ML18081B307
| ML18081B307 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004040313 | |
| Download: ML18081B307 (4) | |
Text
r OPS~G Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 March 31, 1980 Director of Nuclear Reactor Regulation
- u. s. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Olan D. Parr, Chief Gentlemen:
Light Water Reactors Branch III Division of Project Management SPECIAL LOW POWER TEST PROGRAM NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G wishes to advise you that we are supplementing the special low power test program described in our letter dated February 8, 1980, to include two additional tests involving establishment of natural circulation from stagnant condi-tions and boron mixing and cooldown.
A summary of each of these additional tests is provided in the enclosure to this letter.
In addition, it is our intent to perform a test to obtain baseline hydraulic data as requested in your letter of March 17, 1980.
The test outline will be provided for your review in the near future.
PSE&G will evaluate the expected radiation levels following completion of the low power test program.
This evaluation will verify that the radiation levels created by the low power testing will not prevent implementation of any re-quirements for physical alterations dictated by the NRC's Task Action Plan, as presently understood, as well as any currently identified changes to the plant.
PSE&G recognizes that the special natural circulation tests proposed may not be representative of the two-phase flow conditions that might exist following an accident.
- However, we strongly feel that the establishment of two-phase flow conditions during the test program significantly increases the potential risk of damage to plant equipment and this consideration far outweighs the benefits to be gained.
PSE&G will ensure that plant operators involved in the special tests recognize the differences in plant response between subcooled and two-phase reactor coolant flow condi-tions by conducting formal briefings with each licensed oc\\
shift crew prior to commencement of the special test
~ ~
program.
"::> ~ \\ \\
The Energy People
§ 0 0 4 0 4 0 ~ 13 95-0942
Dir. Nuclear Reactor Regulation 3/31/80 Test Repetition for Operator Training Tests will be repeated, as necessary, to insure the fol-lowing minimum operator participation:
PSE&G Tests Nos. 1 thru 6:
These tests will be repeated, as necessary, to insure that each No. 2 Unit licensed shift crew (SRO's and RO's) experiences "hands-on" participation in at least one test and observes or participates in two additional tests.
PSE&G Tests Nos. 7 thru 9:
These tests will be repeated, as necessary, to insure that each No. 2 Unit licensed shift crew (SRO's and RO's) participates in each test.
Station supervisory personnel holding No. 2 Unit SRO Li-censes and not normally assigned on a rotating shift in the Control Room will observe selected special tests to the ex-tent practical and consistent with their supervisory respon-sibilities.
It is not intended to delay the initiation of special tests nor extend the program to insure No. 2 Unit licensed shift operators who are absent from the site due to illness, vacation or other extenuating circumstances meet the participation goals described above.
Operators under-going formal training for No. 2 Unit licenses concurrent with the execution of the special test program will be scheduled to observe at least one test in each of the two major groupings above as part of their training program un-less it appears that this participation would jeopardize their successful passing of the NRC examination (i.e., NRC exam concurrent with or within a week of the special test program).
Should you have any further questions, please do not hesi-tate to contact us.
Encl.
CT31 1/2 f/1Y' R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction
IX.
Boron Mixing and Cooldown Purpose Verify boron mixing and the capability to safely cooldown and depressurize the reactor coolant system on natural circulation.
Initial Conditions Reactor power 1%
Natural circulation established Steam generators being fed by normal f eedwater supply Pressurizer heaters controling pressure Normal primary system temperature and pressure Test Description Test will be initiated by boration of the reactor coolant system and concurrent control bank withdrawal to main-tain 1% power.
Primary coolant samples will be taken from each loop at specified time interval to evaluate boron mixing in the primary~,system. Boration will be terminated when boron concentration is increased 100 ppm.
Primary system temperature and pressure will be reduced at a controlled rate in the natural circulation mode.
Cooldown will be terminated before primary system temperature reaches 450°F.
VIII.
Establishment of Natural Circulation from Stagnant Conditions Purpose Demonstrate that natural circulation can be established by simulated decay heat buildup in the reactor core.
In addition, this will simulate re-establishment of interrupted natural circulation.
Initial Conditions Reactor Power Hot zero power test range Reactor coolant pumps tripped steam generators isolated Pressurizer Heaters ~ontrolling pressure.
Normal primary system temperature and pressure Test Description With stagnant conditions existing throughout the primary system, operator will initiate feed flow to all steam generators and will slowly increase reactor power into the nuclear heating range. 'toc*... e$1;abl..i.~h a driving head for natural circulation.
Establishment of natural circulation will be verified by observing the response of the hot leg and cold leg instrumentation in each loop.
Core exit-,:
thermocouples will be monitored to assess core flow distribution.