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| {{Adams | | {{Adams |
| | number = ML20154L755 | | | number = ML20211J953 |
| | issue date = 02/06/1986 | | | issue date = 11/03/1986 |
| | title = Insp Repts 50-317/85-22 & 50-318/85-20 on 850909-13.No Violation Noted.Major Areas Inspected:Evaluations of Unit 2 Implementation of Equipment Qualification Corrective Action Commitments Per 10CFR50.49 | | | title = Ack Receipt of 860630 & 0728 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/85-22 & 50-318/85-20 |
| | author name = Hubbard G, Potapovs U | | | author name = Ebneter S |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Lundvall A |
| | addressee affiliation = | | | addressee affiliation = BALTIMORE GAS & ELECTRIC CO. |
| | docket = 05000317, 05000318 | | | docket = 05000317, 05000318 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-317-85-22, 50-318-85-20, NUDOCS 8603120225 | | | document report number = NUDOCS 8611110508 |
| | package number = ML20154L753
| | | 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 = 17 | |
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| is o s-U.S.. Nuclear Regulatory Commission Offi'ce of Inspection and Enforcement Report Nos.: 50-317/85-22; 50-318/85-20 Docket Nos.: 50-317/318 License Nos.: DPR-53/69 Licensee: Baltimore-Gas and Electric Company
| | NOV 3 ~ 1986 Docket Nos. 50-317 50-318 Baltimore GTs and Electric Compan ATTN: Mr. A. E. Ludvall, J Vice President, Supply |
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| | - P. O. Box 1475 Baltimore, Maryland 21203 Gentlemen: |
| Charles Center Post Office Box 1475 Saltimore, Maryland 21203 Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 & 2 Inspection at: Baltimore and Lusby, Maryland Inspection Conducted: September 9-13, 1985 Inspector: .2 G. T. Hubbard, Eouipment Qualification and Test Engineer A/ [
| | Subject: Combined Inspection Nos. 50-317/85-22 and 50-318/85-20 This refers to'your letter dated July 28, 1986, in response to our letter dated June 25, 198 Thank you for 1'nforming us of the corrective actions documented in your letter |
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| | - to B. K.' Grimes of NRC, dated June 30,1986 (reference b in your letter to us). |
| Also participating in the inspection and contributing to the report were:
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| R. N. Moist, Engineer, I&E P. Shemanski, Engineer, NRR M. Schaeffer, Reactor Engineer, RI
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| 'L. Cheung, Reactor Engineer, 91 M. Trojovsky, Consultant, Idaho National Engineering Laboratory E. Richards, Consultant, Sandia National Laboratory Approved: %V cA-6%
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| Uldis Potapovs, Chief,[EQIS, Vendor Pronram Branch, I&E Date t
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| I 8603120225 860304 PD ADOCK 0 % 3 7 G
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| | Your corrective actions will be examined during a future inspectio Your cooperation with us is appreciate |
| INSPECTION SUMMARY Inspection on September 9-13,1985 (Inspection Report Nos. 50-317/85-22;
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| -30-318/85-20)
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| Areas Inspected: Announced inspection to review the licensee's' Unit 2 implementation of a program as required by 10 CFR 50.49 for establishing and maintaining the qualification of electric equipment within the scope of 10 CFR 50.49. The inspection included evaluations of the Unit 2
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| . implementation of equipment qualification (EQ) corrective action commitments ~
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| made as a result of deficiencies identified in the December. 16, 1982 Safety Evaluation Report (SER) and the October 13, 1982 Franklin Research Center (FRC) Technical Evaluation Report (TER). The inspection also included followup of Unit 1 findings identified during the October 15-19, 1984 EQ inspection. The inspection involved 245 inspector hours onsit Results: The inspection determined that the licensee has implemented a program for both Units 1 and 2 to meet the requirements of 10 CFR 50.49 and has taken corrective action on the findings of the previous Unit 1 EQ inspection, except for certain deficiencies listed below. No deficiencies were found in the licensee's implementation of corrective action commitments made as a result of SER/TER identified deficiencie .
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| | Sincerely, |
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| | Original signed BY t 1" |
| | James T U188 Stewart D. Ebneter, Director |
| | " Division of Reactor Safety cc w/ encl: |
| | M. Bowman, General Supervisor, chnical Services Engineering Thomas Magette, Administrator, Nuclear Evaluations Daniel Latham, Director, Security Services (Safeguards Only) |
| | Norman J. Bowmaker, Vice President, General Services (Safeguards Only) |
| | ! Public Document Room (PDR) |
| | local Public. Document Room (LPDR) |
| | Nuclear Safety Information Center (NSIC) |
| | NRC Resident Inspector State of Maryland (2) |
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| | l OFFICIAL RECORD COPY RL CC 86-22/20 - 0001. ; PDR ADOCK 05000317 G PDR |
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| | Baltimore Gas and Electric Company 2 bec w/ enc 1: |
| | Region I' Docket Room (with concurrences) |
| | Management Assistant, DRMA (w/o enc 1) |
| | DRP Section Chief M. McBride, RI, Pilgrim T. Kenny, SRI, Salem D. Jaf fe, . LPM, NRR Robert J. Bores,1DRSS |
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| . Potential Enforcement / Report item IInresolved Items Paragraph Number Qualification of Rockbestos 4.A.(9)(b) 50-317/85-22-02; Coaxial Cable 50-318/85-20-02 Qualification of ASCO Solenoid /85-22-07 Valve Model HCX8320A187 . Qualification of Hatfield Cable 4.E.(1) 50-317/85-22-10; 50-318/85-20-09 Failure to Comply with Implemented 4.B.(2) 50-317/85-22-03; Procedures 50-318/85-20-03 Failure to Establish Adequate 4.B.(6) 50-317/85-22-06; Maintenance Procedures for 50-318/85-20-06 Limitorque Motor Valve Operators Open Items: Adequacy of Manually Maintained 4.A.(5) 50-317/85-22-01; Equipment Maintenance Tracking 50-318/85-20-01;'
| | t-l DRSS:RICIC DR RI :RI Cheung/pj Anderson Du |
| System Depth, Scope, and Technical 4.B.(3) 50-317/85-22-04; Expertise of QA/QC Audits 50-318/85-20-04 Establishment of EQ Training 4.B.(4) 50-317/85-22-05; Program 50-318/85-20-05 Question Relative to How ASCO /85-22-08; Valve ISV3828 Was Installed in 50-318/85-20-07 Plant Without Being Qualified Dirty / Dusty Reliance Motors /85-22-09; 50-318/85-20-08 Revision to Qualification Files 4 E.(2) thru 50-317/85-22-11 4.E.(4) thru 13; 50-318/85-20-10 thru 12 Open Item From Previous Inspection: Inadequate Control and Storage of 4.A.(2) 50-317/84-27-02
| | .(bay /86 t9/f/86't&/] /86 0FFICIAL RECORD CG RL CC 86-22/20 - 0002. /09/86 |
| . Qualification Files
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| DETAILS PERSONS CONTACTED:
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| 1.1 Baltimore Gas and Electric Company (BG&E)
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| W. McCaughey, Engineer
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| *R. L. Wenderlich, Senior Engineer A. B. Anuje, Supervisor, Quality Assurance (QA)
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| *D. A. Ensor, Senior Auditor, QA B. S. Montgomery, Senior Engineer
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| * H. Cruse, Manager, Electric Engineering Department
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| * F. Ash, Supervising Engineer
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| * Marion, Senior Engineer
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| * G. Phifer, Jr. , QA Specialist R. B. Snyder, Supervisor, Electrical and Controls (ESC)
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| *K. Sabra, Principal Engineer
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| *R. Olson, Principal Engineer
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| *M. S. Eye, QA Auditor
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| *R. D. Branch, Engineer S. Parr, Engineering Technician J. G. Sites, Qualification Maintenance Program (QMP) Coordinator
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| *J. A. Tiernan, Manager, Nuclear Power
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| *M. Patterson, Senior Engineer J. M. Moreira, General Supervisor, ESC 1.2 BG&E Consultants R. Bell, Engineer, Bechtel Power Corporation, Gaithersburg, MD 1.3 Nuclear Regulatory Commission
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| *C Anderson, Chief, Plant Systems Section, RI
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| *G. Zech, Chief, Vendor Program Branch, I&E U. Potapovs. Chief Equipment Qualification Inspection Section, I&E D. Trimble, Resident Inspector, RI J. A. Schumacher, Peactor Engineer, RI
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| * Denotes those present at the exit interview on September 13, 1985
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| . PURPOSE:
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| The purpose of this inspection was to review the licensee's Unit 2 implementation of the requirements of 10_CFR 50.49 with regard to establishing qualification of electric equipment'within the scope of 10 CFR 50.49 and Unit 2 implementation of comitted corrective actions for SER/TER ~ identified deficiencies. Also included as a part of the inspection was a followup review of Unit 1 findings identified during the October 15-19, 1984 EQ inspectio . BACKGROUND:
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| On March 16, 1984 the NRC held a meeting with BG&E officials to discuss BG8E's proposed methods to resolve the EQ deficiencies identified in the December 16, 1982 SER and October 13, 1982'FRC TER. Discussions also included BG&E's general methodology for compliance with 10 CFR 50.49 and justification for continued operation (JCO) for those equipment items for which environmental qualification was not completed. The
