ML20246M697
| ML20246M697 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 05/12/1989 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905190216 | |
| Download: ML20246M697 (16) | |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699
' PHILADELPHIA A. PA.19101 (215)841 4500 JOHN 5. KEMPCR esuion vece-enesiocut - suctsan May 12, 1989 U. S. Nuclear Regulatory conmission Docket No. 50-353 Attn: Document Control Desk Washington, DC 20555
Subject:
Limerick Generating Station, Unit 2 Power Ascension Testing Program
Reference:
Letter, J. S. Keroper (PECo) to R. J. Clark (NRC) dated June 21, 1988, same subject.
l i
Gentlemen:
This letter is to confirm our recent discussion with your staff regarding the referenced submittal. As indicated verbally, the requested test simpilfications and eliminations are based upon Inform-ation provided by our nuclear -steam supply system vendor, General Electric.
In particular, attached are the transmittal and writeups provided by General Electric for startup tests 5, 16A and 30 E.
If any additional Information is required, please let me know.
Sincerely,
$d/
Attachment j
ERG /dk/051189 cc:
W. T. Russell, USNRC, Administrator, Region I T. J. Kenny, USNRC, Senior Resident Inspector, LGS R. J. Clark, USNRC LGS, Project Manager j
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8905190216 890512
,o PDR ADOCK 05000353
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GE Nuclear Energy y
Generat Dectnc Company '
175 Cunner kenue. San, lose. CA 95125 MC391,(408)925-3005 March 3, 1988 Responds to: N/A PE-3550 Mr. D. B. Fetters Project Manager LGS Unit 2 Philadelphia Electric Company 2301 Market Street-Philadelphia PA 19101
SUBJECT:
LIMERICK GENERATING STATION, UNIT 2 TEST SIMPLIFICATION AND ELIMINATION
Dear Drew:
Revised writeups for Startup Tests 3, 5, 16, 22, 25, 27 and 30 are attached for your use. These revisions incorporate comments made by Ted Johnson, PECO Licensing.
i Mr. Johnson also requested a copy of the NRC Safety Evaluation for the Clinton Power Station, Proposed Changes to the Power Ascension Program. This is also enclosed for your information.
l If you have any questions, please contact me.
Ver uly yours, g
J. W. Millard Project Manager Limerick Generating Station
' RESPONSE REQ'D: No cc:
M. S. Iyer
'A. L. Jenkins A. Lileck J. B. Roche W. J. Coyle R. J.-Stipcevich
'i D. W. Diefenderfer T. Johnson W. T. Ullrich 1
File: LB/1.2.3 #294 046/JWM1/ps 1
5 l
STARTUP TEST 5 - CONTROL R0D DRIVE SYSTEM / HOT FRICTION TESTING
-TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS OBJECTIVE:
Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraph 2.b requires friction testing (for BWR's) of control rods after the core is fully loaded.
Startup Test 5,
Control Rod Drive (CRD) System, perfor;hs friction testing of all CRD's at both rated pressure /
temperature and cold conditions.
It is proposed to reduce the number of CRD's to be hot friction tested to four.
Additionally, it is proposed that CR0 friction testing be performed by measuring the differential pressure between the insert and withdraw lines or between the drive water header pressure downstream of the CR0 Friction Testing Station and reactor pressure.
DISCUSSION:
A centralized CRD Friction Testing Station is to be installed at Unit 2 of the LGS.
The test station is designed to measure CR0 drive line friction and collect friction while eliminating the need to tap into the piping of each HCU.
A single point tap is installed in the main drive water header (common to all HCus) along with a special valving arrange-ment.
The new valve arrangement allows the control rod motion to be regulated from a central point as opposed to being regulated at each individual HCU.
A AP transducer is also employed at this central point to provide a measure of the "under piston" pressure.
Since the over piston pressure is primarily regulated by the reactor vessel pressure, the other side of the AP cell is connected to a reactor vessel pressure instrument line. This combination provides a measure of the CRD piston l
'AP.
l LGS UNIT 2 PAGE 1 3/1/88
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STARTUP TEST 5 - CONTROL ROD DRIVE SYSTEM / HOT FRICTION TESTING TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS The CRD Friction Testing Station is installed permanently in the drive water header and with the exception of the data acquisition equipment no disconnects or transfers of equipment are necessary.
The benefits derived from this modification are ease of operation and reduction of testing time and associated radiation exposure during testing of CRDs after irradiation of plant CRD piping.
