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| {{Adams | | {{Adams |
| | number = ML20212K028 | | | number = ML20216C280 |
| | issue date = 08/08/1986 | | | issue date = 06/23/1987 |
| | title = Insp Rept 50-285/86-19 on 860624-28.No Violation or Deviation Noted.Major Areas Inspected:Emergency Response Capabilities During Exercise of Emergency Plan & Procedures | | | title = Ack Receipt of 870527 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/86-19 |
| | author name = Baird J, Yandell L | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Andrews R |
| | addressee affiliation = | | | addressee affiliation = OMAHA PUBLIC POWER DISTRICT |
| | docket = 05000285 | | | docket = 05000285 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-285-86-19, NUDOCS 8608190028 | | | document report number = NUDOCS 8706300253 |
| | package number = ML20212K020
| | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | page count = 2 |
| | page count = 12 | |
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| | ..JUN l2 31987 r |
| - | | B .'In Reply ~ Refer To: |
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| | ' Docket: ,50-285/86-19 o |
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| | F '0maha Public Power. District E ATTN: R.'L..Andrews, Division Manager- |
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| APPENDIX
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| - ', U.S. ' NUCLEAR REGULATORY COMMISSION
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| ==REGION IV==
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| NRC Inspection Report: 50-285/86-19 License: DPR-40 Docket: 50-285 Licensee: Omaha Public Power District (0 PPD)
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| 1623 Harney Street Omaha, Nebraska 68102 Facility Name: Fort Calhoun Station (FCS)
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| Inspection At: Fort Calhoun, Nebraska Inspection Conducted: June 24-28, 1986 Inspector: duA \ I E![[#
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| J.1r. Baird, NRC Team ~Le er Da'te'
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| Other Inspectors: B. Bartlett, RI, RIV NRC R. Hogan, OIE NRC .
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| L. Rathbun, Pacific Northwest Laboratories G Bryan, Comex Corporation Approved: , E!f/fh L. A. Yandell, Chief, Emergency Preparedness Dat'e '
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| and Safeguards Programs Section Inspection Summary Inspection Conducted June 24-28, 1986 (Report 50-285/86-19)
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| Areas Inspected: Routine, announced inspection of the licensee's emergency response capabilities during an exercise of the emergency plan and procedure Results: Within the emergency response areas inspected, no violations or deviations were identified. Five emergency preparedness deficiencies were identified by NRC and contractor inspectors.
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| DR ADO K O 00 DR
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| | Nuclear: Production |
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| | '1623lHarney Street |
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| | ~ Omaha,. Nebraska 68102 Gentlemen.: |
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| | .Thank you for' your letter of May 27, 1987, in response.to our letter dated |
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| | l' August 13, 1986. We have' reviewed your reply and find it responsive to the concerns. 'We will review the implementation' of your corrective actions.during a future inspection:to determine that full compliance has been achieved and will.be maintained. |
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| l l-2-DETAILS l
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| l Persons Contacted Principal OPPD Personnel
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| *R. Andrews, Division Manager, Nuclear Production L. Borcherding, Quality Assurance Inspector C. Brunnert, Supervisor, Operations Quality Assurance
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| *A. Christensen, Health Physicist M. Core, Supervisor, Maintenance R. Cords, Senior Chemistry / Radiation Protection Technician T. Epley, Engineer
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| *F. Franco, Manager, Radiological Health and Emergency Preparedness
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| * Gates, Manager, Fort Calhoun Station
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| *J. Gasper, Manager, Administrative Services
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| *M. Gautier, Manager, Media Relations M. Hultman, Pipe Fitter R. Hyde, Supervisor, Maintenance Training
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| *R. Jaworski, Section Manager, Technical Services
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| *K. Morris, Division Manager, Quality Assurance and Regulatory Affairs
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| *C, Norris, Supervisor, Radiological Services G. Parrish, Operator, Auxiliary Building
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| *T. Patterson, Manager, Quality Assurance
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| * Roach, Supervisor, Chemistry and Radiation Protection B. Schmidt, Chemist
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| *H. Sterba, Division Manager, Corporate Communications
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| *K. Stultz, Technical Services Contractor Personnel J. Andrews, Hydro Nuclear D. Bloemendaal, Hydro Nuclear T. Jackson, Hydro Nuclear State of Nebraska H. Borchert, Department of Health R. Medina, Civil Defense Agency Federal Emergency Management Agency R. Leonard, Regional Assistance Committee Chairman M. Carroll, Senior Technological Hazards Specialist
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| | Sincerely, |
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| | J. E. Gagliardo, Chief Reactor Projects Branch cc: |
| * Harrell, Senior Resident Inspector Other OPPD, state, and contractor personnel were also contacted during the. inspectio ,
| | W. G. Gates,. Manager Fort Calhoun Station P. O. Box 399 i Fort Calhoun, Nebraska 68023 Harry H. Voigt, Esq. |
| * Denotes those present at the exit intervie . Licensee Action on Previously Identified Deficiencies (0 pen) Deficiency (285/8516-01): The NRC inspector noted that the , | | :LeBoeuf, Lamb, Leiby & MacRae 1333'New Hampshire Avenue, NW .! |
| scenario was improved in the areas of completeness and instructions for players and controllers; however, internal inconsistencies in plant systems status and source term impacted demonstration of scenario objectives. This item remains ope (Closed) Deficiency (285/8516-02): The NRC inspector determined that initial notifications to offsite agencies from the control room were adequate and sufficiently timely. This item is closed; however, a similar deficiency was observed in the emergency operations facility during this exercise (see paragraph 7).
| | Washington, D. C. 20036 j l |
| | Kansas-Radiation Control Program Director |
| | , Nebraska Radiation Control Program Director bcc: (see next.page) _ |
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| (Closed) Deficiency (285/8516-03): The NRC inspector noted that protective action recommendations released by the control room were performed and approved in accordance with procedures. This item is close ~ ~ (Closdd) Deficiency'(285/8516-05): The NRC inspector noted that control
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| _ room: personnel did respond according to procedure and when a release rate
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| was calculated withLa result of 1 E-8 Ci/sec but was transmitted as 1*E+8 Ci/sec, personnel in both the technical support center (TSC) and
| | bcc w/1tr dtd 5/27/87 from licensee: |
| , control room reccgnized the impossible number. This item is close (Closed) Deficiency (285/8516-06): The NRC inspector noted that
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| .information flow in the TSC was sufficiently prompt to allow the efficient handling of accident conditions. This item is close (Closed) Deficiency (285/8516-07): The NRC inspector determined that the analyses of events by the technical staff in the TSC were proper and adequate. This item is close (Closed) Deficiency (285/8516-08): The NRC inspector noted that radio communications with offsite field monitoring teams were adequate. This item is close (Closed) Deficiency (285/8516-09): The NRC inspector observed that first aid practices had been improved and determined that a new stretcher with security straps had been ordered. In addition, the health physics related observations during the previous exercise were adequately addressed although other radiation protection problems were identified during this exercise (see paragraph 6). This item is close .