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| . minutes of the meeting and proposed method'of resolution for each of the EQ deficiencies were documented in May 14 and July 9, 1984 submittals from the licensee. Additionally, BG&E submitted a request dated February 28, 1985 to extend the operation of Unit I to 1 approximately April 5,1985 and to extend the operation of Unit 2 to the fall 1985 refueling outage. JCOs for specific pieces of equipment for both units were submitted with the request. The TER and May 14,1984, July 9,1984, and February 28, 1985 submittals were reviewed by the inspection team rembers and were used to establish a ,
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| status baseline for the Unit 2 inspectio Additionally, inspection team members reviewed Inspection Report N /84-27 dated January 29, 1985 to establish what followup actions were required relative to the findings of the Unit 1 EQ inspection conducted October 15-19, 198 . FINDINGS:
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| ' Followup of October 15-19, 1984 Unit 1 F0 Inspection The NRC inspectors reviewed the licensee's corrective actions relative to the Unit 1 findings identified during the October 1984 EQ inspectio Since the licensee's EQ program for compliance with 10 CFR 50.49 co.ers both Calvert Cliffs Units 1 and 2, there wa some overlap of the followup activities for Unit 1 and the inspection activities for Ur it 2. Where this overlap existed, discussions in
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| the following paragraphs are applicable to the Unit i followup activities as well as to Unit 2 inspection activities and the licensee's overall E0 Progra (1)- (Closed) Qualification Files Not Auditable (50-317/84-?7-01)
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| The NRC inspectors reviewed 20 qualification files relative to followup of Unit 1 findings and 26 qualification files for Unit 2. While the inspectors found the files to be generally adequate and auditable, there were specific file
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| problems which are discussed later in this report-(see paragraph 4.E). The specific file problems were discussed with the licensee and the licensee agreed to take appropriate corrective action. In addition to the. specific problems, some-generic file problems were identified and are discussed in paragraph 4.B.(1). The inspectors determined that the licensee's EQ progran, as defined in Electrical Engineering Department Procedure No.18 (EEDP-18), " Equipment Qualification "
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| Revision 3, dated September 4,1985, implemented procedures which establish auditable qualification files. The files
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| .were found to include completed Qualification Summaries, Qualification Evaluation Worksheets (QEWs), Qualification Report Review Summary (QRRS) sheets, Qualification Maintenance Reouirement sheets and other documentation which supported qualification of specific equipment items. The files included references to test reports and other oualification related data which are maintained in central data files. The qualification files reviewed, except for specific cases discussed in paragraph 4.E., documented licersee evaluations and analysis performed relative to specified performance requirements and qualified life. The files documented the licensee's determinations as to whether equipment is qualified and to what environmental parameters it is qualifie (2) (0 pen) Inadequate Control and Storage of Files in Accordance with N45.2.9-1974 (50-317/84-27-02)
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| During the October 1984 inspection, the NRC inspectors determined that the licensee's electric equipment qualification files and records were not controlled and stored as described in ANSI N45.2.9-1974, entitled " Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants."
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| A licensee internal audit conducted from September 12-October 9, 1984, had identified similar findings in this area, audit finding
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| '84-24-0 During this inspection, the NRC inspectors determined that the equipment files are centrally located and kept locked during non-working hour However, discussions with the licensee disclosed that the audit finding is still open pending file microfilming and hard copies being sent to plant history. The licensee further stated that the audit finding would not be closed until November 30, 198 This item remains open pending NRC review of the duplicate filing system and verification that filing cabinets have the required fire rating to house permanent plant record (3) (Closed) Inadeouate Implementation of Requirements and/or Procedures for Compliance to 10 CFR 50.49 (50-317/84-27-03)
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| The NRC inspectors reviewed EEDP-18; EEDP-20, " Control of Calvert Cliffs Equipment Data Bases," dated July 30, 1985; and Calvert Cliffs Instruction 208 (CCI-208), " Qualification Maintenance Program," dated September 9,1985, to determine that BG&E has implemented procedures to control their
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| qualification program in accordance with 10 CFR 50.49. Since the major area of concern during the October 1984 inspection related to maintenance procedures, further discussion of procedure implementation is addressed in paragraph 4. A.(S) on maintenanc (4) (Closed) Inherent Characteristics in the Facility Change Request (FCR) System which Delay Verification of "As-built" Installations of Qualified 10 CFR 50.49 Equipment (50-317/84-27-04)
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| During the October 1984 inspection, the NRC inspectors determined that Electrical Engineering Department (EED) verification of
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| "as-built" conditions of qualified 10 CFR 50.49' equipment had a built-in-delay of a minimum of five months that could extend to over a year. The inspectors found this delay to be of concern, since a modified or new piece of equipment could be utilized in a safety-related application for a significant period of time during which its qualification would not have been established nor would it have been included on the 10 CFR 50.49 list. During this inspection, the NRC inspectors determined, through review of qualification files and discussions with BG&E personnel, that the EED was receiving notification of
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| "as-built" conditions for new and modified equipment by documented input from plant site personnel. This documented input is received by EED within a week of equipment installation or modification completion and EED then completes documentation to establish equipment qualification and adds the equipment to the 10 CFR 50.49 list if require Additionally the inspectors learned that the licensee is planning a' company reorganization (about January 1,1986) that will involve moving nuclear engineering personnel from corporate offices in Baltimore to the plant site in Lusby. This move of engineering
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| * personnel to the plant site is considered an additional step toward further improvement in the "as-built" time delay problems of the FCR syste (5) (Closed) No Maintenance Program which Includes Activities Necessary to Maintain the Qualified Status of Qualified Equipment (50-317/84-27-05)
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| The NRC inspectors reviewed EEDP-18 and determined that section requires EQ related maintenance to be included as part of'the licensee's EQ progran. It requires EQ files to contain the applicable Qualification Maintenance Requirement sheets (QMRS).
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| The QMRSs identify equipment tag numbers, manufacturer's name and model number, required EQ maintenance actions, replacement parts, and the required implementation dates. Additionally, the licensee has developed CCI-208 to implement qualification maintenance requirements. The inspectors reviewed CCI-208 ar.d determined that it addresses procedures for implementing qualification maintenance requirement .
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| The licensee has identified 658 items of equipment which require EQ related maintenance. As part of its qualification maintenance program (QMP), the licensee has a OMP coordinator at the plant site and has developed a "QMP Equipment List and Status ,
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| Tracking Chart" to track required EQ maintenance, equipment maintenance status, and the dates required maintenance activities are complete for each of the 658 items. The OMP coordinator manually maintains these EQ status tracking charts which are contained in eight notebook volumes to cover the 658 item The inspectors reviewed the status tracking charts for four items of equipment (2-SV-618,-628,-638, and -648) and determined that the individual charts contained sufficient detail to define maintenance requirements and keep track of item maintenance status. However, the inspectors did identify a concern relative to overdue maintenance activities. The inspectors determined that due to the volume of items, the manual tracking system, and that there was no simple method (charts, tables, and/or computer printouts) to identify overdue maintenance, tne licensee could have difficulty identifying overdue maintenance activities if they existed. The licensee did state that they were planning to computerize the tracking system in the future. While the inspectors did not identify any examples of overdue maintenance activities, this concern is identified as a new open item which will be reviewed during a future NRC inspection (50-317/85-22-01; 50-318/85-20-01.)
