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| {{Adams | | {{Adams |
| | number = ML20198D220 | | | number = ML20207J877 |
| | issue date = 05/13/1986 | | | issue date = 07/23/1986 |
| | title = Insp Rept 50-267/86-08 on 860303-07.Violations & Deviation Noted:Critical Exam of Documents by Plant Operations Review Committee Neglected,Design Changes Not Incorporated Into Change Notice 1798A & Annual Safety Rept Not Sent to NRC | | | title = Ack Receipt of 860617 & 24 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/86-08 |
| | author name = Bennett W, Jaudon J, Mcneill W, Skow M | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Williams R |
| | addressee affiliation = | | | addressee affiliation = PUBLIC SERVICE CO. OF COLORADO |
| | docket = 05000267 | | | docket = 05000267 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-267-86-08, 50-267-86-8, NUDOCS 8605230190 | | | document report number = NUDOCS 8607290281 |
| | package number = ML20198D195 | | | package number = ML20207J881 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 6 | | | page count = 1 |
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| APPENDIX C U.S. NUCLEAR REGULATORY COMMISSION
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| | UUL 2 31986 In Reply Refer To: |
| | Docket: 50-267/86-08 Public Service Company of Colorado ATTN: Robert 0. Williams, J Vice President, Nuclear Operations P. O. Box 840 Denver, Colorado 80201-0840 Gentlemen: |
| | Thank you for your letters of June 17, 1986, and June 24, 1986, in response to our letters and Notice of Violation dated May 19, 1986. We have reviewed your reply and find it responsive to the concerns raised.in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be raaintaine |
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| ==REGION IV==
| | Sincerely, |
| NRC Inspection Report: 50-267/86-08 License: DPR-34 Docket: 50-267 Licensee: Public Service Company of Colorado (PSC)
| | ** Original Signed by: |
| P. 0. Box 840 Denver, Colorado 80201-0804 Facility Name: Fort St. Vrain Nuclear Generating Station Inspection At: Fort St. Vrain Nuclear Generating Station, Platteville, Colorado Inspection Conducted: March 3-7, 1986
| | D. E. GAGLIARDO". |
| / $!/3 8 Inspector:k M[ E.(Skpw, Project Engineer, ProjectDate Sectis A, Reactor Projects Branch (paragraphs 1, 2, 3, 4, 6, and 7)
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| Inspector: MA/ M [ 8d R.( Bfnnett, Project Engineer, Project
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| Date Sectibn A, Reactor Projects Branch (paragraphs 1, 2, 4, 5, 6, and 7)
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| Inspector: _
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| , adj (/Y) 3$
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| y. cNeill, Project Engineer, Project Date L L Sec ion A, Reactor Projects Branch (p ragraphs 1, 2, 4, 5, 6, and 7)
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| Approved: _ ms -A 4~ 3 8
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| /). udon, Chief, Project Section A, Dat6 L Rea or Projects Branch
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| . .. | | J. E. Gagliardo, Chief Reactor Projects Branch cc: |
| -2-Inspection Summary Inspection Conducted March 3-7, 1986 (Report 50-267/86-08)
| | J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 191' |
| Areas Inspected: Routine, unannounced inspection of the Quality Assurance Program, Onsite Review Committee, Offsite Review Committee, Offsite Support Staff, and Tests and Experiments Progra Results: Within the areas inspected, four violations and one deviation were identified (paragraphs 3 and 5).
