ML20207P376
| ML20207P376 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/09/1987 |
| From: | Bailey J SOUTHERN COMPANY SERVICES, INC. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.068, RTR-REGGD-1.068 GN-1308, NUDOCS 8701160081 | |
| Download: ML20207P376 (7) | |
Text
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southern Company Services, Inc.
Post Offce Box 282 Waynesbora Georgia 30830 Telephone 404 7221543 404 722-8943 Vogtle Project January 9, 1987 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Mr. B. J. Youngblood Log:
GN-1308 PWR Project Directorate #4 Division of PWR Licensing A U.S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
Letter GN-1277, dated 12/31/86 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 STARTUP TEST PROGRAM: LOSS OF 0FFSITE POWER TEST I
Dear Mr. Denton:
As a result of recent discussions with your staff, Georgia Power Company has revised it:: approach to the loss of offsite power test.
to this letter includes a revised test abstract, FSAR paragraph 14.2.8.2.46, providing a description of the planned conduct of the test.
Also included in Attachment 1 is justification for the changes made.
The information of this letter supercedes the information of the referenced letter. to this letter is a revision to FSAR paragraph 1.9.68.2, removing a previous exception to the loss of offsite power test portion of Regulatory Guide 1.68.
The attached revisions to the FSAR will be incorporated in the next FSAR amendment.
If your staff requires any further information, please do not hesitate to contact me.
Sincerely,
.k*
J. A. Bailey Project Licensing Manager MSH:rbs Attachments xc:
See next page 8701160091 870109
~
PDR ADOCK 05000424 A
'.e Mr.-Denton
~ January 9, 1987' Page 2 xc:
R. E. Conway NRC Regional Administrator-R. A. Thomas NRC Resident Inspector J. E. Joiner, Esquire D. Feig B. W. Churchill, Esquire R. W. McManus M. A. Miller (2)
L. T. Gucwa
.B. Jones, Esquire Vogtle Project File G.-Bockhold, Jr.
=
un n i
ATTACIRENT 1 t
Subject:
Revision for FSAR Section 14.2.8.2.46, Loss of Offsite Power A revision to the Loss of Offsite Power test abstract, Section 14.2.8.2.46, Ammendment 29 (dated 11/86) has been requested and is included below. All sections were revised as shown below. Strikeouts are deletions; additions are underlined. The entire abstract is shown for clarity. Reasons for chan8e are listed below the abstract.
This test causes a loss of offsite power to the entire plant.
14.2.8.2.46 Loss of Offsite Power at Greater Than 10-Percent Power Test A.
Objective To demonstrate pe6mney plant response following a plant trip with no offsite power available.
B.
Prerequisites 1.
The reactor will be operated at approximately 10 to 20 percent power with the reserve auxiliary transformers supplying station electrical load.
2.
The test will occur prior to ascending from the nominal
~ M power plateau.
C.
Test Method 1.
Manwe&&y te6p the remetee, Manually start equipment as required for protection of non safety related secondary equipment.
2.
S&avleeneeve&y feelete non-4E leede wh4eh wow 4d effece pe6nery plant responeer Isolate the reserve auxiliary tr,ansformers.
3._
Verify reactor triD.
34 Vee 644ee64en e4 Verify peeper automatic starting 2
and leed sequeno4ng automatic loading of diesel generators 6e demoneteeeed as desee ned in 44,Grav4,97.
5.
Verify that natural circulation conditions have been established.
46.
Verify that the RCS can be maintained in a stable shutdown condition utilizing the power-operated atmospheric relief valves to remove decay heat.
I
-ATTACHMENT 1 Abstract For Loss Of Offsite Power Test (Continued)..... 01/08/87.........
7 Certain-non safety related secondary plant equipment may be immediately restarted.
D.
Acceptance Criteria 1.
The automatic transfer es from the reserve auxiliary transformerstto the onsite standby power supply is demonstrated as deseeibed in 44,31814,97 2.
The primary plant can be maintained in a stable condition on natural circulation using the battery and diesel power supplies for 30 minutes.
(End Of Abstract Text)
Justification For Changes Section A: OBJECTIVE:
The scope of the test has been expanded to include the entire plant.
Section B: PREREQUISITES:
1.
The reserve auxiliary transformers normally supply power to the station below 20% power. This lineup prevents the turbine / generator from supplying power to the station per design for 30 seconds after turbine trip. This method forces a simultaneous loss of power without turbine coastdown.
2.
Completion of this testing prior to leaving the 20% plateau conforms to recently restated NRC and Reg. Guide 1.68 philosophy of testing safety features as soon as practical. The plant's turbine generator overspeed trips, generator excitation, and other items important to safe operation must be sufficiently adjusted, and these adjustments will require operation at the 20% power plateau.
2
ATTAC K NT 1-Abstract For Loss Of Offsite Power Test-(Continued)..... 01/08/87.........
<Section C: TEST METHOD:
1.
Battery powered lubrication and seal oil system pumps in the
_. secondary plant will be started prior to the test to ensure continuous protection of secondary equipment including the main-turbine generator, main generator, and main feedwater-pump turbines.
2.
Isolating power.from the reserve auxiliary transformers will trip the reactor and the plant.
3.
Resulting reactor trip must be verified.
