ML20238D597

Advises That All Tests Identified within Initial Startup Test Program Essentially Completed.Discussion of Status of Tests Still Remaining Encl

ML20238D597
Person / Time
Site:	Vogtle
Issue date:	09/04/1987
From:	Gucwa L GEORGIA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SL-3083, NUDOCS 8709110276
Download: ML20238D597 (5)

Text

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G3orgia Fbwer Company 333 Piedmont Avenue Atlanta. Goorgia 30309 -

. Telephone 40926 6526 u

Malling Address -.

Post Off#ce Box 4545 Atlanta. Georgia 30302 L

Georgia Power C T.Gucwa the sautnern cdoctnc system Monager Nuclear Safety and Licensing SL-3083 0475m X7GJ17-V750 September 4, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.

20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SIATUS OF INITIAL STARTUP TEST PROGRAM Gentlemen:-

Georgia. Power. Company' (GPC) has completed essentially all of the tests identified within.the initial startup test program for Plant Vogtle l

Unit 1.

A summary. report has been prepared and submitted pursuant to the

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requirements of. Technical Specification 6.8.1.1.

The purpose of this

-letter is to inform you of the status of the tests that still remain from the program.

The enclosure to this letter includes a brief discussion of' these tests.

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

Sincerely, epC~~ 4e--=

L. T. Gucwa EMB/Im-

Enclosure:

Status of Initial Startup Test Program c:

(see next page)

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U. S. Nuclear Regulatory Commission September 4, 1987 Page Two c: Ettomia Power comoany H-A.

E. Conway Mr. J. P. O'Reilly Mr. G. Bockhold, Jr.

Mr. J. F. D' Amico Mr. C. H. Hayes GO-NORMS Southern _Comnany Servicn Mr. R. A. Thomas Mr. J. A. Bailey Shaw. Pittman. Potts & Trowbridae Mr. B. H. Churchill, Attorney-at-Law J_togtman. Sanders. Lockerman & Ashmorg Mr. A. H. Domby, Attorney-at-Law LL._L_Euclear Regulatory Commission Dr. J. N. Graca, Regional Administrator Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies) j Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle

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i Georgians Aaainst flu _ clear Enerav Mr. D. Feig

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Ms. C. Stangler i

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MGeorgia Powe,r m ENCLOSURE m

PLANT V0GTLE - UNIT 1 4'

MRC DOCKET 50-424-

/PExATING LICENSE NPF-68 STATUS uf INITIAL STARTUP TEST PROGRAM Automatic Stears Generator Level Control Test (FSAR 14.2.8.2.25) j Thel objectives of this test are to verify the stability of the J

-automatic steam -generator level control system during simulated transients at various power conditions and to verify the operation of the

. variable speed, feature of the main feedwater pumps.

. Testing - of. the automatic steam generator level control system was n

M conducted : during initial low power (1-15 percent) operation.

Control system adjustments and-- tuning of the feedwater regulating valves were accomplished ac part of this testing.

Steam generator level response was i

then cbserved. during normal plant operations and during transients such 2

as the 10 percent load swing tests (at the 30 and 75 percent power level-test plateaus) and the 50 percent load reduction test (from 75 percent power)..Results from these tests demonstrate the stability of the i

iautomatic steam generator level control system as well_ as proper operation of the variable speed feature of the main feedwater pumps.

Additional confirmation of these findings will be obtained during the 10 l

percent load swing tests and 50 percent load reduction tests that will be conducted from full power conJitions (see below).

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~ LQad Swina Test (FSAR 14.2.8u2.27)

The objective of-this test is to verify proper nuclear plant I

response, including automatic control systems performance, when step load j

changes are introduced to the turbine-generator at 30, 75, and 100 1

percent power levels.

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Load swings of -10 and +10 percent were conducted at the 30 and 75-percent power level test plateaus.

Satisfactory results were achieved l

for these tests with the exception that during the +10 percent swing from 65 to 75 perc'ent power an overshoot occurred due to improper setting of the : turbine load limiter.

