ML060530590
| ML060530590 | |
| Person / Time | |
|---|---|
| Site: | Oconee  (DPR-038, DPR-047, DPR-055) |
| Issue date: | 02/14/2006 |
| From: | Brandi Hamilton Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TSC-2004-09 | |
| Download: ML060530590 (12) | |
Text
I-.
ukeb BRUCE H HAMILTON Vice President I-OPPower.
Oconee Nuclear Station Duke Power ONO1 VP / 7800 Rocherster Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax February 14, 2006 U.
S. Nuclear Regulatory Cormmission Washington, D. C. 20555 Attention: Document Control Desk
Subject:
Oconee Nuclear Station Docket Numbers 50--269, 270, and 287 Final Review Documentation Associated with the RPS/ESPS Digital tJpgrade Technical Specification Change (TSC) Number 2004-09, Supplement 7 In a submittal dated February 14, 2005, Duke Energy Corporation (Duke) proposed to amend Appendix A, Technical Specifications, for Renewed Facility Operating Licenses DPR-38, DPR-47 and DPR-55 for Oconee Nuclear Station, Units 1, 2, and 3. The License Amendment Request (LAR) requests NucLear Regulatory Commission (NRC) to approve the Reactor Protective System (RPS)/Engineered Safeguards Protective System (ESPS) digital modification and associated Technical Specification (TS) change.
The NRC advised Duke by letter dated January 11, 2006, that it will not complete its review of the RPS/ESPS LAR by the October 2006 outage for Unit: 1 as requested by Duke.
The letter further advised Duke that the NRC has suspended review of the LAR until such time final information related to Duke's application has been submitted and docketed.
The letter also provided a list of the areas where final documentation is required to support the NRC review. provides a table that lists the documents identified in the January 11, 2006, letter.
These documents are listed by titLe and document number.
For each document in the table, Duke has provided the letter by which the document was formally submitted as well as any comments regarding the document.
4 0 www. dukepower. corn
iI, U. ',. Nuclear Regulatory Commission February 14, 2006 Page 2 NRC letter dated January 11, 2006, also points out several unresolved technical issues.
All of these issues have been addressed in responses to RAIs in Duke letter dated February 3, 2006 (TSC 2004-0)9, Supplement 6).
Following staff review of the responses to these technical issues, Duke requests further discussions to promptly resolve any additional questions concerning these issues.
The enclosure to the January 11, 2006, NRC letter indicates that submission of procedures and test reports for the factory acceptance test (FAT) and site acceptance test (SAT) after July 1, 2006, could delay a February 2007 NRC review completion date.
As indicated in Duke's letter dated February 3, 2006, the FAT schedule has been delayed resulting in an overall delay to the SAT and associated reports.
Due to the deferral of installation of the digital RPS/ESPS on Unit 1, Duke has re-evaluated its commitments associated with testing.
The FAT procedures will be provided on or before May 10, 2006. The FAT will be performed from May 10 to IMay 30, 2006.
The FAT test results will be provided by June 30, 2006.
After completion of the FAT, the system will be used until no later than October 1, 2006 by procedure writers to perform validation and verification activities on draft Unit 1 plant procedures.
The Unit 1 equ:Lpment will then be moved from the maintenance test facility to make room for Unit 3 equipment.
Prior to deferral of Unit 1 installation, a system availability run and Site Acceptance Testing (SAT) had been scheduled to begin after conclusion of FAT. Since no functional or performance requirements will be verified or substantiated during the availability run or the SAT, Duke has delayed these two activities pending completion of detailed implementation plans for Unit 1, which is now scheduled for Fall 2009.
The FAT is required to assure defined functional and performance requirements are met for the replacement system.
The SAT is normally run after shipment to the site to ensure integrity of the equipment is maintained.
However, since the equipment is already on site and not being shipped, there is no need to run additional performance test-ing.
U. S. Nuclear Regulatory Commission February 14, 2006 Page 3 provides a list of NRC commitments associated with this submittal. to Duke's letter dated February 3, 2006, provides the remaining commitments associated with the RPS/ESPS LAR.
This letter fulfils the NRC information needs identified in the January 11, 2006, letter.
As such, Duke requests NRC to commit to completing its review no later than February, 2007.
Please promptly inform us of any additional information needs.
