP Start Test. Corrective maintenance efforts were ultimately unsuccessful, and on February 4, the DFP was declared inoperable based on excessively long start time Technical Specification 11.3.1.4. requires both the Electric Fire Pump and the DFP to be operable at power, and declaring the DFP inoperable placed the facility in a Limiting Condition for Operation (LCO)
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| requiring a shutdown to be initiated with 24 hour At Big Rock the DFP performs a core spray function as well as providing water for fire fighting. On February 4 the licensee initiated a change to Procedure T7-20 to increase the maximum start time from 20.4 seconds to 45 seconds, citing as engineering justification the Safety Evaluation performed by NRR supporting the approval of Amendment No. 44 to the units Operating Licens This amendment, dated June 9, 1981, revised reactor operating limits based on a new Loss of Coolant Accident (LOCA) analysis. Section 2.3 of the Safety Evaluation concludes that a delay in DFP start time of an additional 25 seconds (45 seconds total) does not affect the LOCA-based reactor operating limit All DFP starts, including those which had exceeded the former 20.4 second limit, were within the revised 45 second limit, thus relieving the licensee of the requirements of the technical specification LC On February 4 the inspector reviewed the problen with the licensee and expressed a concern that the erratic starting behavior of the DFP and the inability of maintenance personnel and vendors to positively identify and correct the cause of the poor performance was a problem that could not be corrected solely by increasing allowable starting times no matter how valid the engineering justificatio The licensee agreed to operate the DFP continuously from February 4 until entering an upcoming scheduled outage period where DFP operability was no longer required by technical specification. The DFP ran continuously except for daily maintenance trouble shooting sessions until February 11. During the outage the licensee brought in manufacturer's representatives to diagnose and correct the problem. Diagnosis and repairs were hampered by the age of the equipment, prompting the
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| licensee to consider the DFP engine for total replacement during the 1986 refueling outage. Unavailability of parts and a shortage of maintenance personnel experienced with the outdated engine make future repairs questionable. Electrical components cleaning, fuel line leak tightness verification, and valve adjustments produced satisfactory start time performance and a pump output capacity test was satisfactorily performed February 15. Following the DFP's return to operability the licensee conducted daily performances of T7-20, n '.h maintenance personnel present, from February 17 to March 3. All tests had start times of less than 7 seconds, a figure consistent with the pump's long term surveillance histor The inspector will monitor the licensee's activities related to DFP engine replacemen . Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the inspection period. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of the containment sphere and turbine building were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of main-tenanc The inspector, by observation and direct interview, verified that the physical security plan was being implemented in accordance with the station security pla The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection control During the inspection period, the inspector walked down the accessible portions of the Liquid Poison, Emergency Condenser, Reactor Depressurization System (RDS), Post Incident, Core Spray and Containment Spray systems to verify operabilit Throughout the report period the licensee experienced problems with high turbine gland seal steam pressure. Turbine gland seal steam normally runs about 2 psig but increased for reasons that remain unclear to about 8 psig, a pressure at which gland seal steam escapes from the turbine shaft gland and condenses to become mixed with lubricating oil at the turbine shaft bearin Presently the quantity of water becoming mixed with oil is minimal and easily removed by a centrifugal purifier and by evaporation from the warm oi Pending determination of corrective action by turbine specialists, operators are reducing load in one mwe increments to keep seal steam pressure under 8 psig. Power has been reduced from 70 mwe to 66 mwe for this purpos .
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| b. On February 10 at 10:00 p.m. the licensee attempted to perform Quarterly Surveillance T90-07, RDS Isolation Valve Test. To perform the test, RDS-101 valves (bypass manual isolation) must be open and the piping between the upstream isolation valve and the depressuri-zation valve pressurized. Erosion of the pilot valve assembly on SV-4985 (B train depressurization valve) caused lifting of that valve and the test was terminated. RDS valves 101 B and C were reclose The licensee, in anticipation of this situation preventing performance of the required surveillance, had scheduled an outage period to perform RDS valve maintenanc The following morning of February 11 the licensee performed primary plant leak rate calculations and determined total unidentified leak rate to be 1.126 gpm. Technical Specification 4.1.2.(c) requires the plant be placed in hot shutdown condition within 12 hour Big Rock Emergency Procedures require that declaration of an Unusual Event be made when plant shutdown is required by a technical specification LCO. All Unusual Event notifications were completed, and the reactor was shutdown within the required period. Leak rate calculations performed after shutdown indicated total unidentified leakage of 0.349 gpm. The licensee suspects leakage through the RDS valves which were manipulated during the surveillance attemp During the outage the licensee replaced depressurization valve top assemblies on SV-4985, SV-4986, and SV-498 Valve RDS 101 B was also replace The reactor was returned to service February 1 Unidentified leakage following startup was 0.192 gp c. On March 7 the inspector discussed with the licensee an event at the Lacrosse facility in which heat generated in a silver zeolite sampling cartridge in use at the offgas sample line caused hydrogen ignition in the sample line and offgas system pipin The licensee had discussed the incident with the Lacrosse licensee and evaluated the use of silver zeolite cartridges at this facilit Currently the silver zeolite cartridges are used for emergency general sampling for all areas but are capable of sampling at the offgas sample poin The licensee had already determined the need for a warning sign at the offgas sample poin d. On March 23 the unit experienced an increase of offgas flow of 6-8.5 CFM with no significant changes in any other plant paramete Investigation revealed a hole in a 10 inch steam line piping elbow downstream of bypass valve CV4014. This was apparently caused by erosion from steam impinging on the elbow's interior surface from a
