ML20211D081
| ML20211D081 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/17/1987 |
| From: | Brey H PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-87062, NUDOCS 8702200320 | |
| Download: ML20211D081 (17) | |
Text
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16805 WCR 19 1/2, Platteville, Colorado 80651 February 17, 1987 Fort St. Vrain Unit No. 1 P-87062 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)
Gentlemen:
Attached 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.
Attachment 1 is a schedule for all of the identified activities that I
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 l on Attachment 1.
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P'87062 Paga 2 February 17, 1987 Attachments 1 and 2 represent detailed internal PSC schedular information and are not intended to create, change, or delete previous PSC commitments to the NRC. PSC will provide updates to the attached schedule twice per month for the duration of the current outage.
Please note that a new activity numbering system has been adopted in order to simplify activity tracking, and as a result all item numbers have been changed from our previous submittal.
If you have any questions concerning the information provided herein,
.please contact Mr. M. H. Holmes at (303) 480-6960. ,
Very truly yours, e
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
0 ATTACHMENT 2 TO P-87062 FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS
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 53). 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 subdivided 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 Completion Certification (Item 53).
Item 3 "CCT's/FT's (EQ Certification)" represents the post modification cold checkout testing and functional testing activities (CCT's/FT's) associated with the modification activities of Item 2.
Item 4 "SSR Work (EQ Certification)" represents 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 53).
Item 5 "PMT's (EQ Certification)" represents the post maintenance testing activities (PMT's) associated with the maintenance activities of Item 4.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 6 "EQ Outage Work Required for Non-Nuclear Dryout."
This item represents that portion of the plant outage modification and maintenance activities that are not required to be complete prior to EQ Certification but must be complete to allow non-nuclear dryout of. the core. This activity may include some EQ associated work identified as not having to be complete prior to the Certification but which must be complete prior to plant criticality.
This item is subdivided into five categories for status-tracking accuracy. The five categories are:
CN/CWP work, CCT's/FT's, SSR work, PMT's, and surveillances. These categories are further defined by Items 7, 8, 9, 10, and 11 respectively.
Item 7 "CN/CWP Work (Non-Nuclear Dryout)" represents plant modification work (Change Notice / Controlled Work Procedure) equipment and systems required for non-nuclear core dryout (Item 11).
Item 8 "CCT's/FT's (Non-Nuclear Dryout)" represents the post modification cold checkout testing and functional testing activities (CCT's/FT's) associated with the modification activities of Item 7 .
Item 9 "SSR Work (Non-Nuclear Dryout)" represents plant preventive and corrective maintenance activities (SSR's) performed on equipment and systems required for non-nuclear core dryout (Item 11).
Item 10 "Surveillances (Non-Nuclear Dryout)." This item represents plant surveillance testing activities performed on equipment and systems required for non-nuclear core dryout (Item 11).
Item 11 "Non-Nuclear Dryout" represents 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 will be accomplished with use of the reheater which will be supplied with steam from the Auxiliary Boiler.
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 12 "EQ Outage 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 criticality. This activity may include some EQ associated work identified as not having to be complete prior EQ Certification (Item 53).
These activities are start-up related. This item is also subdivided into four scheduling categories for status-tracking accuracy. The four~ categories are:
CN/CWP work, CCT's/FT's, SSR and PMT work, surveillances. These categories are further defined by items 13, 14, 15, and 16, respectively.
Item 13 "CN/CWP Work (Reactor Criticality)" represents plant modification work (Change Notice / Controlled Work Procedure) on equipment and systems required for reactor criticality (Item 25).
Item 14 "CCT's/FT's (Reactor Criticality)" represents the post modification cold checkout testing and functional testing activities (CCT's/FT's) associated with the modification activities of Item 13.
Item 15 "SSR/PMT Work (Reactor Criticality)" represents plant preventive and corrective maintenance activities (SSRs and PMTs) performed on equipment and systems required for reactor criticality (Item 25).
Item 16 "Surveillances (Reactor Criticality)." This item represents plant surveillance testing activities performed on equipment and systems required for reactor criticality (Item 25).
Item 17 " Power Ascension Schedule Development / Submittal (Rise to Power)." This activity includes the development of the plant's rise to power schedule. This plan has been developed and will be updated on a bi-weekly basis.
Item 18 "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 53).
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 19 " Preventive Maintenance Program (First Phase)." This item includes the development of PM program controls and implementation of vendor . recommended and EQ required preventive maintenance activities.
Item 20 "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.
Item 21 "Startup NCR Closures (NCR Log)."~ This item includes the identification, generation, disposition and QA approval of non-conforming conditions that will prohibit plant criticality (Item 25) if not closed out.
