ML20205T170
| ML20205T170 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/01/1987 |
| From: | Brey H PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-87125, TAC-63576, NUDOCS 8704070228 | |
| Download: ML20205T170 (15) | |
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16805 WCR 19 1/2, Platteville, Colorado 80651 April 1, 1987 Fort St. Vrain Unit No. 1 P-87125 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267
SUBJECT:
FSV Restart and Power Ascension Schedule
REFERENCE:
PSC letter, Brey to Berkow, dated 12/12/86 (P-86666)
Gentlemn:
Attacnt.d is Public Service Company of Colorado's (PSC) current integrated schedule for Fort St. Vrain (FSV) restart and power ascension activities. The referenced PSC letter submitted a NRC-PSC Restart Interaction Schedule that included a -Power Ascension Plan, Item 6,
and a Startup Issue Identification and Completion Schedule, Item 9.
The FSV Restart and Power Ascension Schedule (Attachment 1) incorporates consolidated schedular information on both of these NRC-PSC interaction activities. is a schedule for all of the identified activities that are required for the EQ Completion Certification, Startup/ Plant Criticality, and Power Ascension to 82%. Attachment 2 is a brief narrative description of the scope of each line item activity shown on Attachment 1.
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- P-87125 Paga 2 April 1, 1987 1
Attachments 1 and 2 represent detailed internal PSC schedular 4
information and are not intended to create, change, or delete previous PSC commitments to the NRC.
Please note that several item numbers have been changed from or added to our previous submittal.
(Reference P-87117). Also, many closed items have been. removed from the schedule narrative.
Public Service Company agreed to provide this update information until restart of the Fort St. Vrain Plant.
Since restart of the plant is imminent, this will be the final schedule update submittal of this nature.
If you have any questions concerning the information provided herein, please contact Mr. M. H. Holmes at (303) 480-6960.
4 Very truly yours, b-d@ h DM H. L. Brey, Manager Nuclear Licensing and Fuels HLB /EHN/jmt Attachments cc: Director of Nuclear Reactor Regulation ATTN: Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Regional Administrator, Region IV ATTN: Mr. J. E. Gagliardo, Chief Reactor Projects Branch Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain
ATTACHMENT 2 TO P-87125 FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS i
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 1 "EQ Outage Work Required for EQ Certification." This item represents plant outage modification and maintenance activities that are required as a result of the EQ program and which must be completed prior to EQ Completion Certification (Item 45). Certain tests and activities may extend beyond the EQ Certification.
Any activities that are not completed at the time of Certification would be identified in the EQ Certification letter.
This item is subdiviced into four scheduling categories for status-tracking accuracy.
The four categories are:
CN/CWP work, CCT's/FT's, SSR work, PMT's. These categories are further defined by Items 2, 3, 4, and 5 respectively.
Item 2 "CN/CWP Work (EQ Certification)" represents that portion of the plant modification work (Change Notice / Controlled Work Procedure) that is required by the EQ program which must be completed prior to EQ l
Completion Certification (Item 45).
(COMPLETE)
Item 3 "CCT's/FT's (EQ Certificationi" represents the post modification cold checkout testing and functional testing activities (CCT's/FT's) associated with the l
modification activities of Item 2.
(COMPLETE)
Item 4 "SSR Work (EQ Certification)" represented that portion of plant preventive and corrective maintenance activities Station Service Request (SSRs) performed on EQ equipment which must be completed prior to EQ Completion Certification (Item 45).
(COMPLETE)
Item 5 "PMT's (EQ Certification)"
represents the post maintenance testing activities (PMT's) associated with the maintenance activities of Item 4.
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FSV RESTART AND POWER ASCENSION SCHEDULE
-LINE ITEM DESCRIPTIONS i
Item 6 "EQL Ou'tage Work Required for. Startup -(Reactor Critical)." This item represents-the balance of the plant outage -modification and maintenance activities that are required.to be complete prior to plant cri ticality.