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| (6) (Closed) Overall Compliance to 10 CFR 50.49 (50-317/84-27-06)
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| The NRC inspectors' review and evaluation of 20 qualification files for Unit 1, 26 qualification files for Unit 2, the licensee's control and storage methods for E0 records and qualification files, the licensee's FCR system, and the licansee's QMP determined that the licensee has implemented an E0 program in compliance with 10 CFR 50.49, except for certain deficiencies discussed in this repor The specific findings described in this report are considered to be isolated instances of noncompliance with the rule and Appendix B to 10 CFR 50 and do not indicate an overall inadequacy'in the licensee's program; therefore, this item is considered close (7) (Closed) Resolution of TER/SER Deficiencies (50-317/84-27-07)
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| The NPC inspectors reviewed 20 qualification files related to Unit 1 and determined that the licensee had adequately resolved the concerns identified in the TER/SER; therefore, there are no outstanding issues remaining relative to the TER/SER (see discussion in paragraph 4.C. relative to Unit 2).
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| (8) (Closed) Establishment of the Qualified Life of 10 CFR 50.49 Equipment Located in the Main Steam Piping Penetration Room (50-317/84-27-08) | | * |
| The NRC's concern with this item pertained to the high temperatures observed in the main steam piping penetration room during the plant walkdown of the October 1984 inspection. The inspectors were concerned as to whether the temperatures (reported to be 140 degrees F) were adequately considered in thermal aging calculations to determine qualified lif During this inspection, the inspectors reviewed the qualification files for the equipment located in the piping penetration room and deter-mined that the high ambient temperatures had been adequately addressed when the qualified life of the equipment was establishe (9) Specific File Deficiencies Identified In Report for October 1984 Inspection While the report for the October 1984 inspection did not identify specific qualification file findings as open items during this inspection, the NRC inspectors reviewed 20 Unit 1 qualification
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| files to determine if adequate corrective actions had been taken regarding the identified findings. The inspectors determined that actions taken by the licensee were adeouate except for the items discussed L. low: While the inspectors' review of Limitoroue motor operated valve (MOV) qualification packages, TER items 19 and 27 (M0V001 and 002), determined that adequate corrective actions had been taken regarding the identified deficiencies, an additional concern was identified relative to MOV maintenance requirements. This concern is discussed in paragraph 4.B.(6). The inspectors reviewed the qualification package for CBLO31 for Pockbestos RSS-6-104 coaxial cable which is used in the General Atomics high-rarge radiation monitoring system (HRRMS) and determined that the licensee had not taken adequate corrective action to establish-qualificatien of the cable. During the previous EQ inspection, the licensee was informed that, based on IE Information Notice (IN) 84-44, their file did not support qualification. However the only addition 11 information in the file during this inspection stated that IN 84-44 "is still under review for final resolution. Presently Rockbestos is retesting to satisfy NRC concerns en qualification data /
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| metnod The expected completion of testing for this cable configuration is December 198 Presently BG&E is attempting to obtain outside test reports providing qualification data, while monitoring the Rockbestos progress." Since these statements did not provide additional information to demonstrate cualification, the licensee was asked to provide
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| any other information it might have to support qualificatio No additional information was provided to the inspectors; therefore, the qualification of this cable is considered not established for the licensee's application as of the time of the inspection. This deficiency is identified as a Potential Enforcement / Unresolved Item (50-317/85-22-02; 50-318/85-20-02).
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| (10) Information Notice Recomendation The NRC inspectors reviewed Calvert Cliffs Instruction (CCil #139,
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| " Organization and Operation of the Plant Operating Experience Assessment Committee (POEAC)," dated February 4, 1985, and the minutes of POEAC Meetings 85-12, 85-14, and 85-17 to evaluate the licensee's actions relative to the NRC recommendation during the October 1984 inspection that a closed-loop system be considered for action items assigned by the POEAC. Based on discussions with the POEAC secretary and review of the POEAC outstanding item lists for the above meetings, the inspectors determined that the licensee was assuring that assigned POEAC action items were being tracked and the POEAC was assuring adequate completion of assigned action item B. EQ Program Compliance with 10 CFR 50.49 The NRC inspectors examined the licensee's EQ Program for establishing the qualification of electric equipment within the scope of 10 CFR 50.4 The licensee's program covers the qualification of all 10 CFR 50.49 equipment for both Units 1 and 2. The program was evaluated by review of the licensee's corrective actions for findings identified during the Unit 1 October 1984 EQ inspection, examination of the licensee's qualification documentation files, examination of procedures which control the licensee's EQ efforts, and examination of the licensee's program for maintaining the qualified status of covered electric equipmen Based on the inspection findings on the followup of the licensee's Unit I corrective actions (discussed in paragraph 4.A.) and the l Unit 2 inspection findings of this inspection the inspection team determined that the licensee has implemented a prcgram to meet the
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| requirements of 10 CFR 50.49, although five Potential Enforcement /
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| Unresolved Items and eight Open Items were identifie (1) Qualification Files, General The NRC inspectors determined that BG&E's implemented program
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| provides for the preparation of qualification documentation files for eouipment within the scope of 10 CFR 50.49. The licensee's program which is described in EEDP-18 requires the establishment of qualification files by the EED. These files are the documents which establish qualification for all items of equipment at Calvert Cliffs Units 1 and 2 within the scope of 10 CFR 50.4 _ -
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| | | ABALTIMORE GAS AND |
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| | . ELECTRIC CHARLES CENTER P. O. BOX 1475 * BALTIMORE MARYLAND 21203 JostPN A.TsERNAN vict Patssotat uvema cataav July 28,1986 Docket No U. S. Nuclear Regulatory Commission 50-318 Region I DPR-53 License No Park Avenue DPR-69 King of Prussia, PA 19406 t |
| Each qualification file includes the following:
| | ATTENTION: Mr. Stewart D. Ebneter, Director Division of Reactor Safety REFERENCES: (a) Letter from Mr. G. G. Zech, to Mr. A. E. Lundvall, Jr., dated March 4,1986, Inspection Report 50-317/85-22; 50-318/85-20 (b) Letter from Mr. J. A. Tiernan, to Mr. B. K. Grimes, dated June 30,1986 (c) Letter from Mr. S. D. Ebneter, to Mr. A. E. Lundvall, Jr., dated l |
| Qualification Sumary
| | June 25,1986, Notice of Violation l - |
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| * Qualification Report Review Qualification Evaluation Summary (QEW)
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| Worksheet
| | ! This refers to inspection Report 50-317/85-22;50-318/85-20, and Reference (c) which l |
| * Qualification Maintenance Requirement Sheet
| | identified four items of apparent noncompliance with NRC requirements. Although it was not required, we responded to Reference (a) with Reference (b). Reference (a) |
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| QMRS Master Log The NRC inspectors' review and evaluation of 20 qualification files for Unit 1 and 26 qualification files for Unit 2 determined that the files did establish qualification of 10 CFR 50.49 equipment items except for specific cases identified in this repor During the review of the files, the inspectors identified many instances where changes were made to the files by crossouts,
| | originally identified the four apparent violations as Potential Enforcement item We have reviewed our previous response to these items and we find our submittal to still be acceptabl Therefore, we refer you to Reference (b) as our response to L |
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| | i Reference (c). |
| whitenut, and/or other means without any indication as to who made the changes and/or when the changes were mad Qualification files where the above was specifically noted were PT0006, M0V011, M0V001, SEALO3, SEALOS, SV0026, and ZS002 Since these files are covered by the requirements of paragraph 4.4 of QAP 7, " Records Management," dated July 3, 1985, which requires changes to records identify who makes or approves
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| the change, when the correction was made, and to leave the original information legible, this finding is an example of the licensee's failure to follow procedures as discussed in paragraph j 4.B.(2).
