Letter Sequence Other |
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Results
Other: 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 Developed, ML20137L915, ML20198K880, ML20198K899, ML20203E922, ML20204C493, ML20204E581, ML20206T869, ML20207Q604, ML20207R069, ML20210F539, ML20210G003, ML20210K842, ML20211B270, ML20211M464, ML20211P598, ML20211P612, ML20212H039, ML20213F038, ML20213F695, ML20213G414, ML20215K603, 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 Adequacy
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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 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 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 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 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 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 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 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 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 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 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 ML20214L1841986-11-20020 November 1986 Summarizes 860929-1002 Site Visit to Gather Info for SER Supporting Restart.Util Response to Selected Items Encl. Application to Amend Tech Specs,Covering SPDS & Reg Guide 1.97 Will Be Submitted,Although Unnecessary for Restart Project stage: Request 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 ML20211B2701987-02-11011 February 1987 Forwards Target Nuclear Organization for Restart (Transition Plan) for Review.Plan Provided to Facilitate Transition from Interim (Prestart) to Ultimate Nuclear Organization. Organizational Chart,Resumes & Position Descriptions 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 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 1986-07-23
[Table View] |
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| ML20137L915 |
| Person / Time |
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| Site: |
Fort Saint Vrain  |
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| Issue date: |
01/20/1986 |
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| From: |
Gahm J PUBLIC SERVICE CO. OF COLORADO |
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| To: |
Berkow H Office of Nuclear Reactor Regulation |
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| References |
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| RTR-NUREG-0578, RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-660, RTR-NUREG-737, TASK-1.A.1.1, TASK-TM P-86047, TAC-61635, NUDOCS 8601280136 |
| Download: ML20137L915 (4) |
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Text
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Oeubiicservice~
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16805 WCR 19 1/2, Platteville, Colorado 80651 January 20, 1986 Fort St. Vrain Unit No. 1 P-86047 Director of Nuclear Reactor _ Regulation U.S. Nuclear Regulating Commission Washington, D.C.
20555 ATTN: Mr. H.N. Berkow, Project Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
COMMISSION POLICY STATEMENT ON ENGINEERING EXPERTISE ON SHIFT
REFERENCES:
(1 ) P-79305, Warembourg to Varga, December 18, 1979 (2 ) G-80049, Speis to Fuller, Received March 31, 1980 (3 ) P-80444, Warembourg to Eisenhut, December 30, 1980 (4 ) G-81142, Miller to Lee, August 6, 1981 (5 ) G-81175, Miller to Lee, October 2, 1981 (6 ) P-81271, Lee to Miller, October 30, 1981 (7 ) G-81223, Kuzmycz to Lee, November 9, 1981 (8 ) G-82080, Clark to Lee, March 19, 1982 (9 ) P-82112, Lee to Clark, April 20, 1982 (10) G-83369, Wagner to Lee, October 13, 1983
Dear Mr. Berkow:
On October 28, 1985, the Nuclear Regulatory Commision published in the Federal Register (43621), the " Commission Policy Statement on Engineering Expertise on Shift."
The purpose of this policy statement was to present the Commission's policy "with respect to ensuring that adequate engineering and accident assessment expertise is possessed by the operating staff at a nuclear power plant."
This policy presents licensees with two options for providing the requisite engineering expertise on shift.
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~2-Option 1 of this policy statement provided for a " combined SR0/STA-Position" in order to meet this need, and option 2 allowed the
" continued use of the STA position." The purpose of this letter is to discuss the position of Public Service Company of Colorado with regard to the aforementioned policy statement.
Public Service Company of Colorado intends to continue its use of a Technical Advisor (TA) position to meet this ongoing need.
The Technical Advisor position has been in use at Fort St. Vrain since early 1980, when, in response to NUREG-0578 Item 2.2.1.b and NUREG-0660 Item I.A.1.1, three engineers were placed on call to the Operations Department with a one hour maximum response time as-discussed in Reference 1.
On March 20,
- 1980, the Commission staff transmitted to PSC the results of their evaluaticn of the implementation of " Category A"
Lessons Learned requirements (Reference 2).
In the discussion of Item 2.2.1.b, the Fort St. Vrain Technical Advisor position was found acceptable as follows:
"The program that the licensee has implemented to satisfy the STA accident assessment function utilizes three engineers who are placed on-call to respond to potential accident conditions at the
~
plant. The licensee has committed to a one-hour response time for the on-call STA, in contrast to the staff's position for a 10 minute response time. We have considered the licensee's argument.
for the relatively long times (i.e.,
hours) for accident conditions to develop' in a gas cooled reactor versus a
significantly shorter time for light water reactors. Considering this unique feature of a gas cooled reactor the staff finds the one-hour response time acceptable.for Fort St. Vrain. The three STA engineers will also fulfill the required operating experience assessment function required by NUREG-0578.
