ML18079A778
| ML18079A778 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/03/1979 |
| From: | Librizzi F Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7908100156 | |
| Download: ML18079A778 (10) | |
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Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 August 3, 1979 Director of Nuclear Reactor Regulation~~lhA
- u. s. Nuclear Regulatory Commission OIJ(J['l"'n1t Washington, DC 20555 I/Jiff fJ&
Attention:
Mr. Albert Schwencer, Chief Gentlemen:
Operating Reactors Branch #1 Division of Operating Reactors ADDITIONAL INFORMATION CYCLE 2 RELOAD ANALYSIS FACILITY OPERATING LICENSE DPR-70 UNIT NO. l SALEM GENERATING STATION DOCKET NO. 50-272 Attached are a description of a Salem No. l cycle 2 startup physics test program and a description of the cycle 2 augmented surveillance pr6gram for th~ detection of dropped contr61 rod rodlets.
This information was requested by Ms. M. Chatterton of your staff.
If you have any que~t~ons concerning this material, please feel free to contact us.
CENTENNIAL OF LIGHT
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1879 1979 Very truly yours, Fran~i Gerieral Manager -
Electric Pr6duction
!Jo~1 I
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790~ 100 'r;6.
95-2001 (300M) 1-79
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General:
Startup Test Program Description Salem Unit 1 Cycle 2 The startup program is written such that there is a mandantory hold point at the zero, 50, and 100%
testing plateau.
The Station Operating Review Committee reviews the data and makes a decision as to continued escalation of power.
Deviations between measurement and design beyond established tolerances could call for a review of test data, a repeat of the measurement or a review of the safety analysis.
Operation is always within FSAR and Technical Specification limits.
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Startup Test Program Description Salem Unit 1 Cycle 2 Test Initial Criticalitv.
Initial Conditions:
Mode 3, Tave = 547°F, CB = 2000ppm Shutdown Banks withdrawn Control Banks inserted Test
Description:
Pull control banks to D at 160 steps.
Dilute to criticality.
Determine point of adding heat.
Checkout reactivity computer.
Acceptance Criteria Design:
Reactivity computer readings are within 4% of doubling time measurements.
FSAR/T.S.
Reactor must achieve criticality with the control banks above the zero power insertion limits.
Startup Test Program Description
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Salem Unit 1 Cycle 2 Test:
Flux Mapping Initial Conditions:
H'ZP, ARO Test
Description:
Operate Flux Mapping System in accordance with O.I.
"Flux Mapping System Normal Operation."
Acceptance Criteria:
Design:
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+ 10% for assembly Power :>. 9
+ 15% for assembly power c:::. 9 FSAR/T.S.
Not applicable below 5% power
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Startup Test Program Description Salem Unit 1 Cycle 2 Test Rod Worth Measurements Initial Conditions:
HZP This test is run several times during the startup program.
It is scheduled to measure all control bank worths.
Based on the results of these measurements, additional shutdown banks will be measured in overlap on the way out.
Test
Description:
Start.boron dilution* at approx. 500pcm/hr.
maintain criticality by adjusting the controlling bank.
Reactivity computer will monitor reactivity as a function of rod. position-.
Acceptance Criteria:
- Design:
Design value + 10% on total banks worth Design value
- 15% on any individual bank Design value not available due to Cycle 2 redesign.
FSAR/T.S.
Worth of all rods less most reactive stuck rod must be 1.6%.4K/K.
- Boron addition for measuring bank worth in overlap.
Startup Test Program Description Salem Unit 1 Cycle 2 Test Boron Endpoint Initial Conditions:
HZP Endpoints are run for each of the following rod configurations:
Test
Description:
ARO; D in; D, C in; D, C, B in; D, D, B, A in.
Adjust RCS boron to near the just critical end-point configuration.
Move rods to endpoint while measuring additional worth on the reactivity computer.
Acceptance Criteria:
Design:
Design* +so ppm FSAR/T.S.
Design* +100 ppm
- Not available yet due to Cycle 2 redesign.
