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| {{Adams | | {{Adams |
| | number = ML20212G552 | | | number = ML20217Q011 |
| | issue date = 10/31/1997 | | | issue date = 08/15/1997 |
| | title = Notification of Significant Licensee Meeting 97-111 W/Util on 971113 to Discuss Review Status of Corrective Actions for Radiation Protection Issues Noted in Insp Repts 50-317/97-02 50-318/97-02,50-317/97-03 & 50-318/97-03 | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-317/97-02 & 50-318/97-02 |
| | author name = Doerflein L | | | author name = Doerflein L |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Cruse C |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | addressee affiliation = BALTIMORE GAS & ELECTRIC CO. |
| | docket = 05000317, 05000318 | | | docket = 05000317, 05000318 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-317-97-02, 50-317-97-03, 50-317-97-2, 50-317-97-3, 50-318-97-02, 50-318-97-03, 50-318-97-2, 50-318-97-3, 97-111, NUDOCS 9711060225 | | | document report number = 50-317-97-02, 50-317-97-2, 50-318-97-02, 50-318-97-2, NUDOCS 9708290109 |
| | document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE | | | title reference date = 06-30-1997 |
| | page count = 3 | | | document type = CORRESPONDENCE-LETTERS, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
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| | August 15, 1997 Mr. Charles Vice President Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 4702 SUBJECT: NRC INSPECTION REPORT NOS. 50 317/97 02 AND 50 318/97 02 AND NOTICE OF VIOLATION |
| | |
| | ==Dear Mr. Cruse:== |
| | This letter refers to your June 30,1997, correspondence in response to our May 29,1997, letter. |
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| | Thank you for Informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program. |
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| | We appreciate your cooperation. |
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| | Sincerely, Ohtginal Signed by: |
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| | Lawrence T. Doerflein, Chief Projects Branch 1 Division of Reactor Projects Docket Nos. 50 317 50 318 cc: . |
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| | T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP) |
| | R. McLean, Administrator, Nuclear Evaluations J. Walter, Engineering Division, Public Service Commission of Maryland cc w/ copy of Licensee's Response Letter: |
| | l K. Burger, Esquire, Maryland People's Counsel i R. Ochs, Maryland Safe Energy Coalition - . |
| | State of Maryland (2) \ |
| | li!NERJR,Illlill pg g,g,PDR G - |
| | "#* OFFICIAL RECORD COPY IE:01 |
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| | Mr. Charles Distribution w/ copy of Licensee's Response Letter: |
| | RI EDO Coordinator S. Stewart Calvert Cliffs A. Dromerick, NRR L. Doorfloin, DRP S. Adams,DRP R. Junod, DRP M. Complon, RI Nuclear Safety Information Center (NSIC) |
| | PUBLIC Region l Dockat Room (with concurrences) |
| | Inspection Program Branch, NRR (IPAS) |
| | DOCDESK DOCUMENT NAME: A:\RL970202.CC To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = |
| | Copy with attachment / enclosure *N' = No copy 0FFICE Rl/DRP ., |
| | Al/DRP NAME SAdamse t) g LDoertlein ddd DATE 08/15/97 / 084(/97 0FFICIAL RECORD COPV |
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| | CnAn.as 11. Caost Baltimon Oas ard Electric Company |
| | % PruWnt Calmt Cliffs Nuclear Power Plant fN Nuclear Energy 16$0CalvertClifT Parkwsy |
| | . 1,95by. Marylard 20557 410 495 4455 j i |
| | i June 30,1997 U. S. Nuclear Regu! story Commission Washington,DC 20$$$ |
| | NITENTION: Document Contml Desk SUBJECT: Calvert CliffsNuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50 317 & $0 318 |
| | ]Lenly to a Nottee ofViolation Inungstlodoort Not3n 117(312V97 02 _ |
| | REFERENCE: (a) Letter imm Mr.1. T. Doerflein (NRC) to Mr. C. (BGE). dated p May 29, 1997. NRC Region 1 Integrated Inspection Report Nos. 50-317/97 02 and 50 318/97 02 and Notice of Violation in response to Reference (a), Attachment (1) details our response to the violations in the subject Nuclear Regulatory Commission Inspection Repott coace ning corrective actions associated with our Motor. |
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| | Operated Valvo Program. |
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| | Should you have questions regarding this matter, we will be pleased to discuss them with you. |
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| | Very truly yours, I |
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| | , (4% |
| | for Charles Vice President Nuclear Energy CliC/SJR/bjd Attachment cc: R. S. Fleishman, E 1ulto Resident inspector,NRC J. B. Silberg. Esquire R.1. McLean, DNR * |
| | A. W. Dromerick, NRC J.11.Waltet PSC |
| | . Director, Project Directorate I 1, NRC L. T. Doerflein, NRC 11. J. Miller, NRC |
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| October 31, 1997 ,
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| MN No. 97111 ,
| | ATTACIORENT (1) |
| U.S. NUCLEAR REGULATORY COMMISSION
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| | NO11CE OF VIOLATION 9041'h97434g AND $641697 4348 O |