A central CRD Friction Testing Station was fabricated and tested at GE to demonstrate the feasibility of the testing concept and to verify that the quality of the test station pressure traces was comparable to those obtained at the HCU location.
NEDE-31511, Final Test Report, CRD Friction Test Station Evaluation dated November 1987 describes the test program and results.
Performance of the control rod drives during friction testing is compared to acceptance criteria which require that during continuous insertion, the differential pressure variation for the CR0 must not exceed a specified limit.
If the limit is exceeded during continuous insertion, a settling test is performed to determine the differential I
settling pressure and variation.
I f
CRD friction testing at the cold condition satisfies the objectives of Regulatory Guide 1.68, Appendix A, paragraph 2.b. The additional testing of Startup Test 5 at rated pressure / temperature is not required by the regulations.
Substantial testing of CRD systems at previous BWR's has shown that testing of four selected CRD's at rated pressure conditions provides adequate information on the response of the system since all of the CRD's will be scram tested at rated pressure conditions.
The scram test is the verification of the safety feature of the control rods.
Testing at previous BWR 4/5 plants (Hope Creek; LaSalle-1 and,2 and Hanford-2) has been performed on only four CRD's at rated pressure.
In addition, more recent testing of BWR/6 plants has performed friction testing on all drives at rated pressure and none have failed the criteria. The NRC safety evaluation for the Clinton Power Station, Pro-posed Changes to the Power Ascension Program, issued in April of 1986, LGS UNIT 2 PAGE 2 3/1/88
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STARTUP TEST 5 - CONTROL R0D DRIVE SYSTEM / HOT FRICTION TESTING TEST SIMPLIFICATION - REDUCED NUMBER OF TESTS ruled the change to Startup Test 5, CRD Hot Friction Testing, Test Simplification to be acceptable to the staff.
The change proposed for Limerick is identical to that proposed for Clinton.
Therefore, it is unnecesssy to friction test all the CRD's at hot conditions and it is recommended that only four CRD's be hot friction tested to demonstrate that there is no thermal expansion problem.
The four CRD's chosen should be the same as those for which scram timing is to be repeated during subsequent test conditions.
CONCLUSION:
CRD friction testing at the cold condition during Startup Test 5 demonstrates the acceptable performance of the CRD system and satisfies the objectives of Regulatory Guide 1.68, Appendix A, paragraph 2.b for friction testing. The proposed change to reduce the number of CRD's to be hot friction tested does not adversely affect any safety systems or safe operation of the plant and therefore does not involve an unreviewed safety question.
Startup Test 5,
Control Rod Drive System, can therefore be simplified by reducing the number of CRD's to be hot friction tested to four.
Additionally, the differential pressure between the drive water header downstream of the CRD Friction Testing Station and reactor pressure is an acceptable substitute for the differential pressure between the l
insert and withdraw lines for performance of CRD friction testing and either method may be used.
Figure 4, taken from NEDE-31511, shows a comparison of pressure differentials between header pressure and reactor pressure (PR) for-the test station and pressure differential between pressure under piston (PU) and reactor pressure (PR) for pressures sensed across the CRD flange.
LGS UNIT 2 PAGE 3 3/1/88 1
STARTUP TEST 5 - CONTROL R0D DRIVE (CRD) SYSTEM (FORMERLY SUT-5) 02 cCTIVES:
The test objectives are to demonstrate that the CRD system operates over the full range of pri. nary coolant temperatures and pressures, from ambient to operating, and to determine the initial operating characteristics of the entire CRD system.
PREREQUISITES:
The process
- computer, scram time recorder, or equivalent recording equipment is online and available to monitor events; the CRD electrical and hydraulic system preoperational testing is completed satisfactorily; and the vessel water level is always above the upper core grid during all CRD movements. The reactor protection system preoperational test is completed, and the scram pilot valves are ready for energization.
TEST METHOD:
For Unit 1, during fuel load, a visual check is made of the position indication of each control rod, and the four-rod displays are checked for missing numbers.
Insert and withdrawal times are verified during fuel load, and again at rated pressure for selected rods. Scram testing will be performed following fuel loading and at rated pressure.
Coupling checks are again verified by the operator.
Friction testing is conducted by measuring the pressure differential between the insert and withdrawal lines during the continuous insertion of a control rod.
