ML20235Z282

Forwards Addl Info on Three Full Power OL Items,Per JB Hopkins 890225 Request.Initial Startup Test Program,Tdi Diesel Generators & NUREG-0737,Item II.F.2 Addressed

ML20235Z282
Person / Time
Site:	Vogtle
Issue date:	03/06/1989
From:	Bailey J GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM GN-1582, NUDOCS 8903150286
Download: ML20235Z282 (7)

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'* Geor;;ia Power Company Fost Office Box 282

• - Waynesboro, Georgia 30830 Telephone 404 554 9961 404 724 8114 Pubt Off c Bo 262 Birmingham, Alabama 35202 b--

wonone 205 870 8 "

Vogtle Project March 6, 1989 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk File: X7BC35 Washington, D. C. 20555 Log: GN-1582 PLANT V0GTLE - UNIT 2 NRC DOCKET NUMBER 50-425 OPERATING LICENSE NUMBER NPF-79 RAI: FULL POWER OPERATING LICENSE ITEMS Gentlemen:

Your letter dated February 25, 1989 from J. B. Hopkins to W. G. Hairston, III requested additional information on three items currently addressed by special license conditions in the Vogtle Unit 2 License No. NPF-79.

The information requested on these items is attached.

'If you should require any additional information, please do not hesitate to contact me.

Sincerely,

=

J pA. Bailey 8 4.

Project Licensing anager JAB /PDG:pwh Attachments xc: NRC Regional Administrator NRC Resident Inspector P. D. Rice J. P. Kane R. A. Thomas B. W. Churchill, Esquire J. E. Joiner, Esquire J. B. Hopkins (2)

G. Bockhold, Jr.

R. J. Goddard, Esquire R. W. McManus Vogtle Project File i\

8903150286 DR 890306 ADOCK 05000425 PDC

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Response to NRC Letter dated February 25, 1989 CN-1582

% Page'One ATTACHMENT STAFF REOUEST.

Item 1. Initial Startup Test Program

a. A commitment to report any changes made to the FSAR Section 14 Initial Test Program in accordance with 10 CFR 50.59 within one month of such change,

b. The number and type of changes made to the Unit 1 FSAR Section 14 Initial Test Program in accordance with 10 CFR 50.59.

RESPONSE

a. Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with 10 CFR 50.59 will be reported in accordance with 50.59(b) within'one month of such change.

b. The following changes were made to the Unit 1 Initial Test Program in accordance with License Condition 2.C.(3) of Operating License NPF-68.

ITEM REFERENCE FSAR SECTION DESCRIPTION

1. SL-2155(4/2/87) 14.2.8.2.47 Separate Natural Circulation Test from Loss of Offsite Power Test.

Allow performance of test using decay heat.

2. SL-2144(5/2/87) 14.2.8.2.28 Revise PERMS test to specifically address monitors which perform safety-realted functions or provide safety-related diagnostic indications.

3. SL-2581(6/5/87) 14.2.8.2.26 Conduct Power Coefficient Determination Test at 100%

power instead of 90%

power.

4. SL-2695(6/19/87) 14.2.8.2.57 Clarify At-Power Inter-comparison of Reactor Protection System Inputs and Plant Computer Outputs Test to define how  ;

inputs to RPS are read.

L Response to NRC Letter dated February 25, 1989 GN-1582 Page Two ATTACHMENT RESPONSE (b) continued.

IIEM REFERENCE FSAR SECTION DESCRIPTION

5. SL-2644(6/19/87) 14.2.8.2.30 Delete Flux Map Test at 90% Power

6. SL-3312(10/2/87) 14.2.8.2.52 Delete 50% load reduction test at 100% power

7. SL-3312(10/2/87) 14.2.8.2.54 Delete Steam Generator.

NRC to GPC(10/8/87) Moisture Carryover Test GN-1440(3/30/88)

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Response to NRC Letter dated. February 25, 1989 GN-1582 Page.Three ATTACHMENT STAFF REOUEST

- Item 2, Transamerica Delaval, Inc. (TDI) Diesel Generators

a. Has Attachment 1 to License No. NPF-79 been incorporated into appropriate procedures?

b. Is so, what proceudres?

c. Have there been any problems with implementing Attachment ~l requirements that lead you to conclude a change is necessary?

d. If so, what problems and changes?

