Letter Sequence Other |
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Results
Other: 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated, 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR, ML19306G340, ML20137H372, ML20197B076, ML20204G924, ML20205T170, ML20206B329, ML20206B459, ML20206F887, ML20207K386, ML20207K441, ML20207K446, ML20207K506, ML20207K512, ML20207P779, ML20207P991, ML20207P993, ML20209E329, ML20209F187, ML20209G043, ML20210A740, ML20210A748, ML20210A757, ML20210T436, ML20210T655, ML20210T686, ML20211D992, ML20211E058, ML20211E084, ML20211E110, ML20211G583, ML20211N368, ML20214Q988, ML20214Q998, ML20214S836, ML20215H964, ML20215H973, ML20215J855, ML20215J871, ML20234C109, ML20235E520, ML20235F508, ML20245C018
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MONTHYEARML20137H3721985-11-26026 November 1985 Memorandum & Order Granting Extension of 851130 Deadline for Environ Qualification of Electrical Equipment to 860531 & Approving Proposal to Allow Operation w/35% Reactor Power Limit During Interim.Served on 851127 Project stage: Other ML20211E0841986-02-20020 February 1986 Issue a to Fort St Vrain:Delayed Firewater Cooldown;Effect of Liner Cooling on Orifice Valve Temps Project stage: Other ML20209F1871986-03-18018 March 1986 Fort St Vrain Steam Generator Temps During Interruption of Forced Cooling from 105% Power Project stage: Other 05000267/LER-1986-020, :on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated1986-08-10010 August 1986
- on 860711,determined That FSAR Analyses for Safe Shutdown Cooling Following 90-minute Loss of Forced Cooling May Be Invalid.Caused by Design Omission.Three Options Presently Being Investigated
Project stage: Other ML20211E0581986-09-30030 September 1986 Effect of Delayed Firewater Cooldown W/Loss of Liner Cooling on Pcrv Temps Project stage: Other 05000267/LER-1986-026, :on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR1986-10-17017 October 1986
- on 860917,FSAR Analysis for Safe Shutdown Cooling W/Firewater Invalid.Caused by Incomplete Analysis/ Inadequate Review.Review & Reanalysis Will Be Performed on Various Accidents Described in FSAR
Project stage: Other ML20211G5831986-10-22022 October 1986 Anticipates Completion of Steam Generator Analysis & App R Modeling Reanalysis Work by Feb 1987,per 860918 Telcon W/Nrc Re Steam Generator Cool Down Studies for App R Project stage: Other ML20197B0761986-10-22022 October 1986 Informs That Util Will Update & Submit Rept on Chernobyl Accident by 861126.Update Will Ctr on Graphite Related Concerns,Including Analysis of Worst Case Explosive Gas Mixtures & Comparison of Reactor Kinetics Behavior Project stage: Other ML20207K5121986-11-13013 November 1986 Fort St Vrain Calculations for Circulator Temp-Related Operating Limits Project stage: Other ML20207K5011986-12-0404 December 1986 Effect of Firewater Cooldown Using Economizer-Evaporator- Superheater (EES) Bundle on Steam Generator Structural Integrity. Draft Rept of Steam Generator Ability to Withstand post-App R Firewater Cooldown Transient Encl Project stage: Draft Other ML20207K4461986-12-12012 December 1986 Issue a to Effect of Firewater Cooldown Using Reheater on Steam Generator Structural Integrity Project stage: Other ML20211N3681986-12-12012 December 1986 Forwards Restart Interaction Schedule,Per 861205 Request Project stage: Other ML20207K5061986-12-22022 December 1986 Issue a to Effect of Intentional Depressurization on Cooldown from 39% Power Using One Reheater Module (1-1/2 H Delay) Project stage: Other ML20207K4411986-12-23023 December 1986 Issue a to Economizer-Evaporator-Superheater (EES) Cooldown from 39% & 78% Power Using Condensate or Firewater (1.5 H Delay) Project stage: Other ML20207K3861986-12-30030 December 1986 Forwards Analyses Supporting Power Operation Up to 39% Power Based on Safe Shutdown Cooling Following 90 Min Interruption of Forced Circulation.Conclusions of Repts Listed.Corrective Actions for LERs 86-020 & 86-026 Also Listed Project stage: Other ML20207P7791987-01-0707 January 1987 Forwards Current Integrated