Rev 0 to Procedure Dcrdr 5.2, Verification of Implemented Human Engineering Discrepancy Corrections| ML20215K570 |
| Person / Time |
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| Site: |
Clinton  |
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| Issue date: |
02/23/1987 |
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| From: |
Holland W
ILLINOIS POWER CO. |
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| To: |
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| Shared Package |
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| ML20215K548 |
List: |
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| References |
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| DCRDR-5.2, NUDOCS 8705110253 |
| Download: ML20215K570 (8) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209E0551999-07-0606 July 1999
1999 Business Plan
ML20206F2231999-04-27027 April 1999
NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station
ML20199H2771999-01-20020 January 1999
Proposed Tech Specs Changing Table 3.3.8.1-1 to Revise Allowable Values for Degraded Voltage Relay Reset & Dropout Setpoints as Specified Per Items 1.c,1.d,2.c & 2.d
ML20206E6281998-12-31031 December 1998
Rev 17 to ODCM for Clinton Power Station
ML20196A0941998-11-20020 November 1998
Proposed Tech Specs Re Div 3 Diesel Generator Droop Issue
ML20196A1501998-11-20020 November 1998
Revised Pages Constituting Rev 3 to CPS TS Bases,Consisting of Pages Annotated with Rev Numbers 3-1,3-2,3-3,3-4 & 3-5. Changes to Text Identified with Rev Bars.No Rev Bars Included for Changes to Format
ML20155A5631998-10-23023 October 1998
Proposed Tech Specs LCO 3.6.1.9, FW LCS (FWLCS) for Implementation of FWLCS Mode of RHR Sys
U-603088, Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)1998-10-0505 October 1998
Proposed Tech Specs Section 5.5.13,allowing Next Scheduled Performance of LLRT of Primary Containment Penetration for RPV Head Spray Piping (IMC-042) to Be Deferred Until Seventh Refueling Outage (RF-7)
ML20153F4201998-09-23023 September 1998
Corrected Proposed Tech Specs Bases Page B 3.8-94 Re SVC Protection Sys
ML20237E4191998-08-24024 August 1998
Proposed Tech Specs SR 3.8.1.17,revising Acceptance Criteria for Meeting ready-to-load Requirement for Division 3 DG
ML20237C3501998-08-17017 August 1998
Proposed Tech Specs Partially Reducing Load at Which DGs Are Required to Be Tested Per Affected SRs in Order to Reduce Stress & Wear on Machines While Still Sufficiently Challenging Machines to Confirm Operability
ML20236X0071998-07-31031 July 1998
Proposed Tech Specs,Revising Acceptance Criteria of SRs 3.8.1.7,3.8.1.12,3.8.1.15 & 3.8.1.20
ML20236Q4661998-07-17017 July 1998
Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4651998-07-17017 July 1998
Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4571998-07-17017 July 1998
Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test
ML20216B1511998-05-0404 May 1998
Proposed Tech Specs Pages,Incorporating Requirements for Static Var Compensator (SVC) Protection Sys Under New TS
ML20217M3351998-04-27027 April 1998
Proposed Tech Specs Re Mgt Changes Occurring in Operations Organization at Plant
ML20203D5651998-02-19019 February 1998
Plan for Excellence
ML20212C6951997-10-23023 October 1997
Proposed Tech Specs,Constituting Rev 2 to CPS TS Bases.Rev Consists of Pages Annotated W/Rev Numbers 2-1 Through 2-14
ML20149J1701997-07-22022 July 1997
Proposed Tech Specs Requesting Exemption to 10CFR50,App a, General Design Criteria to Allow Operation W/Identified Offsite Circuit Condition
ML20149H8991997-06-30030 June 1997
CPS Long Term Improvement Plan
U-602714, Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation1997-04-0101 April 1997
Proposed Tech Specs Table 3.3.8.1-1 Re Loss of Power Instrumentation
ML20133F2051997-01-0707 January 1997