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| | Platteville, Colorado 80651 L. Singleton, Manager, Quality. |
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| | | Assurance Division * |
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| | (same address) |
| . . | | Colorado Radiation Control Program Director bec to DMB-(IE01) |
| -3-DETAILS 1. ' Persons Contacted PSC
| | bcc distrib'. by RIV: |
| *C H. Fuller, Station Manager
| | RPB DRSP Resident Inspector- - |
| *L. W. Singleton, Manager, Quality Assurance
| | R. D. Martin, RA Section Chief (RPB/A) *RSB Secti Chief (RSB/ES) R&SPB MIS S :em RSTS Operator RIVf . |
| *M. J. Ferris, QA Operations Manager
| | C/R A' RPB J JEGagliddo C)\ |
| *R. L. Craun, Nuclear Site Engineering Manager
| | 7/ /86 / G/ |
| *J. M. Gramling, Supervisor, Nuclear Licensing Operations
| | JPfudon:cnm 7/3) /g() g B607290281 PDR 860723 f G |
| .D. Warembourg, Manager, Nuclear Engineering J. W. Gahm, Manager, Nuclear Production T. C. Prenger, QA Services Manager M. Lehr, QA Engineering Supervisor P. F. Moore, QA Technical Support Supervisor D. Frye, Nuclear Licensing Specialist J. Stufflebeam, Executive Secretary /NFSC Clerk M. Holmes, Nuclear Licensing Manager J. Johns, Supervisor, Nuclear Licensing Engineering 0. Clayton, Technical Services Engineer J. Eggebroten, Superintendent, Technical Services Engineering D.-Webber, Staff Assistant to Station Manager W. Crain, Superintendent of Maintenance T. Borst, Support Services Manager / Radiation Protection Manager P. Collins, PORC Clerk The NRC inspectors also contacted other licensee personnel including administrative, clerical, and operations personne * Denotes those attending the exit intervie . Quality Assurance Annual Review The purpose of this inspection was to ascertain whether the licensee is implementing a Quality Assurance (QA) program that is in conformance with regulatory requirements, commitments, and industry guides and standard This inspection objective was accomplished by inspection in the following areas: Tests and Experiments Program, Onsite Review Committee, Offsite Review Committee, and Offsite Support Staff. These areas are addressed in this report in paragraphs 3 through 6. The QA program was found to not have changed significantly since the last inspection of this area in regard to its organization, personnel and staffing. A number of QA program procedures have been revised and reformatted to improve QA effectiveness. Within this area, no violations, deviations, or unresolved items were identifie ,
| | ADOCK 05000267 PDR |
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| -4-3. Onsite Review Committee The purpose of this inspection was to provide a functional review of the Onsite Review Committee to determine that the safety-related responsibilities of the committee are being adequately performed. The Onsite Review Committee for Ft. St. Vrain is the Plant Operations Review Committee (PORC). The NRC inspector reviewed Technical Specification Section Number AC 7.1.2; the PORC Charter, Issue 1, dated November 23, 1983; and the minutes for several PORC meetings. In addition, the NRC inspector interviewed some PORC members, the PORC clerk and a staff assistant concerning POR The NRC inspector found that the PORC Charter appears to meet the requirements of the Technical Specifications. Those documents that required a PORC review were sent to PORC for review. It was noted that the minutes of the PORC meeting were prepared prior to the meeting by the PORC clerk; the minutes included a brief description of each item to be reviewed by PORC. The documents to be reviewed and copies of the draft minutes were provided at the PORC meeting. During discussions with PORC members, the NRC inspector found that documents requiring review by PORC were not provided to members prior to the PORC meeting. At the meeting attended by the NRC inspector, the PORC Chairman read the description of each item from the draft minutes to the PORC committee. If there were questions from the committee, the document undergoing review was read by the Chairman and/or one or more of the other members or alternates of the POR The NRC inspector observed that none of the documents were individually examined by all of the personnel in attendance. Also, he observed that several documents were not examined by any members of the committee during the meeting. If PORC took any actions, reached any conclusions, or made any other changes to the draft minutes, the PORC clerk retyped the minutes as change The PORC Charter defines review as a " deliberate, critical examination . . . ." The NRC inspector determined the those documents identified did not receive a deliberate, critical examinatio This is an apparent violation (50-267/8608-01).
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| The number of PORC meeting attendees was found to meet the minimum quorum required by the Technical Specifications. By memo dated October 18, 1985, the PORC Chairman designated four alternate chairmen. The memo also identified which members and designated alternate members would attend each daily PORC meeting. Each day of the week had a different chairman and four attendees. Only two members were scheduled to attend more than one meeting each week, and that was for only two meetings. Technical Specification AC 7.1.2, Section 2, discusses PORC alternate It states, in part, "An alternate chairman . . ,, if required, shall be appointed in writing by the PORC Chairman to serve in the absence of a chairman . . .
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| ." The NRC inspector concluded that the designation of four alternate chairmen, each preassigned to a specific day of the week, is an apparent violation of the Technical Specification (50-267/8608-02). | |
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| Additionally, the licensee is committed in the Updated FSAR, Revision 3, to the provisions of ANSI N18.7-1972, Administrative Controls for Nuclear
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| -5-Power Plant Section 4.5 of ANSI N18.7-1972 states that PORC ". . .
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| should provide . . . continuing review of the plant operation . ...
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| The NRC inspector concluded that a committee whose personnel substantially change on a daily basis does not provide for a continuing review of plant operations. This is an apparent deviation from the above commitment (50-267/8608-03).
