ML17326B293

LER 87-002-00:on 870324,noted That Sample of Steam Generator Blowdown Not Taken on 870316.Caused by Procedural Deficiencies.Sampling Procedure Modified to Require Sampler to Check for Flow Through line.W/870409 Ltr

ML17326B293
Person / Time
Site:	Cook
Issue date:	04/09/1987
From:	Kriesel T, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-87-002-01, LER-87-2-1, NUDOCS 8704160300
Download: ML17326B293 (5)

Text

REGULATOR NPORNATION DISTRIBUTION - 'TEN (R IDS)

ACCFBSION NBR S704160300 DOC. DATE.: 87/04/09 NOTARI ZED: NO DOCKET ¹ FAC I L.'50-315 Donald C. Cook Nuclear Pouer Plant> Unit 1> Ind iana 5 05000315 AUTH. NAME AUTHOR AFF ILIAT I ON KRIESEL>>. A. Indiana h Nichigan Electric Co.

SNITH> N. G. Indiana h Michigan Elec+ric Co.

'ECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

LER 87-002-00: on '870324> noted that sample of steam generator b l oed oton not taken on 870316. Caused bg pr oc edu'r al deficiencies. Sampling procedure modified to require sampler fl to check for ov through line. 14/870409 l tr.

DISTRIBUTION CODE: IE22D COPIES RECEiVED: LTR ENCL SIZE:

TITLE: 50. 73 Licensee Event Report (LE@) Incident Rpt etc.

REC IP I ENT COPIES REC IP I ENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAN'= LTTR E iCL F D3-3 LA 1 PD3-3 PD 1 1 WIQGINQTON> D 1 INTERNAL: ACRB NICHELSON 1 1 ACRB MOELLER 1

• CRB WYLIE 1 AEOD/DOA 1 AEOD/DSP/ROAB ~ 2 AEOD/DSP/TAPB 1 1 AEOD/DSP/TPAB 1 ERR/ADT 1 NRR/DEST/ADE 1 0 t':RR/DEST/ADS 0 NRR/DEBT/CEB NRR/DEST/ELB 1 NRR/DEBT/ICBM 1 t':RR/DEBT/NEB 1 1 NRR/DEBT/MTB 1 ERR/DEBT/PSB 1 1 NRR/DEBT/RSB 1 1 t':RR/DEBT/SGB 1 1 NRR/DLPG/Hf'8 1' ERR/DLPG/GAB 1 NRR/DOEA/EAB t!RR/DREP/EPB 1 ~ 1 NRR/DREP/RAB 1 1 ERR/DREP/RPB 2 2 NRR/PNAB/ILRB 1 t!RR/PNAS/PTSB 1 gEG I LE 02 1 RES SPEI S> T 1 1 FlLE 01 1 EXTERNAL: E;G8(Q QROH> M 5 H BT LOBBY 4}ARD 1 1 t.r DR 1 NRC PDR. 1 NSIC HARRIS> J 1 1 t'!SIC MAYS, G 1 TOTAL NUMBER OF COPIES REGUIRED: LTTR 44 ENCL 4r

NRC Form 368 U.S. NUCLEAR REOULATORY COMMISSION (94)31 APPROVED OMB NO. 31604104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

DOCKET NUMBER (2) PA E 3 FACILITY NAME (1)

DONALD C. COOK NUCLEAR PLANT, UNIT 1 0 5 0 0 0 315 1OFO 3 NON-REPRESENTATIVE STEAM GENERATOR BLOWDOWN SAMPLE D FICIENCY.

EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

YEAR

'j:.'I SEOUENTIAL REVS~SR MONTH DAY YEAR FACILITYNAMES DOCKET NUMBERIS)

MONTH OAY YEAR N: NUMSER yg 0 5 0 0 0 0 3 158 787 0 0 2 00 04 0 9 8 7 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR (I: (Cnrcp onr or morr of tfrr fol(orf/nP/ (11)

OPERATINQ MODE (Sl 20.402(8) 20.405(c) 50.734)(2)(lv) 73.715s)

POWER 20A05( ~ ) (I ) (I) 50M(c)(I) 50 73(a) (2)(v) 73.71(cl LEVEL OTHER (Sprclfy in Aprtrrct (10 I 20.405(a) (1)(8) 50.38(cl(2) 50.73(al(2)(vll)

Orrow mr/ /n Trxr, HRC Form 20A05(al(1) (III) 50.73( ~ l (2) ( I) 60.73(a)(2)(rllll(A) SSSA/

20A06(a) (I ) I lv) 50.73(a)(2)(ll) 60,73( ~ l(2)(rllll(B) 20.405(a) (I ) (r) 50.7341(21(III) 50,73( ~ ) (2)(x)

LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER T. A. KRIESEL - TECHNICAL PHYSICAL SCIENCES AREA CODE DEPARTMENT SUPERINTENDENT 61 6 46 5 -5 901 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13)

CAUSE SYSTEM COMPONENT MANUFAC TURER

'AUSE I

ri@v" v'PORTABLE SYSTEM COMPONENT MANUFAC.

