ML19320B320

Forwards LER 80-030/03L-0

ML19320B320
Person / Time
Site:	Fort Saint Vrain
Issue date:	07/02/1980
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19320B321	List: ML19320B320 ML19320B323
References
P-80192, NUDOCS 8007100173
Download: ML19320B320 (6)

Text

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puhuc sendee company ofcdemio 16805 ROAD 19% *l

.. - PLATTEVILLE, COLOR ADO 8065.

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July 2, 1980 ,

Fort St. Vrain l Unit No. 1 P-80192 Mr. Karl V. Seyfrit, Director Nuclear Regulatory Comission Region IV Office of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012

Reference:

Facility Operating License No. DPR-34 l

Docket No. 50-267

Dear Mr. Seyfrit:

Enclosed please find a copy of Reportable Occurrence Report No. 50-267/

80-30, Preliminary, submitted per the requirements of Technical Specifi- -

cation AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/80-30.

Very truly yours, Ww Don Warembourg Manager, Nuclear Pro uction DW/cis Enclosure ec: Director, MIPC k\

8007290/73

REPORT DATE: July 2, 1980 REPORTA3LE OCCURRENCE 80-30  ;

ISSUE O 1 OCCURRENCE DATE: June 4, 1980 Page 1 of 5 l

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FORT ST. VRAIN NUCLEAR GENERATING STATION i PUBLIC SERVICE COMPANY OF COLORADO J 16805 WELD COUNTY ROAD 191/2 l' PLATTEVILLE, COLORADO 80651 REPORT No. 50-267/ 80-30 /03-L-0 Preliminary IDENTIFICATION OF OCCURRENCE :

During the regular surveillance test, the steam generator penetration interspace leakage appeared to be in excess of the limit allowed by LCO 4.2.9.

This is being reported as a degraded mode of LCO 4.2.9. per AC 7.5.2(b)2.

EVENT i DESCRIPTION:

On May 28, 1980, during perfor=ance of the scheduled surveillance on PCRV closure leakage, Loop 2 steam generator penetration was found to have a leak rate of 8.23 pounds per hour or 198 pounds per day. This was well within the 400 pounds per daf limit of LCO 4.2.9. j

- On June 4,1980, the surveillance was again performed and indicated steam generator penetration leakage to be 17.83 pounds per hour. This was 428 e)ounds per day and in excess of the LCO 4.2.9 limit of 400 pcunds per day.

A special test, T-145, using a pressure decay method, was written, approved, and performed later that day and showed the leakage rate to be 10.74 pounds per hour or 258 pounds per day, within the limits of LCO 4.2.9. T-145 is a more accurate test and was used at this time to insure Technical Specification compliance.

During performance of T-145, it was noted that the pressure decay rate did not decrease as reactor pressure was approached. This indicated that a pri-mary closure seal was not leaking. Futher investigation revealed a noncon-densible gas was in the hot reheat sa=ple line. A sample was taken, analyzed, and determined to be clean helium. The leakage fleu path is believed to be from the penetration interspace to the cold reheat piping and out of the steam generator via the hot reheat piping (see Figura 1) .

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l REPORTABLE OCCURREHCZ S0-30 1 ISSUE O . i Page 2 of 5 j i

i EVENT  !

DESCRIPTIO[: (Cont' d) <

On June 5,1980, T-145 was again performed and revealed a leakage rate of 10.37 pounds per hour or 249 pounds per day. A letter was sent to the Nuclear Regulatory Commission explaining the situation and requesting temporary re-lief from LCO 4.2.9, permitting up to 700 pounds per day instead of 400 pounds per dav for the suspected internal leakage path.

The Nuclear Regulatory Commission granted the requested temporary relief, agreed to the four administrative controls proposed by Public Service Com-pany, and added one additional ad=inistrative control. The five administrative controls agreed to are as follows:

1. SR 5.3.7, Secondary Coolant Activity, be conducted once each 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in lieu of once per week.

2. A pressure decay test be conducted for the Loop 2 steam generator penetration closures on a weekly basis. This pressure decay test will be utilized to determine the leakage rate. Leakage rate increases of 25% over previously values will be cause for conducting pressure decay tests daily until it can be established that the leak rate has reached an equilibrium value within the 700 pounds per day.

3. SR 5.2.16, PCRV Closure Leakage, be conducted once every two weeks for Loop 2 steam generator penetration closure rather than monthly as a comparison to the pressure decay tests.  ;

4. Radiation process conitors for the reheat steam system will be moni-tored once per shift for indication of primary coolant leakage into the secondary system.

5. Check and record the interspace differential pressure once per shift to comply with LCO 4.2.7.

The following tests were run with indicated results as follows:

To collect all the required data, T-145 was expanded and renu =bered T-147.

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REPORTA3LE OCCURRENCE 80-30 ISSUE O *!

Page 3 of 5

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t EVENT l DESCRIPTION: (Cont ' d) {

i Date Test Results Loop 2 Steas Generator Leakage 1bs/ hour lbs/ day 6-6-80 SR 5.2.16a-m 13.38 321 6-11-80 T-147 14.17 340 6-12-80 T-147 13.89 333 6-13-80 T-147 11.34 272 6-16-80 T-147 10.80 259 6-17-80 Reactor Power Reduced - Turbine Generator Off Line 6- 19-80 SR 5.2.16a-m 6.0 144 6 80 S R ' 5 . 2.16a-m 0.0 0 T-147 0 . 0. 0 6-30-80 Turbine Generator On Line - Reactor Power Increased T-147 12.96 311 The surveillance test is being conducted every other week and the T-cest is being performed weekly in accordance with the ad=inistrative controls agreed upon.

CAUSE DESCRIPTION:

Unknown at this time.

CORRECTIVE ACTION:

The administrative controls agreed to by the Nuclear Regulatory Commissinn and Public Service Company are being followed.

During the next refueltag shutdown, the problem will be investigated and repairs cade ss required. Results will be submitted in a future supple-mental report I

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REPORTABLE OCCURRENCE 80-30 ISSUE O -

Page 5 of 5 Prepared 3y: J Asa B. Reed /

Technical Services 7echnician .

Reviewed By: _ . /.Jd V

..K W. pahn echnical Services Supervisor Reviewed By: M /17 1V) h dh Frank M. Mathie f/

Operations . Manager Approved By: MuA Don Wareebourg Manager, Nuclear Produc[ tion l

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