IR 05000289/1980029
| ML19350E093 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1981 |
| From: | Fasano A, Haverkamp D, Nicholas H, Rekito W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19350E092 | List: |
| References | |
| 50-289-80-29, NUDOCS 8106160654 | |
| Download: ML19350E093 (8) | |
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U.S. NUCLEAR REGULATORY CCMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No.
50-289/S0-29 Docket No.
50-289 Category C
License No. OPR-50 Priority
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Licensee:
Metrooolitan Edison Comoany P. O. Box 480 Middletown, Pennsylvania 17057 Facility Name: Three Mile Island N_uclear Station, Unit 1 Inspection at: Middletown, Pennsylvania Inspection conducted: Acoust 18-21, 1980, and Sectember 1 - October 31, 1980 Ins mctors:
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D. R. Haverkamp, Ser.1 r.
sicent Inspector cate sigr.ed
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W.~A.3 ReKito, Reactor In pector date 'st ned d
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date' signed
/J. H. NJcholas, Readtor Inspector
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Approved by: A. N. Fasano, Chief, Three Mile Island cate signed Section, Projects Branch #2 Insoection Summary:
Inspection on August 18-21, 1980, and Sectember 1 - October 31, 1980, (Inspection Report No. 50-289/80-29)
Areas Inspected:
Routine inspections by resident and region-based inspectors (124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br />) of licensee action on a previous inspection finding; the TMI-l Restart Testing Program; plant operations including facility tours and record reviews; review of periodic (monthly) reports; and licensee actinns on IE Bulletins.
Results:
No items of noncompliance were identified.
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Details 1.
Persons Contacted Metrocolitan Edison Comoany R. Barley, Lead Mechanical Engineer, TMI-l
"J. Colitz, Manager, Plant Engineering, TMI-l T. Crouse, Shift Foreman, TM!-1 D. Deiter, Shift Foreman, TM
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D. Dyckman, Supervisor, Corrective Maintenance, TMI-l J. Flint, Technical Supervisor, TMI-l
- J. Fornicola, Operations Quality Assurance Supervisor
- L. Harding, Supervisor of Licensing, TMI-l C. Hartman, Lead Electrical Engineer, TMI-l
- H. Hukill, Vice President and Director, TMI-1 0. Mitchell, Licensing Engineer, TMI-l V. Orlandi, Lead Instrument and Control (I&C) Engineer, TMI-l
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Porter, Supervisor, Startup and est W. Potts, Manager, Radiological Controls, TMI-l M. Ross, Supervisor of Operations, TMI-l
- R. Toole, Manager, TMI-l P. Velez, Supervisor of Radiological Centrols Technicians, TMI-l The inscector also interviewed several other licensee empicyees during the inspection. They included control room operators, maintenance personnel, engineering staff personnel and general office personnel.
- denotes those present at the exit interview on November 5,1980.
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2.
Licensee Action on a Previous Inscection Findina (Closed) Followup Item 289/80-10-02:
Licensee investigation of Reactor Coolant System Overflow event. The inspector reviewed Met-Ed memorandum from the TMI-l Supervisor of Operations to the Manager, TMI-1, serial OPI-80-22, Revision 2, dated July 21, 1980, " Inadvertent ESAS Actuation 6/27/80, Causing Radioactive Water Spill Inside Containment Building."
The letter described the inad/ertent actuatior and the investigation which was conducted to determine the cause of the incident and to recommend corrective actions to present recurrence. The investigation report included a description of plant conditions prior to the event, Control Room shift manning / location and experience levels, tne sequence of events, an environmental impact assessment, personnel / equipment / safety impact assessments, a narrative discussion of the investigation, and investigation conclusions. The investigation report also included a listing and description of eleven " Items Incorrect / Lessons Learned" as a result of the investigation and six corrective actions to be taken to prevent recurrence.
The investiga-tion report was considered thorough and appropriate. assessments and corrective actions were specified by the licensee. The inscector concurred with the PCR; determination that the event was not reportab;e and had no further questions concerning this item.
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3.
TMI-l Restart Testing Program The inspector met with the licensee's representatives for discussions of the preonerational testing portion of the TMI-l restart testing program.
Interviews and meetings with the startup group included discussions and reviews in the following areas.
Test programs
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Test organization
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Document controls
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Design changes and modifications
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Plant and preventive maintenance
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Equipment portection and cleanieness
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Test and measurement equipment
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Training
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The preceding areas were reviewed in order to ase,ertain their compliance with NRC preoperational test progrca requirements, applicable regulatory guides and licensee commitments (as contained in TMI-:, Recommended Requirements for Restart, Volumes 1, 2, and 3).