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| warming line. The line is normally under vacuum from the main condenser but the size of the hole when first discovered was small enough to be within the capacity of the air ejectors to maintain vacuu _ . _ _ . ... - .- . - . , _ _ - - - - - . . - - _ - - - - . , - _ . , _ _ . _ - _ -
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| e During the period of increased offgas flow the licensee observed a slight increase in radionuclide activity exhausting to atmosphere as short lived nuclides were rushed through the offgas system's hold up volume. This hold up volume, given normal offgas flow rates, provides sufficient time for short lived radionuclides to decay within the volume, thus reducing the total activity discharged to the atmosphere via the stack. Xenon 138, a short lived nuclide monitored by the licensee, increased from a typical valve of 400 uci/sec to around 800 uci/sec. Licensee monitoring of Xenon 133, a long lived nuclide which does not linger in the hold up volume long enough to decay, significantly showed no change. Discharges are limited by 10 CFR 50, Appendix On March 24 a temporary patch was affixed to the elbow's exterio Following fabrication, on March 31, a patch was welded to the elbo During the installation process, declining condenser vacuum required operator action to increase air ejector flow to prevent a reactor scram from low vacuum (22 in. hg). Permanent elbow replacement is planned for the 1986 refueling outag On March 26 the inspector observed portions of hands-on fire training conducted at the sit No violations or deviations were identified in this are . Monthly Maintenance Observation Station maintenance activities of safety-related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides, industry codes or standards, and in conformance with technical specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemente Wor k requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performanc On March 24 the licensee entered a 72 hour LC0 for replacement of Solenoid Valve SV-9153 on Control Valve CV-4094, Exhaust Ventilation Downstream Isolation Valve. Solenoid Replacement was completed within seven hours.
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| . On April 1, during the performance of T7-20, DFP Start Test, the operator observed dripping leakage of fuel oil from a fuel oil filter on the engine. Vibration of the filter during operation brought it in contact with its support bracket, eventually wearing through the filter housing. Filter replacement and bracket modification required entry into a LCO as required by Technical Specification 11.3. Repairs were completed with the 24 LCO requirement During the inspection period the licensee received notification from the Consolidated Pipe and Valve Supply Company that officials of the Golden Gate Forged Flange Company, a supplier of forged flanges sold to the licensee by Consolidated Pipe, had been charged in Federal Court with criminal false statements related to falsified test certification The licensee promptly researched all purchase orders from the vendor and all records of transfer of materials from the terminated Midland Plant and informed the inspector that none of the suspect forged flanges were installed or are in storage at Big Roc No violations or deviations were identified in this are . Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specification (Closed) LER 86001 and 86001, Revision 1, Failure to Perform Required Surveillance Test. This LER describes the licensee's failure to test fire detection instruments located in the recirculation pump room during the 1985 refueling outage, as required by Technical Specification 4.3.3. The omission was attributed to procedural inadequacy which called for testing of several detectors with different surveillance frequencies under a single procedure, thus creating the potential for the oversight. The omission was discovered on January 17, 1986 and the test was performed on February 15, 1986 during the next period permitting recirculation pump room entr The LER was revised by the licensee after determining that wording in the original submittal gave the incorrect impression that the Senior Resident Inspector had granted permission to continue plant operations in violation of a LCO. In fact, Big Rock technical specifications do not include an action statement requiring plant shutdown to perform the required surveillance. When informed of the situation the inspector concurred with the licensee's decision not to voluntarily shutdown the plant to perform the fire detector surveillance. The inspector based his position on the detectors successful surveillance history and the recognition that the
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| The missed surveillance was discussed in Section 5.e of Inspection Report No. 8502 (Closed) LER 86002, Exceeding Technical Specifications Unidentified Leak Rate Limit. This LER discusses the licensee's action to take the unit from 90% power to cold shutdown as required by Technical Specification 4.1. This action was in response to an unidentified leak rate in excess of 1.0 gpm observed during performance of surveillance testing on RDS Valves on February 1 The event is described in detail in Section 3.b of this repor . Licensing Activities By letter dated March 10 the commission issued Amendment No. 83 to Facility Operating License No. DRP-6 for Big Rock Point. The amendment changes technical specifications to reflect a plant staff reorganization implemented in 198 By letter dated March 20, 1986, the Commission issued an exemption from the requirements of 10 CFR 50.62(c)(5) to install an automatic recirculating pump trip to trip the reactor under conditions indicative of an Anticipated Transient Without Scram (ATWS) event. The letter references several engineering evaluations and concludes that the existing installed oversized safety valve capacity at Big Rock is sufficient to limit primary coolant system pressure rise within acceptable limits without an automatic pump tri . Exit Interview The inspector met with licensee representatives (denoted in Section 1)
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| throughout the month and at the conclusion of the inspection period summarized the scope and findings of the inspection activities. The licensee acknowledged these findings. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspectio The licensee did not identify any such documents or processes as proprietar .