Proposed Tech Specs 2.0 Re Safety Limits
ML20133A5951996-12-13013 December 1996
Proposed TSs Re Transfer of Minority Ownership
ML20134M3181996-11-19019 November 1996
Proposed Tech Specs Revising Table 3.3.8.1-1, Loss of Power Instrumentation, by Dividing Function, Degraded Voltage - 4.16 Kv Basis & Degraded Voltage Dropout - 4.16 Kv Basis, re-numbering Items in Table & Revising Associated Notes
ML20128K0711996-10-0404 October 1996
Proposed Tech Specs 3.3.8.1,adding Action Statement & Note Requiring Restoration of Inoperable Degraded Voltage Relays, Rev to Table 3.3.8.1-1
ML20134C1631996-09-20020 September 1996
Proposed Tech Specs,Revising TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months
ML20116N1101996-08-15015 August 1996
Proposed Tech Specs 2.0, Safety Limits, Changing TS to Incorporate Revised SLMCPR as Calculated by GE for CPS Cycle 7
U-602619, Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses1996-08-15015 August 1996
Proposed Tech Specs 5.0, Administrative Controls, Deleting Examples Currently Included in Parentheses
U-602623, Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling1996-08-15015 August 1996
Proposed Tech Specs 3.10.10, Single Control Rod Withdrawal- Refueling
ML20137A1101996-08-14014 August 1996
Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan
ML20137A1021996-07-10010 July 1996
Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan
ML20113E7261996-06-28028 June 1996
Proposed Tech Specs,Allowing Removal of Inclined Fuel Transfer Sys Primary Containment Blind Flange While Primary Containment Required to Be Operable
U-602591, Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures1996-06-21021 June 1996
Proposed Tech Specs,Allowing Utilization of RWP or Equivalent to Control Entry Into High Radiation Area, Clarifying Example Given in TS of Individuals Qualified in Radiation Protection Procedures
ML20108C9431996-05-0101 May 1996
Proposed Tech Specs,Implementing 10CFR50,App J - Option B
ML20107L0011996-04-19019 April 1996
Proposed Tech Specs,Revising Listed TS to Eliminate Core Alterations as Applicable Condition for Which Associated LCO Must Be Met
ML20100H8411996-02-22022 February 1996
Proposed Tech Specs,Changing TS 3.3.4.1, End of Cycle Recirculation Pump Trip Instrumentation, to Delete SR 3.3.4.1.6 Which Requires RPT Breaker Interruption Time to Be Determined at Least Once Per 60 Months
ML20100H7901996-02-22022 February 1996
Proposed Tech Specs,Deleting SR 3.3.8.1.1 Which Requires Channel Check for Loss of Power Instrumentation & Changing TS Table 3.3.8.1-1 to Change Allowable Value for Degraded Voltage Function from 3762V & 3832V to 3876V
ML20100H8171996-02-22022 February 1996
Proposed Tech Specs,Changing TS 3.4.11, RCS P/T Limits, to Incorporate Specific P/T Limits for Bottom Head Region of Rv Separate & Apart from Core Beltline Region of Rv
ML20100H7741996-02-22022 February 1996
Proposed Tech Specs,Proposing to Revise TS 3.6.5.1, Drywell, to Allow Drywell Bypass Leakage Tests to Be Performed at Intervals of Up to Ten Yrs Based on Demonstrated Performance of Drywell Barrier
ML20095G5141995-12-14014 December 1995
Proposed Tech Specs 3.3.1.1, RPS Instrumentation & TS 3.3.6.1, Primary Containment Dwl Isolation Instrumentation to Eliminate Periodic Response Time Testing of Analog Trip Modules
ML20095G6401995-12-14014 December 1995
Proposed Tech Specs Instrumentation Associated W/High Pressure Core Spray Sys,Reactor Core Isolation Cooling Sys & Residual Heat Removal Sys
ML20095G4791995-12-14014 December 1995
Proposed Tech Specs 3.4.2, Flow Control Valves Re Proposed Deletion of Average Rate of Movement Verification Requirement
ML20117E3001995-11-0606 November 1995
Rev 18 to App V Pump & Valve Testing Program Plan
ML20094D2031995-10-27027 October 1995