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| (2) EQ Program Procedures As previously' discussed in paragraphs 4(A)(3) and (5), the NRC inspectors determined that the procedure concerns identified i
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| during the October 1984 EQ inspection had been addressed and i
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| the licensee was implementing procedures to control his EQ activities. Procedure EEDP-18 provides guidelines for the uniform assessment, evaluation, review, and implementation of activities associated with environmental and seismic qualification of 10 CFR 50.49 equipment at Calvert Cliffs. Procedure EEDP-20 is used to control new inputs and changes to the computerized
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| Calvert Cliffs equipment data bases for all electric /instrumen-tation devices at the Calvert Cliffs plan Procedure CCI-208
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| implements requirements for maintaining the cualified status of 10 CFR 50.49 equipment. In addition to reviewing the above EQ program procedures, other licensee procedures were reviewed as they were applicable to the EQ program. These procedures included:
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| QAP-7 Records Management QAP-14 Plant Maintenance QAP-15 Changes, Tests and Experiments 3 QAP-20 Training
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| , QAP-28 Control of Items Covered by the Quality Assurance
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| EEDP-2 Control of Changes, Tests and Experiments
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| EEDP-8 Nuclear Related Indoctrination Training and Qualification EEDP-16 Records Retention During the inspection activities, the NRC inspectors identified two instances where the licensee did not comply with its implemented procedures. The instances of not complying with procedures are as follows:
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| The licensee made changes to documentation ,in its qualification files without complying with the requirements of paragraph 4.4 of QAP-7 (see discussion in paragraph 4.8.(1)).
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| The licensee's responsible engineer failed to review an FCR for the replacement of a flow control valve as required by paragraph 7.8 of 0AP-15 (see discussion in paragraph 4.0.).
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| The above instances of not complying with implemented procedures is identified as a Potential Enforcement / Unresolved Item (50-317/
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| 85-22-03; 50-318/85-20-03). | |
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| (3) Quality Assurance / Quality Control The NRC inspectors' review determined that the quality assurance (QA) organization for BG&E is comprised of a corporate QA organization and a site QA organization. The corporate organization consists of a QA manager who directs the Internal Audits and Programs Unit. This unit is comprised of lead auditors and auditors certified to ANSI N45.2.23 who conduct mostly corporate audit At Calvert Cliffs there is an Operation QA General Supervisor who directs the Senior QA Auditor 0A Specialists, Senior Quality Control (QC) Inspectors and QC Inspectors. These personnel perform EQ receipt inspections, maintenance inspections, and at tines assist the corporate QA organization in joint audit The inspectors reviewed three audits performed by both corporate and site QA organizations in the EQ area. The first audit reviewed was QAG 61-85-05 conducted by the Internal Audits and Program Unit during March-April 1985. This audit was a direct follow-up to the October 1984 NRC inspectinn. The other two audits OAG 61-85-20 and EQ-26-85 were conducted simultaneously from August 20-29, 1985. The corporate audit consisted of a '
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| review of qualification files, status of FCRs and implementation of CCI-208. The site audit consisted primarily of assuring site implementation of CCI-208.
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| ~The inspectors determined from the review of the audit check--
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| lists and discussions with the licensee, that the corporate ,
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| audit (QAG 61-85-20) should have included additional personnel- i who had expertise in the environmental qualification area, i.e.,
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| the inspectors' discussions with the licensee's auditors indicated the following: EQ files were reviewed for procedural compliance onl The auditors did not verify that correct parameters such as operating time, temperature, pressure, humidity, and radiation were in accordance with qualification test reports and plant specific design bases accident parameter Based on the NRC inspectors' review and evaluation of the three audits and discussion with the licensee, the inspectors were concerned with the depth and scope of the audits as well as the lack of adequate technical assistance during the audi This item is identified as an open item which will be reviewed during a future NRC inspection (50-317/85-22-04; 50-318/
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| 85-20-04).
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| (4) EQ Training The NRC intpectors reviewed training requirements for personnel working with EQ equipmen The inspectors determined that an EQ training program had not been established. Although most all
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| technicians and maintenance personnel have attended a lecture given by EQ personnel af ter program implementation, personnel have received most of their training by on-the-job training (0JT). To date, the licensee has documented the completion of only a one hour lecture on May 6,1985 in the EQ area relative to the implementation of CCI-208. The establishment of an EQ training program and the completion of training for personnel working in the EQ area is identified as an open item which will be reviewed during a future NRC inspection (50-317/85-22-05; 50-318/85-20-05).
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| (5) 10 CFR 50.49 List (EQ Master List)
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| The NRC inspectors did not review the licensee's 10 CFR 50.49 list as a separate aspect of this inspection since the licensee's list covers both Calvert Cliffs Units 1 and 2 and the Unit i list was reviewed during the October 1984 inspection with no major findings. The inspectors concluded from their various inspection activities that the licensee's EQ list was comprehensiv The inspectors observed no changes to the list during the inspection as was seen during the previous inspectio f
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| (6) E0 Maintenance Program Since the licensee's maintenance program encompasses Calvert Cliffs Units 1 and 2, the discussion in paragraph 4.A.(5) concern-ing maintenance followup of the October 1984 inspection is applicable to Unit 2 maintenance activities. The NRC inspectors'
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| review of qualification files MOV-001, MOV-002, avi MOV-011 for Limitorque motor valve operators identified one concern relative to periodic operator cycling. The abstract of Wyle Qualification Report 17467 states in part " Continued qualified operation is maintained with the following provisions:.... A periodic. cycling of the valve actuator must be performed at least twice each year to lubricate the operating parts." This maintenan.ce requirement was not addressed in the qualification file, nor were any engineering evaluations performed to determine if this requirement needed to be implemented. The inspectors determined from discussions with the licensee's engineering personnel that most of the qualified Limitorque operators were only operated once per refueling cycle (typically 18 months). Subsequently, the licensee presented the inspectors with a telephone conversation record dated September 13, 1985, concerning a conversation between the licensee and Limitorqu The record stated that "to cycle the Limitorque valve actuators at least twice a year was a recommendation for actuators in long term storage, and was not required for actuators in service." Since this data is in conflict with the Wyle report, the above conflict is identified as a Potential Enforcement /
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| Unresolved item (50-317/85-22-06; 50-318/85-20-06).
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| C. SER/TER Commitments The NRC inspectors evaluated the implementation of Unit 2 EQ corrective action comitments made as a result of SER/TER identified deficiencies. The evaluation was based on the premise that all corrective action comitments had been completed, except for the equipment items for which JCOs were submitted in a February 28, 1985 letter to the NRC. These JCOs were submitted to allow continued operation of Unit 2 until the fall 1985 outag Based on the sample review of the qualification files for which there were no outstanding JCOs and the plant physical inspection, the NRC inspectors identified no deficiencies in the Unit 2 implementation of SER/TER commitment D. PLANT PHYSICAL INSPECTION The plant physical inspection consisted of the examination of six types of safety-related equipment located outside containment on either and/or both Units 1 or 2. The inspectors examined charac-ter':+1cs such as mounting configuration, orientation, interfaces, model number, environment, and physical conditio . -
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| The NRC inspectors identified several concerns during the physical inspection. One concern was that Unit 1 ASCO solenoid valve ISV3828 had a different model number than the other inspected valves, which were qualified by qualification file SV001 The installed valve, located in the component cooling outlet shutdown heat exchanger system, had a model number of HCX8320A187. The other valves inspected had model numbers HPX8320A26. After the physical inspection, the inspectors determined that qualification file SV0011 did not establish qualification of the model HCX8320A187 valve; nor, did the licensee have any other file to establish the qualification of the HCX8320A187 valve. This failure to establish j qualification of a valve located in a harsh environment and a safety-related system is identified as a Potential Enforcement / Unresolved i Item (50-317/85-22-07).
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| Additional NRC discusr. ions with the licensec concerning the above
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| : determined that the model HCX8320A187 valve was probably installed in April 1985 when the control valve (ICV 3828) on which it was mounted was installed as a replacement for another valve. The inspectors further determined that the licensee had failed to follow paragraph 7.8 of QAP 15 which requires that FCRs for !
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| "SR-QUAL (environmentally qualified) items" be reviewed by the l
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| engineer who has been assigned responsibility for EQ by the
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| manager of EE No documented evidence of the review was identified by the inspectors and the responsible engineer admitted to the inspectors that he had not reviewed the FC i This is an example of the licensee failure to follow procedures as discussed in paragraph 4.B.(2).
