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| {{Adams | | {{Adams |
| | number = ML20235W715 | | | number = ML20149F724 |
| | issue date = 10/01/1987 | | | issue date = 02/08/1988 |
| | title = Insp Rept 50-271/87-15 on 870817-21.No Violations or Deviations Noted.Major Areas Inspected:Radiological Controls During Outage Operations,Including Outage Planning & Preparation & Control of Radioactive Matl | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-271/87-15 |
| | author name = Gresickcioffi, Loesch R, Shanbaky M | | | author name = Martin T |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = | | | addressee name = Murphy W |
| | addressee affiliation = | | | addressee affiliation = VERMONT YANKEE NUCLEAR POWER CORP. |
| | docket = 05000271 | | | docket = 05000271 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-271-87-15, NUDOCS 8710160377 | | | document report number = NUDOCS 8802170339 |
| | package number = ML20235W669 | | | title reference date = 12-10-1987 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | package number = ML20149C635 |
| | page count = 5 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
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| | FEB 0 8 1988 Docket No. 50-271 |
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| l U. S. NUCLEAR REGULATORY COMMISSION REGION I ,
| | Vermont Yankee Nuclear Power Corporation |
| Report No. 87-15
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| Docket N License N DRP-28 Priority Category C ;
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| Licensee: Vermont Yankee Nuclear Power Corporation
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| Yb-5, Box 169, Ferry Road Brattleboro, Vermont 05301 i
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| Facility Name: Vermont Yankee Nuclear Power Station l Inspection At: Vernon, Vermont Inspection Conducted: August 17-21, 1987 i
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| Inspectors: 44+k ( Cb - -
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| /0/'ff7 j date
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| J,A.Gresick-Cioffi,RadiationSpeggflist i h<nb-- W ~
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| y M. Loeschi Radiation SpeciaAitt
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| l0lll[ 7 date Approved by: M, f /, A /e[/!f'', '
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| M. M~. ShanbaKy, Cnief / ~date Facilities Radiation Protection Section Inspection Summary: Inspection conducted on August 17-21, 1987 Report N /87-15 Areas Inspected: Routine, unannounced inspcction of radiological controls during outage operations, including: outage planning and preparation; control I of radioactive material; internal and external exposure controls; and ALAR I In addition, LPRM cutting and diving operations were observe Results: No violations or deviations were identified in the revie I 8710160377 871006 l PDR ADOCK 05000271 G PDR,
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| I DETAILS 1.0 Personnel Contacted .
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| 1.1 Licensee Personnel
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| *R. G-ipard 0A Supervisor
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| *R. Leach Radiation Protection Supervisor
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| *J. McCarthy . ALARA Engineer R. Morrissette Plant Health Physicist
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| *J. Pelletier Plant Manager M. Thornhill Health Physicist
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| *R. Wanczyk Operations Superintendent Other licensee and contractor personnel were also contacte !
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| 1.2 NRC Personnel +
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| *D. Haverkamp, Reactor Licensing Engineer i
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| * denotes attendance at the exit interview on August 21, 198 .0 Status of Previously Identified Item _ss 1 (Closed) 83-33-02 (Inspector Follow-Up). Review the formalization i of the ALARA progra The final step in formalizing the ALARA program was accomplished in March of 1987, with the establishment of two administrative procedures, A.P. 0535, "ALARA Documentation, Records, and Reports,"
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| and A.P. 0536, "ALARA Implementation for Design Changes and Work Analysis." Inspector review of these documents found 3cceptable mechanisms in place for planning and execution of work packages with respect to dose reduction and dose-saving materials and technique This item is close .2 (Closed) 85-39-04 (Inspector Follow-Up) Review licensee's assessment of C & HP procedures, policies, and other administrative control The inspector reviewed an independent assessment of the licensee's l
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| Chemistry / Health Physics procedures, policies, and administrative controls, performed between July 11 and September 26, 1986 i
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| (VYSR86-35). The assessment was comprehensive and thorough in the
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| review of the organization, staff qualifications, procedures, training, and departmental communications. As a result of the assessment, the licensee reorganized the Chemistry / Health Physics department into two separata departments, and has begun to implement other assessment recommendations (i.e. reviewing and updating staff qualifications, upgrading and enhancing training, and writing and rewriting necessary Health Physics procedures). This item is close _ _ - _ - _ _ - _ _ _ - _ _ _
| | ATTN: Mr. Warren P. Murphy Vice President and Manager of Operations RD 5, Box 169 Ferry Road Brattleboro, Vermont- 05301 Gentlemen: |
| | | Subject: Inspection 50-271/87-15 This refers to your letter dated December 10, 1987, in response to our letter dated October 6, 198 Thank you for infonning us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed progra Your cooperation with us is appreciate |
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| L 3 l 2.3 (Closed) 87-03-01 (Violation). Failure to adhere to licensee procedure for body burden analysis (A.P. 0533), resulting in L misidentification of internal uptak ;
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| The inspector reviewed the licensee's corrective action as stated in the licensee's reply to the violation, dated April 17, 1987. The a inspector verified that the licensee's corrective actions were !