TURER TO NPRDS

'V'PORTABLE

',P(4)')(LTEP4 SUPPLEMENTAL REPORT EXPECTED (14) MONTH NNNOAY YEAR EXPECTED SU 6 M I SS ION DATE (16)

YES (lf yrr, complrtr EXPECTED SIISMISSIOH DATE( NO ABSTRACT (Limit ro tr/X/rprcrr, Ir., approxlmrtrly fifrrrn r/noir rprcr typrwrittrn linn/ 118l On March 24, 1987, with the reactor at 90 percent power, it was determined that a representative sample of steam generator (S/G) blowdown was not obtained on March 16, 1987. This was the result of a blowdown valve lineup which allowed the normal blowdown sample point to be isolated from the effluent path. This resulted in a sample being taken on a stagnant section of piping.

Samples are required daily for compositing to meet the requirements of 4.11.1.1.1, Table 4.11-1B.

Procedural Deficiencies are the cause of the event.

To prevent recurrence the sampling procedure was changed to require the sampler to verify that there is flow in the piping prior to sampling,

@704 1 603 0 870EI09 0c300013 i5 ADOCK o o PDR PDR 6

NRC Form 388 (94)3)

NRC Forrrr OBBA U.S, NUCLEAR REGULATORY COMMISSION

)94)3)

LICENSEE EV T REPORT (LER) TEXT CONTINUAT APPROVEO OMB NO. 3150M)04 EXPIRES: 8/31/BB FACILITYNAME lll OOCKET NUMBER 12) LER NUMBER 16) PAGE 13)

D. C. COOK NUCLEAR PLANT, YEAR g@C; AS SEQUENTIAL w~

~r::

REVISION NUMBER NUMSEA UNIT 1 o s o o o3 15 8 7 0 2 0 0 020F 0 3 TEXT ///'oro op>>C>> /4 r>>EV/red, IN>> afdlabaV HRC form 3//64 4/117)

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

Descri tion of Event On March 24, 1987, it was determined that a representative sample of steam generator blowdown was not obtained on March 16, 1987. This deficiency was discovered following the investigation of suspicious suspended solids results of the March 16, 1987 sample analyses. This event was the result of the normal sample point, DSX-300, (EIIS/SMV) being bypassed while returning blowdown to service using the normal flash tank {EIIS/TK) on March 15, 1987 at 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br />. The line-up procedure (OHP 4021.025.001) allowed two flow paths while on the normal flash tank. One flow path isolated DSX-300 by closing BD-110. Samples taken while using this configuration would be 'off a stagnant pipe section and would not be representative of the blowdown being discharged. This was the configuration that was present when the blowdown sample was taken on March 16, 1987.

Technical Specification 4.11.1.1.1 requires that steam generator (EIIS/SG) blowdown {EIIS/WI) be sampled and composited daily for the radionuclide analyses described in Table 4.11-1 Part B.

There were no inoperable structures, components, or system's that contributed.

to this event.

Cause of Event Because the blowdown line-up and sampling were done in accordance with approved procedures, it is concluded that procedural deficiencies are the cause of the problem.

Anal sis of the Event The event is reportable under the criteria of 10 CFR 50.73(a)(2)(i) ~

The blowdown procedure which allowed the lineup had been in effect since February 27, 1987, so conditions could have been present for inaccurate samples since that time, However, only the sample taken after the March 15, 1987 blowdown lineup had irregular results, therefore, it is believed that the only missed sample was on March 16, 1987.

Because the sample taken March 16 was not valid and could not be replaced, the daily composites could not be properly prepared, however, routine daily analyses for gross beta-gamma, tritium, and gamma spectroscopy (including Iodine-131) on individual steam generator blowdown samples indicated no abnormal levels. Furthermore, prior to being discharged, the effluent NAC FOAM 366A o U.S.GPO:1988.0 824 538/455 TIP@3)

RC Form OSSA U.S. NUCLEAR REGULATORY COMMISSION I84)r))

LICENSEE EVENT REPORT (LER) TEXT CONTINUATI APPROV EO OMB NO. 3)50&)04 EXPIRES: 8/3l/SB OOCKET NUMBER )2) LER NUMBER I6) PAGE I3)

YEAR SSOVSNTIAL REVISION D.C. COOK NUCLEAR PLANT, UNIT 1 NVMBSR NUMBER o s o o o3 15 87 002 0 0 0 3 DF 0 TEXT ///moro BPBBB /6 B)rrkorL IIBB BNS/BBB/HRC %%dnn 36//A'4/ I )7) is monitored by radiation monitor R-19 (EIIS/RI). If more severe conditions, i.e., increased radiological contamination of blowdown water occurred that day, radiation monitor R-19 would have isolated the effluent pathway.

Based on this information, it is concluded that the event did not pose a threat to the health and safety of the public.

Corrective Actions At the time of discovery, it was too late to obtain the required sample for compositing. No corrective action was possible.

To prevent recurrence the sampling procedure was modified to require the sampler to check for flow through the line on flow indicator DFI-352 (EIIS/FI) prior to sampling.

Since March 17, all samples of blowdown have been verified to be representative of the effluent.

Failed Com onent Identification No component failures were identified during the event.

Previous Similar Events None.

NRC fORM SBBA *U,S,GPO:1886 0.624 538/455 IS4L))

~rnerlcen Qleatrlo INDIANA 8r MICHIGAN ElECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 456, Brldgernan, Ml 49106 Telephone {616) 465.5901 April 9, 1987 U. S. 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:

87-002-0 Sincerely, W. G. Smith, Jr.

Plant Manager

/afh Attachment 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, MPSC G. Charnoff, Esq.

D. Hahn INPO PNSRC Dottie Sherman, ANI Library A. A. Blind File