ML20100A829
| ML20100A829 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 11/29/1984 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 9482N, NUDOCS 8412040101 | |
| Download: ML20100A829 (7) | |
Text
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'N Commonwealth Edison
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'; ) one First Nttionil Plaza, Chictgo. Ilhnois
( O "J ~ Addrsss R ply to: Post Offica Box 767 sj Chicago. Illinois 60690 November 29, 1984 Mr. Harold R. Denton, Director _
Office of Nuclear Reactor Regulation LU.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Startup Tests NRC Docket'Nos. 50-454/455/456/457-
Dear-Mr. Denton:
This letter provides advance copies.of revised Byron /Braidwood FSAR tables containing abstracts of startup tests.
NRC review of these changes is necessary so that the test program can proceed.
Attachment A to this letter describes the changes.
These revised tables will be incorporated into the FSAR in the next amendment.
Testing will proceed in accordance with these revisions unless the NRC objects.
Please address comments and questions regarding this matter to this office.
One signed orignal and fifteen copies of this letter are provided for NRC review.
Very truly yours, f /2,f.ABM= -
~
T. R. Tramm Nuclear Licensing Administrator Enclosure 9482N
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8412040101 841129 A
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ATTACHMENT A DESCRIPTION OF STARTUP TEST REVISIONS Table
. Test Change 14.2-64 Rod Position Indicators The RPI's are being checked for accuracy.
through comparison with the position demand indicator in accordance with the Tech Spec surveillance requirement.
If they do not agree, corrective maintenance is necessary.
There are no calibration adjustments.
14.2-72 Water Chemistry Test power levels were specified at NRC request-(Q423.48)
'14.2-75 Initial Criticality The plant condition was changed from hot shutdown to hot standby.
14.2-81 Pseudo Rod Ejection Acceptance criteria are specified more directly by referencing Table 15.4-3.
14.2-91 Turbine Trip from 20% Power Test added to satisfy NRC request (Q423.45) 9482N
B/B-FSAR AMEND!'.ENT 46 N
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TABLE 14.2-64 4
ROD POSITION INDICATORS (Startup Test)
Plant Condition or Prereouisites 9
~~
Prior to initial criticality,'RCS at hot shutdown no load operating temperature and oressure.
l Test Objective To verify that the digital rod position indication system i
operates as designed.
Test Summary Following core loading and installation of the rod mechanisms, the control rods will be operated over their full range checkcJ h of travel.
over the rod full travel range.The rod position indicators will
-- - ted-e.c c a.d Also bank insertion a arms, deviation alarms and rod bottom setpoints and alarms will be demonstrated to be within limits specifled in the FSAR.
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Acceptance criteria eN bc'-
C'CC""*C O The control rod position indicators are eeMbratet in accordance with Subsection 7.7.1.3.2.
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l i
I 9
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14.2-76
D/C-FSAR AMENDMENT 46 TABLE 14.2-72 i
WATER CHEMISTRY (Startup Test)
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Plant Condition of Prerequisites Prior to heatup fo'lo61ng core load, prior to criticality, l
at criticality, and during power level changes at approximately l 30%, 50%, 75%, and 100% reactor power.
l Test Objective Chemical analyses of the reactor coolant are performed to verify that plant chemistry is within specification and can be maintained within specification.
Test Summary Water for reactor coolant system fill and makeup will be analyzed for. chloride, flouride, suspended solids, silica, aluminum, calcium, and magnesium in order to verify coolant
, purity.
Sampling ability and analysis techniques will be demonstrated.
The ability to control RCS hydrogen, oxygen, and pH concentrations will be demonstrated.
i Acceptance Criteria Water chemistry is in accordance with Westinghouse PWR
. guidelines.
i f
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14.2-84 l
l
..., -. -. - -... ~,, - -.. -. -, - - _ -,.. - -, - -.
D/B-FSAR AMENDMENT 46 g'
TABLE 14.2-75 INITIAL CRITICALITY (Startup Test)
Plant Condition or Prerequisites withtheshutdownmarginrequirementsoftechnicalspecifications.l Plant at hot standby, and RCS boron concentration consistent Nuclear instrumentation aligned,-and conservative reactor trip setpoints made.
Test Objective To bring the reactor critical for the first time.
Test Summary All rods will be withdrawn except the last controlling bank, which is left partially inserted for control after criticality is achieved.
The all-rods-out boron conentration will be measured.
The following procedure limitations will be observed prior
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to and during the performance of the approach to critical test:
a.
A neutron count rate of at least 1/2 count per second must be observed on the source range instrumentation channels with a signal-to-noise ratio greater than 2.
b.
Predictions of critical boron concentration and control rod positions will be provided by the vendor in the initial core loading nuclear design report.
During the approach to' initial criticality, RCC bank withdrawal and RCS boron concentration reduction will be accompanied by nuclear monitoring using inverse count rate ratio plots through which criticality can be predicted.
If nuclear monitoring data indicate that criticality will be achieved before the RCC banks are fully withdrawn, further bank withdrawal will be terminated.
Bank withdrawal may be resumed after it has been verified that a continuation will not result in reducing the shutdown margin to a value less than Technical Specifications requirements.
14.2-87
D/B-FSAR AMENDMERT 46
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f TABLE 14.2-81 i
PSEUDO ROD EJECTION (Startup Test)
Plant Cor.dition or Prerequisites Reactor is critical with the neutron flux level.in the zero power physics testing range.
RCS temperature and pressure are at hot no-load values.
Testing will be repeated at 30%
l reactor power.
Test Objective l
To verify hot channel factors and rod worth with a rod l
cluster control assembly (RCCA) withdrawn from its bank position.
Test Summary Incore measurements will be made with the most reactive RCCA t
l withdrawn from its bank position to determine the resulting hot channel factors.
The worth of the most reactive RCCA will be verified to be conservative with respect to the accident l
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analysis.
Measurements will be made using the incore flux monitoring system.
Tests will be run at hot zero power and at approximately 30% reactor power.
AcceptahEe Criteria F[luesgiveninTable15.4-3.
l hot channel factors and rod worths are less than the va O
e 14.2-93
_. __ _. _ _ _ _ _ _ _ _. _ _. _ _.-_,.~.- _ ~. _..... _.
b[ Y Table 14.2-91
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Turbine Trip From 20% Power (Startup Test)
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Plant Condition or Prerequisites Plant at 20% + 3% of normal steady state full power condition with the auxiliary electrical loads supplied from the unit auxiliary transformer.
Test Objective To verify the ability of the primary and secondary plant and the plant automatic control systems to sustain a trip from 20% power without the turbine bypass to condenser system available, and to bring the plant to a' stable condition following the transient.
l Test Summary The plant will be brought to normal 20% steady state power conditions with the auxiliary loads supplied from the unit auxiliary transformer.
The plant will be tripped by manually tripping the turbine from the turbine control station.
The parameters to be monitored will include nuclear flux; reactor coolant loop temperature; pressuri7er pressure and level; steam generator level, 4
steam flow, and feed flow; turbine trip oper'ation; reacter trip breake-operaton; and controlling group rod position indication.
The parameters will be selected to determine the response of the plant control systems.
Acceptance Criteria The acceptance criteria that must be met to successfully complete the i
turbine test are:
a.
The pressurizer safety valves shall not lift; b.
The pressurizer power operated relief valves shall not lift; The steam generator power operated valves shall operate as designed c.
to remove energy; d.
Safety injection shall not be initiated; and, No unacceptable water hammer in the steam generators and/or e.
-feedwater system shall occur.
I 4. 2-I O 3 1
... _ _ _, _ -, _.