Proposed Tech Specs,Consiting of Changes to TS 3.1.3 to Include 25% Surveillance Overrun Allowed by LCO 3.0.2 Into Allowances of Surveillance Notes for Control Rod Notch Testing Per SR 3.1.3.2 & SR 3.1.3.3
ML20094D2141995-10-27027 October 1995
Proposed Tech Specs,Consisting of Changes to TS 5.2.2.e to Revise Requirements for Controls on Working Hs of Unit Staff That Perform SR Functions
ML20085N0621995-06-23023 June 1995
Proposed Tech Specs Bases,Per TS 5.5.11, TS Bases Control Program
ML20085F5961995-06-0909 June 1995
Proposed Tech Specs,Incorporating Description of Exclusion Area Boundary
ML20087J5691995-05-17017 May 1995
Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual
ML20085J9701995-02-16016 February 1995
Proposed Tech Specs Reflecting Enforcement Discretion Re TS LCO for Div 2 DC Electrical Power Sources
1999-07-06
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20209E0551999-07-0606 July 1999
1999 Business Plan
ML20206F2231999-04-27027 April 1999
NRC Manual Chapter 0350 Restart Action Plan for Clinton Power Station
ML20206E6281998-12-31031 December 1998
Rev 17 to ODCM for Clinton Power Station
ML20236Q4661998-07-17017 July 1998
Rev 0 to Procedure 2800.93, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4651998-07-17017 July 1998
Rev 0 to Procedure 2800.92, Emergency Reserve Auxiliary Transformer Integrated Test
ML20236Q4571998-07-17017 July 1998
Rev 0 to Procedure 2800.91, Emergency Reserve Auxiliary Transformer Test
ML20203D5651998-02-19019 February 1998
Plan for Excellence
ML20149H8991997-06-30030 June 1997
CPS Long Term Improvement Plan
ML20137A1101996-08-14014 August 1996
Rev 19 to App V Second 10-Yr Interval Pump & Valve Testing Program Plan
ML20137A1021996-07-10010 July 1996
Rev 5 to App IV Second 10-Yr Interval Inservice Exam Plan
ML20117E3001995-11-0606 November 1995
Rev 18 to App V Pump & Valve Testing Program Plan
ML20087J5691995-05-17017 May 1995
Rev 17 to App V, Pump & Valve Testing Program Plan of CPS ISI Program Manual
ML20064K5141993-10-11011 October 1993
Rev 16 to Apps Iii,Iv & V of Clinton Power Station ISI Program Manual
ML20249A6601993-04-14014 April 1993
Revised ESA-102, Electrical Engineering Std for Electrical & Physical Characteristics of Class B Electrical Cables
ML20126E4581992-11-30030 November 1992
Rev 13 to CPS IST Program,App III
ML20096G5031992-04-30030 April 1992
Rev 0 to Clinton Power Station Raw Water Treatment & Enhancement Program
ML20058L3371991-07-10010 July 1991
Rev 2 to Procedure Nragp 101-1, Nuclear Review & Audit Group Charter
ML20082J1991991-02-28028 February 1991
Rev 7 to Odcm
ML20059N2201990-08-31031 August 1990
Rev 8 to, Pump & Valve Testing Program Plan
ML20006C2071989-12-31031 December 1989
Rev 6 to Odcm.
ML20006A8321989-10-20020 October 1989
Rev 3 to Inservice Exam Plan.
ML20236A5281989-02-28028 February 1989
Rev 5 to Odcm
ML20151M7611988-07-29029 July 1988
Rev 2 to Inservice Exam Program Plan
ML20196J5731988-03-0101 March 1988
Pump & Valve Testing Program Plan
U-601006, Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes1987-08-20020 August 1987
Rev 3 to Pump & Valve Testing Program Plan & Summary of Changes
ML20234E0931987-06-30030 June 1987
Rev 2 to Pump & Valve Testing Program Plan
ML20215M3511987-06-22022 June 1987
Revised Inservice Exam Program Plan for First 10-yr Interval
ML20215K5701987-02-23023 February 1987
Rev 0 to Procedure Dcrdr 5.2, Verification of Implemented Human Engineering Discrepancy Corrections
ML20212E9701987-02-0606 February 1987
Rev 8 to Station Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats MOV Signature Analysis Sys
ML20212E9611987-02-0606 February 1987
Rev 10 to Station Operating Manual Maint Procedure 8451.01, Preventive Maint for Motor-Operated Valves
ML20213F3631986-10-31031 October 1986
Long-Term Inservice Exam Plan for Class 1,Class 2 & Class 3 Component Supports for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan