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| 4. Offsite Support Staff The purpose of this inspection was to ascertain whether the offsite support staff functions are performed by qualified personnel in accordance with licensee approved administrative controls. The NRC inspectors reviewed the Nuclear Guidelines and Policies Manual, organization charts, and interviewed selected personnel. In regard to offsite support staff, there appeared to be a sufficient staff of qualifled personnel to perform their assigned functions. Personnel appeared to be aware of their functions and responsibilities. Administrative controls were found in place which describe the responsibilities, authorities, and lines of communication for the offsite support staf Those controls or procedures addressed design, quality assurance, procurement and interfaces between onsite and offsite staff No violations or deviations were note . Tests and Experiments Program The purpose of this inspection was to ascertain whether the licensee is implementing a QA program relating to the control of test and experiments that is in conformance with regulatory requirements. In this regard, the NRC inspectors reviewed Licensee Procedures Q-3, Q-11, TSP-21, and four of the most recent changes to Technical Specifications. The NRC inspectors reviewed the licensee's 10 CFR 50.59 Report Submittal, dated July 22, 1985. A sample of four Change Notices (CNs) and five tests were selected from that submittal for further review. The NRC inspectors review of those tests and CNs determined that adequate controls were in effect, safety evaluations were made, and that PORC and Nuclear Facilities Safety Committee (NFSC) reviews were performe However, one problem was found that related to Change Notices. Deviation Request DR-85-35-1-H was written against CN 1902 on March 25, 1985. It discussed a conflict in cable termination instructions with conditions found in the fiel The disposition provided for making the changes required in the field and stated, ". . . a document update will be incorporated in CN-1798A." A review by the NRC inspectors and the licensee of CN-1798A did not indicate that the document update had been accomplished. This is an apparent violation of 10 CFR 50, Appendix B, Criterion III (50-267/8608-04).
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| During review of the latest five 10 CFR 50.59 annual submittals, the NRC inspectors noted a variation of submittal dates. Procedure TSP-21, Issue 2, dated April 21, 1982, required that reports be submitted prior to March 1 of each year. The 1983 report was submitted on March 23, 1984, and the 1984 report was submitted on July 22, 1985. The 1985 report had
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| -6-not been submitted as of this inspection. The licensee stated that the responsibility for preparing the report was shifted from Technical Services to Licensing for the 1984 report and that the decision was made to submit the report at the same time as the FSAR update in July. A change or deviation to TSP-21 was not made to support that decisio Additionally, the licensee stated that TSP-21 was deleted on March 30, 1985, and that a licensing procedure pertaining to the 10 CFR 50.59 report had not been issued as of this inspection. The failure to submit reports at the times required by the procedure is an apparent violation (50-267/8608-05).
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| 6. Offsite Review Committee The purpose of this inspection was to determine if the functions of the offsite review are being performed in accordance with regulatory requirements. The licensee refers to the offsite review committee as the Nuclear Facilities Safety Committee (NFSC). In this regard, Technical Specification AC 7.1.3 and the NFSC Charter, Issue 4, dated January 2, 1984, were reviewed. The NRC inspectors reviewed the minutes of NFSC meetings numbered 94, 96, and 99 through 103, reviewed selected portions of the documents the NFSC reviewed, reviewed NFSC audit reports associated with meetings 101 and 103, and interviewed selected members of the NFSC and the NFSC clerk. In addition, items selected during the PORC and Tests and Experiments portions of this inspection were followed upon during the NFSC inspection. It was verified that NFSC reviewed PORC minutes and safety evaluations. The membership of NSFC was verified. The inspectors found that the NFSC appeared to function in an effective manner. For example, NSFC challenged the PORC evaluation of CN-1876 with regard to an unreviewed safety question. Subsequently, the new equipment was placed in an out-of-service status and an independent review was ordered to resolve the question. Documents for review by the committee were distributed to members with sufficient lead time that questions and comments could be solicited and returned to the NFSC clerk. These questions and comments were then directed to cognizant personnel. Those personnel in turn presented a discussion at the NFSC meeting. The questions and comments were normally resolved in this manner. The minutes were not used as an agenda as with PORC, but were taken at the meetings by the clerk. While the minutes of the NFSC meetings appeared to the more complete than the PORC minutes, the NRC inspectors suggested that the minutes include a brief explanation of the resolution of the comments and questions. This would document the position accepted by the NFSC. No violations or deviations were identified in this portion of the inspectio . Exit Interview An exit interview was held on March 7, 1986, with those personnel denoted in paragraph 1 of this report. The NRC senior resident inspector also attended this meeting. At the meeting, the scope of the inspection and findings were summarized.
