05000280/LER-1985-020, :on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B

:on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B

ML20138M619
Person / Time
Site:	Surry
Issue date:	10/25/1985
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20138M602	List: 05000280/LER-1985-019, :on 850927,individual Rod Position Indicator for Two Rods Inoperable.Spurious Incorrect Rod Position Indication Is Generic Westinghouse PWR Concern.Portion of Sys Outside Containment Tested & No Problems Found 05000280/LER-1985-020, :on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B ML20138M600
References
LER-85-020, LER-85-20, NUDOCS 8511040155
Download: ML20138M619 (3)

LER-1985-020, on 850927,following Controlled Shutdown Due to Hurricane Gloria,Iodine Spike Discovered.Caused by Known Fuel Element Defects in Reactor Core.Level of Dose Equivalent I-131 Monitored Per Tech Spec Table 4.1-2B

Event date:
Report date:
2801985020R00 - NRC Website

text

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POW 28-06-01 NRC Form 384 U.S. NUCLEAR F EOULATO4Y COMMISSION APPFIOVED OMS NO. 3150-0104 EwREs ersues LICENSEE EVENT REPORT (LER)

F ACJLITY NAME (1)

DOCKET NUMSER (2)

PA(ak 0 Surry Power Station. Unit I O 15101010121810,1 loFl013 flTLE 44) lodine Spike EVENT DATE ISI LER NUMBER f6)

REPORT DATE (7)

OTHiR F ACILITIES INVOLVED (8)

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NAME TELEPHONE NUMBER AREA CODE R. F. Saunders, Station Manaaer Rio fu al;17l-;t 11 I n l t1 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRIGED IN THIS REPORT (131 M

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A88Th. ACT ! Limit to 1400 acecer, le, enerosmrety hfreen atng e aonce typewritsee knent USI ABSTRACT On September 27,1985 at 0800 following a controlled unit shutdown from 100%

power because Hurricane Gloria was threatening, the specific activity sample of the reactor coolant showed a dose equivalent 1-131 level of I. 36 microcuries /cc. This exceeds the dose equivalent 1-131 limit of less than 1.0 microcuries/cc specified in Tech. Spec. 3.1.D.2 and is being reported in accordance with the special reporting requirements outlined in T.S. 3.1.D. 4.

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' 0 Il rm n-. - - we, nu.nm IODINE SPIKE Description of the Event On September 27, 1985, at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> following a unit shutdown from 100%,

because Hurricane Gloria was threatening, the Specific Actt/ity Sample of the reactor coolant showed a dose equivalent I-131 level of 1.36 microcuries/cc. This exceeds the dose equivalent I-131 limit of less than 1.0 microcuries/cc specified in Tech.

Spec. 3.1.D.2 and is being reported in accordance with the special reporting requirements outlined in Tech. Spec. 3.1.D.4.

Probable Consequences and Status of Redundant Equipment 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 /> dose at the site boundary will not exceed the 10 CFR 100 limits following a postulated steam generator tube rupture.

Since the dose equivalent I-131 peak was below the Technical Specification upper limit of 10 microcuries/cc, the reactor coolant gross activity was below the value analyzed in the UFSAR for a tube rupture with 1% failed fuel. Therefore, the health and safety of the public were not affected.

Cause

The Iodine Spike was caused by known, but not specifically located, fuel element defects in the reactor core. Post shutdown conditions enhanced the release of fission products, specifically I-131.

This caused an increase of the reactor coolant specific activity.

Immediate Corrective Action

The immediate corrective action was to implement the actions required by Tech.

Spec. Table 4.1-28.

Specifically, the level of dose equivalent I-131 was monitored at least once 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.

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• vfAR Surry Power Station, Unit I o ls jo [o [o [2 l8l 0 8l 5 0 [2l0 0l0 O j3 or 0l 3 IODINE SPIKE Supplemental Information The supplemental information required by T.S.3.1.D.4 "Special Report" is included as follows:

1.

Reactor power history 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the event.

September 25, 1985 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 100%.

September 26, 1985 @ 1906 -

Start rampdown at 150MW/HR.

September 26, 1985 0 2245 -

30% and holding.

September 27, 1985 0 0023 -

Continue rampdown.

September 27, 1985 0 0203 -

Unit off line.

2.

Fuel burnup by core region - as of September 27, 1985.

FUEL BATCH BURNUP S2/5A 35,581 MWD /MTU S2/6A 27,730 MWD /MTU S2/6B 30,097 MWD /MTU 6C 30,440 MWD /MTU 8A 31,186 MWD /MTU 8B 35,716 MWD /MTU 9A 20,244 MWD /MTU 98 23,083 MWD /MTU S2/984 21,62G MWD /MTU 10 8,893 MWD /MTU Cycle 8 Burnup:

7,392 MWD /MTU 3.

Prior to the reactor shutdown, the unit had established a normal letdown rate of 105 gpm.

4.

No degassing operations were performed.

5.

Duration of dose equivalent 1-131 Spike:

September 27, 1985 0 0610 Routine Sample-

. 943 microcuries /cc.

September 27, 1985 0 0800

- Post Shutdown Sample - 1. 36 microcuries/cc.

September 27, 1985 0 1000

- Post Shutdown Sample - 1.4 microcuries/cc.

September 27, 1985 0 1200

- Post Shutdown Sample - I. 3 microcuries/cc.

September 27, 1985 0 1400

- Post Shutdown Sample - 1.16 microcuries/cc.

September 27,19E.i 0 1600

- Post Shutdown Sample

.97 microcuries/cc.

Duration approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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