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217G4111999-10-12012 October 1999
Informs of Changes to Big Rock Point Defueled Emergency Plan, That Meet Requirements of 10CFR50.54(q) & Can Be Made Without NRC Approval.Changes to Plan Are Listed
ML20212L9051999-10-0404 October 1999
Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use
ML20217C5111999-09-30030 September 1999
Forwards Info Re Management & Funding of Irradiated Fuel Notification,Per 10CFR50.54(bb),in Response to NRC Telcon Rai.Revs to Original 990811 Submittal Are Indicated by Redline/Strikeout Method
ML20217C2761999-09-30030 September 1999
Forwards Big Rock Point Plant Annual Rept of Facility Changes,Tests & Experiments,Iaw 10CFR50.59(b)(2).Rept Provides Summary of Changes to Facility Performed Since 981001.No Activities Classified as Tests or Experiments
ML20212K7561999-09-30030 September 1999
Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted
ML20211G1011999-08-25025 August 1999
Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year
ML20210V0561999-08-17017 August 1999
Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1)
ML20211D5661999-08-17017 August 1999
Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc
ML20210S6961999-08-12012 August 1999
Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp
ML20210S6291999-08-11011 August 1999
Forwards Notification to NRC for Review & Approval of Program Intending to Manage & Provide Funding for Mgt of All Irradiated Fuel at Big Rock Point Until Title of Fuel Is Transferred to Secretary of Energy for Disposal
ML20210L0321999-08-0303 August 1999
Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6)
ML20210H2701999-07-28028 July 1999
Informs That Big Rock Point Commits to Listed Actions with Regard to 990511 Amend Request to Delete Definition of Site Boundary & Remove Site Map,Based on Discussion with NRC on 990728
ML20209D6951999-07-0707 July 1999
Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One
ML20210L0491999-06-30030 June 1999
Partially Deleted Request for FOIA Documents Re Source of High Alarms Generated by Radiation Effluent Detector or Detectors in Discharge Canal at Big Rock Point on 980314,15 & 25.Partially Deleted Info Encl
ML20209D7011999-06-21021 June 1999
Requests That NRC Reconsider Decision to Move Resident Inspector from Big Rock Point NPP
ML20196E1601999-06-21021 June 1999
Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily
ML20195D0371999-06-0303 June 1999
Forwards Revised Defueled Ts,Per 990511 Util Request.Page Format in Attachments 1 & 2 of Submittal Do Not Agree with Current Facility Defueled TS Format.Replacement of Encl Pages Requested
ML20207F6631999-06-0303 June 1999
Forwards Rev 33 of Big Rock Point Plant Security Plan,Which Incorporates Exemption from Certain Requirements of 10CFR73 That Reflect Permanent Shutdown & Defueled Condition of Facility.Encl Withheld IAW 10CFR73.21(c)
ML20207D1151999-05-27027 May 1999
Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created
ML20206P4501999-05-11011 May 1999
Requests Transcript of 990413 Public Meeting in Rockville,Md Re Decommissioning of Big Rock
ML20206P0921999-05-0707 May 1999
Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule
ML20206H1011999-05-0404 May 1999
Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld
ML20206J2411999-04-30030 April 1999
Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl
ML20206E7821999-04-29029 April 1999
Forwards Annual Radioactive Environ Rept for 1998 for Big Rock Point Plant. Rept Includes Summaries,Interpretations & Statistical Evaluation of Results of Radiological Environ Monitoring Program
ML20206E3721999-04-29029 April 1999
Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required
ML20206B7381999-04-26026 April 1999
Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined
05000155/LER-1992-008, Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable1999-04-26026 April 1999
Advises That Util Terminated Corrective Actions Re LER 92-008 of Loss of Station Power 125 Volt Dc sys.SOP-28 Has Been Deleted in Entirety.Commitments No Longer Applicable
ML20196K7881999-03-29029 March 1999
Forwards Rept on Certification of Financial Assurance for Decommissioning for Big Rock Plant,Per 10CFR50.75(f)(1).Copy of Trust Agreement Between Consumers Energy & State Bank & Trust Co,Included in Rept
ML20205E3471999-03-29029 March 1999
Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to
ML20204F4611999-03-19019 March 1999
Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy
ML20204E5861999-03-16016 March 1999
Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants
ML20203F8041999-02-11011 February 1999
Forwards Temporary Addendum to Security Plan Re Central Alarm Station,Per 10CFR50.54(p).Encl Withheld,Per 10CFR73.21(c)
ML20203C8971999-02-0808 February 1999
Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP
ML20202H4891999-01-26026 January 1999
Informs That Exemption Request from Various 10CFR73 Physical Protection Requirements, ,was Improperly Based on Requirements of 10CFR50.12.Request Was Resubmitted by Ltr
ML20199H2431999-01-15015 January 1999
Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper
ML20199E1841999-01-13013 January 1999
Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication
ML20199E0781999-01-13013 January 1999
Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5
ML20199D9711999-01-13013 January 1999
Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl
ML20199E9051999-01-12012 January 1999
Submits Revised Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls
ML20199E7671999-01-12012 January 1999
Informs That Licensee Has Elected to Comply with Listed 10CFR50.68(b) Requirements in Lieu of Maintaining Monitoring Sys Capable of Detecting Criticality as Described in 10CFR70.24
ML20199A4151999-01-0404 January 1999
Informs That Individuals Listed on Attachment 1 Will No Longer Maintain Operating License for Plant.Senior Licensed Operators & Licensed Operators No Longer Required at Facility
ML20198K6551998-12-24024 December 1998
Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant
ML20198J4001998-12-21021 December 1998
Requests That Words Decommissioning of in First Sentence of Paragraph a of Fol,License DPR-6 Be Removed from CPC 970919 Request
ML20196H3171998-12-0303 December 1998
Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety
ML20196G7541998-11-25025 November 1998
Requests Withdrawal of Listed Sections of 970919 Amend Request,As Supplemented by Ltrs ,0721 & 1014, Respectively.Util Proposed to Retain Certain Sections of Current Tech Specs (CTS) to Support Withdrawal Request
ML20195G9851998-11-17017 November 1998
Forwards Rev 0 to Vol 9 of Defueled Emergency Plan & Rev 0 to Vol 9A of Defueled Epips
ML20195H5321998-11-13013 November 1998
Provides Confirmation That Revs Required by NRC to Defueled Emergency Plan Prior to Implementation Have Been Completed by Licensee.Items Incorporated Into Plan,Listed
ML20195F2271998-11-12012 November 1998
Forwards Request for Exemption from Certain Requirements of 10CFR73 Re Physical Protection of Plants & Matls.Request Withheld,Per 10CFR73.21
ML20154M5381998-10-14014 October 1998
Forwards Supplement to Plant Defueled TS & Bases, Incorporating Licensee Response to NRC 980416 RAI & Clarifying Listed Items
ML20154M2211998-10-14014 October 1998
Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety
1999-09-30
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20058G8921990-11-0707 November 1990
Forwards Insp Repts 50-155/90-20 & 50-255/90-20 on 900925-28 & 1015-19.Violations Noted
ML20058G2461990-11-0202 November 1990
Forwards Safety Insp Rept 50-155/90-17 on 900904-1015 & Notice of Violation
ML20058F7331990-10-31031 October 1990
Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04
ML20058E7141990-10-30030 October 1990
Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant
ML20058A7671990-10-22022 October 1990
Advises That Review of 900816 Response to NRC Bulletin 90-001 Re Loss of Fill Oil in Rosemount Transmitter Ongoing
ML20059N0081990-09-28028 September 1990
Forwards Insp Rept 50-155/90-10 on 900723-27 & 0806-10 & Notice of Violation
ML20059M2101990-09-25025 September 1990
Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet
ML20059L4771990-09-18018 September 1990
Forwards Safety Insp Rept 50-155/90-13 on 900724-0903. Noncited Violation Noted
ML20059J3091990-09-10010 September 1990
Forwards Exemption from 10CFR55.45(b)(2)(ii) Re Use of Simulation Facility,Per 900404 Request.Util Request to Delay Submittal of Description of Performance Tests & Results Until 910526 Granted
ML20059F2531990-08-31031 August 1990
Forwards Safety Evaluation Supporting Util 891229 Request to Dispose of Dredged Discharge Canal Sediment from Facility
ML20059C6111990-08-27027 August 1990
Forwards Safety Insp Rept 50-155/90-15 on 900814-16.No Violations Noted
ML20059B7771990-08-22022 August 1990
Advises That Util Commitment to Install Two New Recorders That Provide Containment Temp Indication on Front Panel During 1990 Refueling Outage,Acceptable
ML20056B5191990-08-17017 August 1990
