ML20038B025

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LER 81-031/03L-4:on 810512,analysis of RCS Sample Showed Radioiodine Content Approaching Limit & Subsequent Peak Over Limit.Caused by Slight Leakage of Gas Through Fuel Cladding. Levels Monitored.Tech Spec Revision Being Evaluated
ML20038B025
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/11/1981
From: Rowland M
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20038B024 List:
References
LER-81-031-03X, LER-81-31-3X, NUDOCS 8111240612
Download: ML20038B025 (11)


Text

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?          8                      60           61              DOCAET NUVSEH EVENT DESCRIPTION AND PROBA3LE CONSEQUENCES h l o l 2 l l (NP-33-81-37) on 5/12/81 at 1457 hours following a reactor trip, a Reactor Coolant Sy s-{

The analy-- l

,g,3,           gt em (RCS) sample was collected in accordance with T.S. 3.4.8, Table 4.4-4.

the radio-iodine content was approaching the limit. At j gg,4)gsis of the sample showed that 2037 hours, the level peaked at 1.52 uCi/gm dose equivalent iodine I-131 with the limitj [c ls[ 1 l 0 l6 l lbeing 1.0 uCi/gn. There was no danger to the public or station personnel. Other io- l l3;;; j dine spikes have occurred on 7/30/81, 9/2/81, 10/16/81 and 10/23/81 with the level l

 ,3,g,          g peaking at 1.2 uCi/go, 1.96 uCi/gm, 2.17 uCi/gm, and 1.15 uCi/gm, respectively.                                                                              SO I

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                                         $DE                "^$E Co         SEs#EE C                  COMPONENT CODE jogg                                lR lC lg lE [g lClg lFjUjElLlXlXlg { g ] @

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                                                                                                                                                                ' REVISloN 7          8                                                                                                 OCCUR RE NCE           REPORT SEoVE NTI AL                                                                            No.

REPORT No. CoOE TYPE EVENT Y AR h t{,g LER RO l l_l [0l3l1l y l0 l3 l l Xl b l4 l su _ l218]22 23 24 26 21 25 2') 30 31 32 S B IT D FC i BUB. SLPP LIE MAN FACTURER ONPLANT ET HOUHS KE A T O' l1 0l0l0l0l40 W@ lNl@ lBl0l1l5I@ l3'sZl@ l36 Z lh [.__j@l Z lh 3 41 l42N l@ 4J 44 47 33 34 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h I i 10 l lThe cause was a slight leakage of gas through the fuel cladding. Some leakace is nor- I I

   ;,,,j         l mal following a reactor trip when the gases in the fuel rods are further connressed by l
   ,, ,,,        gthe contracting cladding. The levels were monitored to ensure it decayed off to j
       , 3       lbelow limits. A technical specification revision to channe the limit is beine
                                                                                                                                                                                   ]

i,;4; [ evaluated per Facility Change Request 81-163 Revision A. 7 8 9 oTHER STATUS So RY DISCOVERY DESCRIPTION STA 5  % PoWEH l1151 lX lg l 0 l 0 l 0]gl NA l l A lgl Per Table 4.4-4 of Tech Spec 3.4.8 l ACTIVITY CO T Ef 4T LOCATION oF RELEASE RELE ASED OF PELE A5E AMOUNT OF ACTIVITY NA l 1 6 {g gl NA 44 l l 45 80 7 8 9 10 It PER5oNNEL F XPOSURES NU TYPE OFSCRIPTION N^ l iii>i 10 ld"9EPP l@LzJ@l FERSON*gE L NW tEO NU DE SCHIP TION j 1 a l0 ld'REHl0l@l NA11 17 80 7 8 9 L Oss or on D A*.' AGE To FACILITY T v8'E DESCRIPTION l 1 0 [Z Jhj NA "

    '         * "      Punt $ry                                   9111240612 811111                                                                          NRC USE ONLY             ,

i ,su r O PDR ADOCK 05000325 PDR g l;;;;;;;;9l9lj ; I 2 o 8 9 hl tSomPiioN 10 NA S b 389 a 82 Mark Rowland PHONE: (419) 259-5000, r.xt . $ D' irs 81-176 & 81-}ti hatOF PREPARER

