ML20214S652
| ML20214S652 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/29/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM SL-2583, NUDOCS 8706090359 | |
| Download: ML20214S652 (5) | |
Text
Georgia Pbw:r Company
. . 333 Piedmont Avenue
.- Atlanta, Georgia 30308 Telephone 404 526-6526 Mading Address:
Pbst Office Box 4545 Atlanta, Georgia 30302 Georgia Power L. T. Gucwe W NT" 0*N W#
Marager Nuclear Safety and Licensing SL-2583 0321m X7GJ17-V230 May 29, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D,0. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 RESPONSE TO LICENSE CONDITION Gentlemen:
Pursuant to the requirements of NRC NUREG-0737, Item II.F.2 and Condition 2.C(7)a of Operating License NPF-68, enclosed is the implementation report on the reactor vessel level instrumentation system (RVLIS) for Plant Vogtle Unit 1. Items to be addressed in the impicmentation report required for RVLIS are cited in Appendix L to Supplement 1 to the Safety Evaluation Report for Plant Vogtle and are repeated in the enclosure for your convenience. This submittal should be forwarded to the Office of Nuclear Reactor Regulation for review.
Should you have any questions in this regard, please contact this office at any time.
Sincerely, f 4_s= -
L. T. Gucwa JAE/Im
Enclosure:
- 1. Implementation Report on Reactor Vessel Level Instrumentation System for Plant Vogtle Unit 1 c: (see next page) fop gsqgd57E%p P
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GeorgiaPowerd U. S. Nuclear Regulatory Commission May 29, 1987 Page Two c: Georaia Power Comoany Mr. R. E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.
Mr. J. F. D'Amico Mr. C. W. Hayes GO-NORMS Southern Comoany Services Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridae Mr. B.14. Churchill, Attorney-at-Law Troutman. Sanders. Lockerman & Ashmore Mr. A. H. Domby, Attorney-at-Law U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator.
Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)
Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle Georaians Against Nuclear Enerov Mr. D. Feig Hs. C. Stangler l
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GeorgiaPower d ENCLOSURE PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 RESPONSE TO LICENSE CONDITION The following information constitutes the implementation report on the reactor vessel level instrumentation system (RVLIS) for Plant Vogtle Unit 1 as required by NRC NUREG-0737, Item II.F.2 and Operating License Condition 2.C(7)a. The items responded to by the following information were cited in Appendix L of Supplement I to the Safety Evaluation Report for Plant Vogtle and are repeated for the purpose of convenience. Please note - that Items 1, 2, and 3 below are similar to Items - A, B, and C identified in Georgia Power Company (GPC) letter GN-10ll dated July 24, 1986 concerning the RVLIS implementation report.
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 I was completed prior to fuel load. The system was tested, calibrated and made functional prior to initial criticality using Plant Vogtle Unit 1 Startup Test,1-5RP-01.
The results are documented in the test procedure (1-5RP-01) and Hestinghouse Field Service Report NSID-EIS-87-10, Revision 0 and are available for inspection by the NRC.
l ITEM NO. 2
" Summary of licensee conclusions based on test results, e.g.:
(a) the system performs 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."
0321m E-1 05/29/87 SL-2583 700775
GeorgiaPower d ENCLOSURE (Continued)
PESPONSE TO LICENSE CONDITION
-RESPONSE The Plant Vogtle Unit 1 RVLIS performs in accordance with design expectations and within design error _ tolerances. However, during startup testing the upper range level trantmitter (LT-1310) failed the test criteria. Readings for upper and full range level were taken at reactor coolant system (RCS) temperatures of approximately 2000F and 5570F with no pumps running. The readings for the upper range level were 104%
and 108%, respectively. Startup Test 1-5RP-01 acceptance criteria required these readings to be within 3% of each other. The deviation was documented on Deficiency Card # 1-87-807. This acceptance criteria was incorrect. With RCS at cold conditions, the differential pressure transmitter is overranged since it is spanned to the top of the reactor vessel. Hlth the change in RCS fluid density at hot conditions the transmitter / electronics are capable of reading at the top of the stand pipe. Therefore, the 3% accuracy requirement only applies train to train at hot conditions.
ITEM NO. 3
" Description of any deviations of the as-built system from previous design descriptions with any appropriate explanation."
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. However, the Plant Safety Monitoring System Verification and Validation effort is still underway; therefore, modifications to the system software may still be forthcoming.
ITEM N0. 4
" Request for modification of Technical Specifications to include all ICC instrumentation for accident monitoring."
RESPONSE
Modification to the Plant Vogtle Unit 1 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.
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GeorgiaPower d ENCLOSURE (Continued)
RESPONSE TO LICENSE CONDITION 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 1 RVLIS.
ITEM NO. 6
" Confirm that the E0Ps used for operator training will conform to the technical content of NRC-approved E0P guidelines (generic or plant specific)."
RESPONSE
The Emergency. Operating Procedure (EOP) Verification and Validation performed in mid-1985 verified that the E0Ps were substantial working documents and conform to the technical content of site-speci fic E0P guidelines. The November 1986 NRC audit of the E0Ps confirm the acceptability of the procedures. The E0Ps are utilized for operator training.
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SL-2583
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