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| {{Adams | | {{Adams |
| | number = ML20151T203 | | | number = ML20247D002 |
| | issue date = 08/05/1988 | | | issue date = 07/18/1989 |
| | title = Insp Rept 50-155/88-13 on 880602-0718.Violations Noted.Major Areas Inspected:Surveillance Observation of Pressure Test on NSSS & Reactor Depressurization Sys & Security Observations Re Day to Day Plant Activities | | | title = Advises That Violation Noted in Insp Rept 50-155/88-13 Re Insp & Installation Activities of Diaphragms on CRD Scram Valves Withdrawn,Per Licensee Response.Nrc Has Understanding That Util Will Revise Training Program for Personnel |
| | author name = Jackiw I | | | author name = Greenman E |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| | addressee name = | | | addressee name = Hoffman D |
| | 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 = 50-155-88-13, IEB-88-005, IEB-88-007, IEB-88-5, IEB-88-7, NUDOCS 8808160287 | | | document report number = NUDOCS 8907240504 |
| | package number = ML20151T187
| | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | page count = 2 |
| | page count = 8 | |
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| U.S. NUCLEAR REGULATORY COMMISSION
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| l REGION III I f
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| hport No. 50-155/88013(DRP)
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| Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name: Big Rock Point Nu ear Plant Inspection At: Charlevoix, MI 49720 Inspection Conducted: June 2 through July 18, 1988 ,
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| Inspector: E. Plettner 8'd 7N Uate Inspector: N. Williamsen .
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| Date t
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| Approved By: 1 N !
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| ReactorPyojectsSection28 Date Inspection Summary Inspection on June 2 through July 18,1988 (Report No. 50-155/88-013(DRP))
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| Areas Inspected: The inspection was routine, unannounced, and conducted by-the Senior Resident Inspector and the Resident Inspector. The functional '
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| areas inspected consisted of the followina areas. Surveillance observation of the pressure test on the nuclear steam supply system and the reactor depressurization system. Maintenance observation of work performed on motor operated isolation valves and the reinstallation of the reactor depressurization valves. Operational safety verification, radiological
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| practices, and security observations involving day to day plant activitie Startup/ refuel activities associated with the refuel and startup of the reactor. NRC Bulletins on defective piping material and pover oscillations
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| | ,. i JUL 181989 |
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| | Docket No. 50-155 Consumers Power Company s ATTN: David P. Hoffman i Vice President ! |
| | Nuclear Operations l 1945 West Parnall Road |
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| | Jackson, MI 49201 |
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| ir, boiling water reactor Results: The licensee has demonstrated a desire to respond in a timely manner to issues and concerns presented to them by the NRC. The surveillance, maintenanca, operational safety, radiological program, and the security program appeared to ensure public health and safety. Two violations were
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| identified in this report. The violation in the maintenance section addresses inadequate quality controls and the violation in the operational safety section addresses the failure to follow procedure when using a copy
| | l This refers to your response to Inspection Report No. 50-155/88013 regarding the ) |
| - | | l inspection and installation activities of diaphragms on the control rod drive j scram valves. We have reviewed your response and the additional information ! |
| of a controlled documen gDR ApoCK 05000155 '
| | provided and have concluded that no violation of NRC requirements occurre i Therefore, we are withdrawing this violation and adjusting the appropriate records accordingl Since we view the repair activities of th,e scram valves as important to safety j requiring a high degree of overview and inspection, we concur with your ' |
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| | actions to provide additional direction with respect to inspection of this l activity. We viii examine this area during a future inspectio l l |
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| | With regard to your response to violation 155/88013-02, we noted that no I mention was made to provide continuing training on the correct practices for I |
| | using procedures in the field. Based on our discussions with members of your staff, we understand that you will revise your training program for personnel i that use working copy procedures to include the correct control of these procedure ; |
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| | RIlly R I RII RI Rill J cs A |
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| | n W5 M Gro e rney gh Greenman o |
| | /7///89 7/g /89 7/W/89 7/q/89 7/ f7/89 Et907240504 890718 ' /, ,/ S/ |
| | PDR ADOCK 05000155 o PDC |
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| DETAILS Persons Contacted
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| *T. Elward, Plant Superintendent
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| *A. Pet'tjean, Planni:ig and Administrative Services Superintendent G. Withrow, Engineering Maintenance Superintendent
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| *R. Alexander Technical Engineer L. Monshor, Quality As:urance Superintendent
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| *J. Seer, Chemistry / Health Physics Superintendent
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| *R. Scheels, ' Acting Operations Supervisor
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| "R. Hill, Sr. QA Consultant
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| *P. Donnelly, Nuclear Assurance Administrator
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| *R. Schrader, E & M Superintendent, Acting .