| | l RPB Resident Inspector R. D. Martin, RA D. Weiss, RM/ALF RPSB Section Chief (RPB/B) |
| | | MIS System RIV File DRSP RSTS Operator RSB Inspector W. L. Fisher R. L. Bangart-R. E. Hall Project Inspector,.RPB NRR Project Inspector D. B. Matthews, NRR i |
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| _ .(Closed). Defic eh (285/8516-10): The NRC inspector determined from
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| exercise observers that the offsite monitoring teams properly identified y'(- c , samples.';This item is close :M l? .
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| ''3. ~ Exercise Scenario ,
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| p, j MThe_0 PPD exerciseiscenario was reviewed prior to the exercise to determine
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| - y)'*,- e that. provision-had been made for the required level of participation by state and local agencies, and that all major' elements.of emergency
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| ;- g ;, response would b'e exercised by OPPD in accordance with the requirements of-fN7 10'CFR-50.47(b),310 CFR'Part 50, Appendix E, paragraph IV.F, and the y% guidance criteria =in.NUREG-0654, Section I ;. f _/ .
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| Comments from'this review were transmitted to the OPPD scenario committee-
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| , chairman prior'to'the inspection date and each of the comments were addressed prior to the exercise. The scenario was considered to be much<
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| Jimproved over the previous exercise in terms of completeness of scenario data and instructions for players and controllers; however, during this exerr:ise, scenario inconsistencies which were not detected in the scenario review impacted the demonstration of objectives.- The most significant -
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| problem was an error of approximately two orders of magnitude too large for the radioactivity release source term. This conflicted with core damage assessments and offsite monitoring data, and resulted in significant problems in formulating and making protective action recommendations. The presence of internal inconsistencies'was an element in the deficiency (285/8516-01) identified during the previous exercise, and therefore, additional corrective actions must be implemented to close this emergency preparedness deficienc l No violations or deviations were identifie i
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| * Control Room Initial conditions were provided to the control room staff assigned to respond to the simulated emergency at approximately 5:40 a.m. by the
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| controller, and the exercise was initiated with a seismic event centered south of the station which damages the 345 kV southern grid lines. This resulted in declaration ~ of a Notification of Unusual Event (WOUE) by the .
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| licensee at approximately 5:45 ;
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| An Alert was subsequently declared at approximately 6:10 a.m. due to detection of a decrease of containment pressure and the elevation of stack flow and radioactivity indicating the. loss of one fission product barrie At approximately 9:15 a.m., a Site Area Emergency was declared resulting from damage to the station from a second, more severe seismic shoc :
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| Following the seismic shock, all offsite power is lost, one of the diesels fails to start, and a leak in containment results in a high containment radiation monitor alarm. This indicates the loss of two fission product ,
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| barriers. In the same time frame, a maintenance technician working on the ,
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| -5- 1 Plant conditions continued to deteriorate with an increase in the leak rate and radioactivity releas At approximately 10:15 a.m., a General Emergency was declared based on the loss of two fission barriers and the projected loss of the third barrie Offsite power was subsequently restored, the leakage controlled and the release of radioactivity to the environment terminate De escalation, recovery and reentry activities were initiated and the exercise concluded at approximately 3:25 The NRC inspector in the control room observed that personnel demonstrated appropriate use of emergency and abnormal operating procedures, together with classification and notification emergency plan implementing ;
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| procedures for the exercise event In addition, it was noted that control room operators demonstrated a good knowledge of plant systems design and system component locations and characteristic The NRC inspectors observed several instances of prompting during the exercise which impeded evaluation of the ability of the licensee's control room staff to implement procedure Examples are as follows:
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| . When the TSC requested core temperature, a controller gave the answer
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| "just use Psat" instead of looking up the value in a steam tabl This helped the operators know the core was at saturated conditions at a time when there was some discussion concerning superhea . On one occasion a controller said to the shift supervisor, "You're in an LCO now, aren't you?" instead of letting the shift supervisor determine if a limiting condition for operation (LCO) had been reache . A controller responded to a shift supervisor's question regarding what would happen if safety injection was throttled with the statement "nothing will happen, level will continue to climb and I will tell them later." This was at a time when the shift supervisor expected pressurizer level to be climbing due to injection flow when, in fact, level was climbing due to the bubble being formed in the reactor hea The NRC inspector in the control room also noted problems with the licensee's response related to an apparent lack of adequate coordination between the radiological emergency response plan (hereafter referred to as the Plan) and the security plan. For example, members of the licensee's emergency team responding tu the site were delayed access at the security building because security personnel did not know who was to be allowed
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| access to the plant in an emergency. In contrast, the NRC emergency site team badges were recognized by security as allowing access to the plant, but'the control room staff did not know that they were approved badges for this access. In addition, it was subsequently determined during the exercise that no procedures had been provided to control actions if the security' building had tp be evacuated due to radiological condition _ -
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| Based on the observations above, the following items are considered to be emer0ency. preparedness deficiencies:
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| . Prompting of exercise players in the control room detracted from the exercise realism and impeded the demonstration of the control room staff's capabilities to perform during an emergency. (285/8619-01)
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| . Security practices and procedures were not demonstrated to be adequately coordinated with the Plan and emergency plan implementing procedures. (285/8619-02)
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| The following is an observation the NRC inspectors called to the licensee's attention. This item is neither a violation nor an unresolved item. This item was recommended for licensee consideration for improvement, but has no specific regulatory requirement:
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| . More than one commercial telephone line should be provided in the control room to support additional emergency communications, including that expected by the NRC emergency team member (s) stationed in the control roo No violations or deviations were identifie . Technical Support Center The NRC inspector noted that the TSC activation was initiated at approximately 6:08 a.m., when the declaration of Alert was made. TSC staff began to arrive at about 6:24 a.m. and by approximately 7:00 the TSC was ready to be activated except that the TSC communicator was not present and dose assessment was still being performed in the control room because of a shortage of staff for this function in the TS The NRC inspector noted that the TSC activation was completed at approximately 7:22 a.m., about 1 hour and 14 minutes after the declaration of Aler This exceeded the goal of 1 hour for activation established by item 8.2.1 J of Supplement 1 to NUREG-073 The NRC inspector observed periodic, thorough, effective briefings of the TSC staff by the site director and timely telephone briefings of the NRC base team manager located in the NRC Region IV incident response cente In addition, the NRC inspector noted that the TSC technical and core physics staff provided good support in assessing plant status and a good plan of action was develnped for the next 24 hours of the acciden The NRC inspector also noted that status board time tagging of data was improved over previous exercises; however, some problems still existed in the timely display of TSC status board data and the units for containment pressure and containment sump leve The following are observations the NRC inspectors called to the licensee's attention. These observations are neither violations nor unresolved
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| item These items were recommended for licensee consideration for improvement,,but they have no specific regulatory requirement:
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| . LProvisions'should be made for the TSC staff to continue to perform
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| , dose assessment;after the responsibility for this function has been
| | Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 (IY,3EN |
| < transferred to the emergency operations facility (E0F) as a cross
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| check on EOF calculation . Additional communicator support should be provided for the TSC, such as more alternate responders for the TSC communicator and staffing of the NRC emergency notification system (ENS) and health physics network (HPN) telephone . Dedicated emergency response facility / safety parameter display system (ERF/SPDS) terminal operators should be trained and provided to operate the syste No violations or deviations were identifie . Operational Support Center The operational support center (OSC) functions are performed in two separate areas. The operations manager and shift operations personnel set up part of the OSC in the shift supervisors office adjacent to the control room, and all other OSC personnel operate from designated locations in the TSC building. All personnel in the TSC building report to the site director. The NRC inspector noted that this provided excellent face-to-face communication between the OSC and TS After initiation of the exercise, the OSC/TSC was declared operational in a timely manner; however, it was noted that the names of individuals filling each of the key positions were not posted or listed. As a result, it was not clear when the staff positions were actually fille In addition, insufficient personnel in the functional areas of health physics, maintenance and communications were available at various times during the exercise. In some instances, personnel assigned to normal plant functions were recruited to participate in the exercis The NRC inspector noted that accountability was accomplished using a pre-determined list of personnel who are assigned to the OSC/TSC. Other personnal who may report to the OSC/TSC were added to the list and personnel who did not report were deleted. This revised list was used to provide continuous accountability during the exercise. The NRC inspector noted that this method did not provide assurance that personnel added to the list were not missing elsewhere or that personnel deleted from the list were accounted for in another are The NRC inspector cbserved that the tag team monitor coordinator performed well in briefing teams, maintaining a log of health physics activities, assigning tasks to OSC personnel and assisting the health physics / chemistry supervisor. In addition, the maintenance supervisur and staff demonstrated awareness of ALARA concerns by performing a thorough
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| | May 27, 1987 LIC-87-336 L - - |
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| | J. E. Gagliardo, Chief Reactor Projects Branch l U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Tx. 76011 References: 1. Docket No. 50-285 2. Letter NRC (J. E. Gagliardo) to OPPD (R. L. Andrews) dated August 13, 1986 3. Letter OPPD (R. L. Andrews) to NRC (J. E. Gagliardo) dated September 19, 1986 (LIC-87-462) |
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| | ==Dear Mr. Gagliardo:== |
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| | SUBJECT: Inspection Report 86-19, Deficiency 8619-01 Per reference 3, Omaha Public Power District (OPPD) provided a schedule for correcting deficiencies that were identified by Reference 2. In response to Deficiency 8619-01, OPPD stated that a revision of EPT-10, " Annual Radiation Emergency Exercise", would be implemented. OPPD is currently in the process of reviewing, updating, and implementing this procedure, and this letter serves as an update to establish a new implementation date for completing actions related to 8619-01. The proposed completion schedule for this item is now June 30, 1987. If you have any further questions please contact us. |
| -8-analysis of tasks to be performed including all equipment needed, the time to perform the task and the number and type of personnel to accomplish the tas The NRC inspector noted that there were frequent habitability checks in the OSC/TSC after plant conditions warranted it. However, the results of each survey were verbally transmitted and not entered into the health physics / chemistry supervisor's logbook. In addition, it was noted that the particulate, iodine and noble gas (PING) monitor was left in-the
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| " alert" iodine alarm condition for 45 minutes after the first person reported to the TSC area and 20 minutes after the first report of satisfactory TSC habitability was mad 'In addition to the above~ observations, the NRC inspector noted several
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| examples of inadequate implementation of radiological protection for onsite personnel, as follows:
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| Insufficient thermoluminescent dosimeters (TLDs) and self reading dosimeters were provided for OSC/TSC personne . Personnel who were issued self-reading dosimeters in the OSC/TSC (other than teams) were required to zero their own dosimeter . There was no procedure for maintaining dose records or controlling doses for OSC/TSC personnel other than for teams that entered the plan . The use of previous dose records was not demonstrated during the 1 exercis . The chemistry / radiation protection technician assigned to the medical emergency did not check the uninjured worker for contamination. When he was informed of a clothing contamination problem at the frisking station, he did not take action to control the areas which had been contaminate . Safe routing through the plant was not discussed adequately for repair teams or visitor . Contamination control techniques were not demonstrated during the collection and analysis of sample . The tag team monitor coordinator's logbook contained inadequate information on reentry team status. In addition, the information was interspersed with other notes which made the information difficult to locat , .