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| complete. This item is close <
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| 2.4 (Closed) 87-03-02(Unresolved). Review the status and effectiveness of training in internal dosimetry and review the final determination ;
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| of whole body counter count tim The inspector reviewed the training records for the Whole Body &
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| Respiratory Systems Engineer and the Plant Health Physicist. The -
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| licensee provided an internal dosimetry course taught by' Canberra 4 Industries, to these individuals and other plant staff member Discussions with various personnel who attended the course indicated that the course was effective in providing an understanding of whole body counting and internal dosimetr The inspector also reviewed A.P. 0533, Revision 6, " Body Burden
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| ' Analysis" and interviewed whole body counting technicians. The licensee increased the count time to five minutes for all whole body counts. The inspector also reviewed the whole body counting log for anomalous data and found no further instances of false positive counts recorded. This item is close .5 (Closed) 87-03.03 (Unresolved). Review RWP procedure (A.P. 0502)
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| upgrad l The inspector reviewed the newly issued RWP procedure (revision 18).
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| The licensee had revised the procedure to incorporate stronger and clearer instructions for RWP preparation which included specific instructions.on survey frequency to support the RWP conditions and instructions. The licensee chose to keep the requirements for specific work conditions as guidelines to be used in accordance with technician judgement. This item is close .0 Dutage Planning and Preparation and ALARA j The inspector reviewed the licensee's planning and preparatico for the !
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| current refueling outage by review of documentation, observations made l during tours of plant activities, and discussions with licensee g rsonnel, j The licensee employed seven contractor HP personnel as ALARA coordinators to follow outage work packages and to coordinate with outage work group At the time of the inspection, this approach appeared to be effective in controlling and tracking personnel exposures. The licensee utilized l
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| their house technicians as lead technicians for specific-work package However, the house technicians were not involved in the work package planning end preparatio The licensee's 1987 person-rem goal is 443 re This includes a refueling ,
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| outage and extensive ISI (inservice inspection) work for which the l licensee plans to spend 373 person rem. At the time of the inspection,
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| the licensee had expended 85 person-rem, of which approximately 33 person-rom was outage relate .G Internal and External Exposure Controls (j The-licensee's program for internal and external exposure controls was reviewed against the applicable regulatory requirements and current industry practice The licensee's performance related to the ab;ve criteria was determined by:
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| - observations of above vessel LPRM work;
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| - observations of underwater diving operations involving steam dryer modifications;
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| - review of " Personnel Contamination Event Reports";
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| - review of applicable plant procedures;
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| - observations of personnel processing at HP Control Point; and
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| - discussions with various plant personne Within the scope of this review, no violations were identified. The {
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| licensee's program for internal and external exposure control appeared j adequate, although several weaknesses were observed and are discussed !"
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| belo Licensee procedure RP-0520, " Personnel Decontamination Procedure,"
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| incorrectly derives the correction factor, F, used to convert count rate to dose rate. Use of the current value underestimates the dose rate by more than an order of magnitude which could lead to inappropriate actions f in the event of a significant contamination incident. The licensee has obtained the software program " Quince" (an updated version of Varskin) J for use in calculating skin dose. This program is adequate provided the {
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| proper procedural action limits are established to indicate when j additional evaluations should be performed. The inspector discussed the j above finding with licensee managemen The licensee committed to !