Item 22 " Steam Generator 6 Inch Vent Design, Material Procurement and Pre-fabrication." This item represents- the preparation activities for the 6 inch Vent modification (Item 23). This preparation includes the planning, design, procurement and pre-fabrication necessary to support the plant 6 inch vent modification activities.
Item 23 "EES Vent Installation" represents the period for the installation of the Economizer-Evaporator-Superheater (EES) Section 6 inch vent lines on the main steam line. These plant modifications are required by the Safe Shutdown Cooling Technical Specification change using fire water for cooling.
Item 24 " 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 25 " Plant Criticality / Nuclear Dryout/R.0. Training Starts." 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. This activity also includes Reactor Operator Training Starts.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 26 "SLRDIS Technical Specification Submittal / Review and Approval by NRC" includes the SLRDIS Technical Specification change preparation and submittal to the NRC. This activity also includes the NRC review and approval period. When this item is complete, the SLRDIS Emergency Procedure revisions can be issued (Item 27). Target response date 2/6/87.
Item 27 " Release SLRDIS Emergency Procedures." This item involves the " issue for use" of the Emergency Procedure revisions that were required by SLRDIS.
These procedure revisions cannot be " issued for use" until NRC approval of the SLRDIS Technical Specification, but must be issued prior to SLRDIS activation /SPRDS Deactivation (Item 29).
Item 28 "SLRDIS Design and Construction." This activity includes the plant design and modification activity required to install SLRDIS and the follow-up testing of this system. When this activity is complete along with Items 26 and 27, then SLRDIS can be activated (Item 29).
Item 29 "SLRDIS Activation /SPRDS Deactivation." This activity involves the activation of SLRDIS and the deactivation of the existing SPRDS. This activity cannot be implemented until Items 26, 27, and 28 are completed.
Item 30 " 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.
This item is complete.
Item 31 " Safety Related Equipment Walkdown Second Phase, Plan Development." This item includes 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 prcgram and procedure changes to enhance the maintained condition of plant equipment, thereby improving plant operability.
Item 32 " Core Performance Testing." This item includes the activities related to verifying reactor core Segment Three design margins and performance characteristics.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS 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 "NCR History Review for EQ Impact." This issue involves the review of closed out Non-Conformance Reports associated with EQ related equipment. This review (EE-EQ-0044) has been completed by the Vendor and is currently under review by PSC.
Item 36 " Complete EQ Procedural Effort." This activity involves the EQ program controls development, revisions and approvals. A system of procedures has been established to implement the ongoing EQ program at FSV in accordance with the upper level administrative controls and guidelines (Item 39).
When this activity is complete, the EQ program will be established allowing a portion of the EQ MCAR (Item
- 49) to be closed out.
Item 37 " Complete EQ Training Effort (Except Make-up)." This activity involved the EQ training effort necessary to establish the appropriate knowledge level for the personnel that will maintain the EQ program at FSV.
Item 38 " Complete Make-up EQ Training." This activity provided make-up classes for those personnel that could not attend the original EQ training courses of Item 37.
Item 39 " Final Approval of Level 1 Policy and Procedure G-16."
This activity involved the development and approval of the upper tier EQ Policy, Guideline and Program
, Procedure. These documents define the scope of the EQ program and the system of administrative procedures that implement the EQ program at FSV (Item 36). These documents were submitted to the NRC in the EQ Audit Module Submittal (Item 52).
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 40 '
" Finalize MEL." This item represented the final design document approvals for establishing the EQ Master Equipment List. The MEL was submitted to the NRC in the EQ Audit Module Submittal (Item 52).
Item 41 " Finalize Temperature Profiles - Reactor Building."
This issue involved the final engineering analysis required for the development and approval of the post HELB environment temperature profiles for the Reactor Building. This analysis was submitted to NRC with PSC letter P-86664, December 12, 1986.
Item 42 " Finalize Temperature Profiles - Turbine Building."
This issue involved the final engineering analysis required for the development and approval of the post HELB environment temperature profiles for the Turbine Building. This analysis was submitted to NRC with PSC letter P-86673, December 19, 1986.
Item 43 "EQ CN Approval Memo's/ Follow-up Activities." The Work Review Committee approved CN document packages which required additional follow-up actions by NED.
These follow-up actions were documented on memo's from the Station Manager to NED managers.
Item 44 " Final CN/CWP P.O. Reviews." This activity involves 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.
Item 45 " Complete SMAP-27 Binder Reviews (EQ)." This activity includes the maintenance review of the EQ binders, in accordance with SMAP-27, to incorporate the EQ maintenance and surveillance requirements into the plant working procedures.
Item 46 " Binder Document Updates and Telecon Resolution."
This activity involves the incorporation of document changes to the EQ binders as a result of the third party EQ audit. This activity also includes replacing vendor telecons with letters to the vendor requesting verification of the information in the telecons.
