ML19094A749
| ML19094A749 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/01/1976 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Moseley N NRC/IE, NRC/RGN-II |
| References | |
| Download: ML19094A749 (25) | |
Text
{{#Wiki_filter:e e t . VIRGINIA ELECTRIC AND RIOHMOND,VI:a.GINIA 23261 July 1; 1976: I
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- \~ '*i Mr. Norman c. Moseley, Director ~ No. 115 Office of Inspection and Enfo:c~e £ QUl ~ 197b*,; ,IJ9_)J PO&M/ALH:jlf
- u. s. Nuclear Regulatory- Comnu.ss1on -- REGUlATO :*...._ ';'
PJ .'/ , Region TI - Suite 818 ?}, u.s. NUClEAR c~~ti;~)~: /;;/*Docket Nos. 50-280 230 Peachtree Street, Northwest '/'>.. .* .,:')' 50-281 Atlanta, Georgia 30303 ~---:':;- _ .~f>:/Y License Nos* DPR-32
~ r,_:.I , ~ DPR~37
Dear Mr. Moseley:
Pursuant to Surry Power Station Technical Specification 6.6.1.a, the Virginia Electric and Power Company hereby submits a copy of the supplement to the Surry Unit Nos. 1 and 2 Startup Reports dated May 1, and July 31, 1973 respectively. Very truly yours,
- c. M. Stallings Vice President-Power Supply and Production Operations Enclosure cc: Mr. Robert w. Reid, Chief (40 copies)
Operating Reactors Branch 4 6639
- - , -.~ -
e e SURRY POWER STATION SUPPLEMENT TO THE UNIT 1 AND UNIT 2 STARTUP REPORTS JULY 1976 1
e TABLE OF CONTENTS TEST PAGE NO. INTRODUCTION 2 SU-3.lA, STATION BLACKOUT* TEST, UNIT Ill 3 SU-64, LOAD SWING TEST, UNIT Ill 5 SU-70,. PLANT TRIP FROM 100% POWER, UNIT Ill. 6 GRAPHS FOR SU-70,.UNIT 1 8-11 SU-3.lA STATION BLACKOUT TEST, UNIT #2 12 SU-64, LOAD swum TEST, UNIT fl 2 14 SU-70, PLANT' TRIP FROM.100% POWER, UNIT #2 15 GRAPHS FOR SU-70, UNIT 112 16-19 I SU.~ 60, XENON TRANSIENT TEST, UNITS 1 AND 2 20 ST-36, STEAM GENERATOR MOISTURE CARRYOVER 21 MEASUREMENT, ,UNIT ,ffl
- ST-36, STEAM GENERATOR MOISTURE CARRYOVER MEASUREMENT, UNIT 112 (l)
e. I.. INTRODUCTION The reports generated following the startup programs of Surry Land 2 did not include descriptions of several tests wh.ich were planned for perform-ance at 100% power. The units were then restricted to a lower power level due to fuel densification considerations. These tests included several.power transients, 100%-power trips, station blackouts, a Xenon transient test, station heat rate measurement and a steam generator :moisture carryover measurement. Th~ power transients, 100% trip tests, and the station blackouts have been _performed satisfactorily and are discussed in this supplement. The use of part length control rods has been precluded by Technical Specifications, thereby prohibiting the performance of the Xenon transient test. The requirements of the 100% power acceptance test have been satisfied-by verifying reliable steady state full power capabilities during normal operations. Steam generator m9i_stw.:e carryover measurements have been performed; however, results have not been final-* ized due to steam.generator modifications. * (.2)
e SU-3.lA { STATION BLACKOUT TEST
. UNIT 111
SUMMARY
This test is designed to verify the ability of the station control and protection systems to bring the plant safely to hot shutdown conditions following the* loss of power to the 4160 Volt emergency buses. lH and lJ. When the voltage on bus lH or lJ falls below the 90% level, emergency diesel-driven generators Ill and 113 are started. The undervoltage relays respond to a 75% undervoltage condition on bus lH or lJ by opening breakers 15H8 and 15J8 which cause buses lH and lJ to de-energize. Vital buses 1-I and 1-IV are de-energized causing reactor trip and turbine trip. When the diesel generators are running ac rated speed, breakers 15J3 and 15H3 close, re-energizing buses lJ and lH. In* this manner power is supplied to all equipment needed to reach and maintain hot shutdown conditions. This test was performed on March), 1973 at a power level of approximately
- 10%0 Blackout was initiated by manually opening 15H8 and 15J8 and tripping generator lockout relay 86VBU. This simultaneously de-energized emergency buses lH and JJ, and induced a generator trip.
