ML20214S586

Forwards Verification & Validation:Final Rept for Plant Safety Monitoring Sys. All Trouble Repts Resolved.Only One Validation Trouble Rept Re Human Engineering Deficiencies Remains Open

ML20214S586
Person / Time
Site:	Vogtle
Issue date:	06/01/1987
From:	Bailey J SOUTHERN COMPANY SERVICES, INC.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20214S590	List: ML20214S586 ML20214S628
References
RTR-REGGD-01.097, RTR-REGGD-1.097 GN-1373, NUDOCS 8706090334
Download: ML20214S586 (3)

Text

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southem Company serwces, Inc.

Post Offca Box 282 W ynesboro. Georgia 30830 Telephone 404 7221543 404 722-8943 Vogtle Project June 1, 1987 United States Nuclear Regulatory Commission Attn: Document Control Desk File: X7BC35 Washington, D.C. 20555 Log: GN-1373 NRC DOCUMENT NUMBERS 50-424 and 50-425 OPERATING LICENSE NPF-68 CONSTRUCTION PERMIT NUMBER CPPR-109 V0GTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 PLANT SAFETY MONITORING SYSTEM VERIFICATION AND VALIDATION

References:

1. Bailey (GPC) to Denton (NRC), GN-1256, December 22, 1986

2. Bailey (GPC) to Denton (NRC), GN-1283, January 5, 1987

3. Wisenburg (HLP) to NRC, ST-HL-AE-1988, March 19, 1987 Gentlemen:

The Plant Vogtle Plant - Safety Monitoring System (PSMS) is utilized to process and output many of the Regulatory Guide 1.97 Revision 2 variables to plasma displays and external indicators, displays, cabinets, and other equipment. The PSMS consists of three types of modular components: the remote processing units (RPUs); the display processing units (DPUs); and the plasma displays (PDs). The system is seismically and environmentally qualified and is configured to meet single failure -

cri teria.

The Category 1 Regulatory Guide 1.97, Revision 2 variables that are displayed on the Plant Vogtle PSMS as specified in Table 7.5.2.1 of the Plant Vogtle FSAR include the following:

Reactor coolant pressure (wide range) (4 channels)

RCS wide range hT ot (1 per loop)

RCS wide range Tcold (1 per loop)

Wide range steam generator water level (1 per steam generator)

Narrow range steam generator water level (4 per steam generator)

Pressurizer level (3 channels)

Containment pressure (4 channels)

Steamline pressure (3 per steamline)

Refueling water storage tank level (4 channels) A Containment water level (narrow range) (2 channels) $d Containment water level (wide range) (2 channels) ( {t 8706090334 870601 PDR ADOCK 05000424 P PDR _

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U. S. Nuclear Regulatory Commission June 1, 1987 Plant Safety Monitoring System Page Two Verification and Validation -

Condensate storage . tank level (2 per tank)

Auxiliary feedwater flow (2 per loop)

Core exit temperature (50 thermocouples)

RCS subcooling (2 channels)

Neutron flux.(extended range) (2 channels)

Reactor vessel water level (2 channels)

• ' Containment pressure (extended range) (2 channels)

Containment hydrogen concentration (2 channels)

Reference 1 indicated that only six of- the Category 1 Regulatory Guide. 1.97 Revision 2 variables that are displayed on the PSMS are not displayed on the control board via diverse indications. These are:

a. Core exit temperature

b. RCS subcooling

c. Reactor vessel water level (RVLIS)

d. Neutron flux-(NFMS)

e. Containment water level (narrow range)

f. Containment pressure (extended range)

Until the PSMS verification and validation is completed, Georgia Power i

. Company committed to the implementation of procedures that provide instructions to the. operators on how to determine the above information by a means independent of_ the PSMS should the PSMS displayed information become unavailable. - Reference 2 provided clarifications to- the interim commitments made in Reference 1.

The Plant Vogtle PSMS V&V program has been completed. The total number of software units associated with' the PSMS is 1018. A comparison of the software commonality with . that already subjected to a V8V program on- the : South Texas Project Qualified Display Processing System (QDPS) indicates that 653 of the software units associated with the Plant

, Vogtle PSMS were tested on the QDPS. The remaining 365 software units

specific to the Plant Vogtle_ PSMS are due _to the following plant l features

plasma display formats; the Reactor Vessel Water Level

! Indication System (RVLIS); and the Neutron. Flux -Monitoring System (NFMS).

-Reference 3 provides a- summary of the V&V program on the - QDPS which

j. is : utilized to document the testing of the 653 software units that are common to the QDPS. The details of the verification testing on the remaining 365 software units is provided as an attachment ~ to this L letter. The details of the PSMS validation testing is also provided l- in the attachment.

All verification trouble reports have been resolved at this time. Only L one. validation trouble report remains open.

The issue addressed in the open trouble report concerned Human Engineering Deficiencies (HEDs) on the plasma display pages. The severity of the identified HEDs was judged to be minor and, as such, no safety concerns are introduced

!, during system operation with the current plasma displays.

L

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r7 s, a U. S. Nuclear Regulatory Commission. June 1, 1987 Plant. Safety Monitoring System Page Three Verification and Validation If your staff requires any additional information, please do not hesitate

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to contact me.

Sincerely, ob . h J. A. Bailey Project Licensing Manager JAB:jc Attachment-xc: R.'E. Conway J. P. O'Reilly P. D.-Rice L. T. Gucwa R. A. Thomas J. E. Joiner B. W. Churchill M. A. M111er-(2)

G. Bockhold, Jr.

NRC Regional Administrator NRC Resident Inspector R. Goddard R. W. McManus D. Feig-Project Files t

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