ML17325B156

LER 88-012-01:on 881111,identified Turbine Room Sump Not Sampled & Analyzed,Per Tech Spec 4.11.1.1.1,Table 4.11.1. Caused by Failure to Designate Turbine Room Sump Liquid Effluent as Release Pathway.Procedures updated.W/890210 Ltr

ML17325B156
Person / Time
Site:	Cook
Issue date:	02/10/1989
From:	Will Smith, Wojcik J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-88-012, LER-88-12, NUDOCS 8903010306
Download: ML17325B156 (6)

Text

gCCP~RATED DJ~Bt'TIOA DEMONSTl04 SY) TEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8903010306 DOC.DATE: 89/02/10 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana & 05000315 AUTH. NAME AUTHOR AFFILIATION WOJCIK,J.T. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele SMITH,W.G. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R

SUBJECT:

LER 88-012-01:on 881111,turbine room sump not sampled &

analyzed per Tech Spec due to personnel error.

W/8 ltr.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR g TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

ENCL g SIZE:

I NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 STANG,J 1 1 INTERNAL: ACRSMICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADE 8H 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS/SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 R-E~~ 1 1 RES/DSIR/EIB 1 1 WE~SR/P B 1 1 RGN3 FILE 01 1 1 R EXTERNAL: EG&G WILLIAMS,S 4 4 FORD BLDG HOY i A 1 1 I H ST LOBBY WARD 1 . 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 NCTE 10 ALL "RIES" RECIPIENIS:

PIZASE HELP US V3 REDUCE %QUATE! CONI'ACI'IHE DOCUMENT"Z (DhKR)L DESK, ROOM Pl-37 (EXT. 20079) TO EZZMZ?CQ'E YOUR NAME FBI DISTRIBVZZGN LISTS FOR DOCUMENIS YOU DON'T NEED.'

TOTAL NUMBER OF COPIES, REQUIRED: LTTR 45 ENCL 44

NRC Form 356 U.S. NUCLEAR REQULATORY COMMISSION (9.83)

APPROVED OMB NO. 3160010(

LICENSEE EVENT REPORT (LER) EXPIRES; 8/31/58 FACILITY NAME (1) DOCKET NUMBER (2) PACE 3 D. C. Cook Nuclear Plant - Unit 1 3 OFO 4

"""'urbine Room Sump Not Sampled and Analyzed in Accordance with Technical o s o o o 1 1 S ecifications as a Result of Personnel Co nizant Error EVENT DATE (5) LEA NUMBER (6) REPORT DATE (7I OTHER FACILITIES INVOLVED (SI MONTH DAY YEAR YEAR :X%X SEQUENTIAL DAY YEAR FACILITYNAMES DOCKET NUMBERIS)

~NB NUMBER 54 NUMBER MONTH D. C. Cook Plant Unit 2 o so o o316 11 11 88 88 0 1 2 0 10 2 10 89 0 5 0 0 0 THIS REPORT IS SUBMITTED pURSUANT To THE REQUIREMENTS oF 10 cFR (): /Check one or more of the folios/sop) (11)

OPERATINQ MODE (8) 20402(bl 20406(c) 60.73(a) (2) (ivl 73 71(S)

POWE R 20405( ~ l(1)(i) 50.35(cl(1) 50.73(al(2)(vl 73.71(c)

LEYEL 0 9 0 (10) 20405(a)(1) (iil 50.35(c)(2) 60,73(a)(2) (vli) DTHER /specify In 40strect

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<gal 20405( ~ ) (I l(iiil 50.73( ~ )(2)(il 60.73(al(2) (viii)(Al 3664I y .y 20405(all1)(iv) 50.73( ~ ) (2) (8) 60.73(a) (2)(viiil(B) o r '. a v, 20A06(a)(1)(v) 60.73(a)(2)(BI) 60.73(al(2)(a)

LICENSEE CONTACT FOR THIS LER (12)

J. T. Wojcik - Technical Physical Sciences TELEPHONE NUMBER AREA CODE Department Superintendent 6 6 46 5- 5 9 0 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPORT (13) o CAUSE SYSTEM COMPONENT MANVFAC.