The discussions also included test procedures, test procedu)G review and
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approval, test sequencing, test scheduling, test procedure status and availab lity for review. Approved preoperational test procedures will be reviewed as they are received by NRC, Region I.
References used for discussions, interviews and reviews by the inspector included the following.
TMI-l Restart Project Organization and Responsibilities Document,
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Revision 0, approved June 13, 1980 l
TMI-l Recommended Requirements for Restart, Volumes 1, 2, and 3, l
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l approved September 13, 1979 TMI-l Operational Quality Assurance Plan, Revision 8, approved
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L April 18, 1980 l
NUREG 0578, TMI-2 Lessons Learned Task Force Status Report and Short
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Term Recommendations, dated July 1979
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NUREG 0680, TMI-l Restart, dated June 1980
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TMI-1, AP 1047, Startup and Test Manual, Revision 0, approved March
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19, 1980 TMI-1, AP 1043, Engineering Change Modification, Revision 0, approved
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June 12, 1978 Regulatory Guide 1.68, Initial Test Program for Water Ccoled Nuclear
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Power Plants Regulatory Guide 1.8, Personnel Selection and Training
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As a result of discussions with management and the startup group, interviews with licensee personnel, and examination and review of the referenced documents, the inspector verified that the licensee has met the NRC preoperational test program requirements and appears to have adequate administrative and management ccatrols for the required preoperational testing.
No discrr';4ncies were neted during this inspection and the inspector had no further questions at this time.
Implementation of the administrative and manapement controls for the preoperational test program requirements will ce examined during subsequent inspections.
4.
Review of plant Ocerations Inspection tours of selected plant areas were conducted during the day
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shift with respect to housekeeping and clearliness, fire protection, radiological controls, physical security and plant protection, operation and maintenance administrative controls and Technical Specification compliance. Acceptance criteria for the above areas included requirements of Technical Specifications; applicable regulatory guides and standards and approved licensee plans and procedures.
l In addition to conducting the plant area tours, the inspector regularly l
visited the Control Room during normal work hours to observe operations in progress, review logs and records and to conduct discussions with Control Room personnel. The inspector also frequently attended the l
licensee's Plan-of-the-Day (PCD) meetings, held by licensee management
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and supervisory personnel at 9:00 a.m., cach Monday, Wednesday anf Friday, i
to assess licensee evaluation of plant conditions, status and problems and to review the licensee's plans for conducting certain major plant l
operations and maintenance activities which require special department
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caordination and management review.
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No items of noncompliance were idertified during the review and cbservation of plant operations.
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5.
In-Office Review of Periodic. Reoorts The inspector reviewed the periodic reports listed below, which were submitted to the NRC Region I Office, to verify that the report included information required to be reported and that test results and/or supporting information discussed in the report were consistent with design predictions and performance specifications, as applicable.
The reports were dso reviewed to ascertain whetner planned corrective action was adequate for resolution of identified problems, where applicable, and to determine whether any information contained in the report should be classified as an Abnormal Occurrence.
The following TMI-l periodic reports were reviewed.
January Operating Report, dated February 15, 1980
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February Operating Report, dated March 18, 1980
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March Operating Report, dated April 15, 1980
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April Operating Report, dated May 15, 1930 May Operating Report, dated June 16, 1980
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June Operating Report, dated July 24, 1980
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July Operating Report, dated August 15, 1980
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The above reports were closed based on satisfactory in-office review.
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6.
Licensee Actions on IE Bulletins The inspector reviewed the licensee's followup actions regarding the IE Bulletins listed below.