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| -g-Based on observations by the NRC inspector in the OSC, the following item is considered to be an emergency preparedness deficiency:
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| . OSC/TSC implementation of radiological protection for onsite emergency personnel was inadequate to demonstrate satisfactory
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| . achievement of this objective. (285/8619-03)
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| The following are observations the NRC inspectors called to the licensee's attention. These observations are neither violations nor unresolved item These items were recommended for licensee consideration for improvement, but they have no specific regulatory requirement:
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| A method should be established to show the name of the individual filling each OSC/TSC staff position, both initially and for any change in position during the emergenc ~
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| . A method of accountability should be developed which does not depend on a predetermined list of personnel assigned to the OSC/TS . Sufficient personnel should be assigned to exercise participation to perform all necessary functions so that personnel assigned normal plant functions will not have to be recruited to participate during the exercis No violations or deviations were identifie *
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| . Emergency Operations Facility The EOF activation was initiated at approximately 6:30 a.m. based on anticipated public interest in the availability of electric service and the potential for disruption of communications due to the simulated seismic event. At about 8:10 a.m., the recovery manager announced that the E0F would be declared to be activated and would assume direction and control at 8:30 a.m. The activation was not announced at 8:30 a.m. when it occurred; however, the recovery manager did make subsequent announcements of significant events throughout the rest of the exercis The EOF was fully activated when a Site Area Emergency was declared at approximately 9:15 a.m. The NRC inspector noted that the recovery manager provided timely, effective briefings of the EOF staff during the exercise and demonstrated excellent control and direction of utility activitie The E0F activation took approximately 2 hours to complete, which is in excess of the 1 hour activation ~ goal established by Table 2 of Supplement 1 to NUREG-0737, but the NRC inspector noted that EOF activation is not required prior to the declaration of Site Area Emergency. OPPD has established the option to initiate EOF activation during the Alert state of an emergenc The NRC inspector noted that status boards were well maintained during the enercise, but the status of protective action recommendations versus those
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| | Sinc ely, R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector i |
| -10-implemented by offsite authorities was not provided. In addition, it was noted that offsite monitoring team data were not adequately displayed and compared with the dose assessment projection The NRC inspector noted that the recovery manager declared a General Emergency at about 10:15 a.m., based on the loss of two fission product barriers and the projected loss of the thir The protective action recommendation selected from the decision flow chart was to evacuate a 5 mile radius and sectors B, C and D for 10 mile Consultation with the state representatives resulted in approval and transmission of'a recommendation of 2 miles radius evacuation, in disagreement with the recommendation called for by the emergency plan-implementing procedure EIP-E0F-01. The time to reach concurrence with~the states of Iowa and Nebraska on protective actions recommended resulted in delay of this recommendation to about 10:43 a.m. Thus about 28 minutes,were required to approve and issue the recommendation to offsite authorities in noncompliance with the requirements of Section 4.D.3 of Appendix E to Part 50, which states that this must be accomplished within 15 minutes of declaring an emergency. In addition, the NRC inspector noted that OPPD did not consider the dose assessment calculations provided at about 10:13 a.m., which projected whole body doses of 18 rem over a 4 hour period at 10 miles from the plant. This would have required protective actions to be recommended out beyond 10 miles. The high doses calculated by dose assessment were subsequently determined after the exercise to be attributable to an error of approximately two orders of magnitude too high
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| in the source ter Based on the observations above, the following items are considered to be emergency preparedness deficiencies:
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| . Protective action recommendations, which must be formulated and provided within 15 minutes of declaring an emergency, were delayed by periods ranging from 28 to 40 minutes. (285/8619-04)
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| . Protective action decisionmaking was deficient in that OPPD failed to properly consider dose projection calculations which indicated more extensive protective recommendations than were made based on plant statu (285/8619-05)
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| The following are observations the NRC inspectors called to the licensee's attention. These observations are neither violations nor unresolved items. These items were recommended for licensee consideration for improvement, but they have no specific regulatory requirement:
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| . The update message forms transmitting protective action recommendations should have signature approval by the recovery
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| manager prior to transmission to offsite authorities, i
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| . A dosimeter log should be established and maintained for offsite monitoring team member r
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| . A display should be provided showing the protective action recommendations currently recommended and the status of the actual actions implemented by offsite authoritie No violations or deviations were identifie .
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| 8. Inplant Rescue and Medical Scenario The inplant first. aid portion of the exercise began at approximately 9:05 a.m. with the detection of a simulated injury of a maintenance technician and contamination of another maintenance technician working on the containment purge valves. The rescue team _was' dispatched to treat the injured worker and remove him to an area where the Blair. Rescue team ,
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| received him for transportation to the Uryiversity of Nebraska Medical Cente The NRC inspector noted that the Fort Calhoun rescue team did.not take-measures to protect themselves from contamination or limit the spread of contamination in the auxiliary building. In addition,*no check was ,