Forwards Final SALP Rept 50-155/90-01 & Revised Pages to SALP Rept.Overall Performance Did Not Decline,Per 900716 Meeting.Nrc Overstated Concern W/Radiological Controls Functional Area in Initial Rept & Cover Ltr
ML20059A7571990-08-16016 August 1990
Advises That Response to Bulletin 90-001, Transmitters Mfg by Rosemount, Complete,Per
ML20059A1741990-08-16016 August 1990
Informs That NRC NDE Mobile Lab Will Conduct Independent NDE Exams at Plant on 900924-1005.Selected Sys for Exam Listed on Encl
ML20059A1661990-08-16016 August 1990
Forwards Safety Insp Rept 50-155/90-14 on 900730-0803.No Violations Noted
ML20059A3721990-08-14014 August 1990
Ack Receipt of Informing NRC of Change in Completion Date Re on-the-job Training Procedure,Per LER 90-002
ML20058N2211990-08-0707 August 1990
Forwards Safety Insp Rept 50-155/90-12 on 900612-0723.No Violations Noted
ML20058M6141990-08-0707 August 1990
Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date
ML20056A4981990-08-0101 August 1990
Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls
ML20055G7301990-07-20020 July 1990
Requests Util Provide Ref Matls Listed in Encl for Requalification Program Evaluation on 901018 & Wk of 901105
ML20055G2881990-07-16016 July 1990
Advises of fitness-for-duty Insp Scheduled for Wk of 900925- 28 at Plant.Written Policies & Procedures Will Be Reviewed as Part of Insp Process
ML20055G5051990-07-11011 July 1990
Advises That 900511 Rev 95 to Chapters 2,5,6,7,8 & Apps D, M & P for Plant Emergency Plan Consistent w/10CFR50.54(q) & Acceptable.Position of on-call Technical Adviser Should Be Inserted in Table 1 of Chapter 5
ML20055F1661990-07-0606 July 1990
Forwards Initial SALP Rept 50-155/90-01 for Jan 1989 - Apr 1990,prior to 900716 Scheduled Meeting.Two Areas of Improvement & No Areas of Decline Identified Since Last SALP Rept
ML20055D7011990-07-0202 July 1990
Confirms Plans Re 900716 Meeting W/Util in Charlevoix,Mi to Present Initial SALP 9 Rept for Plant
ML20055D1791990-06-28028 June 1990
Forwards Safety Insp Rept 50-155/90-11 on 900501-0611.No Violations Noted
ML20059M9181990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20248A5351989-09-19019 September 1989
Forwards Safety Insp Rept 50-155/89-15 on 890725-0905.No Violations Noted.Unresolved Items Noted Re Compliance W/ Requirements of 10CFR50,App J for Reduced Pressure Testing
ML20247D3541989-09-0606 September 1989
Forwards Environ Assessment & Finding of No Significant Impact Re Tech Spec Change to Delete Section 6.4.2(d) on Calibr of Portable Neutron or Gamma dose-rate Measuring Instruments
ML20246D2191989-08-16016 August 1989
Forwards Amend 100 to License DPR-6 & Safety Evaluation. Amend Revises Tech Specs by Providing for New Organizational Unit Entitled Nuclear Safety Svcs Dept to Discharge Offsite Safety Review Functions Instead of Nuclear Safety Board
ML20245K0581989-08-14014 August 1989
Forwards Safety Insp Rept 50-155/89-14 on 890710-0801 & Notice of Violation
ML20245G1981989-08-10010 August 1989
Forwards Environ Assessment & Finding of No Significant Impact Re 880922 Application & 890117 & 0412 Ltr Suppls, Requesting Changes to Tech Specs to Allow Independent Review & Audit Functions Be Accomplished by Independent Unit
ML20245G5131989-08-10010 August 1989
Forwards SER Accepting Util Response to Generic Ltr 83-28, Item 4.5.3 Re Reactor Trip Reliability on-line Functional Testing of Reactor Trip Sys
ML20245E6301989-08-0202 August 1989
Forwards Safety Insp Rept 50-155/89-13 on 890618-0724 & Notice of Violation
ML20245H5331989-08-0202 August 1989
Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed
ML20247R0971989-07-31031 July 1989
Advises That Operator & Senior Operator Written & Oral Exams Scheduled for Wk of 891113.Ref Matls Listed on Encl & Operator License Applications Should Be Provided at Least 60 Days Prior to Exam Date
ML20245H8231989-07-28028 July 1989
Forwards Amend 98 to License DPR-06 & Safety Evaluation. Amend Requires Compliance W/Amended Physical Security Plan
ML20246K8721989-07-12012 July 1989
Forwards Insp Rept 50-155/89-12 on 890612-14,20-22,26-28 & 0705-06.No Violations Noted
ML20246F9181989-07-0505 July 1989
Forwards TE Murley to Ecology Ctr of Southern California Ack Receipt of Petition & Advising Ctr That Petition Will Be Treated Per 10CFR2.206
ML20246C1201989-06-30030 June 1989
Forwards Safety Insp Rept 50-155/89-09 on 890507-0617.No Violations Noted
ML20245B1831989-06-0909 June 1989
Forwards Safety Insp Rept 50-155/89-10 on 890522-25.No Violations Noted