If there are any questions regarding this submittal, please contact Boyd Shingleton at (864) 885-4716.
Very truly yours, B. H. Hamilton, Vice President Ocornee Nuclear Site
U. S. Nuclear Regulatory Commission February 14, 2006 Page 4 cc:
Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-14 H25 Washington, D. C.
20555 Dr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission -
Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr. M. C. Shannon Senior Resident Inspector Oconee Nuclear Station Mr. Henry Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health & Environmental Control 2600 Bull Street Columbia, SC 29201
U. S. Nuclear Regulatory Commission February 14, 2006 Page 5 B. H. Hamilton, being duly sworn, states that he is Vice President, Oconee Nuclear Site, Duke Energy Corporation, that he is authorized on the part of said Company to sign and file with the U. S. Nuclear Regulatory Commission this revision to the Renewed Facility Operating License Nos.
DPR-38, DPR-47, DPR-55; and that all the statements and matters set forth herein are true and correct to the best of his knowledge.
B. H. Hamilton, Vice President Oconee Nuclear Site S bscribed and sworn to before me this
/ a day of t paed i2006 Notary Public My Commission Expires:
Z-I
ATTACHMENT 1 Pertinent Information Related to Documents Identified in January 11, 2006, NRC Letter Document Title Doc. No.
Comments 1
Detailed System Unknown The system architecture is included in the first half of the SDD (FANP Architecture Document No. 51-5065423). Revision 2 to the SDD was provided in electronic format to NRC staff via compact disk on 1/11/06 and is docketed by reference in Supplement 6 submitted 2/3/06. Revision 3 to the SDD was provided in electronic format to NRC staff via compact disk on 1/14/06 and is docketed by reference in this Supplement.
2 Oconee 1 RPS&ESFAS RTM DOCUMENT RELATED TO FACTORY ACCEPTANCE TEST (FAT)
(Engineered Safety This document is a tool that aids in understanding the origin of the design Features Activation (SIC) requirements and is updated periodically as a prerequisite activity occurs.
System) Requirements The initial version of this document was provided in electronic format to NRC Traceability Matrix staff via compact disk on 8/2/05 and docketed by reference in Supplement 1 dated 10/6/05. Duke provided electronic updates on 10/4/05, 11/1/05,1/10/06 and 1124/06. The latest version (1/24/06) of the RTM was docketed by reference in Supplement 6 dated 2/3/06. One additional update is planned (after FAT is complete). This document is typical of all three units. Any differences between units will be insignificant and will not alter the functional desig1.
3 Teleperm XS Product 2005/26 Provided in electronic format to NRC staff via electronic mail on 12/1/05 and Information on Release docketed by reference in Supplement 6 dated 2/3/06.
3.0.7A of TXS Software 4
Oconee Nuclear Station 38-5069821 Paper copy (Revision 0) provided during the November 2005 NRC audit.
TXS RPS/ESPS Revision 0 provided in electronic format to NRC staff via electronic mail on Replacement System 1/25/06 and docketed by reference in Supplement 6 dated 2/3/06. This Cabinet Design:
document is typical of all three units. Any differences between units will be 1 PPSCA0005 insignificant and will not alter the functional design.
5 Oconee Nuclear Station 38-5069822 Paper copy (Revision 0) provided during the November 2005 NRC audit.
TXS RPS/ESPS Revision 0 provided in electronic format to NRC staff via electronic mail on Replacement System 1/25/06 and docketed by reference in Supplement 6 dated 2/3/06. This Cabinet Design:
document is typical of all three units. Any differences between units will be 1 PPSCA0006 insignificant and will not alter the functional design.
6 ONS Units 1, 2, & 3 51-502388 DOCUMENT RELATED TO FAT RPS/ESF Controls One additional update may be made after FAT is complete, if necessary.
Upgrade Failure Mode Revision 0 of the FMEA was provided in electronic format to NRC staff via and Effects Analysis electronic mail on 12/15/05 and docketed by reference in Supplement 5 dated 1/12/05.
7 ONS 1, 2, & 3 RPS/ESF 51-5045379 Paper copy provided during the November 2005 NRC audit. Provided in Controls Upgrade electronic format to NRC staff via electronic mail on 12/1/05 and docketed by Design Specification for reference in Supplement 6 dated 2/3/06. Revisions 1 and 2 were provided in Key Locks and Key electronic format to NRC staff via electronic mail on 2/9/06 and 2/13/06, Switches respectively, and are docketed by reference in this Supplement.