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| performed at the exi By the time the contaminated worker (noninjured maintenance technician) discovered his contamination he had potentially contaminated the hallway near the health physics office area. No efforts were made to survey or decontaminate this area. This problem with inplant'
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| radiological control was an element in the deficiency identified in .
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| Section 6 of this repor The NRC inspector also noted that the stretcher used for transporting the injured victim was inadequate in that no means for securing the victim on the stretcher was provided. The NRC inspector noted that a new stretcher had been ordered to correct this proble No violations or deviations were identifie . Exercise Critique The NRC inspectors attended the post exercise critiques by the licensee staff on February 26 and 27, 1986, to evaluate the licensee's identification of deficiencies and weaknesses as required by 10 CFR 50.47(b)(14) and Appendix E of Part 50, paragraph IV.F.5. It was noted that many of the observations by the NRC inspectors during the exercise were also independently made and reported by the OPPD staf Both the NRC and licensee's staff identified the deficiencies listed below. Corrective action for identified deficiencies and weaknesses will be examined during a future NRC inspection:
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| . Protective action recommendations were not made in compliance with procedure EIP-E0F-01 in that the recommendation selected through use of the decision chart was changed downward and approved for transmittal to offsite authorities without a supporting basis for the chang i ,
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| ;of protective action recommendation . Offsite monitoring-teams were not briefed on plant and release conditions prior to being dispatched to the fiel . 5,ecurity guards did not respond to the EOF in a timely fashio The following is an observation the NRC inspector called to the licensee's attention. This observation is neither a violation nor unresolved ite This item was recommended for licensee consideration for improvement, but it has no specific regulatory requirement:
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| . More attention should be given to briefing observers on previously identified deficiencies and weaknesses prior to initiation of the exercis No violations or deviations were identifie . Exit Meeting The NRC inspector met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on June 27, 1986. The NRC inspector summarized the purpose and the scope of the inspection and the findings. The NRC inspection team leader stated that although deficiencies were identified during the exercise, implementation of the plan and procedures in many of the areas observed was improved over the
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Category:CORRESPONDENCE-LETTERS
MONTHYEARLIC-99-0098, Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached1999-10-15015 October 1999 Forwards Revs to Fort Calhoun Station EPIPs & Emergency Planning Forms Manual.Document Update Instructions & Summary of Changes Are Included on Confirmation of Transmittal Form Attached ML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted LIC-99-0091, Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util1999-10-0808 October 1999 Submits Suppl Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, in Response to NRC RAI During 990817 Meeting with Util LIC-99-0097, Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls1999-10-0707 October 1999 Forwards Final RO & SRO License Applications,As Requested in ,Certifying That Training Completed for Six RO Candidates,Three Instant SRO Candidates & One Upgrade SRO Candidate.Without Encls ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 LIC-99-0089, Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl1999-09-24024 September 1999 Forwards Preliminary License Exam Applications for Six Ros, Three Instant SROs & One Upgrade SRO Candidate,Per Preparation for Ro/Sro Licensing Exams to Be Administered on 991025-29 at Fcs.Without Encl LIC-99-0092, Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl1999-09-21021 September 1999 Forwards Revised Epips,Including non-proprietary Rev 8 to EPIP-RR-66,rev 3 to EPIP-EOF-24,rev 14 to RERP-Section F,Rev 11 to RERP-Section I,Rev 12 to RERP-Appendix C & RERP & EPIP Indexes.Proprietary Rev 3 to EPIP-EOF-24,pages 1-3,encl LIC-99-0087, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-17017 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams LIC-99-0088, Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls1999-09-16016 September 1999 Forwards Documentation Associated with SRO License Renewal Application for Cd Darrow.Applicant Has Satisfactorily Completed Applicable FCS Requalification Program.Without Encls LIC-99-0080, Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection1999-09-16016 September 1999 Requests Approval of Attached Rev to QAP Contained in App a of Usar,Revising Commitment Re Qualifications of Personnel Performing Quality Control Insps of Activities Affecting Fire Protection LIC-99-0085, Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters1999-09-0808 September 1999 Forwards Revs 18 & 19 to TDB-VI, COLR for FCS Unit 1,IAW TS 5.9.5.Rev 18 Resulted from Reevaluation of Cycle 18 Setpoints & Rev 19 Resulted from Changes in Cycle 19 Refueling Boron Concentrations & Addition of TS Parameters IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License LIC-99-0083, Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase1999-09-0202 September 1999 Requests Participation in internet-based Y2K Early Warning Sys (Yews),As Noted in NRC Info Notice 99-25.Plant Point of Contact Will Be JW Chase ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl LIC-99-0077, Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld1999-08-27027 August 1999 Forwards non-proprietary & Proprietary Revised EP Forms, Including FC-EPF Index,Pp 1 Dtd 990805,pp 2 Dtd 990812,rev 11 to FC-EPF-9,rev 12 to FC-EPF-10,rev 9 to FC-EPF-11,rev 2 to FC-EPF-12 & Rev 3 to FC-EPF-38.Proprietary EP Withheld ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d)1999-08-20020 August 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) LIC-99-0078, Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld1999-08-20020 August 1999 Forwards Rev 16C to FCS Site Security Plan,Per Provisions of 10CFR50.54(p).Rev Has Been Determined Not to Degrade Effectiveness of Current Security Plans.List of Changes, Provided.Encl Withheld ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance LIC-99-0075, Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Fcs,Unit 1,per Plant TS 5.9.1.Revised Rept for June 1999,encl Due to Inadvertent Reporting of Gross Electrical Energy Data When Net Electrical Energy Data Was Required ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill LIC-99-0072, Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable1999-08-0606 August 1999 Requests That Licensee 990526 Application for Amend & Related Documents,Be Withdrawn.Util Requests That NRC Review Attached Responses to Ensure That Upcoming Submittal Will Be Acceptable ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams LIC-99-0068, Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-08-0202 August 1999 Documents OPPD Response to Requested Actions in GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal LIC-99-0040, Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-9903311999-07-28028 July 1999 Forwards Rept of Changes,Tests & Experiments Performed Per 10CFR50.59 & Revs to USAR Other than Those Resulting from 10CFR50.59.Encl Info Covers Period of 981101-990331 LIC-99-0070, Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program1999-07-28028 July 1999 Requests Reinstatement of SRO License Previously Held by K Grant-Leanna (License SOP-43569).Operator Is Current on All requalification-training Topics & Has Completed License Reactivation Program ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application LIC-99-0057, Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 0006301999-07-26026 July 1999 Forwards 1999/2000 Statement of Cash Flow from Operations, as Guarantee of Payment of Deferred Premiums for Period of 990630 to 000630 ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response LIC-99-0071, Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates1999-07-26026 July 1999 Informs That Util Expects to Submit Four Licensing Actions in Each of Fys 2000 & 2001,in Response to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates LIC-99-0069, Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld1999-07-23023 July 1999 Forwards non-proprietary & Proprietary Epips,Including FC- Epf Index Page & Page 2 ,rev 0 to FC- EPF-42,EPIP Index (Page 1 of 2) & EPIP-OSC-2, Cover & Pages 19 & 20.Proprietary Encls Withheld ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept LIC-99-0066, Forwards Fort Calhoun Performance Indicators Rept for May 19991999-07-0707 July 1999 Forwards Fort Calhoun Performance Indicators Rept for May 1999 LIC-99-0060, Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld1999-07-0101 July 1999 Forwards Proprietary & non-proprietary Revs to Fort Calhoun Station Emergency Plan Forms (Epf),Including FC-EPF,FC-EPF-1 & FC-EPF-17.Proprietary Info Withheld ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl LIC-99-0063, Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 9906241999-07-0101 July 1999 Requests Termination of License Held by MR Anderson (License SOP 43812) for Fort Calhoun Station.Anderson Ended Employment Effective 990624 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6561990-11-19019 November 1990 Forwards Amend 134 to License DPR-40 & Safety Evaluation. Amend Addresses Two Administrative Changes ML20216K0541990-11-14014 November 1990 Forwards Safety Evaluation Denying Request for Exemption from Requirements of 10CFR50,App R for Fire Area 34B for Wide Range Nuclear Power Instrumentation Channels.Required Level of Protection Not Provided ML20062E4641990-11-0909 November 1990 Forwards Insp Rept 50-285/90-42 on 901015-19.No Violations or Deviations Noted ML20058H0551990-11-0101 November 1990 Forwards List of Unimplemented Gsis,Per Generic Ltr 90-04 ML20058C6821990-10-24024 October 1990 Offers No Comment on Annual Exercise Scenario Submitted Via ML20058A3901990-10-19019 October 1990 Advises That Maint Team Reinspection Scheduled for Wks of 901203 & 10.Meetings Will Be Scheduled on 901113-14 in Preparation for Insp.List of Required Matls Encl ML20062B6041990-10-12012 October 1990 Forwards Amend 133 to License DPR-40 & Safety Evaluation. Amend Modifies Tech Spec to Increase Refueling Boron Concentration & Revise Storage Requirements of Spent Fuel Pool Region 2 ML20059N3311990-09-28028 September 1990 Forwards Final SALP Rept 50-285/90-24 for Period of May 1989 - Aug 1990.Actions Discussed in 900726 SALP Mgt Meeting & Util 900827 Response to Initial SALP Rept Considered to Be Responsive to NRC Concerns & Recommendations ML20059M6751990-09-28028 September 1990 Forwards Insp Rept 50-285/90-35 on 900729-0910.No Violations or Deviations Noted ML20059K7061990-09-14014 September 1990 Disagrees W/Position That More Detailed Design & Safety Assessment Using Ipe/Pra Appropriate Framework,Per Generic Ltr 89-19 ML20059K3691990-09-14014 September 1990 Ack Receipt & Review of Changes to Emergency Plan Re Emergency Facilities & Equipment Based on Review of .Proposed Changes Acceptable ML20059J9871990-09-13013 September 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010.W/o Map of Exam Area & Preliminary Instructions to Participant Encl ML20056B4071990-08-20020 August 1990 Forwards Insp Rept 50-285/90-34 on 900730-0803.No Violations or Deviations Noted.Unresolved Items Identified in Paragrphs 2.1 & 4.0 of Encl Insp Rept ML20059A2211990-08-17017 August 1990 Forwards Evaluation of Cen 387-P, Pressurizer Surge Line Thermal Stratification. Info Provided by C-E Owners Group in Ref 1 & 2 Inadequate to Justify Meeting All Appropriate Limits for 40-yr Plant Life ML20058M8071990-08-10010 August 1990 Discusses Closeout of NRC Bulletin 90-001, Loss of Fill-Oil Transmitters Mfg by Rosemount. Util Replaced Four Transmitters Which Fell within Scope of Bulletin During Refueling & Maint Outage ML20058N3711990-08-10010 August 1990 Advises That Programmed Enhancements for Generic Ltr 88-17, Loss of DHR, Acceptable ML20056A5761990-08-0707 August 1990 Forwards Request for Addl Info to Review Alternate Seismic Criteria & Methodologies for Facility ML20056A7551990-08-0606 August 1990 Advises of Concluded Investigation Case 4-87-016 Re Alleged False Welding Records,Violations of Employee Protection & Cheating on Welding Performance Tests.Allegations Unsubstantiated ML20056A1721990-07-30030 July 1990 Advises That Written Licensing Exams Scheduled on 901113 & Operating Licensing Exams Scheduled on 901114 & 15.Licensee Requested to Furnish Ref Matl Listed in Encl 1 by 900917 in Order to Avoid Exam Being Rescheduled ML20056A3461990-07-27027 July 1990 Summarizes 900724 Meeting W/Util in Region IV Ofc Re Changes to Operator Licensing Program ML20055J1461990-07-23023 July 1990 Forwards Insp Rept 50-285/90-30 on 900513-0616 & Notice of Violation.App C Withheld from Public Per 10CFR73.21 ML20055G1791990-07-18018 July 1990 Ack Receipt of Advising NRC of Corrective Actions in Response to Violations Noted in Insp Rept 50-285/90-13. Implementation of Actions Will Be Reviewed During Future Insp ML20055G3931990-07-16016 July 1990 Informs That Financial Info Submitted for 1990 in Util Satisfies 10CFR.140 Requirements ML20055F6841990-07-12012 July 1990 Forwards Initial SALP Rept 50-285/90-24 for May 1989 - Apr 1990 IR 05000285/19900021990-07-0909 July 1990 Ack Receipt of 900507 & 0629 Responses to Violations & Deviations Noted in Insp Rept 50-285/90-02 ML20055G0171990-07-0606 July 1990 Forwards Amend 132 to License DPR-40 & Safety Evaluation. Amend Changes Tech Spec Pages 5-1,5-5,5-8 & 5-9a to Incorporate Title Changes as Result of Reorganization & Partial Relocation of Emergency Planning Dept IR 05000285/19900291990-07-0505 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/90-29 ML20055C7901990-06-18018 June 1990 Forwards Insp Rept 50-285/90-26 on 900416-0512.Violations Noted.No Citations Issued for Violations Discussed in Paragraphs 5.a,5.b, & 5.c of Rept ML20055C8051990-06-15015 June 1990 Forwards Insp Rept 