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20205G8771999-03-26026 March 1999 Forwards Copy of Cover Page from Fort St-Vrain Welding Manual,Which Had Been Listed as Encl on Page 4 of 990325 Reply to EA 98-081.Cover Page Had Been Inadvertently Left Out with Original Reply ML20197H8811998-12-0101 December 1998 Forwards Proposed Change to Fsv ISFSI Physical Protection Plan in Which Commitment Is Made to Provide Feature to Security Posture for Facility ML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198K1931997-10-10010 October 1997 Provides Supplemental Info in Support of Util Proposed Rev to Physical Security Plan for Plant Plant Isfsi.Plan Withheld,Per 10CFR2.790(d) & 10CFR73.21 ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141F3521997-05-14014 May 1997 Forwards Proposed Issue 4 of Physical Security Plan for Fort St Vrain ISFSI for Review & Approval.Encl Withheld,Per 10CFR2.790(d) ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan ML20138G2701997-04-28028 April 1997 Provides Response to NRC Comments Re Proposed Sampling & Survey Plan for Fsv Effluent Pathway.Response Documents Fsv Liquid Effluent Discharge Pathway Areas Are Acceptable for Release for Unrestricted Use IAW Draft NUREG/CR-5849 ML20148D4651997-04-24024 April 1997 Forwards Revised Interim Ltr Rept Which Describes Procedures & Results of Confirmatory Survey of Group E Effluent Discharge Pathway Areas at Fsv Station NUREG/CR-5849, Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-58491997-04-23023 April 1997 Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-5849 ML20138B0511997-04-22022 April 1997 Forwards Copy of Proposed Amend to Fsv NPDES Permit, Wastewater Discharge Permit CO-0001121 Requested to Support Repowering Activities,Iaw Section 3.2.d of Fsv Non-Radiological Ts,App B to License DPR-34 ML20140E1061997-04-10010 April 1997 Forwards Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co ML20137S4481997-04-0808 April 1997 Informs That Decommissioning Activities at Fsv Are Complete & NRC Issued Exemption from Requirements of 10CFR50.54(w) in .Property Damage Insurance Policy Is Maintaned to Protect Fsv balance-of-plant Assets ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S5421997-04-0707 April 1997 Forwards Final Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Fort St Vrain Nuclear Station ML20148D5951997-04-0404 April 1997 Forwards Confirmatory Survey for Fsv Nuclear Station, Psc,Platteville,Co, Final Rept ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20148D5811997-03-26026 March 1997 Forwards Confirmatory Survey Plan for Group E Effluent Discharge Pathway Areas at Fsv Nuclear Station, Covered in Final Survey Rept,Vol 6 ML20137G7361997-03-25025 March 1997 Requests Addl Time for Util to Respond to NRC Comments in Re Financial Assurance Mechanism for Fort St Vrain Decommissioning Costs ML20137G9521997-03-24024 March 1997 Forwards Quarterly 10CFR50.59 Rept for Period 961201-970228 Re Changes,Tests & Experiments for Fort St Vrain Decommissioning ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20137C0181997-03-18018 March 1997 Documents That No Personnel Has Received Radiation Exposure at Fsv in 1997 or at Any Time Subsequent to ML20137C0061997-03-18018 March 1997 Documents That There Have Been No Activities Involving Release of Radioactive Matls from Fsv Nuclear Station That Potentially Could Have Affected Environ,Subsequent to Previous Radiological Envion Operating Rept ML20136G1201997-03-11011 March 1997 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1996 & Jan-Mar 1997. All Effluent Releases Completed as of 960703.Repts on Activities After 960703 Reflect Disposal of Solid Waste ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135D7891997-02-27027 February 1997 Forwards Responses to Comments Re Fort St Vrain Final Survey Rept ML20135D9531997-02-27027 February 1997 Forwards Copy of Amend to Util Npdes,Wastewater Discharge Permit CO-0001121,which Clarifies That Monitoring of Farm Pond Outlet Required When Industrial Wastewater Being Discharged Through Upstream Goosequill Ditch ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20134D1551997-01-31031 January 1997 Forwards Util Responses to NRC Comments Provided in NRC Ltr Re Sampling & Survey Plan Used for Final Radiological Survey