| | FAILURE 10 IMP 12 MENT CORREC11VE ACTIONS As REQUIRED BY le CFR PART Sg. APPENDIX 5. CRITERION 16 |
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| | Notice of Violation Nos. 50-317/97 02 08 and 50 318/97 02-08 describe a failms to implenent |
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| | cormtin notices as required by 10 CPR Part 50, Appendix B, Critwien 16. W notice of violation i states, la part: |
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| | 10 CFR 30, 4pendia B, Cr.. rien XVI, 'Cormeln Action," repires that nwaren be established to astwe that conditions adwese to petity, such at fellwn, maV- 2:=, |
| | dqficiencies, deviations, dyrctin material and optoment and ::-: :-. :a are pronptly identyled and oormted, br the once ofsignfloant condition adwrge to paltry, the nearwes shall answe that the cause qfthe condition is determinedmedcornettu action taken to preclude repetition. |
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| | Conernry to the abon, in April 19% 4ter ' pairs topower operated nilqf valw block vain l-MOY403, correctin actions wn not taken to)\dly evaluate the apaNitty of this vain to |
| | ? )bnetton sender design 4aris conditions he itsprior degradedsinte. Also, oorreottw actions wre |
| | ). not taken then lofully evaluate the operabiliQ' ingtdioatione due to potential degraded conditions for the otherpower operatedreligf wrin Nock valves (1-M0Y.403 and2 MOV403 and 405). |
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| ==REGION I==
| | I. - REASON BOR TIRE YtollTION |
| NOTICE OF SIGNIFICANT LICENSEE MEETING Licensee: Baltimore Gas and Electric Company (BGE)
| | ' Calvert Cilffs Nuclear Pour Plant failed to meet the requirwnents of 10 CFR Part 50, Appendix B, Criterion 16 in that: - |
| Facility: Calvert Cliffs Nuclear Power Plant Units 1 & 2 Docket Nos: 50-317/50 318 Time and Date: 1:00 p.m., November 13,1997 Location: Calvert Cliffs Nuclear Power Plant 1650 Calvert Clifis Parkway Lusby, Maryland 20657 4702 Purpose: Review Status of Corrective Actions for Radiation Protection issues noted in inspection Report Nos. 50 317/97 02 &
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| 50 318/97 02:50 317/97 03 & 50 318/97-03 NRC Attendees: l Nicholson, Deputy Director, Division of Reactor Safety (DRS)
| | We did not fully evaluete the operability impact of enlarging the wedge guide grooves of 1 MOV-40L |
| J. White, Chief, Radiation Safety Branch DRS L. Doerflein, Chief, Projects Branch 1, Division of Reactor Projects A. Dromer!ck, Proj<sct Manager, P6oject Directorate I 1, Office of Nuclear Reactor Regulation (NRR) | | ' |
| J. Stewart, Senior Resident inspector, Calvert Cliffs Licensee Attendees: C. Cruse, Vice President - Nuclear Energy P. Katz, Plant General Manager B. Watson, General Supervisor, Radiation Safety T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP)
| | We did not fully evaluate the impact of rubbing and interfmence found in 1.MOV-403 on its past operability or the operability of the other power operated relief valve (PORV) block valus. |
| UllRLEllEI[IIll LO 60 0.F7
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| | We desamined the following reasons for the vloistion: |
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| ,. , ! | | % controlling procedure for the Motor Operated Valve (MOV) Program did not require a MI evaluation that compared MOV oritial characteristlos to eithw the "as found" condition (i.e., an evalution of the impsot of rubbles and laterfence found in 1 MOV 403) ce the "as leR" condition (l.c., an enluation of the impact of the changes made to the valw's internal |
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| | e h personnel involved in the ownt were not sumciently knowledgeable to fbily evaluate the |
| Note: This meeting is open for public observation. Attendance by additional NRC personnel should be made known by November 12,1997 via telephone call to Lawrence Doerflein at (610) 337 5378. Handicapped persons requiring assistance to attend or participate in the meeting shall make their requests known to Lawrence T. Doerflein, Chiaf,-
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| Projects Branch 1, L).S. Nuclear Regulatory Commission, Region I,475 Allendale Road, King of Prussla, PA., 19406,(610) 337 5378, no later than two business days prior to the ,
| | impact that the "as-found" or the "as-leR" condition of I MOV.403 could have on its opwebility or the opusbility of otbet PORY block valves. |
| t meetin Prepared by: Original Signed by: | | |
| Lawrence T. Doerflein, Chief I Projects Branch 1 Division of Reactor Projects :
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| Distribution: *
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| C Cruse, Vice President - Nuclear Energy Division PUBLIC State of Maryland Regional Administrator Secretary, RI Deputy Regional Administrator Secretary, RI DRP Division Secretary, RI DRS Division Secretary, RI DRM Division Secretary, RI DNMS Division Secretary, Rl Region l Receptionist I
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| | A*ITACHMENT (1) |
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| | NOTICE OF VIOLATION $041787 02-08 AND 5041g47-02 03 O |
| | FAILURE TO IMPLEMENT CORRECTIVE ACTIONS AS REQtHRED 11Y |