ML20213F3861986-09-30030 September 1986
Vols I & II to Long-Term Inservice Exam Plan for Class 1, Class 2 & Class 3 Piping & Components for Clinton Power Station,Unit 1, First 10-yr Interval Final Plan
ML20213F3761986-09-30030 September 1986
Inservice Exam Program Plan
ML20214P1141986-08-15015 August 1986
Rev 7 to Operating Manual Maint Procedure 8451.02, Testing of Motor-Operated Valves Using Movats Motor-Operated Valve Signature Analysis Sys
U-600481, Rev 2 to Administrative Procedure 1888.00, Process Control Program1986-03-21021 March 1986
Rev 2 to Administrative Procedure 1888.00, Process Control Program
U-600487, Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program1986-03-18018 March 1986
Rev 1 to Clinton Power Station Inservice Insp - Pump & Valve Testing Program
ML20198S5391986-02-21021 February 1986
Rev 2 to Nuclear Station Engineering Instruction Nsei CS-4, UHS Monitoring. W/860522 Advance Instruction Change 1
ML20138Q0911985-11-30030 November 1985
Rev 1 to Offsite Dose Calculation Manual
ML20138Q9831985-11-30030 November 1985
Inservice Insp Pump & Valve Testing Program
ML20209H1541985-10-29029 October 1985
Rev 2 to Instruction PI-CP-079, Preparation,Review & Approval of Pump & Valve Operability Packages
ML20209H1611985-10-29029 October 1985
Rev 3 to Nuclear Station Engineering Dept Procedure D.22, Engineering Interdisciplinary Review & Impact Assessment for Plant Mode
ML20133N0461985-08-0707 August 1985
Rev 3 to Record Verification Program Plan,Clinton Power Station
ML20134L8921985-07-31031 July 1985
Program for Compliance W/Tmi Action Plan Item I.G.1, `Training During Low Power Testing.'
ML20134P8821985-07-0808 July 1985
Rev 1 to Procedure 1888.00, Process Control Sys. Addl Info Re ATI-VR-001-P-A, Associated Technologies,Inc Vol Reduction & Bitument Solidification Sys, Encl
ML20133N7171985-06-28028 June 1985
Revised Emergency Plan Implementing Procedures,Including Rev 1 to AP-01, Organization & Preparation of Controlled Documents & Rev 1 to Document Control
ML20128M0021985-06-14014 June 1985
Rev 0 to Procedure SPDS-DST-001, SPDS Dynamic Simulation Test Plan
ML20126C5081985-04-30030 April 1985
Offsite Dose Calculation Manual
ML20126B6741985-04-20020 April 1985
Emergency Plan Implementing Procedure EC-13, Reactor Core Damage Estimation
ML20108B4601985-02-28028 February 1985
Preservice Insp Program
ML20116M7781985-02-27027 February 1985
Rev 8 to Radiation Safety Program Augmentation CPS-1, Instructions for Augmenting United States Testing Co Radiation Safety Program at Clinton Power Station
1999-07-06
[Table view] |
Text
Attachm:nt 3 to U-600895 Page 1 of 5 ILLINOIS 70lER COMPANY l NO. DCRDR 5.2 REV. 0 I
CLINTON POWER STATION l TITLE Verification of Implemented HED l Corrections DETAILED CONTROL ROOM DESIGN REVIEW l l DATE 2-23-87 PAGE 1 of 5 REVIEWED BY J .13- APPROVED BY 7[ J7!87 Project /6gineer/Date l Pr6g' ram Manager /Date i
1.0 INTRODUCTION
This procedure establishes the method and requirements for verifying that the implemented corrective actions to Human Engineering Discrepancies (HEDs) comply with established guidelines and do not create a new !TdD.
2.0 APPLICABILITY This procedure applies to all review team members and to the personnel of contractors and subcontractors of either Torrey Pines Technology or Illinois Power involved in the Detailed Control Room Design Review.
3.0 REFERENCES
3.1 Clinton Power Station DCRDR - Program Plan dated September 1984.
3.2 Torrey Pines Technology proposal number GACP 41-212.
3.3 Illinois Power Purchase Order Number X-03757.
3.4 Clinton Power Station Detailed Control Room Design Review -
Operating Experience Review Report.
3.5 Procedure DCRDR 5.1, HE0 Assessment and HED Improvement.
3.6 Procedure DCRDR 3.3, Photographic Record of HEOs.
3.7 2rocedure DCRDR 4.1, Operating Experience Review.