Schedule for Restart & Power Ascension Activities.Schedule Incorporates Consolidated Schedular Info on Both Interaction Activities.Updates Will Be Provided Twice Per Month.W/One Oversize Graph Project stage: Other ML20207P9931987-01-13013 January 1987 SAR for Tech Spec Limiting Condition for Operation 4.3.1 Change Permitting Safe Shutdown Cooling W/Evaporator- Economizer-Superheater Project stage: Other ML20207P9871987-01-15015 January 1987 Forwards Application for Amend to License DPR-34,changing Tech Specs to Require Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power.Fee Paid Project stage: Request ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs Project stage: Other ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs Project stage: Request ML20211E1101987-01-26026 January 1987 Rev a to Engineering Evaluation of Procedure to Recover from Actuation of Steam Line Rupture Detection/Isolation Sys for Power Levels Through P2 Project stage: Other ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan Project stage: Other ML20210A7481987-01-30030 January 1987 Requests Concurrence to Start Up & Operate Facility Through Graduated Rise to Power Up to 100% of Rated Power,Subj to Listed Constraints. Fort St Vrain 1987 Power Ascension Plan Encl Project stage: Other IR 05000267/19870021987-01-30030 January 1987 Partially Withheld Insp Rept 50-267/87-02 on 870106-09 (Ref 10CFR73.21).No Violations or Deviations Noted.Major Areas Inspected:Matl Control & Accounting Project stage: Request ML20210A7401987-02-0202 February 1987 Forwards Updated Nrc/Public Svc Co of Colorado Restart Interaction Schedule, Reflecting Current Target Dates & Recently Completed Items Project stage: Other ML20209G0431987-02-0202 February 1987 Forwards Current Integrated Schedule for Plant Restart & Power Ascension Activities.W/One Oversize Encl Project stage: Other ML20210N8831987-02-0303 February 1987 Forwards Request for Addl Info on 861230 & 870115 Submittals Re Analysis of Firewater Cooldown from 82% of Full Power Project stage: RAI ML20210P0191987-02-0505 February 1987 Summary of 870113 Meeting W/Util Re Completion of Equipment Qualification Program & Program & Approvals Required for Plant Restart Project stage: Meeting ML20210T6861987-02-0505 February 1987 Rev a to Engineering Evaluation of Reanalysis of FSAR Accidents/Transients Relying on EES Cooling. W/Four Oversize Drawings Project stage: Other ML20211D9921987-02-0505 February 1987 Issue a to Economizer-Evaporator-Superheater Cooldowns for Equipment Qualification & App R Events W/Vent Lines (1.5 H Delay) Project stage: Other ML20210T6551987-02-0606 February 1987 Provides Results of Confirmatory Analyses for FSAR Accidents Which Utilize Either EES or Reheater Section of Steam Generator for DHR Project stage: Other ML20210T4361987-02-11011 February 1987 Requests Publication of Fr Notice of Consideration of Issuance of Amend to License DPR-34 & Proposed NSHC Determination & Opportunity for Hearing on 870115 Request Re Operation of evaporator-economizer-superheater Sections Project stage: Other ML20211E9791987-02-12012 February 1987 Forwards Proposed Agenda & Slides for 870226 Meeting W/ Commission & Staff to Secure Commission Approval for Full Power Operation of Facility Project stage: Meeting ML20211D8901987-02-17017 February 1987 Forwards Response to NRC 870203 Request for Addl Info Re Firewater Cooldown from 82% of Full Power,Per Util 861230 & s Project stage: Request ML20207Q7941987-03-0303 March 1987 Forwards Second Request for Addl Info Re Util Analysis of Firewater Cooldown from 82% of Full Power Operation,Based on Review of 861230,870115 & 0217 Submittals Project stage: Approval ML20204G9241987-03-20020 March 1987 Forwards Restart & Power Ascension Schedule,Incorporating Consolidated Schedular Info on NRC-util Interaction Activities.Brief Narrative Description of Scope of Each Line Item Activity Also Encl.W/One Oversize Encl Project stage: Other ML20205B3441987-03-20020 March 1987 Forwards Response to NRC 870303 Second Request for Addl Info Re Firewater Cooldown from 