TVRER REPORTABLE TO NPADS CAUSE SYSTEM COMPONENT MANUFAC.

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SUPPLEMENTAL REPORT EXPECTED (IC) MONTH DAY YEAR EXPECTED SUBMISSION Ilfyes, DATE (16)

YES complete EXPECTED SVIISrt/SSIOH 04 TEI NO ABSTRACT /(lmlt to tc(SO spaces, le., epproir/mately fr/teen s/npleo>>ce typewritten linn/ (15)

This revision is being submieeed to report additional information and analysis resulting from our continued investigation into this event, as a result, has been which has deeermined that the normal discharge of the Turbine it Room Sump is eo an owner controlled unrestricted area.

On November ll, 1988, during a review of plant Technical Specifications and the Off-site Dose Calculation Manual (ODCM),

Turbine Room Sump had noe been sampled and analyzed in accordance with it was identified that the Technical Specification 4.11.1.1.1, Table 4.11.1 as identified in the ODCM.

As a result: 1) composite samples for the Turbine Room Sump have never been directly analyzed for Sr-89, Sr-90, Fe-55 and Gross Alpha, and;

2) monthly grab samples of the Turbine Room Sump have never been sampled or analyzed for dissolved and entrained gases; 3) reporting requirements for exceeding Technical Specificaeion and 10 CFR limits were not met.

The root cause of this event was the failure to designate the Turbine Room Sump liquid effluent as a release pathway to an unrestricted area and, implement all requirements of Technical Specifications. Based on historical data reviewed it is our belief that the regulatory limi,ts of 10 CFR 20, Appendix B, (when averaged over a year) were not exceeded.

To prevent recurrence procedures have been updated to list the required sampling frequencies and analysis for the Turbine Building Sump System, per Technical Specification Table 4.11-].

NRC Form 3SS (8 83 I

NRC Form 366A (94)3)

U$ . NUCLEAR REGULATORY COMMISSION LICENS VENT REPORT HLER) TEXT CONTIN ION APPROVED OM8 NO, 3(60-6104 EXPIRES: 8/31/88 FACILITY NAME (ll DOCKET NUMSFR (2)

LER NUMBER (6) PAGE (3)

D. C. Cook Nuclear Plant BEOVENTIAL REVISION YEAR Unit 1 NUMBER NUMBER TEXT //1 moro BAoco /4 /I)/rkoo L BFF ~ HRC /rorrn 36549) (I7) 0 s 0 0 0 3 1 5 8 8 012 010 2 OF 0 4 This revision is being submitted to report additional information and analysis resulting from our continued investigation into this event, as a result, has been determined that the normal discharge of the Turbine Room Sump is to it an owner controlled unrestricted area.

CONDITIONS PRIOR TO OCCURRENCE Unit 1 at 90 percent thermal power, Unit 2 in refueling mode with no fuel in reactor vessel.

DESCRIPTION OF EVENT On November 11, 1988, during a review of plant Technical Specifications and the Off-site Dose Calculation Manual, it was identified that the Turbine Room Sump System (EIIS/WH), which discharges to an absorption pond (diagram attached) had not been sampled and analyzed in accordance with Technical Specification 4.1l.l.l.l, Table 4.11-1, as required by the Off-site Dose Calculation Yanual.

In the past, composite samples of the Turbine Room Sump have been sampled and directly analyzed for principal gamma emitters, I-131 and H-3 on a daily basis. However, t: he Turbine Building Sump System was not identified as a plant continuous release point. As a continuous release point it is suh$ ect to the analysis program given in Table 4.11-1 of the Plant Technical Specifications.