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| | 10 CFR PART $0. APPENDIX B. CRITERION 16 Badgramm4 Near the end of the Unit 1 1994 Refbeling Outage (RTO), the block valve (1 MOVU O3 ) for PORY l ER%402 was discovered to be leaking. De leak was not expected since the velve had just been overhauled. We determined the luk rate, approximately eight gallons per hour, did not affect the valve's operability. An issue report was generated to invwtigate the leak during tlw 1996 RFO. |
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| | The valve was disassembled and inspected during the 1996 RFO. Rubbing was found in the guide groove of the valve wedge. The rubbing was caused when the disk contacted a weld at the end of the valve's closing stroke. De contact caused the wedge to become cocked in the seat and resulted in the valveleaking. |
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| | Valve Opwation and Test Equipment System (VOTT.S) testing at the start of the Unit 1 1996 RFO had shown an unexpected increase in disk pullout force. $1nce no unexpected increase in disk pull out force was seen in the other Unit I and 2 PORY block valves, the results of the VOTES tests supported our determination of the cause for the leak in 1 MOW 403. |
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| | To cornet the leak, the 1 MOW 403 wedge wu lapped, the wedge's guide grooves were enlarged, and excess base metal was removed. Enlarging the guide grooves and removing additional base metal were performed per the vendor technical manual. We failed to evaluate how changing the valve's internal A dirnensions would Impact the valve's operability. De "as.left" VOT1?S test did show that the disk pullout force was within expected values. |
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| | He System Engineer evaluated the valve repair. Ilowever, the evaluation was not ooordinated between the System Engineer and the Component Engineer. nc System Engineer evaluated the "as found" and |
| | "as-left" conditions of the valve. De System Engineer concluded the rubbing was limited to the seating portion of the stroke and did not affect the valve's ability to stroke shut. De Component Engineer was awwe that the valve had bwn repaired but only evaluated the "as found" and *as left" VOTES test results. De VOTES test ruults for the Unit I and 2 PORY block valves did not Indicate generic concerns. Neither the System Engineer nor the Component Engineer considered the full impact that machining the guide grooves might have on the valve's ability to function under design basis differential pressure conditions. A full evaluation would have considered the impact of changing the valve's internal dlmensions. |
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| | During May 1997, a Performanoe Prodletion Model(PPM) was run on I MOV 403 to verify the valve's satisfactory performance with its guide grooves enlarged. %c PPM determined that the valve in its curmut configuration would operate under design requirements. |
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| | II. CORRECTWE STEPS TAWN AND RRULTS_ACHIEi1D Responsibility for the verifying satisfactory performance of MOVs has been assigned to 2 CV Component Engin**t. ' |
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| | ATTACIIMENT (1) |
| | O NOTICE OF VIOLATION S0 31747 02 08 AND 50-31197-0248 |
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| | O FA11NRE TO IMPIEMENT CORRECT!YE ACTIONS AS REQUIRED BY 10 CFR PART 50. APPENDIX D. CRITERION 16 From a review of maintenance orders of all the PORY block valves, we concluded: |
| | A. He internal dbnensions of no other PORY block valyc had been changed; and B. Internal inspections, VOTES tests, and Motor Power Monitor tests show that one other PORV block valve had rubbing or interference. Cornetive maintenanoc was performed on that valve. |
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| | III. CORIIFMIVE STEPS W111Cll WII .T. IlE TAKEN To AY.DID FURTilER HO1AT10ES Training will be given to increase the knowledge level of selected site penonnel on MOVs: |
| | A. Additional representatives from Engineering will attend PPM training. |
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| | D. Overview training will be given to ensure affected organizations understand the effects of maintenance and modifications on the operability of MOVs. |
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| | The controlling procedure for the MOV Program will be revised to require the MOV Component O Engineer to verify that perfortaanoe of MOVs is satisfactory and require an evaluation when valve internal dimensions which impact the design basis are changed. |
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| | IV. DATE WIIEN Full CSMPLIANCE WII.T. BE AcirfFVED ne PPM training is curnntly scheduled to be completed by Augu-t 1997. |
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| | The ovesview training will be completed prior to the 1998 RFO. |
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| | De controlling procedure for the MOV Program procedure will be revised by December 15,1997. |
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| 1 Distribution (Via E Mail): .