February 14, 2006 Page 2 Document Title Doc. No.
Comments 8
Software Requirements 51-5045380 The initial version of this document was provided in electronic format to NRC Specification,ONS-1 staff via compact disk on 8/23/05 and docketed by reference in Supplement 1 RPS/ESF Software dated 10/6/05. Revisions 3 and 4 to this document was provided in electronic Requirements format to NRC staff via electronic mail on 1/6/06 and 2/9/06, respectively, and Specification (QA1) are docketed by reference in this Supplement. This document is typical of all three units. Any differences between units will be insignificant and will not alter the functional design.
9 ONS Unit 1: RPS and 51-5052833 This document was provided in electronic format to NRC staff via electronic ESFAS Replacement mail on 2/9/06 and is docketed by reference in this Supplement. This Project Open Item Form, document is typical of all three units. Any differences between units will be
'HW Typicals for CRD insignificant and will not alter the functional design. Note: The 01 was (Control Rod Drive) UV actually written against 32-5061401-01, Step 13.2.2 rather than 51-5052833, (under voltage) Test Doc Step 3.12.
Jacks, Doc Step 3.12 10 ONS 1, 2, & 3 RPS/ESF 51 -5052833 Paper copy provided during the November 2005 NRC audit. This document Controls Upgrade was provided in electronic format to NRC staff via electronic mail on 1/25/06 Hardware Design and docketed by reference in Supplement 6 dated 2/3/06. Revision 3 was Solutions provided in electronic format to the NRC staff via electronic mail on 2/13/06 and is docketed by reference in this Supplement.
51-5055761 The initial version of this document was provided in electronic format to NRC ESFAS Configuration staff via electronic mail on 10/6/05 and docketed by reference in Supplement Management Plan 1 dated 10/6/05. This document was revised to label it a Units 1, 2, and 3 document (51-9006444), provided in electronic format to NRC staff via electronic mail on 1/26/06 and is docketed by reference in this Supplement.
12 Oconee Nuclear Station, 51-5058134 Paper copy provided during the November 2005 NRC audit. This document Units 1, 2, & 3 RPS/ESF was provided in electronic format to NRC staff via electronic mail on 1/25/06 Controls Upgrade ID and docketed by reference in Supplement 6 dated 213/06.
Coding Concept 13 ONS Units 1, 2, & 3 51-5058661 The initial version of this document, which was referred to as draft, was RPS/ESFAS Controls provided in electronic format to NRC staff via electronic mail on 6/16/05. The Upgrade Verification and document was provided again in electronic format to NRC staff via electronic Validation Plan mail on 8/1/05 and docketed by reference in Supplement 1 dated 10/6/05.
The latest revision (51-90104194 - renumbered due to its transition to a Units 1, 2, and 3 document) of the V&V plan (design stage) was provided in electronic format to NRC staff via electronic mail on 1/26/06 and is docketed by reference in this Supplement.
14 ONS Unit 1 RPS/ESFAS 51-5065423 The initial version of this document was provided in electronic format to NRC Controls Upgrade staff via electronic mail on 9/29/05 and docketed by reference in Supplement Software Design 1 dated 10/6/05. Revision 2 to the SDD was provided in electronic format to Description NRC staff via compact disk on 1/11/06 and is docketed by reference in Supplement 6 submitted 213/06. Revision 3 to the SDD was provided in electronic format to NRC staff via compact disk on 2/14/06 and is docketed by reference in this Supplement. This document is typical of all three units. Any differences between units will be insignificant and will not alter the functional design.
February 14, 2006 Page 3 Document Title Doc. No.
Comments 15 ONS Unit 1 RPS/ESFAS 51-5066516 The in tial version of this document was provided in electronic format to NRC Controls Upgrade staff via electronic mail on 9/29/05. Revision 2 was provided in electronic Software Requirements format to NRC staff via electronic mail on 2/9/06 and is docketed by reference Review Report in this Supplement. Another V&V review is being performed on Revision 4 to the SRS (51-5045380-04) and will documented in a later revision of the SRR (expected to be issued by 2128/06). This document is typical of all three units.
Any differences between units will be insignificant and will not alter the functional design.
