ML18219C268

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LER-1976-059-00 for Donald C. Cook, Unit 1 - Iodine Spike Following Power Transient, Violation of Limit Specified in Technical Specification 3.4.8
ML18219C268
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 01/24/1977
From: Jurgensen R
American Electric Power Service Corp, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To: James Keppler
NRC/IE, NRC/RGN-III
References
LER-1976-059-00
Download: ML18219C268 (17)
v • d • e


Text

NUCLEAR REGULATORY COMMISSION DOCKET NUMBER NRC FORM ~195 I2 7g)

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SO- 3(A FILE NUMBER

'NRC DISTRIBUTION FoR ART 50 DOCKET MATERIAL INCIDENT REPORT Tp. J G Keppler FROM: Indiana & Michigan P1m Co DATE OF DOCUMENT l"24-77 Brid'gman, .Mich R W Jurgensen DATE RECEIVED gLETTE goRIGINAI R>> 0 NOTOR IZE 0' PROP INPUT FORM NUMBER OF COPIES RECEIVED

"~ kfUNCLASSIFIED ~ one signed COP Y DESCRIPTION ENCLOSURE

.Ltr ts'ans the follo17ing: RO 76- 9)-on 12-24-76'alent og Reactor coolant malysis tw iodine scapi e~ollowing transient,;...',

du'e'ower lp'LANT NAME Cook g ]

NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J COLLINS

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'%rneramn G,*i:M~ED 8 MCO~llX DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 January 24, 1977 Freed~ >~7>

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Mr. J. G. Keppler., Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevel t Road Glen El lyn, IL 60137 Operating Li cense DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of Appendix A Technical Specifications and the United States Nuclear Regulatory Commission Regulatory Guide 1.16, Revision 4, Section 2.b, the following report is submi tted:

RO-50-315/76-59 Sin ce rely,

. W. Ju ens Plant M nager 'RegutBto>'u ":Ip RW J/mj

>> g'ac cc: R. S. Hunter J. E. Dolan G. E. Lien R. Ki ~ lb urn R. J.'Vollen BPI R. C. Callen MPSC K. R. Baker RO: III R. Walsh, Esq.

P. W. Steketee, Esq.

G. Charnoff, Esq.

G. Olson J. M. Hennigan PNSRC R. S. Kei th Dir., IE (30 copies)

Dir., MIPC (3 copies)

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Llt"ENSEE EVENT REPORT CONTROL BLOCK: SE PRINT ALL REQUIRED INFORIVIATIOM3 6""

1'ICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

[opj M I 0 C C 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03 7 89

  • 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT OATE Ion~Icon'~ L ~L 0 5 0 0 3 1 5 68 69 1 2 2 4 7 5 74 0

75 1 2 4 7, 7 80 7 8 57 58 59 60 61 I

EVENT DESCRIPTION Qpg ON DECEMBER 23'976 AT 2100 HOURS POWER REDUCTION WAS STARTED WITH THE UNIT TRIPPED 7 8 9 80 FROM APPROXIMATELY 7X AT 0008 HOURS ON DECEMBER 24, 1976. REACTOR COOLANT ANALYSIS 7 89 ~ .. 80

[oOP4 SHOWED DOSE E UIVALENT I-131 ACTIVITY TO BE 3.1 uCi m. THIS IS IN EXCESS OF LIMIT 7 8 9 7 8 9 80

[oaf R0-50-315/76-52,0N NOVEMBER 20, 1976. (RO-50-315/76- 59 )

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-80 SYSTEM CAUSE COMPON84T COMPONENT CODE CODE COMPONENT CODE SUPPLER MANUFACTURER Ioc7I ~zz ~F z z z z z Z

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48 7 8 9 10 .11 12 CAUSE DESCRIPTION

[oOs] SEE SUPPLEMENT 7 8 9 80

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89 80 FACIUTY STATUS POWER 'THER STATUS METHOD OF DISCOVERY DISCOVERY DESCRIPTION

@171 ~G ~00 0 NA 44 45 46 ROUTINE SAMPLING 80 7 8 9 10 .12 13 FORM OF ACTIVITY COATENT REI.EASED OF RELEASE, AMOUNT OF ACTIVITY LOCATiON OF RELEASE 2J Z Z NA

~ 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~aj ~00 0 Z NA 80 7 89 11 12 13 PERSONNEL INJURIES 7 8 9" 11 12 80 PROBAHLTE CONSEQUENCES Qqg NA 7 8 9 80 LOSS OR DAMAGE TO FACIUTY PE OESCIIIATION 7 89 ~ 10 PUBLICITY NA 7 89 80 ADBITIONAL FACTORS Q~e] NA 7 89 80