82% of Full Power (Safe Shutdown Cooling) Project stage: Request ML20205M8901987-03-30030 March 1987 Forwards Third Request for Addl Info Re Util 861230,870115 & 0217 Submittals Concerning Analysis of Firewater Cooldown from 82% of Full Power.Major Concerns Re Effects of Transient Loading Due to Seismic Motion or Flow Project stage: RAI ML20205T1701987-04-0101 April 1987 Forwards Oversize Current Integrated Schedule for Facility Restart & Power Ascension Activities Required for Equipment Qualification Completion Certification,Startup/Plant Criticality & Power Ascension to 82%.Related Info Encl Project stage: Other ML20206B6031987-04-0101 April 1987 Forwards Comments Re Implication of Chernobyl Reactor Accident.Design Differences Between Fort St Vrain & Chernobyl Preclude Accident Similar to Chernobyl from Occurring at Fort St Vrain Project stage: Approval ML20206B4591987-04-0303 April 1987 Forwards Summary of Equipment Qualification (EQ) Insp Conducted by NRR & IE on 870126-30.EQ Program Approved. Detailed Results of Insp Will Be Provided Project stage: Other ML20206B3291987-04-0707 April 1987 Submits Daily Highlight.Public Svc Co of Colorado Authorized to Restart & Operate Facility HTGR at Level of Up to 35% Full Power.Facility Out of Operation Since 860531,when Shut Down for Equipment Qualification Mods Project stage: Other ML20206F8871987-04-10010 April 1987 Submits Requested Addl Info for Analysis of Firewater Cooldown for 82% Power Operation,Per Project stage: Other ML20209E3291987-04-27027 April 1987 Provides Written Authorization to Operate Reactor at Up to 35% Full Power,Per Section IV of 870406 Confirmatory Order Modifying License DPR-34 Project stage: Other ML20215H9641987-04-30030 April 1987 Forwards Updated Ga Technologies Procedure 909410, Buckle Users Manual, Per 870330 Request.Manual Updated to Include Revs to Computer Code Required by High Temps & Short Times Assumed for Steam Generator Tube Stress Analysis Project stage: Other ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients Project stage: Other ML20215J8711987-05-0404 May 1987 Rev a to Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other ML20215J8551987-05-0404 May 1987 Forwards Rev a to EE-EQ-0057, Evaluation of Test Data for Confirmation of Fire Water Flow Rate to Circulator Water Turbine During EES Cooldown for Safe Shutdown Cooling Project stage: Other ML20214S8361987-05-27027 May 1987 Requests Insp & Audit Per 10CFR50,App B of Licensee Activities Supporting Request for 82% Power Operation. Requests That Insp Be Conducted & Completed within 180 Days Project stage: Other ML20214Q9881987-05-29029 May 1987 Forwards Rept GA909438,Issue Nc, Verification Rept for Buckle Computer Program. Edition of Buckle Code Covered by User Manual Validated & Independently Verified by Rept Project stage: Other 1987-02-11
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Text
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O Public Service-
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P.o. Box 840 Denver, Co 80201-0640 2420 W. 26th Avenue, Suite 100D, Denver, Colorado 80211 R.O. WILUAMS, JR.
NS(([a$k"Enous March 5, 1987 Fort St. Vrain Unit No. 1 P-87090 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 Docket No. 50-267
SUBJECT:
Assessment of Additional Concerns Regarding Fort St. Vrain Restart Gentlemen:
At the Fort St.
Vrain restart briefing on Thursday, February 26, 1987, the NRC Commissioners requested that the General Counsel and the NRC Staff review the matters relating to the indictment issued by the U. S. Attorney for the District of Colorado on February 25, 1987, against three former Public Service Company of Colorado (PSC) employees and the recent resignation of one of these employees, the Fort St. Vrain Manager of Nuclear Production. The Commissioners requested that this review be completed prior to the Commissioners issuing a final decision on the restart of Fort St. Vrain.
Attached for your information is PSC's assessment of the additional concerns discussed at the Fort St. Vrain restart briefing. PSC will utilize Mr.