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 4 DATE OF EVENTS: May 12, July 30, September 2, October 17, and October 23, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reacter Coolant System (RCS) Dose Equivalent I-131 exceeded technical specification limits after reactor trip Conditions Prior to Occurrence: The unit was in Mode 3 with Power (MWT) = 0 and Load (Gross MWE) = 0. Description of Occurrence: At 1457 hours on May 12, 1981 following a reactor trip, an RCS sample was collected in accordance with Technical Specification 3.4.8, Tabic 4.4-4. The analysis of the sample showed that the dose equivalent 1-131 was .94 uCi/gm. A second sample was taken which exceeded Technical Specification 3.4.8 limit of 1.0 uCi/gm. At 2037 hours on May 12, 1981, the Icvel peaked at 1.52 uCi/gn. After a reactor trip at 0812 hours on July 30, 1981 and 1405 hours on September 2, 1981, a similar event occurred. The level peaked at 1.2 uci/gm at 1730 hours on July 30, 1981 and at 1.96 uCi/gm at 2040 hours on September 2, 1981. Following a reactor trip on October 16, 1981 at 2334 hours, the dose equivalent 1-131 peaked at 2.17 uCi/gm on October 17, 1981 at 0620 hours. Following a reactor trip on October 22, 1981 at 1518 hours, the dose equivalent I-131 peaked at 1.15 4 uCi/gm on October 23,1981 at 0600 hours. The following information is supplied per reporting requirements. Power History Reactor power was constant until 0022 hours on May 12, 1981 when it was reduced in anticipation of Reactor Coolant Pump (RCP) 2-1 being shutdown due to a seal problem. At 0058 hours, RCP 2-1 was taken out of service with reactor power at 75%. Date Time Reactor Power 5/10/81 1400 100% 5/11/81 1200 100% 5/12/81 0100 73% 0200 74% 0300 74% 1457 TRIP LER #81-031

I TOLEDO ELJSON COMPANY DAVIS-BESS NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATI0'; FOR LER NP-33-81-37 PAGE 2 On July 30, 1981, reactor power was decreased from 99.8% to 30% in six minutes to maintain condenser vacuum, then tripped at 0812 hours. Date Time Reactor Power 7/28/81 All day 99.46% 7/29/81 Till 1100 99.76% 1100 98.21% 1200 98.59% 1300 98.99% 1400 99.6% 2300 99.6% 7/30/81 0100 99.8% 0812 TRIP On September 2, 1981, reactor power was at approximately 100% until a reactor / turbine trip at 1405 hours. Date Time Reactor Power 9/1/81 1200 99.9% 2300 99.4% 9/2/81 1200 99.3% 1300 99.4% 1405 TRIP Reactor power was constant at 99.7% until a reactor / turbine trip at 2334 hours on October 16, 1981. Date Time Reactor Power 10/14/C1 1200 99.75% 0 10/15/81 1200 99.73% 10/16/81 0200 99.84% 2200 99.59% 2300 70.02% 2334 TRIP LER #81-031

r

   . TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 3 SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 Reactor power was constant at 96% until a runback brought power down to approxi-mately 9% and the reactor was tripped.

Date Time Reactor Power s 10/21/81 0100 90.10%

      .I                                   0800              88.28%

4' 2000 96.33% 10/22/81 1000 96.26% 1100 93.64% 1200 81.80% 1300 49.11% 1400 26.48% 1500 14.01% 1545 TRIP Fuel Burnup by Core Region - See attached computer printout Cleanup Flow History - 48 hours prior to the first limiting exceeding sample: The letdown flow during this time: May 10, 1981 - 86 gpm May 11, 1981 - 86 gpm May 12, 1981 - 102 gpm July 28, 1981 - 65 gpm July 29, 1981 - 65.5 gpm July 30, 1981 - 64 gpm August 31, 1981 - 66 gpm September 1, 1981 - 66 gpm September 2, 1981 - 67 gpm October 14, 1981 - 66.6 gpm October 15, 1981 - 66.6 gpm October 16, 1981 - 66.6 gpm 4 October 20, 1981 - 120 gpm October 21, 1981 - 120 gpm October 22, 1981 - 120 gpm There was no degassing operation. LER #81-031

                                                                                                - n_.

