ML18081B313
| ML18081B313 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/17/1980 |
| From: | Parr O Office of Nuclear Reactor Regulation |
| To: | Mittl R Public Service Enterprise Group |
| References | |
| NUDOCS 8004070101 | |
| Download: ML18081B313 (3) | |
Text
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Distribution NRC PDR RDeY~ng Lo ca 1 PDR
- ll.4i"'l60t-e Docket File-~4Kreger MAR 1 7 1980 LWR #2 File MLErnst LWR #3 "File RPDenise DFRoss ELD Docket No. 50-311 DBVassallo IE(3)
Mr. R. L. Mittl, General Manager licensing and Environment Engineering and Construction Department Public Service Electric and.Gas Company 80 Park Place
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Newark, New Jersey 07101
Dear Mr. Mitt 1:
SAVarga NSIC FJWilliams TIC RLBaer(6)
ACRS(l6)
RABenedict THoughton DTi bbitts CG raves GHolahan RJMattson SHanauer JKni ght RTedesco
SUBJECT:
LOH POl~ER TEST PROGRAM - SIMULATED LOSS OF ALL AC PO!*JER TEST -
SALEM UNIT 2 Members of your staff and the NRC staff had a conference call on March 10, 1980 to discuss a number of aspects of the low po1tJer test program you have proposed to perform on Unit 2 of the Salem Nuclear Generating Station.
One item that was discussed was the use of reactor coolant system (RCS) pump heat to simulate decay heat in the test that simulated the loss of both on-site and off-site AC power.
The NRC staff members agreed to consider this approach further and pro-vide your organization with their preliminary reaction to the acceptability of this approach.
This was done during a telephone conversati~n on March 13, 1980 between Mr. Liden of PSE&G and Messrs. Baer and Licitra of the NRC staff. This letter is being written to confirm the points made during the March 13, 1980 telephone conversation.
The NRG staff tentatively agrees that the use of RCS pump heat to simulate decay heat is acceptable for the subject test provided that the test adequately* covers the items discussed below.
- 1.
System Thermodynamic Response If there actually were a loss of AC power event, the void fraction in the shell side of the steam generator would decrease and the steam driven auxiliary feedwater (AF) pump \\*muld be operated at maximum flo\\'J rate and would not be throttled until steam generator level had been recovered. If the plant had been operating at or near its normal full power levels the decay heat would be high.
This heat would be transported to the steam generators by natural circulation within the reactor coolant system (RCS).
Because of the high decay heat, the syst~m temperature would initially increase because steam flow to the turbine is stopped upon reactor trip. Ultimately, the atmospheric dump valves would probably be operated manually to reduce system temperatureJtl./J 800;407 o~ 9!
OFFICE~,-*.............. -................ *.
- SURNAME~........... - - -... *........ *.... * * * * -
DATE~....................................
NRC FORM 318 (9-76) NRCM 0240
'i:ru.s. GOVERNMENT PRINTING OFFICE: 1979-289-369
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MAR 1 7 1980 To obtain meaningful operator training in a simulated loss of AC power event, it appears that the test should be initiated with a level in the steam genera-tor that corresponds approximately to the shell-side water inventory that would exist at full power.
However~ this initial water level should be suf-ficient to completely cover the U-tubes.
The test should be initiated with the steam driven AF pump discharge valve set at an intermediate position such that the system coold0t-1n rate will be limited to about 50 F/hr. With this approach, the operator's actions would be similiar to that for the actual event since he would not need to throttle AF flow until normal level is achieved on the shell side of the steam generator. Once the normal water level is achieved, the AF pump flow could be throttled severely, and shell side temperature and pressure could be permitted to rise (from the RCS pump heat) to permit trai ni rw of the operator in manually using the atmos-pheric dump valves.
- 2.
Minimum Use of AC Power Performance of the simulated loss of all AC power test re.quires the use.of some AC power. If the RCS pumps are used to provide heat input, as you propose, AC pmver must be available for the RCS pumps, for the charging pumps (for RCS pump sea 1 injection) and for the coo 1 i ng systems for the pump motors.
However, within the constraints of (l)_public health and safety and (2) limiting the risk to plant equipment to prudent levels, we will require that as many AC buses as possible be de-energized.
Only in this manner do we believe that the capability of the plant to withstand a complete loss of AC power can be demonstrated to a reasonable degree, and the operator training benefits can be maximized.
In order to expedite both your detailed planning for the test and our review, we request that you* prepare a detailed proced.ure for the simulated loss of all AC power test.as soon as possible. This procedure should cover the items discussed
.above can be submitted for NRC staff revie\\'J.
The procedure should clearly iden-tify the AC buses to be left energized and the systems that are provided power by these buses.
When we receive the procedure, 1-:e will try to promptly initiate our review.
This will probably lead to one or more meetings to resolve any questions or differences of opinion on the details of the test.
If you have any questions, do not hesitate to call either Robert Baer, Emanuel Licitra or me.
Sincer/~/
Olan o. P~r: Chief Light Water Reactors Branch No. 2 Division of Project Management
. OFFICE
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NRC FORM 318 (9*7.6) NRCM 0240
- -A-u.s. GOVERNMENT PRINTING OFFICE: i.979-289-369 '
Mr. R. L. Mittl, General Manager cc:
Richard Fryling, Jr., Esq.
Assistant General Counsel Public Service Electric & Gas Company 80 Park Place Newark, New Jersey 07100 Mark Wett~rhahn, Esq.
Conner, Moore & Cober 1747 Pennsylvania Avenue, N.W.
Suite 1050 Washington, D.C.
20006 Mr. Leif J. Norrholm U.S. Nuclear Regulatory Commission Region I Drawer I Hancocks Bridge, New Jersey 08038 March 17, 1980 fi!
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