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LGS UNIT 2 PAGE 1 3/1/88
7 STARTUP TEST 5 - CONTROL R0D DRIVE (CRD) SYSlEM (FORMERLY SUT-5) j TEST METHOD:
I For Unit 2, during fuel load, a visual check is made of the position indication of each control rod, and the four-rod displays are checked for missing numbers.
Insert and withdrawal times are verified during fuel load, and again at rated pressure for selected rods.
Scram testing will be performed following fuel loading and at rated pressure.
Coupling checks are again verified by the operator.
Friction testing is conducted by measuring the pressure differential between the insert and withdrawal lines or between the drive water header pressure downstream of the CRD Friction Testing Station and reactor pressure during the continuous insertion of a control rod.
ACCEPTANCE CRITERIA:
Scram times and friction test results fall within acceptance limits.
Each CRD has normal insert and withdrawal times within the limits indicated.
L L
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LGS UNIT 2 PAGE 2 3/1/88 1
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F/GURE4 l
12-
STARTUP TEST.MA SELECTED PROCESS TEMPERATURES SUBSTITUTE WITH Tt.]NICAL SPECIFICATION SURVEILLANCE OBJECTIVE:
Regulatory Guide 1.68 (Revision 2; August 1978), Appendix A, does not specifically address requirements for measurement of selected process temperatures.
Startup Test
- 16A, Selected Process Temperatures, establishes low pump speed limits for the recirculation pumps to avoid coolant temperature stratification in the reactor pressure vessel (RPV) bottom head region and assures that idle recirculation loop.
temperature differentials are within Technical Specification limits prior to restarting recirculation pump (s).
It is proposed that the Technical Specification Surveillance procedures associated with the determination of recirculation loop temperature differentials be substituted for this portion cf the testing and that testing of the low pump speed limit be deleted.
DISCUSSION:
During initial heatup at hot standby conditions, the bottom drain line temperature and applicable reactor parameters are monitored as recirculation pump speed is slowly lowered to determine the proper setting of the low speed limiter.
The coolant temperature in the bottom head region of the RPV may be colder than that in the recircu-lation loops or reactor pressure steam space area due to flow stagna-tion and the introduction of relatively cold control rod drive cooling water when the recirculation flow is at a low value.
Excessive thermal stresses, temperature transients and neutron flux scrams may occur when reactor recirculation flow is increased, sweeping this cooler water into the core.
Therefore, it is necessary that the minimum MG set speed be set above the point where recirculation flow would not provide adequate mixing in the lower plenum.
Testing at
" previous BWRs has demonstrated that the minimum pump speed limits currently established are sufficiently above the point where adequate mixing would not occur such that this testing can be deleted, see Table 1.
LGS UNIT 2 PAGE 1 3/1/88
STARTUP TEST 16A - SELECTED PROCESS TEMPERATURES SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE i
Following recirculation pump trips, Start Test 16A monitors the bottom l
drain line temperature to determine if temperature stratification l
occurs in the idle loop (s).
Plant Technical Specifications place
)
limits on the temperature differential between the idle loop (s) and the reactor pressure vessel steam space coolant temperature to prevent restart of idle recirculation loops with significantly cooler water.
l Compliance with these Technical Specification surveillance require-ments meets the objectives of Startup Test 16A following the recirculation pump trip (s).
Therefore, the portion of Startup Test I
16A associated with measuring the recirculation loop (s) temperature differential can be substituted with the Plant Technical Specification surveillance procedure associated with idle loop (s) startup.
The NRC, in their safety evaluation report on Hope Creek Power Ascen-sion Program Test Modifications, dated January 22, 1986, found it acceptable to substitute tcchnical specification surveillance tests for portions of the selected process temperature tests.
This allowed deletion of the tpst to establish the low-speed limiter for the recirculation pumps.
The staff noted that testing performed at Limerick I
and Susquehanna had demonstrated ample margins for stratification.
CONCLUSION:
Testing of the minimum recirculation pump speed at previous plants to determine applicable stratification limits provides assurance that proper performance of the recirculation system occurs at the currently set low pump speed limits.
Compliance with the Plant Technical Specification Surveillance requirements for idle recirculation loop
- startup, via existing surveillance procedures will satisiy the objectives of Startup Test 16A, Selected Process Temperatures, pripr to restart of idle recirculation loop (s).