NUREG-0828, Concurs W/Interpretation of Intent of Item 4(5) of SER Re NUREG-0828,Sections 4.5, Wind & Tornado Loadings & 4.8, Tornado Missiles. Alternate Shutdown Bldg Will Be Manned When Tornado Warning Broadcast for General Area1989-06-0808 June 1989
Concurs W/Interpretation of Intent of Item 4(5) of SER Re NUREG-0828,Sections 4.5, Wind & Tornado Loadings & 4.8, Tornado Missiles. Alternate Shutdown Bldg Will Be Manned When Tornado Warning Broadcast for General Area
ML20248C0501989-05-31031 May 1989
Forwards Amend 97 to License DPR-6 & Safety Evaluation.Amend Adds Operability & Surveillance Requirements for Alternate Shutdown Sys to Tech Spec Sections 11 & 12 & Includes Tech Specs for Active Fire Barriers & Fire Detection
ML20247K8741989-05-24024 May 1989
Forwards App to SALP 8 Rept 50-155/89-01 for Sept 1987 - Dec 1988,per 890328 Meeting
ML20247A6281989-05-16016 May 1989
Forwards Safety Insp Rept 50-155/89-06 on 890326-0506.No Violations Noted
ML20247A2921989-05-12012 May 1989
Advises That 890406 Rev 92 to Vol 9 of Site Emergency Plan Including Changes to Chapter 7, Emergency Facilities & Equipment & App J, Primary & Secondary Communications, Acceptable
ML20247A3221989-05-12012 May 1989
Grants 880926 Request for Partial Exemption from Annual Fees of 10CFR171,based on Size & Age of Plant.Invoice Encl
ML20246L8121989-05-0202 May 1989
Forwards Amend 96 to License DPR-6 & Safety Evaluation.Amend Revises OL to Allow Increase in Amount of Byproduct Matl Plant May Possess from 10.5 to 45 Ci Cs-137,as Sealed Sources
ML20245L3221989-04-28028 April 1989
Ack Receipt of 881223 Submittal of Rev 8 of QA Topical Rept CPC-2A Re Transfer of QA Assigned Functions to Other Plant Organizations & Continuing QA Organizations Program Control. Topical Rept Acceptable & Meets 10CFR50,App B
ML20245C8541989-04-20020 April 1989
Advises That Independent post-implementation Verification of Software Question Outstanding for Amend 91 Closed
1990-09-28
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20212L9051999-10-0404 October 1999
Forwards Environ Assessment & Finding of No Significant Impact Re 990511 Application for Amend,As Supplemented on 990603 & 0728.Proposed Amend Would Make Changes to TSs by Deleting Definition,Site Boundary & Use
ML20212K7561999-09-30030 September 1999
Forwards Insp Rept 50-155/99-05 on 990731-0921,site Insp & 990929 Public Meeting.No Violations Noted
ML20211G1011999-08-25025 August 1999
Confirms Discussions & Agreement to Have Mgt Meeting in Region III Office on 990929.Purpose of Meeting to Discuss Decommissioning Activities,Priorities,Challenges & Successes & to Preview Plans & Schedules for Next Year
ML20210V0561999-08-17017 August 1999
Advises of Plan to Stop Using Ofc Complex at Plant,Which Consumers Energy Co Had Provided for NRC Resident Inspectors Under 10CFR50.70(b)(1)
ML20210S6961999-08-12012 August 1999
Forwards Insp Rept 50-155/99-04 on 990609-0730.No Violations Noted.No Safety Issues or Enforcement Items Were Identified During Insp
ML20210L0321999-08-0303 August 1999
Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety & Documents Listed in App B Being Released in Part (Ref FOIA Exemption 6)
ML20209D6951999-07-0707 July 1999
Ack Receipt of Which Requested That NRC Reconsider Decision to Move NRC Resident Inspector from Big Rock Point Plant.Determined Decision to Be Correct One
ML20196E1601999-06-21021 June 1999
Forwards Insp Rept 50-155/99-03 on 990416-0608.No Violations Noted.Overall,Reactor Decommissioning Activities Performed Satisfactorily
ML20207D1151999-05-27027 May 1999
Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Reorganization,Division of Licensing Project Management Created
ML20206P0921999-05-0707 May 1999
Responds to Discussing Impact That Delays to Wesflex Sys Approval Would Have on Big Rock Point Decommissioning Cost & Schedule
ML20206H1011999-05-0404 May 1999
Forwards Safety Evaluation for Exemption from Certain Physical Protection Requirements.Enclosure Contains Safeguards Info & Being Withheld
ML20206E3721999-04-29029 April 1999
Informs That Based on Licensee Determinations That Changes in Rev 1 Do Not Decrease Effectiveness of Defueled EP & That Plan Continues to Meet Applicable Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required
ML20206B7381999-04-26026 April 1999
Forwards Insp Rept 50-155/99-02 on 990226-0415.No Violations Noted.Activities in Areas of Facility Mgt & Control,Decommissioning Support,Spent Fuel Safety & Radiological Safety Were Examined
ML20205E3471999-03-29029 March 1999
Informs That USNRC Granted Encl Exemption from Certain Requirements of 10CFR73,to Allow Implementation of Safeguards Contingency Plan Reflecting Permanent Shutdown & Defueled Condition of Brpnp in Response to