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| L. Callan, Executive Director for Operations, OEDO H. Thompsori, D,;puty Executive Director for Regulatory Programs, OEDO A. Thadani, Acting Deputy Executive Director for Regulatory Effectiveness, OEDO S. Collins, Director, Office of Nuclear Reactor Regulation J. Roi, Deputy Director, Division of Reactor Program Management, NRR R. Spessard, Director, Divislun of Reactor Controls and Human Factors, NRR J. Lleberman, Director, Office of Enforcement R. Zimmelman, Associate Director for Projects, NRR B. Boger, Director, Division of Reactor Projects l/ll, NRR T. Martin, Director, Office for Analysis and Evaluation of Operational Data, AEOD V., Kennedy, RI EDO Coordinator ,
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| J. Scuder, IRM/FOl l N. Green, Jr., Policy Development & Technical Support Branch '
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| S. Bajwa, Director, Pro!. set Directorate I 1, NRR A. Dromerick, PD l 1, NRR D. Screnci, Public Affairs, RI N. Sheehan, Field Public Affairs Officer, RI S. Stewart, SRI, Calvert Cliffs M. Campion, ORA .
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| D. Chawaga, ORA J. Wiggins, DRS L. Nicholson, DRS l DOCUMENT NAME: A:\MTG97111.CC
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| To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE Rl/DRP -
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| NAME LDoerflein #% rb -
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| DATE 10ht /97 OFFICIAL RECORD COPY -
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| | TOTA P.05 |
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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: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
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
ML20199K8481999-01-19019 January 1999
Forwards Insp Repts 50-317/98-11 & 50-318/98-11 on 981025-1212.No Violations Noted
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
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)
ML20198S4291999-01-0707 January 1999
Requests Addl Info Re License Renewal Application as Application Relates to Staff Position on Environ Qualification
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] |
Text
o
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August 15, 1997 Mr. Charles Vice President Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 4702 SUBJECT: NRC INSPECTION REPORT NOS. 50 317/97 02 AND 50 318/97 02 AND NOTICE OF VIOLATION
Dear Mr. Cruse:
This letter refers to your June 30,1997, correspondence in response to our May 29,1997, letter.
Thank you for Informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
We appreciate your cooperation.
Sincerely, Ohtginal Signed by:
<
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Lawrence T. Doerflein, Chief Projects Branch 1 Division of Reactor Projects Docket Nos. 50 317 50 318 cc: .
T. Pritchett, Director, Nuclear Regulatory Matters (CCNPP)
R. McLean, Administrator, Nuclear Evaluations J. Walter, Engineering Division, Public Service Commission of Maryland cc w/ copy of Licensee's Response Letter:
l K. Burger, Esquire, Maryland People's Counsel i R. Ochs, Maryland Safe Energy Coalition - .