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| Additionally the inspectors had questions regarding the HCX8320A187 valve and why the valve was not on the qualification maintenance requirement sheets of CCI-208 and what role QA/QC should have had i to prevent the installation of unqualified equipment. Resolution of these questions is identified as an open item (50-317/85-22-08;
| | Should you have any further questions regarding this reply, we will be pleased to discuss them with yo Very truly yours, f |
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| 50-318/85-20-07) which will be reviewed during a future NRC inspectio Another concern identified by the inspectors was that the Reliance
| | l JAT/SRC/ dim l cc: D. A. Brune, Esquire |
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| ; motors, model P14G408NFV (qualification file MTR024) located in
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| ; emergency core cooling system (ECCS) pump rooms 21 ECCS and 22
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| ; ECCS were observed to be dusty / dirty. The inspectors were concerned that the accumulation of dust / dirt could eventually be severe enough to cause motor winding failure. The inspectors reconnended to the licensee that the motors be cleaned. This item is identified as an open item which will be reviewed during a future NRC inspection 50-317/85-22-09; 50-318/85-20-0 DETAILED REVIEW 0F QUALIFICATION FILES The NRC inspectors examined in depth 26 qualification files for selected Unit 2 equipment types and one new file for Unit 1 equipment '
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| to verify the qualified status of equipment within the scope of 10 CFR 50.49. In addition to comparing plant service conditions I with qualification test conditions and verifying the bases for these conditions, the inspectors reviewed areas such as required
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| | | ' J. E. Silbergd,Eskuire S.A.McNe Ni C T. Foley, NRC |
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| post-accident operating time compared to the duration of time the equipment has been demonstrated to be qualified, similarity of tested equipment to that installed in the plant (e.g., insulation class, materials of components of the equipment, test configuration compared to installed configuration, and documentation of both),
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| evaluation of adequacy of test conditions, aging calculations for qualified life, and replacement interval determination, effects of decreases in insulation re'sistance on equipment performance, adequacy of demonstrated accuracy, evaluation of test anamolies, and applicability of EQ problems reported in IE ins / Bulletins and their resolutio (1) The NRC inspectors' review of file CBLO11 for a 14AWG, Hatfield 3 conductor cable determined that while the licensee was able tn resolve (after much discussion) all the inspectors' concerns regarding the file and support cable qualification, the file itself was deficient in some areas. Examples where the file was deficient are: The QEW in the fil. indicated the cat'ie was qualified for submergence aw lications, however, the file did not support qualification for submergence. The licensee was able to demonstrate, to the inspectors' satisfaction, that the cable was not used in a submerged application; therefore, the cable was qualified for its plant application.
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| < The file did not document proof of similarity between the installed and the tested cables. The licensee was able to l demonstrate similarity with documentation not referenced I in the fil A reference contained in the file stated that the Hatfield cable was cualified for 40 years at 111.9'C; however, no data, calculations, or specific references were found in the file to support this qualified lif The licensee eventually was able to justify the above qualified life by recalculating thermal aging using material properties given in qualification file CBLO1 The licensee stated that it would revise this qualification file to resolve all the questions identified by the
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| inspectors; however, this lack of documentation in the file is identified as a Potential Enforcement / Unresolved l
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| Item (50-317/85-22-10; 50-318/85-20-09). The NRC inspectors review of file CBLO29 for Brand-Rex coaxial cable identified three areas that were not addressed adequately in the file. These areas were as follows:
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| (a) Data and/or specific references were not identified in the file to provide a comparison between qualifi-cation test parameters and actual plant requirement This item was resolved by additional licensee data provided the inspectors during the inspectia (b) The file did not address plant performance requirements of the cable. The licensee resolved this item by referencing qualification file VT0001 for the acoustical monitoring system. File VT0001 documented that the cable was part of the system tested during the acoustical monitoring system qualification tests; therefore, demonstrating adequate performance of the cable in its only safety-related application at Calvert Cliff (c) The file did not adequately address margins; however, the licensee resolved this issue by data in the VT000 The licensee agreed to revise file CBLO29 to resolve the above identified file inadequacies. The revision of this file is identified as an open item (50-317/85-22-11; 50-318/85-20-10)
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| which will be reviewed during a future NRC inspectio . The NRC inspectors review of file HRRMS1 for the General Atomic high range radiation detector (model RD-231 determined that the file did not adequately address performance require-ments and margins as in file CBLO29. The licensee was able to resolve the NRC concerns in these areas and agreed to revise the file to reflect resolution of these concern The revision to this file is identified as an open item (50-317/85-22-12; 50-318/85-20-11) which will he reviewed during a future NRC inspectio The NRC inspectors' review of files SEAL 01 for Paychem heat shrink tubing and SEALO3 for Raychem NE!S conduit sealing kits determined that data in the file supported oualification of the equipment items; however, the files were not finalized pending notification of completion of field work under FCRs 84-1075 and 84-134 Finalization of these qualification files by the licensee is identified as an open item (50-317/
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| 85-22-13; 50-318/85-20-12) which will be reviewed during a future NRC inspectio .F. IE informatinn Notices and Bulletins The NRC inspectors did not review the licensee's system for the review of ins / Bulletins as a separate aspect of this inspection since the licensee's system covers both Calvert Cliffs Ifnits 1 and 2 and this system was reviewed during the October 1984 inspectio Paragraph 4.A.(10) of this report discusses NPC findings relative to one NRC l
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| recommendation provided the licensee during the previous E0 inspection.
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| this inspection i
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| The NRC one identified inspectors' review finding (see of qualification discussion files during(9)(b)
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| in paragraph on Rockbestos cable) relative to inadequate licensee action on one information notice.
