ML20006G009

Special Rept 90-02:on 900122,plant Shutdown Initiated Due to Unidentified Leakage in Rcs.Dose Equivalent Iodine Exceeded Tech Spec Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Iodine Decreased to Below Tech Spec Levels

ML20006G009
Person / Time
Site:	Crystal River
Issue date:	02/21/1990
From:	Boldt G FLORIDA POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0290-12, 3F290-12, 90-02, 90-2, NUDOCS 9003010469
Download: ML20006G009 (6)

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coneonatiou February 21, 1990  !

3F0290-12 U. S. Nuclear Regulatory Commission

• Attention: Document Control Desk Washington, D. C. 20555 -

Subject:

Crystal River Unit 3 Docket No. 50 302 >

Operating License No. DPR-72  !

Special Report 90 02  ;

Dear Sir:

Enclosed is Special Report 90-02 which is submitted in accordance with Technical Specification 3.4.8. ,

Should there be any questions, please contact this office.

Very truly yours, i bkh Gary Boldt  ;

Vice President, Nuclear Production WLR: mag Enclosure xt: Regional Administrator, Region II Senior Resident Inspector .

E 9003010469 900221 $) /r l gen noockosooggg2 g ,J/>

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' POST OFFICE box 219

• CRYSTAL RIVER, FLORIDA 326294219 * (904) 563 2943 A Florlds Progress Cornpany P- , _

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l SPECIAL REPORT 90-02 j 1

Background

Crystal River Unit 3 began plant shutdown due to Reactor Coolant System (RCS) UNIDENTITIED LEAKAGE at 1205 January 22, 1990. Plant 1 chemists collected and analyzed RCS samples during the shutdown. l At 1710 an RCS sample was obtained and analyzed for iodine activity 1 in accordance with Technical Specification requirements. Analysis )

of the sample showed Dose Equivalent Iodine (DEI) to be 1.605 l pCi/g. This value exceeded the Technical Specification limit of l 1.0 pCi/g. Plant chemists continued sampling and analysis of the l ACS at approximately four hour intervals until DEI decreased below l the Technical Specification limit. Dose Equivalent Iodine  !

decreased to below the Technical Specification limit by 1705 on ,

January 23, 1990.

In accordance with Technical Specification Requirements, this report contains the results of the DEI analysis, and documentation i of reactor power history, fuel burnup, and the time duration during J which DEI exceeded the Technical Specification limit. ,

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1. Reactor Power History. Forty eight hours before DEI exceeded the Technical Specification limit, reactor power was maintained at approximately 98.5% of rated thermal power. Five hours before DEI exceeded 1.0 4Ci/g, power decrease began. Reactor power history is presented in Figure 1.

2. Fuel Burnup by Core Region. This information is presented in Table 1 and Figure 2.

3. Cleanup (Letdown) Flow History. Reactor Coolant System letdown flow was approximately 70 gpm forty eight hours before DEI exceeded the Technical Specification limit. Letdown flow was increased to approximately 97 gpm by 0200 on January 23, 1990.

Letdown flow readings are presented in Table 2.

4. History of Degassing Operations. Reactor Coolant System degassing operations began at 1200 on January 22, 1990.

Degassing continued throughout the event.

5. Time Duration of Event. The first DEI sample to exceed the Technical Specification limit of 1.0 pCi/g was taken at 1710 on January 22, 1990. An RCS sample taken twenty four hours

( later showed that DEI concentration had decreased below

) 1.0 4Ci/g. Sample times and DEI concentration values are presented in Figure 3.

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TABLE.1 - FUEL BATCE NUESERS-AVERAGE NUMBER OF BATCM BURNUP fMWD/MT) ASSEMSLIES 4 29,669.1 1 5 17,895.5 4 7 37,909.7 24 8 27,869.2 60 2' 31,048.8 8 9 16,653.1 80 TABLE 2 - LETDOWN FLOWS LETDOWN DATE f1HE FLOW (aca) 1/18/90 1111 68.013 1/19/90 0927 74.111 1/20/90 0027 72.730 1/20/90 2352 71.050 1/22/90 1331 70.29 1/22/90 1600 68.18 1/22/90 1800 60.48 1/22/90 1930 80.61

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