Based on the above discussion, the proposed change will not affect any safety systers or the safe operation of the plant, and as such, does not involve an unreviewed safety question. Therefore, the Plant Technical LGS UNIT 2 PAGE 2 3/1/88
1 STARTUP TEST'ISA - SELECTED PROCESS TEMPERATURES SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE o
Specification Surveillance procedures for idle recirculation loop startup can be substituted for that portion of Startup Test 16A, Selected Process Temperatures, which measures the recirculation loop temperature differential prior to pump restart and the testing of the low pump speed limit can be deleted.
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LGS UNIT 2 PAGE 3 3/1/88 i
l STARTUP TEST 16A - SELECTED PROCESS TEMPERATURES 1
SUBSTITUTE WITH TECHNICAL SPECIFICATION SURVEILLANCE l
Table 1 - Select Process Temperature Startup Test Data Recirculation Pump Speed Temperature Differential (deg C) l Plant A(%)/B(%)
Steam Dome - Bottom Head Drain Chinshan Unit 1 20/20 8
Caorso 20/20 6
Brunswick Unit 1 20/20 8
Hatch Unit 2 20/20 7
Limerick Unit 1 18/18 10 Susquehanna Unit 2 24/25 2
Startup Test Specification 81 Level 1 Criterion (23A1918)
Technical Specification 3/4.4.1.4 81 (145 deg F)
REFERENCES:
1.
G. V. Kumar and H. J. Yang, "Chinshan Unit 2 Startup Test Results Final Summary Report," General Electric Company, April 1980 (NED0-24805).
2.
R. H. Torres, "Caorso Startup Test Results Final Summary Report,"
General Electric Company, November 1980 (NED0-24884).
3.
I.
D.
Poppel, " Brunswick Unit 1 Startup Test Results Final Summary Report,"
- Company, November 1977 (NED0-24562).
4.
R. W. Turkowski and W. Yee, " Final Summary Report Edwin I. Hatch Unit 2 Startup Test Results," General Electric Company, October 1979 (NED0-24734).
5.
Philadelphia Electric Company LGS-1 Startup Test Procedure 16.1-1, January 26, 1985.
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6.
Susquehanna Steam Electric Station Unit II General Electric Startup Test Report ST 16.1, June 19, 1984.
1 LSS UNIT 2 PAGE 4 3/1/88
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LGS FSAR TABLE 14.2-3 (Cont'd)
(Page 10 of 23)
(STP-161 Selected Process Temperatures Verification (Formerly SUT-14)
Unit: 1 Test Ob.iectives - The test objectives are:
to establish the proper setting for the low-speed limiter for the recirculation pumps, to keep the bottom head water temperature from being too low; and to demonstrate that.the bottom head drain temperature corresponds to bottom head coolant temperature, during normal operation.
Prerequisites - The reactor is in a low power condition.
Test Methods - With recirculation pumps at approximately 28% of maximum speed, allow the reactor to attain a steady-state condition. Data are recorded; then the speed of the pumps is slowly lowered until 20% of maximum speed or the minimum stable speed is reached, whichever is greater.
Data are again-
-recorded. The empirical data are analyzed to determine the optimum low speed limiter setting.
Acceptance Criteria - The resultant low-speed' setting maintains upper and lower region coolant temperatures within the specified limits.
Unit 2 Test Obiectives - The test objective is: To demonstrate that the bottom head drain -temperature corresponds to bottom head coolant temperature, during normal operation.
Prerequisites - The reactor core flow is >95% of rated.
Test Method - With co e flow at >95% of rated comparo bottom drain line temperature with recirculation loop coolant temperature.
Acceotance Criteria - The bottom head drain temperature corresponds to the bottom head coolant temperature within specified limits.
I I
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4 I
3 STARTUP TEST 30E - RECIRCULATION SYSTEM CAVITATION TEST DELETION I
OBJECTIVE:
{
Regulatory Guide 1.68 (Revision 2, August 1978), Appendix A, paragraph 5.s requires that the recirculation flow control system be calibrated as necessary and its performance verified.
At conditions of high flow and low power, both the jet pumps and the recirculation pumps may cavitate.
The analytically determined cavitation region of t;' power-flow map is protected by a cavitation interlock which will run back recirculation f1cus at low power if the cavitation limit is exceeded. Startup Test 30E, Recirculation System Cavitation, verifies that no recirculation system cavitation will occur in the operable region of the power-flow map.
Currently, this test is planned to be performed at Test Condition 3, where power will be lowered at high recirculation flow until a recirculation pump runback occurs, or the plant is at approximately 20%
power and no runback has occurred or there is indication of cavitation.
