ML19321A662

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Forwards IE Circular 80-15, Loss of Reactor Coolant Pump Cooling & Natural Circulation Cooldown. No Written Response Required
ML19321A662
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 06/20/1980
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Eric Turner
HOUSTON LIGHTING & POWER CO.
References
NUDOCS 8007240039
Download: ML19321A662 (1)


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UNITED STATES

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NSIC June 20, 1980 CENTRAL FILES In Reply Refer To:

RIV Docket Nos. 50-498/IE Circular No. 80-15 50-499/IE Circular No. 80-15 Houston Lighting & Power Company ATTN:

Mr. E. A. Turner, Vice President Power Plant Construction and Technical Services Post Office Box 1700 Houston, Texas 77001 Gentlemen:

This Circular is forwarded for information.

No written response to this IE Circular is required.

If you,have any questions related to this matter, please contact this office.

Sincerely,

  • f-Karl V. S it Director

Enclosures:

1.

IE Circular No. 80-15 2.

List of Recently Issued IE Circulars i

8007240039

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SSINS No.: 6835 Accession No.:

UNITED STATES 8005050073 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.

20555 IE Circular No. 80-15 Date:

June 20, 1980 Page 1 of 4 LOSS OF REACTOR COOLANT PUMP COOLING AND NATURAL CIRCULATION C00LDOWN Description of Circumstances:

This Circular contains information on the St. Lucie Unit I response to a total loss of component cooling water (CCW) flow to reactor coolant pumps.

Pres-surizer level and primary system pressure response indicate that voids were formed in the reactor vessel during the ensuing natural circulation cooldown.

The void was believed to have been steam in the area located directly under the reactor vessel head.

At time 0226 on June 11, 1980 with St. Lucie Unit 1 at full power, an electrical short across a solenoid valve terminal board caused one of two j

series containment isolation valves in the CCU return from all reactor coolant pumps (RCP) to fail shut. The terminal short resulted from environmental effects of a minor steam leak in the immediate vicinity of the solenoid valve.

After unsuccessful attempts to restore CCW flow, the reactor was tripped manually at time 0233.

Within two minutes, all four RCPs were also manually tripped. A natural circulation cooldown was initiated at approximately 0300.

Component cooling water flow to RCPs was restored at 0400.

The solenoid operated air valve whose terminal board had shorted was bypassed with a temporary air line to reopen the CCW valve (HCV-14-6).

Although variations in seal leakoff flowrates were observed, the seals on the four idle RCPs did not fail.

St. Lucie has Byron Jackson reactor coclant pumps with three stage mechanical seals plus a vapor seal.

Controlled reactor coolant bleedoff flow is used for seal cooling and lubrication.

The pumps do not have a seal water injection system.

The natural circulation cooldown continued uneventfully until after time 0600.

The highest cooldown rate achieved was approximately 65 to 70 F per hour.

Between 0600 and 0630 RCS pressure was reduced from 1140 to 690 psi by charging water through the pressurizer auxiliary spray line.

Pressurizer level incre.ased rapidly around 0700 while char iaj Pressurizer level continued variations f' ginp:

ity 49%gaugQiaggrayAjg,me the cooldown and depressurization cont RCS loops, pressurizer level decreased DUPLICATE DOCUMENT increase in level when charging throug two minute interval while charging int Entire document preyiously at 88 gpm, pressurizer level rose at a entered into system under:

than the charging flowrate.

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