, 3.8 Procedure DCRDR 4.2, Control Room Survey 3.9 Procedure DCRDR 4.4, DCRDR & E0P Integrated SFTA 3.10 Procedure DCRDR 4.5, DCRDR & E0P Integrated Verification 3.11 Procedure DCRDR 4.6, DCRDR & EOP Integrated Validation SS/355 5110253 870328 1 ADOCK 0500 P
Attachnent 3 to U-600895 l Page 2 of 5 ILLINOIS POWER COMPANY l NO. DCRDR 5.2 REY. O I
CLINTON POWER STATION l TITLE Verification of Implemented HED l Corrections DETAILED CONTROL ROOM DESIGN REVIEW l l DATE 2-23-87 PAGE 2 of 5 I
I 4.0 DISTRIBUTION Distribution List No. 1.3.
5.0 RESPONSIBILITIES 5.1 The DCRDR Program Manager will'be responsible for approval of this procedure and changes thereto.
5.2 The DCRDR Principal Investigator and Project Engineer will be responsible for the review and implementation of this procedure under the contract authority.
6.0 REQUIREMENTS 6.1 OBJECTIVE The objective of the Verification of Implemented HED Corrections (VIHC) is to ensure that the implemented corrective actions for existing HEDs conform to the guidelines used with procedures in references 3.5 HE0 Assessment and HED Insrovement 3.7 Operating Experience Review 3.8 Control Room Survey 3.9 DCRDR & E0P Integrated SFTA 3.10 DCRDR & E0P Integrated Verification 3.11 DCRDR & E0P Integrated Validation and assure that they do not introduca new HEDs.
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SS/355
Attschmsnt 3 1 to U-600895 j l Page 3 of 5 -
ILLIN0IS POWR COMPANY l NO. DCRDR 5.2 REV. 0 [
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CLINTON PORR STATION l TI_TLE Verification ~of Implemented HED "
l Corrections DETAILED CONTROL ROOM DESIGN REVIEW l l DATE 2-23-87 PAGE 3 of 5 I
i 6.2 TASKS The overall VIHC phase will include the following specific activities:
- Preparation of a VIHC survey form to assess each implemented corrective action. (Figure 1)
- Complete a VIHC survey form for each implemented corrective action.
- Preparation of a report summarizing the VIHC findings.
6.3 METHODOLOGY The methodology will follow the checklist procedure used during the ,
Control Room Survey, Reference 3.8, for each corrective action.
Each corrective action will be reviewed by a human factors special-ist recording the data on a VIHC survey form (Figure 1). The review will determine whether the corrective action complies with the guidelines or impacts on the SFTA.
A Reference / Comment space is provided for corrective actions that do not comply with the guidelines or impact the SFTA. The human factors specialist will provide a brief statement explaining how the listed control room item or device does not satisfy the guideline or convention.
If the corrective action complies with the guidelines, the completed VIHC form is filed with the HED.
If the corrective action does not comply with the originating guide-line, the completed VIHC form and HED are submitted to the AIT for additional assessment per Procedure 5.1. ]
If the corrective action does not comply with guidelines other than !
the originating one, this new compliance is documented on an HED I form and submitted to the AIT for assessment. I l
Diagrams or photographs will be used as necessary to clarify a corrective action that does not satisfy the guideline.
SS/355 l
Attachm:nt 3 to U-600895 l Page 4 of 5 ILLINOIS poler COMPANY l NO. DCRDR 5.2 REV. 0 l
CLINTON POWER STATION l TITLE Verification of Implemented HED l i
l Corrections DETAILED CONTROL ROOM DESIGN REVIEW l l DATE 2-23-87 PAGE 4 of 5 I
I 6.4 DOCUMENTATION t
The VIHC effort will be documented in a VIHC Summary Report.
7.0 EFFECTIVE DATE This procedure becomes effective immediately upon approval.
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SS/355
1 Attachm:nt 3 l to U-600895
.l Page 5 of 5 ILLINOIS POWER COMPANY NO. DCRDR 5.2 REV. O CLINTON POWER STATION TITLE Verification of Implemented HED l Corrections DETAILED CONTROL ROOM bESIGN REVIEW l DATE 2-23-87 PAGE 5 of 5 P
I I
DETAILEO CON (ROL ROOM DESIGN REVIEW VERIFICATION OF IMP!EMENTED HED CORRECTIONS (VIHC) f a
085tRVt4. . . _ . .. f DATE. PAGE OF LOCATION _ . . _ . _ . . . .