EVALUATION OF RESULTS Immediately following the loss of power to buses lH and lJ~ emergency diesel generators /Fl and //3 started and restored power to these buses in the proper manner. Both the reactor and turbine tripped and the ensuing transients.* (3)
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\ did not cause actuation of any safety valves or the safety injection system. All systems performed properly, bringing Unit 1 to the hot shutdown condition. CONCLUSIONS This test was successfully completed with all systems performing properly. (4)
*e
/, SU-64 LOAD SWING TEST UNIT Ill
SUMMARY
The. purpose, of the Load Swing Test, Sl.]-64, is* to demonstrate the ability of- the automatic control systems to respond to a 10% step change in load* in a safe and*orderly manner. The load change is accomplished by changing the turbine demand* downward by an amount equivalent to a 10% reactor output decrease, followed shortly there-after by a. return to full power. A chart recorder, is used to obtain data on
~arious plant par~eters during the transients.
This test was performed on Unit 1 on Feb~ary 9, 1975, at an initial power level of 100%. EVALUATION OF RESULTS The plant control systems performed properly, restoring equilibrium conditions following each load transient within 10 minutes, without operator intervent:i,on, without the actuation of the steam generator relief or safety valves, pressurizer relief or safety valves, and without safety injection or reactor trip. The oscillations 'in plant variables were convergent ori the equilibrium condition, with minimum and maximum valves within the expected ranges, as . specified by the test procedure *. CONCLUSIONS The load swing test at 100% power demonstrated. the ability of Surry 1 to experience such transients without any abnormal or undesirable result. (5)
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SU-70 PLANT TRIP FROM 100% POWER UNIT /11
SUMMARY
The purpose. of the SU-70 test is to verify.the ability of the plant to sustain a trip from 100% power in the proper manner. Also, the response time of the resistance temperature detectors (RTD's) to changes in the primary coolant temperature is compared to design criterion. This test was performed on Unit 1 on Feb. 9, 1975. The attached curves are illustrative of the resulting transient... EVALUATION OF RESULTS The total plant response to trip from 100% power was satisfactory. The acceptance criteria of the test were met in ~he following manner:
- 1. Pressurizer safety valves did not lift.
- 2. Steam generator safety valves did not lift.
- 3. Safety injection was not initiated.
4 G Overall RTD response time was less than the maximufu:-al lowab-le 7. 8 0
,seconds~. (Actual. RTD response* time* was 5.28 seconds).
- 5. Nuclear flux dropped to 25% within 2 seconds after initiation of the turbine trip.
- 6. All full length rods were released and dropped.
Following trip, the steam dump valves opened properly to maintain reactor coolant temperature (Tave) and then modulated closed in a manner such that Tave smoothly approached its equilibrium value. The feedwater control system adjusted the steam generator levels to a new equilibrium level in a satisfactory manner. The pressurizer pressure decreased by 280 psia after plant trip, but was smoothly (6)
e e rest~red to its initial level. CONCLUSIONS This test demonstrated the ability of the plant to trip from* 100% without any abnormal condition or results *
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t=O* (11)
e e SU-3.lA STATION BLACKOUT TEST UNIT /12
SUMMARY
The purpose of this test is to verify the ability of the control and protection systems to bring the plant safely to a hot shutdown condition
- following a loss of electrical power to the 4160 Volt emergency buses 2H and 2J.
A 90% undervoltage condition on bus Hor J, starts the emergency diesel-driven generators 2 and 3. A 75% undervoltage con~ition causes an automatic brea~er operation which opens breakers 25H8 & 25J8 de-energizing buses 2H and 2Jc Vital buses 2-I and 2-IV are de-energized, causing a reactor trip and* turbine trip. The generator will trip 30 seconds latero After the diesels reach a sufficient speed, breakers 25J3 and 25H3 close, re-energizing buses 2J and 2H. This provides power*to all equipment required to reach and maintain hot shutdown. This test was performed on April 13, 1974 at a power level of 37%. The test was initiated by manually opening 25H8 and 25J8 and tripping generator lockout relay 86VBU~ thus simultaneously de-energizing emergency* buses 2H and. 2J, and tripping the generator. EVALUATION OF RESULTS Upon loss of power to 2H and 2J *buses, the diesels started, came up to running speed,. and closed on bus 2H and 2J, restoring power to these .buses. The reactor and turbine trips occurred as expected, and the ensuing transients were normal, with no safety injection or safety valve actuation. (1 :2)
e e.
" C,harging pump"B" failed to start *on loss of voltage on .r/ bus. as--i-e
-aaeuld ha11e elene. This was determined to be due. to dirty and misaligned electrical contacts in the starting circuit. This condition was corrected and the pump satisfactorily tested. Abnormal occurrence report AO-S2-74-02 was filed concerning this failure. CONCLUSIONS This test was completed satisfactorily with_all systems functioning as required with the. exception noted aboveo The failure of the "B" charging pump to start did not effect the validity of the test.