of Liquid Effluent Pathway at Ft St Vrain ML20134C8481997-01-30030 January 1997 Forwards Draft Confirmatory Survey Rept for Fsv Nuclear Station,Psc,Platteville,Co Providing Info on Essap Activities on 960930-1003 ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20133E0481997-01-0202 January 1997 Forwards Comments to Fsv Nuclear Station, Decommissioning Project Final Survey Rept (Volumes 4-11), for Consideration ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20132F2841996-12-19019 December 1996 Forwards Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments Affecting Decommissioning of Plant,Covering Period of 960901-1130 ML20133A8591996-12-16016 December 1996 Forwards Original & Copy Transcripts of Public Hearing,Held on 961203 in Platteville,Co Re Decommissioning & License Termination of Util Ft Saint Vrain Nuclear Generating Station ML20133N0011996-12-0404 December 1996 Recommends That NRC Require License to Modify Submission of Unexecuted Draft Trust Agreement Remaining Decommissioning Costs for Ft St Vrain Nuclear Generating Station in Listed Ways ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20135A5861996-11-25025 November 1996 Submits Suppl Info Re Annual Environ Rept for 1995 Operation of Fsv ISFSI ML20135A6361996-11-20020 November 1996 Submits Copy of Describing Discharge Practices for Groundwater Seeping Into Fsv'S Reactor Building Sump ML20134L4721996-11-14014 November 1996 Notifies NRC That Util Adopted Fsv ISFSI Emergency Response Plan to Direct Emergency Response for Radiological Accidents Occuring at Site,Until 10CFR50 License Is Terminated ML20134F4351996-10-30030 October 1996 Forwards Sections 1,2,6 & 8 from Survey Packages F0015, F0039 & F0126 & Sections 1,2 & 6 from Survey Package F0115 to Support on-site NRC Insp ML20134G5991996-10-30030 October 1996 Forwards Volumes 1-12 to Final Survey Rept for Groups A,B,C Rev 1,D Rev 1,E,F Rev 1 & G-J for NRC Approval in Support of Forthcoming Request for Termination of Fsv 10CFR50 License ML20133D7691996-10-22022 October 1996 Forwards Preliminary Rept Re Orise Support of NRC License Insp at Fsv on 960930-1003 ML20136B1411996-10-15015 October 1996 FOIA Request for Documents Re NOV Addressed to Scientific Ecology Group Re NRC Insp Rept 50-267/94-03 & OI Investigation Repts 4-94-010 & 4-95-015 ML20128M6181996-10-0404 October 1996 Forwards Ltr from PSC to Co Dept of Public Health & Environ Describing Monitoring Practices at Plant ML20128G8041996-10-0101 October 1996 Forwards Fsv Decommissioning Fire Protection Plan Update 1999-03-26
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl ML20247K7741989-09-15015 September 1989 Informs That Partial Review of 890125 & 0320 Submittals Re Helium Circulators complete.Ten-yr Insp Recently Conducted on Circulator C-2105.Insp Revealed No Defects or Unacceptable Conditions ML20247K4141989-09-15015 September 1989 Advises That Tech Specs Re Upgrade Program,Requested in NRC ,Must Be Approved by NRC Before Defueling ML20247D4691989-09-11011 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-15 ML20247H3431989-09-0808 September 1989 Ack Receipt of Informing NRC of Status of Security Sys Upgrades ML20247H2891989-09-0606 September 1989 Concurs W/Util 890714 Request for Changes to Basis for Limiting Condition for Operation 4.2.2 of Facility Tech Specs Re Statement About Automatic Initiation of Backup Bearing Water Sys ML20247B2661989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executives Meeting on 890818 in Arlington,Tx.Topics Discussed Included, Improving Communications,Salp Process in Region IV & Enforcement.List of Attendees & Agenda Encl ML20246J2911989-08-30030 August 1989 Forwards Amend 72 to License DPR-34 & Safety Evaluation. Amend Imposes Early Shutdown by Limiting Reactor Power to 2% of Full Power After 900630 ML20246E5941989-08-21021 August 1989 Forwards Insp Rept 50-267/89-14 on 890710-14 & Notice of Violation.Two Separate Findings of Missing Info in Semiannual Effluent Rept,Resulting in Failure to Satisfy Tech Spec Administrative Requirements Identified ML20246A2651989-08-16016 August 1989 Forwards Insp Rept 50-267/89-13 on 890626-30.Violations Noted But No Citation Issued.Expresses Concern About Status of Model FSV-1 & FSV-1A Shipping Casks ML20245J3511989-08-14014 August 1989 