ELV-00599, Forwards Implementation Rept on Reactor Vessel Level Instrumentation Sys,Per NUREG-0737,Item II.F.2 & Sser 1

Forwards Implementation Rept on Reactor Vessel Level Instrumentation Sys,Per NUREG-0737,Item II.F.2 & Sser 1

ML20244B794
Person / Time
Site:	Vogtle
Issue date:	06/08/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM ELV-00599, ELV-599, NUDOCS 8906130294
Download: ML20244B794 (3)

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. w o. saircon, m - ELV-00599 sena vu ry.wm - 1476n-Nuoem Ower'" June 8, 1989 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk' Washington, D. C. 20555 PLANT V0GTLE -' UNIT 2 NRC D.0CKET 50-425 OPERATING LICENSE NPF-81 RVLIS IMPLEMENTATION REPORT Gentlemen:

Phrsuant to the requirements of. NUREG-0737, Item II.F.2 and Supplement 1 to the Safety Evaluation. Report (SSER 1) for Plant Yogtle, enclosed is the implementation report on the reactor vessel level instrumentation _ system

.(RVLIS) for Plant Vogtle Unit 2. The content of the report is based on

. Appendix L.to SSER 1 and the specific items addressed are repeated in the enclosure for your convenience.

If you have any questions. in this regard, please contact this office at any

. time.

Sincerely, yt.) LL-c W. G. Hairston, III NJS/gm

Enclosure:

1. RYLIS Implementation Report xc:- Georgia Power Company Mr. C. K. McCoy Mr.- G. Bockhold, Jr.

Mr.~ R. M. Odom .

Mr. J. P. Kane NORMS U. S. Nuclear Regulatory Commission Mr. S. D. Ebneter, Regional Admini strator p%

Mr. J. B. Hopkins, Licensing Project Manager, NRR , g Mr. J. F. 'Rogge, Senior Resident Inspector, Vogtle P..

8906130294 890608 PDR ADOCK 05000425

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ENCLOSURE PLANT V0GTLE - UNIT 2.

NRC DOCKET 50-425 OPERATING LICENSE NPF-81 RVLIS' IMPLEMENTATION REPORT

.The following information constitutes the implementation report on the Reactor Vessel Level Instrumentation System (RVLIS) for Plant Vogtle Unit 2 as required by NRC NUREG-0737,. Item II.F.2.

ITEM NO. 1

" Notification that the system installation, functional testing, and calibration is complete and test results. are available for inspection."

. RESPONSE The.RVLIS installation for Plant Vogtle Unit 2 was completed prior to fuel load. The system was tested, calibrated and made functional prior to initial criticality using Plant Vogtle Unit 2 Startup Test 2-5RP-01. The results are documented in the test procedure 2-5RP-01 and in Westinghouse Field Service Procedures NSID-EIS-87-18, Revision 1, and NSD-EIS-88-57, Revision 0 and 1, and are available for inspection by the NRC.

ITEM NO. 2 "Sunanary of' licensee conclusions based on test results, e. g.:

(a) The system perfonns in accordance with design expectations and within design error tolerances; or (b) description of deviations from design performance specifications and basis for concluding that the deviations are acceptable."

RESPONSE

The Plant Vogtle Unit 2 RVLIS performs in accordance with design expectations and within design error tolerances.

ITEM NO. 3

" Description of any deviations of the as-built system from previous design descriptions. with any appropriate explanation."

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Eitt,LOSURE RVLIS IMPLEMENTATION REPORT

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RESPONSE.

Based on analysis of test results, no changes are currently proposed to the RVLIS. The system _is installed and functions as described in the Final Safety Analysis Report.

ITEM NO. 4-

" Request for modification of. Technical Specifications to include all ICC .

instrumentation for. accident monitoring."

RESPONSE

Modification of the' Plant Vogtle Technical Specifications to include all

. Inadequate Core Cooling (ICC) instrumentation for accident monitoring will not be needed since.the current Technical Specifications already address the subject instrumentation.

ITEM NO. 5

" Request for NRC approval of the plant-specific installation."

RESPONSE

Based on the information provided by this implementation report, GPC requests NRC approval of the Plant Vogtle Unit 2 RVLIS.

ITEM NO. 6 "Confinn that E0Ps used for operator training will conform to the technical content of the NRC-approval E0P guidelines (generic or plant specific)."

RESPONSE

The Emergency Operating' Procedure (EOP) Verification and Validation performed

. in the Fall .of 1988 verified that the site-specific E0Ps were substantial working documents and conform to the technical content of the Westinghouse Emergency-Response Guidelines. The Fail,1988 NRC audit of the E0Ps confinns the acceptability of the procedures. The E0Ps are utilized for operator training.

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