50-285/90-25 on 900402-06 & 16-19 & Notice of Violation.Violations Pertain to Inadequate Assessment Aids,Detection Aids,Compensatory Measure & Key Control ML20059M9681990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C4101990-02-23023 February 1990 Advises That 891010 & 1207 Changes to Emergency Plan Reviewed by Emergency Preparedness Staff & Acceptable ML20248C7421989-09-28028 September 1989 Forwards Insp Rept 50-285/89-32 on 890801-31.Noted Violations Not Being Cited to Encourage & Support Util self-identification & Correction of Problems.One Unresolved Item Discussed in Paragraph 7.a of Rept ML20248C4901989-09-22022 September 1989 Forwards Summary of 890828 Enforcement Conference in Arlington,Tx to Discuss Violations Noted in Insp Repts 50-285/89-10 & 50-285/89-31.Attendance List Also Encl ML20247Q6361989-09-21021 September 1989 Forwards Amend 8 to Indemnity Agreement B-67,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements IR 05000285/19890011989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-285/89-01.NRC Will Withdraw Items 3 & 4 If Review of Safety Evaluation Documentation Found to Be Adequate ML20247L2491989-09-18018 September 1989 Advises That 890907 Meeting W/Util Re Status of Plant Safety Enhancement Program Provided for Better Understanding of Progress Util Made in Implementing Program.List of Attendees & Meeting Slides Encl ML20247L6161989-09-0606 September 1989 Advises That 890808 Priority Description & Interim Milestones for Rev of safety-related Procedures & Commitment to Final Completion Date of 901231 Acceptable.Nrc Should Be Notified If Interim Milestones Cannot Be Met ML20247A3151989-08-30030 August 1989 Forwards Final SALP Rept 50-285/89-19 for May 1988 - Apr 1989,summary of 890713 Meeting to Discuss SALP Rept & Util 890817 Response to SALP Rept ML20247B1611989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20247B4191989-08-29029 August 1989 Forwards Insp Rept 50-285/89-28 on 890701-31.No Violations or Deviations Noted.One Unresolved Item Identified ML20246F0161989-08-25025 August 1989 Forwards Insp Rept 50-285/89-30 on 890724-28.No Violations or Deviations Noted ML20246D5521989-08-23023 August 1989 Discusses Util Response to Generic Ltr 89-08, Erosion/ Corrosion-Induced Pipe Wall Thinning, & Advises That Licensee Maintain,In Auditable Form,Records of Program ML20246E0791989-08-18018 August 1989 Discussess Insp Repts 50-285/89-10 & 50-285/89-23 on 890227-0303 & 0508-10 & Forwards Notice of Violation. Decision Not Reached by NRC Re Failures to Adequately Protect Safeguards Info from Compromises,Per 10CFR73.21 ML20246A0531989-08-17017 August 1989 Forwards Supplemental Safety Evaluation for Rev 4 to Inservice Testing Program for Pumps & Valves,Per Generic Ltr 89-04 ML20245H8901989-08-15015 August 1989 Forwards Safety Evaluation Supporting Util 890215 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Vendor Interface for Reactor Trip Sys Components ML20245K3431989-08-11011 August 1989 Forwards Safety Evaluation Determining That Isolation Devices Qualified & Acceptable for Interfacing Safety & Nonsafety Sys Re Implementation of ATWS Rule 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217G9261999-10-15015 October 1999 Forwards Insp Rept 50-285/99-10 on 990913-17.One NCV Noted ML20217G2331999-10-14014 October 1999 Forwards Insp Rept 50-285/99-09 on 990913-17.No Violations Noted ML20217B5111999-10-0606 October 1999 Forwards Amend 193 to License DPR-40 & Safety Evaluation. Amend Revises TS Sections 2.10.4,3.1 & Table 3-3 to Increase Min Required RCS Flow Rate & Change Surveillance require- Ments for RCS Flow Rate ML20216H7231999-09-29029 September 1999 Informs That Util 980325 Response to GL 97-06, Degradation of SG Internals, Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Fort Calhoun Station,Unit 1 ML20212L9571999-09-27027 September 1999 Informs That Follow Up Insp for Drill/Exercise Performance Indicator Will Be Conducted During Wk of 991001 IR 05000285/19990081999-09-0707 September 1999 Forwards Insp Rept 50-285/99-08 on 990907-0811.No Violations Noted.Insp Consisted of Exam of Activities Conducted Under License as Relate to Safety & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211P2581999-09-0303 September 1999 Forwards Insp Rept 50-285/99-06 on 990809-12.No Violations Noted.Insp Consisted of Exam of Activities Under License as Related to EP & to Compliance with Commission Rules & Regulations & with Conditions of License ML20211L3241999-09-0202 September 1999 Informs That Due to Administrative Error,Page 2-50 of TSs Contained Error on 2.10.2(2) of Amend 192 to License DPR-40 Issued on 990727.Corrected Page Encl ML20211J9231999-09-0202 September 1999 Forwards SE Accepting Licensee 990301 Requests for Relief Re Third 10-year ISI Interval for Plant,Unit 1.Relief Proposed Alternatives to Requirements in ASME B&PV Section XI,1989 Edition,Paragraphs IWA-5242(a) & IWA-5250(a)(2) ML20211F4491999-08-25025 August 1999 Forwards Ltr from Ja Miller,Dtd 990819,which Notified State of Iowa of Deficiency Identified During 990810,Fort Calhoun Station Biennial Exercise.One Deficiency Identified for Not Adequately Demonstrating Organizational Capability ML20210R1491999-08-13013 August 1999 Forwards Insp Rept 50-285/99-07 on 990719-23.No Violations Noted.Nrc Identified One Issue Which Was Evaluated Under Risk Significance Determination Process & Was Determined to Be of Low Risk Significance ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210P8991999-08-0909 August 1999 Forwards FEMA Final Rept for 990630 Offsite Medical Drill. No Deficiencies or Areas Requiring Corrective Action Identified During Drill ML20210N1991999-08-0909 August 1999 Informs That as Result of NRC Review of Licensee Responses to GL 92-01,rev 1,suppl 1 & Suppl 1 Rai,Staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210G1851999-07-27027 July 1999 Forwards Amend 192 to License DPR-40 & Safety Evaluation. Amend Consists of Changes to TS in Response to 990129 Application ML20216D6951999-07-26026 July 1999 Informs That During 990614 Review of Fort Calhoun,Nrc Noted That Drill/Exercise Performance Indicator Has Entered White Band,Which Indicated Level of Licensee Performance That Warranted Increased Regulatory Response ML20210D9471999-07-22022 July 1999 Forwards Amend 191 to DPR-40 & Safety Evaluation.Amend Authorizes Rev to Licensing Basis as Described in Updated Safety Analysis Rept to Incorporate Mod for Overriding Containment Isolation ML20210C0201999-07-20020 July 1999 Informs That Due to Administrative Oversight,Revised TS Bases Provided in to Fort Calhoun Station Were Not Dated.Dated Pages to TS Encl ML20210C2041999-07-20020 July 1999 Discusses 990715 Mgt Meeting with Midamerican Energy Co Re risk-informed Baseline Insp Program Recently Implemented at Cooper & Fort Calhoun Stations ML20210B0761999-07-19019 July 1999 Forwards Insp Rept 50-285/99-05 on 990601-0710.No Violations Noted ML20209G5351999-07-15015 July 1999 Informs That Staff Incorporated Rev of TS Bases Provided by Licensee Ltr Dtd 980904,into Fort Calhoun Station Tss. Staff Finds Revs to Associated TS Bases to Be Acceptable. Revised Bases Pages Encl ML20209F5741999-07-12012 July 1999 Ack Receipt of Transmitting Exercise Scenario for Upcoming Biennial Offsite Exercise Scheduled 