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| * Bielinski, Production and Plant Performance, Superintendent, Acting
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| *T. Hagan, Director Nuclear Training The inspector a'.so contacted other licensee personnel in the Operations, Maintenance, Radiation Protection, and Technical Department * Denotes those present at exit intervie . Monthly Surveillance Observation (61726)
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| The NRC inspectors observed Technical Specification required surveillance tests. The reviews and observations were conducted to verify that facility surveillance operations were performed in accordance with the requirements established in the Operating License and Technical Specificatio The Senior Resident Inspector (SRI) observed the licensee's performance of the following surveillance tests on the indicated dates:
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| June 20, 1988, TV-10, "Pressure Test of Nuclear Steam Supply System,"
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| Revision 37, dated June 14, 1988, with approved. temporary changes to allow the use of a new hydro test pump. A failed relief valve in the Reactor Water Clean-up System was noted during the test. A maintenance work order was issued and a new valve installed. The licensee also replaced two other relief valves in the system since they were the same age as the failed valve. A second test was performed and observed by the SRI on June 22, 1988, with satisfactory result July 13,1988, T30-30, "RDS Cabinet Test (Sensor Cabinet C/ Actuation Cabinet 3)," Revision 24, dated January 11, 1988. The procedure was satisfactorily performed by a licensed operator and an auxiliary operato No violations or deviations were identified in this are _ _
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| . Monthly Maintenance Observation ' ?703)
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| 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 and industry codes or standards and in conformance with technical specification The following items were considered during this review: the limiting .
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| 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 ond/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qual fied personnel; parts and materials used were properly certified; radiological controls were implemented; and fire prevention controls were implemente Work 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 June 18, 1988, the SRI observed the performance of maintenance on motor operated Valve IA-760 under Work Request 88-PCS-007 The SRI reviewed the certification test reports of the Reactor Depressurization System Valves from Wyle Laboratory. The certification reports identified each main valve and its associated pilot valve, the full-stroke time, the leak rates, acceptance criteria, and test proceoure used to perform the test. Pilot valve assembly number one failed the test on the first attemp Repairs were made and testing was conducted with the second test results being satisfactory. The certificate numbers were 49294-1, -2, -3, and -4. The SRI observed the installation of the valves on June 24 and 25, 1988, under Maintenance Work Orders 88-RDS-065 and 06 During the refueling / maintenance outage the licensee replaced the diaphragms in the Control Rod Drive Scram Valves (CRDSV), a safety-related system. All 64 valve diaphragms were replaced and tested for proper operatio It was during post maintenance testing that personnel discovered excessive air leakage from the valves. The licensee investigated the problem and found that the diaphragms had been installed upside down and, in addition, four of the 64 diaphragms had been incorrectly manufactured resulting in failure of the diaphragm Subsequently, all 64 diaphragms, manufactured by Hammel-Dahl, were replaced for a second time. The licensee sent a letter to General Electric and the Boiling Water Reactor Owner's Group to inform them of the possible defective diaphragms. Big Rock Point was one of the first plants to replace these diaphragms because of General Electric's Service Information Letter No. 457. The SRI inquired into the amount of Quality Control (QC)
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| provided during the maintenance activit The results of the inquiry revealed that QC had reviewed the purchase agreement documents before work and work completion documents. During the first installation performed in
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| April and May.1988, of the 64 diaphragms, no member'of:the plant's QC organization observed the activity through one complete disassembly, repai*, and reassembly process. No inspection was performed to include a dimensional. check of the diaphragms or a comparison between diaphragms fcr consistency. The failure to inspect installation activities.and perform measurements or tests of material ~ is an apparent violation of quality .