51-9001334 This document was provided in electronic format to NRC staff via electronic ESFAS Faclory mail on 11/30/05 and docketed by reference in Supplement 4 dated 11/30/05.
Acceptance Test Plan The FAT plan was revised to take out Functions 2 and 12 (Tcold) and an updated version of this document (Revision 2) was provided in electronic format to NRC staff via electronic mail on 1/26/06 and docketed by reference in Supplement 6 dated 213/06. Revision 4 was provided in electronic format to NRC staff via electronic mail on 2/14/06 and is docketed by reference in this Supplement. This document is typical of all three units. Any differences between units will be insignificant and will not alter the functional design.
17 Dedication Package for 51-9002116 This document was provided in electronic format to NRC staff via electronic Absopulse Power Supply mail on 11/1/05 and docketed by reference in Supplement 2 dated 11/3/05.
18 ONS Units 1, 2, & 3 51-9005043 This document was provided in electronic format to NRC staff via electronic RPS/ESFAS Controls mail on 11/2/05 and docketed by reference in Supplement 2 dated 11/3/05.
Upgrade Software Safety Plan 19 ONS Units 1, 2, & 3 51-9008803 This document was provided in electronic format to NRC staff via electronic RPS/ESFAS Controls mail on 12/20/05 and docketed by reference in Supplement 5 dated 1/12/06.
Upgrade Software Installation Plan 20 TXS Supplemental EQ 66-5015893 This document was provided in electronic format to NRC staff via electronic (Equipment mail on 5/3/05 and docketed by reference in Supplement 1 dated 10/6/05.
Qualification) Summary Test Report 21 ONS RPS/ESFAS 66-5065212 DOCUMENT RELATED TO FAT Replacement Project EQ This document was provided in electronic format to NRC staff via electronic Summary Test Report mail on 1/4/06 and docketed by reference in Supplement 5 dated 1/12106.
The body of the report establishes EQ requirements and will not be revised.
Section 4.9 of the report has 5 open items related to EQ testing that are currently being addressed. The cabinet internal temperature EQ test is being conducted during the FAT. The current status of these items was provided by electronic mail on 2/13/06. The status of these five open items will be
_updated as changes occur.
22 TUV Certificate on 968/K 110/02 This document was provided in electronic format to NRC staff via electronic Communication mail on 11/2/05 and docketed by reference in Supplement 2 dated 11/3/05.
Processor
I February 14, 2006 Page 4 Document Title Doc. No.
Comments 23 TUV Documentation on 968/K 110.01/02 This document was provided in electronic format to NRC staff via electronic SCP2 Testing mail on 11/30/05 and docketed by reference in Supplement 4 dated 11/30/05.
24 TUV Certificate on 968/K 109/02 This document was provided in electronic format to NRC staff via electronic Processing Module mail on 5/10/05 and docketed by reference in Supplement 1 dated 10/6/05.
25 FANP (Framatome ANP)
NGLP/2004/en/00 This document was provided in electronic format to NRC staff via electronic Report, "TELEPERM XS 94 mail on 10/31/05 and docketed by reference in Supplement 2 dated 11/3/05.
Simulation - Concept of Validation and Verification 26 Configuration NSD 106 The current version of NSD 106 has been provided to NRC. NSD 106 is Management generic to the entire Duke Nuclear Generation Department and is subject to revision during the staff review process as a result of other activities and reviews. This document was provided in electronic format to NRC staff via electronic mail on 8/23/05 and docketed by reference in Supplement 1 dated 10/6/05.
27 Software and Data NSD 800 The current version of NSD 800 has been provided to NRC. NSD 800 is Quality Assurance generic to the entire Duke Nuclear Generation Department and is subject to (SDQA) Program revision during the staff review process as a result of other activities and reviews. This document was provided in electronic format to NRC staff via electronic mail on 5/5/05 and docketed by reference in Supplement 1 dated 110/6/05.
28 Reactor Building Narrow OSC-2495 The original version of this calculation was provided in electronic format to Range Pressure NRC staff via compact disk on 6/23/05 and docketed by reference in Instrument Loop Supplement 1 dated 10/6/05. Supplement 1 indicated that the calculation Accuracy Calculation would be revised as a result of the modification. This calculation will be (ESFAS) revised for each unit. However, it is typical of all three units. Any differences between units will be insignificant. The revised calculation was provided in electronic format to NRC staff via electronic mail on 2/3/06 and docketed by reference in Supplement 6 dated 2/3/06.
