Text

Special Rept:On 870408,RCS Dose Equivalent I-131 Exceeded Tech Spec Limits.Caused by Leaking Fuel Cladding.Leaking Fuel Will Be Identified by Ultrasonic Testing & Resolved During Next Refueling Outage
	ML17325A102
Person / Time
Site:	Cook
Issue date:	05/08/1987
From:	Will Smith; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8705110340
	Download: ML17325A102 (16)
	v • d • e

gr 4 REQULATORY FORMATION DISTRIBUTION BY M (RIDS)

ACCESSION NBR: 8705110340 DOC. DATE,: 87/05/08 NOTARIZED:

NO DOCKET 0 FACIL:50-315 Donald C.

Cook Nuclear Paver Planti Unit ir Ind iana Zc 05000315 AUTH. NAME AUTHOR AFFILIATION SMITHI W. Q.

Indiana h Michigan Electric Co.

RECIP, NAME RECIPIENT AFFILIATION Document Control B~anch (Document Control Desk)

SUBJECT:

Special rept: on 870408 RCS dose equivalent I-131 exceeded Tech Spec limits. Caused bg leaking Fuel cladding. Leaking fuel vill be identified bg ultrasonic testing 8r resolved during next refueling outage.

DIBTRIBUTION CODE:

IE22D COPIEB RECEIVED: LTR i

ENCL i

BIIE:

.11 TITLE: 50. 73 Licensee Event Report (LER)I Incident Rpt.

etc.

NOTES:

RECIPIENT ID CODE/NAME PD3-3 LA WIQQINQTON D INTERNAL: ACRB MICHELSON AEOD/DQA AEOD/DSP/TPAB NRR/DEBT/ADS NRR/DEBT/ELB NRR/DEBT/MEB NRR/DEST/PSB NRR/DEST/SQB NRR/DLPG/GAB NRR/DREP/EPB NRR/DREP/RPB NRR/PMAS/PTSB RES SPEIS> T EXTERNAL:

EQRQ QROHr M LPDR NSIC HARRISr S CQPIEB LTTR ENCL 1

1 1

0 1

1 1

2 2

1 1

5 5

1 1

1 RECIPIENT ID CODE/NAME PD3-3 PD ACRS MOELLER AEOD/DSP/ROAB NRR/DEST/ADE NRR/DEBT/CEB NRR/DEBT/ ICSB NRR/DEBT/MTB NRR/DEST/RSB NRR/DLPG/HFB NRR/DOEA/EAB NRR/DREP/RAB N R/P AS/ILRB L

02 QN3 FILE 01 H ST LOBBY WARD" NRC PDR NSIC MAYSr Q COP IES LTTR ENCL 1

1 2

2 0

1 1

TOTAL NUMBER OF COPIES REQUIRED:

LT1R 41 ENCL 39

Donald C. Cook Nuclear Plant P.O. Box 458, Bridgman, Michigan 49106 May 8, 1987 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C.

20555 Operating License DPR-58 Docket No. 50-315 Document Control Manager:

Attached is the special report being submitted in accordance with Technical Specification 3.4.8 and 6.9.1, to inform you that on April 8, 1987 the Unit One reactor coolant DOSEQ Xodine 131 exceeded the

< 1.0 pCi/gram limit during a controlled shutdown.

Sincerely, W.

G. Smith, Jr.

Plant Manager CC John E. Dolan A. B. Davis, Region III M. P.,Alexich R. F. Kroeger H. B. Brugger R.

W. Jurgensen NRC Resident Inspector R.

C. Callen G. Charnoff, Esp.

D. Hahn INPO D. Wigginton, NRC PNSRC A. A. Blind Dottie Sherman, ANX Library File 8705110340 870508 PDR ADQCK 05000315 8

PDR

DOSE EQUIVALENT IODINE-131 EXCEEDING TECHNICAL SPECIFICATIONS FOLLOWING POWER TRANSIENT This special report is being submitted pursuant to the requirements of Appendix A Technical Specifications 3.4.8 and 6.9.1.