This activity may include some EQ associated. work identified as not having to be complete prior EQ Certification (Item 45).
l These activities are start-up related. This item is-i also. subdivided into four scheduling categories for 4
status-tracking accuracy.
-The four_ categories are:
j CN/CWP
- work, CCT's/FT's, SSR and.
- work, j
- surveillances.
These categories are further defined by items 7, 8, 9, and 10,_respectively.
Item 7 "CN/CWP Work (Reactor Criticality)" represents plant modification work (Change Notice / Controlled Work Procedure) on equipment and systems required for reactor criticality.
Item 8 "CCT's/FT's (Reactor Criticality)" represents the post I
modification cold checkout ' testing and func tio'nal -
testing activities (CCT's/FT's) associated with the modification activities of Item 7.
Item 9 "SSR/PMT Work (Reactor Criticality)" represents plant i
preventive and corrective maintenance activities (SSRs and PMTs) performed on equipment and systems required j
for reactor criticality.
Item 10 "Surveillances (Reactor Criticality)."
This item represents plant surveillance testing. activities performed on equipment and systems required for j
reactor criticality.
Item 11 "EQ Required NCR Closures (NCR' Log)."
This item includes the identification, -generation, disposition and QA approval of non-conforming conditions associated with the EQ related equipment.
All EQ related non-conformance reports (NCR's) must be closed-out prior to PSC certifying to the NRC that the EQ program is complete (Item 45).
Item 12 "Startup NCR Closures-(NCR Log)." This item includes l
the identification, generation, disposition and. QA i
approval of non-conforming conditions that will prohibit plant criticality if not closed out.
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 13 "EES Vent Modifications." Development, Training, and Implementation of PM Program.
J Item 14
" Steam Generator 6
Inch Vent Design, Material Procurement and Pre-fabrication."
This item represented the preparation activities for the 6 inch vent modification (Item 15).
This preparation included the planning, design, orocurement and pre-fabrication necessary to support tne plant 6 inch vent modification activities.
(COMPLETE)
Item 15 "EES Vent Installation" represents the period for the installation of the Ec o n omi z e r-Ev a po ra t o r-S u pe rh e a t e r (EES) Section 6 inch vent lines on the main steam line. These plant modifications were required by the Safe Shutdown Cooling Technical Specification change l
using fire water for cooling.
(COMPLETE)
Item 16 "EES Vent Modification Procedure Revisions and Training." This activity represented the. required operating and emergency procedure changes and subsequent training as a result of the EES Vent l
Modifications." (COMPLETE)
Item 17
" Firewater / Emergency Feedwater Header Modifications."
A test was conducted to determine the time required to install the Firewater Spool Piece on Emergency Feedwater Header (EFH). The results of this analysis determined the final design of system cross-ties.
l (COMPLETE)
Item 18
" Firewater / Emergency Feedwater Header Procedures and Training." This item encompassed the preparation of the required operating and emergency procedures and subsequent training as a result of the new emergency Feedwater Header Configuration (Spool Piece l
Installation).
(COMPLETE)
Item 19 SLRDIS Item 20 "SLRDIS Operator Action Time Walkdown." This activity verified the time required to reestablish forced circulation following actuation of the SLRDIS in order to meet the recovery time specified in the Technical l
Specifications.
(COMPLETE) ___.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 21
" Surveillance Procedure (PDR) Valve Closure." This activity. involved changing procedures governing circulator water turbine valves which must be operated as part of SLRDIS recovery. Changes are based upon vendor's 0&M manuals.
(COMPLETE)
Item 22 "SLRDIS Technical Specification Submittal / Review and Approval by NRC" includes the SLRDIS - Technical Specification change preparation and submittal to the NRC. This activity also included the NRC review and approval.
(Reference G-87058, Amendment 50)
(COMPLETE)
Item 23
" Release SLRDIS Emergency Procedures."
This item involved the " issue. for use" of the Emergency Procedure revisions that were required by SLRDIS (Item l
25).
(COMPLETE)
Item 24 "SLRDIS Design and Construction."
This activity included the plant design and modification activity required to install StRDIS and the follow-up testing l
of this system.