RESP 0Mgg

a. Attachment 1 of License No. NPF-79 has been incorporated into the appropriate procedures,

b. Changes to the maintenance and surveillance procedures for the TDI diesel engines are subject to the provisions of 10CFR50.59 per the requirements of procedure 00056-C, " Safety and Environmental Evaluations".

The frequency of the major engine overhauls are consistent with the Design Review / Quality Revalidation report maintenance matrix.

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These requirements are incorporated into the following procedures:

28714-C "EOC [End of Cycle) Diesel Generator Checkout" 27576-C " Alternate EOC Diesel Generator Checkout" 27575-C "5 year Diesel Generator Checkout" 27578-C "10 Year Diesel Generator Checkout" All connecting rod and cylinder block inspections will be performed by- proceudre 27562-C, " Emergency Diesel Generator Maintenance".

Operations procedures 13145-2, " Diesel Generators" and 14980-2,

" Diesel Generator Operability Test" cover engine air rolls for the Unit 2 Emergency Diesel Generators.

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Response to NRC Letter dated February 25, 1989 GN-1582 Page Four ATTACHMENT

. RESPONSE continued.

Procedure 55038-G, " Diesel Start Log" triggers turbocharger inspection after 40 non-prelubed starts. Turbocharger inspections are performed by procedure 27570-C, " Diesel Generator Turbocharger Maintenance".

Trending of engine oil will be performed by procedure 54170,

" Diesel Generator Lube Oil Analysis, Trending cnd Evaluation".

c. The requirements of' Attachment 1 have been implemented with no major problems.

d. No maj or problems or necessary changes have been identified with the requirements of Attachment 1. However, after sufficient Emergency Diesel Generator operating experience has been obtained, revisions or changes. to the TDI Diesel Generator Owners Group recommendations may be proposed.

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Response to NRC Letter dated February 25, 1989 GN-1582

-Page Five ATTACHMENT STAFF REOUEST Item 3. NUREG-0737 Item II.F.2

a. Describe in more detail what calibrations have been and will be performed on the reactor vessel level instrumentation system prior to exceeding 5% power.

b. Based, on Unit 1 calibration data, how much' is the dynamic calibration expected to change the instrument calibration?

c. Based on your estimated. schedule and Unit 1 experience, approximately when will the dynamic calibration take place during Unit 2 startup.

RESPONSE

a. During the period of June 13th thru June 24th,1988, Westinghouse was on the Vogtle site to test, fill and calibrate the RVLIS hydraulics for Unit 2. This effort entailed the following:

o A visual inspection was performed on the entire system to verify installation requirements.

o All instruments in the system were functionally tested prior to filling.

o The system was pressure-tested to ensure system' integrity, o The system was put under a vacuum and filled with de-aerated, de-mineralized water.

o A fill verification test was performed on the filled system at 300 psi.

o All transmitters were final-calibrated from the sensors.

During the peirod of Tanuary 29th thru February 3rd, 1989, Westinghouse returned ta site to perform the initial start-up and functional testing of the RVLIS electronics. The following was performed:

o Scaling factors, based on plant specific data provided by the utility, were loaded into the system memory.

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Response to NRC Letter dated. February 25, 1989 GE-1582 Page Six ATTACHMENT RESPONSE (a) continued.

o Complete functional tests were performed which included five (5) point checks on each analog input, and digital input checks. Also, various simulated plant conditions were input to check system algorithm and scaling factors, o Analog output channels were calibrated.

Currently, a data logger is connected to the RVLIS input in anticipation of -plant heat-up, during which data will-be collected to correct the dynamic range compensation curve fit to actual plant conditions.

b. The dynamic ' calibration has no effect on the instrument (transmitter) calibration. The dynamic calibration is an adj ustment of the curve fit based on actual differential pressures and system temperatures collected during plant heat-up with all pumps running. This adjustment is done with scaling factors in the electronics. The dynamic range transmitter is not disturbed.

Based on Unit 1 experience, only minor adjustments to the scaling factors are expected.

c. The final scaling factors based on the heat-up data will be input into the electronics memory approximately four weeks after the data is collected and sent to Westinghouse. Data collection is complete when the plant reaches no-load, t-average, which is expected by mid-March. The data will then be compiled and new dynamic head coefficients will be generated. Westinghouse personnel will then input the new coefficients and perform final checkout of the RVLIS system. Thse actions are currently expected to be complete by the end of April.

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