~18 NA 7 89 80 J L RI SCHL I NG PHGNE(616)465-5901(368)

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~ i SUPPLEME 0 REPORTABLE OCCURRENCE RO 50 5 76 59 ff INDIANA & MICHIGAN'OWER COMPANY DONALD C. COOK NUCLEAR PLANT Iodine S'ike Followin PowerTransient As this shutdown was planned and, due to the iodine spiking noted following reactor trip on November 20, 1976, a revised sampling program had been set up to increase the data collection frequency. This program consisted of collecting samples each two hours prior to unit shutdown, each half hour for the first four hours following reactor trip and each two hours after that period until data stabilized.

Reactor power had been slowly decreasing during the week prior to shutdown due to core stretch out, with power in the 90%%d range 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first out-of-specification sample.* On December 23, 1976, at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, reactor power reduction was started with the unit tripped from approximately 7S power at 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on December 24, 1976. In pre-paration for shutdown, CVCS purification flow had been increased to maximum (120-125 gpm) on December 13, 1976, and maintained at this level through shutdown.", Volume control tank hydrogen pressure was reduced at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on December 23, 1976, in preparation for degassing of the system with remain-ing degassing operations (VCT level increase and venting to the gas header) starting at 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on December 24, 1976, with three tank purges completed by 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on December 25, 1976.

Primary coolant I-131 activity following return to equilibrium after the November 30, 1976 reactor trip had stabilized at 1.5-- 2.0xlO-z wCi/cc.~

I-131 activity remained at this level until 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 24, 1976 when the activity increased to 2.5 yCi/cc, approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> following initiation of power reduction. Iodine release at this time period is consis-tent with data reported in Westinghouse Electric Corporation WCAP-8637, "Iodine Behavior Under Transient Conditions in the Pressurized Water Reactor." The increased data collection sampling frequency after the spike indicates that the I-131 activity began decreasing immediately following the initial spike with values remaining constant at approximately 1.6 pCi/cc for an 8 - 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> period before further decrease (See Figure 2). I-133, 135 values showed trends similar to the I-131 activity (Figure 3). DOSE E(UIVALENT I-131 values peaked at 3. 1 pCi/gm at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 24, 1976, with values exceeding the 1.0 pCi/gm specification for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the spike. DOSE EQUIVALENT I-131 values were in the "Acceptable Operation" portion of Technical Specifications Figure 3.4-1 at all times during the transient.*

Fuel burnup by core region is indicated in Table 1.

As iodine values began decreasing immediately following the spike and have remained at low values during fuel movement operations (1.5x10 " pCi/cc) and with all data similar to that following the November 20, 1976, incident, the December 24, 1976 spike is also attributed to the normal spiking phenomena during power transients rather than fuel clad failure. No iodine spiking was noted during depressurization of the reactor coolant system.

  • See Figure 1 Coolant samples are brought to ambient conditions before counting; therefore, units of pCi/cc and pCi/gm are interchangeable.

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INDIANA 8 MICHIGAN POKIER COMPANY DONALD C. COOK NUCLEAR PLANT TABLE 1 FUEL BURNUP BY CORE REGION REGION NO. BURNUP FOR CUMULATIVE ENERGY FOR CUMULATI>/E PERIOD BURNUP PERIOD ENERGY (MMD/MTU (MHD/MTU) (BTU), (BTU) 0.3023E+04 0.1894+05 0.7285+13 0.6565+14 0 '272+04 0. 1915+05 0. 7803+13 0. 4566+14

3. 0.2375+04 0.1350+05 0.5632-:13 0.3201+14 Core Total 0.2891+04 0.1721+05 0.2072+14 0.1233+15 Period: October 1, 1976 - December 30, 1976

INDIANA 5 MICHIGAN POWER COMPANY DONALD C. COOK t'IUCLEAR PLANT TABLE 1 FUEL BURNUP BY CORE REGION REGION NO. BURNUP FOR CUMULATIVE Ei'lERGY FOR CUMULATIVE PERIOD BURNUP PERIOD ENERGY (MWD/MTU) 'MWD/MTU (BTU) (BTU) 0.3023E+04 0.1894+05 0.7285+13 0.6565+14

2. 0.3272+04 0 '915+05 0.7803+13 0.4566+14
3. 0.2375+04 0.1350+05 0.5632+13 0.3201+14 Core Total 0.2891+04 0.1721+05 0.2072+14 0.1233+15 Period: October 1, 1976 - December 30, 1976

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