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   ,   TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37                                  PAGE 4 The dose equivalent I-131 exceeded 1.0 uCi/gm at 2037 hours on May 12, 1981 at 1330 hours on July 30, 1981, at 1623 hours on September 2, 1981, at 0620 hours on October 17, 1981, and at 0600 hours on October 23, 1981. It was below that limit at 0350 hours on May 13, 1981, 0130 hours on July 30, 1981, 0830 hours 4          on September 3, 1981, 0630 hours on October 17, 1981, and 1345 hours on October 23, 1981. The total time duration was approximately 9 hours, 11 hours, 16 hours, 28 hours, and 11.25 hours respectively. The maximum level was 1.52 uCi/gm on May 12, 1.2 uCi/gm on July 30, 1.96 uCi/gm on September 2, 2.17 uCi/gm on October 17, and 1.15 uCi/gm on October 23, 1981.

Specific Activity Analysis: Date Time Activity (uCi/gm) Dose Equivalent 7-131 5/12/81 0500 0.132 1845 0.94 2037 1.52 5/13/81 0013 1.14 0350 0.99 0555 0.74 0815 0.16 7/30/81 1025 0.98 1330 1.1 1730 1.2 2130 1.2 7/31/81 0130 0.98 0535 , 0.75 1400 0.44 9/2/81 1623 1.18 2040 1.96 9/3/81 0005 1.70 0220 1.52 0430 l'.29 0830 0.85 10/16/81 1210 0.12 10/17/81 0230 1.81 0620 2.17 0 2.11 0830 1230 1.84 1520 1.58 LER #81-031

TOLEDO EDISON COMPANY

 . DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37                                   PAGE 5 Date        Time         Activity (uCi/gn) Dose Equivalent I-131 10/17/81    1905                         1.27 4                          2245                         1.30 10/18/81    0230                         1.14 0630                         0.89 10/23/81    0230                         1.02 0600                         1.15 1000                         1.15 1345                         0.88 Designation of Apparent Cause of Occurrence: A reactor trip typically causes an iodine spike in the RCS. This is caused by a slight amount of gas leakage through the fuel rod cladding due to transient conditions. The gas leak is a result of in-creased compression of gas by the contracting cladding. Any small defects would allow some gas to escape.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. There was no venting of containment gases until the levels had decayed. The highest levels found in any sample were still well below the allowa-ble limit of 60 uCi/gm per Figure 3.4-1 of Technical Specification 3.4.8. Corrective Action: A corrective action is not applicable. Iodine spikes are typical following a reactor trip. No damage is indicated to the fuel. Monitoring of I-131 level continued until it dropped below technical specification limit of 1 uCi/gm. 4 At 0555 hours on May 13, 1981, the level dropped to .74 uCi/gn; at 0535 hours on July 30, 1981, it dropped to .75 uCi/gm; at 0830 hours oa September 3, 1981, it dropped to .85 uC1/gm; at 0630 hours on October 18, 1981 it dropped to .89 uCi/gm; and at 1345 hours on October 23, 1981, it dropped to .88 uCi/gm. A technical speci-fication revision to change the limit is being evaluated per Facility Change Request 81-163 Revision A. Failure Data: There have been two previous reports of high iodine levels - see Licensee Event Reports NP-33-80-ll4 (60-088) and NP-33-81-15 (81-016) . LER #81-031

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               @679 LABFLi PPPORMANCF      DATA OttTPUT BEGMENT 6                                                                                        .
         '     Pass PLaNTi TUI.LDO E01504 ED'. DAVIS BESSE ONE         ,
         '     A ',81 YTMFt YEAR 81 MONTH 09 DAY 99 HOUR 98 MfHUTE 41 REF EST
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFOR.'!ATION FOR LER NP-33-81-37 PAGE 10

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