\
(lJ)
- SU-64 LOAD SWING TEST e
UNIT /12
SUMMARY
_The purpose of the Load Swing Test, _SU-64, is to demonstrate the ability of the automatic* control systems to respond to a 10% step change in ).cad in a safe and orderly manner. The load change is accomplished by reducing the turbine. demand
~ . .
by an. amount equivalent to a 10% decrease in reactor. output, followed shortly thereafter by a return to full power~ A chart recorder is used to monitor* various plant parameters during the-transients. This test was _performed on Unit /12, on April 13, 1974, at an initial power level of approximately 100%. -EVALUATION OF RESULTS
*The plant control systems performed properly, restoring equilibrium conditions following each load transient within 20 minutes, without operator intervention. None of the following systems were actuated during the test:.
steam generator relief or saf_ety valves,.pressurizer relief or safety valves, safety injection, or reactor trip. The oscillations in plant variables were convergent on the equilibrium condition, with minimum and maximum values within the expected range, as specified .by the test procedure. CONCLUSIONS. The load swing test at 100% power demonstrated the ability of Surry Unit
#2 to experience such transients without any abnormal or undesirable results.
(14).
e SU-70 PLANT TRIP FROM 100% POWER UNIT /12
SUMMARY
The. purpose of the Plant Trip From 100% Power, SU-70, is to vetify the ability of the plant to sustain a trip from 100% *power in a smooth and orderly manner. The response time_ of the resistance temperature detectors to changes* in primary coolant temperature is also compared to design criteron. This test was performed on Unit 2 on April 18, 1975. EVALUATION OF.RESULTS
.The total plant response to the reactor trip from 100% power was excel-lentc The steam dump valves opened properly to accomodate the loss of turbine demand and modulated closed within seven seconds such that Tave, as seen on recorder 1, smoothly approached the equilibrium value. The feedwater control system quickly and smoothly controlled the steam.generator levels. The pressur-izer pressure deviated from its initial value by a maximum of 170 psi and was properlyi restored.
lo Pressurizer safety valves ~id not lift.*
- 2. Steam generator safety valves did not lift.
3.* Safety i~jection was not initiated.
- 4. RTD response time was 5.18 sec., within the 7 .8 sec. (max) acceptance criterion.
- 5. Nuclear flux dropped to 25% within 2 seconds after initiation of the turbine trip *.
-6. All full length rods were released and _dropped.
CONCLUSIONS This test was successful.* The curves obtained during the transient are attached. (15)
e : ... RECORDER Ill SU-70 e UNIT 112 t=O
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(16)
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I ; (17)
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e SU-60 XENON TRANSIENT TEST UNIT 1 & 2
SUMMARY
The purpose of this test is to verify t~e stability of the core during Xenon oscillations and to demonstrate the suppression of such an oscillation witl;l the part length control rods. The use of part length control rods has been precluded by Technical Specifications. The stability of the core during Xenon oscillations has now been demonstrated by several years of operation, during which time, many oscillations have occurred. This test has therefore been deleted. (20)
I
."\
ST-36 STEAM GENERATOR MOISTURE CARRYOVER MEASUREMENT UNIT Ill
SUMMARY
Initial testing of moisture carryover from the steam generators resulted in an average carryover in excess of the *acceptance criteria of .25%. Several modifications were made to improve upon this *value. These improvements in-cluded reducing the diameter of the swirl vane separator *outlet orifices and increasing the deck plate relief area. The Steam Generator Moisture Carryover Measurement test, ST-36, utilized radioactive tracer technique to measure the amount of moisture carryover in the steam generators. About 100 millicuries. of radioactive N~2~ (in the form of Na 2co ) was injected into the feedwater stream of each steam generator and 3 the moisture carryover was determined by measuring the activity of the vapor-liquid mixture at various points in the steam. generator and its associated piping. This test was performed on Unit #1 on Dec. 29, 1975 at power levels of 90% and 100%. EVALUATION OF RESULTS The acceptance criterion was met after the modifications in that the moisture carryover (averaged over all 3 steam generators) was less than .25%. As determined by Westinghouse calculations the moisture carryover for Unit #1 is .17% at 100% power with steam generator "B" contributing more moisture than either "A" or "c". (21)
e e CON:CL'fiSION
~
This test demonstrated the ability of the moisture separating equipment in the steam generators to reduce the mositure carryover below the design maximum of .25%. (22)
e ,"; '<'\ ,, ... e ST-36 STEAM GENERATOR MOISTURE CARRYOVER MEASUREMENT UNIT 112
SUMMARY
This test, ST-36, utilized radioactive tracer techniques to measure the moisture carryover from the moisture separators in the steam generators. The specific activity of the liquid-vapor mixture was measured yielding the moisture content of the mixture. This test was performed on Unit lf2 on Oct. 1-2, 1975 at power levels of 90, 95 and 100%0 EVALUATION OF RESULTS Moisture carryover values are as follows: Power Level Moisture Carryover 90% .36% 95% .64% 100%* .98% None of the above moisture carryover values meet the acceptance criterion of .25% max. CONCLUSIONS The Unit 112 steam generators have experienced the same moisture carryover problem previously exhibited on Unit #1. Similar modification to reduce the diameter of the swirl vane separator outlet orifice and increase the deck plate relief area have been performed on Unit #2 and are similarly expected to reduce the moisture carryover to a value less than 025%. (~3)}}