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| control requirements of 10 CFR 50, . Appendix B, Criterion X, as implemented by Big Rock Point's, "Quality Assurance Description for Operational Nuclear Power Plants," as described in Section 10. (155/88013-01).
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| Work on the CRDSVs was performed by Consumers Power Company's traveling ,
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| maintenance crew who had their own supervisor. Training was conducted for the crew prior to allowing work to commence on the CRDSV. Corrective actions taken b/ the licensee prior to the second installation in June 1988, were to revise the installation procedure, and have a plant QC individual observe at least one complete installation, The SRI verified by record review and interview that the licensee implemented the corrective actions. Full-stroke testing proved operability of the CRDS This problem resulted in an extended outage, a great deal of rework and testing, and additional cost to purchase the replacement part One violation was identified in this are . Operational Safety Verification (71707)
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| 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 maintenanc The inspector observed plant housekeeping /
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| cleanliness conditions and controls. During the. inspection period, the inspector walked down the accessible portions of the Reacto Depressurization Post Incident, Core Spray, and Containment Spray systems to. verify operabilit During plant tours conducted this period, the SRI noted that. copies of the controlled documents used to direct safety activities listed below were found at their associated work site without being marked "Working Copy" or "Working Controlled Copy," on the date shown:
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| June 18, 1988: System Operating Procedures (S0P) 19, "Make up System," Revision 14 June 21, 1988: S0P 15, "Condensate System," Revision 9 June 21, 1988: 50P 11, "Radioactive Waste System," Revision 11 July 6, 1988: Administrative Procedure 4.2.1, "Material Control," Revision . -
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| 10 CFR 50, Appendix B, Criterion V, as implemented by Big Rock Point's,
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| "Quality Assurance Program Description for Operational Nucle'ar Power Plants," as described in Section 5.0, requires that activities affecting quality shall be prescribed by documented procedures. Administrative Procedure 4.1.8 "Procedure Assurance," Revision 1, dated February 12, 1988, Section 12.0 titled "Short Term Controlled Documents," requires that controlled documents needed as working level procedures shall be clearly marked "Working Copy" or "Working Controlled Copy." Failure of the three working SOP's and the working Administrative Procedure to be marked
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| "Working Cr,sy" or "Working Controlled Copy," is an apparent violatio (155/88013-02).
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| One violation was identified in this are . Radiological Protection Observations (71709)
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| The NRC inspectors verified that-selected activities of the licensee's -
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| radiological protection program were. implemented in compliance with the facility policies, procedures, and regulatory requirements. The activities observed and/or reviewed during this inspection period were that health physics (HP) supervisory personnel were conducting plant tours to check on activities in progress. Radiation work permits contained the appropriate information to ensure work was performed in a safe and controlled manner. Personnel in radiation controlled areas (RCA) were wearing the required personnel monitoring equipment and protective clothing. Radiation and/or contamir.sted areas were properly posted and controlled based on the activity levels within the are Personnel properly frisked prior to exiting an RC No violations or deviations were identified in this are . Security Observations (71881)
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| The NRC Inspectors verified by observation or record review that physical security measures were being implemented as prescribed in the licensee's approved physical security plan. The elements contained in the inspection ,
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| were security manning requirements, access control of both personnel and' !
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| vehicles, and detection / assessment aids. Throughout the inspection period, the inspectors observed that personnel within the protected area )
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| (PA) properly displayed their identification badges. Vehicles were '
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| properly authorized, searcheu, and escorted or controlled within the P Persons and packages were properly checked and cleared before entry into the PA. When security equipment failure or impairment occurred the 1 required compensatory measures were empluyed. Security force actions !
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| were conducted in a professional manne '
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| No violations or deviations were identified in this are . Startup Testing - Refueling (72700)
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| On June 11, 1988, during refueling operations the licensee found that a l fuel bundle could not be placed into the position required by the fuel !