(COMPLETE)
Item 25 "SLRDIS Activation /SPRDS Deactivation." This activity involves the activation of SLRDIS and the deactivation of the existing SPRDS.
Item 26 Plant Operations Item 27 "Non-Nuclear Dryout" represented that period when the plant conditions allow for non-nuclear dryout of the core.
The duration of this period is dependent upon the moisture level in the. core, and plant systems available.
Non-nuclear dryout was accomplished with use of the reheater which was supplied with steam from l
the Auxiliary Boiler.
(COMPLETE)
Item 28
" Preparation for Power Ascension." This item includes the performance of the various activities included in the Overall Plant Operating Procedures) OPOP's applicable to taking the plant critical and increasing power from zero to 82%.
Item 29
" Nuclear Dryout." represents that period of time when plant conditions and regulatory constraints allow for plant criticality and nuclear dryout of the core. The duration of this period is dependent upon the moisture levels in the core, plant systems available and other regulatory constraints. ---
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM OESCRIPTIONS Item 30
" Reactor Operator Training."
Item 31
" Surveillance Testing Reactor."
Item 32
" Core Performance Testing."
This item includes the activities related to verifying reactor core Segment Three design margins and performance characteristics.
Item 33
" Power Ascension to 35%" represents the period of time starting with the 6 inch vent modification completion, and extending through plant operation at an elevated power level based on the existing Safe Shutdown Cooling Technical Specifications.
This activity includes operation at a 10% hold point, pending approval from NRC Region IV.
Item 34
" Power Ascension to 82% and Continued Operation" represents the period of time after plant operation at 35% (Item 33) when the plant conditions and regulatory restraints will allow for an elevated plant power level governed by the proposed Safe Shutdown Cooling Technical Specifications.
Item 35
" Final CN/CWP P.O. Reviews." This activity involved the engineering review of purchase order documentation associated with the EQ modification (CN/CWP) activities, to ensure that the purchasing requirements meet the. requirements set forth in the EQ binders.
(COMPLETE)
Item 36 "QA Review of EQ P.O. Review." QA final review to ensure adequacy of purchasing requirements and l
specifications for EQ related equipment.
(COMPLETE)
Item 37
" Complete SMAP-27 Binder Reviews (EQ)." This activity included the maintenance review of the EQ binders, in acccrdance with SMAP-27, to incorporate the EQ maintenance and surveillance requirements into the l
plant working procedures.
(COMPLETE)
Item 38
" Binder Document Updates and Telecon Resolution."
This activity involved the incorporation of document changes to the EQ binders as a result of the third party EQ audit. This activity also included replacing vendor telecons with letters to the vendor requesting verification of the information in the telecons.
l (COMPLETE)
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 39
This activity included the final engineering and administrative approval of the EQ Binder Change Notice (CN) documents to incorporate these documents into the controlled design document l
system.
(COMPLETE)
Item 40
" Update 0 & M Library (EQ Related)." This issue involved the controlled vendor manual program developed in response to Generic Letter 83-28 and the
' implementation of this pro for the EQ related (COMPLETE) gram vendor manuals.
Item 41 "EQ MCAR Closure." This issue involved the closecut of Management Corrective Action Request 85-001 which QA as a result of insufficient EQ was generated by (COMPLETE) program controls.
Item 42 "Close EQ Related CAR Items." This activity involved the disposition and QA approval of EQ related Corrective Action Requests. This activity consisted of EQ related CARS that were completed before the EQ MCAR 85-001 (Item 41) was closed out and additional EQ CAR items not tied to the MCAR close-out.
(COMPLETE)
Item 43
" Resolution of Audit Findings."
This activity involves the resolution of any audit findings resulting from the NRC EQ Audit (Item 51).
(COMPLETE)
Item 44 "EQ Completion Status Letter." This item was the PSC generated letter which indicated progress / status of the FSV Program Activities.
(Reference P-87077, February 25,1987.)
(COMPLETE)
Item 45 "EQ Completion Certification Letter."