Forwards Amend 71 to License DPR-34 & Safety Evaluation. Amend Revises Provisions in Tech Specs Re Radiological Effluents ML20246A6841989-08-14014 August 1989 Forwards Exam Rept 50-267/OL 89-02 Administered During Wk of 890710 ML20245J5651989-08-10010 August 1989 Forwards Insp Rept 50-267/89-17 on 890717-21 & Notice of Violation ML20245H3891989-08-0808 August 1989 Forwards Insp Rept 50-267/89-12 on 890601-0715 & Notice of Violation ML20245J4421989-08-0808 August 1989 Forwards Safety Evaluation,Responding to Issues Re Tech Spec Upgrade Program & Defueling of Plant.Requests That Tech Spec Changes Be Requested within 30 Days of Ltr Date ML20248E0041989-08-0303 August 1989 Forwards Team Insp Rept 50-267/89-08 on 890522-26 & Notice of Violation.Response Should Include Corrective Actions Taken or Planned to Ensure That Reactor Water Cooling Sys 46 Operated as Designed IR 05000267/19890071989-07-28028 July 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-07 ML20247N7581989-07-26026 July 1989 Discusses Licensee 890616 Request Re Changes to Previous Commitments Concerning Plans to Shut Down Plant.Commitment 2c to Be Subj of Separate Correspondence.Commitment 7 to Be Considered Not Applicable.W/Revised Summary of Commitments ML20247M4281989-07-25025 July 1989 Responds to 890120 & 0616 Requests for Relief from Requirements of Fuel Surveillance Program.Nrc Considers Util Obligations Under Fuel Surveillance Program Will Terminate W/Planned Shutdown of Reactor by 900630 ML20247M4521989-07-25025 July 1989 Forwards Request for Addl Info Re Reactor Defueling.Info Needed within 30 Days of Ltr Date ML20247L9801989-07-14014 July 1989 Discusses 890711 Meeting in Region IV Ofc Re Introduction of AC Crawford & Future Plans for Facility.Slides Presented at Meeting & List of Attendees Encl ML20247L5971989-07-14014 July 1989 Forwards Insp Rept 50-267/89-15 on 890623-27 & Notice of Violation.Response Should Describe Corrective Actions to Assure That safety-related Changes Introduced by Other Parts of Organization Are Properly Incorporated Into Procedures ML20246M6941989-07-11011 July 1989 Forwards Agenda for 890808 Meeting of Senior Util Executives Sponsored by Region IV at Univ of Texas.Map to Facilitate Access to Meeting Room Also Encl ML20246F4851989-07-10010 July 1989 Discusses Util Re Alternative Compensatory Measures Instituted,Per Fire Protection Operability Requirement-16.Proposed Guidance Adequate ML20246J2791989-07-0707 July 1989 Forwards Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable. Technical Evaluation Rept Also Encl ML20245G4491989-06-22022 June 1989 Forwards Exam Rept 50-267/OL-89-01 Administered During Wk of 890523 ML20245G4831989-06-20020 June 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-06 ML20245F8161989-06-20020 June 1989 Proposes Meeting in Region IV to Discuss SALP Process in Region Iv,Improving Communication W/Licensee Mgt,Region IV Enforcement Philosophy,How to Improve Safety Performance & Topics Util Wishes to Discuss ML20245A2201989-06-15015 June 1989 Forwards Insp Rept 50-267/89-10 on 890501-31.No Violations or Deviations Noted ML20244C1221989-06-0808 June 1989 Forwards Insp Rept 50-267/89-07 on 890319-0430 & Notice of Violation ML20248B8741989-06-0505 June 1989 Forwards Draft Reg Guide, Assuring Availability of Funds for Decommissioning Nuclear Reactors, Task CE 025-4,for Use in Preparing Preliminary Decommissioning Plan for Plant 1990-08-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20236R9191998-07-20020 July 1998 Ltr Contract:Mod 4 to Task Order 27, Task Area No 4 of Basic Contract - Fort St Vrain Insp Under Contract NRC-02-95-003 ML20199H8141997-11-21021 November 1997 Responds to Requesting Clarification as to Whether Increase in Tritium & Iron-55 Contamination Limits That Were Approved for Plant Apply to All Licensees ML20198H5601997-09-16016 September 1997 Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety ML20141C8611997-05-0909 May 1997 Informs of Approval of Fsv Final Survey Rept & Effluent Pathway Survey Plan & Supporting Analysis ML20141K9881997-05-0505 May 1997 Forwards Amend 89 to License DPR-34 & Supporting Safety Evaluation.Amend Designates All Elements of Approved Decommissioning Plan as License Termination Plan