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| load sequence Procedure TR-46. . Fuel loading activities were stopped until the problem could be resolved. The reactor had been verified subcritical throughout the performance of the procedure. Core verification was performed with a TV camera to ensure all remaining fuel bundles were correctly loade No other bundles were found out of position. The reactor engineer made the necessary temporary changes, with approval, to the fuel load sequence procedure to place the misplaced bundle into.its correct position. The remaining steps of the procedure were completed without further problems. Final core verification was performed satisfactoril The. licensee will be performing an' evaluation to determine the root cause and recommend actions to prevent reoccurrenc This apparent violation of the fuel load sequence procedure will not be issued because it appears to meet the five criteria stated in 10 CFR 2, Appendix C (V), Section G.1: (a) it was identified by the licensee; (b) it fits in Severity Level IV or V; (c) it was reported, if required; (d) It is being corrected including measures to prevent recurrence, within a reasonable time; and (e) it was not a violation that could reasonably be expected to have been prevented by the licensee's corrective action for a previous violatio On June 27, 1988, at 7:59 p.m., the reactor at Big Rock Point achieved criticality following an 80 day refueling outage. The NRC inspectors observed the start-up. Besides the normal on-shift crew, an extra Reactor Operator and Auxiliary Operator were present. The start-up was performed in a professional manner with detailed procedures. Procedures used during the start-up were TV-34, "Reactor Start-up with Low Source Counts,"
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| Re<1sion 3, dated February 20, 1987; General Operating Procedure (GOP) 1,
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| "Plant Start-up from Cold Shutdown," Revision 115, dated May 14, 1988; '
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| and Technical Data Book 15.5.I.2, "Control Rod Withdrawal and Insertion Sequence Cycle 23," Revision 8 The plant continued to heat up within required limits and the required turbine overspeed trip tests were performed. Problems were encountered when the licensee tried to place the generator on line. When an electrical problem c: curred in the generator excitation and automatic voltage control, power ascension was halted to perform repairs. After rep- were completed and power was raised to approximately 20 megawatts elt ., control room Operators noted that each one of the three nei . stalled Wide Range Monitor (WRM) nuclear systems was indicating lev e than expected. Power ascension was halted until a course of action could be determined by the Plant Review Committee (PRC). Following several hours of discussion, the PRC decided to allow Instrument and ,
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| Control (I&C) technicians to move the detectors to a higher flux positio '
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| At 4:54 a.m., on June 29, power was raised to 35 megawatts electrical and a heat balance calculation was performe i I&C technicians using the heat balance calculation results attempted to !
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| calibrate the WRMi s with no success. The shift supervisor contacted l appropriate management personnel and a decision was made to shutdown the reacto Plant personnel commenced shutdown at 5:25 a.m., per GOP-6, i
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| "Plant Shutdown to Hot Shutdown," Revision 115. Shutdown was completed '
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| at 7:47 a.m., when all rods were fully inserte !
