ML20067D243

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Forwards Summary of Test Procedure Tp 664/2,Section 9.5, Determination of Saturation Margin & RCS Pressure Vs Time Following Simulated Loss of Pressurized Heaters, to Fulfill 811214 Partial Initial Decision Requirements
ML20067D243
Person / Time
Site: Crane Constellation icon.png
Issue date: 12/07/1982
From: Hukill H
GENERAL PUBLIC UTILITIES CORP.
To: Haynes R, Stolz J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation
References
5211-82-272, NUDOCS 8212130104
Download: ML20067D243 (6)
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osOffie d

7 x48 Route 441 South Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386

$Nriter"s Direct Dial Number:

Deconber 7,1982 5211-82-272 IfficeofNuclearReactorRegulations Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Mr. R. C. Haynes Region I, Regional Administrator U. S. Nuclear Regulatory Comnission 631 Park Avenue King of Prussia, PA 19406 Gentlemen:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Reactor Coolant Systerr. (RCS) Pressure Control Following A Loss Of Offsite Power (LOOP)

In paragraph 755 of its December 14, 1981 Partial Initial Decision (PID), the Atomic Safety and Licensing Board (ASLB), acknowledging the importance of RCS pressure in maintaining natural circulation, imposed as a pre-restart condition the requirement that Licensee demonstrate the ability to control RCS pressure using the HPI system, without relying on the pressurizer heaters. The ASLB specified that the demonstration be performed under conditions of a simulated or actual LOOP, with the RCS average temperature close to the normal operating temperature.

Further, the ASLB stated that the demonstration may be done using the normal makeup and letdown system (rather than the complete HPI system) in order to avoid unnecessary wear and tear on the safety valves.

Appropriate testing was performed at TMI-l during the hot functional testing in the fall of 1981. We believe this test is responsive to the above ASLB requirement. These tests were performed at normal plant temperature and pressure and did not use equipment to control pressure not normally avail-able following a LOOP.

(Reactor Coolant Pumps were used only to maintain RCS Temperature due to an absence of decay heat). The test performed demon-strated that pressurizer filling to control plant pressure is not of concern and therefore, the use of other than normal letdown was not necessary.

In addition, extrapolating the data shows that sufficient pressure to maintain 8212130104 821207 PDR ADOCK 05000289 P

PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

4 Messrs. J. F. Stolz & R. C. Ilaynes 5211-82-272 adequate saturation margin to support natural circulation is available for a.

substantial time beyond two hours particularly as plant cooldown occurs.- In addition, plant cooldown would tend to further increase saturation margin..

It should be noted that the test length of two hours was selected, in that it is the maximum time necessary to connect certain pressurizer heaters to the onsite power system.

The detailed test procedure and results are available onsite for NRC review.

Based on the above, we request the NRC staff to concur that we have fulfilled the ASLB requirement.

Sincerely, vr

~ I) g

. D.'iukill Director, TMI-l llDil: CWS:vj f Attachments 2

1

. ~. -,

.e

Summary of Test Procedure TP 664/2, Section 9.5 - Dete?uination of Saturation Margin and RCS Pressure Versus Time Following a Simulaued Loss of Pressurizer Heaters During the performance of TP 664/2, (Pressurizer Operation Tect) a portion of the test consisted of de-energizing all five (5) banks of pressurizer heaters and determining the degradation of both the Tsat margin and Reactor Coolant System (RCS) pressure over a two (2) hour period. At the end of the two hour time period 126KW of pressurizer heaters (Bank 4, Group 9) were energized and verification that the RCS pressure stabilized and/or began to increase was performed. This was done to

~

verify that the heat losses from the pressurizer did not exceed 126KW as previously determined analytically. The conditions that existed prior to de-energizing all banks of pressurizer heaters are listed below:

a.

Average RCS Pressure (NR) - 2163.75 psig.

b.

Average RCS Tc - 532.3*F.

c.

Average RCS Th - 533.l*F.

d.

Average RCS Tsat Margin - 113.4*F.

c.

Reactor Coolant Pumps in operation - 4.

f.

Additional Testing in progress - None.

The conditions that existed following the two (2) hour time period wherein the pressurizer heaters were de-energized are listed below:

a.

Average RCS Pressure (NR) - 1943.5 psig.

b.

Average RCS Tc - 532.2*F.

c.

Average RCS Th - 533.0*F.

d.

Average RCS Tsat Margin - 99.6*F.

e.

Reactor Coolant Pumps in operation - 4 The data above shows that a 50*F saturation margin can be maintained for a two (2) hour time period in the event of a loss of pressurizer heaters. The average rate of depressurization was found to be approximately 110 PSI / hour. Upon energizing the 126KW

Of Pressurizer heaters, the RCS pressure stabilized demonstrating that pressurizer

-heat losses do not exceed 126KW. Graphs showing the RCS Pressure and Tsat margin versus time for the two.(2) hour period wherein pressurizer heaters were de-energized are attached.

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  • (MINUTE,S) 3 TP 664/2

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