29 Wide Range RCS OSC-2759 The original version of this calculation was provided in electronic format to Pressure Uncertainty, NRC staff via compact disk on 6/23/05 and docketed by reference in (ESFAS HPI & LPI Supplement 1 dated 10/6/05. Supplement 1 indicated that the calculation setpoints) would be revised as a result of the modification. Duke decided to issue a new calculation for those units with the digital upgrade complete that is applicable to all three units. OSC-8829 was provided in electronic format to NRC staff via electronic mail on 2/3/06 and docketed by reference in Supplement 6 dated.2/3/06.
30 RPS Main Feedwater OSC-3395 The original version of this calculation was provided in electronic format to Pump Pressure NRC staff via compact disk on 6/23/05 and docketed by reference in Instrument Loop Supplement 1 dated 10/6/05. No revision is required.
Accuracy Ca lulation February 14, 2006 Page 5 Document Title Doc. No.
Comments 31 RPS Flux/Fk)w Ratio OSC-3416 The original version of this calculation was provided in electronic format to Uncertainty Evaluation NRC staff via compact disk on 6/23/05 and docketed by reference in Supplement 1 dated 10/6/05. Supplement 1 indicated that the calculation would be revised as a result of the modification. Duke decided to issue a new calculation for those units with the digital upgrade complete that is applicable to all three units. OSC-8857 was provided in electronic format to NRC staff via electronic mail on 2/3/06 and docketed by reference in Supplement 6 dated ' 3/06.
32 Reactor Building OSC-3446 The original version of this calculation was provided in electronic format to Pressure Instrument NRC staff via compact disk on 6/23/05 and docketed by reference in Loop Accuracy Supplement 1 dated 10/6/05. No revision is required.
Calculation (ESFAS &
OSC-4048 The original version of this calculation was provided in electronic format to Temperature Trip NRC sl:aff via compact disk on 6/23/05 and docketed by reference in Function Uncertainty Supplement 1 dated 10/6/05. Supplement 1 indicated that the calculation Analysis and Variable would be revised as a result of the modification. Duke decided to issue a new Low Pressure Safety calculation for those units with the digital upgrade complete that is applicable Limit to all three units. OSC-8828 was provided in electronic format to NRC staff via electronic mail on 2/3/06 and docketed by reference in Supplement 6 dated /Y3/06.
34 Power-Imbalance Safety OSC-5604 The original version of this calculation was provided in electronic format to Limits and Tech. Spec.
NRC staff via compact disk on 6/23/05 and docketed by reference in Setpoints Using Error-Supplement 1 dated 10/6/05. The calculation is still valid but will be Adjusted Flux/Flow Ratio revisecl/replaced using the uncertainties calculated in OSC-7237 (high flux of 1.094 calc) and OSC-3416 (flux/flow/imbalance calc) to generate the safety limit power-imbalance envelope that Oconee Nuclear Design verifies for every reload core design. The digital RPS uncertainties on flux and flux/flow decreased relative to what was used in OSC-5604. Therefore, it is not necessary to revise OSC-5604 at this time. However, it must be revised prior to verifying the power-imbalance envelope for the first digital RPS cycle (03C24).
35 RPS High Flux and OSC-7237 The original version of this calculation was provided in electronic format to Pump/Power Monitor NRC s aff via compact disk on 6/23/05 and docketed by reference in Trip Function Uncertainty Supplement 1 dated 10/6/05. Supplement 1 indicated that the calculation Analysis would be revised as a result of the modification. Duke decided to issue a new calculation for those units with the digital upgrade complete that is applicable to all three units. OSC-8856 was provided in electronic format to NRC staff via electronic mail on 2/3/06 and docketed by reference in Supplement 6 dated 2/3/06.
February 14, 2006 Page 6 Document Title Doc. No.
Comments 36 ONS Unit 1 - RPS &
OSC-8623 This document was initially provided in electronic format to NRC staff via ESFAS Syst'em electronic mail on 8/23/05 and docketed by reference in Supplement 1 dated Functional Description 10/6/05. Revision 3 to this document was provided in electronic format to NRC staff via electronic mail on 1/6/06 and docketed by reference in Supplement 6 dated 2/3/06. This document is typical of all three units. Any differences between units will be insignificant and will not alter the functional design.