NUREG/CR-5849, Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-58491997-04-23023 April 1997 Requests That Licensee Provide Evidence That Average Contamination Levels in Group E Effluent Discharge Pathway Areas Meet Averaging Criteria in Draft NUREG/CR-5849 ML20137S1691997-04-0707 April 1997 Fifth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App K ML20137S0821997-04-0707 April 1997 Forwards Insp Rept 50-267/97-01 on 970310-11.No Violations Noted ML20137R6921997-04-0404 April 1997 Informs of Approval for Request for Addl 45 Days to Remedy Deficiencies Identified in NRC Re Financial Assurance Mechanism for Fsv Decommissioning Costs ML20137J8051997-03-31031 March 1997 Third Partial Response to FOIA Request for Documents.Records in App F Encl & Will Be Available in Pdr.App G & H Records Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20137H1131997-03-24024 March 1997 Second Partial Response to FOIA Request for Documents. Forwards Documents Listed in App D.Documents Also Available in Pdr.Documents Listed in App E Withheld in Part (Ref FOIA Exemption 6) ML20136B1331997-02-28028 February 1997 First Partial Response to FOIA Request for Documents. Documents Listed in App a Already Available in Pdr.Forwards App B Documents.App C Documents Being Withheld in Entirety (Ref FOIA Exemption 5) ML20135A8711997-02-14014 February 1997 Requests That Encl Deficiencies Identified in Financial Assurance Mechanism for Fort St Vrain Decommissioning Cost Be Addressed within 45 Days ML20133L4961997-01-0707 January 1997 Forwards Comments That Need to Be Resolved Before Final Approval of Util Submittal Entitled, Proposed Sampling & Survey Plan for Effluent Pathway,Ft St Vrain Final Survey Program ML20132G0421996-12-23023 December 1996 Forwards Insp Rept 50-267/96-05 on 961203-05.No Violations Noted ML20135B3861996-11-25025 November 1996 Informs That NRC Reviewed Util 961114 Submittal (P-96096) Entitled, Fort St Vrain Final Emergency Response Plan, & Meets Requirements of 10CFR50.54(q) ML20128G1421996-09-25025 September 1996 Advises NRC Approved Decommissioning Plan, Impact Of... Fsv Final Decommissioning, Satisfies All Elements of License Termination Plan as Required by Rev to Reactor Decommissioning Rule 10CFR50.82(a)(9) ML20136B2561996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Falsification of Radiation Survey Records.Revised NOV Encl ML20136B2731996-04-0202 April 1996 Informs That NOV Issued on 951030 Revised to Reflect NRC Reanalysis of Info Re Util Failure to Assure Compliance w/10CFR50.9 Concerning Accuracy of Radiation Survey Records. Revised NOV Encl ML20136B3241996-04-0202 April 1996 Informs That NRC Will Be Withdrawing NOV ,based on Reevaluation of Evidence Provided & Response to NOV ML20058G9671993-12-0707 December 1993 Ack Receipt of Ltrs of 931110,responding to Notice of Violation & Proposed Imposition of Civil Penalty Issued on 931013 IR 05000267/19930021993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Deviations Noted in Insp Rept 50-267/93-02. Deficiency Determined to Have Contributed to 930527 Crane Overload Event IR 05000267/19930011993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/93-01 ML20056G0041993-06-25025 June 1993 Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process ML20128D6931992-12-0101 December 1992 Forwards Exemption from Requirement in 10CFR50,app E,Section IV.F.2 to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise. EA & SE Also Encl ML20198C7511991-06-25025 June 1991 Suggests That Region Iv/Senior Util Executive Conference Be Held During Month of Sept 1991 in Arlington,Tx to Provide Open Forum for Candid Discussions Limited to Topics of General Interest & Not Pertain to Plant Specific Issues ML20058K0231990-11-30030 November 1990 Forwards Insp Rept 50-267/90-17 on 901001-1109.No Violations or Deviations Noted ML20062H8131990-11-29029 November 1990 Forwards Partially Withheld Insp Rept 50-267/90-18 on 901022-26 & Notice of Violation ML20062H2041990-11-21021 November 1990 Forwards Insp Rept 50-267/90-19 on 901015-19.No Violations or Deviations Noted ML20058J0121990-11-16016 November 1990 Forwards Insp Rept 50-267/90-20 on 901029-1102.Violations Noted But Not Cited IR 05000267/19900161990-10-30030 October 1990 Discusses Insp Rept 50-267/90-16 on 900928 & 901018 Enforcement Conference & Forwards