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M9991999-10-22022 October 1999 Forwards Response to NRC 990930 RAI Re Void Swelling Degradation Mechanism,Per License Renewal Application for Ccnpp,Units 1 & 2 ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20216J8671999-10-0101 October 1999 Forwards Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant. Rev Accurately Presents Changes Made Since Previous Submittal,Necessary to Reflect Info & Analyses Submitted to NRC or Prepared,Per to NRC Requirements ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20216H7831999-09-28028 September 1999 Forwards Addl Info Re NRC SER for Ccnpp,Units 1 & 2,per License Renewal Application ML20212D5361999-09-20020 September 1999 Forwards Rev 1 to Calculation CA04048, Fuel Handling Accident During Reconstitution, as Agreed During 990909 Telcon ML20212C1861999-09-15015 September 1999 Requests That NRC Complete Review of TR CED-387-P,Rev 00-P, Abb Critical Heat Flux Correlations for PWR Fuel, by 000201.Util Expects to Use ABB-NV Correlation for Current non-mixing Vane Fuel in Reload Analyses in 2000 for Ccnpp ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211H9841999-08-31031 August 1999 Provides Comments Re Data Entered in Rvid for Ccnpp,Units 1 2,per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20211J1611999-08-17017 August 1999 Documents Bg&E Consultations with MD Dept of Natural Resources Re Potential Impacts to Chesapeake Bay Critical Area & Forest Interior Dwelling Bird Habitat,Per Ccnpp License Renewal.Telcons Ref Satisfy Consulting Requirement ML20210V1181999-08-17017 August 1999 Forwards Toxic Gases Calculations for Control Room Habitability,As Discussed During 990713 Telcon.Util Will Make Final Submittal for Toxic Gases After NRC Has Completed Review of ARCON96 ML20210T5061999-08-16016 August 1999 Forwards Rev 0 to Ccnpp COLR for Unit 2,Cycle 13, Per Plant TS 5.6.5 ML20210U2761999-08-13013 August 1999 Forwards Listed Info Re Guarantee of Payment of Deferred Premiums for Ccnpp,Units 1 & 2,IAW 10CFR140.21 Requirements ML20210S8131999-08-12012 August 1999 Forwards Summary of Various Open Licensing Actions for Bg&E That Were Completed During Unit 2 Refueling Outage Ending 990506 ML20210S8101999-08-12012 August 1999 Forwards Application Requesting Renewal of License for Mv Seckens,License SOP-10369-2.Without Encl ML20210S7901999-08-12012 August 1999 Forwards semi-annual Fitness for Duty Program Performance Data for Period of 990101-990630,IAW 10CFR36.71(d) ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N5881999-08-0606 August 1999 Forwards ISI Rept for Ccnpp,Unit 2,fulfilling Intentions & Requirements Stated in Program Plan & Commitment to Comply with ASME Code Section XI ISI Requirements ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20210N5491999-08-0505 August 1999 Requests That License SOP-10371-2,for RW Scott,Be Renewed IAW 10CFR55.57.Individual Has Satisfactorily Discharged License Responsibilities Competently & Safely.Without Application ML20210N5471999-08-0505 August 1999 Requests That License SOP-10031-3,for DF Theders,Be Removed from Active Files for Ccnpp,Due to Individual Being Reassigned to Position No Longer Requiring License ML20210N9291999-08-0404 August 1999 Forwards Clarification to Initial Response to Biennial Rept on Status of Decommissioning Funding,As Required by 10CFR50.75(f)(1) ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210E4941999-07-23023 July 1999 Informs That 1999 Emergency Response Plan Exercise Objectives Is Scheduled for Wk of 991025.Exercise Scenario Will Test Integrated Capability & Major Portion of Elements Existing within Emergency Response Plan ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210C5011999-07-21021 July 1999 Informs That SL Walters,License OP-10096-3 & CC Zapp,License Number SOP-2188-9,have Been Reassigned within Organization & No Longer Require NRC License,Per 10CFR50.74(a).Removal of Subject Licenses from Active Files for Ccnpp,Requested ML20210C2681999-07-20020 July 1999 Forwards Certified Copy of Listed Nuclear Liability Policy Endorsement,Per 10CFR140.15(e) ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20211N9101999-07-20020 July 1999 Forwards Correspondence Author Received from New 7th Democratic Club Civic,Inc Raising Some Serious Concerns About Renewal of Nuclear Reactor Licenses for Calvert Cliffs Power Plant ML20210C8461999-07-19019 July 1999 Informs That CF Farrow,License OP-10648-1,will No Longer Be Employed with Bg&E,As of 990709,per 10CFR50.74(a).Removal of Subject License from Active Files for Ccnpp,Requested ML20209J5171999-07-16016 July 1999 Forwards Comments from Accuracy Review of License Renewal Application SER ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20209C1391999-07-0202 July 1999 Forwards Responses to Open & Confirmatory Items Based on Review of SER for Bg&E Application for Renewal of Operating Licenses for Calvert Cliffs.Bg&E Intends to Forward Comments Based on Accuracy Verification in Near Future ML20210D1531999-06-30030 June 1999 Informs of Receipt of from New 7th Democratic Civic Club,Inc Expressing Support for License Renewal. Requests Consideration in Addressing Concerns & Recommendations ML20209B5781999-06-29029 June 1999 Submits Response to GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20210D1741999-06-24024 June 1999 Expresses Opinions on Renewal of Nuclear Reactor Licenses Re Plant & Support Renewal Application of Bg&E.Requests That NRC Revise Procedures to Allow Sufficient Time for Public to Review,Evaluate & Respond to Info ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196C4291999-06-21021 June 1999 Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes ML20195J8271999-06-16016 June 1999 Ack Receipt of to Jackson,Chairman of NRC Re Environ Impacts of Increased Patuxtent River Complex Flight Operations on Ccnpp.Clarification & Correction of Listed Statement Found on Page Two,Provided 1999-09-08
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062G6791990-11-21021 November 1990 Forwards SE Determining That Load Profile Used During Surveillance Test Procedures Meets Requirement of Tech Spec 4.8.2.3.2.e,per Unresolved Item Noted in Insp Repts 50-317/90-80 & 50-318/90-80 IR 05000317/19900281990-11-14014 November 1990 Discusses 901102 Enforcement Conference Re Insp Repts 50-317/90-28 & 50-318/90-28 Covering Security Event ML20216K1541990-11-13013 November 1990 Forwards Safety Insp Repts 50-317/90-31 & 50-318/90-31 on 901029-1102.No Violations Noted ML20217A0131990-11-0909 November 1990 Forwards Insp Repts 50-317/90-25 & 50-318/90-25 on 900916-1020.One Noncited Violation Noted ML20058E9821990-11-0101 November 1990 Forwards List of Unimplemented Generic Safety Issues at Plant,Per Util 900627 Response to Generic Ltr 90-04 ML20058A7001990-10-19019 October 1990 Forwards Safeguards Insp Repts 50-317/90-28 & 50-318/90-28 on 901010 & 11.Violation Noted ML20058A6841990-10-17017 October 1990 Forwards Insp Repts 50-317/90-23 & 50-318/90-23 on 900812- 0915.No Violations Noted ML20059N9421990-10-12012 October 1990 Advises of Resolution of Auxiliary Feedwater Issue,Per .Issue Concerns Ability of AFW Sys to Provide Flow to Steam Generators Following Pipe Break ML20062B2041990-10-12012 October 1990 Advises of Acceptance of 900924 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28, Item 2.2,Part 2 Vendor Interface for Safety-Related Components IR 05000317/19900081990-10-11011 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-08 & 50-318/90-08 ML20059N5781990-10-0909 October 1990 Advises That Util 900510 Submittal of Revised Section of Inservice Insp Program Plan Addressed Provisions of Safety Evaluation ML20062B8361990-10-0909 October 1990 Forwards Special Team Insp Rept 50-317/90-24 on 900904-07 Re 900830 Reactor Vessel Water Level Anomaly ML20059N2231990-10-0101 October 1990 Forwards Safety Evaluation Accepting Proposed Actions Re Potential Design Deficiency,Per LER 89-023 ML20059N1181990-09-28028 September 1990 Forwards Safety Insp Repts 50-317/90-22 & 50-318/90-21 on 900827-31.No Violations Noted.Post Maint Testing Program Assessed to Be Comprehensive,Well Implemented & Met Objectives of Performance Improvement Program ML20059M7751990-09-27027 September 1990 Advises That NRC Approved Request for Relief from ASME Code Section XI Re Reactor Coolant Charging Pumps in ML20059K7041990-09-0707 September 1990 Ack Receipt of Util 900515 Response to Violations Noted in Insp Repts 50-317/90-01 & 50-318/90-01.Agrees That Thrust of Notice of Violation Not Accurate But That Actual Violation Was Failure to Comply w/10CFR50,App B,Criterion Xvi ML20059E3371990-08-27027 August 1990 Forwards Insp Repts 50-317/90-17 & 50-318/90-15 on 900710-13.No Violations Noted.Util Requested to Provide Complete Corrective Actions Being Considered to Prevent Recurrence of Welding Deficiencies within 30 Days ML20059E1921990-08-24024 August 1990 Forwards Insp Repts 50-317/90-18 & 50-318/90-17 on 900716-20.No Violations Noted ML20059E2981990-08-23023 August 1990 Advises That 890313,1103 & 900228 Revs 9,10 & 11 to Plant Contingency Plan,Consistent w/10CFR50.54 & Acceptable.Revs Withheld (Ref 10CFR73.21) ML20058N3641990-08-0909 August 1990 Forwards Notice of Withdrawal of 900801 Applications for Amend to License DPR-69 Re Shift of Min Pressurization Temp Between 530 & 20 Psia on Heatup & Cooldown Curves ML20058P1331990-08-0808 