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| revising the personnel contamination procedure. This will be reviewed in a future inspection (50-271/87-15-01)
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| e i Procedure OP-532, " Chemistry / Health Physics Department Key Control,"
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| lacks guidanca on what actions are to be taken in the event a locked j i
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| l high-radiation area key is lost. In addition, the procedure improperly j l
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| identifies the number of keys under control of the shift supervisor. The i l inspector noted that no documentation existed for locations of the
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| 1 various locked high-radiation areas. Discussions with several health physics technicians revealed that although most thought they knew where all the areas are located, none could specify how many areas were accessible with the high-radiation master key .0 Control of Radioactive Material The licensee's program for the control of radioactive material was reviewe The number of exits from the RCA was reduced prior to the outage. All exits other than the central HP control point are equipped with friskers and a HP watch techniciar. All other exits are sealed off and include a lead / wire security seal. Plant QA personnel perform a daily surveillance to ensure that unmonitored exits have not been use The main access control point utilizes three new Eberline PCM-1B whole body triskers'for a more effective control on personnel contamination During the course of the inspection, the inspector received an allegation regarding contamination located outside the RCA. The individual stated that he had discovered an area next to the Radwaste Building reading .
| | Sincerely, Original Signed By: |
| approximately 20,000 dpm. He further stated that the soil was known by
| | Wdliam J. Lazarus |
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| plant personnel to be contaminated to a depth of at least 2 to 3 fee The inspector sampled the soil and gave the sample to the licensee for analnis. The licensee's equipment identified the contaminates to be Co-60, Cs-137, Mn-54 and Zn-65 with a total activity of approximately !
| | Thomas T. Martin, Director Division of Radiation Safety and Safeguards cc: |
| 1E-2 uc/gm. These results were discussed with the licensee in subsequent telephone conversation ;
| | J. Gary Weigand, President and Chief Executive Officer J. P. Pelletier, Plant Manager John DeVincentis, Vice President, Yankee Atomic R. W. Capstick, Licensing Engineer Cort Richardson, Vermont Public Interest Research Group, In Gerald Tarrant, Commissioner, Vermont Department of Public Service Peter W. Agnes, Assistant Secretary of Public Safety, Comonwealth of Massachusetts Public Document Room (PDR) |
| The licensee stated that a full investigation of this matter will be conducte Pending followup on the history of the contamination, the licensee's actions relative to its discovery, and appropriate corrective actions, this item will remain unresolved (50-271/87-15-02).
| | Local Public Document Room (LPDR) |
| | Nuclear Safety Information Center (NSIC) |
| | NRC Resident Inspector State of New Hampshire State of Vermont Coninonwealth of Massaschusetts lgg21JggfKg$ [ |
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| | "0FRCiM !EC0!!D COPY" |
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| 6.0 Exit Meeting j i
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| The inspector met with the licensee denoted in Section 1.1 at the I conclusion of the inspection on August 21, 1987. The scope and finding j of the inspection were discussed at that tim ]
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| | Vermont Yankee Nuclear 2 Power Corporation bec: . ' |
| .j | | Region I Docket Room (with concurrences) |
| | Management Assistant, DRMA (w/o encl) |
| | Section' Chief, DRP G.-Grant, SRI, Vermont Yankee M. Fairtile, PM, NRR Robert J. Bores, DRSS a |
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| | T DL RI:DRSS RI:DRSM RI:D ' |
| | Loesch Shanbaky Bella 1/ti /88 1/7L/88 'J/ y/88 0FFICIAL RECORD COPY rl vt. yankee 87-15 1/19/88 |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999
Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure
ML20217L8591999-10-21021 October 1999
Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation
ML20217M1181999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20217D9711999-10-13013 October 1999
Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure
ML20217F1261999-10-12012 October 1999
Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104
BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999
Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station
ML20217C1501999-10-0707 October 1999
Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant
BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999
Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl
ML20212J7891999-10-0404 October 1999
Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant
ML20212J6501999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl
ML20216J3531999-09-29029 September 1999
Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process
BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999
Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17
BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999
Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1
BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999
Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing
BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999
Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested
BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999
Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal
ML20212C1621999-09-17017 September 1999
Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System
BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999
Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions
BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999
Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld
ML20216F3171999-09-13013 September 1999
Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation
BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999
Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp
BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999
Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution
ML20211G4791999-08-27027 August 1999
Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core
BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999
Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies
ML20211E8841999-08-25025 August 1999
Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz
ML20211E1371999-08-20020 August 1999
Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified
ML20211H0851999-08-19019 August 1999
Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness
BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999
Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered
BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999
Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02
BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999
Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings
ML20210M5791999-07-30030 July 1999
Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed
ML20211E1701999-07-28028 July 1999
Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS
ML20210G5041999-07-27027 July 1999
Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916
ML20210J3031999-07-27027 July 1999
Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change
ML20210G4271999-07-27027 July 1999
Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630
ML20216D7321999-07-26026 July 1999
Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations
ML20209G2721999-07-14014 July 1999
Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station
ML20209J0601999-07-14014 July 1999
Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included
ML20209G6931999-07-14014 July 1999
Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion
ML20209G1531999-07-12012 July 1999
Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10
ML20196J2321999-06-30030 June 1999
Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible
ML20196J7421999-06-29029 June 1999
Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC
ML20209B6111999-06-29029 June 1999
Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants
ML20196J2431999-06-29029 June 1999
Informs That Author Received Call from NRR on Dirt Spreading Ltr & Questions Re Cover Ltr Statement Where Util Asks to Be Allowed to Dispose of Future Soil in Same Manner Provided Same Acceptance Criteria Met
ML20209C3751999-06-28028 June 1999
Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld
ML20209B5861999-06-28028 June 1999
Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl
ML20196G5241999-06-22022 June 1999
Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21
BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999
Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
ML20195H1741999-06-15015 June 1999
Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed
1999-09-30
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20062G6581990-11-20020 November 1990
Documents 901011 drop-in Meeting Re Refueling Outage Progress,Recent Allegations & NRC Insps
ML20062F2731990-11-20020 November 1990
Forwards Request for Response to Allegation NRR-90-A-0050. Encl Withheld (Ref 10CFR9.17 & 9.21)
ML20062F3681990-11-14014 November 1990
Forwards Safeguards Insp Rept 50-271/90-11 on 900829-31 & Notice of Violation
ML20058F2601990-10-31031 October 1990
Forwards Ref Matl Requirements for Reactor Operator Licensing Exams Scheduled for Wk of 910211
ML20058E0791990-10-26026 October 1990
Advises That NRC Will Perform fitness-for-duty Program Insp. Util Written Policies & Procedures Requested
ML20058D2651990-10-23023 October 1990
Forwards Insp Rept 50-271/90-80 on 900806-17 & Notice of Violation
ML20058B5511990-10-18018 October 1990
Advises That 900922 Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-08,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable
ML20062B6981990-10-12012 October 1990
Extends Invitation to Participate in 910220 Symposium & Workshop in King of Prussia,Pa Re Engineering Role in Plant Support
ML20059N7121990-10-10010 October 1990
Responds to Util Re Discovery of Flaws in Feedwater Check Valves 27B & 96B.NRC Believes Valve 96B Should Be Reinspected at Next Reload Outage to Verify Util Fracture Mechanics Analyses
ML20059N1351990-09-28028 September 1990
Forwards Safety Insp Rept 50-271/90-09 on 900703-0812 & Notice of Violation
IR 05000271/19900061990-09-14014 September 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-271/90-06
ML20059H0601990-09-0707 September 1990
Discusses Unescorted Access to Licensee Facilities & fitness-for-duty Program,Per .Nrc Regulations Do Not Prohibit Licensee from Accepting Access Authorization Program of Another Licensee,Contractor or Vendor
ML20058M6221990-08-0606 August 1990
Discusses Licensee Engineering Initiatives.Encourages Initiation of Initiative Similar to Region V Licensees Establishment of Engineering Mgrs Forum to Foster Disciplined & Coordinated Approach to Initiatives
ML20056A9311990-08-0202 August 1990
Forwards Safety Insp Rept 50-271/90-08 on 900716-20.No Violations Noted
ML20056A4021990-07-25025 July 1990
Forwards Radiological Controls Insp Rept 50-271/90-06 on 900618-22 & Notice of Violation
ML20055H0011990-07-17017 July 1990
Confirms 900703 Telcon W/J Pelletier & J Durr Announcing SSFI to Be Conducted at Facility During Wks of 900806 & 17. Requests Info Listed in Encl 1 Forwarded No Later than 900720
ML20059M8731990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20055C6071990-05-21021 May 1990
Advises That Util 900427 Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Box Bow Confirmed That Util Does Not Presently Use Channel Boxes in-core for Longer than One Bundle Lifetime.Action Complete
ML20248E0751989-09-26026 September 1989
Forwards Amend 11 to Indemnity Agreement B-49,reflecting Changes to 10CFR140,effective 890701,which Increase Primary Layer of Nuclear Energy Liability Insurance
ML20248A3851989-09-25025 September 1989
Forwards Safety Insp Rept 50-271/89-12 on 890718-0905.No Violations Noted
IR 05000271/19890801989-09-25025 September 1989
Ack Receipt of Informing NRC of Steps to Correct Violations Noted in Insp Rept 50-271/89-80
IR 05000271/19890131989-09-22022 September 1989
Forwards Safety Insp Rept 50-271/89-13 on 890807-11 & 0828-0901.No Violations Noted
ML20247M8651989-09-19019 September 1989
Forwards Safety Insp Rept 50-271/89-14 on 890807-11. Corrective Actions for Six Violations & Two of Three Open Items Found Acceptable & Items Closed.Resolution for Thomas & Betts Connector Qualified Life Inadequate
ML20247N0861989-09-15015 September 1989
Forwards Safety Insp Rept 50-271/89-15 on 890821-25.No Violations Noted
ML20247N2441989-09-14014 September 1989
Forwards Safety Insp Rept 50-271/89-11 on 890822-24.No Violations Noted
ML20246P2501989-09-0101 September 1989
Forwards Technical Evaluation Rept Concluding That Rev 4 to ODCM Uses Methodology Consistent W/Nrc Guidelines & Acceptable Interim Ref.Requests That Points Raised in Conclusions Section Be Addressed within 6 Months
ML20246Q0121989-08-31031 August 1989
Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted
IR 05000029/19890141989-08-31031 August 1989
Forwards Insp Repts 50-029/89-14 & 50-271/89-10 on 890717-21.No Violations Noted
ML20246P3671989-08-30030 August 1989
Approves Procedures for Disposal of Slightly Contaminated Septic Waste Onsite,Per 10CFR20.302(a).Disposal Involves Exposure Pathways Less Significant than Pathways Considered in Fes.Procedures Should Be Incorporated in ODCM
