Letter Sequence Other |
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MONTHYEARML20137L9151986-01-20020 January 1986
Comments on 851028 Commission Policy Statement on Engineering Expertise on Shift,Per NUREG-0737,Item I.A.1.1 Re Shift Technical Advisor.Util Pleased W/Incorporation of Technical Advisor Position in Operating Staff
Project stage: Other
ML20198K8801986-05-30030 May 1986
Forwards Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station. Plan Provides Preliminary Results of Util Mgt Review of Implications of 851226 Overcooling Incident.Formal Plan Expected by 860703
Project stage: Other
ML20198K8991986-06-0202 June 1986
Smud Action Plan for Performance Improvement at Rancho Seco Nuclear Generating Station
Project stage: Other
ML20206H3941986-06-20020 June 1986
Summarizes NRC Concerns Expressed at 860610 Meeting Re Preliminary Version of Action Plan for Performance Improvement at Plant.Formal Plan Scheduled for Submittal on or About 860701 Should Resolve Listed Concerns
Project stage: Meeting
ML20203E9221986-06-30030 June 1986
Forwards Rev 4 to Updated FSAR for Prairie Island Nuclear Generating Plant.Two New Vols Provided for Reprinting of Apps of Original FSAR
Project stage: Other
ML20206T8691986-07-0303 July 1986
Forwards Action Plan for Performance Improvement. Plan Addresses 851226 Event & Includes Prioritization Process Which Identifies Actions That Will Be Completed Before Restart.Review Requested
Project stage: Other
ML20202G0431986-07-0303 July 1986
Discusses Systematic Assessment Program Portion of Performance Improvement Program,Per 860617 & 18 Discussions. Little Progress Made to Define & Implement Meaningful Sys Review & Test Program.Review of Program Suggested
Project stage: Approval
ML20204E5811986-07-17017 July 1986
Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program
Project stage: Other
ML20204E5741986-07-21021 July 1986
Forwards Rev 1 to Instruction QCI-12, Plant Performance & Mgt Improvement Program, Per 860717 Meeting Request
Project stage: Meeting
05000312/LER-1986-011, :on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed1986-07-23023 July 1986
- on 860424,during Visual Insps of Internal Wiring Terminations,Seven Internal Compression Terminations Failed.Caused by Loose Conductor/Lug Assemblies in Bailey Cabinets.Maint Stds & Insp Plan Developed
Project stage: Other
ML20204C4931986-07-23023 July 1986
Responds to Retrospective Part of Issue 2a Re Completeness of Staff & Licensee Actions Associated W/Control Sys,Per Stello 860313 Memo to Denton in Response to Investigation of 851226 Incident.Issue 2a Closed
Project stage: Other
ML20203G5531986-07-23023 July 1986
Notification of 860814 Meeting W/Util in Bethesda,Md to Discuss Action Plan for Performance Improvement
Project stage: Meeting
ML20197C6991986-07-25025 July 1986
Preliminary Deterministic Failure Consequence Analysis for Non-Nuclear Instrumentation (Nni) & Integrated Control Sys (ICS) Power Supply Failure
Project stage: Other
ML20212E9511986-07-29029 July 1986
Forwards General Comments on Util 860703 Action Plan for Performance Improvement.Prior to Scheduled 860814 Working Meeting W/Util,Staff Will Provide Addl Comments to Be Addressed in Meeting Agenda
Project stage: Meeting
ML20197C7041986-08-25025 August 1986
Preliminary Suppl 1 to Deterministic Failure Consequence (DFC) Analysis for Non-Nuclear Instrumentation (Nni) & Integrated Control Sys (ICS) Power Supply Failures:Loss of Nni X or Y/Ics AC Power (Auto-Bus Transfer-ABI-Failure)
Project stage: Other
ML20214N8311986-09-0505 September 1986
Forwards Request for Addl Info Re Util Action Plan for Performance Improvement & Preliminary List of Issues to Be Resolved in Electrical,Instrumentation & Control Portion of Proposed SER
Project stage: RAI
ML20210K8421986-09-12012 September 1986
Rev 1 to Design Basis Rept
Project stage: Other
ML20210G0031986-09-15015 September 1986
Forwards Amend 1 to Action Plan for Performance Improvement. Util Determined Installation of Emergency Feedwater Initiation & Control Sys Prior to Restart Feasible
Project stage: Other
ML20210G2431986-09-15015 September 1986
Forwards Audit Plan for Safety Evaluation of Facility Action Plan for Performance Improvement of Control Room Design & Spds.Audit Should Be Conducted in Early Oct to Preclude Impact on Proposed Restart Date
Project stage: Approval
ML20197C7211986-09-19019 September 1986
Preliminary Rev 1 to Control Room/Technical Support Ctr Essential Air Conditioning Sys Status Rept
Project stage: Other
NL-86-672, Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy1986-09-26026 September 1986
Forwards Rev 1 to A-5415, Design Basis Rept, as Requested. Review of Current Emergency Feedwater Initiation & Control Sys Design Should Address Inconsistencies w/1983 SER Not Technical Adequacy