ML20204F4611999-03-19019 March 1999
Forwards Insp Rept 50-155/99-01 on 990113-0225.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy
ML20203C8971999-02-0808 February 1999
Informs That NRR Contracted with PNNL to Evaluate Storage of Spent Fuel at Number of Decomissioning Nuclear Power Facilities.Forwards Request for Info Re Spent Fuel Storage at Big Rock NPP
ML20199H2431999-01-15015 January 1999
Forwards Insp Rept 50-155/98-09 on 981201-990112 & Nov.One Weakness Identified Re Event Involving Ungrappling Fuel Bundle Without Being Fully Seated in Rack & Without Independent Verification That Ungrappling Bundle Was Proper
ML20199D9711999-01-13013 January 1999
Forwards Plant Defueled TS Administrative Replacement Pp.On 990104 Staff Informed NRC That Pp Numbering for Table of Contents Was Incorrect.Subj Pp Requested to Be Replaced with Encl
ML20199E0781999-01-13013 January 1999
Informs That Staff Has Received Request for Exemption from Various 10CFR73 Pyhsical Protection Requirements Dated 981112.Exemption Request Improperly Based on Requirements of 10CFR50.12 Instead of Applicable Requirements of 10CFR73.5
ML20199E1841999-01-13013 January 1999
Forwards Environ Assessment & Finding of No Significant Impact Re Proposed Exemption from Certain Physical Protection Requirements of 10CFR73.Assessment Forwarded for Fr Publication
ML20198K6551998-12-24024 December 1998
Forwards Amend 120 to License DPR-6 & Safety Evaluation. Amend Changes License DPR-6 & App A,Ts to Reflect Permanently Shutdown & Defueled Status of Plant
ML20196H3171998-12-0303 December 1998
Forwards Insp Rept 50-155/98-08 on 980827-1130.No Violations Noted.Inspection Covered Activities in Areas of Radiological Safety
ML20154M2211998-10-14014 October 1998
Forwards Insp Rept 50-155/98-07 on 980827-1007.No Violations Noted.Insp Consisted of Examination of Activities in Areas of Facility Mgt & Control,Decommissioning Support (Including Physical Security),Sf Safety & Radiological Safety
ML20154E0121998-09-30030 September 1998
Forwards Exemption from 10CFR50.54(q) Re Plant & Suppls ,1120& 980302,0429 & 0828 Which Requested Exemption from Certain Protions of 10CFR50.47(b) & App E to 10CFR50 to Allow Brpnp to Discontinue Offsite EP Activities
ML20239A2491998-09-0303 September 1998
Forwards Insp Rept 50-155/98-06 on 980716-0826.No Violations Noted.Overall,Reactor Decommissioning Activities Were Generally Performed Satisfactorily & as Planned.Potential Weaknesses Were Identified in Review of SE Procedure
ML20237E2731998-08-25025 August 1998
Discusses NRC Insp Rept 50-155/98-03 on 980527.Violations Noted.Insp Findings Documented in NRC Insp Rept Sent to Util by Ltr
ML20237C5461998-08-19019 August 1998
Refers to Revs 133,134 & 135 to Portions of Big Rock Point Plant Emergency Plan.Based on Determinations That Changes in Revs 133-135 Do Not Decrease Effectiveness of Emergency Plan,Nrc Approval Not Required
ML20236Y0441998-08-0505 August 1998
Forwards Summary of Decommissioning Insp Plan Through March 1999.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability
ML20236V0651998-07-28028 July 1998
Ack Receipt of 980605 Request for Withdrawal of 980325 Request for License Amend for DPR-6,paragraph 2.C.(5), Physical Protection & Closes TAC MA0756
ML20236U4311998-07-24024 July 1998
Forwards Insp Rept 50-155/98-05 on 980528-0715.No Violations Noted.Nrc Concern That Programmatic Assessments of RPP Were Not Initiated Following Identification of Multiple Deficiencies in RP Program During First Half of 1998
IR 05000155/19980041998-07-0808 July 1998
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/98-04
ML20236M4131998-07-0707 July 1998
Ack Receipt of Ltr Dtd 980512,transmitting Changes Identified as Rev 14 to Big Rock Point Security Suitability, Training & Qualification Plan.No NRC Approval Required
ML20249C4391998-06-25025 June 1998
Ack Receipt of ,Which Transmitted Changes to Rev 14 to Suitability,Training & Qualification Plan,Submitted Under Provisions 10CFR50.54(p)
ML20249B3041998-06-16016 June 1998
Forwards Insp Rept 50-155/98-03 on 980407-0527.Violation Noted & Being Considered for Escalated Enforcement Action. Notice of Violation Not Presently Being Issued for Insp Finding
ML20248F3541998-05-28028 May 1998
Responds to to P Harris Which Requested That NRC Retain Resident Inspector at Big Rock Site to Monitor Project for Period of Five Years.Informs That NRC Intends to Assign Inspector to Site for One Year
ML20247M9481998-05-15015 May 1998