This item represented the PSC generated letter certifying to the NRC that the FSV EQ program has been implemented and l
meets the requirements of 10CFR50.49.
(COMPLETE)
Item 46 "NRC Response and Approval of Certification Letter."
Item 47 "SMAP-25 Review / Final SSR Closure."
This activity represented the EQ review performed on all EQ related Station Service Requests (SSR's) to ensure that the EQ basis has been maintained during normal maintenance activities.
(COMPLETE)
FSV RESTART AND POWER ASCENSION SCHEDULE
-LINE ITEM DESCRIPTIONS Item 48
" CADS Walkdown Closure." This activity involves the closecut of the EQ walkdown documentation.
Maintenance deficiencies were identified during the walkdown generating Corrective Action Da ta Sheets (CADS) which are closed out when the associated SSR work has been completed.
. Item 49 "NRC Issue SER on Profiles." This activity included the NRC review and approval of the post HELB environmental profiles for the Reactor and Turbine Buildings and the development and issuance of the NRC's Safety Evaluation Report on this issue.
(Reference G-87071, March 13, 1987) (COMPLETE)
Item 50
" Completion of ED-103 Reviews."
This activity involves the engineering review of plant modification Change Notice and Controlled Work Procedure documents to ensure that the EQ basis of equipment -has been maintained during the modification activities.
ED-103 is the Engineering Design Procedure used to control this activity.
Item 51 "NRC EQ Audit Evaluation and Staff Review." This item represented the NRC activity, post EQ Audit, to assess the FSV EQ program success, and to prepare staff recommendations to the Commission for plant startup.
(COMPLETE)
Item 52 "NRC Coninssioner's Meeting." The NRC Commissioner's meeting assessed FSV progress to resolve EQ and other regulatory and management issues and to obtain NRC's approval for plant startup.
(COMPLETE)
Item 53 "NRC Approval of Power Ascension Plan." This item represents the period of time required for any final NRC/PSC interactions and for issuance of documentation of NRC approval of FSV startup.
Item 54 "0ngoing Activity Plan Development."
The ongoing activity plan is a master plan and schedule of the various activities and programs that are being implemented at FSV. These various activities are not a constraint to plant startup.. -.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 55
" Safety Related Equipment Walkdown First Phase, Operability."
This item represented the walkdown activity, engineering analysis, and initiation of maintenance activities to address generic maintenance issues that were identified during the EQ walkdown.
(COMPLETE)
Item 56
" Safety Related Equipment Walkdown Second Phase, Plan Development." This item included the development of a long term program plan to systematically perform a plant walkdown to verify the as-built condition, name plate data, and identifying possible program and procedure changes to enhance the maintained condition of plant equipment, thereby improving plant operability.
(CCMPLETE)
Item 57
" Management Change Impact Assessment /NRC Approval."
The impact of management position vacancies will be evaluated.
Corrective Action will be developed as required.
(Reference P-87090, March 5, 1987)
Item 58 "NRC approval of EDG Power Modification Submittal".
This activity involves the NRC review and approval of electrical indepdendence and emergency diesel generator issues. The key issues requiring approval prior to restart were:
1.
Manual capabilities exist to energize the associated 480 VAC essential buses from at least one EDG set for a postulated single failure in the permissive control logic circuitry.
2.
Paralleling of the two redundant EDG sets is precluded for a single failure in the permissive control logic circuitry.
3.
Demonstrate through testing the operability of DC control power automatic throwover feature in each 480 VAC essential switchgear unit and feeder breaker protective coordination.
A meeting with NRC in Washington, DC was held on February 9, 1987 to discuss schedules and commitments for these items.
(Reference G-87078)
(COMPLETE) _.
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FSV RESTART-AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 59
" Review / Revise Emergency Procedure for APP-R."
This activity includes review of the existing Emergency Procedure to reflect the Fire Protection paths identified in PSC's Appendix R
submittals.
Appropriate revision or preparation of new procedures is also included.