August 1990 Forwards Radiation Safety Insp Repts 50-317/90-14 & 50-318/90-12 on 900625-29.No Violations Noted ML20058N0481990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Other Power Reactor Licenses in Region 1 Should Provide for Sharing of Info & Experiences Involving Engineering Initiatives & Solutions of Problems Common to All ML20056A4081990-07-24024 July 1990 Forwards Insp Repts 50-317/90-12 & 50-318/90-11 on 900604-08.No Violations Noted ML20055G5931990-07-18018 July 1990 Forwards Corrected Cover Ltr for Insp Repts 50-317/90-10 & 50-318/90-10,revising Insp Rept Numbers ML20055H1211990-07-18018 July 1990 Advises That Encl Review of Cen 387-P, C-E Owners Group Pressurizer Surge Line Flow Stratification Evaluation, Inadequate.Insufficient Bases Provided to Conclude That Power Surge Line Meets Code Limits for 40-yr Plant Life ML20055G5951990-07-18018 July 1990 Corrected Cover Ltr Forwarding Insp Repts 50-317/90-10 & 50-318/90-10 ML20055F9241990-07-17017 July 1990 Informs That All Activities Re Reactor Vessel Level Monitoring Sys & Core Exit Thermocouples Completed Except for Tech Specs Based on Review of 870501 & 880427 Submittals ML20055F9561990-07-17017 July 1990 Advises That Actions Re NRC Bulletin 87-002, Fastener Testing to Determine Conformance W/Applicable Matl Specs, Adequate,Per Insp Repts 50-317/90-08 & 50-318/90-08 ML20055G1331990-07-12012 July 1990 Forwards Insp Repts 50-317/90-13 & 50-318/90-13 on 900603-30.No Violations Observed ML20055F5421990-07-10010 July 1990 Advises That Requalification Program Evaluation Scheduled for Wk of 901022.Facility Requested to Furnish Approved Items Listed in Encl 1, Ref Matl Requirements in Order for Examiners to Adequately Prepare for Visit ML20055E5311990-07-0606 July 1990 Forwards Request for Addl Info Re Facility Control Assembly Action Program,Per 900607 Control Element Assembly Failure at Maine Yankee.Confirmation of NRC Understanding That Util Intends to Implement C-E Plan Also Requested ML20055E9081990-07-0202 July 1990 Forwards Exam Repts 50-317/90-07OL & 50-318/90-07OL on 900507-10 ML20055J3181990-06-29029 June 1990 Forwards Insp Repts 50-317/90-10 & 50-318/90-10 on 900604-08.No Violations Noted ML20055D0731990-06-27027 June 1990 Advises That Reactor Operator & Senior Reactor Operator Licensing Exams Scheduled for Wk of 901029.Ref Matls,Listed on Encl,Should Be Provided by 900829 IR 05000317/19900041990-06-14014 June 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/90-04 & 50-318/90-04.Also Ack Schedular Slippage from 900601 to 0701 for Resolution of Unresolved Items ML20059M8351990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248E9161989-10-12012 October 1989 Advises That Licensing Activities Associated W/Nrc Bulletin 88-004,considered Complete ML20248D3591989-09-25025 September 1989 Forwards Amend 10 to Indemnity Agreement B-70,reflecting Changes to 10CFR140,effective 890701 IR 05000317/19890191989-09-22022 September 1989 Forwards Safety Insp Repts 50-317/89-19 & 50-318/89-20 on 890807-11.No Violations Noted ML20247Q2781989-09-21021 September 1989 Forwards Safety Insp Repts 50-317/89-21 & 50-318/89-21 on 890818 & Notices of Violation & Deviation ML20247P6701989-09-20020 September 1989 Forwards Request for Addl Info Re Util 890525 Response to Generic Ltr 88-14, Instrument Air Supply Problems Affecting Safety-Related Equipment. Info Requested within 35 Days of Ltr Date ML20247P6611989-09-18018 September 1989 Requests Addl Info Re Generic Ltr 88-05, Boric Acid Corrossion of Carbon Steel Reactor Pressure Boundary.... NRC Should Be Notified of Full Implementation of Program within 30 Days Following Implementation ML20247Q2371989-09-15015 September 1989 Requests Addl Info Re Util 890502 Response to Generic Ltr 89-08 Re Implementation of long-term Erosion/Corrosion Monitoring Program to Ensure Structural Integrity of All & Two Phase high-energy Carbon Steel Sys at Plant ML20247G2841989-09-13013 September 1989 Approves 890207 Request to Withhold CEN-382(B)-P, Verification of Acceptability of 1-PIN Burnup Limit of 60 Mwd/Kg for Calvert Cliffs,Units 1 & 2 from Public Disclosure (Ref 10CFR2.790) ML20247E8311989-09-0909 September 1989 Requests Util Furnish Ref Matl in Encl List, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exam, by 891004.Written Exam Scheduled for 891204 & Operating Exams Scheduled for 891205-08 ML20246Q1781989-09-0505 September 1989 Discusses Conclusions of Investigation 1-89-003 Re QC Inspector Harassment & Intimidation by Craft Personnel. Insufficient Evidence Found to Conclude Incidents Constitute Violation of 10CFR50.7.Response Requested within 30 Days ML20246K1251989-08-31031 August 1989 Ack Receipt of & Payment of Civil Penalty in Amount of $75,000,proposed by NRC in ML20246L3301989-08-28028 August 1989 Forwards Insp Repts 50-317/89-14 & 50-318/89-14 on 890516-0703 & Notice of Violation.Mgt of Surveillance Programs Has Been Source of Continuing Concern to NRC IR 05000317/19890121989-08-24024 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/89-12 & 50-318/89-12 ML20246G1221989-08-22022 August 1989 Forwards Safety Insp Repts 50-317/89-17 & 50-318/89-18 on 890717-21 & Notice of Deviation 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20138H3831999-10-25025 October 1999 Forwards Draft Model of Renewed License for Calvert Cliffs, Unit 2 to Illustrate How List of Minimum Requirements Could Be Incorporated Into License Condition ML20217M1721999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept Form Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20212M2631999-10-0404 October 1999 Informs That Staff Concluded That Licensee Responses to GL 97-06 Provides Reasonable Assurance That Condition of Util SG Internals in Compliance with Current Licensing Bases for Calvert Cliffs Nuclear Power Plant ML20212J7811999-09-30030 September 1999 Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future ML20212J5611999-09-29029 September 1999 Informs That on 990916,NRC Completed mid-cycle Plant Performance Review of Calvert Cliffs.No Areas in Which Util Performance Warranted Addl Insp Beyond Core Insp Program Identified.Historical Listing of Plant Issues,Encl ML20212A2001999-09-0808 September 1999 Forwards Insp Repts 50-317/99-06 & 50-318/99-06.Two Violations Being Treated as Noncited Violations ML20211N8971999-09-0707 September 1999 Responds to Ltr to D Rathbun of NRC Dtd 990720,in Which Recipient Refers to Ltr from Wc Batton Expressing Support on Renewal Application of Baltimore Gas & Electric Co for Calvert Cliffs Plants ML20211K3091999-08-27027 August 1999 Informs That During 990826 Telcon,L Briggs & B Bernie Made Arrangements for NRC to Inspect Licensed Operator Requalification Program at Calvert Cliffs Npp.Insp Planned for Wk of 991025 ML20210Q1941999-08-11011 August 1999 Informs That Info Submitted in 981130 Application Re CEN-633-P,Rev 03-P,dtd Oct 1998,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210N1291999-08-0505 August 1999 Forwards NRC Response to W Batton Ltr Expressing Support of Renewal Application for Calvert Cliffs Plants as Requested in Ltr ML20211C0951999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20210J0741999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by Nrc.Web Site Should Reflect Info within 2 Wks ML20211C3251999-07-30030 July 1999 Expresses Appreciation for Participation in Y2K Training & Tabletop Exercise Held on 990714 ML20211B5381999-07-30030 July 1999 Expresses Appreciation for Support in Y2K Training & Tabletop Exercise Held on 990714.Suggests Referral to NRC Y2K Web Site to View Issues & Lessons from Tabletop That Will Be Tracked by NRC ML20210D0911999-07-22022 July 1999 Responds to to Chairman Jackson Referring to Ltr from New 7th Democratic Civic Club,Inc.Forwards Staff Response to W Batton,President of New 7th Democratic Civic Club,Inc ML20210A5021999-07-20020 July 1999 Responds to ,Expressing Support for Renewal of Operating Licenses for Calvert Cliffs Plant & to Concerns Re Lack of Specificity for License Renewal Regulations & Length of Time Set Aside for Public Comment ML20210B7651999-07-15015 July 1999 Forwards SER Denying Licensee Proposed TS Amend Dtd 981120, to Delete TS Requirements for Tendon Surveillance & Reporting Because TS Requirements Duplication of Requirements in 10CFR50.55a.Notice of Denial Encl ML20209G2081999-07-13013 July 1999 Forwards Insp Repts 50-317/99-05 & 50-318/99-05 on 990509- 0626.No Violations Noted ML20210A6311999-07-0606 July 1999 Discusses Closure of TACs MA0532 & MA0533 Re Response to Requests for Addl Info