As a result: 1) composite samples for the Turbine Room Sump have never been directly analyzed for strontium-89, strontium-90, iron-55 and Gross Alpha;

2) monthlv grab samples of the Turbine Room Sump have never been sampled or analyzed for dissolved and entrained gases (gamma emitters); and 3) reporting requirements for exceeding Technical Specifications and 10 CFR limits were not TRe't o CAUSE OF EVFNT The root cause of this event was the failure to designate the Turbine Room Sump as a radioacti.ve liquid effluent release pathway to an unrestricted area and as a result fail to implement all requirements of Technical Specification Table 4.11.1 when procedures for implementing the radioactive liquid waste sampling and analyses program were prepared.

ANALYSIS OF EVENT This event i.s considered reportable under the criteria of 10 CFR 50.73 (a)(2)(i)(B) as a literal violation of Technical Specifications, under 10 CFR 50.73(a)(2)(vii4.)(B) for releasing in excess of two times the limiting combined Maximum Permissible Concentration when averaged over a one hour period under 10 CFR 20.405 (a)(I)(v) for exceeding ten times the Technical Specification lim4(: to an unrestricted area.

NRC FORM BBBA *U S,GPO.1986 0 824 538/455 (94)3)

NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSE ENT REPORT (LER) TEXT CONTINU ION APPROVED OMB NO. 3150&(04 EXPIRES: 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) LFR NUMBER (6) PAGE (3)

D. C. Cook Nuclear Plant YEAR j~@?

SEQUENTIAL NUMBE R

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'.'+ REVISION NUMBE R Unit 1 0 S 0 0 O 8 8 0 1 2 0 1 03 pF 0 4 TEXT ///rforo BPoco /4//I/rfr/ Irfo Br/I//I/onf/HRC Form 36643/ (17)

The only potential source of radioactive influent to the Turbine Building Sump System is secondary system leakage. The secondary system with highest concentration of radioactivity is the steam generator blowdown system. Based on these facts and the conservative assumption that iron-55, strontium-89 and strontium-90 release concentrations for the turbine room sump were equal to the maximum release concentrations for, the steam generator blowdown flash tank, a comparison of steam generator blowdown flash tank quarterly composite data and turbine room sump daily composite data to 10 CFR 20 limits were performed for nine fifteen-day periods spanning from 1981 to 1987 when primary to secondary leakage was the greatest and when releases to the unrestricted areas occurred.

This comparison identified: 1) on five occasions the limits of Technical Specification 3.11.1.1 were exceeded; 2) on three of the five occasions the reporting requirements of: 10 CFR 50.72 (b)(2)(iv)(B) would have been applicable; and, 3) on one of the five occasions the reporting requirements of 10 CFR 20.405 (a)(1)(v) would have been applicable. As a result of the failure to recognize that releases via the Turbine Room Sump were to an unrestricted area the reporting requirements as previously identified were not met. The Maximum Permissible Concentration (MPC) fractions for the five occasions ranged from 1.03 to 10.09. It is our belief based on data reviewed that the regulatory limits nf 10 CFR 20, Appendix B, when averaged over a year were not exceeded and therefore did not result in any impact on the health and safety of the public.

CORRECTIVE ACTION To prevent recurrence procedures have been updated to list the required sampling frequencies and analysis for the Turbine Room Sump System, per Technical Specification Table 4.11-1.

FAILED COMPONENT IDENTIFICATION None.

NRC FORM 366A + U,S.GPO:1986 0 624 538/455 (94)3)

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P.O. Box 458 Bridgrnan, MI 49106 6164655901 .

g lNDMNA NlCHEGiAN POWER February 10, 1989 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Operating License DPR-58 Docket No. 50-315 Document Control Manager:

In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ortin S stem, the following report is being submitted:

88-012-01 Sincerely, W. G. Smith, Jr.

Plant Manager WGS:clw Attachment cc: D. H. Williams, Jr.

A. B. Davis, Region M. P. Alexich III P. A. Barrett J. E. Borggren R. F. Kroeger NRC Resident Inspector Wayne Scott, NRC R. C. Callen G. Charnoff, Esq.

Dottie Sherman, ANI Library D. Hahn

'NPO PNSRC A. A. Blind S. J. Brewer/B. P. Lauzau