Technical Specification 3.4.8 states in part:

"The specific activity of the primary coolant shall be limited to:

a.

<1.0 pCi/gram DOSE EQUIVALENT I-131..."

On April 8, 1987 with the unit in mode 3, it was found that the Dose Equivalent I-131 activity in the Unit 1 reactor coolant system had exceeded the Technical Specification limit.

Conditions Prior to Occurrence Unit 1 at 90 percent reactor thermal power.

Descri tion of Event April 7, 1987 At 2252 hours0.0261 days 0.626 hours 0.00372 weeks 8.56886e-4 months Unit 1 entered the Excessive Reactor Leakage Procedure.

Letdown was isolated and excess letdown was placed in service at 2257 hours0.0261 days 0.627 hours 0.00373 weeks 8.587885e-4 months .

April 8, 1987 At 0027 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months normal letdown was established at 75 gpm and excess letdown was removed.

At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months the unit started a controlled shutdown from 90K power because of a high reactor coolant system leak rate.

At 0104 hours0.0012 days 0.0289 hours 1.719577e-4 weeks 3.9572e-5 months letdown was increased to 120 gpm.

An Event Initiated Surveillance was entered at 0142 hours0.00164 days 0.0394 hours 2.347884e-4 weeks 5.4031e-5 months to comply withTechnical Specification 3.4.8 Table 4.4-4, Item b, which requires sampling of the primary coolant between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period and analyzing for iodines.

The unit entered mode 3 at 0503 hours0.00582 days 0.14 hours 8.316799e-4 weeks 1.913915e-4 months .

At 0718 hours0.00831 days 0.199 hours 0.00119 weeks 2.73199e-4 months letdown was manually isolated when it was discovered that there was a packing leak on QRV-111 (which is in the letdown purification pathway).

Laboratory analysis of a reactor coolant sample taken at 0739 hours0.00855 days 0.205 hours 0.00122 weeks 2.811895e-4 months indicated the reactor coolant Dose Equivalent Iodine-131 concentration was 1.28 pCi/gram which exceeded the Technical Specification limit of 1.0 pCi/gram.

At 0902 hours0.0104 days 0.251 hours 0.00149 weeks 3.43211e-4 months an Event Initiated Surveillance was entered to comply with Technical Specification 3.4.8 Table 4.4-4 Item 4a, which requires sampling primary coolant once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months whenever the specific activity exceeds 1.0 pCi/gram DOSE EQUIVALENT I-131 or 100/- pCi/gram and analyzing for iodines.

E April 9, 1987 Dose Equivalent Iodine-131 activity increased to a maximum of 1.72 pCi/gram at 1500'ours.

April 10, 1987 Unit 1 entered mode 5 at 0230.

At 1749 hours0.0202 days 0.486 hours 0.00289 weeks 6.654945e-4 months 1'etdown purification was established after being isolated because of the leak on QRV-111.

Laboratory analysis of a reactor coolant sample taken at 2130 indicated a Dose Equivalent Iodine-131 value of 0.853 pCi/gram.

~

P

~

All subsequent Dose Equivalent Iodine-131 analysis of reactor coolant indicated decreasing levels of iodine.

During this event no degassing activities took place and all applicable Technical specification action items were met.

Fuel burnup by region and all additional data as required by Technical Specification 3.4.8 is found in the attachments.

4 Cause of Event Leaking fuel cladding, reacting predictably to a power transient.

Anal sis of Event During this event, iodine release from fuel was consistent with data reported in Westinghouse Electric Corporation WCAP-8637, "Iodine Behavior Under Transient Conditions in the Pressurized Water Reactor".

Dose Equivalent Iodine-131 values were in the "acceptable operation" portion of Technical Specification Figure 3.4-1 at all times during this event.

All applicable Technical Specification action items were met during this time. It is concluded that the event did not pose a threat to the health and safety of the public.

Corrective Action ( lanned)

Leaking fuel will be identified by ultrasonic testing and resolved during the next refueling outage for Unit 1 currently scheduled for July and August 1987.