IE Bulletin (IEB) 79-04, " Incorrect Weights for Swing Check Valves
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Manufactured by Velan Engineering Corporation," dated March 30, 1979 l
IES 79-07, " Seismic Stress Analysis of Safety Related Piping," dated
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l April 14, 1979-IEB 79-09, " Failures of GE Type AK-2 Circuit Breaker in Safety-Related
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Systems," dated April 16, 1979 I
IES 79-10, "Requalification Training Program Statistics," dated May
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11, 1979 IES 79-11, " Faulty Overcurrent Trip De4ces in. Circuit Breakers for
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Engineered Safety Systems," dated May 18, 1979
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IES 79-15, " Deep Draft Pump Deficiencies," dated July 11, 1979
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IEB 79-18, " Audibility Problems Encountered on Evacuation of Personnel
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from High Noise Areas,"_ dated September 7, 1979 IES 79-21, " Temperature Effects on Level Measurements," dated August
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13, 1979 IEB 79-23, " Potential Failure of Emergency Diesel Generator Field
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Exciter Transformer," dated September 12, 1979 IES 79-?4, " Frozen Lines," dated September 27, 1979
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IEB 79-25, " Failures of Westinghouse BFD Relays in Safety-Related
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Systems," dated November 2, 1979 IEB 79-28, "Possible Malfunction of NAMCO Model EA 180 Limit Switches
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at Elevated Temperatures," dated December 5, 1979 IEB 80-04, " Analysis of a PWR Mcin Stream Line Break with Continued
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Feedwater Addition," dated February 8,1980 IEB 80-05, " Vacuum Condition Resulting in Oc.: ye to Chemical Volume
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Control System Holdup Tanks," dated March 10, 1980 IEB 80-06, " Engineered Safety Feature Reset Controls," dated March
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13, 1980 IEB 80-09, "Hydromotor Actuator Deficiencies," dated April 17, 1980
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IES 80-12, " Decay Heat Removal System Operability," dated May 9,
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IEB 80-16, " Potential Misapplication of Rosemount Inc., Models 1151 l
and 1152 Pressure Transmitters With Either A or 0 Output Codes,"
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cated June 27, 1980
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IEB 80-20, " Failures of Westinghouse Type W-2 Spring-Return-to-Neutral
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Control Switches," dated July 31, 1980
l The review included discussions with licensee personnel, review of selected j
facility records, and observation of selected facility equipment and
components.
The inspector verified that licensee management forwarded copies of the bulletin response to appropriate onsite management representatives, that information and corrective action discussed in the reply was accurate and effected as described, and that the reply was submitted within the time period described in the bulletins.
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Acceptance criteria for the above review included inspector judgement and requirements of applicable Technical Specifications and facility procedures.
.The inspector found the licensee's actions regarding the Bulletins listed above to be complete and acceptable, with the exception of items noted below.
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IEB 79 required that all corrective actions for accessible areas
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be compl_ted within 120 days from issuance of Bulletia and that a schedule be provided for completing corrective action, in inaccessible areas. The licensee's response dated January 9,1980, identified proposed mcdifications of the High Radiation Monitoring Alarm System to assure audibility or visibility of alarms in high noise areas and committed to providing a schedule for completing these modifications at a later date. The inspector determined that as of October 31, 1980, none of the corrective actions had been implemented. The licensee's representative stated that a schedule would be provided and corrective actions will be completed prior to the next plant startup. This approach appeared to be acceptable to the inspector at this time.
IEB 79-18 will remain open pending further review of licensee's required actions during a subsequent inspection (289/79-BU-18).
The licensee's response to IES 79-21 identified the potential error
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in Steam Generator and Pressurizer level indication due to post
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accident containment ambient temperatures and committed to revising applicable emergency procedures and conducting specific operator training for these revised procedures prior to TMI-1 Restart. The inspector determined that the corrective actions were not yet completed, however licensee management is tracking the completion of these
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actions.
IEB 79-21 will receive further review to verify completion of corrective actions during a subsequent inspection (289/79-EU-21).
IEB 79-24 required that licensee's perform a review to assure that
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safety-related lines are adequately protected from freezing curing extremely cold weather and report the results of thei-review to the NRC by October 31, 1979. The licensee's response dated November 6, 1979 stated.a special procedure had been developed to inspect the condition / adequacy of all safety related freeze protection. The inspector verified that a special inspection had been performed on November 13, 1979, in accordance with work request #C1983.
During review of these records the inspector noted several instances where heat trace systems were found to be inoperable and no report of findings was submitted to the NRC. The licensee stated that a report of findings and corrective actions taken would be submitted to the NRC.
IEB 79-24 will remain open pending licensee completion of required actions and NRC review during a subsequent inspection (289/79-5U-24).
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The licensee's response to IEE 80-06, dated July 2,1980, identified
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a possible design deficiency for certain sampling system valves to return to " normal" upon reset of the containment isolation signal and committed to performing required verification tests by February 1981. The licensee's representative explained that subsequent to the initial response it was determined that the installed control room switches are different from those shown on the drawings, and as such no problem exists with their remaining in the emergency mode position upon reset of the containment isolation signal. The licensee's representative further stated that the applicable drawings were being corrected and a revised response to the NRC was being prepared.
IEB 80-06 will remain open pending further review of licensee's required actions during a subsequent inspection (289/80-SU-06).
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Exit Interview Meetings were held with senior facility management periodically during the course of the inspcction to discuss the inspection scope and findings.
The inspector met with the licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on November 5, 1980.
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