ML20246K6371989-08-23023 August 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-271/89-80
ML20246E7981989-08-21021 August 1989
Advises That Violation Re Testing of CO2 Sys Noted in Insp Rept 50-271/89-04 Still Valid Due to No Alternate to Testing Established,Per Util Requesting Withdrawal of Violation
ML20246D7591989-08-21021 August 1989
Forwards SER Accepting Util Responses to Generic Ltr 83-28, Item 2.2.1, Required Actions Based on Generic Implications of Salem ATWS Events
ML20246G2211989-08-18018 August 1989
Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits,Per NRC Info Notice 81-26.Util Should Ensure That Procedures Incorporate Applicable Dose Limits in 10CFR20
ML20246B7791989-08-11011 August 1989
Confirms 890808 Telcon Re Util Participation in NRC Regulatory Impact Survey on 891025.Feedback from Licensee Will Be Evaluated to Determine Changes to Be Made to NRC Regulatory Approach to Enhancing Safe Operation of Plants
ML20248E0131989-08-0101 August 1989
Forwards Safety Insp Rept 50-271/89-09 on 890531-0717. Results Discussed in Rept
ML20247N5051989-07-25025 July 1989
Forwards FEMA Rept of 871202-03 Exercise of Offsite Radiological Emergency Preparedness Plans.State of Offsite Emergency Preparedness Not Adequate to Assure Protection of Public Health & Safety
ML20245G1321989-07-21021 July 1989
Requests That Encl Ref Matl Be Furnished to NRC by 890821 for Senior Reactor Operator Licensing Exams Scheduled for Wk of 891023.Item 19 of Encl 1 Re Requalification Program Should Be Submitted by 890906 for Wk of 891106 Evaluation
ML20246N1331989-07-12012 July 1989
Forwards Safeguards Insp Rept 50-271/89-08 on 890515-19 & Notice of Violation
ML20246L2691989-07-10010 July 1989
Documents Results of Meeting 89-074 W/Util on 890510 in King of Prussia,Pa Re Various Operator Licensing Topics, Including Training Program Status,Related Mods & Requalification Program/Exam
ML20246B1371989-06-22022 June 1989
Forwards TE Murley Acknowledging Receipt of Ecology Ctr of Southern CA Petition,For Info
ML20245A6081989-06-15015 June 1989
Forwards Safety Insp Rept 50-271/89-07 on 890418-0530.No Violations Noted
ML20244D0251989-06-0707 June 1989
Forwards Safety Evaluation Accepting Util Second 10-yr Interval Inservice Insp Program Plan.Relief Granted to Requirements That License Determined to Be Impractical to Perform at Facility
ML20244B4521989-06-0202 June 1989
Forwards Maint Team Insp Rept 50-271/89-80 on 890227-0310 & Notice of Violation.Written Response Addressing Unresolved Item Re Drywell Paint Peeling Requested within 30 Days
IR 05000271/19890051989-05-31031 May 1989
Notifies of Error Identified in Insp Rept 50-271/89-05 Transmitted on 890504.No Deficiencies Identified in Licensee Implementation of Design Change to Comply W/ 10CFR50.62 Should Have Been Stated in Results Section
ML20247M0281989-05-26026 May 1989
Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre Petition Expressing Concerns Re 880309 Power Oscillation Event.Petitioner Request Under 10CFR2.206 Denied.W/O Encls
ML20247M8981989-05-24024 May 1989
Forwards Request for Addl Info Re 880727 Response to Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. Response Should Be Sent to Viking Sys,Intl at Listed Address
ML20247H9991989-05-24024 May 1989
Forwards Second Request for Addl Info Re Use of Frosstey Computer Code for LOCA Analysis.Response Requested within 45 Days of Receipt of Ltr
ML20247C6601989-05-19019 May 1989
Informs That Util Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Fulfills Requirement
ML20247K0841989-05-18018 May 1989
Forwards Safety Insp Rept 50-271/89-04 on 890320-23 & Notice of Violation
ML20246L9191989-05-0505 May 1989
Forwards Resident Safety Insp Rept 50-271/89-02 on 890214-0417.No Violations Noted.Programmatic/Performance Weaknesses Noted Re Implementation of Corrective Actions for Deficiencies
1990-09-07
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217N3901999-10-25025 October 1999
Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure
ML20217L8591999-10-21021 October 1999
Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation
ML20217M1181999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20217D9711999-10-13013 October 1999
Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure
ML20217C1501999-10-0707 October 1999
Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant
ML20212J7891999-10-0404 October 1999
Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant
ML20212J6501999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl
ML20212C1621999-09-17017 September 1999
Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System