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 47 " Finalize EQ Binder CN's." This activity includes the final engineering and administrative approval of the EQ Binder Change Notice (CN) documents to incorporate these documents into the controlled design document system. When this activity is finalized. Item 45 can be completed.
Item 48 " Update 0 & M Library (EQ Related)." This issue involves the controlled vendor manual program developed in response to Generic Letter 83-28 and the implementation of this program for the EQ related vendor manuals. This activity is an input to the EQ Maintenance Review SMAP-27 (Item 45).
Item 49 "EQ MCAR Closure." This issue involves the closeout of Management Corrective Action Request 85-001 which was generated by QA as a result of insufficient EQ program controls. This item will be resolved and closed out with the completion of Items 50 and 36.
Item 50 "Close EQ Related CAR Items." This activity involves the disposition and QA approval of EQ related Corrective Action Requests. This activity consists of EQ related CARS that must be complete before the EQ MCAR 85-001 (Item 49) can be closed out and additional EQ CAR items not tied to the MCAR close-out.
Item 51 "PSC Audit Prep." This activity represented the final preparation for the NRC EQ Audit, including trial audits, presentation preparation, security clearances and facilities for the NRC inspectors.
Item 52 " Resolution of Audit Findings." This activity involves the resolution of any audit findings resulting from the NRC EQ Audit (Item 60).
Item 53 "Eq Completion Status Letter." This item is the PSC generated letter which indicates progress / status of the FSV Program Activities.
Item 53a "EQ Completion Certification Letter." This item represents the PSC generated letter certifying to the NRC that the FSV EQ program has been substantially implemented and meets the requirements of 10CFR50.49.
FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 54 "SMAP-25 Review / Final SSR Closure." This activity represents the EQ review performed on all EQ related Station Service Requests (SSR's) to ensure that the EQ basis has been maintained during nomal maintenance activities.
Item 55 " CADS Walkdown Closure." This activity involves the closeout of the EQ walkdown documentation.
Maintenance deficiencies were identified during the walkdown generating Corrective Action Data Sheets (CADS) which are closed out when the associated SSR work has been completed.
Item 56 "NRC Issue SER on Profiles." This activity include.s 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.
Item 57 " 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 58 "EQ Audit Module Submittal." This item represented the PSC submittal to the NRC of the key EQ program documents necessary for the NRC Audit preparation.
This submittal was made prior to the NRC EQ Audit (Item 60) to NRC Region IV at the Arlington, Texas meeting on January 13, 1987.
Item 59 "NRC I & E Region IV PEP and Pre EQ Audit Meetings."
This item represented the scheduled NRC/PSC meeting at Region IV to discuss the PEP status and EQ Audit preparations.
Item 60 "NRC I & E EQ Audit / Findings." This activity represented the NRC EQ Audit held on 1/26/87 and the identification of audit findings to PSC. Audit finding resolutions were initiated on a daily basis upon the identification of any finding.
Item 61 "NRC EQ Audit Evaluation and Staff Review." This item ,
represents the NRC activity, post EQ Audit, to assess I the FSV EQ program success, and to prepare staff recommendations to the Commission for plant startup. ,
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FSV RESTART AND POWER ASCENSION SCHEDULE LINE ITEM DESCRIPTIONS Item 62 "NRC Comissioner's Meeting." The NRC Commissioner's meeting will assess the FSV progress to resolve EQ and other regulatory and management issues and to obtain NRC's approval for plant startup.
Item 63 "NRC Lag Time Until Permission to Restart is Granted."
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 64 " Emergency Diesel Generator Near Term Fix (CN-1622F)."
This activity involved a design change in the source point of DC control power to the undervoltage protection system on the 480 VAC essential buses, which initiates EDG start upon loss of voltage. The change in the source point was from the DC bus direct to the DC control power automatic throwover scheme in each of 480 VAC switchgear units. Completed.
Item 65 " Safe Shutdown Cooling Flowpath 35% Submittal." This activity included the technical evaluation of power operation that can be supported by the Safe Shutdown Cooling flowpaths and the existing Tech. Specs. Note:
this is submitted for NRC information only.
(Reference PSC letter P-86682, December, 30,1986)
Item 66 " Implement Revised RERP Accountability." This activity includes the staff augmentation of the revised RERP Accountubility program. This item is an NRC Comitment to be completed prior to plant startup.
Item 67 "EDG Elect. Ind, & DC Cnti Pwr Mod Submittal." This activity involves preparing a PSC submittal to the NRC to address the EDG Independence and the DC Control Power Single Failure Issues. The PSC submittal includes an in-depth engineering evaluation on the EDG independence and an assessment of the results. In addition, the submittal contains comitments associated with design changes and tests to resolve short and long term issues on the DC Control Power System. All comitments include a well defined schedule. All of the above items are in response to discussions held with the NRC staff on August 14 and December 9, 1986. (Reference P-87008, dated January 9,1987)
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FSV RESTART AND POWER ASCENSION SCHEDULE i LINE ITEM DESCRIPTIONS s
9 Item 68 " Safe Shutdown Cooling With EES Only." This activity ~
involved the reanalysis with reliance upon EES
( Eco nom i ze r- Eva po ra to r- Su pe rh ea te r ) sections only,to achieve Safe Shutdown Cooling. Note: this submittal is for NRC information onl (Reference PSC letter P-86683, December 30, 1986) y.