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| . | | Consumers Power 2 JUL 181989 Company |
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| | l We will gladly discuss any questions you have concerning this matte J Siacerely, ! |
| .. | | l original r:1 gad by '# L h*7 Edward G. Greenman, Director l Division of Reactor Projects cc: Mr. Kenneth W. Berry, Director Nuclear Licensing Thomas W. Elward,, Plant Manager 1 DCD/DCB (RIDS) |
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| | Licensing Fee Management Branch Resident Inspector, RIII , |
| During.the review of this event, the. licensee determined that the' shutdown met the criteria of Emergency Plan Implementing Procedures (EPIP-1) and at 8:00 a.m., on June 29, a Notification of-Unusual Event was declared. The NRC, the State.of Michigan, and the Charlevoix County Sheriff's Department were notified.within ten minutes. The event was terminated at 2:30 p.m.,
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| when the reactor achieved cold shutdown and the above agencies.were notified of the same. The licensee contacted General Electric, the equipment vendor, for assistance and subsequent repairs were completed by the morning of July 1. A reactor start-up was commenced per procedure but was terminated at 6:44 a.m., when the source range nuclear instruments failed to properly respond. A PRC meeting was conducted, a course of action was determined, subsequent repairs were.made, and post maintenance testing was completed. A reactor start-up commenced, with criticality being achieved at 5:41 p.m. on July When attempting to place the turbine generator on line early on July 2, a problem with the hydrogen seal oil system was discovered which resulted in a plant shutdown. Repairs were made and the reactor was re-started on July 7. The NRC inspector monitored the WRM's during power ascensio Following a heat balance calculation, I&C personnel were unable to calibrate WRM Channel 2. The channel was placed in the inoperable condition and power ascension was stopped until repairs could be accomplished. General Electric was contacted, repair parts for each of the three WRM channels were obtained and installed, and the WRM's were calibrated satisfactorily on July 1 Power ascension was resumed with heat balance calculations and calibrations of instruments being performed as necessar The NRC has been conducting a separate follow-up inspection of the problems encountered during the~ start-up of the WRM's. . Inspection Report No. 50-155/88017(DRS) will be completed after review of the Licensee's Event Report dealing with the same subjec No violations or deviations were identified in this are . Licensee Action on IE Bulletins
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| The NRC requested that all licensees review NRC Bulletin No. 88-05, Supplement 1, "Nonconforming Material Supplied By Piping Supplies Inc. at Folsom, New Jersey and West Jersey Manufacturing Company at Williamstown, New Jersey." The bulletin included information on defactive piping materials supplied by Piping Supplies Incorporated and also by West Jersey Manufacturing Company. The licensee's
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| investigation of the problem described in the bulletin revealed that Big Rock Point had never purchased any material from the above companie This item will remain open pending written confirmation from the license .. . .
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| NRC Bulletin No. 88-07, "Power Oscillations In Boiling Water Reactors (BWR)," issued June 15,.1988, required all BWR licensees to thoroughly brief all licensed reactor operators or shift technical advisors regarding the March 9, 1988, LaSalle Unit 2 event within 15 days of receipt. The event involved excessive neutron flux oscillation while the reactor was on natural circulation. The licensee completed the briefing of required on-shift individuals within the 15 day Other' required members of the ~
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| licensee staff who were on leave reviewed the material upon their retur The SRI reviewed the attendance sheet to verify licensee's action Item 1 of Requested Actions for NRC Bulletin No. 88-07 is close No violations or deviations were ident).'ied in this are . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
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| throughout the month and at the conclusion of the inspection period and 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 P i
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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: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] |
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,. i JUL 181989
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Docket No. 50-155 Consumers Power Company s ATTN: David P. Hoffman i Vice President !
Nuclear Operations l 1945 West Parnall Road
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Jackson, MI 49201
Gentlemen:
l l 1 l
l This refers to your response to Inspection Report No. 50-155/88013 regarding the )
l inspection and installation activities of diaphragms on the control rod drive j scram valves. We have reviewed your response and the additional information !
provided and have concluded that no violation of NRC requirements occurre i Therefore, we are withdrawing this violation and adjusting the appropriate records accordingl Since we view the repair activities of th,e scram valves as important to safety j requiring a high degree of overview and inspection, we concur with your '
actions to provide additional direction with respect to inspection of this l activity. We viii examine this area during a future inspectio l l
With regard to your response to violation 155/88013-02, we noted that no I mention was made to provide continuing training on the correct practices for I
using procedures in the field. Based on our discussions with members of your staff, we understand that you will revise your training program for personnel i that use working copy procedures to include the correct control of these procedure ;
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RIlly R I RII RI Rill J cs A
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n W5 M Gro e rney gh Greenman o
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PDR ADOCK 05000155 o PDC
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Consumers Power 2 JUL 181989 Company
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l We will gladly discuss any questions you have concerning this matte J Siacerely, !
l original r:1 gad by '# L h*7 Edward G. Greenman, Director l Division of Reactor Projects cc: Mr. Kenneth W. Berry, Director Nuclear Licensing Thomas W. Elward,, Plant Manager 1 DCD/DCB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII ,
Ronald Callen, Michigan !
Public Service Commission !
Michigan Department of l Public Health !
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