ML20216F3171999-09-13013 September 1999
Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation
ML20211G4791999-08-27027 August 1999
Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core
ML20211E8841999-08-25025 August 1999
Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz
ML20211E1371999-08-20020 August 1999
Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified
ML20211H0851999-08-19019 August 1999
Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness
ML20216D7321999-07-26026 July 1999
Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations
ML20209G6931999-07-14014 July 1999
Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion
ML20209G2721999-07-14014 July 1999
Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station
ML20196G5241999-06-22022 June 1999
Responds to Re Changes to Vermont Yankee Guard Training & Qualification Plan,Rev 8,Errata A.No NRC Approval Is Required.Encl Will Be Withheld from Public Disclosure Per 10CFR73.21
ML20212J0541999-06-17017 June 1999
Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First
ML20195J7221999-06-14014 June 1999
Forwards Insp Rept 50-271/99-03 on 990329-0509.Two Severity Level IV Violations Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
ML20195E1441999-06-10010 June 1999
Ack Receipt of Correspondence to NRC Commissioners Re Vermont Yankee Nuclear Power Station.Correspondence Forwarded to Staff for Appropriate Action
ML20207G0921999-06-0404 June 1999
Forwards Insp Rept 50-271/99-04 on 990426-28.No Violations Noted.Insp Evaluated Performance of Emergency Response Organization During 990427,Vermont Yankee Nuclear Power Station full-participation Exercise
ML20196J3001999-06-0404 June 1999
Informs That NRR Reorganized,Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Was Created. Reorganization Chart Encl
ML20207E6001999-05-28028 May 1999
Forwards Operator Licensing Exam Rept 50-271/99-302 on 990510-11.Exam Addressed Areas Important to Public Health & Safety.Exam Developed & Administered Using Guidelines of NUREG-1021,Interim Rev 8.Both Applicants Passed Exam
ML20207B8201999-05-25025 May 1999
Informs Licensee of Individual Exam Results for Applicants on Initial & Retake Exams Conducted on 990510-11 at Licensee Facility.Without Encls
ML20206K1481999-05-0606 May 1999
Forwards Insp Rept 50-271/99-02 on 990215-0328.Three Severity Level IV Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
ML20206J9951999-05-0505 May 1999
Informs That Util Authorized to Administer Initial Written Exams to Applicants Listed on 990510.Region I Operator Licensing Staff Will Administer Operating Test
ML20206G6391999-05-0404 May 1999
Informs That Version of Holtec Intl Rept HI-981932 Marked as Proprietary Submitted by Util Will Be Withheld from Pubic Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended
ML20206E8641999-04-29029 April 1999
Forwards SER Concluding That Flaw Evaluation Meets Rules of ASME Code Concerning Util 990329 Request to Extend Reinspection Period for Jet Pump Riser Circumferential Weld Flaws Discovered During 1998 Refueling Outage
ML20206A6871999-04-22022 April 1999
Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co
ML20205P1551999-04-0909 April 1999
Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Insp Program Subject to Rev
ML20205K7461999-04-0808 April 1999
Advises That Info Contained in Holtec Intl Affidavit, Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20205K7531999-04-0707 April 1999
Discusses Alternative Proposal for Reexamination of Circumferential Welds in Plant Rpv.Nrc Has Determined That Alternative Proposal Meets Conditions in BWRVIP-05 Rept. Forwards Safety Evaluation
ML20205J0331999-03-31031 March 1999
Informs That on 980423 NRC Oi,Region I Field Ofc,Initiated an Investigation to Determine Whether Williams Power Corp Employee,Working at Vynp,Had Been Threatened & Eventually Fired in April 1998
ML20204J4321999-03-19019 March 1999
Forwards from Ve Quinn to Cl Miller Forwarding IEAL-R/85-11, Vermont Yankee Nuclear Power Station Site- Specific Offsite Radiological Emergency Preparedness Alert & Notification Sys QA Verification, for Info
ML20204D7481999-03-16016 March 1999
Forwards Insp Rept 50-271/99-01 on 990104-0214.No Violations Noted.Security Program Insp Found That Licensee Implementing Security Program That Effectively Protects Against Acts of Radiological Sabotage
DD-99-04, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-04) Has Expired.Commission Declined Review.Decision Became Final Action on 990308.With Certificate of Svc.Served on 9903121999-03-11011 March 1999
Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-04) Has Expired.Commission Declined Review.Decision Became Final Action on 990308.With Certificate of Svc.Served on 990312
ML20207L5591999-03-0101 March 1999
Requests Addl Info in Response to Questions 6,7 & 11 of RAI Re GL 96-06 Program at Vermont Yankee Nuclear Power Station
IR 05000271/19980141999-03-0101 March 1999
Forwards Request for Addl Info Based on Review of Util 961115 & 970313 Responses to GL 96-05 & Insp Rept 50-271/98-14 of GL 96-05 Program at Vermont Yankee Nuclear Power Station
ML20207L5471999-02-26026 February 1999
Forwards Request for Addl Info for Ongoing Review of Vermont Yankee IPEEE Submittal Dtd 980630.RAI Related to Fire, Seismic,Internal Flooding & High Wind,Flood & Other External Event Areas
ML20203H9791999-02-18018 February 1999
Forwards SER Accepting Licensee 970123 Info Supporting Util Determination That Exam Coverage Achieved During Reactor Pressure Vessel Shell Weld Insp Constitutes Alternative Which Provides Acceptable Level of Quality & Safety
ML20203H7631999-02-12012 February 1999
Responds to 981120 Request for NRC Authorization to Perform Alternative Testing to That Specified by ASME BPV Code & Asme/Ansi, Code for Operation & Maint of Npps. Reviewed & Agreed That 990114 SER Needs Revision
ML20203H8431999-02-11011 February 1999
Refers to 990201 Request for Withdrawal of 980501 Amend Request.Amend Request Superceded with Another Proposed Change to Ts.Informs That Commission Filed Encl Notice of Withdrawal of Application for Amend to FOL with Ofc of Fr
ML20203D1691999-02-0505 February 1999
Acknowledges Inputs,Comments & Requests for Action Re Vermont Yankee Nuclear Power Plant,Provided by Electronic Mail Messages Dtd 990110-13
ML20202G2611999-01-28028 January 1999
Forwards Insp Rept 50-271/98-14 on 981122-990104.No Violations Noted.Nrc Initial Review of Scram Discharge Vol Drain Valve Failures Indicates That Licensee Design Change Process Was Not Effective
ML20199K7081999-01-21021 January 1999
Forwards Corrected SE for Amend 163 Issued to FOL DPR-28 on 981228.Determined That Pages 2 & 3 of SE Required Clarification
ML20199K6891999-01-20020 January 1999
Informs of Completion of Review of YAEC-1339 Re Allowing Use of FIBWR2 to Validate Reload Analyses Which Include New Fuel Rods & Varied Water Tube Designs.Forwards SE Concluding That Use of YAEC-1339 at Vermont Yankee NPP Acceptable
ML20202C9551999-01-20020 January 1999
Informs That Licensee Has Been Authorized to Administer Initial Written Exam to Applicants as Listed on 990122. Operator Licensing Staff Will Administer Operating Test to Applicants
ML20199L5901999-01-14014 January 1999
Forwards SER Accepting Util 981120 Request for Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maintenance of Nuclear Power Plants
IR 05000271/19970131998-12-23023 December 1998
Forwards Insp Rept 50-271/97-13 on 981011-1121.No Violations Noted.Radioactive Liquid & Gaseous Effluent Control Programs Were Considered to Be Well Implemented
ML20198S1661998-12-17017 December 1998
Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5)
1999-09-30
[Table view] |
Text
, y-b i
FEB 0 8 1988 Docket No. 50-271
,
Vermont Yankee Nuclear Power Corporation
'
ATTN: Mr. Warren P. Murphy Vice President and Manager of Operations RD 5, Box 169 Ferry Road Brattleboro, Vermont- 05301 Gentlemen:
Subject: Inspection 50-271/87-15 This refers to your letter dated December 10, 1987, in response to our letter dated October 6, 198 Thank you for infonning us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed progra Your cooperation with us is appreciate
Sincerely, Original Signed By:
Wdliam J. Lazarus
.
Thomas T. Martin, Director Division of Radiation Safety and Safeguards cc:
J. Gary Weigand, President and Chief Executive Officer J. P. Pelletier, Plant Manager John DeVincentis, Vice President, Yankee Atomic R. W. Capstick, Licensing Engineer Cort Richardson, Vermont Public Interest Research Group, In Gerald Tarrant, Commissioner, Vermont Department of Public Service Peter W. Agnes, Assistant Secretary of Public Safety, Comonwealth of Massachusetts Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New Hampshire State of Vermont Coninonwealth of Massaschusetts lgg21JggfKg$ [
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"0FRCiM !EC0!!D COPY"
. SI_ JOA,
.
.
'
FEB 0 s 1989 '
Vermont Yankee Nuclear 2 Power Corporation bec: . '
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
Section' Chief, DRP G.-Grant, SRI, Vermont Yankee M. Fairtile, PM, NRR Robert J. Bores, DRSS a
.
T DL RI:DRSS RI:DRSM RI:D '
Loesch Shanbaky Bella 1/ti /88 1/7L/88 'J/ y/88 0FFICIAL RECORD COPY rl vt. yankee 87-15 1/19/88
,
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