Item 60 "Close Start-up Related CAR Items." This activity involved two CARS:
- 1)86-105 Resolution of deficiencies listed in SMAP-1 as a result of EQ walkdown performed October, 1985; and 2)86-167 Resolution of retesting required by SPAP-1.
(COMPLETE)
Item 61
" Pre-startup Monitoring." This item involves a review of selected areas of plant activities such as testing, TCR's, SSR's, CWP's, procedural updates, training, etc, for the purpose of verifying the completion of activities which may effect startup.
Item 62
" Prepare Breaker Test Auto Throwover Scheme (CN-2529)". This activity is a consnitment made by PSC to NRC at the January 13, 1987 Arlington, Texas meeting.
This was a subject related to the Emergency Diesel Generator electrical independence activity.
(COMPLETE)
Item 63
" Perform Breaker Test Auto Throwover Scheme (CN-2529)."
Item 64
" Perform Critical Evaluation of SS and SRO." This activity includes all efforts involved with the development and implementation of an evaluation process for Shift Supervisors (SSs) and Senior Reactor Operators (SR0s).
Item 65
" Alternate Cooling Method Corrective Action CN-2007."
This CN required moving Alternate Cooling Method Transfer Switches to meet Appendix R-Separation Criteria. Actual construction work and testing are completed.
(COMPLETE)
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 66
" Complete Licensing Commitment Log Restart Issues (LERs)." This log is comprised of all LERs which must be closed out prior to restart of the plant.
Remaining LERs:
86-028 - Completion of CWP for grounding of spare conductors.87-003 C Engine Start / Failure Analysis (Item 71).
l 87-006 - Repair of fire barrier seals.
l 87-008 - Performance test.
Item 67 "EES Transient Analysis."
There are other.
accidents / transients evaluated in the FSAR which rely on the EES for decay heat removal besides Safe Shutdown Cooling with firewater. This item involves reanalysis of these accidents / transients to verify that the decay heat removal options in the FSAR are adequate for power operation at the 82% power level.
The results of these analyses were submitted to the the NRC to support operation at the 82% power level.
(Reference P-87053, February 6, 1987.)
(COMPLETED)
Item 68
" Wrong Loop Dump Analysis "
This item involved reanalysis of the steam generator tube leak with wrong loop dump accident scenario. The reanalyses included all available options for this accident.
Documentation of the results of the analyses were submitted to the NRC to support operation at the 82%
power level.
(Reference P-87053, February 6, 1987.)
(COMPLETED)
Item 69
" Supplemental 82%
Power Level Submittal."
This activity included the response to nine NRC questions which were telecopied to PSC Licensing in late January and Revised GA Report GA909269, Issue A, "EES Cooldown for EQ and Appendix R Events With Vent Lines." (P-87055)
(COMPLETE)
Item 70
" Additional Sup,nlemental 82% Power Level Submittal."
This activity involves i.ha preparation of PSC responses to further NRC questions on the 82% power level submittal.
This also covers the continued dialogue between NRC and PSC on these issues.,
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 71 "C
Engine Start Failure Analysis."
Root cause analysis and resolution of -problems associated with "C"
Engine (Emergency Diesel Generator).
(Reference LER 87-003, P-87088)
Item 72 "NRC Review and Approve SSC Flowpath." This activity involves the NRC review of PSC Safe Shutdown Cooling submittals-involving reheater elimination analysis, EES cooling capability, and FSAR accident reanalysis.
This activity also includes NRC review and approval of 35% and 82% power levels.
4 Issue 73 "PPS Spurious Trip Analysis." Analysis to determine root cause and define resolution for false trips.
(One potential cause is thought to be electrical
" noise.")
- ; ev 74
" Hanger / Snubber Setpoint Issue."
This activity l'"y"--
requires that various spring loaded pipe snubbers be inspected for proper settings prior to startup.
Item 75
" Correct Demineralization Regeneration Problems."
This item covers the replacement of acid lines in the demineralization area.
(Complete to support startup.)
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OVERSIZE
~ DOCUMENT PAGE PULLED SEE APERTURE CARDS 4
NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492 = 8989
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