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-e Startup.Test Program Description Salem Unit 1 Cycle 2 Test Isothermal Temperature Coeffic~ent Initial Conditions:
HZP The coefficient is measured at each of the following rod configurations:
ARO; D in.
Test
Description:
Starting with T
= 547°F, cooldown the ave primary system approx. soF.
Heat the primary system back up to 547°F.
The X-Y recorder will plot reactivity vs Tave Acceptanc~ Criteria:
Design:
Not available due to redesign of Cycle 2.
FSAR/T.S.
MTC
< OxlO - 4 AK/K *
- The. de.sign value of Doppler coefficient :ls-adaea to the isothermal measurement to~derive the moderator temperature coefficient.
Startup Test Program Description Salem Unit l Cycle 2 Test Power Coefficient Initial Conditions:
Reactor power is not changing.
The Xenon concentration is within 3% of its equilibrium value.
This test is run twice during the startup program.
First from.50% power (down to 30%), then from 100% (dmm to 80%).
Test
Description:
Take a heat balance.
Decrease power level approximately 10% and stabilize.
Take another heat balance.
Decrease power another*lO%
stabilize, and take another heat balance.
Perform this same sequence on the way back up to the original power level.
Acceptance Criteria:
Design:
Design value + 30%
FSAR/T.S.
Must fall between upper and lower curve assumed in FSAR_accident analysis.
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AUGMENTED SURVEILLANCE PROGRAM SALEM NO. l CYCLE 2 The purpose of the augmented surveillance program for Salem l cycle 2 is to detect the presence of dropped rodlets.
The program relies on several techniques, which when evaluated can detect the occurrence of dropped rodlets.
Two power distribution measurements, using the incore flux mapping system, will be taken at beginning of life hot zero power conditions (where one is normally taken).
Flux map analysis will pay particular attention to flux depressions.
If the design acceptance criteria for flux maps is exceeded (as outlined in the standard startup program) all rod worths will be measured to the N-1 condition.
The results of the above tests will be reported in the Salem l cycle 2 startup test report.
During normal power operation, periodic power distribution measurements are performed.
These flux maps will be closely analyzed for significant flux depressions.
A change in the difference between measured and predicted reaction rate integrals on the order of five to ten percent, between consecutive flux maps, could be an indication of dropped rodlets.
To compliment the flux map results, the following plant para-meters will be continuously monitored:
- 1.
The reactivity computer which receives its input from the four excore power range neutron flux detectors, con-tinuously calculates and displays reactivity.
The reac-tivit~ computer has sufficient sensitivity to detect the worth of one rodlet (approximately 10 pcm)
- Whether a
- dropped rodlet will be detected by this means, depends on the core location of the rodlet and the amount it perturbs the core leakage flux.
- 2.
A dropped rodlet which adds negative reactivity to the core, will cause the primary coolant temperature to drop due to the moderator temperature defect.
By monitoring each loop's average temperature (Tavg) this effect can be seen.
The number of rodlets detectable depends on the value of the existing moderator temperature coefficient.
- It is expected that this instrumentation will detect the worth of one rodlet at the beginning of life and three rodlets at the end of life.
- 3.
To distinguish between expected and unexpected reactivity changes, control rod motion must be monitored.
That is, reactivity change due to turbine load, xenon; boration, or dilution resulting in demand control rod motion must be separated from reactivity changes due to dropped rodlets.
e 2 -
Delta flux (AI) is very sensitive to control rod motion and therefore, can be used to detect control bank motion.
Additional control room recorders will be used for this program.
The recorders will be scaled to obtain adequate resolution of the parameters being monitored.
Chart speed will be sufficiently high to distinguish short term (dropped rodlets) from long term (xenon) ~ransients.
When an unexplained indication appears on the reactivity computer and Tavg recorders, with no control bank motion, a full core flux map will be taken as soon as core conditions allow.
All indications of dropped rodlets will be analyzed to determine their effects on safety and appropriate corrective action will be taken.
In addition, all indications of dropped rodlets will be reported.
After a period of approximately three months (during cycle 2 operation) an evaluation of the test program will be performed to determine if the program should be continued for the remainder of the cycle.
A summary report of this test program will be pre-pared at this point.