Additionally, minor adjustments were made to j

the automatic steam generator level control system. The load swing tests at the 100 percent power level remain to be completed.

These tests will be conducted in conjunction with the maintenar,a outage planned to begin in early October.1987.

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Georgia Power n ENCLOSURE (Continued)

STATUS OF INITIAL STARTUP TEST PROGRAM Large Load Reduction Test (FSAR 14.2.8.2.52)

The objective of this test is to demonstrate satisfactory plant response during large load reductions without tripping the reactor or actuating safety equipment.

A 50 percent load reduction test was conducted from 75 percent power.

The results were unsatisfactory in that a faulty relay card in the rod control system required the operators to manually insert control rods to reduce reactor power.

The plant was stabilized, however, and the reactor did not trip.

This test is planned to be repeated from 100 percent power in conjunction with the maintenance outage planned to begin in early October 1987.

Steam Generator Moisture Carrvover Test (FSAR 14.2.8.2.54)

The objective of this test is to determine the moisture carryover performance of the steam generators.

This test is currently being reviewed in conjunction with the secondary. plant chemistry.

The test requires that the polishing system be out of service for approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, which the secondary plant chemistry is unable to support at this time.

Thermal Exoansion Test (FSAR 14.2.8.j2.48)

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The objectives of the thermal expansion test are (1) to demonstrate l

that essential Nuclear Steam Supply System (NSSS) and Balance of Plant (80P) components can expand without obstruction and that the expansion is in accordance with design, (2) to verify during cooldown that the components return to their approximate baseline cold positions, (3) to I

resolve discrepancies from hot functional testing, and (4) to test 1

modifications made since hot functional testing.

Any systems not tested l

during hot functional testing are tested as part of the thermal expansion I

test.

i Walkdowns of essential components have been conducted at temperature plateaus during plant heatup (ambient,

2500F, 3500F,

4500F, and full temperature plateaus) and at the 30, 50, 75, 90 and 100 percent i

power levels.

Displacement data cellected at each plateau wa-evaluated J

and found acceptable prior to proceeding to the next plateau.

The 100 percent power data has also been evaluated and found acceptable.

The 1

remaining action for this test involves the verification during cooldown that the components return to their approximate baseline cold conditions.

This will be accomplished during the plant tooldown associated with th6 maintenance outage planned to begin in early October 1987.

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. Georgia Power n ENCLOSURE (Continued)

STATUS OF INITIAL STARTUP TEST PROGRAM Dynamic Response Test (FSAR 14.2.8.2.43)

The objectives of the dynamic response test are (1) to verify during power range testing that the stress analysis of essential NSSS and 80P components under transient conditions are in accordance with design, (2) to resolve discrepancies from hot functional

tasting, (3) to stest modifications made since hot functional testing, and (4) to test systems not tested during hot functional testing.

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Numerous measurements and visual inspections were performed to ve'rify, component response to steady-state and transient loadings.

The testing.

.has essentially been completed with the exception of verifying main steam system response to the rapid closure of the turbine stop valvest from.

approximately 100 percent power.

This test will be conducted in conjunction with the maintenance outage planned tu begin in early Oc:tober 1987.

Power Ascension Test Seauence (FSAR 14.2.8.2 5.01 l

The power ascension test sequence defines the overall sequence of testing for tests conducted at the various plateaus following the low power physics testing at 0-5 percent power.

No specific objectives exist j

for this test sequence.

The test sequence remains open pending t

completion of the power ascension testing.

H PlAILt_EerformancfLIftst (FSAR 14.2.4,2.55)

The objectives of the plant performance test are to (1) monitor secondary plant systems under loaded conditions during power ascensior testing and (2) to make adjustments to the systems as necessary to improve plant efficiency.

The secondary plant systems were observed throughout the power ascension test program.

Several problems associated with the calorimetric determination of reactor power and with level control of certain feedwater heaters were identified and resolved.

Adjustments will continue to be made to the plant systems to improve plant efficiency.

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