Notice of Violation ML20062B3971990-10-15015 October 1990 Forwards Insp Rept 50-267/90-14 on 900801-0930.No Violations or Deviations Noted ML20058A0941990-10-12012 October 1990 Confirms 901018 Enforcement Conference in Region IV Ofc Re Violations & Radiation Program Weakness Noted in Insp Rept 50-267/90-16.Proposed Agenda Encl ML20059N8231990-10-0303 October 1990 Forwards FEMA Final Radiological Emergency Preparedness Exercise Rept, for 891115 Exercise.One Deficiency & Several Areas Requiring Corrective Actions Identified ML20059C1381990-08-24024 August 1990 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 900605 Application,For Info ML20056B4021990-08-20020 August 1990 Forwards Insp Rept 50-267/90-11 on 900601-0728.No Violations or Deviations Noted ML20058M8681990-08-0808 August 1990 Forwards Insp Rept 50-267/90-13 on 900709-13.No Violations or Deviations Identified.Licensee Commitment to Revise Manual Dose Assessment Procedure to Incorporate Appropriate Unit Conversion Factor,Noted ML20056A3601990-07-31031 July 1990 Forwards Insp Rept 50-267/90-10 on 900611-15.No Violations or Deviations Noted.Actions Taken Re Previously Identified Insp Findings & Status Examined ML20055J3951990-07-31031 July 1990 Ack Receipt of 900713 Request for Exemption from FY90 Annual Fee Requirements of 10CFR171.Annual Fee Will Not Be Billed ML20059D1281990-07-30030 July 1990 Ack Receipt of 900713 Request for Full Exemption from FY90 Annual Fee Requirements of 10CFR171 for Plant.Annual Fee Will Not Be Billed While Request Under Review ML20055G5921990-07-19019 July 1990 Agrees W/Removal of B Helium Circulator,Per Requesting NRC Concurrence.Solution to Correct Leakage Problem by Removal of Circulator Acceptable ML20055D2031990-06-26026 June 1990 Ack Receipt of 900525 Response to 900402 Emergency Preparedness Insp Rept & 900427 Notice of Violation ML20055C8021990-06-18018 June 1990 Concludes That Financial Info Forwarded by Meets Requirements of 10CFR140.21 ML20248H7751989-10-0303 October 1989 Forwards Insp Rept 50-267/89-19 on 890821-26 & 29-30.No Violations or Deviations Noted IR 05000267/19890081989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-08. Understands That Revised Flow Test Surveillance Procedures Performed on 890821 & 0921 & cross-connect Valves Stroked IR 05000267/19890171989-10-0202 October 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-267/89-17. Implementation of Corrective Actions Will Be Examined During Future Insps ML20248B2971989-09-26026 September 1989 Forwards Insp Rept 50-267/89-16 on 890716-0831 & Notice of Violation IR 05000267/19890121989-09-22022 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-267/89-12 ML20247K9051989-09-19019 September 1989 Advises That 890726 Request for Approval of Route to Transport Spent Reactor Fuel Approved.Route,From Facility to DOE Inel in Idaho,Encl ML20247L1381989-09-19019 September 1989 Advises That Request to Delete Requirement to Provide Status Repts on Performance Enhancement Program Approved.Updated List of Commitments Encl 1998-07-20
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UUL 2 31986 In Reply Refer To:
Docket: 50-267/86-08 Public Service Company of Colorado ATTN: Robert 0. Williams, J Vice President, Nuclear Operations P. O. Box 840 Denver, Colorado 80201-0840 Gentlemen:
Thank you for your letters of June 17, 1986, and June 24, 1986, in response to our letters and Notice of Violation dated May 19, 1986. We have reviewed your reply and find it responsive to the concerns raised.in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be raaintaine
Sincerely,
D. E. GAGLIARDO".
J. E. Gagliardo, Chief Reactor Projects Branch cc:
J. W. Gahm, Manager, Nuclear Production Division Fort St. Vrain Nuclear Station 16805 WCR 191'
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Platteville, Colorado 80651 L. Singleton, Manager, Quality.
.
Assurance Division *
(same address)
Colorado Radiation Control Program Director bec to DMB-(IE01)
bcc distrib'. by RIV:
RPB DRSP Resident Inspector- -
R. D. Martin, RA Section Chief (RPB/A) *RSB Secti Chief (RSB/ES) R&SPB MIS S :em RSTS Operator RIVf .
C/R A' RPB J JEGagliddo C)\
7/ /86 / G/
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ADOCK 05000267 PDR
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