120 100 80 60 40 20 0

UNIT j. CYCLE 9 RCS RADIOCHEMISTRY STARTING 0043 4/6/87

POWER LETDOWN

- I-131

- I-133 DOSEQ o

p ~o1E 1 1E 2 0

120 TIME (Hours)

ATTACHMENT 41 REACTOR COOLANT IODINE SPIKING DATA (UNIT ONE)

Date/Time Date/Time of Reactor Trip or Shutdown RCS DOSEQ I-131 exceeded 1.0 4-8-87/0100 pCi/gm 4-8-87/0739 DATE TIME POWER (8)

LETDOWN (GPM)

I-131 gCi/cc DOSEQ I-131 (uCi/cc) 4/6/87 4/7/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/8/87 4/9/87 4/9/87 4/9/87 4/9/87 4/9/87 4/9/87 4/9/87 4/9/87 4/9/87 4/10/87 4/10/87 4/10/87 4/10/87 4/10/87 4/10/87 4/10/87 4/10/87 4/11/87 4/11/87 4/11/87 4/11/87 0043 0300 0037 0325 0506 0739 0930 1130 1330 1513 1727 1926 2138 2252 0049 0249 0452 0652 0958 1200 1500 1800 2055 0041 0355 0555 0915 1200 1456 1753 2130 0023 0330 0904 1707 90.5 90.5 90 32 0 (A) 0 0

0 0

120 120 75 120 (E) 120 0 (S) 0 0

0 0

0 120 (C) 120 120 0

0 50 2.85-~

2.81-~

3.25-~

5.18-~

1.88-~

.984 1.06 1.15 1.04 1.04

.999 1.02 1.16 1.19 1.23 1.22 1.23 1.21 1.25 1.36 1.56 1.49 1.42 1.27 1.33 1.19 1.23 1.23 1.12 1.14

.821

.592

.447

.321

.195 5.76-~

5.92-~

6.61-~

8.81-~

.250 1.28 1.35 1.44 1.28 1.27 1.21 1.21 1.37 1.40 1.43 1.41 1.41 1.37 1.40 1.52 1.72 1.63 1.54 1.36 1.42 1.27 1.30 1.30 1.17 1.19

. 853 (D)

.614

.462

.339

.199 (A)

(s)

(C)

(D)

(E)

CVCS Less CVCS Demineralizer in service 120 than 1 pCi/gram.

Demineralizer in service 120 gpm at gpm at 1749 0104.

Unit Subcritical at 0503 Excess letdown only, Demineralizers bypassed at 0718.

CORE-PACKAGE:

BURNUP 12 APRIL 1985 BURNUP CALCULATION

SUMMARY

SHEET D ~ C ~

COOK NUCLEAR PLANT (SPECIAL RUN-IODINE SPIKE)

UNIT NO.

1 CYCLE NO.

9 REPORT NO.

52A DATE:

APRIL 8, 1987 PERIOD:

APRIL 1. 8, 1987 REGION NO.

BURNUP FOR PERIOD (MWD/MTU)

CUMULATIVE BURNUP (MWD/MTU)

ENERGY FOR PERIOD (BTU)

CUMULATIVE ENERGY (BTU)

H 1

J 2

Kl-K44 3 K45-K80 4

AA1 AA48 5 AA49 AA80 6

0.1552E+03 0.2203E+03 0.2374E+03 0.2270E+03 0.3097E+03 0.2669E+03 0.3202E+05 0.3504E+05 0.3222E+05 0.2800E+05 0.1757E+05 0.1501E+05 0.7600E+ll 0.1541E+12 0.3845E+12 0.3086E+12 0.5598E+12 0.3217E+12 0.1568E+14 0.2450E+14 0.5218E+14 0.3807E+14 0.3175E+14 0.1810E+14 CORE TOTAL 0.2513E+03 0.2510E+05 0.1805E+13 0.1803E+15

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

< 1.0 pCi/gram DOSE EQUIVALENT I-131, and b.

< 100/E pCi/gram.