Ack Receipt of Ltr Dtd 980312,which Transmitted Changes Identified as Rev 7 to Safeguards Contingency Plan,Submitted Under Provisions of 10CFR50.54(p)
ML20217D1221998-04-21021 April 1998
Forwards Insp Rept 50-155/98-02 on 980203-0406.No Violations Noted.Emergency Preparedness Exercise Was Completed Satisfactorily,However,Unusual Event Was Declared When Algae Containing Co-60 Alarmed Discharge Canal Radiation Monitor
ML20217A5991998-04-16016 April 1998
Forwards Request for Addl Info Re Proposed Changes to Proposed Defueled TS as Detailed in .Questions Were Discussed W/Licensee Staff on 980121-22 & 980311.RAI Summarizes Questions That Remain
ML20216J4411998-04-16016 April 1998
Informs That Consumer Request for Exemption from Certain Requirements of 10CFR50.54, Condition of Licenses, Based On,In Part,Determination That Plant Permanantly Shut Down & Defueled Not Required
ML20216J9861998-04-16016 April 1998
Forwards SE Approving Licensee 970919 Submittal of Training Program for Certified Fuel Handlers.Comments Also Encl
ML20247L4021998-04-14014 April 1998
Discusses Rev 131 to Chapter 5 & Rev 132 to Chapters 2,3 & Appendix H of Big Rock Point Plant Emergency Plan Submitted Under Provisions of 10CFR50.54(q).No NRC Approval Required
ML20216G9071998-04-0808 April 1998
Responds to Asking Number of Questions Re Activities at Big Rock Point Nuclear Plant.Particularly on 980203 NRC Requested Addl Info from Utility Re Proposed Changes to Emergency Preparedness Plan
ML20217J2131998-04-0202 April 1998
Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided
IR 05000155/19970151998-03-20020 March 1998
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-155/97-15
ML20246H0091998-03-19019 March 1998
Discusses Rev 130 to App a of Big Rock Point Nuclear Plants Emergency Plan,Received in Sept 1997.NRC Approval Not Required Based on Determination That Changes Do Not Decrease Effectiveness of Emergency Plan
ML20203K7501998-02-26026 February 1998
Forwards Summary of Decommissioning Insp Plan for Remainder of Fy 1998.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events, Resource Availability
ML20203H8511998-02-23023 February 1998
Forwards Request for Addl Info Re Exemption from Offsite Emergency Planning Requirements.In Accordance with 10CFR50.30(b),response Must Be Executed in Signed Original Under Oath or Affirmation
ML20202J8111998-02-14014 February 1998
Forwards Insp Rept 50-155/97-15 on 971205-980202 & Notice of Violation.Activities in Areas of Facility Mgt & Control, Decommissioning Support & Spent Fuel Safety
ML20203E0811998-02-13013 February 1998
Informs That on 980331 & 0401,NRR Will Be Holding 1998 Decommissioning Power Reactor Counterparts Meeting in Arlington,Tx.Recipient Requested to Make Presentation at Subj Meeting.Meeting Agenda Encl
ML20202D7751998-02-0808 February 1998
Ack Receipt of Ltr Dtd 980116,which Transmitted Changes Identified as Rev 32 to Big Rock Point Security Plan, Submitted Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Plan
1999-09-30
[Table view] |
Text
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ymtb
/ sol e
NOV 121986 Docket No. 50-155 Consumers Power Company ATTN: Dr. F. W. Buckman Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 Gentlemen:
On April 24, 1986, Region III issued Inspection Report No. 50-155/86004(DRP)
documenting your commitment to replace the diesel engine for the diesel fire pump at the Big Rock Point Nuclear Plant. This commitment was required by my staff following discussions with your staff on the diesel engine reliability and maintainability.
-
Pursuant to NRC Manual Chapter 0514, "NRC Program for Management of Plant Specific Backfitting of Nuclear Power Plants," we have prepared an evaluation setting forth the justification for our position. A copy of this evaluation is enclosed for your informatio Please call me if you have any questions regarding this evaluation. If you wish to appeal our decision, the basis for your appeal should be addressed to me with a copy to the NRC Executive Director for Operation
Sincerely, cr!ainnl
.' r r, O. KeT(19@orD P
James G. Keppler Regional Administrator Enclosure: As stated cc w/ enclosure:
4 Mr. Kenneth W. Berry, Director Nuclear Licensing
'
D. P. Hoffman, Plant
{ Superintendent DCS/RSB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan s611140144 861112 5 Public Service Commission PDR ADOCK 0500 P
Nuclear Facilities and -
Environmental Monitoring Section T. H. Cox, ED0 p
/
RII RIII R II RIII gA .- ,/
rab /mnj N i avis Ke pjer g N*% 0 * gs l} u MBL h
-- -