It is proposed that the testing be deleted based upon Limerick Generat-ing Station Unit 1 test data and experience at previous BWR startups.
DISCUSSION:
Acceptable response of the system near the cavitation region is deter-mined by analyzing test data and comparing to acceptance criteria which l
define the required system performance.
The recirculation system cavitation test for Limerick Generating Station Unit I was performed in j
Test Condition 3.
The test was to verify that the recirculation cavita-tion runback logic settings were adequate to prevent operation in possible cavitation areas.
This was accomplished without taking a runback by defeating the runback circuitry, establishing core flow at
>95%, and inserting control rods to reduce reactor power and therefore reactor feed flow. When the runback circuitry was activated at approxi-mately 20% feed flow, no recirculation system cavitation was noted. The applicable acceptance ctiterion was satisfied.
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LGS UNIT 2 PAGE I 1/88 1
STARTUP TEST 30E - RECIRCULATION SYSTEM CAVITATION TEST DELETION L
During the recirculation pump cavitation searches performed at previous
).
BWR startups :(including. Limerick Unit 1) no pump cavitation has been experienced' prior to reaching the analytical setpoints of the cavitation-interlocks.
The predicted cavitation curve. for the jet pumps is based on. empirical L
data determined from the Moss Landing test program.
The recirculation pump cavitation curve is based on the pump vendor supplied data.
Based on this information the intcrlock is set at 20% feedwater flow.
t.t normal operation, rated core flow, there is about a 10% power margin
.between the interlock setpoint and predicted cavitation.
The margin increases as flow is reduced as shown on the attached figure.
The verification of -the cavitation runback logic will be performed during phase one' of the initial test program.
CONCLUSION:
Cavitation interlock-setpoints are designed to allow maximum operation in the power / flow map but are conservatively set to assure that no.
recirculation system cavitation occurs.
Tests at LGS Unit I and previ-ous BWR startups have demonstrated.that cavitation interlock setpoints have been conservative, and therefore since no cavitation has been observed prior to reaching the interlock sctpoints, the deletion of this test is justified.
~,his proposed testing deletion will not adversely affect any safety related systems or safe operation of the plant and does not involve an unreviewed safety question. Therefore, Startup Test 30E, Recirculation System Cavitation, can be deleted as stated above.
REFERENCE:
~
1.
Philadelphia Electric Company Limerick Generating Station Unit No..
1, Startup Report, Rev. 2, G. M. Leitch, March 1986.
LGS UNIT 2 PAGE 2 1/88
(STP-30) Recirculation System (Formerly SUT-27)
!Lnit_1 Test Objectives - The test objectives are:
to determine transient responses and steady-state conditions following recirculation pump trips at selected power levels; to obtain jet pump performance data; and to demonstrate that no recirculation system cavitation occurs in the operation region of the power flow map.
Prerequisites - The recirculation system preoperational test is completed; the process computer is available; and power testing is in progress.
Test Method - Single-pump and two-pump trips are performed from specified power levels.
The single-pump trips are initiated by opening the generator field breaker on the applicable motor generator or by opening the M-G set drive motor breaker.
The two-pump trip is initiated by tripping the recirculation pump trip (RPT) breakers.
Reactor pressure, reactor level, steam and feedwater flow, and neutron flow are recorded during the transient and steady-state conditions.
The data recorded during rated power operation verify the noncavitation performance of the recirculation pumps and the jet pumps.
Acceptance Criteria - All responses to the pump trip test transients are within limits.
Pump performance testing under operating conditions verifies the noncavitation within the operating range.
Plant stability is within specified limits.
Unit 2 Test Objectives - The test objectives are:
to determine transient responses and steady-state conditions following recirculation pump trips at selected power levels; and to obtain jet pump performance data.
Prerequisites - The recirculation system preoperational test is completed; the process computer is available, and power testing is in progress.
l l
Test Method - Single-pump and two-pump trips are performed from specified l
power levels.
The single-pump trips are initiated by opening the generator l
field breaker on the applicable motor generator or by opening the M-G set drive motor breaker.
The two-pump trip is initiated by tripping the recirculation pump trip (RPT) breakers.
Reactor pressure, reactor level, steam and feedwater flow, and neutron flux are recorded during the transient and steady-state conditions.
Acceptance Criteria - All~ responses to the pump trip test transients' are within limits.
Plant stability is within specified limits.
_ - _ _ _ _ _ _ _ _ _ _. -