ML18142A021
| ML18142A021 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 07/27/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 087A, 87A, NUDOCS 8408070039 | |
| Download: ML18142A021 (8) | |
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VIRGINIA ELECTRIC AND POWER COMPANY.
RICHMOND, VIRGINIA 23261 W. L. STEWART VxcE PRESXDENT NUCLEAR OPERATIONS July 27, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. D. G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Serial No. 087A NO/TAH:acm Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 VIRGINIA ELECTRIC POWER COMPANY SURRY POWER STATION UNITS NO. 1 AND 2 NORTH ANNA POWER STATION UNITS NO. 1 AND 2 CONTROL ROOM DESIGN REVIEW PROGRAM PLAN In the submittal of Vepco 's Control Room Des.ign Review Program Plan, we acknowledged that the March 29, 1984 meeting between the NRC and the Westinghouse Owners Group (WOG) on the Information and Control issues could have a significant impact on the schedule and/or the methodology of the plan.
We stated that if this proved to be true, we would provide the NRC with a schedule. for developing these revisions to the plan within thirty (30) days of the resolution of the issues.
We considered the issues resolved with the issuance of the summary of the meeting by Mr. H. Brent Clayton on April 5, 1984.
The outcome of the meeting has no significant impact on our methodology and will not impact the schedule of the performance of the CRDR.
The principal change is the authorization of the use of the WOG Emergency Response Guidelines as the basis for the Task Analysis and the Verification and Validation sections.
We are providing replacement pages with these changes identified by vertical lines in the right hand margins.
These changes reflect the agreement between Messers. Hugh Thompson and H. Brent Clayton of the NRC and the WOG.
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. i Attachments: 20 copies Very ~rul~ours, itJ:U W. L. Stewart
e VIRGINIA ELECTRIC AND POWER COMPANY TO cc:
Mr. James P. O'Reilly Regional Administrator Region II USNRC Suite 2900 101 Marietta St.
Atlanta, Georgia 30303 Harold R. Denton Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. J. Don Neighbors Surry Project Manager Mailstop 438 7920 Norfolk Ave.
USNRC Bethesda, Maryland 20014 Mr. Leon B. Engle North Anna Project Manager Mailstop 428 7920 Norfolk Ave.
USNRC Bethesda, Maryland 20014 Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. M. W. Branch NRC Resident Inspector North Anna Power Station
.* Virgi~ia Electric and~wer Company Program Plan 1.3.3.3 System Functions and Task Analys1s (SFTA> - System functions and tasks are 1dentified and evaluated in this task. A 4-step procedure 1s employed:
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Identification of systems and subsystems by review of plant documentation and Westinghouse Owner's Group Emergency Response Guidelines and Background Documents.
o Identification of normal and emergency operating procedures to undergo task analysis.
o Identification of system/subsystem functions through document review and operator interviews.
o Identification and analysis of CR operational tasks.
Task analysis data are used as input for the Verification of Task Performance capabilities and the Validation of Control Room Functions (see paragraphs 1.3.3.5 and 1.3.3.6).
There are two basic types of products produced by this analysis. The first product is a tabular listing of major 1-9
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0 VICE PRESIDENTS R.H. LEASBURG, SR. VP
- ENG CONSTR W.L. STEWART, VP* NUCLEAR OPS DEPT.
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I STATION MANAGERS CORPORATE MANAGERS E.W. HARRELL, MGR
- NORTH ANNA PS R.F. SAUNDERS, MGR
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I W.R. CARTWRIGHT, MGR
- NUCLEAR OPS SUPPORT R.J. HARDWICK, MGR
- NUCLEAR PROGRAMS & LICENSING J.M. DAVIS, MGR
- CONSTRUCTION CRDRTEAM (SEE FIGURE 2*2)
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Program Plan main exception, are titled similar to the Section 6.0 subsection titles. For example, the Annunciator System Review Task Plan CTP-3.1> incorporates as criteria the guidelines contained in 0700 Section 6.3.
The main exception to this approach is that Section 6. 1 - Workspace, of 0700, was further subdivided into seven task plans that, 1n general, follow the additional breakdown of Section 6. l. Thus, General Layout - 6. 1. 1 becomes the Workspace Task Plan, Horkstation Design - 6. 1.2 becomes the Anthropometrics Task Plan, Emergency Equipment - 6. 1.4 becomes the Emergency Equipment Task Plan, and Environment - 6.1.5 becomes HVAC, Illumination, Ambient Noise, and Maintainability Task Plans.
The guidelines in Section 6. 1.3 - Multi-Unit Contro 1 Rooms. wa*s integrated into a 11 other task pl ans as appropriate.
- d. Some minor exceptions to this general classification scheme for the evaluation criteria occurred that was caused. primarily, by individual interpretations of specific guideline statements.
As an example, 6.l.l.6b of 0700, while appropriately in subsection 6.1 - Control Room Workspace, explains the need for dedicated communication links between.the control room boundary and a remotely located shift supervisor's office <note that it also refers to guideline 6.2. 1.7 - Point-To-Point Intercom Systems>.
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_-Virginia Electric and ~er Company Program Plan 4.4.2 Method The procedure to be employed by Vepco in conducting the System Functions and Task Analysis CSFTA> involves a top-down approach starting with an identification of system units and progressing through analysis of selected operator tasks. Throughout this process. the emphasis will be on identifying and analyzing operator information and control requirements with respect to maintaining critical plant safety functions (i.e.. containment integrity, reactivity control, RCS inventory control and heat transfer).
Since the HOG ERGs (Rev. 1) and associated background information were based on a technically sound rationale for the allocation of functions to operators and plant subsystems, it should not be necessary to perform an independent system functions analysis and allocation. Instead, the ERGs and background information, together with available plant specific emergency response procedures. will be used as the starting point for the top-down analysis of tasks and task elements which control room personnel must perform.
Therefore, the first step in this process will be to review the ERGs to identify the generic operator tasks to be performed for each ERG.
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Virginia Electric and~wer Company Program Plan Selection of event scenarios and system ~unctions will form the basis for the selection of appropriate ERGs.
The generic task analysis data will provide the initial input for the development of plant-specific task analysis information for the Surry and North Anna Power Stations.
This approach to task analysis has the following general characteristics:
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An inventory of tasks that must be accomplished for each event scenario is developed.
A sample of a typical Task Sequence Chart indicating the tasks required for a reactor trip or safety injection event illustrates the output of this step <see Figure 4-1>.
o For each of the tasks identified above, a typical Task Data Form (see Figure 4-2> will be prepared indicating:
the operating event the title of the task the task objective 4-23
_-~ Virginia Electric and,wer Company Program Plan be accomplished effectively within: 1) the structure of defined emergency procedures, and 2) the design of the control room as it exists.
As with Verification of Task Performance Capabilities, Validation of Control Room Functions is an extension of the SFTA.
In this case, emphasis is placed on determining the adequacy of the control room design for supporting operator task sequences required to identify and evaluate plant status and to mitigate selected transients.
4.7.2 Method NUREG-0700 recommends that the validation process involve selected sequences analyzed during the SFTA.
Therefore, the exact combination of task sequences to be included in the validation effort will be determined based on the results of the sequence selection process of the SFTA.
The principal activities during this task involve observation of operators performing selected event sequences on the Surry and North Anna simulators.
The following process will be employed during this task:
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