R. O. Williams, Jr., Vice President, Nuclear Operations in an acting role to maintain executive oversight of plant operations and fulfill the administrative functions of the Manager of Nuclear Production.
PSC will also utilize the plant operational background and experience of Mr. D. W. Warembourg on an interim basis acting as Manager of Nuclear Production for those responsibilities related to operational matters (as described in the Technical Specifications).
PSC's interim staffing plan for the Manager of Nuclear Production position will assure that effective executive oversight of plant operations is maintained, and that the conduct of plant operations are directed by a senior manager with an in-depth knowledge of Fort St. Vrain plant operations.
gi ys P
t P-87090 Paga 2 March 5.-1987 As further detailed in the attached assessment, PSC has concluded that events and circumstances described in the indictment involving Fort St. Vrain contracts have not had any adverse impacts on plant safety or safe plant operations.
PSC believes that a favorable determination allowing restart and operation of the Fort St. Vrain plant within the restrictions of the proposed Power Ascension Plan is warranted and is hereby requested.
If the NRC requires any further information relating to these matters, 'please do not hesitate to contact us.
Your early consideration and prompt resolution of these matters is greatly appreciated.
Very truly yours,
~
R. O. Williams, Jr.
Vice President, Nuclear Operations R0W/MHH:jmt Attachment cc: Regional Administrator, Region IV Attn: Mr. R. D. Martin Office of Nuclear Reactor Regulation Attn: Mr. F. J. Miraglia Office of Inspection and Enforcement Attn: Mr. J. M. Taylor Mr. R. E. Farrell Senior Resident Inspector Fort St. Vrain
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Attichment to P-87090 4'
LPage 1-m v
ASSESSMENT l0F ADDITIONAL CONCERNS
'REGARDING FORT ST.',VRAIN RESTART INTRODUCTION Publien Service Company of Colorado'and the NRC staff met with the Commission on February 26, 1987 to present information concerning the status.of the plant and progress of PSC in addressing previously identified management concerns, all in support of a request for restart of Fort St. Vrain.
Two significant : events occurred in the days just prior'to the meeting. On Monday, February 23, 1987, Jack Gahm,= Manager of the '
Fort St. Vrain. Nuclear Production Division, resigned from the company.
' for personal ~ reasons. _ On Wednesday, February 25,.1987,.a Federal.
Grand Jury Indictment was made public. The indictment named O. R.
Lee (former Vice President of Electric Production for PSC, the person to: whom 1the. Fort St. Vrain organization reported), Jack Gahm..and others as defendants. 'The indictment identified, among other things, two contracts associated with the management and operation of Fort St. Vrain which had allegedly been instruments in certain " kickback" operations engaged in by the defendants.
Neither the Commission, the Staff, nor.PSC was, on the day of the Commissioners meeting, able-to fully assess the possible impact; of these events on PSC's request for restart.
Immediately following the resignation of Jack Gahm, R. O. Williams, the Vice President, Nuclear Operations, named himself acting in the position of Manager of Nuclear Production, thereby maintaining the necessary continuity-of chain of command and delegation of authority.
This -information was provided at the Commissioners meeting on February 26, 1987.
PSC also identified at that meeting-that PSC had initiated appropriate steps to secure a replacement, and that an external search had been initiated.
Since the meeting with the Commissioners, PSC has further examined the two concerns that were identified at the meeting:
the interim measures to be taken by PSC to ensure that senior management attention, support, and direction of the conduct of operations is fulfilled during the period that the Manager of Nuclear Production position remains vacant, and a reexamination of the conduct of work associated with the contracts identified in the indictment as supporting Fort St. Vrain. The results of the examinations and the actions to be taken are discussed below.
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Attachment:
to P-87090'
.Page 2
-INTERIM STAFFING PLAN:
The departure of Mr.. Gahm from the organization'has been_ assessed
~
from.the perspective of.PSC's immediate need to assure that effective-
- executive oversight of the operations is-maintained, and that the conduct of operations are overviewed by a senior manager with _in-depth knowledge - of Fort St. Vrain operations.
Interim actions have been identified toLaddress these two key requirements.
Longer ' term-organizational plans which address these requirements and. incorporate-the results of several key organizational studies which have been in progress will be accelerated.