APPLICABILITY:

MODES 1, 2, 3, 4 and 5

ACTION:

NODES 1, 2 and 3*

a.

With the specific activity of the primary coolant

> 1.0 pCi/gram DOSE EQUIVALENT I-131 but within the allowable limit (below and to the left of the line) shown on Figure 3.4-1, operation may continue for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months provided that operation under these circumstances shall not exceed 10 percent of the unit's total yearly operating time.

The provisions of Specification 3.0.4 are not applicable.

b.

With the specific activity of the primary coolant

> 1.0 uCi/gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one con-tinuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T

< 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

avg c.

With the specific activity of the primary coolant

> 100/E pCi/gram, be in HOT STANDBY with T

< 500'F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

avg MODES 1, 2, 3, 4 and 5

a ~

With the specific activity of the primary coolant

> 1.0 pCi/gram DOSE EQUIVALENT I-131 or

> 100/E >Ci/gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits.

A REPORTABLE OCCURRENCE shall be prepared and submitted to the Commission pursuant to Specification 6.9.1.

This report shall contain the results of the specific activity analyses together with the following information:

avg D.C.

COOK - UNIT 1

3/4 4-21

REACTOR COOLANT SYSTEM ACTION:

Continued 1.

Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 2.

Fuel burnup by core region, 3.

Clean-up flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded, 4.

History of de-gassing operations, if any, starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded>

and 5.

The time duration when the specific activity of the primary coolant exceeded 1.0 pCi/gram DOSE EgUIYALENT I-131 SURVEIL'LANCE RE UIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling 'and analysis program of Table 4.4-4.

O.C.

COOK - UNIT 1

3/4 4-22

~

n,t s ~

E C4 6 260 1

P 2M V

V U

t" CS0

'O CJ 0

CC 100 R

so.

0 d

ACCEPTABLE OPERATlON I

UNACCEPTABLE OPERAT1ON 29 30 40 SD 60 70 80 PERCENT QF RATED THER~1POWER FlGURF 3'.4-1 DOSE EQUIVALENTi-131 Primary Coolant Specific ActivityLimitVersus Percept of RATED THERMALPOWER with the Primary Coolant Specific Activity>1.0p,Ci/gram

"..ose Equivalent M3't O.C.

COOK - UNIT 1 3/4 4-24

TABLE 4.4-4 PRIMARY COOLANT SPECIFIC ACITIVITYSAMPLE ND ANALYSIS PROGRAM TYPE OF MEASUREMENT AND ANALYSIS 1.

Gross Activity Determination 2.

Isotopic Analysis for 00SE E(UIVA-LENT I-131 Concentration 3.

Radiochemical for E Determination 4.

Isotopic Analysis for Iodine Including I-131, I-133, and 1-135 MINIMUM

~FRE UENCY 3 times per 7 days with a maximum time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months between samples.

1 per 14 days 1 per 6 months*

a)

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , whenever the specific activity exceeds 1.0 uCi/gram DOSE EQUIVALENT I-131 or IOO/E pCi/gram, and b)

One sample between 2 8 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following a

THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.

I MODES IN glQCH SAMPLE AND ANALYSIS RE UIRED 1, 2, 3, 4

1 4f 1, 2, 3

Until the specific activity of the primary -.coolant system is restored within its limits.

Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since reactor was )ast subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

V

INDIANA & MICHIGAN POWER COMPANY DONALD C.

COOK NUCLEAR PLANT TABLE 1

SUMMARY

OF RELEASE RATES DURING POWER TRANSIENT CONDITIONS 0

TIME 0.5 hr R/Ro 13 0.5 1.0 hr 1.0 3.5 hr 19 40.5 3.5 5.0 5.25 7.5 10.0 14.0 5.0 hr 5.25 hr 7.5 hr 10 hr 14 hr 56'9 25 0.0

Reference:

Westinghouse Electric Corp.,

WCAP-S637, "Iodine Behavior Under Transient Conditions In The Pressurized Hater Reactor",

November, 1975.

ML17325A102

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