4.-
The diesel generators will autostart and autoload on loss of offsite power. Timing and sequencing verification will not be performed. The preoperational test will have performed this measurement. Verification of autostart and autoload are sufficient.
5.
The order of performance has been changed between this and the following step because natural circulation is normally verified within ten minutes. This occurs prior to the 30 minute requirement for maintaining the RCS stable, 6.
The order of performance was changed. Stable conditions are a part of this test.
7.
In order to protect equipment and preserve chemistry conditions in the secondary side, certain equipment includiigg main feedwater pump and main turbine lubricating oil, turning gear motors, generator seal oil pumps, condensate pumps, and circulating water pumps may be immediately restarted.
Service and instrument air to the control and auxiliary buildings and containment will not be restarted until 30 minutes after start of the test.
I i
Section D:
ACCEPTANCE CRITERIA:
1.
References to preoperational testing were deleted. The original intent was to take credit for the prcoperational test in FSAR Section 14.2.8.1.97 and not perform'this activity during startup testing. Automatic starting and loading will now be verified as requested by the NRC.
2.
Grammar correction.
I i-(End of Justification Text.)
i 3
_,~
. ~. ~
ATTACHMENT 2 VEGP-FSAR-1 listing of the plant structures, systems, components, and the design features and performance capability tests that should be demonstrated during the initial test program.
The guide also provides information on inspections that will be performed by the NRC and provides guidance on the preparation of procedures for the conduct of initial test programs.
l((.
1.9.68.2 VEGP Position 24 Conform as follows, except for Appendix A Section 5, Subsections E, F, I, M, U, CC, HH, II, Jef#and KK, Section 1, Il l
Subsection 0 (1), and Section 4, Subsection T.
29 Reverse flow through idle RCS loops will not be measured as required by paragraph 5(m).
VEGP will not be licensed to 16 24 operate with idle loops, therefore, these measurements are not applicable.
Tests U and MM will not be performed as the results obtained will be similar to the results obtained during a turbine trip from 100 percent power which will be performed.
The closure times for the MSIVs will be verified during hot functional and preoperational testing.
The loss of or bypass of feedwater heaters test (test KK) will not be performed as results will be similar, but less severe than those obtained during the load swing test, section 14.2.8.2.27.
15 The gaseous and liquid radwaste systems (test CC) will be tested as decribed in the gaseous waste processing system preopera-tional test abstract (paragraph 14.2.8.1.48) and the liquid waste processing system preoperational test abstract (paragraph 14.2.8.1.49).
Performance of these tests during the power ascension test phase would produce the same results as testing during the preoperational test phase.
The complete loss of flow at full power test (test II) will not O.
l be performed.
Results for reactor coolant system (RCS) flow W
rates obtained in the flow coastdown test, paragraph 14. 2. 8 ~. 2. 5, will verify that the RCS flowrates assumed in section 15.3.2 are conservative.
The load swing test (test HH) will be performed at 30 percent, 75 percent and 100 percent.
A load swing at 50 percent power 24 will not be performed.
This conforms with the standard l
Amend. 9 8/84 Amend. 15 3/85 Amend. 16 4/85 Amend. 17 7/85 Amend. 19 9/85 Amend. 24 6/86 Amend. 25 9/86 1.9-60 Amend. 29 11/86
ATTACHENT 2 VEGP-FSAR-1 i
Westinghouse startup program.
The load swings at 30 percent, 75 percent and 100 percent power and are adequate to demonstrate 4
the dynanic response of the facility.
The dropped control test (test F) will not be performed.
The design has been verified and documented by testing at a prototype plant.
In addition, difficulties identified in a recent INPO report in performing the test have caused significant transients in the reactor plant resulting in peaking problems.
23 The pseudo-rod ejection test (test E) will be performed with the reactor critical at zero power, at the zero power rod insertion limit.
The pseudo-rod ejection test at greater than 10 percent power will not be performed.
Tests have been performed to validate the rod ejection accident analysis at prototype plants.
Testing of the reactor vessel head lifting rig and internal lifting rig (test 0 (1)) shall be in accordance with paragraph 19 9.1.5.2.3.4 "Special Lifting Devices" as delineated in table 9.1.5-7.
site power test (test JJ) will be performed fo d the large loa test from the 75 er plateau
'k[byisolatingonlythosenon-r'-
a c would affect primary g plant response.
t M di start;ing and
(
} y _ r
,u ng will be performed in ~piragraph' 14.2.T~rrth---
Demonstration of incore and excore nuclear instrumentation to detect control rod misalignment (test I) will not be performed 29 because the individual rod position indication system is the primary means of determining control rod misalignments.
The natural circulation test (4.T) will be performed during power ascension using decay heat instead of nuclear heat.
A decay heat test is preferable because it eliminates the need to determine actual reactor power level and avoids unrelated trips.
/
1.9.68.3 Regulatory Guide 1.68.2, Revision 1, July 1978, Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants 1.9.68.3.1 Regulatory Guide 1.68.2 Position This guide describes an initial startup test program acceptable to the NRC for demonstrating hot shutdown capability and the potential for cold shutdown from outside the control room.
Amend. 15 3/85 Amend. 17 7/85 Amend. 25 9/86 1.9-60a Amend. 29 11/86