Item 69 " Reheater Elimination Analysis Specification)." This activity documented the Safety -
(Technical ~
f' Analyses and submited the License amendment request -
necessary to eliminate the reheaters from the -
, licensing basis at 82% power level to achieve Safe '
Shutdown Cooling. (P-87002 dated January 15,1987) "c ~
Item 70 "LER 86-021 Corrective Action CN-2424."
involves a firewater single failure modification.
This CN '
_[N Three manual valves (one 10-inch and two 4-inch ,
valves) have been installed and leak tested. -
Item 71 " Review PEP Commitments for Constraints to Startup." ,
This item represented the management improvements and ,
performance enhancements undertaken by PSC (PEP, SALP, TRM,QEP) to emphasize their importance to plant -
s
. s restart and future operations. ?^ ,
Item 72 " 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 ,
l 1s also included. .
Item 73 " Firewater on Emergency Feedwater Header". A test was conducted to detennine the time required to install the Firewater Spool Piece on Emergency Feedwater Header (EFH). The EFH System drain time analysis is currently underway. The results of this analysis will -
- determine the final design of system cross-ties.
Item 74 " Pre-startup Monitoring." This item involves a rev'iew .
of selected areas of plant activities such as testing, . . ,
TCR's, SSR's, CWP's, procedural updates, training, <
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- etc, for the purpose of verifyirg the completion of activities which may effect startup. e-i
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-I LINE ITEM DESCRIPTIONS m *
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Item 75' x "NRC approval of EDG Power Modification Submittal".
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, This activity involves the NRC review and approval of
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the submittal identified in Item 67. The key issues requiring approval prior to restart are:
' - 1. Manual capabilities exist to energize the
- < ~ associated 480 VAC essential buses from at least
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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 g breaker protective coordination.
A meeting- with NRC in Washington, DC was held on m February 9, 1987 to discuss schedules and conunitments
', .for these items.
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,,- s . Item 76 '
" Prepare Breaker Test Auto Throwaver Scheme (CN-
~
e 2529)". This activity is a commitment made by PSC to
, NRC at the January 13, 1987 Arlington, Texas meeting.
This is a subject related to the Emergency Diesel J. -
Geherator electrical independence activity.
item 77 " Perform Breaker Test Auto Throwover Scheme (CN-2529)."
~"' Iteni 78 ~
" Perform Critical Evaluation of SS and SRO." This activity includes all efforts involved with the
. t
_~ development and implementation of an evaluation
.% process for Shift Supervisors (SSs) and Senior
,- Reactor Operators (SR0s).
'.'Itetd 79 "I & E Bulletin 86-002 Corrective Action CN-2007."
This CN required moving Alternate Cooling Method s Transfer Switches to meet Appendix R Separation Criteria. Actual construction work and testing are completed.
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Item 80 " 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.
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FSV RESTART AND POWER ASCENSION SCHEDULE.
LINE ITEM DESCRIPTIONS-i Item 81 " Tendon Testing / Heavy Loads Conflict." This activity seeks resolution of two conflicting commitments:
- 1) Movement of heavy loads over the PCRV are limited during power operation per Heavy Loads Program
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- (NUREG 0612).
- 2) PSC commitment to inspect PCRV tendons per P-85071 dated March 5, 1985 (Revised Tendon Surveillance Program).and P-86042 (First Six-Month PCRV Tendon Interim Surveillance and Status Report).
l' Item 82 "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, Feburary 6, 1987)
Item 83 " 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 i submitted to the NRC to support operation at the 82%
power level. (Reference P-87053, February 6, 1987)
Item 84 " Prepare and Submit Power Level Commitment Letter."
This letter from PSC to NRC requested authorization for plant startup and power ascension with hold points for NRC approval at specifically designated power levels of 10%, 35% and 82%. (Reference P-87038, dated January 30,1987) l l Item 85 " Supplemental 82% Power Level Submittal." This activity includes 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) i i
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FSV RESTART AND POWER ASCENSION SCHEDULE !
LINE ITEM DESCRIPTIONS
.I Item 86 "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.
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OVERSIZE DOCUMENT PAGE PULLED SEE APERTURE CARDS NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS 1 APERTURE CARD /HARD COPY AVAILABLE FROM RECORD SERVICES BRANCH,TIDC FTS 492-8989
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