State of Maryland (2) \
li!NERJR,Illlill pg g,g,PDR G -
"#* OFFICIAL RECORD COPY IE:01
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Mr. Charles Distribution w/ copy of Licensee's Response Letter:
RI EDO Coordinator S. Stewart Calvert Cliffs A. Dromerick, NRR L. Doorfloin, DRP S. Adams,DRP R. Junod, DRP M. Complon, RI Nuclear Safety Information Center (NSIC)
PUBLIC Region l Dockat Room (with concurrences)
Inspection Program Branch, NRR (IPAS)
DOCDESK DOCUMENT NAME: A:\RL970202.CC To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" =
Copy with attachment / enclosure *N' = No copy 0FFICE Rl/DRP .,
Al/DRP NAME SAdamse t) g LDoertlein ddd DATE 08/15/97 / 084(/97 0FFICIAL RECORD COPV
a
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CnAn.as 11. Caost Baltimon Oas ard Electric Company
% PruWnt Calmt Cliffs Nuclear Power Plant fN Nuclear Energy 16$0CalvertClifT Parkwsy
. 1,95by. Marylard 20557 410 495 4455 j i
i June 30,1997 U. S. Nuclear Regu! story Commission Washington,DC 20$$$
NITENTION: Document Contml Desk SUBJECT: Calvert CliffsNuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50 317 & $0 318
]Lenly to a Nottee ofViolation Inungstlodoort Not3n 117(312V97 02 _
REFERENCE: (a) Letter imm Mr.1. T. Doerflein (NRC) to Mr. C. (BGE). dated p May 29, 1997. NRC Region 1 Integrated Inspection Report Nos. 50-317/97 02 and 50 318/97 02 and Notice of Violation in response to Reference (a), Attachment (1) details our response to the violations in the subject Nuclear Regulatory Commission Inspection Repott coace ning corrective actions associated with our Motor.
Operated Valvo Program.
Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yours, I
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, (4%
for Charles Vice President Nuclear Energy CliC/SJR/bjd Attachment cc: R. S. Fleishman, E 1ulto Resident inspector,NRC J. B. Silberg. Esquire R.1. McLean, DNR *
A. W. Dromerick, NRC J.11.Waltet PSC
. Director, Project Directorate I 1, NRC L. T. Doerflein, NRC 11. J. Miller, NRC
(
.
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ATTACIORENT (1)
'
NO11CE OF VIOLATION 9041'h97434g AND $641697 4348 O
FAILURE 10 IMP 12 MENT CORREC11VE ACTIONS As REQUIRED BY le CFR PART Sg. APPENDIX 5. CRITERION 16
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_
Notice of Violation Nos. 50-317/97 02 08 and 50 318/97 02-08 describe a failms to implenent
cormtin notices as required by 10 CPR Part 50, Appendix B, Critwien 16. W notice of violation i states, la part:
'
10 CFR 30, 4pendia B, Cr.. rien XVI, 'Cormeln Action," repires that nwaren be established to astwe that conditions adwese to petity, such at fellwn, maV- 2:=,
dqficiencies, deviations, dyrctin material and optoment and ::-: :-. :a are pronptly identyled and oormted, br the once ofsignfloant condition adwrge to paltry, the nearwes shall answe that the cause qfthe condition is determinedmedcornettu action taken to preclude repetition.
'
Conernry to the abon, in April 19% 4ter ' pairs topower operated nilqf valw block vain l-MOY403, correctin actions wn not taken to)\dly evaluate the apaNitty of this vain to
? )bnetton sender design 4aris conditions he itsprior degradedsinte. Also, oorreottw actions wre
). not taken then lofully evaluate the operabiliQ' ingtdioatione due to potential degraded conditions for the otherpower operatedreligf wrin Nock valves (1-M0Y.403 and2 MOV403 and 405).
I. - REASON BOR TIRE YtollTION
' Calvert Cilffs Nuclear Pour Plant failed to meet the requirwnents of 10 CFR Part 50, Appendix B, Criterion 16 in that: -
J t
We did not fully evaluete the operability impact of enlarging the wedge guide grooves of 1 MOV-40L
'
We did not fully evaluate the impact of rubbing and interfmence found in 1.MOV-403 on its past operability or the operability of the other power operated relief valve (PORV) block valus.
,
We desamined the following reasons for the vloistion:
e
<
% controlling procedure for the Motor Operated Valve (MOV) Program did not require a MI evaluation that compared MOV oritial characteristlos to eithw the "as found" condition (i.e., an evalution of the impsot of rubbles and laterfence found in 1 MOV 403) ce the "as leR" condition (l.c., an enluation of the impact of the changes made to the valw's internal
' dimensions).
.
e h personnel involved in the ownt were not sumciently knowledgeable to fbily evaluate the
impact that the "as-found" or the "as-leR" condition of I MOV.403 could have on its opwebility or the opusbility of otbet PORY block valves.