"We have reviewed the licensee's October 29 and December 12, 1979, submittals describing their STA program.
In addition, during the site visit we discussed the program with the licensee and determined that a satisfactory STA program is in operation.
We find that their STA program satisfies the staff's requirements described in Section 2.2.1.b of NUREG-0578 and is therefore acceptable."
a
4 In November 1980, the Nuclear Regulatory Commision issued NUREG-0737 which, in Item I.A.1.1, endorsed the Shift Technical Advisor position as a requirement for the operating staff as described in Item 2.2.1.b of NUREG-0578 and Item I.A.I.1 of NUREG-0660.
Public Service Company of Colorado responded to the NUREG-0737 Item I.A.I.1 in detail via correspondence to the Commission (Reference 3).
In that letter, the Fort St. Vrain training program for Technical Advisors was discussed, as well as the duties, responsibilities, accountability, and qualification requirements for the Fort St. Vrain Technical Advisor position.
In addition, the long range plans for the Technical Advisor position at Fort St. Vrain were clarified, as required by NUREG-0737. Public Service Company of Colorado stated its intent to:
"1.
Retain the TA's as permanent Fort St. Vrain staff for the duration of operating license in lieu of upgrading SR0's to a college level engineering degree.
"2.
Upgrade the operator and SRO training and requalification requirements to include courses in heat transfer, fluid flow, and thermodynamics as well as other upgrading as outlined in Attachment 5 [to P-80444], but retain the Technical Advisors as the college level expertise rather than providing this expertise to the operator."
On August 6,
1981, the Commission issued an Order confirming PSC's commitments to Three Mile Island Action Plan related items (Reference 4).
In that letter, the Commission granted acceptance of the Fort St. Vrain Technical Advisor position _as follows:
"The licensee has agreed to the requirements of Item 1.A.1.1 (sic), ' Shift Technical Advisor' with the exception that instead of the staff's position for a 10 minute response time, the-licensee has committed 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 to develop, the staff finds the one hour response time acceptable for the Fort St. Vrain Nuclear Generating Station."
The Commission staff, on October 2, 1981, via Reference 5 transmitted the determination that the " Shift Technical Advisor section should be included in the Technical Specifications...The bases for this determination is contained in our" (the NRC's) " March 20,
- 1980, letter to Public Service."
In response to that request, PSC submitted a request for an amendment to the Fort St. Vrain Technical Specifications (Reference 6) to include the Technical Adviso'r position in section AC 7.1.1 as part of the operating staff, and to place a requirement for a one hour response time capability. This amendment was issued by the Commision as Amendment No.24 to the Facility Operating License on November 9,1981 (Reference 7).
e
. On March 19,
- 1982, PSC was advised of the results of a post-implementation review of Shift Technical Advisor training programs (Reference 8).
In that letter, PSC was advised:
"Our review indicated that your STA training. program is acceptable in meeting the intent of the guidelines set forth in the above referenced letters.
You are requested to propose a-Technical Specification change incorporating the following qualification requirements for the STA as paragraph 6.3.2:
'The Shift Technical Advisor.shall have a bachelor degree-or equivalent in a scientific or engineering disc'.pline with specific training in plant design and response and analysis of the plant for transients and accidents.'"
PSC responded on April 20, 1982, via Reference 9 with a request for an amendment to section AC 7.1, as requested in G-82080. This change was implemented as Amendment No. 36 to the Facility Operating License upon receipt of G-83369 (Reference 10).
PSC has been pleased with the results of the incorporation of the Technical Advisor position into the operating staff at Fort St.
Vrain, and is continuing to explore areas ;nto which Technical Advisor manpower and experience can be utilized to e, hance operations of Fort St.
Vrain.
'A large scale review of the Technical Advisor training program was recently completed at the suggestion of the Institute of Nuclear Power Operations (INPO) relative to the INP0 accreditation program, and new candidates for the Technical Advisor program are presently being trained in accordance with that enhan~ced program.
Early feedback from that effort has been good, and we anticipate that the level of preparation of these candidates will be superior.
If you have questions regarding this matter,' please contact Frank Novachek of my staff at (303) 785-2224.
l Sincerely,.
l ahm Manager, Nuclear Production Fort St..Vrain Nuclear Generating Station JWG:JMS/jlr
_.