05000280/LER-1981-047, Updated LER 81-047/03X-1:on 810910,following Reactor Trip & While Returning to Power,Specific Activity of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit. Caused by Fuel Element Defect in Reactor Core

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Updated LER 81-047/03X-1:on 810910,following Reactor Trip & While Returning to Power,Specific Activity of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit. Caused by Fuel Element Defect in Reactor Core
ML20062F680
Person / Time
Site: Surry Dominion icon.png
Issue date: 08/03/1982
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20062F679 List:
References
LER-81-047-03X, LER-81-47-3X, NUDOCS 8208120112
Download: ML20062F680 (3)
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LER-2081-047, Updated LER 81-047/03X-1:on 810910,following Reactor Trip & While Returning to Power,Specific Activity of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit. Caused by Fuel Element Defect in Reactor Core
Event date:
Report date:
2802081047R00 - NRC Website
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i c 13 tReactor Coolant system indicated a dose equivalent I-131 level greater than the l I t, 6 41 IT. S . 3.1.D. ? l imi t . Since the intecrity of the steam cenerator tubes was maintained I l c I s ! land the activity remained helow the T.S. 3.3.1.D.3 limit, the health and aafety I fcisI lof the enblic were nnt affected. This event is renort nbl e nor T. S.6. 6.2.b. (2) and I jo 7, (the special reporting requirements of T.S.3.1.D.4.  ;

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Ii ; o i IThis event was caused by a fuel element defect in the Reactor Core. Post trip l l i 61 1 teonditions in the core enhanced the release of fission products to the reactor i lii;; Icoolant system resultine in an iodine snike durine the return to power. I li t al l I l

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. UPDATE REPORT - PREV.IOUS REPORT DATE 9-30-81 ATTACilME'iT 1 SURRY POWER STATION, UNIT NO 1 DOCKET No: 50-280 REPORT NO: 81-047/03X-1 EVENT DATE: 09-10-81 TITLE OF Tile EVENT: Fuel Element Defect in the Reactor Core

1. DESCRIPTION OF EVENT:

On September 10, 1981, following a Reactor Trip, samples of the Reactor Coolant showed a Dose Equivalent I-131 level in excess of the T.S.3.1.D.2 limit of < 1.0 microcuries/cc. The Dose Equivalent I-131 r'eturned to within the T.S! limit 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> later.

On September 12, 1981, while returning to power, samples of the Reactor Coolant showed a Dose Equivalent 1-131 level in excess of the T.S.3.1.D.2 limit of < 1.0 microcuries/cc. The dose equivalent I-131 returned to within the T.S. limit approximately two hours later. Both events, I-131 in excess of T.S. limits, are reportable per T.S.6. 6.2.b(2) and T.S. 3.1.D. 4.

2. PROBABLE CONSEQUENCES and STATUS of REDUNDANT EQUIPMENT
  • i The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appropriatcly small fractien of 10 CFR 100 limits following a postulated steam generator tube rupture. Since the dose equivalent I-131 peak was below the Technical Specifi-cation upper limit of 10 microcuries/cc, the reactor coolant gross activity was below the value analyzed in the FSAR for a tube rupture and 17. failed fuel.

Therefore, the health and safety of, the public were not affected.

3. C y 0F Tile EVENT:

The Iodine Spike was caused by known, yet not specifically located, fuel element defects in the reactor core. Post trip conditions enhanced the release of fission products , specifically I-131, during the return to power. This caused an increase in the coolant specific activity level.

4 IMMEDIATE CORRECTIVE ACTION:

The immediate corrective action was to implement the actions required by T.S. Tabic 4.1-2B. Specifically, the level of dose equivalent I-131 was monitored every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> until the level returned to less than 1.0 microcuries/cc.

5. SCllEDULED CORRECTIVE ACTION:

No further corrective actions will be taken at this time.

6. ACTION TAKEN TO PREVENT RECURRENCE:

The specific activity of the reactor coolant system will continue to be monitored as required by T.S. Table 4.1.2.B.

7. CENERIC IMPLICATIONSi There are no generic implications associated with this event.

UPDATE REPORT - PREVIOUS REPORT DATE_9-3_0-g ATTACllMENT: Page 2 of 2 REPORT NO:: 81-047/03X-1 SUPPLEMENTAL INFORMATION The supplemental information required by T. S.3.1.D.4 "Special Report" is included as follows. ,

1, Reactor Power History 48 Hours prior to this Event:

Septemb er 8, 1981 - 1250 Reactor Power at 100%, I-131 in spec.

September 9, 1981 1250 Reactor Power at 100%, I-131 in spec.

September 10,1981 6 11ours at 100%, Turbine Runback, (1200) Reactor Trip.

September 10,1981 - 1250 Reactor Shutdown, I-131 out of spec.

Sept ember 11,1981 - 1815 Reactor Shutdown, I-131 in spec.

September 12,1981 _ 0005 Reactor Power at 22%, L 131 out of spec.

September 12,1981 _ 0158 Reactor Power at 34%, I-131 in spec.

2 Fuel Burnup by core region - as of 0000, September 12, 1981 Fuel Batch 4A: 13,196 FMD/MrU 6B: 13,090 FMD/NTU 4C: 26,012 MWD /KrU 6C: 22,975 FMD/MTU -

7A: 18,163 FMD/MrU 7B: 17,662 FMD/MTU 8A: 2,323 MWD /MTU 8B: 2,005 FMD/MrU Cycle 6 Burnup - 1967.61 FND/KFU

3. Average cleanup flow rate 116 gpm.
4. No De-Gassing operations were performed.

5 Duration of I-131 Spike :

September 10, 1981 (1250 lir. ) - Dose Equivalent Iodine Sample 1.99 Microcuries/cc September 11, 1981 (1710 lir. ) - Dose Equivalent Iodine Sample 1.08 Microcuries/cc l (1815 lir.) Dose Equivalent Iodine Sample .976 Microcuries/cc September 12, 1981 (0005 lir.) Dose Equivalent Iodine Sample 1.04 Microcuries/cc (0158 Hr. ) - Dose Equivalent Iodine Sample .867 Mircrcuries/cc Duration of I-131 spike approximately 30 llours.

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