Project stage: Other
ML20211C1331986-10-0909 October 1986
Summary of 860814 Meeting W/Util,B&W,American Nuclear Insurers & Lrs,Inc in Bethesda,Md Re Detailed Aspects of Action Plan for Performance Improvement at Plant.Viewgraphs Encl
Project stage: Meeting
ML20215K6031986-10-16016 October 1986
Submits Results of Survey on Engineering Expertise on Shift. Findings of Survey Include That Plants Utilize Shift Technical Advisors That Are on-call & That Differences from Commission Policy Statement Handled on case-specific Basis
Project stage: Other
ML20197C7121986-10-30030 October 1986
Preliminary Rept of Deterministic Failure Consequence Analysis for Instrument Air Sys. Draft Preliminary Instrument & Svc Air Sys Status Rept Encl
Project stage: Draft Other
ML20197C6821986-10-30030 October 1986
Forwards Response to 860530 Request for Addl Info Necessary for Preparation of SER Supporting Plant Restart. Instrumentation & Control Sys & non-nuclear Instrumentation Schematic Drawings Will Be Sent Separately
Project stage: Request
ML20213F6951986-11-0606 November 1986
Forwards non-nuclear Instrumentation & Instrumentation & Control Sys Schematics & Piping & Instrument Drawings,In Response to NRC 860530 Request
Project stage: Other
ML20213F0381986-11-0707 November 1986
Advises of Revised Schedule for Completion of NUREG-0737, Item III.D.3.4 Re Control Room Habitability.Provisions to Complete Item III.D.3.4 Will Be Implemented Prior to Startup from Current Outage Anticipated in Early May 1987
Project stage: Other
ML20211M4641986-12-0303 December 1986
Advises of Actions Taken in Response to Recent Burnout of Pressurizer Heater Bundle.Sessions Scheduled at Lynchburg Simulator During Feb 1987 to Polish Operator Skills & Awareness,Per Performance Improvement Action Plan
Project stage: Other
ML20211P5981986-12-15015 December 1986
Forwards Amend 2 to Action Plan for Performance Improvement. Amend Identifies Specific Actions Required for Accomplishment Prior to or During Restart
Project stage: Other
ML20211P6121986-12-31031 December 1986
Amend 2 to Action Plan for Performance Improvement
Project stage: Other
ML20212H0391987-01-12012 January 1987
Responds to Questions Discussed During 861216 Telcon Re SPDS & Main Feedwater (MFW) Indication in Control Room.Util Will Revise Action Plan,Section 4B.19 Re MFW Pump Trips
Project stage: Other
ML20207Q6041987-01-20020 January 1987
Advises of Future Plans to Take Reactor Out of Cold Shutdown & Proceed Through Heatup to Hot Shutdown Conditions,Based on Interpretation of 851226 Confirmatory Action Ltrs for pre-start Activities
Project stage: Other
ML20210F5391987-02-0303 February 1987
Confirms Telcon Re Arrangements for Evaluation of Requalification Program.Evaluation Visit Scheduled for Wk of 870504.Ref Matl Requirements for Program Evaluation & Requirements for Administration of Written Exams Encl
Project stage: Other
ML20213G4141987-02-26026 February 1987
Advises That All Steps Necessary to Ensure That Reorganizational Efforts Do Not Adversely Impact Restart Schedule Taken,Per 870205 Request
Project stage: Other
ML20207R0691987-03-0303 March 1987
Advises That Plans to Proceed W/Sys Testing Program & Precriticality Startup Program,Including Hot Shutdown, Consistent W/Confirmatory Action Ltrs for Prestartup Activities.W/O Rept
Project stage: Other
ML20206K5881987-04-10010 April 1987
Forwards SER Accepting Util 860513 Proposed Replacement of Hydraulic Snubbers W/Energy Absorbers for Seismic Support of Certain safety-related Piping
Project stage: Approval
ML20214L0191987-05-13013 May 1987
Forwards Request for Addl Info on Section 3.2.4 of Facility Restart Rept Re Steam Generator Overfill & Flooding of Main Steam Headers to Complete Review
Project stage: RAI
NUREG-1286, Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues1987-10-0707 October 1987
Forwards SER Re Restart Following 851226 Event (NUREG-1286). Requests Response to 870814 Request for Addl Info to Resolve Restart Issues
Project stage: Approval
ML20055C2051988-02-12012 February 1988
Forwards Safety Evaluation Supporting Util 871223 & 880211 Submittals Re Proposed Amends to Tech Specs (PA 155,Rev 2) for Plant.Salp Input Also Encl
Project stage: Approval
1986-07-25
[Table View] |
Submits Results of Survey on Engineering Expertise on Shift. Findings of Survey Include That Plants Utilize Shift Technical Advisors That Are on-call & That Differences from Commission Policy Statement Handled on case-specific Basis| ML20215K603 |
| Person / Time |
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| Site: |
Rancho Seco, 05000000, Fort Saint Vrain |
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| Issue date: |
10/16/1986 |
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| From: |