Since the meeting with the Commissioners, the Vice President, Nuclear Operations has had extensive discussions with the three managers who report. to the position of Manager of Nuclear Production. From these
' discussions, it was concluded that much of the key administrative activity already involved Vice Presidential review and approval and -
+
that the direct involvement of the Vice President in these. matters on an interim basis would be beneficial. Typical activities involve staffing, resource allocation, planning, and the performance of the organization in support of operations. These activities are already
- receiving significant attention by the Vice President and the concensus of these discussions was that his direct involvement at this time would, in fact, provide more timely resolution of a number of pending items. Thus, the. acting role of the Vice President will remain in place for all administrative matters.
The_ role of the Manager of Nuclear Production in the conduct of operations, including those responsibilities described in the Technical Specifications, was discussed extensively with the Station Manager, C. H. Fuller, and D.
W.
Warembourg,- former Manager of Nuclear Production (1978-1984) and currently Manager of Nuclear Engineering. From these discussions, it was concluded that those l-responsibilities and
. duties. associated with plant conduct of operations could be clearly identified and assigned to Mr. Warembourg on an interim basis.
This arrangement avoids diluting senior g
management attention to conduct of operations with administrative duties, assures that the necessary checks and balances remain in force, and provides the Station Manager with the most seasoned and.
i-knowledgeable advice, guidance, and direction available, while l
permitting the Vice President to pursue his responsibilities and
[
maintain executive oversight.
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.Page -
- Mr. -- Wa'rembourg, - already maintains an < office :at the site and has devoted approximately fifty percent of his time to the review and management of work; at the ~ site. His increased direct attention, together_with the enhanced _on-site attention byo Mr. Williams --will provide- : effective.
executive-and operational oversight of the
~
operations in~this interim period.
As a part :of the Performance Enhancement Program, PSC has-been examining the. effectiveness of the current. organization.
These activities were reviewed with the Region IV and NRR staff during the January-1987 PEP progress l review held at the Region.IV. offices.
Studies relating to improvements in the utilization of our technical
-staff' in the efficient and. effective support of operations, consolidation and. enhancement of -training, planning and _ outage management, and the effectiveness of systems and procedures, are all nearing' completion and will be. factored into organizational plans which.PSC will implement-in the near future.
The factors _of-
-executive oversight and continuity of oversight of the conduct of operations by persons with an in-depth knowledge of Fort St. Vrain will continue to receive PSC_'s highest attention as we move from the interim _ measures discussed above to a permanent organizational configuration.- PSC will continue to keep Region IV and'the NRR staff informed of our progress on these matters.
ASSESSMENT OF WORK PERFORMANCE UNDER ZACHARY CONTRACTS Performance Enhancement Program In ~ response to an analysis and evaluation of the Management of Fort St. Vrain by the NUS Operating Services Corporation in January 1985, Public Service Company submitted to Region IV an implementation plan for the Performance Enhancement Program (P-85107).
In early 1985, PSC hired VZM (Zachary) to assist with the implementation and monitoring of that program.during its early phases of development.
During 1985, the primary responsibility of VZM was to assemble-material submitted by PSC Project Managers and to track project performance until that responsibility could be passed to an internal function.
Although PEP projects were initiated and tracked during 1985, the involvement of VZM was insignificant in terms of the evolution of the PEP program as it exists today.
It is the opinion of Public Service Company, that the work done by VZM on the Performance Enhancement Program was quality work and had no adverse impact on the goals and objectives of the PEP program or safe operations of Fort St. Vrain.
I
.c Attachment to P-87090 Page 4 Maintenance Contract In August of 1985, PSC signed a contract with Zachary Industries for the management of maintenance activities at Fort St.
Vrain.
Throughout the duration of this contract, the majority of maintenance employees, employed under a previous contract, remained on site and were. unaffected by the reassignment to the Zachary contract.
Furthermore, all safety.related work was. conducted under the
-provisions of Fort St.
Vrain Quality Assurance Program, which was administered and controlled by PSC personnel.
It is the opinion of the Fort St. Vrain Station Manager and Quality Assurance management in place in 1985, that the workmanship performed-under the Zachary contract was quality work and had no adverse impact on the quality and safe operation of 'the Fort St. Vrain Nuclear Generating Station.
.