A '
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i*.
A*ITACHMENT (1)
NOTICE OF VIOLATION $041787 02-08 AND 5041g47-02 03 O
FAILURE TO IMPLEMENT CORRECTIVE ACTIONS AS REQtHRED 11Y
_
10 CFR PART $0. APPENDIX B. CRITERION 16 Badgramm4 Near the end of the Unit 1 1994 Refbeling Outage (RTO), the block valve (1 MOVU O3 ) for PORY l ER%402 was discovered to be leaking. De leak was not expected since the velve had just been overhauled. We determined the luk rate, approximately eight gallons per hour, did not affect the valve's operability. An issue report was generated to invwtigate the leak during tlw 1996 RFO.
The valve was disassembled and inspected during the 1996 RFO. Rubbing was found in the guide groove of the valve wedge. The rubbing was caused when the disk contacted a weld at the end of the valve's closing stroke. De contact caused the wedge to become cocked in the seat and resulted in the valveleaking.
Valve Opwation and Test Equipment System (VOTT.S) testing at the start of the Unit 1 1996 RFO had shown an unexpected increase in disk pullout force. $1nce no unexpected increase in disk pull out force was seen in the other Unit I and 2 PORY block valves, the results of the VOTES tests supported our determination of the cause for the leak in 1 MOW 403.
To cornet the leak, the 1 MOW 403 wedge wu lapped, the wedge's guide grooves were enlarged, and excess base metal was removed. Enlarging the guide grooves and removing additional base metal were performed per the vendor technical manual. We failed to evaluate how changing the valve's internal A dirnensions would Impact the valve's operability. De "as.left" VOT1?S test did show that the disk pullout force was within expected values.
He System Engineer evaluated the valve repair. Ilowever, the evaluation was not ooordinated between the System Engineer and the Component Engineer. nc System Engineer evaluated the "as found" and
"as-left" conditions of the valve. De System Engineer concluded the rubbing was limited to the seating portion of the stroke and did not affect the valve's ability to stroke shut. De Component Engineer was awwe that the valve had bwn repaired but only evaluated the "as found" and *as left" VOTES test results. De VOTES test ruults for the Unit I and 2 PORY block valves did not Indicate generic concerns. Neither the System Engineer nor the Component Engineer considered the full impact that machining the guide grooves might have on the valve's ability to function under design basis differential pressure conditions. A full evaluation would have considered the impact of changing the valve's internal dlmensions.
During May 1997, a Performanoe Prodletion Model(PPM) was run on I MOV 403 to verify the valve's satisfactory performance with its guide grooves enlarged. %c PPM determined that the valve in its curmut configuration would operate under design requirements.
II. CORRECTWE STEPS TAWN AND RRULTS_ACHIEi1D Responsibility for the verifying satisfactory performance of MOVs has been assigned to 2 CV Component Engin**t. '
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ATTACIIMENT (1)
O NOTICE OF VIOLATION S0 31747 02 08 AND 50-31197-0248
,
O FA11NRE TO IMPIEMENT CORRECT!YE ACTIONS AS REQUIRED BY 10 CFR PART 50. APPENDIX D. CRITERION 16 From a review of maintenance orders of all the PORY block valves, we concluded:
A. He internal dbnensions of no other PORY block valyc had been changed; and B. Internal inspections, VOTES tests, and Motor Power Monitor tests show that one other PORV block valve had rubbing or interference. Cornetive maintenanoc was performed on that valve.
III. CORIIFMIVE STEPS W111Cll WII .T. IlE TAKEN To AY.DID FURTilER HO1AT10ES Training will be given to increase the knowledge level of selected site penonnel on MOVs:
A. Additional representatives from Engineering will attend PPM training.
D. Overview training will be given to ensure affected organizations understand the effects of maintenance and modifications on the operability of MOVs.
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The controlling procedure for the MOV Program will be revised to require the MOV Component O Engineer to verify that perfortaanoe of MOVs is satisfactory and require an evaluation when valve internal dimensions which impact the design basis are changed.
IV. DATE WIIEN Full CSMPLIANCE WII.T. BE AcirfFVED ne PPM training is curnntly scheduled to be completed by Augu-t 1997.
The ovesview training will be completed prior to the 1998 RFO.
De controlling procedure for the MOV Program procedure will be revised by December 15,1997.
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TOTA P.05
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