Miraglia F
Office of Nuclear Reactor Regulation |
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| To: |
Russell W
Office of Nuclear Reactor Regulation |
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| Shared Package |
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| ML20215G605 |
List: |
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| References |
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| FOIA-87-299, RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM GL-86-04, GL-86-4, TAC-61631, TAC-61635, NUDOCS 8610280229 |
| Download: ML20215K603 (3) |
|
Text
W w
/
UNITED STATES E'
yi NUCLEAR REGULATORY COMMISSION
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'l W ASHING TON, D. C. 20555
\\.'.... /
007 1 6 1986 MEMORANDUM FOR:
William T. Russell, Director Division of Human Factors Safety FROM:
Frank J. Miraglia, Director 4
Division of PWR Licensing-B l
SUBJECT:
RESULTS OF SURVEY ON ENGINEERING EXPERTISE ON SHIFT, FORT ST. VRAIN AND RANCHO SECO (TAC N0. 61635)
In your memorandum to me dated August 12, 1986 on the subject of Results of Survey on Engineering Expertise on Shift, you pointed out that one of the findings of the survey is that Fort St. Vrain and Rancho Seco utilize Shift Technical Advisors (STA) that are on-call; and that these differences from the i
Commission Policy Statement are to be handled on a case specific bases. Our views on each of these are as follows:
"3 Generic Letter 86-04 provided to all power reactor licensees a copy of the
,d Federal Register Notice of the Policy Statement on Engineering Expertise on
}
Shift.
The Policy Statement offers the licensees two options for meeting j
the current requirements for providing Engineering Expertise on Shift.
1 Option 2 calls for using a dedicated STA.
1.
Fort. St. Vrain 1
1 Fort St. Vrain, in response to Generic Letter 86-04, has stated that they plan to continue to use a separate STA (option 2 of the Policy Statement).
j The STA is on-call to respond within one hour, in contrast to the position 1
of the Policy Statement that the STA should assume an active role in shift activities. The former staff position required the STA to be able
.a to respond within 10 minutes (NUREG-0737, Item I.A.1.1),
a In an enclosure to a letter dated August 6, 1981 to Mr. 0.R. Lee, Vice j
President Electric Production, Public Service of Colorado, from James R.
j Miller, Chief, Standardization and Special Projects Branch, Division of j
Licensing, the Commission issued an Order confirming the Licensee's i
commitments on TMI related issues.
Item III.2. of this Order states that j
"the licensee has agreed to the requirements of Item I.A.1.1, " Shift 2
Technical Advisor" with the exception that instead of the staff's i
position for a 10 minute response time, the licensee has conrnitted to
{
a one-hour response time for the on-call STA.
Considering the unique
.[
features of gas cooled reactor, i.e., long times for accident conditions CONTACT:
F. Allenspach, F0B/DPLB 3
49-24921 l
pl OgO 3
.j..
' William T. Russell OCT i 61986 to develop, the staff finds the one-hour response time acceptable for the Fort St. Vrain Nuclear Generating Station."
Based on the previous review and Order by the Commission, we do not intend to pursue this issue any further with the licensee.
2.
Rancho Seco As a result of the December 25, 1985 incident at the Rancho Seco plant the utility has submitted an Action Plan for Performance Improvement. The staff is reviewing this plan.
During the course of this review, we will address the subject of the utility's on-call STA.
Origimi eigned by, Frank J. Miraglia Frank J. Miraglia, Director Division of PWR Licensing-B cc:
K. Heitner S. Miner H. Berkow J. Stolz D. Jones C. Goodman L. Crocker Distribution:
Central Files F. Allenspach D. Crutchfield i
F. Miraglia F08 Plant Files j
FOB:PWR-B*
F0B:PWR-B*
A/
t's D:
9 b/09 b/ y 8 b/ /y86 0FFICIAL RECORD COPY
i!
William T. Russell -
todevelop,thestaff.findstheone-hourresponsetimeaccept'ablefor the Fort St. Vrain Nuclear Generating Station."
Based on the previous review and Order by the Commissi n, we do not intend to pursue this issue any further with the licensee.
2.
Rancho Seco
' As a result of the December 25, 1985 incident the Rancho Seco plant the utility has submitted an Action Pla for Performance Improvement. The staff is reviewing this pl n.
During the course of this review, we will address the subject o the utility's on-call STA.
/
Frank J. Mi glia, Director Division f PWR Licensing-B S. Miner H. Berkow J. Stolz D. Jones C. Goodman L. Crocker Distribution:
Central Files F. Allenspach D. Crutchfield F. Miraglia F0B Plant Files e
F0.PWR-Bff#
F0 A/D:PWR-B D:PWR-B 710/
8 b/
86 b/
8 b/
8 0FFICIAL RECORD COPY