ML18081B035
| ML18081B035 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/08/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002120560 | |
| Download: ML18081B035 (9) | |
Text
,PS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 February 8, l980 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
SPECIAL LOW POWER TEST PROGRAM NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-3ll Public Service Electric and Gas wishes to advise you that we are proceeding with the development of a special low power test program to :Oe performed on Salem 2 during the initial startup program at power levels up to five percent.
A summary of each of the spec"ial low power tests to be performed a;l:'.e provided in the enclosure to this letter.
The detailed procedures and safety evaluations of these tests will be provided for your rev'iew and approval prior to per-forming the tests.
The test program is designed to demonstrate the capability of Salem 2 to attain and maintain natural circulation under a number of different plant conditions as well as provide hands-on training for-our operating staff.
It is our intent to have each Salem 2 licensed operator participate in the conduct of at least one of the tests that demonstrate natural circulation capability during the initial startup program.
CENTENNIAL OF LIGHT
(?J 1879 1979 A
95-2001 (300M) 1-79
)
Mr. Olan D. Parr, Chief February 8, 1980 Page 2 It should be noted, however, that while every effort will be made to attain the test objectives, some modifications to the program may become neces*sary should the need become apparent during the development of the detailed test procedures or preparation of the safety evaluations.
Should you have any questions in this regard, please do not hesitate to contact us.
Enclosure
- 1;;;;;
- :-s, R. L. Mittl
(';erieral Manager -
Licensing and Environment Engineering and Construction
- 1.
Natural Circulation Verification Purpose Verify establishment of natural circulation in the primary system Initial Conditions Reactor Coolant Pumps operating Steam Generators being fed by n9rmal feedwater supply Pressurizer Heater controlling pressure Reactor Power = 3%
Normal primary system temperature and pressure Test Description Test will be initiated by tripping of all reactor coolant pumps.
The operator will verify establishment of natural circulation by observing response of the hot leg and cold leg temperature instrumentation in each loop.
Core exit thermocouples will be. monitored to assess core flow distribution.
Salem 2
II.
Natural Circulation with Simulated Loss of Offsite Power Purpose Verify that natural circulation cooling can be established and maintained following loss of offsite power.
Initial' Conditions Reactor Power 1%.
Reactor Coolant Pumps operating.
Auxiliary Feed System operating on offsite power.
Pressurizer Heaters controlling pressure.
Normal primary system temperature and pressure.
Test Description Test will, be initiated by a si:n:rql,a,ted loss of offsite power.
Reactor coolant pumps will be tripped, auxiliary feed pump and pressurizer heater loads will be transferred to diesel power.
The operator will verify establishment of natural circulation by response of hot leg and cold leg temperature instrumentation in each loop.
Core exit thermocouples will be monitored to assess the core flow distribution.
\\i Salem 2
III. Natural Circulation with Loss of Pressurizer Heaters Purpose Verify establishment of natural circulation and determine the rate of decrease of margin to saturation while in this mode and the ability to reestablish margin through cooldown and makeup.
Initial Conditions Reactor Power = 3%
Reactor Coolant Pumps operating Secondary system steam flow adjusted to maintain constant primary coolant temperature.
Steam generators being fed by normal feedwater supply Pressurizer heaters controlling pressure Test Description Test will be initiated by tripping pressurizer heaters and reactor coolant pumps.
Establishment of natural circula-tion will be verified by observing response of hot leg and cold leg temperature instrumentation in each loop.
Core exit thermocouples will be monitored to assess the core flow distribution.
The operator will observe the saturation meter to verify margin.
Prior to reaching saturation, secondary side steam flow will be increased to affect cooldown and re-establishment of saturation margin will be verified.
In conjunction with cooldown, the operator feeds the primary system to compensate for shrinkage.
Salem 2
IV.
Effect of Steam Generator Isolation (Secondary Side) on Natural Circulation Purpose Verify the effects of steam generator isolation (secondary side) on natural circulation.
Initial Conditions Reactor Power 3%
All steam generators fed by normal feedwater supply Reactor coolant pumps on Secondary system steam flow adjusted to maintain constant temperature.
Test Description Trip reactor coolant pumps and verify establishment of natural circulation.
Cooldown using steam dumps to provide sufficient margin to steam generator. safeties.
Isolate steam generators one at a time until two are isolated or primary system temperature starts to increase.
Hot and cold leg temperature will be monitored to ensure that sufficient heat is being removed by the natural circulation process.
The steam generators will be returned to service one at a time and the re-
- establishment of natural circulation will be verified in each loop.
Core exit thermocouples will be monitored to assess core flow distribution.
Salem 2
V.
Natural Circulation at Reduced Pressure Purpose Verify operation and test accuracy of primary system saturation meter.
Provide operations personnel with online experience in using saturation meter to monitor and control margin to saturation.
Provide operational verification so that changes in saturation margin will not affect natural circulation provided adequate margin to saturation exists.
Initial Cond~tions Reactor Power ~.3%
Reactor coolant pumps operating Steam generators being fed by normal feedwater supply Pressurizer heaters controlling pressure Reactor coolant system pressure normal Secondary system steam flow adjusted to maintain constant temperature
'lr.est ne*scription Test is initiated by tripping of reactor coolant pumps and veri£ying establishment of natural circulation.
Primary system pressure will be reduced as primary system temperature is held constant.
Accuracy of saturation meter will be verified during pressure reductions.
The effect of each pressure reduc-tion on natural circulation will be observed.
Core exit thermo-couples will be monitored to assess core flow distribution.
Salem 2.*
VI.
Determine the cooldown capability of the charging and letdown system.
Purpose Determine the cooldown capability of the charging and letdown system with the secondary plant isolated.
Initial Cond~tions Reactor shutdown Pressurizer heaters controlling pressure Reactor coolant pumps running All steam generators fed by normal feedwater flow Test Description Trip three reactor coolant pumps.
Cooldown using steam dumps to provide margin to steam generator safeties.
Isolate all steam generators.
Establish charging and letdown for maximum cooling capability.
Verify the cooldown capability of the charging and letdown system from the hot and cold leg temperatures in the active loop.
This will be accomplished by periodically inter-rupting feed and bleed to permit heatup.
Core exit thermo~
couples will be monitored to assess core flow distribution.
Salem 2
VII. Simulated Loss of All Onsite and Offsite AC Power to Auxiliary Feedwater System Purpose To verify:
- 1.
Hot standby conditions can be maintained,
- 2.
Auxiliary feedwater can be controlled by manual means; i.e., with loss of AC power and control air,
- 3.
Ability of 125-volt battery to supply 125-volt vital AC, and
- 4.
Selected equ;i,pment a,reas do not exceed maximum design temperature.
Initial Conditions Reactor at hot standby Reactor Coolant Pumps operating.
Pressurizer heaters controlling primary system pressure.
Test Description Test will be initiated by:
- 1.
Tripping pressuriz~r h~ateis,
- 2.
Removing AC power from auxiliary feedwater components and main steam power reliefs,
- 3.
Tripping selected spa,ce a,nd equipment coolers,
- 4.
Tripping vital battery chargers and AC power to inverter,,
- 5.
Isolating main feedwater and main steam lines,
- 6.
Establishing manual control of auxiliary feedwater,
- 7.
After two hours, terminating the test by restoring AC power and returning equipment-to normal service.
Salem 2
_J