37 Engineered Safeguard OSS-0311.00 This document was initially provided in electronic format to NRC staff via Feature Actuation 0012 electronic mail on 5/2/05 and 9/29/05 and docketed by reference in System (ESIFAS)
Supplement 1 dated 10/6/05. Revision 3 to this document was provided in Replacement Project electronic format to NRC staff via electronic mail on 1/6/06 and docketed by Secification reference in Supplement 6 dated 2/3/06.
38 Reactor Prolection OSS-0311.00 This document was initially provided in electronic format to NRC staff via System (RPS) 0013 electronic mail on 5/2/05 and docketed by reference in Supplement 1 dated Replacement Project 10/6/0;5. Revision 2 to this document was provided in electronic format to Specification NRC staff via electronic mail on 1/6/06 and docketed by reference in
_Supplement 6 dated 2/3/06.
39 Duke Power Company, Procedure No.
DOCUMENT RELATED TO FAT Oconee Nuclear Station, IP/0/A/0305/015 This procedure covers the currently installed analog system. A paper copy of "Nuclear Instrumentation the current revision was provided during November 2005 NRC audit. As a RPS Removal from and result of the digital modification, this procedure will be replaced by Return to Service for approximately 30 new procedures prior to implementing.
Channels A, B, C and D, Rev. 031, EL7QS No.
These procedures are currently in preparation. Following completion of the RPS-Q-ENTRY FAT, the system will be available for V&V of each procedure. V&V is expected to commence in June 2006 and to be completed by October 2006.
Upon completion of the V&V, each procedure will be available for staff review.
40 Documentation of SDQA-10143-DOCUMENT RELATED TO FAT Software Requirements ONS This document was provided in electronic format to NRC staff via electronic and SDQA for mail on 11/30/05 and docketed by reference in Supplement 4 dated 11/30/05.
RPS/ESFAS System This document will be revised to reference documents that were not available Replacement when the SDQA plan was initially issued. This document would be revised as a result of required software changes which may occur during FAT.
41 SIVAT LSELS Test Case Paper copy provided during November 2005 NRC audit. This document was Specifications, Job L010400A provided in electronic format to NRC staff via electronic mail on 1/25/06 and 4310002, Outputs:
docketed by reference in Supplement 6 dated 2/3/06.
EFHV0037 42 Teleperm XS Function TXS-1 003 This document was provided in electronic format to NRC staff via electronic Blocks, Version 2.60 FB-V10.0/01.04 mail on 9/29/05 and docketed by reference in Supplement 6 dated 2/3/06.
ADDON, Version 1.2 Duke provided an updated manual (Version 2.61) for release 3.07.a on 2/14/06 and is docketed by reference in this Supplement.
43 SIVAT-TXS Simulation TXS-1 047 Paper copy provided during November 2005 NRC audit. This document was Based Validation Tool, V2.0/01.04 provided in electronic format to NRC staff via electronic mail on 1/25/06 and Version 1.4.0 docketed by reference in Supplement 6 dated 2/3/06.
List of Commitments RA -
l Commitment Status 4.B The body of the report establishes EQ requirements and will not be revised. Section In Progress 4.9 of the report has 5 open items related Ito EQ testing that are currently being addressed. The cabinet internal temperature EQ test is being conducted during the FAT. The current status of these items was provided by electronic mail on 2/13/06.
The status of these five open items will be updated as changes occur.
1.Q The original version of this calculation was provided in electronic format to NRC staff Scheduled via compact disk on 6/23/05 and docketed by reference in Supplement 1 dated 10/6/05.
Calculation OSC-5604 is still valid but will be revised/replaced using the uncertainties calculated in OSC-7237 (high flux calc) and OSC-3416 (flux/flow/imbalance calc) to generate the safety limit power-imbalance envelope that Oconee Nuclear Design verifies for every reload core design. It must be revised prior to verifying the power-imbalance envelope for the first digital RP ' cycle (03C24).
N/A These procedures (reference Procedure No. IP/0/AN0305/015) are currently in In Progress preparation. Following completion of FAT, the system will be available for V&V of each procedure. V&V is expected to commence in June 2006 and to be completed by October 2006. Upon completion of the V&V, each procedure will be available for staff review.