GulClutt CAITERIA ITIM NO . . _ . . M0 AgitRthCE NO: .
f
$09'Cf of let0- I COAAECTIVE ACfl04
- i. rhe .e,.e e e e. - e .h . , s es.o..
8.1 82 8.3 ._ - . 6.4 . . . . _ _ 85 88 ;
87 88 89 . _ _ '
Osse the terrottawe atten compey web the aheve .et.d geadstums?
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- 2. Does the correcteve arsame ame.st the $7TA? I l
MFEMiltt/Coassetst; s
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WAGAAM/PtIOTO NO :
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Figure 1. Sample Verification of Implemented HED Correction Form
Attrchment 4 to U-600895 JUSTIFICATION FOR REVISING THE DISPOSITION OF HEDs 6.6,009 and 6.9.007 s.
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'Attachmtnt 4-
.to U-600895
~Page 1 of.2 e
Indication Visibility Concern on P680 Panel- HED 6~6,009
'1.- .
1 HED 6.6,009 identified concerns with.the visibility of some indications on the P680 console. (P680 is the nuclenet control console.) Two concerns were originally identified: When an operator was in a seated position some controls and status. lights were not visible, and when the operator was in.a standing position the top row of annunciators in the center section of the panel were not visible due to the panel overhang. ,
I The corrective action proposed for this HED centered on-the panel-overhang. (The management review team evaluated the visibility of lights and controls and determined that no corrective action was required.) The corrective action originally proposed for the overhang -
> concerns was to cut out a section directly.over the annunciators.
However, further review of this HED indicates that the originally proposed corrective action is not warranted. Based on the following justification the panel overhang will not be removed. ,
- a. The purpose of the overhang removal is to enhance operator view of P680 (center section) annunciators when standing close to the panel. Since operators do not typically stand in that location, and since the annunciators are clearly visible to other operators.in the control room, it appears that the benefit of this change is marginal. Experience to date has shown that plant operations are not impeded by the current configuration.
- b. Removal of this lip may introduce / create significant lighting-glare problems on the CRTs and the full core display.
- c. The disruption to control room and panel operation created by l this work could adversely effect plant safety during any plant condition.
f d. Cutting the overhang may introduce metal filings or other debris into the P680 panel and possibly affect its circuitry.
t
- 2. Remote Shutdown Panel Reactor Water Level Indication - HED 6.9.007 HED 6.9.007 identified a concern on the Remote Shutdown Panel (RSP).
The concern was that the reactor water'1evel on the RSP indicators.
could only be read to +60 inches above instrument zero. At one point j in CPS No. 4003.01, REMOTE SHUTDOWN, when alternate shutdown cooling is
, utilized'to bring the reactor to cold shutdown, it is necessary to' fill i the reactor to the level of the main steam lines (approximately 120 i inches above instrument zero) so that a recirculation path back to the suppression pool can be established through an open safety relief valve i (SRV).
In order to resolve this Category B HED, IP stated they would install j indicators to monitor the water level up to the main steam lines.
4
Attachmsnt 4 to U-600895 Page 2 of 2 Upon further evaluation, it was determined that the instrumentation currently installed on the RSP is adequate to shut down the reactor in accordance with CPS 4003.01. Installation of additional instrumentation is not required for the following reasons.
- a. In the event the need to evacuate the Main Control Room arises and, the reactor must be shutdown from the RSP, level indication is provided up to 60 inches. This corresponds to approximately 320 inches above top of active fuel,
- b. If, while at the RSP, the Alternate Shutdown Cooling mode is utilized to bring the reactor to cold shutdown conditions, the operator is directed to slowly fill the vessel to the main steam lines utilizing the Control Rod Drive (CRD) system. With the level indication available, the operator can verify that the level is or is not increasing. If the level increases to the upper limit of the level indicators and no other system manipulations are made, level will continue to increase to the main steam lines and flow out the open SRV.
If level is not increasing using the CRD system, the operator is directed to utilize the RHR system to increase level, and the operator can verify increasing level up to approximately 60 inches.
Thus, adequate reactor core cooling can be maintained in the cold shutdown condition utilizing the above methods without additional reactor water level instrumentation.
E _ ____ _