to GL 92-01,rev1,suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20211H8431999-06-23023 June 1999 Ack Participation of Calvert Cliffs Nuclear Engineering Dept in NRC Cooperative Research Project with Univ of Virginia. Copy of Relevant Portion of NRC Cooperative Agreement with Univ of Virginia Encl ML20196C6831999-06-21021 June 1999 Discusses Proposed Alternative Submitted by Bg&E for Calvert Cliffs NPP to Requirements of 10CFR50.55a(g)(4) in Regard to Compliance with Latest Approved Edition of ASME Code,Section XI for Third Ten Year Insp Interval Beginning on 990701 ML20196E0371999-06-16016 June 1999 Forwards Insp Repts 50-317/99-03 & 50-318/99-03 on 990321-0508.Apparent Violation Being Considered for Escalated Enforcement Action ML20207G4331999-06-0707 June 1999 Informs That in Response Request by Nrc,Fema Evaluated Adequacy of Evacuation Plans & Training of Local First Responders for Area Around Ccnpp.Copy of FEMA & Encl to Ltr,Which Provides FEMA Recommendations Encl ML20207G4701999-06-0707 June 1999 Informs of Reorganization in NRR Ofc,Effective 990328. Organization Chart Encl ML20207B2491999-05-21021 May 1999 Forwards Insp Repts 50-317/99-04 & 50-318/99-04 on 990405-16.No Violations Noted.Insp Revealed Few Potential & Plausible Aging Effects NRC Team Determined Should Be Included in License Renewal Application ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206A6171999-04-22022 April 1999 Responds to Request for Statistics on Allegation Re Plant by J Osborne.Encl Tables Provides Breakdown of Allegations by Source Category for Allegations Receive in CY95-98 & First Six Month of 1999 ML20205R0961999-04-15015 April 1999 Forwards Insp Repts 50-317/99-01 & 50-318/99-01 on 990131- 0320.One Violation of NRC Requirements Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20205P1381999-04-0909 April 1999 Discusses 990223 Ppr.Forwards Plant Issues Matrix & Insp Plan.Since Spring 1998 Unit 1 Operated at Essentially Full Power.Unit 2 Had Similar Power History Except for Jul 1998 Manual Reactor Trip Due to Small Bore Pipe Steam Leak ML20205P1281999-04-0808 April 1999 Forwards Monthly Status Rept on Licensing Activities & Regulatory Duties of NRC for Mar 1999.Targets for Licensing Action Age & Completion Rates & License Renewal Process for Calvert Cliffs Remains on Schedule ML20205E5511999-03-26026 March 1999 Forwards Insp Repts 50-317/99-02 & 50-318/99-02 on 990208-12.No Violations Noted.Insp Was First of Three Planned Visits to Verify Ccnpp License Renewal in Compliance with Requirements of Rule for License Renewal ML20205G8841999-03-24024 March 1999 Discusses Bg&E Application Filed on 980408 for Renewal of Operating Licenses DPR-53 & DPR-68 for Calvert Cliffs Units, 1 & 2.For Listed Reasons,Partial Exemption from 10CFR170 Fees Granted IAW 10CFR170.11(b)(1) ML20205B0291999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of License Renewal Application for Plants,Units 1 & 2,dtd 980408,that Staff Determines Has Generic Value to Industry ML20204H6281999-03-21021 March 1999 Forwards SER Reflecting Status of Staff Review of Util License Renewal for Calvert Cliffs Nuclear Power Plants, Units 1 & 2 ML20207E9641999-03-0404 March 1999 Forwards Insp Repts 50-317/98-12 & 50-318/98-12 on 981213- 990130 & Notice of Violation Re Failure of Maint Workers to Tighten Bolting for Svc Water Heat Exchanger ML20207G8631999-02-25025 February 1999 Forwards Operator Initial Exam Repts 50-317/99-301OL & 50-318/99-301OL on 990122 & 25-29 (Administration) & 990201- 05 (Grading).All Applicants Passed All Portions of Exams ML20203D3981999-02-0505 February 1999 Forwards Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20203A6141999-02-0303 February 1999 Submits Details on Listed Areas Re Inspection Plan of Insp Scheduled for 990203 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20199G4121999-01-20020 January 1999 Forwards SE Accepting Util USI A-46 Implementation Program for Plant ML20199K8481999-01-19019 January 1999 Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted ML20199L6621999-01-19019 January 1999 Informs That Licensee Authorized to Administer Initial Written Exam to Listed Applicants on 990122.NRC Region I Operator Licensing Staff Will Administer Operating Test to Applicants ML20199F4101999-01-0808 January 1999 Forwards SE Accepting Util 960213,0725 & 981202 Responses to GL 95-07, Pressure Locking & Thermal Binding of Safety- Related Power-Operated Gate Valves ML20198S4291999-01-0707 January 1999 Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification ML20198S7491999-01-0707 January 1999 Forwards SER Accepting Licensee ,Suppl by 980424 & 1124 Ltrs Proposing Changes to Rev 49 of Calvert Cliffs Nuclear Power Plant Quality Assurance Program Description in Accordance with 10CFR50.54(a)(3) ML20196K2991999-01-0404 January 1999 Forwards Notice of Consideration of Approval of Transfer of Facility Operating License & Matl License & Opportunity for Hearing in Response to Application ML20202D0271998-12-15015 December 1998 Forwards Notice of Withdrawal of Application for Amend to License DPR-69.Proposed Change Would Have Modified Svc Water Head Tanks.Without Encl ML20198L3431998-12-12012 December 1998 Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A ML20198B1791998-12-10010 December 1998 Advises of Planned Insp Effort Resulting from Calvert Cliffs NPP Review Conducted on 981110.Details of Insp Rept for Next 6 Months & Historical Listing of Plant Issues Considered During Process Encl 1999-09-08
[Table view] |
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NOV 3 ~ 1986 Docket Nos. 50-317 50-318 Baltimore GTs and Electric Compan ATTN: Mr. A. E. Ludvall, J Vice President, Supply
- P. O. Box 1475 Baltimore, Maryland 21203 Gentlemen:
Subject: Combined Inspection Nos. 50-317/85-22 and 50-318/85-20 This refers to'your letter dated July 28, 1986, in response to our letter dated June 25, 198 Thank you for 1'nforming us of the corrective actions documented in your letter
- to B. K.' Grimes of NRC, dated June 30,1986 (reference b in your letter to us).
Your corrective actions will be examined during a future inspectio Your cooperation with us is appreciate
Sincerely,
.
Original signed BY t 1"
James T U188 Stewart D. Ebneter, Director
" Division of Reactor Safety cc w/ encl:
M. Bowman, General Supervisor, chnical Services Engineering Thomas Magette, Administrator, Nuclear Evaluations Daniel Latham, Director, Security Services (Safeguards Only)
Norman J. Bowmaker, Vice President, General Services (Safeguards Only)
! Public Document Room (PDR)
local Public. Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Maryland (2)
,
} 8dh a \
l OFFICIAL RECORD COPY RL CC 86-22/20 - 0001. ; PDR ADOCK 05000317 G PDR
7_
,
Baltimore Gas and Electric Company 2 bec w/ enc 1:
Region I' Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
DRP Section Chief M. McBride, RI, Pilgrim T. Kenny, SRI, Salem D. Jaf fe, . LPM, NRR Robert J. Bores,1DRSS
-
t-l DRSS:RICIC DR RI :RI Cheung/pj Anderson Du
.(bay /86 t9/f/86't&/] /86 0FFICIAL RECORD CG RL CC 86-22/20 - 0002. /09/86
~ -
.
.
-
.
.
ABALTIMORE GAS AND
. ELECTRIC CHARLES CENTER P. O. BOX 1475 * BALTIMORE MARYLAND 21203 JostPN A.TsERNAN vict Patssotat uvema cataav July 28,1986 Docket No U. S. Nuclear Regulatory Commission 50-318 Region I DPR-53 License No Park Avenue DPR-69 King of Prussia, PA 19406 t
ATTENTION: Mr. Stewart D. Ebneter, Director Division of Reactor Safety REFERENCES: (a) Letter from Mr. G. G. Zech, to Mr. A. E. Lundvall, Jr., dated March 4,1986, Inspection Report 50-317/85-22; 50-318/85-20 (b) Letter from Mr. J. A. Tiernan, to Mr. B. K. Grimes, dated June 30,1986 (c) Letter from Mr. S. D. Ebneter, to Mr. A. E. Lundvall, Jr., dated l
June 25,1986, Notice of Violation l -
l l Gentlemen:
I
! This refers to inspection Report 50-317/85-22;50-318/85-20, and Reference (c) which l
identified four items of apparent noncompliance with NRC requirements. Although it was not required, we responded to Reference (a) with Reference (b). Reference (a)
l L
originally identified the four apparent violations as Potential Enforcement item We have reviewed our previous response to these items and we find our submittal to still be acceptabl Therefore, we refer you to Reference (b) as our response to L
i Reference (c).
Should you have any further questions regarding this reply, we will be pleased to discuss them with yo Very truly yours, f
!
l JAT/SRC/ dim l cc: D. A. Brune, Esquire
!
' J. E. Silbergd,Eskuire S.A.McNe Ni C T. Foley, NRC
./
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