990810.Scenario Reviewed & Acceptable ML20209G5591999-07-0808 July 1999 Forwards Detailed Listing of Staff Concerns with C-E TR NPSD-683,rev 3 & RCS pressure-temperature Limits Rept ML20209D8771999-07-0101 July 1999 Summarizes 990630 Public Meeting Conducted in Fort Calhoun, Ne Re Results of Completed Culture Survey,Plant Status, Facility Activities Re New NRC Oversight Process & License Renewal.Licensee Handout & Attendance List Encl ML20196F4931999-06-24024 June 1999 Discusses 990617 Public Meeting at Dana College,Blair,Ne Re Overview of Pilot Insp Program ML20196D2321999-06-21021 June 1999 Forwards Corrected Cover Ltr for Insp Rept 50-285/99-04. Original Cover Ltr Incorrectly Stated That Rept Contained Two Noncited Violations,When Rept Actually Documented Only One ML20195J2121999-06-14014 June 1999 Ack Receipt of Ltr Dtd 990316,which Transmitted Rev 16B to Site Security Plan,Rev 2 to Safeguards Contingency Plan & Rev 6 to Training & Qualification Plan for Plant,Under Provisions of 10CFR50.54(p) IR 05000285/19990041999-06-11011 June 1999 Corrected Ltr Forwarding Insp Rept 50-285/99-04 on 990425-0531.Insp Determined That One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation, Consistent with App C of Enforcement Policy ML20195J2481999-06-11011 June 1999 Forwards Insp Rept 50-285/99-04 on 990425-0531.Violations Identified & Being Treated as Noncited ML20195G3141999-06-10010 June 1999 Ack Receipt of & Encl Objectives for Facility Emergency Plan Exercise,Scheduled for 990810 ML20195E8391999-06-0909 June 1999 Ack Receipt of Transmitting Changes to Licensee Emergency Plan,Rev 14 & Emergency Plan Implementing Procedure OSC-1 Under Provisions of 10CFR50,App E,Section IV ML20207G4741999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP-OSC-1, Emergency Classification,Rev 31,under Provisions of 10CFR50, App E,Section V ML20207G4631999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Ep,App B,Rev 4,under Provisions of 10CFR50,App E,Section V.No Violations Identified During Review ML20207G2981999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station Radiological Er Plan,Section E,Rev 22,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required Due to Determination That Effectiveness Unchanged ML20207G4661999-06-0808 June 1999 Ack Receipt of Which Transmitted Changes to Fort Calhoun Station EP Implementing Procedure EPIP OSC-1, Emergency Classification,Rev 30,under Provisions of 10CFR50, App E,Section V ML20195G3621999-06-0808 June 1999 Ack Receipt of ,Which Transmitted Changes to Fort Calhoun Station Emergency Plan,App A,Rev 15,under Provisions of 10CFR50,App E,Section V.Nrc Approval Not Required ML20207G3401999-05-27027 May 1999 Informs That NRC Held Planning Meeting on 990511 for Fort Calhoun Station to Identify Insp Activities at Facility for Next 6 to 12 Months.Informs of NRC Planned Insp Activities & Offers Licensee Opportunity to Provide Feedback ML20207A9041999-05-24024 May 1999 Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl ML20206U6331999-05-18018 May 1999 Forwards Insp Rept 50-285/99-03 on 990314-0424.Four Violations of NRC Requirements Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20206L4151999-05-10010 May 1999 Forwards SE of OPPD Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20206H4471999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key,Encl for Info.Without Encl ML20206E7201999-04-28028 April 1999 Responds to Meeting Conducted 990419 in Fort Calhoun,Ne Re Results of PPR Completed 990211.Addl Topics Discussed Included New Assessment Process & Upcoming Actions Planned in Response to Y2K Concerns ML20205Q5671999-04-15015 April 1999 Forwards Amend 190 to License DPR-40 & Safety Evaluation. Amend Revises TS 5.2.f & TS 5.11.2 to Change Title of Shift Supervisor to Shift Manager ML20205J2751999-04-0202 April 1999 Forwards Insp Rept 50-285/99-02 on 990131-0313.No Violations Noted.During Insp,Licensee Conduct of Activities at Fort Calhoun Station Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices ML20205A7191999-03-19019 March 1999 Informs That on 990211 NRC Staff Completed PPR of Fort Calhoun Station.Review Was Conducted for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20207K6151999-03-11011 March 1999 Forwards Insp Rept 50-285/99-01 on 990208-26.One Noncited Violation Was Identified ML20207E8691999-03-0303 March 1999 Forwards Correction to Amend 188 to License DPR-40 for Plant,Unit 1.Administrative Error,Three Pages of TSs Contained Errors,An Incorrect Page Number,Missing Parenthesis & Misspelled Words ML20203F2041999-02-11011 February 1999 Informs That During 990208 Telcon Between Mc Ralrick & J Pellet & T Stetka,Arrangements Were Made for Administration of Licensing Examinations at Fort Calhoun Station for Week of 991018 1999-09-07
[Table view] |
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B .'In Reply ~ Refer To:
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F '0maha Public Power. District E ATTN: R.'L..Andrews, Division Manager-
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Nuclear: Production
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~ Omaha,. Nebraska 68102 Gentlemen.:
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.Thank you for' your letter of May 27, 1987, in response.to our letter dated
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l' August 13, 1986. We have' reviewed your reply and find it responsive to the concerns. 'We will review the implementation' of your corrective actions.during a future inspection:to determine that full compliance has been achieved and will.be maintained.
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Sincerely,
J. E. Gagliardo, Chief Reactor Projects Branch cc:
W. G. Gates,. Manager Fort Calhoun Station P. O. Box 399 i Fort Calhoun, Nebraska 68023 Harry H. Voigt, Esq.
- LeBoeuf, Lamb, Leiby & MacRae 1333'New Hampshire Avenue, NW .!
Washington, D. C. 20036 j l
Kansas-Radiation Control Program Director
, Nebraska Radiation Control Program Director bcc: (see next.page) _
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J. E. Gagliardo, Chief Reactor Projects Branch l U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Tx. 76011 References: 1. Docket No. 50-285 2. Letter NRC (J. E. Gagliardo) to OPPD (R. L. Andrews) dated August 13, 1986 3. Letter OPPD (R. L. Andrews) to NRC (J. E. Gagliardo) dated September 19, 1986 (LIC-87-462)
Dear Mr. Gagliardo:
SUBJECT: Inspection Report 86-19, Deficiency 8619-01 Per reference 3, Omaha Public Power District (OPPD) provided a schedule for correcting deficiencies that were identified by Reference 2. In response to Deficiency 8619-01, OPPD stated that a revision of EPT-10, " Annual Radiation Emergency Exercise", would be implemented. OPPD is currently in the process of reviewing, updating, and implementing this procedure, and this letter serves as an update to establish a new implementation date for completing actions related to 8619-01. The proposed completion schedule for this item is now June 30, 1987. If you have any further questions please contact us.
Sinc ely, R. L. Andrews Division Manager Nuclear Production RLA/me cc: LeBoeuf, Lamb, Leiby & MacRae W. A. Paulson, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector i
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